ML24261B978: Difference between revisions

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4800 Concord Road
4800 Concord Road
York, SC  29745
York, SC  29745
SUBJECT:  CATAWBA NUCLEAR STATION UNITS 1 AND 2 - NOTIFICATION OF AN NRC  
SUBJECT:   
CATAWBA NUCLEAR STATION UNITS 1 AND 2 - NOTIFICATION OF AN NRC  
FIRE PROTECTION TEAM INSPECTION (FPTI) (NRC INSPECTION REPORT  
FIRE PROTECTION TEAM INSPECTION (FPTI) (NRC INSPECTION REPORT  
05000413/2024010, 05000414/2024010) AND REQUEST FOR INFORMATION  
05000413/2024010, 05000414/2024010) AND REQUEST FOR INFORMATION  
Line 38: Line 39:
Mr. Montgomery, our respective staffs confirmed arrangements for a two-week onsite  
Mr. Montgomery, our respective staffs confirmed arrangements for a two-week onsite  
inspection.  The schedule for the inspection is as follows:
inspection.  The schedule for the inspection is as follows:
*Week 1 of onsite inspection: November 18-22, 2024
*
*Week 2 of onsite inspection:  December 9-13, 2024
Week 1 of onsite inspection: November 18-22, 2024
*
Week 2 of onsite inspection:  December 9-13, 2024
The team lead and senior reactor analyst will work with your staff prior to the start of the  
The team lead and senior reactor analyst will work with your staff prior to the start of the  
inspection to select the scope of structures, systems, and components for evaluation; identify  
inspection to select the scope of structures, systems, and components for evaluation; identify  
Line 46: Line 49:
review.  We request that your staff transmit copies of the documents listed in the enclosure to  
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  
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.September 19, 2024
information so that it will arrive in the NRC Region II office by the dates listed in the enclosure.
N. Flippin 2
September 19, 2024
 
N. Flippin
2
During the weeks leading up to the inspection, the team leader will discuss with your staff the  
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)  
following inspection support administrative details:  (1) office space size and location; (2)  
Line 93: Line 99:
  on 09/19/24
  on 09/19/24


N. Flippin                                                     3
N. Flippin
 
3
SUBJECT:     CATAWBA NUCLEAR STATION UNITS 1 AND 2 - NOTIFICATION OF AN NRC
SUBJECT:
            FIRE PROTECTION TEAM INSPECTION (FPTI) (NRC INSPECTION REPORT
CATAWBA NUCLEAR STATION UNITS 1 AND 2 - NOTIFICATION OF AN NRC  
            05000413/2024010, 05000414/2024010) AND REQUEST FOR INFORMATION
FIRE PROTECTION TEAM INSPECTION (FPTI) (NRC INSPECTION REPORT  
            (RFI) DATED SEPTEMBER 19, 2024
05000413/2024010, 05000414/2024010) AND REQUEST FOR INFORMATION  
 
(RFI) DATED SEPTEMBER 19, 2024
 
DISTRIBUTION:
DISTRIBUTION:
P. Carman, RII
P. Carman, RII
Line 109: Line 114:
R2EICS
R2EICS
RIDSNRRDIRS
RIDSNRRDIRS
ADAMS Accession :  ML24261B978
ADAMS Accession :  ML24261B978
SUNSI Rev Compl.     Yes  No   ADAMS       Yes  No   Reviewer Initials
SUNSI Rev Compl.
Publicly Avail       Yes  No   Sensitive   Yes  No   Sens. Type Initials
Yes  No
RII:DRS/EB2         RII:DRS/EB2
ADAMS
J. Montgomery       D. Bacon
Yes  No
9/18/2024           9/19/2024
Reviewer Initials
                              OFFICIAL RECORD COPY
Publicly Avail
                    Fire Protection Team Inspection Document Request
Yes  No
Sensitive
Yes  No
Sens. Type Initials
RII:DRS/EB2
RII:DRS/EB2
J. Montgomery
D. Bacon
9/18/2024
9/19/2024
OFFICIAL RECORD COPY


