ML21196A101

Notification of an NRC Fire Protection Team Inspection (Fpti) (NRC Inspection Report 05000280/2021011 and 05000281/2021011) and Request for Information (RFI)

ML21196A101
Person / Time
Site:	Surry
Issue date:	07/15/2021
From:	Scott Shaeffer NRC/RGN-II/DRS/EB2
To:	Lawrence D Dominion Energy Virginia
T Francis
References
IR 2021011
Download: ML21196A101 (6)

See also: IR 05000280/2021011

Text

UNITED STATES

NUCLEAR REGULATORY COMMISSION

REGION II

245 PEACHTREE CENTER AVENUE NE, SUITE 1200

ATLANTA, GEORGIA 30303-1257

July 15, 2021

Doug E. Lawrence

Site Vice President

Surry Power Station

Dominion Energy Virginia

5570 Hog Island Road

Surry, VA 23883-0315

SUBJECT: SURRY POWER STATION, UNITS 1 AND 2 - NOTIFICATION OF AN NRC

FIRE PROTECTION TEAM INSPECTION (FPTI) (NRC INSPECTION REPORT

05000280/2021011 and 05000281/2021011) AND REQUEST FOR

INFORMATION (RFI)

Dear Mr. Lawrence:

The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC),

Region II staff will conduct a fire protection team inspection (FPTI) at the Surry Power Station,

Units 1 and 2, in September and October 2021. The inspection team will be led by Mr. William

Monk, a Senior Reactor Inspector from the NRC Region II Office. The inspection team will be

comprised of four inspectors from the NRC Region II office. The inspection will be conducted in

accordance with Inspection Procedure 71111, Attachment 21N.05, Fire Protection Team

Inspection, the NRCs baseline fire protection inspection procedure.

On July 7, 2021, during e-mail and phone call exchanges between Maria S. Groshner of your

staff and Mr. Monk, our respective staffs confirmed arrangements for a two-week onsite

inspection. The schedule for the inspection is as follows:

• Week 1 of onsite inspection: September 20-24, 2021

• In-Office Review: September 27 - October 01, 2021

• Week 2 of onsite inspection: October 04-08, 2021

The team lead and senior reactor analyst (SRA) will work with your staff prior to the start of the

inspection to select the scope of structures, systems, and components for evaluation; identify

additional documents needed to support the inspection; and obtain unescorted plant access.

The enclosure to this letter provides an initial list of the documents the team will need for their

review. We request that your staff transmit copies of the documents listed in the enclosure to

the NRC Region II office for team use in preparation for the inspection. Please send this

information so that it will arrive in the NRC Region II office by the dates listed in the enclosure.

D. Lawrence 2

During the weeks leading up to the inspection, the team leader will discuss with your staff the

following inspection support administrative details: (1) office space size and location; (2)

specific documents requested to be made available to the team in their office spaces; (3)

arrangements for reactor site access (including radiation protection training, security, safety,

and fitness for duty requirements); and (4) the availability of knowledgeable plant staff and

licensing organization personnel to serve as points of contact during the inspection.

We request that during the on-site inspection weeks you ensure that copies of analyses,

evaluations, or documentation regarding the implementation and maintenance of the station fire

protection program, including the success path necessary to achieve and maintain the nuclear

safety performance criteria / safe shutdown, be readily accessible to the team for their review.

Of specific interest for the fire protection portion of the inspection are those documents which

establish that your fire protection program satisfies NRC regulatory requirements and conforms

to applicable NRC and industry fire protection guidance (i.e., fire protection compliance

assessment documents). Also, personnel should be available at the site during the inspection

who are knowledgeable regarding those plant systems required to achieve and maintain safe

and stable plant conditions, including the electrical aspects of the nuclear safety capability

assessment / safe shutdown, reactor plant fire protection systems and features, and the station

fire protection program and its implementation.

This letter does not contain new or amended information collection requirements subject to the

Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Existing information collection

requirements were approved by the Office of Management and Budget under control

number 3150-0011. The NRC may not conduct or sponsor, and a person is not required to

respond to, a request for information or an information collection requirement unless the

requesting document displays a currently valid Office of Management and Budget control

number.

This letter and its enclosure will be made available for public inspection and copying at

http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in

accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.

Your cooperation and support during this inspection will be appreciated. If you have questions

concerning this inspection or the inspection teams information or logistical needs, please

contact William Monk, the team lead inspector, in the Region II office at (404) 997-4579 or

william.monk@nrc.gov, or me at (404) 997-4521.

