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Category:Inspection Plan
MONTHYEARIR 05000390/20250102024-11-0404 November 2024 Notification of an NRC (FPTI) (NRC Inspection Report 05000390/2025010 0500039/ 2025010) (RFI) IR 05000390/20230062024-02-28028 February 2024 Annual Assessment Letter for Watts Bar Nuclear Plant Units 1 and 2 - Report 05000390/2023006 and 05000391/2023006 IR 05000390/20230052023-08-30030 August 2023 Updated Inspection Plan for Watts Bar Nuclear Plant, Units 1 and 2 - Report 05000390/2023005 and 05000391/2023005 ML23067A2372023-03-0808 March 2023 WB_2023-02_RP_inspection_doc_request IR 05000390/20220062023-03-0101 March 2023 Annual Assessment Letter for Watts Bar Nuclear Plant, Units 1 and 2 - Report 05000390/2022006 and 05000391/2022006 ML22327A1902022-11-28028 November 2022 Information Request for the Cyber-Security Baseline Security Inspection, Notification to Perform Inspection 05000390 2023403; 05000391 2023403 ML22250A4852022-09-0707 September 2022 Requalification Program Inspection IR 05000390/20220052022-08-31031 August 2022 Updated Inspection Plan for Watts Bar Nuclear Plant, Units 1 and 2 - Report 05000390/2022005 and 05000391/2022005 - Final IR 05000390/20210062022-03-0202 March 2022 Annual Assessment Letter for Watts Bar Nuclear Plant, Units 1 and 2 (Report No. 05000390/2021006 and 05000391/2021006) ML22018A0292022-01-18018 January 2022 Region 2 RFI - 2022 Program Inspections ML21267A1392021-09-23023 September 2021 Document Request for Upcoming RP Inspection at Watts Bar IR 05000390/20200062021-03-0303 March 2021 Annual Assessment Letter for Watts Bar Nuclear Plant, Units 1 and 2 - Report 05000390/2020006 and 05000391/2020006 ML20338A3202020-12-0303 December 2020 Notification of an NRC Fire Protection Team Inspection (NRC Inspection Report 05000390/2021011 and 05000391/2021011) and Request for Information ML20268B8672020-09-24024 September 2020 Document Request for Watts Bar Nuclear Plant Radiation Protection Inspection Inspection Report 2020-04 ML20253A1782020-09-0909 September 2020 Emergency Preparedness Program Inspection Request for Information IR 05000390/20200052020-08-31031 August 2020 Assessment Followup Letter and Updated Inspection Plan for Watts Bar Nuclear Plant, Units 1 and 2 - Report 05000390/2020005 and 05000391/2020005 ML20266G4592020-08-14014 August 2020 Notification of Inspection and Request for Information IR 05000390/20190062020-03-0303 March 2020 Annual Assessment Letter for Watts Bar Nuclear Plant Units 1 and 2 - NRC Report 05000390/2019006 and 05000391/2019006 ML20028D4882019-12-0202 December 2019 Notification of Inspection and Request for Information IR 05000390/20180062019-03-0404 March 2019 Annual Assessment Letter for Watts Bar Nuclear Plant, Units 1 and 2 - Report 05000390/2018006 and 05000391/2018006 ML19063B8992019-02-28028 February 2019 ISI Sgisi RFI 2019002 Combined ML18282A4462018-10-0909 October 2018 Emergency Preparedness Program Inspection Request for Information ML18215A1362018-08-0202 August 2018 Radiation Safety Baseline Inspection RFI 2018003 Public ML18191B2472018-07-10010 July 2018 Notification of Conduct of a Triennial Fire Protection Baseline Inspection - U.S. Nuclear Regulatory Commission Inspection Report 05000390/2018011 and 05000391/2018011 ML18187A0142018-07-0303 July 2018 RP Inspection Document Request - August 2018 ML18059A1502018-02-28028 February 2018 EOC Assessment Letter ML17271A0052017-09-21021 September 2017 Notification of Inspection and Request for Information ML17142A1862017-05-19019 May 2017 Emergency Preparedness Inspection and Request for Information Dated: May 19, 2017 IR 05000390/20160062017-03-0101 March 2017 Annual Assessment Letter for Watts Bar Nuclear Plant, NRC Inspection Report 05000390/2016006 and 05000391/2016006 ML17059C9572017-02-23023 February 2017 Notification of Inspection and Request for Information IR 05000391/20166112016-08-31031 August 2016 Mid-Cycle Assessment Letter - Watts Bar Nuclear Plant Unit 2 (NRC Inspection Report 05000391/2016611) IR 05000390/20160052016-08-31031 August 2016 Mid Cycle Assessment Letter for Watts Barr Nuclear Plant Unit 1, NRC Inspection Report 05000390/2016005 ML16062A2862016-03-0202 March 2016 Annual Assessment Letter IR 05000391/20166072016-03-0202 March 2016 End-Of-Cycle Assessment Letter - Watts Bar, Unit 2 (NRC Inspection Report 05000391/2016607) IR 05000391/20156062015-09-0101 September 2015 Mid-Cycle Assessment Letter - Watts Bar Nuclear Plant Unit 2 (NRC Inspection Report 