Saturday, September 19, 2020

NRC Schedules Webinars to Present Environmental Findings on Proposed Spent Nuclear Fuel Storage Facility in Texas

Nuclear Regulatory Commission - News Release
No: 20-046 September 16, 2020
CONTACT: David McIntyre, 301-415-8200

NRC Schedules Webinars to Present Environmental Findings on Proposed Spent Nuclear Fuel Storage Facility in Texas

The Nuclear Regulatory Commission will hold four webinars in October to present its draft environmental findings and receive comments on Interim Storage Partners’ proposed consolidated spent nuclear fuel storage facility in Andrews County, Texas.

The NRC remains committed to opportunities for the public to inform the agency’s decisions related to its draft Environmental Impact Statement on the ISP proposal. In 2017, the NRC staff held two webinars and two in-person meetings in Texas and New Mexico. This fall, the agency planned similar public meetings; however, in-person meetings during the comment period will not be possible because of the COVID-19 public health emergency.

Information for the webinars will be posted on the NRC’s Public Meetings webpage. They will be held at different times of the day to maximize opportunities for the public to participate. The webinars are tentatively scheduled for Oct. 1 from 6-9 p.m.; Oct. 6 from 2-5 p.m.; Oct. 8 from 6-9 p.m.; and Oct. 15 from 11 a.m.-2 p.m. All times are Eastern.

The draft EIS for ISP’s proposed consolidated interim spent nuclear fuel storage facility was published in May for a 120-day public comment period, which has been extended because of the COVID-19 public health emergency, for a total comment period of 180 days.

Comments will be accepted through Nov. 3, including by mail to the Office of Administration, Mail Stop: TWFN-7-A60M, ATTN: Program Management, Announcements and Editing Staff, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; email at WCS_CISF_EIS@nrc.gov; and posting online at the federal government’s rulemaking website, using Docket ID NRC-2016-0231. Information regarding the NRC’s review of the ISP application is available on the NRC website, including the draft EIS, reader’s guides in English and Spanish, and a detailed explanation of how to submit comments.

Peach Bottom Atomic Power Station, Units 2 and 3 - Senior Reactor and Reactor Operator Initial License Examinations

Peach Bottom Atomic Power Station, Units 2 and 3 - Senior Reactor and Reactor Operator Initial License Examinations

ADAMS Accession No.  ML20261H403

PBAPS.pdf

Susquehanna Steam Electric Station, Units 1 and 2 - Senior Reactor and Reactor Operator Initial License Examinations

Susquehanna Steam Electric Station, Units 1 and 2 - Senior Reactor and Reactor Operator Initial License Examinations


ADAMS Accession No.  ML20261H398

Wednesday, September 16, 2020

Cost-Benefit Analysis - Valuing Nonfatal Cancer Risks in Cost-Benefit Analysis

 $$$ SECY-20-0074: Valuing Nonfatal Cancer Risks in Cost-Benefit Analysis


Docketed 8/27/2020 

​​​​​​​Document Title:
SECY-20-0074: Valuing Nonfatal Cancer Risks in Cost-Benefit Analysis

Document Type:
Commission SECY Paper

Document Date:
08/12/2020

N2

Friday, September 11, 2020

ZOOM WEBINAR: Security & Nuclear Power, 9/28, 8 pm ET

ZOOM WEBINAR: 

Security & Nuclear Power, 9/28, 8 pm ET


The September 11, 2001 attacks on the U.S. using hijacked commercial aircraft heightened security concerns around the nuclear power industry. The hijackers flew flight training missions over New York’s Indian Point nuclear power station. United Flight 99 crashed just 130 miles from Pennsylvania’s Three Mile Island power station.


Nuclear security concerns include criminal and military-style acts -- armed intrusion, vehicles or missiles carrying explosives, and insider sabotage -- targeting operating nuclear stations or radioactive materials including nuclear waste. 


Three Mile Island Alert security consultant Scott Portzline is hosting a Zoom webinar on this topic Monday, September 28 at 8PM ET. Register

Thursday, September 3, 2020

Susquehanna Steam Electric Station, Units 1 and 2 - Updated Inspection Plan (Inspection Report 05000387/2020005 and 05000388/2020005)

Susquehanna Steam Electric Station, Units 1 and 2 - Updated Inspection Plan (Inspection Report 05000387/2020005 and 05000388/2020005)

ADAMS Accession No.  ML20240A279

Susquehanna--1.pdf

Peach Bottom Atomic Power Station, Units 2 and 3 - Updated Inspection Plan (Inspection Report 05000277/2020005 and 05000278/2020005)

