Wednesday, April 29, 2020
Beaver Valley Work Hour Rule Exemption / Plan
| Document Title: | Beaver Valley Work Hour Rule Exemption Request Due to Pandemic (L-20-140) |
| Document Type: | Exemption from NRC Requirements Letter |
| Document Date: | 04/18/2020 |
Docketed at 4:29pm on 4/20/2020
Document Title:
Limerick Generating Station, Unit 1 - Issuance of Relief Request I4R-23 Associated with Pandemic-Related Issues - Examination of Containment Surfaces Requiring Augmented Examination (Category E-C) (EPID L-2020-LLR-0044 [COVID-19])
Document Type:
Letter
Safety Evaluation
Document Date:
04/20/2020
Docketed at 3:29pm on 04/20/2020
Document Title: Beaver Valley Power Station, Units 1 and 2 - Verbal Part 26 Exemption - Delivered 4/18/20 at 7:00 p.m.
Document Type:
Exemption from NRC Requirements
Document Date:
04/18/2020
TMI-1 Changes to Tech Spec Base Changes
Document Title:
Three Mile island Nuclear Station, Unit 1 - Submittal of Changes to Technical Specifications Bases
Document Type:
Letter
License-Application for Facility Operating License (Amend/Renewal) DKT 50
Technical Specification, Bases Change
Document Date:
04/13/2020
ML20104B817
https://adamswebsearch2.nrc.
Three Mile island Nuclear Station, Unit 1 - Submittal of Changes to Technical Specifications Bases
Document Type:
Letter
License-Application for Facility Operating License (Amend/Renewal) DKT 50
Technical Specification, Bases Change
Document Date:
04/13/2020
ML20104B817
https://adamswebsearch2.nrc.
Peach Bottom Unit 1, Decomm Status Report - 2019
| Document Title: | Peach Bottom Atomic Power Station, Unit 1, Decommissioning Status Report - 2019 |
| Document Type: | Letter Status Report |
| Document Date: | 03/27/2020 |
Beaver Valley Work Hour Rule Exemption / Plan
Placed in ADAMS at 12:20 today 4/20/20, dated 4/18/20
| Document Title: | Beaver Valley Work Hour Rule Exemption Request Due to Pandemic (L-20-140) |
| Document Type: | Exemption from NRC Requirements Letter |
| Document Date: | 04/18/2020 |
Docketed at 4:29pm on 4/20/2020
Document Title:
Limerick Generating Station, Unit 1 - Issuance of Relief Request I4R-23 Associated with Pandemic-Related Issues - Examination of Containment Surfaces Requiring Augmented Examination (Category E-C) (EPID L-2020-LLR-0044 [COVID-19])
Document Type:
Letter
Safety Evaluation
Safety Evaluation
Document Date:
04/20/2020
Docketed at 3:29pm on 04/20/2020
Document Title: Beaver Valley Power Station, Units 1 and 2 - Verbal Part 26 Exemption - Delivered 4/18/20 at 7:00 p.m.
