ML24052A405

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Notification of an NRC Fire Protection Team Inspection - NRC Inspection Report 05000338/2024010- 05000339/2024010- RFI
ML24052A405
Person / Time
Site: North Anna  Dominion icon.png
Issue date: 02/22/2024
From: William Monk
Division of Reactor Safety II
To: Hilbert L
Virginia Electric & Power Co (VEPCO)
References
IR 2024010
Download: ML24052A405 (7)


See also: IR 05000338/2024010

Text

Lisa Hilbert

Site Vice President

North Anna Power Station

1022 Haley Drive

Mineral, VA 23117

SUBJECT:

NORTH ANNA POWER STATION, UNITS 1 AND 2 - NOTIFICATION OF AN

NRC FIRE PROTECTION TEAM INSPECTION (FPTI) (NRC INSPECTION

REPORT 05000338/2024010 AND 05000339/2024010) AND REQUEST FOR

INFORMATION (RFI)

Dear Lisa Hilbert:

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 North Anna Power

Station, Units 1 and 2, in May 2024. 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 three 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 (FPTI), the NRCs baseline fire protection inspection procedure.

On February 20, 2024, during e-mail and phone call exchanges between Mrs. Charlene

Chotalal 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: 29 APR - 03 MAY 2024

In-Office Review:

06 MAY - 10 MAY 2024

Week 2 of onsite inspection: 13 MAY - 17 MAY 2024

The team lead (TL) 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 (SSCs) for evaluation

(the inspection samples); 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.

February 22, 2024

L. Hilbert

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 (FPP), 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.

L. Hilbert

3

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) 997-4518.

Sincerely,

Dan Bacon, Branch Chief

Engineering Branch 2

Division of Reactor Safety

Docket Nos. 50-338 & 50-339

License Nos. NPF-4 & NPF-7

Enclosure:

Fire Protection Team Inspection

Document Request

cc w/enclosure: via ListServ

Signed by Bacon, Daniel

on 02/22/24

ML24052A405

X

SUNSI Review

X

Non-Sensitive

Sensitive

X

Publicly Available

Non-Publicly Available

OFFICE

RII/DRS

RII/DRS

NAME

W. Monk

D. Bacon

DATE

2/21/2024

2/22/2024

Enclosure

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 March 15, 2024, 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 (i.e., Certrec), then the remote

document access must allow inspectors to download, save, and print the documents in the

NRCs regional office or site Residents 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 March 25, 2024. We request that the additional information provided from the second

RFI be made available by April 22, 2024.

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.

2

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

Fire PRA Summary Report, and list of Fire PRA calculations, if NFPA 805 licensing

basis.

A.4

NFPA 805 Transition Report, developed in accordance with NEI 04-02. Safety

Evaluation Reports if Appendix R licensing basis.

A.5

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

equipment list (SSEL)).

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 GL 86-10 evaluations) performed since the last fire protection team

inspection.

A.9

Fire Protection System(s) Design Basis Document. NFPA 805 Report.

A.10

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

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 Only.

A.13

Sites Technical Specifications (electronic format only).

A.14

Updated Final Safety Analysis Report (UFSAR) Fire Protection (electronic format

only).

o

Section 9.10, Fire Protection

o

Section 18.2.7, Fire Protection Program

A.15

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

o

Fire Protection Program and 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.

3

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:

o Two risk rankings of components from your site-specific PRA: one sorted

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

Importance

o A list of the top 500 cut-sets

A.22

Copy of the Quality Assurance (QA) Program Manual (including specific fire

protection QA manual, if applicable).