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| {{#Wiki_filter:UNITED STATES | | {{#Wiki_filter: |
| NUCLEAR REGULATORY COMMISSION
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| REGION II
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| 245 PEACHTREE CENTER AVENUE NE, SUITE 1200
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| ATLANTA, GEORGIA 30303-1257
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| July 15, 2021
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| Doug E. Lawrence
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| Site Vice President
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| Surry Power Station
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| Dominion Energy Virginia
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| 5570 Hog Island Road
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| Surry, VA 23883-0315
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| SUBJECT: SURRY POWER STATION, UNITS 1 AND 2 - NOTIFICATION OF AN NRC
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| FIRE PROTECTION TEAM INSPECTION (FPTI) (NRC INSPECTION REPORT
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| 05000280/2021011 and 05000281/2021011) AND REQUEST FOR
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| INFORMATION (RFI)
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| Dear Mr. Lawrence:
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| The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC),
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| Region II staff will conduct a fire protection team inspection (FPTI) at the Surry Power Station,
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| Units 1 and 2, in September and October 2021. The inspection team will be led by Mr. William
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| Monk, a Senior Reactor Inspector from the NRC Region II Office. The inspection team will be
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| comprised of four inspectors from the NRC Region II office. The inspection will be conducted in
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| accordance with Inspection Procedure 71111, Attachment 21N.05, Fire Protection Team
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| Inspection, the NRCs baseline fire protection inspection procedure.
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| On July 7, 2021, during e-mail and phone call exchanges between Maria S. Groshner of your
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| staff and Mr. Monk, our respective staffs confirmed arrangements for a two-week onsite
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| inspection. The schedule for the inspection is as follows:
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| * Week 1 of onsite inspection: September 20-24, 2021
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| * In-Office Review: September 27 - October 01, 2021
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| * Week 2 of onsite inspection: October 04-08, 2021
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| The team lead and senior reactor analyst (SRA) will work with your staff prior to the start of the
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| inspection to select the scope of structures, systems, and components for evaluation; identify
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| additional documents needed to support the inspection; and obtain unescorted plant access.
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| The enclosure to this letter provides an initial list of the documents the team will need for their
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| review. We request that your staff transmit copies of the documents listed in the enclosure to
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| the NRC Region II office for team use in preparation for the inspection. Please send this
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| information so that it will arrive in the NRC Region II office by the dates listed in the enclosure.
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| D. Lawrence 2
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| During the weeks leading up to the inspection, the team leader will discuss with your staff the
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| following inspection support administrative details: (1) office space size and location; (2)
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| specific documents requested to be made available to the team in their office spaces; (3)
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| arrangements for reactor site access (including radiation protection training, security, safety,
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| and fitness for duty requirements); and (4) the availability of knowledgeable plant staff and
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| licensing organization personnel to serve as points of contact during the inspection.
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| We request that during the on-site inspection weeks you ensure that copies of analyses,
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| evaluations, or documentation regarding the implementation and maintenance of the station fire
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| protection program, including the success path necessary to achieve and maintain the nuclear
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| safety performance criteria / safe shutdown, be readily accessible to the team for their review.
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| Of specific interest for the fire protection portion of the inspection are those documents which
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| establish that your fire protection program satisfies NRC regulatory requirements and conforms
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| to applicable NRC and industry fire protection guidance (i.e., fire protection compliance
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| assessment documents). Also, personnel should be available at the site during the inspection
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| who are knowledgeable regarding those plant systems required to achieve and maintain safe
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| and stable plant conditions, including the electrical aspects of the nuclear safety capability
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| assessment / safe shutdown, reactor plant fire protection systems and features, and the station
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| fire protection program and its implementation.
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| This letter does not contain new or amended information collection requirements subject to the
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| Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Existing information collection
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| requirements were approved by the Office of Management and Budget under control
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| number 3150-0011. The NRC may not conduct or sponsor, and a person is not required to
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| respond to, a request for information or an information collection requirement unless the
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| requesting document displays a currently valid Office of Management and Budget control
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| number.
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| This letter and its enclosure will be made available for public inspection and copying at
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| http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in
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| accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.
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| Your cooperation and support during this inspection will be appreciated. If you have questions
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| concerning this inspection or the inspection teams information or logistical needs, please
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| contact William Monk, the team lead inspector, in the Region II office at (404) 997-4579 or
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| william.monk@nrc.gov, or me at (404) 997-4521.
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| Sincerely,
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| /RA/
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| Scott Shaeffer, Chief
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| Engineering Branch 2
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| Division of Reactor Safety
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| Docket No. 50-280 & 50-281
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| License No. DPR-32 & DPR-37
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| Enclosures:
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| Fire Protection Team Inspection
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| Document Request
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| cc w/enclosure: via ListServ
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| D. Lawrence 3
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| SUBJECT: SURRY POWER STATION, UNITS 1 AND 2 - NOTIFICATION OF AN NRC
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| FIRE PROTECTION TEAM INSPECTION (FPTI) (NRC INSPECTION REPORT
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| 05000280/2021011 and 05000281/2021011) AND REQUEST FOR
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| INFORMATION (RFI) DATED JULY 15, 2021
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| Adams Accession :ML ML21196A101______________________________
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| OFFICIAL RECORD COPY
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| Fire Protection Team Inspection (FPTI) Document Request
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| The initial request for information (i.e., first RFI) concentrates on providing the inspection team
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| with the general information necessary to select appropriate samples to develop a site-specific
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| inspection plan. The first RFIs requested information is specified below in items A.1 thru A.22,
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| and is requested to be provided by August 20, 2021, or sooner, to facilitate the selection of the
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| specific items that will be reviewed during the onsite inspection weeks.