Peach Bottom Atomic Power Station, Units 2 and 3 - Updated Inspection Plan (Inspection Report 05000277/2020005 and 05000278/2020005)

ADAMS Accession No.  ML20240A275

Peach-1.pdf

BRAIDWOOD STATION, UNITS 1 AND 2; CALVERT CLIFFS NUCLEAR POWER PLANT, UNITS 1 AND 2; CLINTON POWER STATION, UNIT 1; R. E. GINNA NUCLEAR POWER PLANT; LIMERICK GENERATING STATION, UNITS 1 AND 2; NINE MILE POINT, UNITS 1 AND 2; AND PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 AND 3 – REQUEST TO USE ALTERNATIVE CODE CASE OMN-26 (EPID L-2020-LLR-0012)

 BRAIDWOOD STATION, UNITS 1 AND 2; CALVERT CLIFFS NUCLEAR POWER PLANT, UNITS 1 AND 2; CLINTON POWER STATION, UNIT 1; R. E. GINNA NUCLEAR POWER PLANT; LIMERICK GENERATING STATION, UNITS 1 AND 2; NINE MILE POINT, UNITS 1 AND 2; AND PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 AND 3 – REQUEST TO USE ALTERNATIVE CODE CASE OMN-26 (EPID L-2020-LLR-0012)

ADAMS Accession No. ML20232A171

ML20232A171.pdf

Tuesday, September 1, 2020

FRN Multiple Exemptions COVID - July 2020


Document Title: 
FRN - Notice of Issuance of Multiple Exemptions Regarding Various Parts of 10 CFR Due to COVID-19 Impacts for July 2020

Document Type:
Exemption from NRC Requirements Federal Register Notice

Document Date: 
08/21/2020
 

Susquehanna Steam Electric Station, Units 1 and 2 - Updated Inspection Plan (Inspection Report 05000387/2020005 and 05000388/2020005)

Susquehanna Steam Electric Station, Units 1 and 2 - Updated Inspection Plan (Inspection Report 05000387/2020005 and 05000388/2020005)

ADAMS Accession No.  ML20240A279

Susquehanna-.pdf

Peach Bottom Atomic Power Station, Units 2 and 3 - Updated Inspection Plan (Inspection Report 05000277/2020005 and 05000278/2020005)

Peach Bottom Atomic Power Station, Units 2 and 3 - Updated Inspection Plan (Inspection Report 05000277/2020005 and 05000278/2020005)

ADAMS Accession No.  ML20240A275

Peach.pdf

Wednesday, August 26, 2020

NRC Fines TVA More Than $600,000 for Discrimination Violations; Cites Two Managers for Their Roles

Nuclear Regulatory Commission - News Release
No: 20-042 August 25, 2020
CONTACT: Scott Burnell, 301-415-8200


NRC Fines TVA More Than $600,000 for Discrimination Violations; Cites Two Managers for Their Roles

The Nuclear Regulatory Commission staff has issued a $606,942 civil penalty to the Tennessee Valley Authority, an order prohibiting a senior TVA executive from NRC-licensed activities for five years, and a Notice of Violation to another TVA manager.

The enforcement actions stem from NRC investigations finding that two former TVA employees were subjected to adverse actions after raising concerns about a chilled work environment in which employees are less likely to report safety issues for fear of reprisal.

The NRC found that TVA’s former vice president of regulatory affairs and former director of corporate nuclear licensing violated the NRC’s employee protection rule and engaged in deliberate misconduct. The NRC is prohibiting the former vice president of regulatory affairs from any involvement in NRC-licensed activities for five years, since he was a decisionmaker for the adverse employee actions. The NRC is issuing a Notice of Violation to the former director of corporate nuclear licensing.

The NRC staff continues to review and inspect work environment issues and TVA’s corrective actions at the utility’s corporate office and its three nuclear power plants (Browns Ferry, Sequoyah and Watts Bar). As stated in the most recent annual assessment of Watts Bar, the NRC staff has determined that TVA has made progress in addressing these issues.

TVA and the two individuals have 30 days to respond to the NRC’s enforcement actions.

Wednesday, August 19, 2020

NRC Names New Senior Resident Inspector at Beaver Valley Nuclear Power Plant

Nuclear Regulatory Commission - News Release
No: I-20-017 August 18, 2020
Contact: Diane Screnci, 610-337-5330 Neil Sheehan, 610-337-5331


NRC Names New Senior Resident Inspector at Beaver Valley Nuclear Power Plant

The Nuclear Regulatory Commission has selected Gwynne Eatmon as the new senior resident inspector at the Beaver Valley nuclear power plant in Shippingport, Pa.