Document Type:
Exemption from NRC Requirements
Document Date:
04/18/2020
N2
MJK
Beaver Valley Part 26 / PN DEP Non-Disclosure
|
Beaver Valley - REACTOR COOLANT SYSTEM (RCS) PRESSURE BOUNDARY DEGRADED
U.S. Nuclear Regulatory Commission
Operations Center
Operations Center
Event Reports For
4/24/2020 - 4/27/2020
4/24/2020 - 4/27/2020
| 54680 |
| Power Reactor | Event Number: 54680 |
| Facility: BEAVER VALLEY Region: 1 State: PA Unit: [] [2] [] RX Type: [1] W-3-LP,[2] W-3-LP NRC Notified By: JUSTIN E. CROCKER HQ OPS Officer: HOWIE CROUCH | Notification Date: 04/24/2020 Notification Time: 07:00 [ET] Event Date: 04/24/2020 Event Time: 01:30 [EDT] Last Update Date: 04/24/2020 |
| Emergency Class: NON EMERGENCY 10 CFR Section: 50.72(b)(3)(ii)(A) - DEGRADED CONDITION | Person (Organization): FRANK ARNER (R1DO) |
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current. PWR | Current RX Mode | |||||||
| 2 | N | N | 0 | Refueling | 0 | Refueling |
Event Text
| REACTOR COOLANT SYSTEM (RCS) PRESSURE BOUNDARY DEGRADED "At 0130 [EDT] on April 24, 2020, during the Beaver Valley Power Station, Unit 2 refueling outage, while performing examinations of the 66 reactor vessel head penetrations, it was determined that one penetration could not be dispositioned as acceptable per ASME Code Section XI. Penetration 37 will require repair prior to returning the vessel head to service. The indication was not through wall and there was no evidence of leakage based on inspections performed on the top of the reactor vessel head. The examinations were being performed to meet the requirements of 10 CFR 50.55a(g)(6)(ii)(D) and ASME Code Case N-729-4 to find potential flaws/indications before they grow to a size that could potentially jeopardize the structural integrity of the reactor vessel head pressure boundary. This event is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(ii)(A). "There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified." |
Edwin Lyman @NucSafetyUCS 4/27/20, 9:02 AM
Summary of 4/2/20 COVID Public Meeting
Document Title:
Summary of April 2, 2020, Public Meeting with Nuclear Industry to Discuss COVID-19 Regulatory Impacts.
Document Type:
Document Date:
Summary of April 2, 2020, Public Meeting with Nuclear Industry to Discuss COVID-19 Regulatory Impacts.
Document Type:
Meeting Summary
Memoranda
Memoranda
Document Date:
Beaver Valley Summary of March 31 Public Mtg
Document Title:
Beaver Valley Power Station, Unit Nos. 1 and 2 - Summary of March 31, 2020, Public Meeting with Energy Harbor Nuclear Corp. to Discuss COVID-19 Potential Submittals of Regulatory Actions
Document Type:
Meeting Summary
Document Date:
04/27/2020
Beaver Valley Power Station, Unit Nos. 1 and 2 - Summary of March 31, 2020, Public Meeting with Energy Harbor Nuclear Corp. to Discuss COVID-19 Potential Submittals of Regulatory Actions
Document Type:
Meeting Summary
Document Date:
04/27/2020
Monday, April 27, 2020
Saturday, April 25, 2020
Wednesday, April 22, 2020
NRC Schedules Virtual Meeting to Discuss 2019 Safety Performance of Three TVA Nuclear Power Plants
Nuclear Regulatory Commission - Press Release
No: II-20-011 April 21, 2020
Contact: Roger Hannah, 404-997-4417
NRC Schedules Virtual Meeting to Discuss 2019 Safety Performance of Three TVA Nuclear Power Plants
Nuclear Regulatory Commission staff will discuss the 2019 safety performance of the Browns Ferry, Sequoyah, and Watts Bar nuclear power plants during a virtual meeting scheduled for April 30.
The three-unit Browns Ferry plant is located in north Alabama, and the Sequoyah and Watts Bar plants, both of which have two units, are in east Tennessee. All three plants are operated by the Tennessee Valley Authority.
The session will be held from 2-4 p.m., Eastern Time, with NRC employees responsible for plant inspections participating, including the resident inspectors based at the site. The meeting will be accessible via Skype. For individuals without access to Skype, the telephone conference number is 301-415-0333, passcode is 74672#.
The NRC determined that the Browns Ferry, Sequoyah, and Watts Bar nuclear power plants operated safely during 2019 and all three plants are currently under the NRC’s normal level of oversight.
The NRC Reactor Oversight Process, which requires thousands of hours of inspection each year, 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 at the Browns Ferry, Sequoyah, and Watts Bar plants are performed by NRC resident inspectors and other inspection specialists from the Region II office in Atlanta.
The annual assessment letters for the Browns Ferry plant, the Sequoyah plant, and the Watts Bar plant, which include upcoming inspection plans for the plants, are available on the NRC website. Current performance information for Browns Ferry Unit 1, Browns Ferry Unit 2, Browns Ferry Unit 3, Sequoyah Unit 1, Sequoyah Unit 2, Watts Bar Unit 1, and Watts Bar Unit 2, is also available, updated on a quarterly basis.
