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MONTHYEARJAFP-05-0118, Request for Exemption from 10 CFR 50, Appendix R, III.G.2.c Requirement for a One-Hour Rated Fire Barrier Wrap2005-07-27027 July 2005 Request for Exemption from 10 CFR 50, Appendix R, III.G.2.c Requirement for a One-Hour Rated Fire Barrier Wrap Project stage: Request ML0608600142006-04-0303 April 2006 RAI, Regarding Exemption Request for Hemyc Fire Wrap Project stage: RAI JAFP-06-0079, Response to NRC Requests for Additional Information Regarding Fitzpatrick'S Proposed Exemption Request for Hemyc Fire Wrap2006-05-17017 May 2006 Response to NRC Requests for Additional Information Regarding Fitzpatrick'S Proposed Exemption Request for Hemyc Fire Wrap Project stage: Response to RAI ML0621400672006-09-0707 September 2006 Environmental Assessment Related to an Exemption Related to an Exemption from Certain Fire Protection Requirements of 10 CFR 50, Appendix R, Iii. G.2.c Project stage: Approval ML0621903772006-09-27027 September 2006 Exemption from the Requirements of 10 CFR Part 50, Appendix R Project stage: Approval 2006-05-17
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Category:Letter type:JAFP
MONTHYEARJAFP-23-0065, License Amendment Request to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 4, and Administrative Changes to the Technical Specifications2023-12-14014 December 2023 License Amendment Request to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 4, and Administrative Changes to the Technical Specifications JAFP-23-0069, Supplemental Response to Part 73 Exemption Request Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements2023-12-0707 December 2023 Supplemental Response to Part 73 Exemption Request Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements JAFP-23-0057, and Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-22022 November 2023 and Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation JAFP-23-0064, Emergency Plan Document Revision2023-11-15015 November 2023 Emergency Plan Document Revision JAFP-23-0063, Registration of Spent Fuel Cask Use2023-11-13013 November 2023 Registration of Spent Fuel Cask Use JAFP-23-0059, Registration of Spent Fuel Cask Use2023-10-24024 October 2023 Registration of Spent Fuel Cask Use JAFP-23-0048, Supplemental Information for License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis2023-08-31031 August 2023 Supplemental Information for License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis JAFP-23-0050, Physical Security Plan, Revision 242023-08-31031 August 2023 Physical Security Plan, Revision 24 JAFP-23-0047, Correction to the 2022 Annual Radioactive Effluent Release Report2023-08-30030 August 2023 Correction to the 2022 Annual Radioactive Effluent Release Report JAFP-23-0040, License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis2023-08-0303 August 2023 License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis JAFP-23-0043, 10 CFR 50.46 Annual Report2023-07-31031 July 2023 10 CFR 50.46 Annual Report JAFP-23-0038, License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 Safety Relief Valves (S/Rvs) Setpoint Lower Tolerance2023-07-28028 July 2023 License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 Safety Relief Valves (S/Rvs) Setpoint Lower Tolerance JAFP-23-0033, License Amendment Request - Technical Specifications (TS) Section 3.3.1.2, Source Range Monitors (SRM) Instrumentation2023-06-28028 June 2023 License Amendment Request - Technical Specifications (TS) Section 3.3.1.2, Source Range Monitors (SRM) Instrumentation JAFP-23-0025, 2022 Annual Radiological Environmental Operating Report2023-05-10010 May 2023 2022 Annual Radiological Environmental Operating Report JAFP-23-0023, 2022 Annual Radioactive Effluent Release Report2023-04-27027 April 2023 2022 Annual Radioactive Effluent Release Report JAFP-23-0010, 2022 REIRS Transmittal of NRC Form 52023-03-20020 March 2023 2022 REIRS Transmittal of NRC Form 5 JAFP-23-0008, Supplement to Inservice Inspection Summary Report Cycle 252023-02-22022 February 2023 Supplement to Inservice Inspection Summary Report Cycle 25 JAFP-22-0053, Inservice Inspection Summary Report Cycle 252022-12-20020 December 2022 Inservice Inspection Summary Report Cycle 25 JAFP-22-0046, Core Operating Limits Report Cycle 262022-10-17017 October 2022 Core Operating Limits Report Cycle 26 JAFP-22-0040, 10 CFR 50.46 Annual Report2022-07-29029 July 2022 10 CFR 50.46 Annual Report JAFP-22-0033, Core Operating Limits Report Mid-Cycle 252022-06-23023 June 2022 Core Operating Limits Report Mid-Cycle 25 JAFP-22-0032, Response to Request for Additional Information for James A. FitzPatrick Nuclear Power Plant to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b..2022-06-16016 June 2022 Response to Request for Additional Information for James A. FitzPatrick Nuclear Power Plant to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b.. JAFP-22-0030, Oswego County and New York State Participation in the Emergency Plan2022-05-13013 May 2022 Oswego County and New York State Participation in the Emergency Plan JAFP-22-0029, 2021 Annual Radiological Environmental Operating Report2022-05-11011 May 2022 2021 Annual Radiological Environmental Operating Report JAFP-22-0028, 2021 Annual Radioactive Effluent Release Report2022-04-27027 April 2022 2021 Annual Radioactive Effluent Release Report JAFP-22-0026, 2021 REIRS Transmittal of NRC Form 52022-04-0707 April 2022 2021 REIRS Transmittal of NRC Form 5 JAFP-22-2020, Supplemental Information No. 1 for James A. FitzPatrick Nuclear Power Plant to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b. and 10CFR 50.69, Risk-Info2022-03-0404 March 2022 Supplemental Information No. 1 for James A. FitzPatrick Nuclear Power Plant to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b. and 