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Category:Letter
MONTHYEARML24032A0202024-01-31031 January 2024 NPDES Biocide/Corrosion Treatment Plan Annual Report, Cy 2023 ML23319A2452024-01-29029 January 2024 Issuance of Amendment Nos. 366 and 360; 164 and 71 Regarding the Adoption of TSTF-567, Revision 1, Add Containment Sump TS to Address GSI-191 Issues CNL-24-017, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions2024-01-17017 January 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions ML24018A0142024-01-17017 January 2024 Engine Systems, Inc., Report No. 10CFR21-0137, Rev. 1, 56913-EN 56913 ML24011A3182024-01-11011 January 2024 Submittal of Discharge Monitoring Report (Dmr), October 2023 ML24011A3172024-01-11011 January 2024 Submittal of Discharge Monitoring Report (Dmr), September 2023 ML24011A3202024-01-11011 January 2024 Submittal of Discharge Monitoring Report (Dmr), December 2023 ML24011A3162024-01-11011 January 2024 Submittal of Discharge Monitoring Report (Dmr), August 2023 ML24011A3192024-01-11011 January 2024 Submittal of Discharge Monitoring Report (Dmr), November 2023 IR 05000327/20234422024-01-11011 January 2024 95001 Supplemental Inspection Report 05000327/2023442 and 05000328/2023442 and Follow-Up Assessment Letter ML24010A2132024-01-10010 January 2024 CFR 21.21 Final Report Regarding Siemens Medium Voltage Circuit Breakers ML24018A0952024-01-0404 January 2024 Engine Systems, Inc., 10CFR21 Reporting of Defects and Non-Compliance Report No. 10CFR21-0137, Rev. 0 ML24004A0332024-01-0303 January 2024 Interim Report of a Deviation or Failure to Comply Crompton Instruments Type 077 Ammeter ML24004A0402024-01-0303 January 2024 Response to NRCs November 8, 2023, Request for Additional Information - Related to Independent Spent Fuel Storage Installation CNL-23-068, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-21021 December 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation CNL-23-036, Application to Revise Function 5 of Technical Specification Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation, for the Sequoyah Nuclear Plant and Watts Bar Nuclear Plant (SQN-TS-23-02 and WBN-TS-23-08)2023-12-18018 December 2023 Application to Revise Function 5 of Technical Specification Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation, for the Sequoyah Nuclear Plant and Watts Bar Nuclear Plant (SQN-TS-23-02 and WBN-TS-23-08) ML23346A1222023-12-12012 December 2023 Annual Non-Radiological Environmental Operating Report - 2023 IR 05000327/20234202023-11-28028 November 2023 Security Baseline Inspection Report 05000327/2023420 and 05000328/2023420 CNL-23-067, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-11-27027 November 2023 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML23324A4362023-11-0909 November 2023 Exam Corporate Notification Letter Aka 210-day Letter ML23307A0822023-11-0808 November 2023 Request for Additional Information August 4, 2022, Exemption Request for Deviating from the Conditions of Certificate of Compliance No. 1032, Amendment No. 3, Related to Sequoyah Nuclear Plant Independent Spent Fuel Storage Installation IR 05000327/20230032023-11-0303 November 2023 Integrated Inspection Report 05000327/2023003 and 05000328/2023003 ML23306A1592023-11-0202 November 2023 Enforcement Action EA-22-129 Inspection Readiness Notification ML23292A0792023-10-19019 October 2023 Tennessee Valley Authority - Emergency Plan Implementing Procedure Revision, Includes EPIP-5, Revision 58, General Emergency IR 05000327/20230112023-10-16016 October 2023 Triennial Fire Protection Inspection Report 05000327/2023011 and 05000328/2023011 ML23285A0882023-10-12012 October 2023 Submittal of Sequoyah Nuclear Plant, Units 1 and 2, Submittal of Updated Final Safety Analysis Report Amendment 31 ML23284A4252023-10-11011 October 2023 10 CFR 50.59 and 10 CFR 72.48 Changes, Tests, and Experiments Summary Report; Commitment Summary Report; and Update to the Fire Protection Report ML23283A2792023-10-10010 October 2023 Revisions to the Sequoyah Nuclear Plant Units 1 and 2 Technical Requirements Manual ML23279A0612023-10-0505 October 2023 Paragon Energy Solutions LLC, Part 21 Final Report Re Potential Defect with Eaton Jd and Hjd Series Molded Case Circuit Breakers (Mccbs) ML23277A0462023-10-0404 October 2023 Revisions to the Sequoyah Nuclear Plant Units 