Tuesday, April 21, 2020
NRC Schedules Virtual Meeting to Discuss 2019 Safety Performance of Brunswick and Harris Nuclear Power Plants
Nuclear Regulatory Commission - Press Release
No: II-20-010 April 20, 2020
Contact: Roger Hannah, 404-997-4417
NRC Schedules Virtual Meeting to Discuss 2019 Safety Performance of Brunswick and Harris Nuclear Power Plants
Nuclear Regulatory Commission staff will discuss the 2019 safety performance of the Brunswick and Harris nuclear power plants during a virtual meeting scheduled for April 29.
The two-unit Brunswick plant is located on the southeastern coast of N.C., and the single-unit Harris plant is in the central part of the state south of Raleigh. Both plants are operated by Duke Energy.
The session will be held from 3-4 p.m., Eastern Time, with NRC employees responsible for plant inspections participating, including the resident inspectors based at the site. The meeting will be accessible via Skype. For individuals without access to Skype, the telephone conference number is 301-415-0333, passcode 7352349#.
The NRC determined that the Brunswick and Harris plants operated safely during 2019. Both plants are currently under the NRC’s normal level of oversight.
The NRC Reactor Oversight Process, which requires thousands of hours of inspection each year, 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 at the Brunswick and Harris nuclear power plants are performed by NRC resident inspectors and other inspection specialists from the Region II office in Atlanta.
The annual assessment letters for the Brunswick plant and the Harris plant, which include upcoming inspection plans for the plants, are available on the NRC website. Current performance information for Brunswick Unit 1, Brunswick Unit 2, and Harris is also available and is updated on a quarterly basis.
Wednesday, April 15, 2020
NRC Issues Report on Review of Indian Point Pipeline Issues; Reactors Remain Safe
Nuclear Regulatory Commission - News Release
No: 20-023 April 15, 2020
CONTACT: Scott Burnell, 301-415-8200
NRC Issues Report on Review of Indian Point Pipeline Issues; Reactors Remain Safe
An expert team of Nuclear Regulatory Commission staff and outside specialists has concluded the Indian Point Energy Center nuclear power plant would remain safe should there be a potential accident on a 42-inch natural gas pipeline near the plant. The team’s report also recommends several follow-up actions, including that the plant owner, Entergy, revisit the assumptions it made in its analysis.
The team’s safety conclusion is based on two factors. First, the Algonquin Incremental Market pipeline has a very small chance of rupture near Indian Point, due to the pipeline’s modern construction, quality control and additional “high consequence” requirements for inspection and an integrity management program. Second, Indian Point’s safety systems sit well outside the potential impact zones for postulated AIM pipeline accident effects such as heat, pressure and projectiles. The team’s analyses also determined that any pipeline-related increase in Indian Point’s risk fell below the NRC’s thresholds for prompting additional action.
The team’s report was submitted in response to direction from Margaret M. Doane, the NRC’s Executive Director for Operations, following an NRC Inspector General report on the agency’s handling of public concerns about the pipeline issues. The team reviewed how Entergy and the NRC analyzed potential hazards from the proposed AIM pipeline in 2014, as well as how the NRC processed a public stakeholder’s petitions for enforcement action related to the pipeline. The team recommended that Entergy update the assumptions used in its analysis with the new information the team developed during its review. The team also recommended several improvements to NRC processes related to the conduct of technical reviews, peer review, inspection support, interagency cooperation and public petition processing. The NRC intends to hold a public meeting near the plant regarding the report when the region has sufficiently recovered from the COVID-19 public health emergency.
The team included experts in NRC engineering reviews and probabilistic risk analysis, as well as a Pipeline and Hazardous Materials Safety Administration safety expert. The team also incorporated important insights from researchers at Sandia National Laboratories with expertise on natural gas modeling and fire risk. All team members were independent of those performing prior reviews regarding the AIM pipeline and its potential effects on Indian Point. The team’s work was peer-reviewed by a mechanical engineering expert from the NRC’s independent Advisory Committee on Reactor Safeguards.