Eatmon joined the NRC in 2011 as a reactor inspector as part of the agency’s Nuclear Safety Professional Development Program in the Region IV Office in Arlington, Texas. Upon completion of the program, she worked as a reactor inspector in the Region IV Division of Reactor Safety, conducting inspections at operating nuclear power plants.

In 2014, she began serving as the resident inspector at the North Anna nuclear power plant near Mineral, Va. More recently, she was the acting senior resident inspector at the Vogtle nuclear power plant near Augusta, Ga.

Eatmon holds both bachelor’s and master’s degrees in mechanical engineering from New Mexico State University.

Each U.S. commercial nuclear power plant has at least two NRC resident inspectors, who serve as the agency’s eyes and ears at the facility, conducting inspections, monitoring significant work projects and interacting with plant workers and the public.

Thursday, August 13, 2020

Susquehanna Steam Electric Station, Units 1 and 2 - Integrated Inspection Report 05000387/2020002 and 05000388/2020002

 Susquehanna Steam Electric Station, Units 1 and 2 - Integrated Inspection Report 05000387/2020002 and 05000388/2020002


​​​​​​​ADAMS Accession No.  ML20224A179
SUS2020_002.pdf

Peach Bottom Atomic Power Station: Major Loss of Emergency Preparedness Capabilities

 Peach Bottom - LOSS OF TECHNICAL SUPPORT CENTER VENTILATION SYSTEM


U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
8/11/2020 - 8/12/2020

** EVENT NUMBERS **
54829
Power ReactorEvent Number: 54829
Facility: Peach Bottom
Region: 1     State: PA
Unit: [2] [3] []
RX Type: [2] GE-4,[3] GE-4
NRC Notified By: John Whelan
HQ OPS Officer: Brian P. Smith
Notification Date: 08/11/2020
Notification Time: 20:22 [ET]
Event Date: 08/11/2020
Event Time: 13:34 [EDT]
Last Update Date: 08/11/2020
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(3)(xiii) - Loss Comm/Asmt/Response
Person (Organization):
MEL GRAY (R1DO)



UnitSCRAM CodeRX CritInitial PWRInitial RX ModeCurrent PWRCurrent RX Mode
2NY97Power Operation97Power Operation
3NY100Power Operation100Power Operation


Event Text


LOSS OF TECHNICAL SUPPORT CENTER VENTILATION SYSTEM

"At 1334 EDT on Tuesday August 11th, the Peach Bottom Atomic Power Station (PBAPS) Technical Support Center (TSC) Ventilation System lost power due to a trip of the Station Blackout (SBO) electric power supply breaker. The trip was due to a fault at the Conowingo Dam and Conowingo was not able to realign electric power to the SBO within an hour. Power restoration is complete and TSC Ventilation was restored at 1725 EDT.

"This report is being submitted pursuant to 10CFR 50.72(b)(3)(xiii) as a Major Loss of Emergency Preparedness Capabilities due to a reduction in the effectiveness of the Onsite Technical Support Center (TSC).

"The NRC Resident Inspector has been notified."
 

Tuesday, August 11, 2020

Beaver Valley - RFO Summary Report

 Hello Eric,


This docketed today.  
See page three for CRDM coming attractions nozzle 27 & 37.
N2
MJK

Document Title:
Beaver Valley Power Station, Unit No. 2 - Twenty-First Refueling Outage lnservice Inspection Summary Report

Document Type:
Inservice/Preservice Inspection and Test Report
Letter

Document Date:
07/28/2020

Beaver Valley Inspection Hardship

Dear Beaver Valley Trackers,

Hardship at Beaver Valley so they request deferral of Inspections.

This Smells.
N2
MJK

ML20206K865

https://adamswebsearch2.nrc.gov/webSearch2/main.jsp?AccessionNumber=ML20206K865 

Document Title:
Beaver Valley Power Station, Unit 2 - Relief Requests 2-TYP-4-RV-06 and 2-TYP-4-RV-07 from the Requirements of the ASME Code (EPID L-2020-LLR-0053 and EPID L-2020-LLR-0054 [COVID-19])

Document Type:
Code Relief or Alternative
Letter
Safety Evaluation

Document Date
08/07/2020

Thursday, August 6, 2020

Peach Bottom Atomic Power Station, Units 2 and 3 - Audit Plan Regarding License Amendment Request to Implement Riskinformed Extended Completion Times (L-2020-LLA-0120)

Subject:  Peach Bottom Atomic Power Station, Units 2 and 3 - Audit Plan Regarding License Amendment Request to Implement Riskinformed  Extended Completion Times (L-2020-LLA-0120)

ADAMS Accession No. ML20217L346

Oversight of Security at Decommissioning Reactors


Document Title:
OIG-17-A-09-Status of Recommendations: Audit of NRC'S Oversight of Security at Decommissioning Reactors dated August 4, 2020.