10CFR 50.69, Risk-Informed JAFP-22-0017, Amendments to Indemnity Agreements2022-02-15015 February 2022 Amendments to Indemnity Agreements JAFP-22-0007, Summary of Changes to Exelon Generation Company, LLC, Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-102022-01-31031 January 2022 Summary of Changes to Exelon Generation Company, LLC, Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-10 JAFP-22-0010, Supplemental Information in Response to Order Consenting to License Transfers and Approval of Draft Conforming License Amendments2022-01-24024 January 2022 Supplemental Information in Response to Order Consenting to License Transfers and Approval of Draft Conforming License Amendments JAFP-22-0008, Response to Request for Supplemental Information by the Office of Nuclear Reactor Regulation to Support Review of a License Amendment Request to Eliminate Selected Response Time Testing for Reactor Protection System and Primary2022-01-14014 January 2022 Response to Request for Supplemental Information by the Office of Nuclear Reactor Regulation to Support Review of a License Amendment Request to Eliminate Selected Response Time Testing for Reactor Protection System and Primary JAFP-21-0093, Propose Change to Eliminate Selected Response Time Testing for Reactor Protection System and Primary Containment Isolation Instrumentation2021-10-18018 October 2021 Propose Change to Eliminate Selected Response Time Testing for Reactor Protection System and Primary Containment Isolation Instrumentation JAFP-21-0089, Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2021-09-27027 September 2021 Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position JAFP-21-0087, Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments2021-09-16016 September 2021 Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments JAFP-21-0083, Notification of Readiness for NRC 95001 Inspection2021-09-0909 September 2021 Notification of Readiness for NRC 95001 Inspection JAFP-21-0081, Supplement to Application to Revise Technical Specifications to Adopt TSTF-582, Revision 0, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements2021-09-0303 September 2021 Supplement to Application to Revise Technical Specifications to Adopt TSTF-582, Revision 0, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements JAFP-21-0075, Proposed Relief Request Associated with Reactor Pressure Vessel Water Level Instrumentation Partial Penetration Nozzle Repairs2021-08-12012 August 2021 Proposed Relief Request Associated with Reactor Pressure Vessel Water Level Instrumentation Partial Penetration Nozzle Repairs JAFP-21-0073, Response to Request for Additional Information Regarding Application to Revise the James A. FitzPatrick Nuclear Power Plant Limiting Condition for Operation (LCO) 3.5.1, ECCS - Operating Surveillance.2021-08-0909 August 2021 Response to Request for Additional Information Regarding Application to Revise the James A. FitzPatrick Nuclear Power Plant Limiting Condition for Operation (LCO) 3.5.1, ECCS - Operating Surveillance. JAFP-21-0069, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2021-07-30030 July 2021 Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors JAFP-21-0070, License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b2021-07-30030 July 2021 License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b JAFP-21-0071, 10 CFR 50.46 Annual Report2021-07-29029 July 2021 10 CFR 50.46 Annual Report JAFP-21-0064, Supplemental Information - Proposed Alternative Concerning ASME Section XI Repair/Replacement Documentation for Replacement of Pressure Retaining Bolting2021-07-0707 July 2021 Supplemental Information - Proposed Alternative Concerning ASME Section XI Repair/Replacement Documentation for Replacement of Pressure Retaining Bolting JAFP-21-0053, Emergency License Amendment Request - One Time Extension to TS 3.5.1 Condition a, TS 3.6.1.9 Condition a, and TS 3.6.4.1 Condition a Completion Time to Support Residual Heat Removal (RHR) Pump Motor Replacement2021-06-14014 June 2021 Emergency License Amendment Request - One Time Extension to TS 3.5.1 Condition a, TS 3.6.1.9 Condition a, and TS 3.6.4.1 Condition a Completion Time to Support Residual Heat Removal (RHR) Pump Motor Replacement JAFP-21-0052, Emergency License Amendment Request, One Time Extension of Condition a to TS 3.5.1, TS 3.6.1.9, and TS 3.6.4.1 Completion Time to Support Residual Heat Removal (RHR) Pump Motor Replacement2021-06-13013 June 2021 Emergency License Amendment Request, One Time Extension of Condition a to TS 3.5.1, TS 3.6.1.9, and TS 3.6.4.1 Completion Time to Support Residual Heat Removal (RHR) Pump Motor Replacement JAFP-21-0051, Emergency License Amendment Request - One Time Extension to TS 3.5.1 Condition a, TS 3.6.1.9 Condition a, and TS 3.6.4.1 Condition a Completion Time to Support Residual Heat Removal (RHR) Pump Motor Replacement2021-06-13013 June 2021 Emergency License Amendment Request - One Time Extension to TS 3.5.1 Condition a, TS 3.6.1.9 Condition a, and TS 3.6.4.1 Condition a Completion Time to Support Residual Heat Removal (RHR) Pump Motor Replacement JAFP-21-0050, Emergency License Amendment Request, One Time Extension of Condition a to TS 3.5.1, TS 3.6.1.9, and TS 3.6.4.1 Completion Time to Support Residual Heat Removal (RHR) Pump Motor Replacement2021-06-12012 June 2021 Emergency License Amendment Request, One Time Extension of Condition a to TS 3.5.1, TS 3.6.1.9, and TS 3.6.4.1 Completion Time to Support Residual Heat Removal (RHR) Pump Motor Replacement JAFP-21-0044, Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments2021-06-11011 June 2021 Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments JAFP-21-0042, Reply to a Notice of Violation; EA-20-1382021-06-0303 June 2021 Reply to a Notice of Violation; EA-20-138 JAFP-21-0041, Supplement to Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing2021-05-17017 May 2021 Supplement to Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing JAFP-21-0040, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2021-05-14014 May 2021 Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs 2023-08-31
