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 Facility
Event 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
 
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.

 

 
 
Department of Justice
U.S. Attorney’s Office
Southern District of Ohio

FOR IMMEDIATE RELEASE
Tuesday, July 21, 2020

U.S. Attorney, FBI to announce charges related to $60 million bribe to state official & associates

COLUMBUS, Ohio – Federal officials will brief the media on a public corruption racketeering conspiracy involving $60 million.

 

The briefing will be held:

 

TODAY: TUESDAY, JULY 21, 2020

WHEN:           2:30PM

WHERE:         U.S. Attorney’s Office

                        Main Conference Room

                        303 Marconi Blvd. Suite 200

                        Columbus, Ohio 43215

WHO:             U.S. Attorney David M. DeVillers

                        Chris Hoffman, FBI, Special Agent in Charge

 *Pool coverage is strongly encouraged for video footage. Reporters not present in person will be given opportunity to ask questions via conference telephone line.*

Room available at 2:15PM. ID and valid media credential will be required for entrance on Marconi Blvd., where someone will bring you into the building. No TV lighting provided. Please practice social distancing inside the main conference room/common areas and wear a mask.

Contact Jennifer Thornton at jennifer.thornton@usdoj.gov by 1PM to join via conference telephone line. 

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

 

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.
 

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