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
 
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.
 
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
 

 

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."
Nuclear Regulatory Commission - News Release
No: 20-038 July 9, 2020
CONTACT: David McIntyre, 301-415-8200
 
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.
 
Nuclear Regulatory Commission - News Release
No: I-20-015 July 6, 2020
Contact: Diane Screnci, 610-337-5330 Neil Sheehan, 610-337-5331
 
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
 

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)

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