Document Type:
Memoranda

Document Date:
08/04/2020

Fire Protection During Decommissioning


Document Title:
Regulatory Analysis for DG-1370 proposed Revision 1 of Regulatory Guide (RG) 1.191, Titled, Fire Protection Program for Nuclear Power Plants During Decommissioning

Document Type: 
Fire Protection Plan
Regulatory Analysis

Document Date:
08/05/2020

Wednesday, August 5, 2020

NRC to Hold Webinars Seeking Public Comment on Updating Generic Environmental Impact Statement for Renewing Reactor Licenses

Nuclear Regulatory Commission - News Release
No: 20-040 August 4, 2020
CONTACT: Scott Burnell, 301-415-8200

NRC to Hold Webinars Seeking Public Comment on Updating Generic Environmental Impact Statement for Renewing Reactor Licenses
Nuclear Regulatory Commission staff will hear the public’s views on updating the Generic Environmental Impact Statement used by the agency when considering applications to renew operating reactor licenses.

NRC staff will consider written comments on the updated GEIS scoping process until Nov. 2, following the publication of a notice in the Federal Register. Include Docket ID NRC-2020-0175 with your comment, via the regulations.gov website. The notice includes details for participating in webinars Aug. 19 and Aug. 27, with two sessions each day from 1:30-4 p.m. and from 6:30-9 p.m. to discuss the GEIS process and gather input.

The GEIS covers environmental topics relevant to all nuclear power plant licensees seeking renewed licenses. The NRC is reviewing the document to re-evaluate potential impacts and apply what the agency has learned during previous license renewals. The agency will consider whether to modify, add to, consolidate, or delete any of the 78 environmental issues currently evaluated in the GEIS.

The NRC is particularly interested in comments in several areas, including greenhouse gas emissions, groundwater quality degradation, the impact of new reactors on existing reactor license renewals, and the consideration of small modular or advanced reactor license renewals.

Wednesday, July 29, 2020

NRC Schedules Regulatory Conference with International Isotopes Inc.

Nuclear Regulatory Commission - News Release
No: IV-20-012 July 28, 2020
Contact: Victor Dricks, 817-200-1128

NRC Schedules Regulatory Conference with International Isotopes Inc.

The Nuclear Regulatory Commission will hold a regulatory teleconference on Aug. 4 with officials from International Isotopes Inc. to discuss two apparent violations of regulatory requirements identified by the NRC during an inspection.

The teleconference will begin at 9 a.m. Central Time and will be open to the public. NRC officials will be available to answer questions following the business portion of the meeting. The public will have the opportunity to listen to the meeting and ask questions via a phone bridge by calling 888-972-4310, passcode 3411918#.

The purpose of the conference is to discuss the apparent violations identified in a June 22 inspection report. They involve the licensee’s failure to properly review and approve operating procedures through their radiation safety committee prior to implementation. These procedures were used by International Isotopes when a significant contamination event occurred at the Harborview Medical Center in Seattle, Wash., on May 2, 2019.

The inspection was conducted at the company’s facility in Idaho Falls, Idaho, in February.

No decision on the final safety significance of the apparent violations or any NRC actions will be made at the meeting.

NRC Proceeding "Three Mile Island 50-320 LT"

TMI Unit 2 - Unopposed Motion of DEP.pdf

Tuesday, July 28, 2020

NRC Approves Changes to Three Mile Island Nuclear Generating Station Emergency Planning Requirements

Nuclear Regulatory Commission - News Release
No: 20-039 July 27, 2020
CONTACT: David McIntyre, 301-415-8200

NRC Approves Changes to Three Mile Island Nuclear Generating Station Emergency Planning Requirements

The Nuclear Regulatory Commission has granted a request to alter the emergency preparedness plan for the Three Mile Island Nuclear Generating Station in Londonderry Township, Pa., to reflect the plant’s decommissioning status. Exelon Generation Co. LLC requested the change.

The change comes in the form of exemptions from NRC requirements no longer appropriate for a plant that has permanently ceased operations. These exemptions are consistent with NRC actions for other decommissioning plants. Once Exelon implements the exemptions, state and local governments may rely on their comprehensive emergency management (“all hazard”) planning for off-site emergency response should events occur at TMI, rather than having a dedicated offsite radiological emergency response plan. As a result, there will not be a 10-mile emergency planning zone as currently identified in TMI’s license. The plant will maintain an onsite emergency plan and response capabilities, including the continued notification of state government officials in the event of an emergency declaration.

