The EFMR Monitoring Group is a non-profit, non-partisan organization which monitors radiation levels surrounding Peach Bottom Atomic Power Station, Susquehanna Steam Electric Station and Three Mile Island Nuclear Station.
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 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 confirmedthese 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.
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.
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 Facility
Event 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
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)."
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.
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.
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)
Document Title: Three Mile Island Nuclear Station Unit 1 - Termination of Emergency Response Data System Feed to the U.S. Nuclear Regulatory Commission
NRC to Hold Virtual Meeting to Discuss 2019 Performance of Davis-Besse and Perry Nuclear Power Plants
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.
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
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."
NRC Submits Report to Congress on Best Practices for Community Advisory Boards
Near Decommissioning Nuclear Power Plants
The Nuclear Regulatory Commission has submitted to Congress its report on best practices for community advisory boards associated with decommissioning activities at nuclear power plants. The report was mandated by the Nuclear Energy Innovation and Modernization Act.
To prepare the report, NRC staff conducted 11 public meetings from August through October 2019 to obtain insights from host states, communities near nuclear power plants, and existing community advisory boards. Staff also conducted two webinars to provide people unable to attend the meetings in person an opportunity to participate in the process.
The NRC staff used public comments from these meetings, responses to a questionnaire issued in September, and direct outreach to state and local officials and organizations to compile its report. The NRC received 1,235 oral and written comments from 216 commenters through these outreach efforts.
The report to Congress is available on the NRC website.
NRC Senior Resident Inspector Newly Assigned to Limerick Nuclear Power Plant
Nuclear Regulatory Commission officials in King of Prussia, Pa., have selected Adam Ziedonis as the new senior resident inspector at the Limerick Generating Station. The two-unit site is operated by Exelon Nuclear and is located in Limerick, Pa.
Ziedonis joins NRC Resident Inspector Sherlyn Haney at Limerick.
Most recently, Ziedonis was the senior resident inspector at the Hope Creek Generating Station in Hancocks Bridge, N.J. He has also been a resident inspector at the Salem nuclear power plant in Hancocks Bridge, N.J., and the Peach Bottom Atomic Power Station in Delta, Pa., and a region-based reactor inspector.
Ziedonis joined the agency’s Region I office in 2004 after earning his bachelor’s and master’s degrees in mechanical engineering from Drexel University in Philadelphia. He is a graduate of the NRC’s Nuclear Safety Professional Development Program and a registered Professional Engineer in the Commonwealth of Pennsylvania.
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 major work projects and interacting with plant workers and the public. Resident inspectors are assigned to a site for up to seven years.
Subject: Three Mile Island Nuclear Station, Unit 1 - Exemption Request from Certain Requirements of 10 CFR Part 73, Appendix B, "General Criteria for Security Personnel" (EPID L-2020-LLE-0096 [COVID-19]) ADAMS Accession No. ML20161A391 ML20161A391.pdf
Subject: Dresden, LaSalle, Limerick, Nine Mile Point, Peach Bottom, Quad Cities - Individual Notice of Consideration of Issuance of Amendments to Renewed Facility Operating Licenses, Proposed No Significant Hazards Consideration Determination, Opportunity for Hearing (Letter and Federal Register Notice) ADAMS Accession Nos.: ML20156A365 (Letter); ML20156A400 (FRN) ML20156A365.pdf ML20156A400.pdf