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| Electronic format is the preferred format, except where specifically noted. If electronic files are
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| made available via a secure document management service, then the remote document access
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| must allow inspectors to download, save, and print the documents in the NRCs regional office.
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| If a secure document management service is utilized, it is recommended that a separate folder
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| be used corresponding to each item listed below. Documents should be identified by both
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| document number and noun name. Electronic media on compact disc or paper records (hard
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| copy) are also acceptable.
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| The inspection team will examine the returned documentation from the first RFI and
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| identify/select specific inspection samples to provide a more focused follow-up request to
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| develop the second RFI. The inspection team will submit the specific selected samples to your
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| staff by September 3, 2021. We request that the additional information provided from the
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| second RFI be made available by September 10, 2021.
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| This document request is based on typical documents that a generic plant might have. As such,
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| this generic document request is not meant to imply that any specific plant is required to have all
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| the listed documents. It is recognized that some documents listed below may not be available
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| for your plant. In addition, the document titles listed below are based on typical industry
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| document names; your plant-specific document titles may vary.
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| Enclosure
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| A. DESIGN AND LICENSING BASIS DOCUMENTS
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| A.1 The current version of the Fire Protection Program/Plan and Fire Hazards
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| Analysis (FHA).
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| A.2 Post-fire safe shutdown analysis (or Post-fire Nuclear Safety Capability,
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| Systems, and Separation Analysis Fire if NFPA 805 licensing basis) and the
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| supporting calculations that demonstrate acceptable plant response.
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| A.3 (If NFPA 805 licensing basis) Fire PRA Summary Report, and list of Fire PRA
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| calculations.
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| (If Appendix R licensing basis) Portions of the plants individual plant
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| examination for external events (IPEEE) report addressing fire events. Also,
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| include the results of any post-IPEEE reviews and listings of actions taken / plant
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| modifications conducted in response to IPEEE information that relate to fire risk.
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| A.4 (If NFPA 805 licensing basis) NFPA 805 Transition Report, developed in
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| accordance with NEI 04-02.
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| (If Appendix R licensing basis) Licensing basis documents for fire protection
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| (safety evaluation reports, pertinent sections of the final safety analysis report,
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| exemptions, deviations, letters to/from the NRC regarding fire protection/fire safe
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| shutdown, etc.).
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| A.5 List of post-fire safe shutdown systems and components (i.e., safe shutdown
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| equipment list).
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| A.6 List of fire areas with automatic fire suppression systems and types (i.e. wet pipe,
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| CO2, Halon, etc.).
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| A.7 List, with descriptions, of design change packages performed since the last fire
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| protection team inspection associated with fire protection or post-fire safe
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| shutdown systems.
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| A.8 List, with descriptions, of any fire protection program changes and evaluations
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| (not limited to Generic Letter 86-10 evaluations) performed since the last fire
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| protection team inspection.
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| A.9 Fire Protection System(s) Design Basis Document. 10 CFR 50 Appendix R
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| Report.
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| A.10 List of applicable NFPA codes and standards and issuance dates (i.e., codes of
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| record).
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| A.11 A list or document identifying any deviations from the NFPA codes of record.
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| A.12 Facility Operating License (FOL) - Fire Protection Requirements.
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| A.13 Technical Specifications (electronic format only).
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| 2
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| A.14 Updated Final Safety Analysis Report (UFSAR) (electronic format only).
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| o Section 9.10, Fire Protection Page 9.10-1
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| o Section 18.2.7, Fire Protection Program Page 18-10
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| A.15 COPY of NRC Safety Evaluation Reports that form the licensing basis for:
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| o Fire Protection Program; and
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| o Post-fire Nuclear Safety Capability / Safe Shutdown.
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| A.16 COPY of NRC approved exemptions for plant fire protection and post-fire nuclear
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| safety capability features.
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| A.17 COPY of exemption requests submitted but not yet approved for plant fire
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| protection and post-fire nuclear safety capability features.
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| A.18 LIST of nuclear safety capability design changes completed in the last three years
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| (including their associated 10 CFR 50.59 and NFPA 805 plant change
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| evaluations).
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| A.19 List of the top 25 highest fire CDF scenarios for each unit.
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| A.20 List of the top 25 highest fire LERF scenarios for each unit.
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| A.21 From your most recent PRA including external events and fires:
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| a. Two risk rankings of components from your site-specific PRA: one sorted by
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| Risk Achievement Worth (RAW), and the other sorted by Birnbaum
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| Importance
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| b. A list of the top 500 cut-sets
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| A.22 Copy of the Quality Assurance Program Manual (including specific fire protection
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| QA manual, if applicable).
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| 3
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| }} | | }} |