05000391/2015606) IR 05000390/20150052015-09-0101 September 2015 Mid-Cycle Assessment Letter for the Watts Bar Nuclear Plant Unit 1, NRC Inspection Report 005000390/2015005 IR 05000390/20140012015-03-0404 March 2015 Annual Assessment Letter for Watts Bar Nuclear Plant Unit 1, NRC Inspection Report 05000390/2014001 IR 05000391/20156012015-02-27027 February 2015 End-Of-Cycle Assessment Letter - Watts Bar Nuclear Plant, Unit 2 (NRC Inspection Report 05000391/2015601) IR 05000391/20146062014-09-0303 September 2014 Mid-Cycle Assessment Letter Watts Bar Nuclear Plant, Unit 2 (NRC Inspection Report 05000391/2014606) ML14245A1232014-09-0202 September 2014 Mid-Cycle Letter ML14125A0452014-05-0505 May 2014 Plant, Notification of Inspection and Request for Information IR 05000390/20130012014-03-0404 March 2014 Annual Assessment Letter Watts Bar Nuclear Plant Unit 1 (Report 05000390/2013001) IR 05000391/20136062013-09-0303 September 2013 Mid-Cycle Assessment Letter - Watts Bar Nuclear Plant Unit 2 (NRC Inspection Report 05000391/2013606) ML13246A1912013-09-0303 September 2013 Mid Cycle Assessment Letter ML13123A2732013-05-0303 May 2013 Ti 2515-182 Phase 1 RFI - MSC IR 05000390/20136012013-03-0404 March 2013 Annual Assessment Letter for Watts Bar Nuclear Plant Unit 2 (IR 05000390-13-601) IR 05000390/20120012013-03-0404 March 2013 Annual Assessment Letter for Watts Bar Nuclear Plant Unit 1 (Report 05000390/2012001) ML12248A1022012-09-0404 September 2012 Mid Cycle Assessment Letter Watts Bar 2012 IR 05000390/20120062012-09-0404 September 2012 Mid Cycle Assessment Letter Watts Bar 2012 ML12065A3502012-03-0505 March 2012 Inspection/Activity Plan, 03/01/2012 - 06/30/2013 2024-02-28
[Table view] Category:Letter
MONTHYEARIR 05000390/20250102024-11-0404 November 2024 Notification of an NRC (FPTI) (NRC Inspection Report 05000390/2025010 0500039/ 2025010) (RFI) CNL-24-074, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-10-23023 October 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions IR 05000390/20243012024-10-17017 October 2024 Operator Licensing Examination Approval 05000390/2024301 and 05000391/2024301 ML24282B0412024-10-15015 October 2024 Request for Withholding Information from Public Disclosure for Sequoyah Nuclear Plant, Units 1 and 2 and Watts Bar Nuclear Plant, Units 1 and 2 ML24261C0062024-10-0404 October 2024 Correction to Amendment No. 134 to Facility Operating License No. NPF-90 and Amendment No. 38 to Facility Operating License No. NPF-96 ML24260A1682024-10-0404 October 2024 Regulatory Audit Summary Related to Request to Add and Revise Notes Related to Technical Specification Table 3.3.2-1, Function 5 ML24284A1072024-09-26026 September 2024 Affidavit for Request for Withholding Information from Public Disclosure for Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2 CNL-24-060, Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description2024-09-24024 September 2024 Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description CNL-24-047, Decommitment of Flood Mode Mitigation Improvement Systems2024-09-24024 September 2024 Decommitment of Flood Mode Mitigation Improvement Systems ML24262A0602024-09-23023 September 2024 Summary of August 19, 2024, Meeting with Tennessee Valley Authority Regarding a Proposed Supplement to the Tennessee Valley Authority Nuclear Quality Assurance Plan CNL-24-065, Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-09-18018 September 2024 Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions 05000390/LER-2024-002, Automatic Reactor Trip Due to Main Generator Protection Relay Actuation2024-09-0505 September 2024 Automatic Reactor Trip Due to Main Generator Protection Relay Actuation IR 05000390/20240052024-08-28028 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Watts Bar Nuclear Plant, Units 1 and 2 - Report 05000390-2024005 and 05000391-2024005 ML24218A1442024-08-27027 August 2024 Issuance of Amendment Nos. 169 and 75 Regarding Technical Specification Surveillance Requirement 3.9.5.1 to Reduce the Residual Heat Removal Flow Rate IR 05000390/20244022024-08-20020 August 2024 – Security Baseline Inspection Report 05000390-2024402 and 05000391/2024402 - Public CNL-24-061, Supplement to Application to Revise Function 5 of Technical Specification Table 3.3.2-1, ‘Engineered Safety Feature Actuation System Instrumentation,’ for the Sequoyah and Watts Bar (SQN-TS-23-02 and WBN-TS-23-08),2024-08-19019 August 2024 Supplement to Application to Revise Function 5 of Technical Specification