March 4, 2020, NRC Generic Fundamentals Examination Results for Susquehanna Steam Electric Station, Units 1 and 2 (Cover Letter Publicly Available, Enclosures Withheld from Public)
March 4, 2020, NRC Generic Fundamentals Examination Results for Susquehanna Steam Electric Station, Units 1 and 2 (Cover Letter Publicly Available, Enclosures Withheld from Public)
ADAMS Accession No. ML20105A188
March 4, 2020, NRC Generic Fundamentals Examination Results for Peach Bottom Atomic Power Station, Units 2 and 3 (Cover Letter Publicly Available, Enclosures Withheld from Public)
March 4, 2020, NRC Generic Fundamentals Examination Results for Peach Bottom Atomic Power Station, Units 2 and 3 (Cover Letter Publicly Available, Enclosures Withheld from Public)
ADAMS Accession No. ML20105A182
NRC Schedules Virtual Meeting to Discuss 2019 Safety Performance of Farley and Hatch Nuclear Power Plants
Nuclear Regulatory Commission - Press Release
No: II-20-008 April 14, 2020
Contact: Roger Hannah, 404-997-4417
NRC Schedules Virtual Meeting to Discuss 2019 Safety Performance of Farley and Hatch Nuclear Power Plants
Nuclear Regulatory Commission staff will discuss the 2019 safety performance of the Farley and Hatch nuclear power plants during a virtual meeting scheduled for April 21.
The two-unit Farley plant is located in southern Alabama and the two-unit Hatch plant is in southern Georgia. Both nuclear power plants are operated by Southern Nuclear Operating Co.
The session will be held from 4-5:30 p.m., Eastern Time, with NRC employees participating who are responsible for plant inspections, including the resident inspectors based at the site.
The meeting will be accessible to the public and media via Skype. For individuals without access to Skype, the telephone conference number is 301-415-0333, passcode 68905#.
The NRC determined that the Farley and Hatch plants operated safely during 2019 and all inspection findings and performance indicators had very low safety significance. As a result, both plants remain under the NRC’s normal level of oversight.
The NRC Reactor Oversight Process, which requires thousands of hours of inspection each year, 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 at the Farley and Hatch plants are performed by NRC resident inspectors and other inspection specialists from the NRC Region II office in Atlanta.
The annual assessment letters for the Farley plant and the Hatch plant, which include upcoming inspection plans for the plants, are available on the NRC website. Current performance information for Farley Unit 1, Farley Unit 2, Hatch Unit 1, and Hatch Unit 2 is also available and is updated on a quarterly basis.
20-008.ii_.pdf
No: II-20-008 April 14, 2020
Contact: Roger Hannah, 404-997-4417
NRC Schedules Virtual Meeting to Discuss 2019 Safety Performance of Farley and Hatch Nuclear Power Plants
Nuclear Regulatory Commission staff will discuss the 2019 safety performance of the Farley and Hatch nuclear power plants during a virtual meeting scheduled for April 21.
The two-unit Farley plant is located in southern Alabama and the two-unit Hatch plant is in southern Georgia. Both nuclear power plants are operated by Southern Nuclear Operating Co.
The session will be held from 4-5:30 p.m., Eastern Time, with NRC employees participating who are responsible for plant inspections, including the resident inspectors based at the site.
The meeting will be accessible to the public and media via Skype. For individuals without access to Skype, the telephone conference number is 301-415-0333, passcode 68905#.
The NRC determined that the Farley and Hatch plants operated safely during 2019 and all inspection findings and performance indicators had very low safety significance. As a result, both plants remain under the NRC’s normal level of oversight.
The NRC Reactor Oversight Process, which requires thousands of hours of inspection each year, 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 at the Farley and Hatch plants are performed by NRC resident inspectors and other inspection specialists from the NRC Region II office in Atlanta.
The annual assessment letters for the Farley plant and the Hatch plant, which include upcoming inspection plans for the plants, are available on the NRC website. Current performance information for Farley Unit 1, Farley Unit 2, Hatch Unit 1, and Hatch Unit 2 is also available and is updated on a quarterly basis.