Sincerely,

/RA/

Scott Shaeffer, Chief

Engineering Branch 2

Division of Reactor Safety

Docket No. 50-280 & 50-281

License No. DPR-32 & DPR-37

Enclosures:

Fire Protection Team Inspection

Document Request

cc w/enclosure: via ListServ

D. Lawrence 3

SUBJECT: SURRY POWER STATION, UNITS 1 AND 2 - NOTIFICATION OF AN NRC

FIRE PROTECTION TEAM INSPECTION (FPTI) (NRC INSPECTION REPORT

05000280/2021011 and 05000281/2021011) AND REQUEST FOR

INFORMATION (RFI) DATED JULY 15, 2021

Adams Accession :ML ML21196A101______________________________

OFFICIAL RECORD COPY

Fire Protection Team Inspection (FPTI) Document Request

The initial request for information (i.e., first RFI) concentrates on providing the inspection team

with the general information necessary to select appropriate samples to develop a site-specific

inspection plan. The first RFIs requested information is specified below in items A.1 thru A.22,

and is requested to be provided by August 20, 2021, or sooner, to facilitate the selection of the

specific items that will be reviewed during the onsite inspection weeks.

Electronic format is the preferred format, except where specifically noted. If electronic files are

made available via a secure document management service, then the remote document access

must allow inspectors to download, save, and print the documents in the NRCs regional office.

If a secure document management service is utilized, it is recommended that a separate folder

be used corresponding to each item listed below. Documents should be identified by both

document number and noun name. Electronic media on compact disc or paper records (hard

copy) are also acceptable.

The inspection team will examine the returned documentation from the first RFI and

identify/select specific inspection samples to provide a more focused follow-up request to

develop the second RFI. The inspection team will submit the specific selected samples to your

staff by September 3, 2021. We request that the additional information provided from the

second RFI be made available by September 10, 2021.

This document request is based on typical documents that a generic plant might have. As such,

this generic document request is not meant to imply that any specific plant is required to have all

the listed documents. It is recognized that some documents listed below may not be available

for your plant. In addition, the document titles listed below are based on typical industry

document names; your plant-specific document titles may vary.

Enclosure

A. DESIGN AND LICENSING BASIS DOCUMENTS

A.1 The current version of the Fire Protection Program/Plan and Fire Hazards

Analysis (FHA).

A.2 Post-fire safe shutdown analysis (or Post-fire Nuclear Safety Capability,

Systems, and Separation Analysis Fire if NFPA 805 licensing basis) and the

supporting calculations that demonstrate acceptable plant response.

A.3 (If NFPA 805 licensing basis) Fire PRA Summary Report, and list of Fire PRA

calculations.

(If Appendix R licensing basis) Portions of the plants individual plant

examination for external events (IPEEE) report addressing fire events. Also,

include the results of any post-IPEEE reviews and listings of actions taken / plant

modifications conducted in response to IPEEE information that relate to fire risk.

A.4 (If NFPA 805 licensing basis) NFPA 805 Transition Report, developed in

accordance with NEI 04-02.

(If Appendix R licensing basis) Licensing basis documents for fire protection

(safety evaluation reports, pertinent sections of the final safety analysis report,

exemptions, deviations, letters to/from the NRC regarding fire protection/fire safe

shutdown, etc.).

A.5 List of post-fire safe shutdown systems and components (i.e., safe shutdown

equipment list).

A.6 List of fire areas with automatic fire suppression systems and types (i.e. wet pipe,

CO2, Halon, etc.).

A.7 List, with descriptions, of design change packages performed since the last fire

protection team inspection associated with fire protection or post-fire safe

shutdown systems.

A.8 List, with descriptions, of any fire protection program changes and evaluations

(not limited to Generic Letter 86-10 evaluations) performed since the last fire

protection team inspection.

A.9 Fire Protection System(s) Design Basis Document. 10 CFR 50 Appendix R

Report.

A.10 List of applicable NFPA codes and standards and issuance dates (i.e., codes of

record).

A.11 A list or document identifying any deviations from the NFPA codes of record.

A.12 Facility Operating License (FOL) - Fire Protection Requirements.

A.13 Technical Specifications (electronic format only).

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A.14 Updated Final Safety Analysis Report (UFSAR) (electronic format only).

o Section 9.10, Fire Protection Page 9.10-1

o Section 18.2.7, Fire Protection Program Page 18-10

A.15 COPY of NRC Safety Evaluation Reports that form the licensing basis for:

o Fire Protection Program; and

o Post-fire Nuclear Safety Capability / Safe Shutdown.

A.16 COPY of NRC approved exemptions for plant fire protection and post-fire nuclear

safety capability features.

A.17 COPY of exemption requests submitted but not yet approved for plant fire

protection and post-fire nuclear safety capability features.

A.18 LIST of nuclear safety capability design changes completed in the last three years

(including their associated 10 CFR 50.59 and NFPA 805 plant change

evaluations).

A.19 List of the top 25 highest fire CDF scenarios for each unit.

A.20 List of the top 25 highest fire LERF scenarios for each unit.

A.21 From your most recent PRA including external events and fires:

a. Two risk rankings of components from your site-specific PRA: one sorted by

Risk Achievement Worth (RAW), and the other sorted by Birnbaum

Importance

b. A list of the top 500 cut-sets

A.22 Copy of the Quality Assurance Program Manual (including specific fire protection

QA manual, if applicable).

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