SECY-20-0071, Weekly Information Report - Week Ending July 17, 2020
| ML20204A931 | |
| Person / Time | |
|---|---|
| Issue date: | 07/31/2020 |
| From: | Catherine Haney NRC/EDO/AO |
| To: | Commissioners NRC/OCM |
| C. COOK, 415-6397 | |
| References | |
| SECY-20-0071 | |
| Download: ML20204A931 (9) | |
Text
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INFORMATION REPORT JULY 31, 2020 SECY-20-0071 FOR: The Commissioners FROM: Catherine Haney Assistant for Operations Office of the Executive Director for Operations
SUBJECT:
WEEKLY INFORMATION REPORT - WEEK ENDING JULY 17, 2020 CONTENTS Enclosure Office of the Chief Human Capital Officer A Office of the Chief Information Officer B Office of Nuclear Reactor Regulation C Office of Nuclear Material Safety and Safeguards D Office of the Secretary E Catherin Digitally signed by Catherine Haney e Haney Date: 2020.07.31 16:00:10 -04'00' Catherine Haney Assistant for Operations, OEDO
Contact:
C. Cook, OEDO 301-415-6397
ML20204A931 OFFICE OEDO OEDO/AO NAME CCook CHaney DATE 7/24/20 7/31/20 Office of the Chief Human Capital Officer (OCHCO)
Items of Interest Week Ending JULY 17, 2020 ARRIVALS BOONE, TANNER NUCLEAR PROCESS ENGINEER NMSS BROWN, LADONNA ADMINISTRATIVE ASSISTANT R-II CAPONI, LOUIS GENERAL ENGINEER NRAN OCHCO GENTIS, DANIEL HUMAN RESOURCES SPECIALIST R-III GRAY, ARLISHA ADMINISTRATIVE ASSISTANT R-II HARTAGE, KAYLEH GENERAL ENGINEER NRAN OCHCO RANSFORD, TAMLA BRANCH CHIEF OCHCO RETIREMENTS NONE DEPARTURES ARCHER, ALEXANDER L. STUDENT INTERN OCHCO CONRON, CAROLYN STUDENT INTERN NRR HEATH, JERMAINE A. TECHNICAL ASSISTANT NRR JULY 31, 2020 ENCLOSURE A
Office of the Chief Information Officer (OCIO)
Items of Interest Week Ending JULY 17, 2020 Freedom of Information Act (FOIA) and Privacy Act (PA) Requests and Appeals Received During the Period of July 13 - July 17 Tracking Requesters Requesters Request Description Received Number Name Organization as submitted by requester Date 2020- Priscilla Conner & The transcript(s) of the NRCs interview(s) 07/10/2020 000269 Leonard Winters of the Administrative Coordinator in the Maintenance Planning Group at Peach Bottom Atomic Power Station in connection with the referenced NRC investigation, 1-2014-027.
2020- Priscilla Conner & Transcripts of interviews conducted by 07/11/2020 000270 Leonard Winters the Office of Investigations in OIG Case No. 1-2014-027.
2020- Koji Copies of the RASCAL result data ran 07/14/2020 000271 Hayasaki after the Tsunami hit the Fukushima nuclear plant; and a copy of the two-page analysis based on SOARCO "State-of-the-Art Reactor Consequence Analyses."
2020- Kathleen Environmental An updated list of active & inactive 07/15/2020 000272 OKelley Record Search facilities that possess or use radioactive materials, that are listed in the Material Licensing Tracking system database.
2020- Samantha L. Envirosite An updated electronic listing of the NIRS 07/15/2020 000273 Sederquest Corporation Land Use Control (LUC) data.
2020- Joni Pintado A copy of Amendment #46 of license 07/15/2020 000274 number 13-02650-02, dated 8/2009 docket number 030-13685/030-13705.
2020- E. Amy Alder, Cohen, Any and all records regarding the 07/16/2020 000275 LaBrecque Harvey, application for and initial construction of Wakeman & the Maine Yankee Atomic Power Station Guekguezian, in Wiscasset, Lincoln County, Maine, LLP Operating License No. DPR-36, U.S. AEC Docket Number 50-309, including but not limited to the Final Safety Analysis Report and all Addenda thereto.
