ML22343A117

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Notification of an NRC Protection South Texas Project - Baseline Inspection (NRC Inspection Report) 05000498/2023010 and 05000499/2023010) and Request for Information
ML22343A117
Person / Time
Site: South Texas  STP Nuclear Operating Company icon.png
Issue date: 12/12/2022
From: James Drake
NRC/RGN-IV/DORS/EB2
To: Gerry Powell
South Texas
Drake J
References
IR 2023010
Download: ML22343A117 (11)


See also: IR 05000498/2023010

Text

December 12, 2022

Mr. G. T. Powell

President and CEO

STP Nuclear Operating Company

P.O. Box 289

Wadsworth, TX 77483

SUBJECT: SOUTH TEXAS PROJECT - NOTIFICATION OF AN NRC FIRE PROTECTION

BASELINE INSPECTION (NRC INSPECTION REPORT) 05000498/2023010 AND

05000499/2023010 AND REQUEST FOR INFORMATION

Dear Mr. Powell:

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

Region IV staff will conduct a triennial fire protection baseline inspection at South Texas Project

in January 2023. The inspection team will be comprised of three reactor inspectors from the

NRC Region IV office and one reactor inspector from the NRC Region I 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.

The schedule for the inspection is as follows:

Information gathering visit:

January 9 - 12, 2023

Onsite inspection:

January 30 - February 3, 2023, and February 13 - 17, 2023

The purpose of the information gathering visit is to obtain information and documentation

needed to support the inspection and to become familiar with the fire protection program, fire

protection features, post-fire safe shutdown capabilities and plant layout.

The team lead will review the initial set of documents requested in the enclosure to select the

scope of structures, systems, and components for evaluation, and identify additional

documents needed to support the inspection. The enclosure to this letter provides an initial list

of the documents the team will need for review. We request that your staff transmit copies of

the documents listed in the enclosure to the NRC Region IV office for team use in preparation

for the inspection. Please send this information so that it will arrive in the NRC Region IV

office by the dates listed in the enclosure.

During the inspection planning meeting(s), the team leader will discuss 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

G. Powell

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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, 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, reactor plant fire protection systems and features, and the station fire

protection program and its implementation.

PAPERWORK REDUCTION ACT STATEMENT

This letter contains mandatory information collections that are subject to the Paperwork

Reduction Act of 1995 (44 U.S.C. 3501 et seq.). The Office of Management and Budget (OMB)

approved these information collections (approval number 3150-0011). Send comments

regarding this information collection to the Information Services Branch, Office of the Chief

Information Officer, Mail Stop: T6 A10M, U.S. Nuclear Regulatory Commission, Washington,

DC 20555-0001, or by e-mail to Infocollects.Resource@nrc.gov, and to the Desk Officer,

Office of Information and Regulatory Affairs, NEOB-10202, (3150-0011) Office of

Management and Budget, Washington, DC 20503.

PUBLIC PROTECTION NOTIFICATION

The NRC may not conduct nor 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 OMB 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

G. Powell

3

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

me, the team lead inspector, in the Region IV office at (817) 200-1558,

(817) 773-6712 (m), or James.Drake@nrc.gov.

Sincerely,

Jim Drake

Senior Reactor Inspector Engineering Branch 2

Division of Reactor Safety

Docket Nos: 05000498 and 05000499

License Nos: NPF-76 and NPF-80

Enclosure:

Triennial Fire Protection Inspection Document Request

cc w/ encl: Distribution via LISTSERV

Signed by Drake, James

on 12/12/22

ML22343A117

SUNSI Review

By: JFD

ADAMS:

Yes

No

Sensitive

Non-Sensitive

Non-Publicly Available

Publicly Available

Keyword

NRC-002

OFFICE

SHP:DRSS/MLB

NAME

J. Drake

SIGNATURE

/RA/

DATE

12/12/22

Enclosure

Triennial Fire Protection Inspection Document Request

The documents and information requested below should generally be made available to

the inspection team prior to the inspection. 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.

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

folder be used corresponding to each item listed below. It is recommended that multiple

documents within each folder be individually entered and combined into a ZIP file which

is uploaded into the same folder. Documents should be identified by both document

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

are also acceptable.

Where C-size paper drawings are requested, please prepare two copies. Retain one copy

on site for the Teams use during the inspection weeks. Send one copy to the team leader

at the NRC Region IV office.

To allow review before the on-site information gathering visit, the documents requested in

items

A.1 thru A.13 should be made available to the team no later than December 30, 2022.

Based on review of the documentation, the team leader will identify the scope for the

inspection prior to the end of the on-site information gathering visit or in-office review of the

information obtained.

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.

To allow review before the on-site inspection weeks, all requested documents should be

made available to the team no later than January 16, 2023.