[Table view] Category:Report
MONTHYEARRS-21-001, Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel Piping2021-01-0404 January 2021 Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel Piping ML20303A1752020-10-23023 October 2020 Proposed Relief Request from Section XI Repair/Replacement Documentation for Bolting Replacement of Pressure Retaining Bolting ML19301A5052019-08-13013 August 2019 JAF-CALC-NBI-00205 Setpoint Calculation for Vessel Lo-Lo Lvl Primary Containment Isolation Function (02-3LT-57A,B and 02-3STU-258A,B) ML18019A2692018-02-12012 February 2018 Flood Hazard Mitigation Strategies Assessment JAFP-17-0085, High Frequency Confirmation Report for March 12, 2012, Information Request Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1, Seismic2017-08-30030 August 2017 High Frequency Confirmation Report for March 12, 2012, Information Request Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1, Seismic JAFP-17-0084, Report of Full Compliance with March 12, 2012, Commission Order to Modify Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)2017-08-29029 August 2017 Report of Full Compliance with March 12, 2012, Commission Order to Modify Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) JAFP-17-0078, Focused Evaluation Summary Pursuant to 10 CFR 50.54(f) Request for Information Regarding Recommendation 2.1: Flooding of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2017-07-27027 July 2017 Focused Evaluation Summary Pursuant to 10 CFR 50.54(f) Request for Information Regarding Recommendation 2.1: Flooding of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident JAFP-17-0054, James a FitzPatrick - Submittal of Stress Analysis Summary for the 24-10-130 Weld Overlay2017-05-25025 May 2017 James a FitzPatrick - Submittal of Stress Analysis Summary for the 24-10-130 Weld Overlay ML17110A2742017-04-20020 April 2017 Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI Division 1 ML16043A4112016-02-18018 February 2016 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50 Section 50.54(f) Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Review JAFP-15-0129, Submittal of 10 CFR 71.95 Report Involving 8-120B Cask2015-11-0606 November 2015 Submittal of 10 CFR 71.95 Report Involving 8-120B Cask JAFP-15-0036, J.A. Fitzpatrick Flood Hazard Reevaluation Report - Response to NRC Request for Information Per 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fuskushima Dai-2015-03-12012 March 2015 J.A. Fitzpatrick Flood Hazard Reevaluation Report - Response to NRC Request for Information Per 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fuskushima Dai-ichi ML15007A0902015-02-12012 February 2015 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-13-109 (Severe Accident Capable Hardened Vents) ML15007A1502015-01-0707 January 2015 Seismic Walkdown Report Update - Entergy'S Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Re the Seismic Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident. JAFP-15-0007, Seismic Walkdown Report Update - Entergy'S Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Re the Seismic Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accid2015-01-0707 January 2015 Seismic Walkdown Report Update - Entergy'S Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Re the Seismic Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident. JAFP-14-0143, Expedited Seismic Evaluation Process Report (CEUS Sites), Response NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from The.2014-12-30030 December 2014 Expedited Seismic Evaluation Process Report (CEUS Sites), Response NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from The. JAFP-14-0094, 10 CFR 50.46 Annual Report - Changes and Errors in Emergency Core Cooling System Evaluation Models2014-08-0101 August 2014 10 CFR 50.46 Annual Report - Changes and Errors in Emergency Core Cooling System Evaluation Models ML14176A9612014-06-24024 June 2014 Submittal of Non-Proprietary BWROG Technical Product, BWROGTP-11-006 - ECCS Containment Walkdown Procedure, Rev 1 (January 2011), as Formally Requested During the Public Meeting Held on April 30, 2014 ML14073A1552014-04-0101 April 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident ML14007A6812014-02-21021 February 2014 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) ML14043A4282014-02-15015 February 2014 Mega-Tech Services, LLC, Technical Evaluation Report Regarding the Overall Integrated Plan for James A. FitzPatrick Nuclear Power Plant, TAC Nos.: MF1077 ML13247A0362013-08-20020 August 2013 Letter from R. Dale Roberts 10 CFR 71.95 Report on the 8-120B Cask ML13273A6912013-08-20020 August 2013 Redacted - Letter from R. Dale Roberts 10 CFR 71.95 Report on the 8-120B Cask JAFP-13-0096, James a FitzPatrick Nuclear Power Plant, 10 CFR 50.46 Annual Report - Changes and Errors in Emergency Core Cooling System Evaluation Models2013-08-0101 August 2013 James a FitzPatrick Nuclear Power Plant, 10 CFR 50.46 Annual Report - Changes and Errors in Emergency Core Cooling System Evaluation Models JAFP-13-0035, Response to Request for Additional Information on Core for Plate Rim Hold Down Bolting, Plant Specific Analysis and Inspection Plan, License Renewal Commitment 232013-04-17017 April 2013 Response to Request for Additional Information on Core for Plate Rim Hold Down Bolting, Plant Specific Analysis and Inspection Plan, License Renewal Commitment #23 JAFP-12-0134, FitzPatrick - Seismic Walkdown Report, Response to NRC Request