JULY 31, 2020 ENCLOSURE B
Office of Nuclear Reactor Regulation (NRR)
Items of Interest Week Ending JULY 17, 2020 NuScale Submits Letter Requesting Standard Design Approval Based on the NuScale Standard Plant Design Certification Application On July 13, 2020, NuScale Power, LLC (NuScale) submitted a letter (Agencywide Documents Access and Management System (ADAMS) Accession No. ML20195C766) requesting approval of the current NuScale Small Modular Reactor design under Subpart E, Standard Design Approvals [SDA], of Title 10 of the Code of Federal Regulations (10 CFR) Part 52, upon completion of the U.S. Nuclear Regulatory Commission (NRC) staffs review and issuance of the Final Safety Evaluation Report. Issuance of the SDA will document completion of the NRC staffs, as well as the Advisory Committee on Reactor Safeguards technical review of the NuScale design.
Staff Accepts a NuScale Topical Report on Minimum Control Room Staffing for Review On July 14, 2020, the NRC accepted for review a NuScale topical report on the minimum control room staffing plan (ADAMS Accession No. ML20163A556) as part of the ongoing SDA pre-application activities.
Staff Hosted Public Meeting to Exchange Technical Information on Activities of Industry Materials Programs On July 14, 2020, the NRC staff held a public meeting to exchange technical information related to the activities of industry materials programs (ADAMS Accession No. ML20195B149).
Industry participants included the Electric Power Research Institute (EPRI) Materials Reliability Program (MRP), EPRI BWR Vessels and Internals Project (BWRVIP), Pressurized Water Reactor Owners Group (PWROG), International Materials Research, and EPRI Welding Repair and Technology Program. Example topics from the agenda included: probabilistic fracture mechanics; status of the BWRVIP, PWROG, and MRP efforts; 10 CFR 50.55a rulemaking; Regulatory Guide 1.99; FAVOR code update; and status of related research.
Staff Hosted Public Meeting on Draft Interim Staff Guidance Related to Subsequent License Renewal On July 16, 2020, the NRC staff held its 5th public meeting to discuss three draft interim staff guidance (ISG) documents (ADAMS Accession Nos. ML20156A330, ML20156A324, and ML20156A338), regarding proposed revisions to the electrical, structural, and mechanical portions of NUREG-2191, Generic Aging Lessons Learned for Subsequent License Renewal Report and NUREG-2192, Standard Review Plan for Review of Subsequent License Renewal Applications for Nuclear Power Plants. The purpose of the meeting was to assist stakeholders prepare public comments on the draft ISGs.
Staff Released a Report on Evaluation Techniques and Guidance for the Resolution of Source Terms Development for Advanced Reactors On July 17, 2020, the NRC staff publicly released a report titled, Technology-Inclusive Determination of Mechanistic Source Terms for Offsite Dose-Related Assessments for Advanced Nuclear Reactor Facilities. A link to the report has been posted on the NRC JULY 31, 2020 ENCLOSURE C
Advanced Reactor Webpage at: https://www.nrc.gov/reactors/new-reactors/advanced.html#advRxRef. The report fulfills a requirement in the Nuclear Energy Innovation and Modernization Act to provide evaluation techniques and guidance for the resolution of source terms development for advanced reactors. The report adheres to Implementation Action Plan Strategy 3, which is to develop guidance for a flexible non-LWR regulatory review process.
Staff Approved Licensing Requests for Regulatory Relief Related to the COVID-19 Public Health Emergency The NRC staff has reviewed and approved several licensing requests seeking temporary flexibilities to maintain the safe and secure operation of the U.S. nuclear fleet during the pandemic. A summary of approved licensing actions provided during this reporting period are summarized below. A complete list of licensing actions approved by the NRC in response to the COVID-19 public health emergency is available on the NRC public website at https://www.nrc.gov/about-nrc/covid-19/reactors/licensing-actions.html.
Licensing Request for Regulatory Relief Related to COVID-19 Braidwood Station, Units 1 and 2 (Exelon Generation Company, LLC)
Type Subject Incoming Request Decision Exemption Select Requirements of 10 CFR 6/15/2020 07/09/2020 Part 73, Appendix B, General Non-public ML20169A348 Criteria for Security Personnel (security-related)
Fermi Unit 2 (DTE Energy Company)
Type Subject Incoming Request Decision Exemption Select Requirements of 10 CFR 07/06/2020 07/14/2020 Part 26, Fitness for Duty ML20188A339 ML20192A180 Programs, Section 26.205, Work hours 07/11/2020 ML20193A003 JULY 31, 2020 ENCLOSURE C
Office of Nuclear Material Safety and Safeguards (NMSS)
Items of Interest Week Ending JULY 17, 2020 NMSS Staff Receive Performance Assessment for Review On July 10, 2020, the U.S. Nuclear Regulatory Commission (NRC), Office of Nuclear Material Safety and Safeguards (NMSS) staff acknowledged receipt of the U.S. Department of Energys (DOEs) 2020 Savannah River Site Saltstone Disposal Facility (SDF) Performance Assessment (PA) for technical review. The 2020 SDF PA replaces the 2009 SDF PA that led to the staffs issuance of the April 12, 2012, Type IV Letter of Concern for the SDF. The letter notified the DOE that the NRC staff did not have reasonable assurance that the performance objective for dose to an off-site member of the public required by Title 10 of the Code of Federal Regulation (10 CFR ) 61.41 would be met (Agencywide Documents Access and Management System (ADAMS) Accession No. ML120650576). The 2020 SDF PA and design changes DOE has implemented since the 2009 SDF PA represent a significant departure from the natural and engineered system that formed the basis for the 2012 letter. Therefore, the staff is administratively closing the 2012 Letter of Concern. The fundamental areas that led to the letter will be reviewed within the entire scope of the 2020 SDF PA and supporting documents.