1 and 2 Technical Specification Bases ML23275A0272023-09-29029 September 2023 Submittal of Discharge Monitoring Report (DMR) Quality Assurance Study 43 Final Report 2023 ML23271A1662023-09-28028 September 2023 Registration of Spent Fuel Storage Cask Pursuant to 10 CFR 72.212(b)(2) CNL-23-059, Supplement to Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-2023-09-20020 September 2023 Supplement to Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03 CNL-23-061, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision2023-09-20020 September 2023 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision IR 05000327/20234032023-09-14014 September 2023 Cyber Security Inspection Report 05000327/2023403 and 05000328/2023403 (Cover Letter) ML23257A0062023-09-14014 September 2023 Enforcement Action EA-22-129 Inspection Postponement Request ML23254A2192023-09-11011 September 2023 Emergency Plan Implementing Procedure Revisions ML23254A0652023-09-0707 September 2023 Registration of Spent Fuel Storage Cask Pursuant to 10 CFR 72.212(b)(2) CNL-23-057, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC-EPIP-1, Revision 76 and CECC-EPIP-9, Revision 642023-09-0505 September 2023 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC-EPIP-1, Revision 76 and CECC-EPIP-9, Revision 64 IR 05000327/20230052023-08-29029 August 2023 Updated Inspection Plan for Sequoyah Nuclear Plant, Units 1 and 2 - Report 05000327/2023005 and 05000328/2023005 ML23233A0122023-08-17017 August 2023 Unit 1 Cycle 25 Refueling Outage - 90-Day Inservice Inspection Summary Report - Supplement ML23233A0142023-08-15015 August 2023 Discharge Monitoring Report (Dmr), July 2023 ML23215A1212023-08-0303 August 2023 301 Exam Administrative Items (2B) Normal Release ML23215A1572023-08-0303 August 2023 Enforcement Action EA-22-129 Inspection Readiness Notification CNL-23-028, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03 and WBN-TS-23-06)2023-08-0202 August 2023 Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03 and WBN-TS-23-06) ML23192A4472023-07-31031 July 2023 Staff Assessment of Updated Seismic Hazards at TVA Sites Following the NRC Process for the Ongoing Assessment of Natural Hazards Information 2024-01-04
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML23307A0832023-11-0808 November 2023 Enclosure - Request for Additional Information HDI-Sequoyah NDE Exemption Request 10-30-2023 ML23307A0822023-11-0808 November 2023 Request for Additional Information August 4, 2022, Exemption Request for Deviating from the Conditions of Certificate of Compliance No. 1032, Amendment No. 3, Related to Sequoyah Nuclear Plant Independent Spent Fuel Storage Installation ML23062A5952023-02-27027 February 2023 Staff follow-up Questions to Tva'S 12/19/2022 Response of the Staff'S Rsi Regarding 08/04/2022 SQN Exemption Request ML23062A5942023-02-27027 February 2023 Enclosure - NRC SQN Exemption Rsi Response Staff Follow Up Questions ML22343A0692022-12-0808 December 2022 NRR E-mail Capture - Request for Additional Information - Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Revise Technical Specification 3.4.12 (L-2022-LLA-0103) ML22257A0622022-09-14014 September 2022 Requalification Program Inspection - Sequoyah Nuclear Plant ML22255A0842022-09-0909 September 2022 Document Request for Sequoyah Nuclear Plant - Radiation Protection Inspection - Inspection Report 2022-04 ML22227A0272022-08-11011 August 2022 NRR E-mail Capture - Request for Additional Information Related to Alternative Requests RP-11 for Sequoyah Nuclear Plant, Units 1 and 2, and IST-RR-9 for Watts Bar Nuclear Plant, Units 1 and 2 ML22214A1582022-08-0202 August 2022 NRR E-mail Capture - Request for Additional Information for Sequoyah Units 1 and 2 License Amendment Request for Fire and Seismic PRA Modification to 10 CFR 50.69 (L-2022-LLA-0033) ML22151A0102022-05-27027 May 2022 NRR E-mail Capture - Revised Request for Additional Information Re Sequoyah Nuclear Plant Alternative Request RV-02 ML22151A0092022-05-26026 May 2022 NRR E-mail Capture - Request for Additional Information Re Sequoyah Nuclear Plant Alternative Request RV-02 ML22146A3322022-05-26026 May 2022 NRR E-mail Capture - Request for Additional Information Related to Sequoyah Nuclear Plant'S LAR to Adopt TSTF-505 ML22144A1002022-05-12012 May 2022 NRR E-mail Capture - Request for Additional Information