 
Fire Protection Team Inspection Document Request
The initial request for information (i.e., first RFI) concentrates on providing the inspection team
Enclosure
with the general information necessary to select appropriate samples to develop a site-specific
The initial request for information (i.e., first RFI) concentrates on providing the inspection team  
inspection plan.  The first RFIs requested information is specified below in items A.1 thru A.21,
with the general information necessary to select appropriate samples to develop a site-specific  
and is requested to be provided by Friday, October 18, or sooner, to facilitate the selection of
inspection plan.  The first RFIs requested information is specified below in items A.1 thru A.21,  
and is requested to be provided by Friday, October 18, or sooner, to facilitate the selection of  
the specific items that will be reviewed during the onsite inspection weeks.
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  
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  
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.
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  
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  
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  
document number and noun name.  Electronic media on compact disc or paper records (hard
copy) are also acceptable.
copy) are also acceptable.
 
The inspection team will examine the returned documentation from the first RFI and  
The inspection team will examine the returned documentation from the first RFI and
identify/select specific samples to provide a more focused follow-up request to develop the  
identify/select specific 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  
second RFI.  The inspection team will submit the specific selected samples to your staff by
Friday, October 25, 2024.  We request that the additional information provided from the second  
Friday, October 25, 2024.  We request that the additional information provided from the second
RFI be made available by Friday, November 8, 2024.
RFI be made available by Friday, November 8, 2024.
 
This document request is based on typical documents that a generic plant might have.  As such,  
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  
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  
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  
for your plant.  In addition, the document titles listed below are based on typical industry
document names; your plant-specific document titles may vary.
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 and Fire Hazards Analysis
A.2
Post-fire Nuclear Safety Capability, Systems, and Separation Analysis (NSCA),
and the supporting calculations that demonstrate acceptable plant response.
A.3
Fire PRA Summary Report, and list of Fire PRA calculations
A.4
NFPA 805 Transition Report, developed in accordance with NEI 04-02
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
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.
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.
A.13
Technical Specifications (electronic format only).
A.14
Updated Final Safety Analysis Report (electronic format only).
A.15
Copy of NRC Safety Evaluation Reports that form the licensing basis for:
*
Fire Protection Program
*
Post-fire Nuclear Safety Capability
A.16
Copy of exemption requests submitted but not yet approved for plant fire
protection and post-fire nuclear safety capability features.


 
3
 
A.17
 
List of post-fire safe shutdown-related design changes completed in the last three  
 
years (including their associated 10 CFR 50.59 and/or fire protection program  
 
change evaluations).
 
A.18
 
List of the top 25 highest fire CDF scenarios for each unit
 
A.19
 
List of the top 25 highest fire LERF scenarios for each unit
 
A.20
 
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.21
 
Copy of the Quality Assurance Program Manual (including specific fire protection  
 
QA manual, if applicable)
 
 
 
 
 
 
 
 
 
 
 
                                                                                      Enclosure
A.        DESIGN AND LICENSING BASIS DOCUMENTS
 
      A.1      The current version of the Fire Protection Program and Fire Hazards Analysis
 
      A.2      Post-fire Nuclear Safety Capability, Systems, and Separation Analysis (NSCA),
              and the supporting calculations that demonstrate acceptable plant response.
 
      A.3     Fire PRA Summary Report, and list of Fire PRA calculations
 
      A.4      NFPA 805 Transition Report, developed in accordance with NEI 04-02
 
      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
 
      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.
 
      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.
 
      A.13    Technical Specifications (electronic format only).
 
      A.14    Updated Final Safety Analysis Report (electronic format only).
 
      A.15    Copy of NRC Safety Evaluation Reports that form the licensing basis for:
 
                  *  Fire Protection Program
                  *  Post-fire Nuclear Safety Capability
 
      A.16    Copy of exemption requests submitted but not yet approved for plant fire
              protection and post-fire nuclear safety capability features.
 
 
 
 
 
 
 
 
 
                                              2
A.17    List of post-fire safe shutdown-related design changes completed in the last three
      years (including their associated 10 CFR 50.59 and/or fire protection program
      change evaluations).
 