for Information Per 10 CFR 50.54 (F) Re the Seismic Aspect of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2012-11-27027 November 2012 FitzPatrick - Seismic Walkdown Report, Response to NRC Request for Information Per 10 CFR 50.54 (F) Re the Seismic Aspect of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident ML12342A1402012-11-27027 November 2012 Seismic Walkdown Report, Response to NRC Request for Information Per 10 CFR 50.54 (F) Re the Seismic Aspect of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident JAFP-12-0135, Flooding Walkdown Report - Entergys Response to NRC Request for Information Pursuant to 10CFR50.54(f) Flooding Aspects of Recommendation 2.3 of Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2012-11-27027 November 2012 Flooding Walkdown Report - Entergys Response to NRC Request for Information Pursuant to 10CFR50.54(f) Flooding Aspects of Recommendation 2.3 of Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident JAFP-12-0134, Engineering Report, JAF-RPT-12-00015, Rev. 0, Jaf Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3 Seismic, Book 1 of 32012-11-21021 November 2012 Engineering Report, JAF-RPT-12-00015, Rev. 0, Jaf Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3 Seismic, Book 1 of 3 JAFP-12-0134, Engineering Report JAF-RPT-12-00015, Rev. 0, Jaf Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3 Seismic, Book 1 of 3, Attachment C, Pages 74 Through 5732012-11-21021 November 2012 Engineering Report JAF-RPT-12-00015, Rev. 0, Jaf Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3 Seismic, Book 1 of 3, Attachment C, Pages 74 Through 573 ML12342A1392012-11-21021 November 2012 Engineering Report JAF-RPT-12-00015, Rev. 0, Jaf Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3 Seismic, Book 1 of 3, Attachment C, Pages 74 Through 573 ML12342A1382012-11-21021 November 2012 Engineering Report, JAF-RPT-12-00015, Rev. 0, Jaf Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3 Seismic, Book 1 of 3 JAFP-12-0134, Engineering Report JAF-RPT-12-00015, Rev. 0, Jaf Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3 Seismic, Book 2 of 3, Attachment C, Pages 283 Through 5732012-11-21021 November 2012 Engineering Report JAF-RPT-12-00015, Rev. 0, Jaf Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3 Seismic, Book 2 of 3, Attachment C, Pages 283 Through 573 ML12342A1422012-11-21021 November 2012 Engineering Report JAF-RPT-12-00015, Rev. 0, Jaf Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3 Seismic, Book 2 of 3, Attachment C, Pages 551 Through 573 ML13163A2662012-05-18018 May 2012 from Bhalchandra Vaidya to Samson Lee: G20120172, 2.206 Petition ML13162A6272012-02-20020 February 2012 Summary of R1 Containment Vents ML1127000692011-09-26026 September 2011 Enclosure 2, Mfn 10-245 R4, Description of the Evaluation and Surveillance Recommendations for BWR/2-5 Plants ML1125101872011-09-0808 September 2011 NRC Investigation Report Nos. 1-2009-041, 1-2010-019, and 1-2010-031 ML1024601002010-09-0202 September 2010 Enclosure 2, RA-ENO-EP1-10-135, Response to NRC Supplemental RAIs 1, 4, 5, and 6 for James a FitzPatrick Cycle 20 SLMCPR Submittal ML1012704392010-05-0505 May 2010 Y020100187 - List of Historical Leaks and Spills at U.S. Commercial Nuclear Power Plants JAFP-09-0091, 10 CFR 50.46 Annual Report - Changes and Errors in Emergency Core Cooling System (ECCS) Evaluation Models2009-07-31031 July 2009 10 CFR 50.46 Annual Report - Changes and Errors in Emergency Core Cooling System (ECCS) Evaluation Models JAFP-09-0056, Summary of Plant and Independent Spent Fuel Storage Installation Changes, Tests, and Experiments for 2007 and 2008 as Required by 10 CFR 50.59 and 10 CFR 72.482009-05-11011 May 2009 Summary of Plant and Independent Spent Fuel Storage Installation Changes, Tests, and Experiments for 2007 and 2008 as Required by 10 CFR 50.59 and 10 CFR 72.48 JAFP-08-0131, Enclosure 2, Structural Integrity Associates, Inc. Calculation 0800769.311 Crack Growth Analysis for Recirculation Inlet Nozzle N-2C2008-12-0404 December 2008 Enclosure 2, Structural Integrity Associates, Inc. Calculation 0800769.311 Crack Growth Analysis for Recirculation Inlet Nozzle N-2C ML0835903392008-12-0404 December 2008 Enclosure 2, Structural Integrity Associates, Inc. Calculation 0800769.311 Crack Growth Analysis for Recirculation Inlet Nozzle N-2C JAFP-08-0131, Enclosure 3, Structural Integrity Associates, Inc. Calculation 0800769.316 Reconciliation of Recirculation Inlet N2 Nozzle-to-Safe End Weld Overlay Repair with Nozzle Stress Report2008-12-0303 December 2008 Enclosure 3, Structural Integrity Associates, Inc. Calculation 0800769.316 Reconciliation of Recirculation Inlet N2 Nozzle-to-Safe End Weld Overlay Repair with Nozzle Stress Report ML0831006632008-11-19019 November 2008 Request for Additional Information Third 10-Year Interval Inservice Inspection Program Plan Relief Request RR-CRV-01 JAFP-08-0103, Certificate of Compliance Not Met During Receipt of Low-Level Radioactive Waste Shipment at Barnwell, Sc Disposal Facility2008-10-0202 October 2008 Certificate of Compliance Not Met During Receipt of Low-Level Radioactive Waste Shipment at Barnwell, Sc Disposal Facility ML0810102772008-09-0808 September 2008 Renewed Facility Operating License No. DPR-59 / Appendix C - Additional Conditions ML0821900132008-08-0707 August 2008 Monthly Operating Reports Second Quarter 2008 JAFP-08-0067, BWR Vessels and Internals Project, Lntegrated Surveillance Program (ISP) Data for FitzPatrick (Excerpted from BWRVIP-135, Revision 1)2008-07-31031 July 2008 BWR Vessels and Internals Project, Lntegrated Surveillance Program (ISP) Data for FitzPatrick (Excerpted from BWRVIP-135, Revision 1) 2021-01-04
[Table view] Category:Technical