Table 3.3.2-1, ‘Engineered Safety Feature Actuation System Instrumentation,’ for the Sequoyah and Watts Bar (SQN-TS-23-02 and WBN-TS-23-08), ML24219A0262024-08-12012 August 2024 Request for Withholding Information from Public Disclosure IR 05000390/20240022024-08-0707 August 2024 Integrated Inspection Report 05000390/2024002 and 05000391/2024002 Rev ML24204A2652024-07-25025 July 2024 Regulatory Audit Summary Related to Request to Revise Technical Specification Surveillance Requirement 3.9.5.1 to Reduce the Residual Heat Removal Flow Rate ML24199A0012024-07-22022 July 2024 Clarification and Correction to Exemption from Requirement of 10 CFR 37.11(c)(2) ML24172A1342024-07-15015 July 2024 Exemptions from 10 CFR 37.11(C)(2) (EPID L-2023-LLE-0024) - Letter ML24170A8002024-07-15015 July 2024 Issuance of Amendment Nos. 168 and 74 Regarding Revision to Technical Specification Table 1.1-1 for Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Bolts IR 05000390/20244402024-07-12012 July 2024 95001 Supplemental Inspection Supplemental Report 05000390-2024440 and 05000391-2024440 and Follow-Up Assessment Letter 05000391/LER-2024-003, Inoperability of Both Trains of Unit 2 Low Head Safety Injection2024-07-11011 July 2024 Inoperability of Both Trains of Unit 2 Low Head Safety Injection ML24131A0012024-07-0202 July 2024 Issuance of Amendment Nos. 167 and 73 Regarding Adoption of Technical Specification Task Force Traveler TSTF-427-A, Revision 2 CNL-24-052, Response to Request for Additional Information Regarding Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14)2024-06-27027 June 2024 Response to Request for Additional Information Regarding Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14) CNL-24-018, License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-276-A, Revision 2, Regarding TS 3.8.1 AC Sources – Operating to Clarify Requirements for Diesel Generator Testing (WBN-TS2024-06-25025 June 2024 License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-276-A, Revision 2, Regarding TS 3.8.1 AC Sources – Operating to Clarify Requirements for Diesel Generator Testing (WBN-TS ML24089A1152024-06-21021 June 2024 Transmittal Letter, Environmental Assessments and Findings of No Significant Impact Related to Exemption Requests from 10 CFR 37.11(c)(2) ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc ML24100A7642024-05-16016 May 2024 Issuance of Amendment No. 166 Regarding Revision to Technical Specification 3.8.2, AC Sources-Shutdown, to Remove Reference to C-S Diesel Generator (CNL-23-062) IR 05000390/20240012024-05-14014 May 2024 Integrated Inspection Report 05000390/2024001 and 05000391/2024001 CNL-24-040, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-05-0808 May 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions 05000391/LER-2024-002, Re Automatic Reactor Trip Due to Steam Generator 3 Level LO-LO2024-05-0606 May 2024 Re Automatic Reactor Trip Due to Steam Generator 3 Level LO-LO IR 05000391/20240072024-04-30030 April 2024 Assessment Follow-up Letter for Watts Bar Nuclear Plant, Unit 2 – Report 05000391/2024007 ML24120A1182024-04-29029 April 2024 – Notification of NRC Supplemental Inspection (95001) and Request for Information CNL-24-037, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 422024-04-22022 April 2024 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 42 ML24087A1912024-04-18018 April 2024 Exemption from Select Requirements of 10 CFR Part 73, Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting CNL-24-010, License Amendment Request to Recapture Low-Power Testing Time (WBN-TS-23-19)2024-04-17017 April 2024 License Amendment Request to Recapture Low-Power Testing Time (WBN-TS-23-19) CNL-24-024, Hydrologic Engineering Center River Analysis System Project Milestone Status Update2024-04-17017 April 2024 Hydrologic Engineering Center River Analysis System Project Milestone Status Update CNL-24-033, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-04-17017 April 2024 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML24072A0052024-04-15015 April 2024 Issuance of Amendment Nos. 165 and 72 Regarding Increase in the Maximum Number of Tritium Producing Burnable Absorber Rods and Supporting Changes, and Revision to the Updated Final Safety Analysis Report CNL-24-004, Application to Modify the Watts Bar Nuclear Plant, Unit 1 and Unit 2 Technical Specifications for Main Control Room Chiller Completion Time Extension (WBN-TS-23-13)2024-04-0404 April 2024 Application to Modify the Watts