A.18   List of the top 25 highest fire CDF scenarios for each unit
 
A.19   List of the top 25 highest fire LERF scenarios for each unit
 
A.20   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.21   Copy of the Quality Assurance Program Manual (including specific fire protection
      QA manual, if applicable)
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
                                        3
}}
}}

Latest revision as of 10:43, 24 November 2024

Notification of an NRC Fire Protection Team Inspection NRC Inspection Report 05000413-2024010, 05000414-2024010 and Request for Information
ML24261B978
Person / Time
Site: Catawba  Duke Energy icon.png
Issue date: 09/19/2024
From: Daniel Bacon
Division of Reactor Safety II
To: Flippin N
Duke Energy Carolinas
References
IR 2024010
Download: ML24261B978 (6)


See also: IR 05000413/2024010

Text

Nicole Flippin

Site Vice President

Duke Energy Carolinas, LLC

Catawba Nuclear Station

4800 Concord Road

York, SC 29745

SUBJECT:

CATAWBA NUCLEAR STATION UNITS 1 AND 2 - NOTIFICATION OF AN NRC

FIRE PROTECTION TEAM INSPECTION (FPTI) (NRC INSPECTION REPORT

05000413/2024010, 05000414/2024010) AND REQUEST FOR INFORMATION

(RFI)

Dear Nicole Flippin:

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 at the Catawba Nuclear Station

Units 1 & 2 in November and December of 2024. The inspection team will be led by Jonathan

Montgomery, 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, the NRCs baseline fire protection inspection procedure.

On September 6, 2024, in an e-mail exchange between Sherry Andrews of your staff and

Mr. Montgomery, our respective staffs confirmed arrangements for a two-week onsite

inspection. The schedule for the inspection is as follows:

Week 1 of onsite inspection: November 18-22, 2024

Week 2 of onsite inspection: December 9-13, 2024

The team lead and senior reactor analyst 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 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.

September 19, 2024

N. Flippin

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 onsite 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.

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 Jonathan Montgomery, the team lead inspector, in the Region II office at (404) 997-

4880 or jonathan.montgomery@nrc.gov, or me at (404) 997-4518.

Sincerely,

Daniel Bacon, Chief

Engineering Branch 2

Division of Reactor Safety

Docket No. 50-413, 50-414

License No. NPF-35, NPF-52

Enclosures:

Fire Protection Team Inspection

Document Request

cc w/enclosure: via ListServ

Signed by Bacon, Daniel

on 09/19/24

N. Flippin

3

SUBJECT:

CATAWBA NUCLEAR STATION UNITS 1 AND 2 - NOTIFICATION OF AN NRC

FIRE PROTECTION TEAM INSPECTION (FPTI) (NRC INSPECTION REPORT

05000413/2024010, 05000414/2024010) AND REQUEST FOR INFORMATION

(RFI) DATED SEPTEMBER 19, 2024

DISTRIBUTION:

P. Carman, RII

D. Rivard, RII

A. Wang, RII

D. Jackson, RII

J. Seat, RII

R2EICS

RIDSNRRDIRS

ADAMS Accession : ML24261B978

SUNSI Rev Compl.

Yes No

ADAMS

Yes No

Reviewer Initials

Publicly Avail

Yes No

Sensitive

Yes No

Sens. Type Initials

RII:DRS/EB2

RII:DRS/EB2

J. Montgomery

D. Bacon

9/18/2024

9/19/2024

OFFICIAL RECORD COPY

Fire Protection Team Inspection Document Request

Enclosure

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.21,

and is requested to be provided by Friday, October 18, 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 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

Friday, October 25, 2024. We request that the additional information provided from the second

RFI be made available by Friday, November 8, 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 and Fire Hazards Analysis

A.2

Post-fire Nuclear Safety Capability, Systems, and Separation Analysis (NSCA),

and the supporting calculations that demonstrate acceptable plant response.

A.3

Fire PRA Summary Report, and list of Fire PRA calculations

A.4

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

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

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.

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.

A.13

Technical Specifications (electronic format only).

A.14

Updated Final Safety Analysis Report (electronic format only).

A.15

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

Fire Protection Program

Post-fire Nuclear Safety Capability

A.16

Copy of exemption requests submitted but not yet approved for plant fire

protection and post-fire nuclear safety capability features.

3

A.17

List of post-fire safe shutdown-related design changes completed in the last three

years (including their associated 10 CFR 50.59 and/or fire protection program

change evaluations).

A.18

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

A.19

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

A.20

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.21

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

QA manual, if applicable)