20-008.ii_.pdf
Friday, April 10, 2020
Response to Request for Additional Information Related to License Amendment Request for Proposed Changes to the Three Mile Island Nuclear Station Permanently Defueled Emergency Plan and Emergency Action Level Scheme
TMI-20-005
February 19, 2020
U.S. Nuclear Regulatory Commission
ATTN: Document Control Desk
Washington, DC 20555-0001
Three Mile Island Nuclear Station, Unit 1
Renewed Facility Operating License No. DPR-50
NRC Docket No. 50-289
Three Mile Island Nuclear Station, Unit 2
Renewed Facility Operating License No. DPR-73
NRC Docket No. 50-320
Subject:
Response to Request for Additional Information Related to License Amendment Request for Proposed Changes to the Three Mile Island Nuclear Station Permanently Defueled Emergency Plan and Emergency Action Level Scheme
Thursday, April 9, 2020
Two Percent Question
The Holtec LLCs have failed to comply with 10 C.F.R. §§ 50.75(b)(1) and (e)(1)(i) because the license transfer application and the supporting PSDAR and decommissioning cost estimate impermissibly assume an annual two percent real rate of return on nuclear-decommissioning trust monies.
DEP Raises Serious Questions About TMI-2 License Transfer, (Letter to NR)
April 6, 2020
Kristine L. Svinicki, Chairman
U.S. Nuclear Regulatory Commission Office of the Chairman
Mail Stop O-16 B33
Washington, D.C. 20555-0001
U.S. Nuclear Regulatory Commission Office of the Chairman
Mail Stop O-16 B33
Washington, D.C. 20555-0001
Re: Three Mile Island Unit 2 License Transfer Dear Chairman Svinicki:
I am writing to you to express my serious concern regarding the proposed license transfer of the Three Mile Island Unit 2 (TMI Unit 2) nuclear power plant from GPU Nuclear Corporation to the EnergySolutions’ subsidiary TMI-2 Solutions, LLC (TMI-2 Solutions).
As you are aware, in 1979, the TMI Unit 2 power reactor had the worst nuclear accident in U.S. history. The TMI Unit 2 nuclear accident resulted in damage to the majority of the reactor core, released millions of curies of radioactive noble gases into the environs, and grossly contaminated the interiors of the containment and auxiliary buildings. Because of this, we understand there are very high radiation areas within TMI Unit 2 that present a grave risk to personnel that enter. Despite the limited entries into the containment building to remove damaged nuclear fuel in the 1980s, there are vast areas in the plant with unknown radiological conditions related to the TMI Unit 2 accident. I firmly believe TMI Unit 2 is the most radiologically contaminated facility in our nation outside of the Department of Energy’s weapons complex.
When it was announced that TMI Unit 1 was going to be permanently shut down, the Commonwealth’s residents and the Pennsylvania Department of Environmental Protection (DEP)) believed this to mean that TMI Unit 1 would enter into a SAFSTOR status for several decades and be decommissioned first. This would allow for the further decay of radioactivity within TMI Unit 2 and reduce worker exposure and possible environmental releases of radiation during clean up.
However, this understanding is no longer the case. With the announcement of GPU Nuclear Corporation planning to shed its responsibility for TMI Unit 2 to TMI-2 Solutions, we now understand that TMI-2 Solutions plans to immediately begin the decommissioning of TMI Unit 2 with the accrued $800 million in the financial assurance fund that GPU Nuclear Corporation and the NRC currently control. This leaves us with many questions and concerns, which I outline in more detail below, about what a license transfer of TMI Unit 2 will mean for Pennsylvania, the local environment, and the communities surrounding Three Mile Island.