MONTHYEARRS-21-001, Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel Piping2021-01-0404 January 2021 Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel Piping ML19301A5052019-08-13013 August 2019 JAF-CALC-NBI-00205 Setpoint Calculation for Vessel Lo-Lo Lvl Primary Containment Isolation Function (02-3LT-57A,B and 02-3STU-258A,B) JAFP-17-0085, High Frequency Confirmation Report for March 12, 2012, Information Request Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1, Seismic2017-08-30030 August 2017 High Frequency Confirmation Report for March 12, 2012, Information Request Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1, Seismic JAFP-17-0078, Focused Evaluation Summary Pursuant to 10 CFR 50.54(f) Request for Information Regarding Recommendation 2.1: Flooding of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2017-07-27027 July 2017 Focused Evaluation Summary Pursuant to 10 CFR 50.54(f) Request for Information Regarding Recommendation 2.1: Flooding of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident JAFP-17-0054, James a FitzPatrick - Submittal of Stress Analysis Summary for the 24-10-130 Weld Overlay2017-05-25025 May 2017 James a FitzPatrick - Submittal of Stress Analysis Summary for the 24-10-130 Weld Overlay JAFP-15-0036, J.A. Fitzpatrick Flood Hazard Reevaluation Report - Response to NRC Request for Information Per 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fuskushima Dai-2015-03-12012 March 2015 J.A. Fitzpatrick Flood Hazard Reevaluation Report - Response to NRC Request for Information Per 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fuskushima Dai-ichi ML15007A1502015-01-0707 January 2015 Seismic Walkdown Report Update - Entergy'S Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Re the Seismic Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident. JAFP-15-0007, Seismic Walkdown Report Update - Entergy'S Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Re the Seismic Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accid2015-01-0707 January 2015 Seismic Walkdown Report Update - Entergy'S Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Re the Seismic Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident. ML14176A9612014-06-24024 June 2014 Submittal of Non-Proprietary BWROG Technical Product, BWROGTP-11-006 - ECCS Containment Walkdown Procedure, Rev 1 (January 2011), as Formally Requested During the Public Meeting Held on April 30, 2014 ML14007A6812014-02-21021 February 2014 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) ML14043A4282014-02-15015 February 2014 Mega-Tech Services, LLC, Technical Evaluation Report Regarding the Overall Integrated Plan for James A. FitzPatrick Nuclear Power Plant, TAC Nos.: MF1077 JAFP-13-0035, Response to Request for Additional Information on Core for Plate Rim Hold Down Bolting, Plant Specific Analysis and Inspection Plan, License Renewal Commitment 232013-04-17017 April 2013 Response to Request for Additional Information on Core for Plate Rim Hold Down Bolting, Plant Specific Analysis and Inspection Plan, License Renewal Commitment #23 ML12342A1402012-11-27027 November 2012 Seismic Walkdown Report, Response to NRC Request for Information Per 10 CFR 50.54 (F) Re the Seismic Aspect of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident JAFP-12-0134, FitzPatrick - Seismic Walkdown Report, Response to NRC Request for Information Per 10 CFR 50.54 (F) Re the Seismic Aspect of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2012-11-27027 November 2012 FitzPatrick - Seismic Walkdown Report, Response to NRC Request for Information Per 10 CFR 50.54 (F) Re the Seismic Aspect of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident ML12342A1392012-11-21021 November 2012 Engineering Report JAF-RPT-12-00015, Rev. 0, Jaf Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3 Seismic, Book 1 of 3, Attachment C, Pages 74 Through 573 ML12342A1382012-11-21021 November 2012 Engineering Report, JAF-RPT-12-00015, Rev. 0, Jaf Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3 Seismic, Book 1 of 3 JAFP-12-0134, Engineering Report JAF-RPT-12-00015, Rev. 0, Jaf Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3 Seismic, Book 2 of 3, Attachment C, Pages 283 Through 5732012-11-21021 November 2012 Engineering Report JAF-RPT-12-00015, Rev. 0, Jaf Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3 Seismic, Book 2 of 3, Attachment C, Pages 283 Through 573 JAFP-12-0134, Engineering Report JAF-RPT-12-00015, Rev. 0, Jaf Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3 Seismic, Book 1 of 3, Attachment C, Pages 74 Through 5732012-11-21021 November 2012 Engineering Report JAF-RPT-12-00015, Rev. 0, Jaf Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3 Seismic, Book 1 of 3, Attachment C, Pages 74 Through 573 JAFP-12-0134, Engineering Report, JAF-RPT-12-00015, Rev. 0, Jaf Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3 Seismic, Book 1 of 32012-11-21021 November 2012 Engineering Report, JAF-RPT-12-00015, Rev. 0, Jaf Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3 Seismic, Book 1 of 3 ML12342A1422012-11-21021 November 2012 Engineering Report JAF-RPT-12-00015, Rev. 0, Jaf Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3 Seismic, Book 2 of 3, Attachment C, Pages 551 Through 573 ML13163A2662012-05-18018 May 2012 from Bhalchandra Vaidya to Samson Lee: G20120172, 2.206 Petition ML1024601002010-09-0202 September 2010 Enclosure 2, RA-ENO-EP1-10-135, Response to NRC Supplemental RAIs 1, 4, 5, and 6 for James a FitzPatrick Cycle 20 SLMCPR Submittal JAFP-08-0131, Enclosure 2, Structural Integrity Associates, Inc. Calculation 0800769.311 Crack Growth Analysis for Recirculation Inlet Nozzle N-2C2008-12-0404 December 2008 Enclosure 2, Structural Integrity Associates, Inc. Calculation 0800769.311 Crack Growth Analysis for Recirculation Inlet Nozzle N-2C ML0835903392008-12-0404 