A.

DESIGN AND LICENSING BASIS DOCUMENTS

A.1

Post-fire Nuclear Safety Capability, Systems, and Separation Analysis

A.2

Fire Hazards Analysis and/or NFPA 805 Design Basis Document

A.3

Fire Probabilistic Risk Assessment (PRA) Summary Document or full

PRA Document

A.4

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

A.5

Fire Risk Evaluations (i.e., NFPA 805 Section 2.4.3)

A.6

Plant Change Evaluations (i.e., NFPA 805 Section 2.4.4)

2

A.7

Facility Operating License.

A.8

Technical Specifications (electronic format only).

A.9

Updated Final Safety Analysis Report (electronic format only).

A.10

A list of the ten most risk significant plant systems for core damage

frequency from the fire protection probabilistic risk assessment.

A.11

A list of the ten most risk significant plant systems for large early

release frequency from the fire protection probabilistic risk

assessment.

A.12

Plant layout drawings which identify: (electronic format and C-size

paper drawings)

Plant fire area boundaries

Combustible control zone drawings

Areas protected by automatic fire suppression and detection

A.13

For recovery actions, provide the following:

Manual Action Feasibility Study

Operator Time Critical Action Program

Timelines for time-critical manual actions

Timeline validations

B.

GENERAL PLANT DESIGN DOCUMENTS

B.1

Piping and instrumentation diagrams (P&IDs) and legend list for

components used to achieve and maintain post-fire safe shutdown for the

sample systems or fire areas selected (electronic format and C-size paper

drawings).

B.2

Piping and instrumentation diagrams and legend list for fire protection

systems, including the fire water supply; water suppression sprinklers;

and deluge, gaseous suppression systems for the sample systems or fire

areas selected (electronic format and C-size paper drawings).

B.3

AC and DC electrical system single line diagrams, from off-site power

down to the highest safety-related bus level (typically 4kV, EDG bus)

(electronic format and C-size paper drawings).

B.4

Single line diagrams for motor control centers (MCCs) that supply post-

fire nuclear safety component loads for the sample systems or fire areas

selected (electronic format and C-size paper drawings).

B.5

Equipment location drawings which identify the physical plant locations of

post- fire safety shutdown equipment for the sample systems or fire area

selected (electronic format and C-size paper drawings

3

C.

CLASSIC FIRE PROTECTION

C.1

Copy of fire protection program implementing procedures (e.g.,

administrative controls, surveillance testing, and fire brigade).

C.2

List, with descriptions, of calculations and engineering analyses,

studies, or evaluations for the fire protection system, including the fire

water system.

C.3

Last two completed surveillances of fire protection features for the

sample systems or features within the fire areas selected (detection,

suppression, damper inspections, damper tests, penetration inspections,

barrier inspections, etc.).

C.4

List, with descriptions, of routine tests, surveillances, and

preventive maintenance on fire pumps, including pump

controllers and batteries.

C.5

Last two completed annual fire pump pressure and flow tests with a

complete copy of the test procedure.

C.6

Last two completed monthly and/or quarterly fire pump tests with a

complete copy of the test procedure.

C.7

Last two completed fire water system flow tests and flushes with a complete

copy of the test procedure.

C.8

For Fire Brigade Drills, provide the following:

Last five fire brigade drill critiques

Last drill critique for a drill with off-site fire department support

Last unannounced drill critique

Last back-shift drill critique

Dates, shifts, and locations of unannounced drills for last three years

Summary of any unsatisfactory drill performance items for last three years

Last unannounced drill critique by a qualified individual independent

of the licensees staff

C.9

For fire brigade equipment provide the following:

Procedure for inventory and inspection

Most recent inspection and inventory results

4

C.10

Fire Brigade Qualifications, including self-contained breathing apparatus

(SCBA), and training lesson plans.

C.11

Copy of the evaluation or analysis of the effects of fire suppression

activities on the ability to achieve the nuclear safety performance criteria

for the sample systems or fire areas selected demonstrating:

The automatic or manually actuation of a suppression system, due to a

fire in a single location, will not indirectly cause damage to the success

path

The inadvertent actuation or rupture of a suppression system

will not indirectly cause damage to the success path

Adequate drainage for areas protected by water suppression systems

The hydrostatic rating of any floor penetration seals installed within

the fire areas that are credited with keeping water from leaking into fire

areas below

C.12

Pre-fire plans for all fire areas.

C.13

Impairment Log (at start of inspection) for fire protection features that are

out of service.

C.14

List of penetration seal work, re-work, or installation activities, in the last

three years.

C.15

List of fire wrap work, re-work, or installation activities, in the last three years.

C.16

Fire protection system health reports for the two most recent quarters.