The exemption request included analyses to show the exemptions are warranted. When compared to an operating power reactor, the risk of an offsite radiological release is significantly lower, and the types of possible accidents are significantly fewer, at a nuclear power reactor that has permanently ceased operations and removed fuel from the reactor vessel. The NRC staff evaluated and confirmed these analyses, along with considering comments from the Federal Emergency Management Agency. Based on the NRC staff’s evaluation and recommendation, the Commission today approved the exemptions. The exemptions, a safety evaluation and associated license amendments reflecting the change will be issued in the next few weeks. Under the exemptions, Exelon may not implement the change to its emergency preparedness plans until Jan. 20, 2021.

Exelon holds the operating license for TMI Unit 1, a single pressurized-water reactor that began operations in 1974. TMI Unit 1 ceased operations Sept. 20, 2019. All spent fuel has been permanently moved from the reactor vessel to the spent fuel pool for storage. The exemptions from certain emergency preparedness requirements are part of several changes to the plant’s licensing basis and technical specifications the licensee requested to reflect TMI’s decommissioning status. TMI Unit 2 has been in a non-operating status since the accident in 1979. General Public Utilities Nuclear Inc. retains the license for TMI-2 and is owned by FirstEnergy Corp. The TMI-2 defueling was completed in April 1990, and all spent fuel has been removed from the site. The U.S. Department of Energy took title and possession of the TMI-2 spent fuel and stores it at Idaho National Laboratory.

Friday, July 24, 2020

FirstEnergy Corp. Statement on HB 6 Investigation - News Release

FirstEnergy Corp. Statement on HB 6 Investigation
 |PR Newswire |About:  FE
AKRON, Ohio, July 21, 2020 /PRNewswire/ -- FirstEnergy Corp. ( FE) today issued the following statement:

This afternoon, FirstEnergy Corp. received subpoenas in connection with the investigation surrounding Ohio House Bill 6. We are reviewing the details of the investigation and we intend to fully cooperate.

Forward-Looking Statements: This statement includes forward-looking statements within the meaning of the Private Securities Litigation Reform Act of 1995 based on information currently available to management. Unless the context requires otherwise, as used herein, references to "we", "us", "our", and "FirstEnergy" refer to FirstEnergy Corp. Forward-looking statements are subject to certain risks and uncertainties and readers are cautioned not to place undue reliance on these forward-looking statements. These statements include declarations regarding management's intents, beliefs and current expectations. These statements typically contain, but are not limited to, the terms "anticipate," "potential," "expect," "forecast," "target," "will," "intend," "believe," "project," "estimate," "plan" and similar words. Forward-looking statements involve estimates, assumptions, known and unknown risks, uncertainties and other factors that may cause actual results, performance or achievements to be materially different from any future results, performance or achievements expressed or implied by such forward-looking statements, which may include the following: the extent and duration of the novel coronavirus (known as COVID-19) and the impacts to our business, operations and financial condition resulting from the outbreak of COVID-19 including, but not limited to, disruption of businesses in our territories, volatile capital and credit markets, legislative and regulatory actions, the effectiveness of our pandemic and business continuity plans, the precautionary measures we are taking on behalf of our customers and employees, our customers' ability to make their utility payment and the potential for supply-chain disruptions; mitigating exposure for remedial activities associated with retired and formerly owned electric generation assets, including, but not limited to, risks associated with the decommissioning of TMI-2; the ability to accomplish or realize anticipated benefits from strategic and financial goals, including, but not limited to, executing our transmission and distribution investment plans, controlling costs, improving our credit metrics, strengthening our balance sheet and growing earnings; legislative and regulatory developments including, but not limited to, matters related to rates, compliance and enforcement activity; economic and weather conditions affecting future operating results, such as significant weather events and other natural disasters, and associated regulatory events or actions; changes in assumptions regarding economic conditions within our territories, the reliability of our transmission and distribution system, or the availability of capital or other resources supporting identified transmission and distribution investment opportunities; changes in customers' demand for power, including, but not limited to, the impact of climate change or energy efficiency and peak demand reduction mandates; changes in national and regional economic conditions affecting us and/or our major industrial and commercial customers or others with which we do business; the risks associated with cyber-attacks and other disruptions to our information technology system, which may compromise our operations, and data security breaches of sensitive data, intellectual property and proprietary or personally identifiable information; the ability to comply with applicable reliability standards and energy efficiency and peak demand reduction mandates; changes to environmental laws and regulations, including, but not limited to, those related to climate change; changing market conditions affecting the measurement of certain liabilities and the value of assets held in our pension trusts and other trust funds, or causing us to make contributions sooner, or in amounts that are larger, than currently anticipated;  the risks and uncertainties associated with litigation, arbitration, mediation and like proceedings; labor disruptions by our unionized workforce; changes to significant accounting policies; any changes in tax laws or regulations, , or adverse tax audit results or rulings; the ability to access the public securities and other capital and credit markets in accordance with our financial plans, the cost of such capital and overall condition of the capital and credit markets affecting us, including the increasing number of financial institutions evaluating the impact of climate change on their investment decisions; actions that may be taken by credit rating agencies that could negatively affect either our access to or terms of financing or our financial condition and liquidity; and the risks and other factors discussed from time to time in our Securities and Exchange Commission (SEC) filings. Dividends declared from time to time on our common stock during any period may in the aggregate vary from prior periods due to circumstances considered by our Board of Directors at the time of the actual declarations. A security rating is not a recommendation to buy or hold securities and is subject to revision or withdrawal at any time by the assigning rating agency. Each rating should be evaluated independently of any other rating. These forward-looking statements are also qualified by, and should be read together with, the risk factors included in our filings with the SEC, including but not limited to the most recent Annual Report on Form 10-K and Quarterly Report on Form 10-Q together with any subsequent Quarterly Reports on Form 10-Q and Current Reports on Form 8-K. The foregoing review of factors also should not be construed as exhaustive. New factors emerge from time to time, and it is not possible for management to predict all such factors, nor assess the impact of any such factor on our business or the extent to which any factor, or combination of factors, may cause results to differ materially from those contained in any forward-looking statements. FirstEnergy expressly disclaims any obligation to update or revise, except as required by law, any forward-looking statements contained herein as a result of new information, future events or otherwise.