December 2008 Enclosure 2, Structural Integrity Associates, Inc. Calculation 0800769.311 Crack Growth Analysis for Recirculation Inlet Nozzle N-2C JAFP-08-0131, Enclosure 3, Structural Integrity Associates, Inc. Calculation 0800769.316 Reconciliation of Recirculation Inlet N2 Nozzle-to-Safe End Weld Overlay Repair with Nozzle Stress Report2008-12-0303 December 2008 Enclosure 3, Structural Integrity Associates, Inc. Calculation 0800769.316 Reconciliation of Recirculation Inlet N2 Nozzle-to-Safe End Weld Overlay Repair with Nozzle Stress Report ML0821900132008-08-0707 August 2008 Monthly Operating Reports Second Quarter 2008 ML0821004582008-07-31031 July 2008 BWR Vessels and Internals Project, Lntegrated Surveillance Program (ISP) Data for FitzPatrick (Excerpted from BWRVIP-135, Revision 1) JAFP-08-0067, BWR Vessels and Internals Project, Lntegrated Surveillance Program (ISP) Data for FitzPatrick (Excerpted from BWRVIP-135, Revision 1)2008-07-31031 July 2008 BWR Vessels and Internals Project, Lntegrated Surveillance Program (ISP) Data for FitzPatrick (Excerpted from BWRVIP-135, Revision 1) JAFP-07-0125, ENT-FLU-002-R-005, Rev 0, James A. FitzPatrick, License Renewal Application - Amendment 14, Fluence Calculation, Non-Proprietary Version2007-10-31031 October 2007 ENT-FLU-002-R-005, Rev 0, James A. FitzPatrick, License Renewal Application - Amendment 14, Fluence Calculation, Non-Proprietary Version ML0732400252007-08-10010 August 2007 Federal Consistency Overview ML0713504332007-04-0505 April 2007 JAF-RPT-05-AMM30, Rev 4, Draft, Aging Management Review of Nonsafety-Related Systems and Components Affecting Safety-Related Systems, (FitzPatrick) ML0705206612007-02-20020 February 2007 E-mail from Entergy to T. Le & Document - GE-NE-B1100732-01, Rev. 1, Final Report, Class II, February 1998 Plant FitzPatrick RPV Surveillance Materials Testing and Analysis of 120 Degree Capsule at 13.4 EFPY ML0701605692007-01-16016 January 2007 JAFNPP - SEIS Web Reference - Mills 2003: Status of the Lake Ontario Food Web in a Changing Ecosystem ML0701203042006-12-27027 December 2006 JAFNPP - SEIS Web References - Chppm Noise Levels of Army Equipments ML0603903722005-09-30030 September 2005 NEDO-33087, Rev. 1, J.A. Fitzpatrick Nuclear Power Plant Aprm/Rbm/Technical Specifications/Maximum Extended Operating Domain (Arts/Meod). ML0701602142005-07-31031 July 2005 JAFNPP - SEIS Web Reference - Mills Et Al 2005 JAFP-05-0118, Request for Exemption from 10 CFR 50, Appendix R, III.G.2.c Requirement for a One-Hour Rated Fire Barrier Wrap2005-07-27027 July 2005 Request for Exemption from 10 CFR 50, Appendix R, III.G.2.c Requirement for a One-Hour Rated Fire Barrier Wrap ML0701103402005-06-30030 June 2005 EPA Shooting Range Bmps - JAFNPP SEIS Reference BVY 04-088, Fitness-for-Duty Program Performance Report for the Period January - June 20042004-08-30030 August 2004 Fitness-for-Duty Program Performance Report for the Period January - June 2004 JAFP-03-0065, Summary of Plant Changes, Tests, & Experiments for 2001/2002 as Required by 10 CFR 50.59 & 10 CFR 72.48, & Summary of Commitment Changes for 2001/20022003-05-12012 May 2003 Summary of Plant Changes, Tests, & Experiments for 2001/2002 as Required by 10 CFR 50.59 & 10 CFR 72.48, & Summary of Commitment Changes for 2001/2002 JAFP-03-0052, 2002 Personnel Radiation Exposure Summary Report2003-04-15015 April 2003 2002 Personnel Radiation Exposure Summary Report ML0305202692003-02-15015 February 2003 Follow-up Report, Reference Event #39516 ML0636202142002-03-31031 March 2002 JAFNPP Er Ref 8-15 DOE Eia International Energy Outlook 2002 ML0732012262001-01-0101 January 2001 Onondago Reservation Census Population NRC Generic Letter 1979-451979-09-25025 September 1979 NRC Generic Letter 1979-045: Transmittal of Reports Regarding Foreign Reactor Operation Experiences ML17037C2661976-01-23023 January 1976 Letter Regarding a Report Entitled 1974 Nine Mile Point Aquatic Ecology Studies. 2021-01-04
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Entergy Nuclear Northeast Entergy Nuclear Operations, Inc.
James A. Fitzpatrick NPP Is Entergy P.O. Box 110 Lycoming, NY 13093 Tel 315 349 6024 Fax 315 349 6480 T.A. Sullivan July 27, 2005 Site Vice President - JAF JAFP-05-0118 United States Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
SUBJECT:
James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 License No. DPR-59 Request For Exemption From 10 CFR 50, Appendix R, III.G.2.c Requirement For A One-Hour Rated Fire Barrier Wrap
REFERENCE:
- 1. NRC Information Notice 2005-07: Results of Hemyc Electrical Raceway Fire Barrier System Full Scale Fire Testing, dated April 1, 2005.
Dear Sir or Madam:
Pursuant to the provisions of 10 CFR 50.12(a), Entergy Nuclear Operations, Inc. (ENO) is submitting a request for an exemption from the requirements of 10 CFR 50, Appendix R, "Fire Protection Program for Nuclear Power Facilities Operating Prior to January 1, 1979," as it applies to the James A. FitzPatrick Nuclear Power Plant (JAF) for Fire Area IC.
NRC Information Notice 2005-07 (Reference 1) provided licensees the details of Hemyc electrical raceway fire barrier system (ERFBS) full-scale fire tests conducted by the NRC's Office of Nuclear Regulatory Research. The test results concluded that the Hemyc ERFBS does not provide the level of protection expected for a one-hour rated fire barrier, as originally designed.
Enclosure 1 summarizes the bases for this exemption request, provides a detailed evaluation of the installed fire barrier wrap and its application, and provides the adequacy of the existing fire barrier wrap to maintain the circuit functional during a fire, thereby providing an equivalent level of fire protection and safe shutdown capability in accordance with 10 CFR 50.48 and 10 CFR 50, Appendix R.