Secretary
Rachel Carson State Office Building | P.O. Box 2063 | Harrisburg, PA 17105-2063 | 717.787.2814 | www.dep.pa.gov
Rachel Carson State Office Building | P.O. Box 2063 | Harrisburg, PA 17105-2063 | 717.787.2814 | www.dep.pa.gov
Kristine L. Svinicki, Chairman - 2 - April 6, 2020
Concerns with Three Mile Island Unit 2 License Transfer
Environmental & Safety Impacts
Due to the TMI Unit 2 power reactor partial meltdown, it is our understanding there are still very high radiation areas within TMI Unit 2 that would present a grave risk to any personnel that enter. Related to this understanding, I have the following questions about environmental impacts and safety associated with the decommissioning of TMI Unit 2:
- What increased environmental surveillance and pollution controls will the NRC require during clean-up of TMI Unit 2 to ensure any radiological releases are detected?
- The TMI Unit 2 facility is in the middle of the Susquehanna River, a major water supply for the region that drains into the Chesapeake Bay. What environmental and pollution controls will be put in place to ensure no contamination of this critical water source?
- What flood controls will be utilized during decommissioning to mitigate a worst-case flood scenario on the Susquehanna (e.g. a weather event similar to Hurricane Agnes in 1972 that produced 19-inches of rain in Pennsylvania)?
- Will the NRC require a local decommissioning advisory committee to be established to assure the clean-up of TMI Unit 2 is transparent to the public and local and state governments?Cost of Clean-Up & Financial ResponsibilityAs noted above, GPU Nuclear Corporation and the NRC currently have $800 million in its financial assurance fund for decommissioning TMI Unit 2. However, estimates have shown it will cost $1.2 billion to decommission TMI Unit 2. For these reasons, I have the following questions, related to the cost and financial responsibility of cleaning up TMI Unit 2:
- Given there is a significant disparity between the estimated cost to decommission TMI Unit 2 from the amount of funds currently available, what funding source will be used to cover the deficit?
- Since the radiological conditions inside TMI Unit 2 are unknown, the actual cost to decommission it could be much higher than the current estimate of $1.2 billion. What legal and financial assurances will be put in place to address this potential?
- Who will the NRC require to retain financial responsibility to clean-up TMI Unit 2 after the license has been transferred?
Radioactive Waste Handling - Due to the severe contamination from the partial meltdown and the unknown radioactivity levels of materials that will need to be disposed, I request to know the following information related to how the radioactive waste from TMI Unit 2 will be handled:• Has the U.S. Department of Energy agreed to dispose of the TMI Unit 2 reactor vessel, which has a portion of the damaged nuclear fuel from the 1979 accident still fused inside?
Kristine L. Svinicki, Chairman - 3 - April 6, 2020
- How will TMI-2 Solutions dispose of any contaminated lead shielding, which is now mixed waste, that may be present in TMI Unit 2?
- Are there volume and activity estimates of the Class B & C low-level radioactive waste that cannot be shipped to the EnergySolutions disposal site in Utah?
- Has the low-level radioactive waste disposal site in Texas agreed to accept the Class B & C waste?
- Is there any greater than Class C low-level radioactive waste in TMI Unit 2? If so, will that remain onsite?
- If asked by the licensee, will the NRC consider and approve very low-level radioactive waste to be disposed of in non-hazardous landfills in Pennsylvania?Given my stated concerns, I hope you and your fellow Commissioners will thoughtfully consider the unique aspects of the severely damaged TMI Unit 2 nuclear reactor and not approve a license transfer until all parties are satisfied that the decommissioning can be done safely. Equally important, we require firm legal assurances that financial resources are available to complete decommissioning once started, including bonding between the Commonwealth and licensee.I also expect no radioactive waste from TMI Unit 2 will be left on Three Mile Island.Additionally, I ask your executive staff and the current and proposed licensee brief my fellow local and state officials responsible for protection of the public and environment. Obviously, the current health crisis will dictate whether this meeting is in person or virtual. Furthermore, in that the licensee has recently amended the Post-Shutdown Decommissioning Activities Report (PSDAR) and has proposed a significant schedule change, the Pennsylvania DEP expects the NRC to hold a local PSDAR meeting after the COVID-19 situation has resolved so that the proposed clean-up work at TMI Unit 2 and timeline can be presented to the public, with ample opportunity for questions and discussion.Should you or your staff have any questions regarding my stated concerns or wish to discuss them further, please feel free to contact David J. Allard, Director for Bureau of Radiation Protection, by e-mail at djallard@pa.gov or by telephone at 717.787.2480.Sincerely,Patrick McDonnell Secretary