SOURCE FirstEnergy Corp.

2nd Event Report: Global Nuclear Fuel - CONCURRENT REPORT FOR FIRE SUPPRESSION OUT OF SERVICE

The 2nd Event Report today on Global Nuclear Fuel License # SNM-1097.  This facility is prone to failure and seeking: Exemption from Reporting Certain Unplanned Contamination Events.  

Fuel Cycle FacilityEvent Number: 54797
Facility: Global Nuclear Fuel - Americas
RX Type: Uranium Fuel Fabrication
Comments: Leu Conversion (Uf6 To Uo2)
Leu Fabrication
Lwr Commerical Fuel
Region: 2
City: Wilmington   State: NC
County: New Hanover
License #: SNM-1097
Docket: 07001113
NRC Notified By: Phillip Ollis
HQ OPS Officer: Thomas Herrity
Notification Date: 07/22/2020
Notification Time: 10:04 [ET]
Event Date: 07/21/2020
Event Time: 10:30 [EDT]
Last Update Date: 07/22/2020
Emergency Class: Non Emergency
10 CFR Section:
PART 70 APP A (c) - Offsite Notification/News Rel
Person (Organization):
MARK MILLER (R2DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)



Event Text
CONCURRENT REPORT FOR FIRE SUPPRESION OUT OF SERVICE

The following was received from Global Nuclear Fuels, America:

"At 1030 (EDT) on July 21st, 2020, the New Hanover County Deputy Fire Marshall was notified per State code requirements that the fire suppression system for the Fuel Manufacturing Operation Sandblast Building was impaired. An underground pipe that feeds water to the sprinkler system had developed a leak. The building is normally unoccupied and no other buildings are affected. Compensatory measures were enacted and communicated to the Deputy Fire Marshall. Because the New Hanover County Deputy Fire Marshall was notified, a concurrent notification to the NRC Operations Center is being made per 10 CFR 70, Appendix A(c)."

The licensee will notify Region 2.
 

Event Report: Global Nuclear Fuel - CONCURRENT REPORT FOR FIRE SUPPRESSION OUT OF SERVICE

Current Event Notification Report for July 23, 2020
U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
7/22/2020 - 7/23/2020

** EVENT NUMBERS **

Fuel Cycle FacilityEvent Number: 54777
Facility: Global Nuclear Fuel - Americas
RX Type: Uranium Fuel Fabrication
Comments: Leu Conversion (Uf6 To Uo2)
Leu Fabrication
Lwr Commerical Fuel
Region: 2
City: Wilmington   State: NC
County: New Hanover
License #: SNM-1097
Docket: 07001113
NRC Notified By: Mr. Phillip Ollis
HQ OPS Officer: Thomas Herrity
Notification Date: 07/14/2020
Notification Time: 10:13 [ET]
Event Date: 07/13/2020
Event Time: 10:15 [EDT]
Last Update Date: 07/14/2020
Emergency Class: Non Emergency
10 CFR Section:
PART 70 APP A (c) - Offsite Notification/News Rel
Person (Organization):
MARK MILLER (R2DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
Event Text