If you have any questions, please contact Mr. Rick Plasse, Regulatory Compliance Manager, at (315) 349-6793.
Very truly you'd Sullivan Site Vice President TAS:GB:gb : Request for Exemption cc: Mr. Samuel J. Collins Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406-1415 Mr. John P. Boska, Project Manager Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop 0-8B-1 Washington, DC 20555-0001 Office of the Resident Inspector U.S. Nuclear Regulatory Commission James A. FitzPatrick Nuclear Power Plant P.O. Box 136 Lycoming, NY 13093
Enclosure I to JAFP-05-0118 Entergy Nuclear Operations, Inc. - James A. FitzPatrick Docket No. 50-333 Request for Exemption from 10 CFR 50, Appendix R, III.G.2.c Requirement for a One-Hour Rated Fire Barrier Wrap
Enclosure 1 to JAFP-05-0118 EVALUATION PURSUANT TO-I0 CFR 50.12 CRITERIA
- 1. Exemption Requested In accordance with the requirements of 10 CFR 50.12(a)(2)(ii), the James A. FitzPatrick Nuclear Power Plant (JAF) requests exemption to the requirements of 10 CFR 50, Appendix R, Section IlI.G.2.c to the extent that a fire barrier wrap (Hemyc) used to protect a safe shutdown power cable located in the West Cable Tunnel, lacks sufficient evidence to demonstrate that it meets the acceptance criteria for a rated 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> fire barrier. This exemption request is consistent with an exemption granted to JAF for a 30 minute fire barrier wrap (FP-60) in the same location (Reference 1).
- 2. Physical Arrangement and Fire Protection Features Fire Area Boundaries The West Cable Tunnel (Fire Area 1C/Fire Zone CT-1) is a tunnel through which the majority of Division I cables from the Control Room Complex to the Electrical Switchgear Rooms are routed (Figure 1).
Fire Area 1C/Fire Zone CT-1 is separated from the adjoining plant areas by 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> rated fire barriers (with the exception of the non-rated exterior barriers which are below-grade).
There is no exposed structural steel in or supporting fire rated barriers in the West Cable Tunnel.
Safe Shutdown Capabilities For a postulated fire in the West Cable Tunnel (CT-1), safe shutdown compliance strategy credits High Pressure Coolant Injection (HPCI) for reactor coolant makeup and B Train Residual Heat Removal (RHR) for suppression pool cooling. Cold shutdown is achieved using B Train Alternate Shutdown Cooling (ASD).
Fire Area 1C contains A Train safe shutdown equipment and cables. Therefore, postulating the occurrence of a fire in Fire Area 1C, safe shutdown capabilities are dependent upon B Train equipment and subsequently B Train DC power and the HVAC equipment which supports it (Reference 2). Air Handling Unit 72AHU-30B is required to provide proper ventilation of Battery Room B (Fire Area 4/Fire Zone BR-3). The 600 volt power cable (1ABVBBKO55) which supplies power to the air handling unit is partially routed in Fire Area 1C, Fire Zone CT-1.
Ventilation of Battery Room B is required to support Appendix R safe shutdown compliance. However, loss of the air handling unit will not cause the immediate loss of any safe shutdown function. Per calculation (Reference 3), it will take 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for the B Battery Room (BR-3) to heat up to the point it will exceed the manufacturers qualification of the batteries. This value is based on the worst case heat up rate resulting from the loss of ventilation from a fire in the Battery Room Corridor (Fire Area 16/Fire Zone BR-5), which shares a common barrier with the Battery Rooms. To ensure the availability and operability of 72AHU-30B to ventilate the B Battery Room during a fire in Fire Area 1C, Fire Zone CT-1, the approximately 40 feet of 5 inch conduit (conduit number 1CK201 BD1I) containing IABVBBKO55 was wrapped with Hemyc to comply with 10CFR50 Appendix R, Section IlI.G.2.c.
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Enclosure 1 to JAFP-05-0118 Fire Barrier Wrap Capabilities The Hemyc Electrical Raceway Fire Barrier System (ERFBS) is constructed of Hemyc mats consisting of Kaowool insulation inside an outer covering of Siltemp high-temperature fabric. Hemyc mats that are directly wrapped around the electrical raceway utilize 2-inch-thick Kaowool blankets.
NRC Tested Configuration Based on the NRC March 2005 Hemyc tests, the closest test configuration to the actual configuration used at JAF is the 4 inch cable filled conduit wrapped with Hemyc. The Hemyc material tested by the NRC used Refrasil fabric for both the internal and external covering which, based on analysis performed by Sandia National Laboratory, is expected to perform similar to Siltemp. Stainless steel bands were used for attachment to the conduit. The spacing of the banding was per Promatec's maximum spacing requirement of 9 inch centers. The test specimen used butt joints with 6 inch wide collar over wraps and a minimum 2 inch overlap at the blanket seams. Tests were also performed on Hemyc wrapped structural supports consisting of 2 inch tube steel and unistrut as well as 18" by 24" by 8" junction boxes.
The tested 4 inch cable filled conduit (30.0% fill) reached a single point temperature of 3250 F at 43 minutes, however, the maximum temperature achieved on the internal bare
- 8 wire after 60 minutes was 1990 F. The test data documents that the wrapped unistrut and tube steel supports reached a single point temperature of 3250 F at a distance of 3 inches in from the exposed support steel after 22-32 and 13-25 minutes respectively.
The banded junction box reached its failure criteria (average temperature increase of 250'F) after 31 minutes.
During the fire testing, the outer layer of Refrasil material consistently experienced a phenomenon of thermal shrinkage. This shrinkage led to the mats contracting and opening gaps in the ERFBS at the over wrapped butt joints and at the 2 inch overlap.