cc: David J. Allard, Director, Bureau of Radiation Protection, DEP
NRC Commissioner Jeff Baran, Washington, DC 20555-0001
NRC Commissioner Annie Caputo, Washington, DC 20555-0001 NRC Commissioner David A. Wright, Washington, DC 20555-0001 David Lew, Regional Administrator, U.S. NRC Region I,
NRC Commissioner Jeff Baran, Washington, DC 20555-0001
NRC Commissioner Annie Caputo, Washington, DC 20555-0001 NRC Commissioner David A. Wright, Washington, DC 20555-0001 David Lew, Regional Administrator, U.S. NRC Region I,
2100 Renaissance Blvd., Ste. 100, King of Prussia, PA 19406-2713
Tuesday, April 7, 2020
NRC to Conduct Public Webinar on April 21 to Discuss Indian Point Nuclear Power Plant Decommissioning Topics
Nuclear Regulatory Commission - News Release
No: I-20-002 April 7, 2020
Contact: Diane Screnci, 610-337-5330 Neil Sheehan, 610-337-5331
NRC to Conduct Public Webinar on April 21 to Discuss Indian Point Nuclear Power Plant Decommissioning Topics
The Nuclear Regulatory Commission staff will hold a webinar for interested members of the public on April 21 regarding the decommissioning of the Indian Point nuclear power plant, located in Buchanan, N.Y.
The purpose of the webinar will be to provide key facts regarding the decommissioning process and how the NRC regulates such activities through on-site inspections and other reviews.
The webinar will begin at 1 p.m., Eastern Time. Participants will be able to view slides prepared by NRC staff and ask questions verbally and in writing via a web page set up to host the session. Online registration is required to take part. The meeting notice will contain information on how to access the webinar via phone bridge.
One of the two operating reactors at the plant, Unit 2, is scheduled to permanently cease operations in late April. The other, Unit 3, will be taken offline for the last time in April 2021. The Unit 1 reactor was permanently shut down in 1974 and has been in long-term storage since then, awaiting eventual decommissioning.
The NRC is currently reviewing an application to transfer the license for the plant from Entergy to Holtec, which has proposed decommissioning the facility in a more accelerated manner.
Monday, April 6, 2020
NRC Schedules Virtual Meeting to Discuss Performance of Honeywell Facility
Nuclear Regulatory Commission - Press Release
No: II-20-007 April 6, 2020
Contact: Roger Hannah, 404-997-4417
NRC Schedules Virtual Meeting to Discuss Performance of Honeywell Facility
The Nuclear Regulatory Commission staff will discuss the results of a performance review of the Honeywell uranium conversion facility in Metropolis, Ill., during a virtual meeting scheduled for April 14.
The session will be held from 1-3 p.m., Eastern Time (12-2 p.m., Central Time) with NRC officials from the Region II office in Atlanta and the agency’s headquarters in Rockville, Md., as well as Honeywell officials at the facility in Metropolis. The meeting can be accessed by the public and media via Skype and NRC officials will be available following the formal portion of the meeting to answer questions. For individuals without access to Skype, a telephone conference call number will also be available.
The NRC staff assessed performance of the Honeywell facility during the period beginning Jan. 1, 2018 and ending Dec. 31, 2019, in safety operations, safeguards, radiological controls, facility support and other areas. Although the safeguards area was assessed, that information is not publicly available due to its sensitive nature. The NRC staff review determined that Honeywell continued to conduct its activities safely and securely, protecting public health and the environment.
The NRC does not have resident inspectors at the Metropolis facility, but fuel facility inspectors from its Atlanta regional office conduct periodic inspections of various aspects of the operation.
Because the review found that none of the program areas needed improvement and the facility is currently in a “ready-idle” status with a reduced amount of material on site, the NRC has adjusted its inspection program accordingly. That reduction in overall inspections will remain in effect for the next two years if the facility remains in “ready-idle” status.
A copy of the NRC letter to the company regarding the performance review is publicly available on the NRC website.