San Onofre Nuclear Generating Station Reactor Pressure Vessel Arrives in Utah On July 14, 2020, the San Onofre Nuclear Generating Station (SONGS) Unit 1 Reactor Pressure Vessel (RPV) arrived safely at EnergySolutions' licensed disposal facility in Clive, Utah. The RPV left the SONGS site on May 25 and was transported via rail to Apex, Nevada on a 36-axle Schnabel train car that weighed 2.2 million pounds. On June 29, it was transferred to a special transport for the last leg of its journey via highway to Clive, Utah. The shipment was Class A low-level waste and a Category 1 radioactive material shipment compliant with 10 CFR part 37 requirements.
NMSS Staff Participate in California Coastal Commission Meeting On July 16, 2020, the NMSS staff participated in the California Coastal Commission (CCC)
SONGS Independent Spent Fuel Storage Installation (ISFSI) meeting to answer CCC questions regarding NRC spent fuel storage and transportation requirements. Eight groups and approximately 25 individuals provided a diversity of opinions on the SONGS UMAX cask Inspection and Maintenance Program (IMP), urging the CCC to either support or deny it. The IMP describes the UMAX cask inspection, monitoring, and maintenance techniques, as well as potential canister remediation measures. At this meeting the CCC approved the IMP, which was required as a condition of a CCC permit for the expansion of the SONGS ISFSI.
TN Americas LLC, Standardized NUHOMS Horizontal Modular Storage System; List of Approved Spent Fuel Storage Casks; Certificate of Compliance No. 1004, Renewed Amendment No. 16; Direct Final Rule; Correction; (RIN 3150-AK39; NRC-2019-0202)
On July 17, 2020, the NRC published a notice in the Federal Register (85 FR 43419) correcting a notice that was published in the Federal Register on June 30, 2020 (85 FR 39049), revising the TN Americas LLC, Standardized NUHOMS Horizontal Modular Storage System listing within the List of approved spent fuel storage casks to include Renewed Amendment No. 16 to JULY 31, 2020 ENCLOSURE D
Certificate of Compliance No. 1004. This action is necessary to provide ADAMS accession numbers in the Availability of Documents table listing that were inadvertently omitted. The correction is effective on September 14, 2020, if no significant adverse comments are received by July 30, 2020.
Holtec International HI-STORM Flood/Wind Multipurpose Canister Storage System, Certificate of Compliance No. 1032, Amendment No. 4: Direct Final Rule; Confirmation of Effective Date; Part 72 of Title 10 of the Code of Federal Regulations (10 CFR);
[Regulatory Identifier Number (RIN) 3150-AK41; NRC-2019-0250]
On July 17, 2020, the NRC published a notice confirming the effective date of July 14, 2020 (85 FR 43419), for the direct final rule that was published in the Federal Register on April 30, 2020 (85 FR 23904). The direct final rule amends the NRC's spent fuel storage regulations by revising the Holtec International HI-STORM Flood/Wind Multipurpose Canister Storage System listing within the List of approved spent fuel storage casks to include Amendment No. 4 to Certificate of Compliance No. 1032. The effective date of July 14, 2020, for the direct final rule published April 30, 2020, is confirmed.
JULY 31, 2020 ENCLOSURE D
Office of the Secretary (SECY)
Items of Interest Week Ending JULY 17, 2020 Document Released to Public Date of Subject Document Information Papers
- 1. SECY-20-0060 07/15/20 Weekly Information Report - Week Ending 07/03/2020 Federal Register Notices Issued
- 1. Emergency Preparedness for Small Modular Reactors and Other New Technologies, (NRC-2015-0225; 3150-AJ68)
JULY 31, 2020 ENCLOSURE E