CONCURRENT REPORT FOR FIRE SUPPRESSION OUT OF SERVICE

"At 1015 EST on July 13, 2020, the New Hanover County Deputy Fire Marshall was notified per State code requirements that the fire suppression system for various Fuel Manufacturing Operation Shop Areas was taken offline for planned maintenance to conduct a NFPA [(National Fire Protection Association)] required 5-year inspection. These inspections will be ongoing throughout the week. Compensatory measures were enacted and communicated to the Deputy Fire Marshall. Because the New Hanover County Deputy Fire Marshall was notified, a concurrent notification to the NRC Operations Center is being made per 10 CFR 70, Appendix A(c)."

Licensee will notify Region 2.


On 07/11/2020 10:24 AM Michael J Keegan wrote:


Dear Global Nuclear Fuel America Trackers,

Catchy Title: Exemption from Reporting Certain Unplanned Contamination Events
Zip file of three documents, and then those referenced are pasted farther below.
Global Nuclear Fuel America (GNFA) looks to have had several "Unplanned Contamination Events" seems just too many to have to write it up, how about an Exemption.  Some of the fuel is enriched up to 8% and intended to be high burnup.  Fermi 2 is scheduled to utilize GNF3 an Experiment see note farther below.

Zip of 3
GNFA Amendment 15 - Exemption from Reporting Certain Unplanned Contamination Events

Document Title: GNF-A Response to NRC Request for Additional Information

Document Type: Letter
                               Response to Request for Additional Information (RAI)

Document Date: 04/16/2020
https://adamswebsearch2.nrc.gov/webSearch2/main.jsp?AccessionNumber=ML19009A271
Document Title: Global Nuclear Fuels-Americas (GNF-A) - Request for Exemption from 24-Hour Reporting Requirement of 10 CFR 70.50(b)(1).

Document Type: Letter

Document Date:01/09/2019

The link below is a zip file of 3 documents.  What I am picking up on is that Fermi 2 use of GNF3 is an experiment, and scheduled for next RFO (21) for a 24 month fuel cycle using high burnup fuel which is 3X as nasty according to Marvin Resnikoff (citation needed) 
I have only skimmed these documents, they require study and informed / expert interpretation.   Elsewhere GNF America has authorization for enrichment up to 8%.  Most likely the new GNF3 for first time "Experimental Use" at Fermi 2 will be Proprietary. 

A multitude of problems at Fermi 2 but no financial resources to secure Expertise / Legal at level necessary.
Pro bono contributions have been generous, but those resources are exhausted.

Zip of 3
GE Hitachi Nuclear Energy Transmittal of Event-Specific CPR/ICPR Biases and Uncertainties and Peak Pressure Adders for AOO Licensing Applications.

Tuesday, July 21, 2020

Three Mile Island:  NRC Inspection Report No. 05000289/2020003, Exelon Generation Co., LLC, Three Mile Island Nuclear Station, Unit 1

Three Mile Island:  NRC Inspection Report No. 05000289/2020003, Exelon Generation Co., LLC, Three Mile Island Nuclear Station, Unit 1

Saturday, July 18, 2020

Susquehanna Steam Electric Station, Units 1 and 2 - Regulatory Audit for License Amendment Request to Revise Technical Specification 3.8.1 to Create a New Condition for an Inoperable Manual Synchronization Circuit (EPID L-2020-LLA-0118)

Subject: Susquehanna Steam Electric Station, Units 1 and 2 - Regulatory Audit for License Amendment Request to Revise Technical Specification 3.8.1 to Create a New Condition for an Inoperable Manual Synchronization Circuit (EPID L-2020-LLA-0118)
 
ADAMS Accession No. ML20189A182
 

Three Mile Island Nuclear Station, Unit 1 - Termination of Emergency Response Data System Feed to the U.S. Nuclear Regulatory Commission

Subject:  Three Mile Island Nuclear Station, Unit 1 - Termination of Emergency Response Data System Feed to the U.S. Nuclear Regulatory Commission

ADAMS Accession No.:  ML20178A606

Friday, July 17, 2020

TMI Unit 1 - Termination of Emergency Response Data System Feed

Document Title:     Three Mile Island Nuclear Station Unit 1 - Termination of Emergency Response Data System Feed to the U.S. Nuclear Regulatory Commission

Document Type:     Letter

Document Date:     07/16/2020

NRC to Hold Virtual Meeting to Discuss 2019 Performance of Davis-Besse and Perry Nuclear Power Plants

Nuclear Regulatory Commission - News Release
No: III-20-007 July 14, 2020
Contact: Viktoria Mitlyng, 630-829-9662 Prema Chandrathil, 630-829-9663

NRC to Hold Virtual Meeting to Discuss 2019 Performance of Davis-Besse and Perry Nuclear Power Plants
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Nuclear Regulatory Commission staff will discuss the 2019 safety performance of two nuclear power plants in Ohio during a virtual meeting scheduled for July 23.