For virtual meeting access or telephone call-in information, please contact either Tom Vukovinsky at 404-997-4622 (email: Thomas.vukovinsky@nrc.
Thursday, April 2, 2020
Sen. Muth Calls on Exelon to Make Greater Commitment to Worker and Community Safety
Capitolwire: Text of Senator Muth’s April 1 press release.
Limerick Township, Pa. -- Senator Katie Muth (D-Berks, Chester, Montgomery) today renewed her call on Exelon to improve its commitment to worker and community safety during the refueling at the Limerick Generating Station in Montgomery County, and made a short list of requests of the corporate energy giant in a letter to senior executives.
“Thus far, Exelon has provided an inadequate pandemic response plan, withheld information from county and state officials, and failed to prioritize the safety of its employees, contract workers, community first responders, as well as all residents of the 44th senatorial district and entire region,” Senator Muth wrote. “This is grossly irresponsible as Exelon has brought at least 1,400 workers to the epicenter of Pennsylvania’s Covid-19 pandemic.”
In an effort to contain the spread of Covid-19 through Montgomery County and beyond, Senator Muth is asking Exelon to do the following:
* Provide a complete list of worker accommodations. A previously provided list is incomplete. This list will ensure that first responders are geographically aware of potential risk of exposure to Covid-19 and better inform hospitality employees of the need to take precautions in the cleaning and service of lodgings.
* Work with federal, state, and county officials to create and implement a 14-day, controlled quarantine protocol for all contracted workers. Exelon should continue to fully compensate workers during this time and cover all costs incurred by
workers during the quarantine.
* Continue to work with federal, state, county, and local officials throughout the refueling process, particularly improving transparency with regard to care of employees displaying symptoms of Covid-19, as requested by Congresswoman Dean and Commissioners Arkoosh and Moscowitz.
“These requests are simply a call for corporate responsibility to ensure maximum preventative measures to ensure safety and reduce harm of both workers, their families, essential workers across the tri-county area,” wrote Senator Muth. “It is my understanding that the plan is for many of these workers to move onto additional refueling projects, such as the scheduled Beaver Valley refueling project in western PA, as well as at other nuclear facilities across the country, and without proper safety and quarantine measures, we are risking a massive spread of Covid-19 across this state and nation.”
“By fulfilling these requests for increased mitigation, Exelon has an opportunity to right its wrongs and previous negligence, and demonstrate a commitment to protecting the health and safety of workers, their families and the community at large,” she concluded.
NRC Schedules Virtual Meeting to Discuss Performance of Framatome Facility
NRC Schedules Virtual Meeting to Discuss Performance of Framatome Facility
The Nuclear Regulatory Commission staff will discuss the results of a performance review for the Framatome nuclear fuel fabrication facility in Richland, Wash., during a virtual meeting scheduled for April 7.
The session will be held from 4-5:30 p.m. Eastern Time (1-2:30 p.m. Pacific Time) with NRC officials from the Region II office in Atlanta and the agency’s headquarters in Rockville, Md., as well as Framatome officials at the facility in Richland. The meeting will be accessible to the public and media via Skype and NRC officials will be available following the formal portion of the meeting to answer questions. For individuals without access to Skype, a telephone conference number will be available.
The NRC staff assessed performance of the Framatome facility in Richland during the period beginning Jan. 1, 2018, and ending Dec. 31, 2019, in safety operations, safeguards, radiological controls, facility support and other areas. Although the safeguards area was assessed, that information is not publicly available due to its sensitive nature. The NRC staff review determined that Framatome continued to conduct its activities safely and securely, protecting public health and the environment.
The review found that no program area needed improvement, which means the NRC will continue its normal inspection program for such facilities. The NRC does not have resident inspectors at the Richland facility. Facility inspectors from the agency’s Atlanta regional office conduct periodic inspections of various aspects of the operation.
A copy of the NRC letter to the company regarding the performance review is publicly available on the NRC website.
For virtual meeting access or telephone call-in information, please contact either Richard Gibson Jr., at 404-997-4718 (email: Richard.gibson@nrc.gov
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