Bar Nuclear Plant, Unit 1 and Unit 2 Technical Specifications for Main Control Room Chiller Completion Time Extension (WBN-TS-23-13) IR 05000390/20244012024-04-0202 April 2024 – Security Baseline Inspection Report 05000390/2024401 and 05000391/2024401 - (Public) CNL-24-020, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Units 1 and 2, Request for Approval of Quality Assurance Program Description and Application to Revise the Technical Specifications Associated with QAPD Requirements2024-04-0101 April 2024 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Units 1 and 2, Request for Approval of Quality Assurance Program Description and Application to Revise the Technical Specifications Associated with QAPD Requirements CNL-24-007, Annual Insurance Status Report2024-03-27027 March 2024 Annual Insurance Status Report CNL-24-008, Guarantee of Payment of Deferred Premiums - 2023 Annual Report2024-03-27027 March 2024 Guarantee of Payment of Deferred Premiums - 2023 Annual Report 05000391/LER-2024-001, Automatic Reactor Trip Due to Main Generator Protection Relay Actuation2024-03-27027 March 2024 Automatic Reactor Trip Due to Main Generator Protection Relay Actuation CNL-24-025, Notice of Intent to Pursue License Renewal for Watts Bar Nuclear Plant, Unit 1 - Submittal Schedule2024-03-25025 March 2024 Notice of Intent to Pursue License Renewal for Watts Bar Nuclear Plant, Unit 1 - Submittal Schedule ML24081A0262024-03-21021 March 2024 Emergency Plan Implementing Procedure Revisions ML24079A0312024-03-19019 March 2024 Wb 2024-301, Corporate Notification Letter (210-day Ltr) 2024-09-05
[Table view] |
Text
SUBJECT:
WATTS BAR NUCLEAR PLANT UNITS 1 & 2 - NOTIFICATION OF AN NRC FIRE PROTECTION TEAM INSPECTION (FPTI) (NRC INSPECTION REPORT 05000390/2025010, 05000391/2025010) AND REQUEST FOR INFORMATION (RFI)
Dear Delson C. Erb:
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 Watts Bar Nuclear Plant Units 1 & 2 in February of 2025. The inspection team will be led by Philipp Braaten, 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 October 29, 2024, in an e-mail exchange between Charles Andrew Barker of your staff and Philipp Braaten, our respective staffs confirmed arrangements for a two-week onsite inspection.
The schedule for the inspection is as follows:
- Week 1 of onsite inspection: February 10-14, 2025
- Week 2 of onsite inspection: February 24-28, 2025 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.November 4, 2024 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, 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 safe shutdown analysis, 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 Philipp Braaten, the team lead inspector, in the Region II office at (404) 997-4651 or philipp.braaten@nrc.gov or me at (404) 997-4518.
Sincerely, Daniel Bacon, Chief Engineering Branch 2 Division of Operating Reactor Safety Docket No. 50-390, 50-391 License No. NPF-90, NPF-96 Enclosures:
Fire Protection Team Inspection Document Request cc w/enclosure: via ListServ Signed by Bacon, Daniel on 11/04/24 SUBJECT: WATTS BAR NUCLEAR PLANT UNITS 1 & 2 - NOTIFICATION OF AN NRC FIRE PROTECTION TEAM INSPECTION (FPTI) (NRC INSPECTION REPORT 05000390/2025010, 05000391/2025010) AND REQUEST FOR INFORMATION (RFI) DATED NOVEMBER 4, 2024
DISTRIBUTION:
RidsNrrPMWattsBar Resource
ADAMS ACCESSION NUMBER :ML24305A177 X Non-Sensitive X Publicly Available X SUNSI Review Sensitive Non-Publicly Available
OFFICE RII/DORS RII/DORS
NAME P. Braaten D. Bacon DATE 10/31/24 11/04/24 Fire Protection Team Inspection 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.21, and is requested to be provided by Friday, December 13, 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, December 20, 2024. We request that the additional information provided from the second RFI be made available by Friday, January 31, 2025.
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 and Fire Hazards Analysis
A.2 Post-fire Safe Shutdown Analysis, and the supporting calculations that demonstrate acceptable plant response.
A.3 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 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
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 approved exemptions for plant fire protection and post-fire nuclear safety capability features.
A.16 COPY of exemption requests submitted but not yet approved for plant fire protection and post-fire nuclear safety capability features.
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