Related to Tva'S Request to Revised the TVA Plants' Radiological Emergency Plans ML21237A4952021-08-25025 August 2021 Document Request for Sequoyah Nuclear Plant - Radiation Protection Inspection - Inspection Report 2021-04 ML21160A0352021-06-0303 June 2021 Document Request for Sequoyah Nuclear Plant - Radiation Protection Inspection - Inspection Report 2021-03 ML21095A0482021-04-0505 April 2021 NRR E-mail Capture - Sequoyah Nuclear Plant, Units 1 and 2 - Request for Additional Information Regarding Request to Transition to Westinghouse Fuel ML21092A0972021-04-0202 April 2021 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML20259A4782020-09-15015 September 2020 Emergency Preparedness Program Inspection Request for Information ML20261H4172020-09-14014 September 2020 NRR E-mail Capture - Sequoyah Nuclear Plant, Units 1 and 2 - Request for Additional Information Regarding Hydrologic UFSAR Update ML20261H4162020-09-0202 September 2020 NRR E-mail Capture - Draft Request for Additional Information - Sequoyah Nuclear Plant, Units 1 and 2, Request to Revise UFSAR Hydrologic Analysis ML20189A2112020-07-0101 July 2020 Request for Additional Information Regarding Hydrologic UFSAR Update ML20106F1042020-04-14014 April 2020 Request for Additional Information Regarding the Hydrologic Analysis LAR ML20161A3902020-04-0909 April 2020 Request for Supporting Information for the Sequoyah SPRA Audit Review - Follow-up to Plant Response Question 5 ML20098D8612020-04-0707 April 2020 Notification of an NRC Fire Protection Team Inspection (FPTI) (NRC Inspection Report 05000327/2020012 and 05000328/2020012) and Request for Information) ML20036E2842020-02-0505 February 2020 20200123 - Sequoyah Radiation Safety Inspection Document Request Letter ML19323D7562019-11-18018 November 2019 Nrc'S Request for Additional Information - Exigent Amendment ML19235A0992019-08-22022 August 2019 Emergency Preparedness Program Inspection Request for Information ML19162A2462019-06-11011 June 2019 RP Inspection Document Request 2019-03 ML19149A6222019-05-29029 May 2019 NRR E-mail Capture - Request for Additional Information - Sequoyah Nuclear Plant, Units 1 and 2, Request for Alternative to 18-ISI-1 EPID: L-2019-LLR-0006 ML19148A7912019-05-28028 May 2019 NRR E-mail Capture - Sequoyah Nuclear Plant and Watts Bar Nuclear Plant - Final Request for Additional Information Related to Request for Alternative to OM Code Requirements ML19015A4192019-01-15015 January 2019 NRR E-mail Capture - RAI - Sequoyah Nuclear Plant, Units 1 and 2, LAR to Adopt 10 CFR50.69 Risk-informed SSC ML18344A0752018-12-10010 December 2018 NRR E-mail Capture - Request for Additional Information - Sequoyah 1 and 2, Request to Modify Essential Raw Cooling Water Motor Control Center Breakers and to Revise Updated Final Analysis Report (SQN-TS-17-04) ML18296A0022018-10-22022 October 2018 NRR E-mail Capture - Additional Information Needs - Sequoyah Units 1 and 2, Request to Modify Essential Raw Cooling Water Motor Control Center Breakers Revise Updated Final Analysis Report (SQN-TS-17-04) ML18283B0592018-10-10010 October 2018 NRR E-mail Capture - Additional Information Needs Identified During Audit - Sequoyah 1 and 2, Request to Modify Essential Raw Cooling Water Motor Control Center Breakers Revise Updated Final Analysis Report (SQN-TS-17-04) ML18283A6232018-09-25025 September 2018 04 RP Inspection Document Request ML18233A1942018-08-21021 August 2018 NRR E-mail Capture - Additional Information Needs Identified - Sequoyah 1 and 2, Request to Modify Essential Raw Cooling Water Motor Control Center Breakers and to Revise Updated Final Analysis Report (SQN-TS-17-04) ML18138A1102018-05-17017 May 2018 Enclosurequest for Additional Information (Letter to E. D. Schrull Request for Additional Information Regarding Tennessee Valley Authority'S Decommissioning Funding Plan Update for Browns Ferry and Sequoyah Isfsis) ML18057A6372018-02-23023 February 2018 NRR E-mail Capture - Request for Additional Information Related to TVA Fleet Topical Report TVA-NPG-AWA16 - EPIC: L-2016-TOP-0011) ML17191A2062017-07-0606 July 2017 NRR E-mail Capture - Sequoyah Nuclear Station, Unit 1 & 2 - Request for Additional Information Related to LAR for Technical Specification 3.8.1.17 Note Modification (CAC Nos. MF9398 and MF9399) ML17150A0792017-05-23023 May 2017 NRR E-mail Capture - Request for Additional Information Related to TVA Fleet LAR for EAL Change to Adopt NEI-99-01 Rev.6 (CAC Nos. MF9054 - MF9060) ML17112A0402017-04-20020 April 2017 NRR E-mail Capture - Sequoyah Nuclear Station, Unit 1 & 2 - Request for Additional Information Related to LAR for Technical Specification 3.8.1, AC SOURCES-OPERATING ML17004A0612017-01-0404 January 2017 Notification of NRC Triennial Fire Protection Inspection (Team)(Report 05000327/2017007 and 05000328/2017007) ML15194A3882015-07-13013 July 2015 Request for Additional Information Related to LAR to Revise Ice Condenser Ice Mas Tech Spec ML15175A2912015-06-24024 June 2015 E-mail Re. Request for Additional Information RR RP-07 ML15159B1642015-06-22022 June 2015 Requests for Additional Information for the Review of the Sequoyah Nuclear Plant, Units 1 and 2, License Renewal Application-Set 25 (TAC Nos. MF0481 and MF0482) ML15050A0962015-02-19019 February 2015 E-mail Re. Request for Additional Information Related to LAR to Ice Condendser Inc Mass Tech Spec ML15042A4702015-02-11011 February 2015 E-mail Re. Request for Additional Information Related to License Amendment Request to Revise Technical Specification on Ultimate Heat Sink ML14318A8052014-11-12012 November 2014 Requalification Program Inspection - Sequoyah Nuclear Plant ML14254A2042014-09-22022 September 2014 Requests for Additional Information for the Review of the Sequoyah Nuclear Plant, Units 1 and 2, License Renewal Application - Set 22 (TAC Nos. MF0481 and MF0482) ML14220A2132014-08-0808 August 2014 E-mail Re. Request for Additional Information Regarding Voluntary Risk Initiative National Fire Protection Association Standard 805 2023-02-27
[Table view] |
See also: IR 05000327/2020012
Text
UNITED STATES
NUCLEAR REGULATORY COMMISSION
REGION II
245 PEACHTREE CENTER AVENUE NE, SUITE 1200
ATLANTA, GEORGIA 30303-1257
April 7, 2020
Mr. James Barstow
Vice President, Nuclear Regulatory Affairs and Support Services
Tennessee Valley Authority
1101 Market Street, LP 4A-C
Chattanooga, TN 37402-2801
SUBJECT: SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2 - NOTIFICATION OF AN NRC
FIRE PROTECTION TEAM INSPECTION (FPTI) (NRC INSPECTION REPORT
05000327/2020012 and 05000328/2020012) AND REQUEST FOR
INFORMATION (RFI)
Dear Mr. Barstow:
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 Sequoyah Nuclear Plant,
Units 1 and 2, in June 2020. The inspection team will be led by Mr. Philipp Braaten, a 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 March 30, 2020, during a telephone conversation between Andy McNeil of your staff and
Mr. 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: June 8 - 12, 2020
- Week 2 of onsite inspection: June 22 - 26, 2020
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.
J. Barstow 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, 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 Philipp Braaten, the team lead inspector, in the Region II office at (404) 997-4651 or
philipp.braaten@nrc.gov or me at (404) 997-4521.
Sincerely,
/RA/
Scott Shaeffer, Chief
Engineering Branch 2
Division of Reactor Safety
Docket No. 50-327 & 50-328
License No. DPR-77 & DPR-79
Enclosures:
Fire Protection Team Inspection
Document Request
cc w/enclosure: via ListServ
J. Barstow 3
SUBJECT: SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2 - NOTIFICATION OF AN NRC
FIRE PROTECTION TEAM INSPECTION (FPTI) (NRC INSPECTION REPORT
05000327/2020012 and 05000328/2020012) AND REQUEST FOR
INFORMATION (RFI) dated April 7, 2020
Adams Accession: ML20098D861________________________________
SUNSI Yes No ADAMS Yes No Reviewer Initials
Publicly Avail Yes No Sensitive Yes No Sens. Type Initials
RII:DRS/EB2 RII:DRS/EB2
S. Shaeffer P. Braaten
4/7/2020 4/ 7/2020
OFFICIAL RECORD COPY
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.22,
and is requested to be provided by May 4, 2020, 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 May
11, 2020. We request that the additional information provided from the second RFI be made
available by May 25, 2020.
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
of 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 (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
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:
8
- Post-fire Nuclear Safety Capability.
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)
8