C.17

Fire protection program health reports for the two most recent quarters.

C.18

Licensee evaluations of industry operating experience concerning fire

protection issues completed in the last three years.

C.19

List of fire event analysis reports for the last three years.

C.20

Fire protection program requirements (e.g., limiting conditions for

operation, surveillance test requirements) covered by technical

specifications, the technical requirements manual, the updated final safety

analysis report, procedures or similar documents.

C.21

Fire Protection System(s) Design Basis Document.

C.22

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

codes of record).

C.23

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

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C.24

Organization charts of site personnel down to the level of fire protection

staff personnel.

C.25

A contact list of key site personnel who will be supporting this inspection,

giving the office location and phone number.

C.26

The team would like to observe an unannounced fire brigade drill in the

plant, if possible, during the week of July 11, 2022. Please put us in

contact with the appropriate personnel for planning fire brigade drills during

the onsite information gathering trip.

C.27

The team would like to perform a walkdown of the sample fire protection

systems and/or fire areas with fire protection personnel in the plant during

the week of June 27, 2022. Please put us in contact with the appropriate

personnel for planning the walkdowns during the onsite information

gathering trip.

D.

ELECTRICAL

D.1

Electrical system health reports for the two most recent quarters.

D.2

Surveillance procedures and last surveillance demonstrating

operability of components required for alternative shutdown.

E.

OPERATIONS

E.1

The team would like to perform a walkthrough of a sample of post-fire

safe shutdown procedures with qualified operators in the plant during

the week of June 27, 2022. Please put us in contact with the

appropriate personnel for planning the walkthroughs during the onsite

information gathering trip.

E.2

List, with descriptions, of licensed operator Job Performance Measures

(JPMs) for operator actions required to achieve and maintain post-fire

safe shutdown.

E.3

List, with descriptions, of non-licensed operator training associated with

non- licensed operator actions to achieve and maintain post-fire

nuclear safe shutdown (including JPMs, in-field training walkdowns,

simulations, or initial qualification).

E.4

Lesson plans for post-fire safe shutdown training for licensed and non-

licensed operators.

E.5

Thermal hydraulic calculation or analysis that determines the time

requirements for time-critical manual operator actions.

E.6

Operating procedures to achieve and maintain post-fire safe shutdown

from the control room and requiring a control room evacuation.

6

E.7

For safe shutdown equipment and tools, provide the following:

Procedure for inventory and inspection

Most recent inspection and inventory results

.

E.8

List, with descriptions, of procedures that implement cold shutdown repairs

E.9

For cold shutdown repairs, if required, provide the following:

Procedure for inventory and inspection (i.e., needed tools, material, etc.)

Most recent inspection and inventory results

F.

ADMINISTRATIVE CONTROL, OVERSIGHT, AND CORRECTIVE

ACTION PROGRAMS

F.1

Copies of procedures that control the configuration of the fire protection

program, features, and post-fire safe shutdown methodology and system

design. Also, copies of procedures that govern the implementation of plant

modifications, maintenance, and special operations and their impact on fire

protection.

F.2

List of open and closed condition reports for the fire protection systems

for the last three years.

F.3

List of open and closed condition reports associated with the post-fire

safe shutdown analysis for the last three years.

F.4

List of open and closed condition reports associated with operator

actions to achieve and maintain post-fire safe shutdown for the last

three years.

F.5

List of open and closed condition reports associated with the fire

protection program including plant change evaluations, post-fire

operating procedures and/or training, timeline evaluations for

operator actions, and supporting engineering evaluations, analysis, or

calculations for the last three years.

F.6

List of open and closed condition reports for emergency lighting units for

the last three years.

F.7

Self-assessments, peer assessments, and audits of fire protection

activities for the last three years.

F.8

Self-assessments, peer assessments, and audits of post-fire nuclear

safety capability methodology for the last three years.

F.9

Provide administrative procedures that control temporary modifications,

permanent plant changes, design changes, procedure changes, ageing

management changes, equivalency evaluations, suitability analyses,

calculations, commercial grade dedication, safety-security interface, and

repairs.

7

F.10

Provide procedures that control the following: combustible controls, hot

work, monitoring, compensatory measures, and workarounds.

F.11

Last five hot work permits (at power).

F.12

Last five transient combustible permits (at power).

G.

AGING MANAGEMENT PROGRAM

G.1

Copies of the aging management programs applicable to fire protection

including but not limited to the following:

Fire Protection

Fire Water System

Aboveground Metallic Tanks

Buried and Underground Piping and Tanks

G.2

Copies of procedures, work orders, preventive maintenance tasks, or

other documents which implement the commitments made as part of

the license extension related to fire protection.

G.3

List of aging management activities related to fire protection performed to date.