The Davis-Besse nuclear power plant is in Oak Harbor, Ohio., and the Perry nuclear power plant is in Perry, Ohio. All the units are operated by Energy Harbor Nuclear Corp.

The virtual session will begin at 5:30 p.m., Eastern Time. Online registration is required to participate. Following registration, a confirmation email will be sent with details on how to join the meeting. To hear the presentation, those interested must register to obtain the phone call-in number.

NRC staff responsible for plant inspection and oversight will participate, including the resident inspectors based full-time at the sites.

Davis-Besse and Perry operated safely during 2019. At the conclusion of the year, all inspection findings and performance indicators for the plants were green, or of very low safety significance. As a result, the plants in 2020 will receive the normal level of oversight, which entails thousands of hours of inspection each year.

The NRC Reactor Oversight Process uses color-coded inspection findings and indicators to measure plant performance. The colors start at green and increase to white, yellow or red, commensurate with the safety significance of the issues involved. Inspection findings or performance indicators with more than very low safety significance trigger increased NRC oversight.

Inspections are performed by two NRC resident inspectors assigned to each plant and specialist inspectors from the Region III Office in Lisle, Ill.

The annual assessment letters for Davis Besse and Perry, as well as the meeting notice, are available on the NRC websiteCurrent performance information for the plants is also available and is updated on a quarterly basis.

Monday, July 13, 2020

Exelon: Issuance of Amendments Revising the High Radiation Area Administrative Controls (EPID L-2019-LLA-0133 and L-2019-LLA-0134)la

SUBJECT:  Braidwood Station, Units 1 and 2; Byron Station, Unit Nos 1 and 2; Calvert Cliffs Nuclear Power Plant, Units 1 and 2; Clinton Power Station, Unit No. 1; Dresden Nuclear Power Station, Units 2 and 3; James A. FitzPatrick Nuclear Power Plant; LaSalle County Station, Units 1 and 2; Limerick Generating Station, Units 1 and 2; Nine Mile Point Nuclear Station, Units 1 and 2; Peach Bottom Atomic Power Station, Units 2 and 3; Quad Cities Nuclear Power Station, Units 1 and 2; R.E. Ginna Nuclear Power Plant; and Three Mile Island Nuclear Station, Unit 1 – Issuance of Amendments Revising the High Radiation Area Administrative Controls (EPID L-2019-LLA-0133 and L-2019-LLA-0134)

ADAMS Accession No. ML20134H940

Exelon_ML20134H940.pdf

Friday, July 10, 2020

New publication about the Three Mile Island accident, (Scientific Reports, July, 2020)

Abstract
The 1979 accident at the Three Mile Island nuclear power station in Pennsylvania released about 22 million Curies of xenon-133 into the environment. Because physical dosimetry indicated exposures to the nearby population of less than about 2 mSv, discernible impacts to the health of the exposed population are not generally believed to have resulted. However, there is contrary evidence, including especially the results of biodosimetry via cytogenetic analysis using the FISH method. This report examines the discrepancy between the results of physical dosimetry and biodosimetry, which among the small number of persons examined indicated exposures between 600 and 900 mSv. The paradox reveals a fundamental error in the health physics body of knowledge: the definition of the energy imparted to tissue, ε, fails to properly account for the temporal distribution of ionization products resulting from dilute contamination with an internally incorporated beta-emitting radionuclide. Application of a century-old result describing “shot noise” in an electronic system repairs the deficiency. The Xe-133 concentration in the tissue of those individuals exposed to the most intense portion of the radioactive plume released from the TMI facility is shown to have been on the order of 0.1 μCi/l, persisting for multiple hours. Shot noise reference doses in the range from 820 to 1,700 mSv follow, a result which is consistent with biodosimetric analysis. The finding should motivate a comprehensive re-evaluation of the conventional understanding of the 1979 accident at the Three Mile Island nuclear power station, especially regarding its impact upon the population of the surrounding area.
"Correcting that single omission, it is shown that the true biological impact to those most exposed to radioactive releases from the damaged facility (measured as a reference dose) lies in the range at or above 1,000 mSv. The exposure is sufficient to explain acute effects observed at the time of the accident, including radiation sickness."