The stitched joints of the junction boxes also opened up, however, the Hemyc material on the banded junction box remained in place (References 4 and 5). It appeared that the 6 inch collars would often contract and move with one side of the material. Refrasil shrinkage was common during the testing, usually great enough to expose the conduit.
The 2 inch overlapping joints also experienced failures. In these examples, Refrasil shrinkage led to the joints being pulled apart under the Y/2 inch Stainless Steel banding.
JAF Installed Configuration While the configuration used at JAF was not specifically tested, the testing performed by the NRC supports the expectation that the installed configuration will meet or exceed a 30 minute fire rating. The Hemyc wrap at JAF consists of aluminized Siltemp on the inner and outer covering that, by materials of construction, can be expected to have better heat resistive properties than non-aluminized Siltemp or the Refrasil material tested by the NRC. The aluminized Siltemp is coated with a reflective material that serves to reflect more radiant energy versus the standard Siltemp or Refrasil. The overlap collars used at JAF are also larger than those used on the test specimen and the banding is generally spaced less than 9 inches on center. The tested configuration used 6 inch collars, while the JAF configuration has collars approximately 8 to 9 inches, which would reduce the potential for openings as documented in the NRC test. The protected conduit at JAF is a 5 inch cable filled conduit (27.2% fill) which has a thermal mass per unit length greater then the 4 inch conduit used in the test. Although the Hemyc wrap 2 of 10
Enclosure 1 to JAFP-05-0118 used at JAF may be subject to similar thermal shrink, which could potentially expose the conduit, the additional thermal mass of the conduit would inherently provide additional fire endurance by effectively reducing the rate of rise of the internal temperature of the conduit and, therefore, the exposure to the cable.
The 5 inch conduit is secured in place near the ceiling with 5 seismically qualified structural supports. The first 3 feet 9 inches of the conduit where it passes through the concrete wall to the north is 5 inch flex-conduit. The remainder is rigid conduit with one inline pull box. All of the supports are completely wrapped with Hemyc (no exposed steel) up to the ceiling mounted base plate. A portion of the base plates are left exposed. The base plates are Hilti bolted to the concrete ceiling, which would act as a heat sink for a fire in this area, thereby minimizing the heat transfer into the supports.
Based on this configuration it is not expected that the heat transfer through the exposed base plates or Hemyc wrapped supports would be sufficient to adversely impact the functionality of the protected cable or reduce the fire resistance of the conduit wrap.
The 5 inch conduit at JAF contains an approximately 12" by 18" by 8" pull box inline with the conduit. Although this is similar in shape to the junction box tested, the Hemyc has been applied in a different manner than the tested junction box configuration. Based on photographs provided by the NRC, it appears the junction box was wrapped using 2 individual Hemyc mats (each mat covering 3 sides of the junction box) stitched together and then banded with stainless steel bands. The pull box at JAF is wrapped in a manor consistent with the rest of the conduit. The pull box is completely wrapped horizontally with one piece of Hemyc and then banded in place using 3 stainless steel bands spaced 8 inches on center. The vertical end pieces were then stitched in place and further secured by the conduit wrap butted against it. This configuration results in very few stitched joints, which is the primary weak point documented in the test report. If the pull box wrap were to shrink during a fire, the exposure would be expected at the corners of the end pieces. This is not expected to heat up the pull box to the point it would cause the cable to fail. Based on the configuration of the wrap on the pull box versus the banded junction box tested, it is expected that the pull box would perform better then the 31 minutes documented in the test.
In addition to the above, observations of the limited temperature rise experienced on the bare #8 wire support expectations that the cable within the JAF conduit would remain functional through the 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Appendix R requirement. The bare #8 wire located on the inside of the 4 inch filled conduit reached a maximum temperature of 199 0F after 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
This temperature is just slightly above the 90'C (1940F) normal rated temperature of the JAF cable and well below the 2500C (4820F) short circuit rating (Reference 6). No internal temperature was recorded on the junction box tested and the heat transfer through the supports into the conduit is expected to be minimal. Demonstrating that the maximum recorded temperature is below the cable insulation ignition temperature complies with the guidance provided for fire barrier wraps in Generic Letter 86-10.
As demonstrated above, the JAF configuration will meet or exceed a 30 minute fire rating. Additionally, based on the 199 0F internal temperature documented in the test, there is reasonable assurance that the cable would maintain functionality through the 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Appendix R requirement.
Fixed Combustibles and Ignition Sources The majority (over 90%) of the in-situ combustible loading in the West Cable Tunnel is cable (Reference 7) which has been determined by analysis to meet standards similar to 3 of 10
Enclosure 1 to JAFP-05-0118 IEEE Standard 383-1974. Specifically, the original cables for JAF were specified and ordered prior to issuance of IEEE 383-1974. An analysis was performed by JAF (Reference 8) which evaluated the flame retardant standards specified for the cable used in open raceway and it was determined that the cable installed at JAF meets performance criteria similar to IEEE 383-1974.
Cables that are identified to be from a manufacturer not included in the original purchase orders have been verified as meeting IEEE 383-1974 specifications for flame spread based on their manufacturer's catalog specifications.
The remaining combustibles located within the West Cable Tunnel are made up of (1) a fiberglass water tank (shower waste tank 74TK-3). The fiberglass tank is of cylindrical construction, with the axis parallel to horizon. The tank has two small pumps associated with it. The pumps are unlikely ignition sources for the tank due to the curved tank surface, which minimizes the potential for 'banking" of heat under the tank, as well as the generally low ignitability of the fiberglass tank itself. The distance of the tank from the subject wrap is approximately 21 feet; (2) fiberglass ("Bondstrand") piping of 3 inch nominal diameter. The only fiberglass components within 20 feet of the protected cable are two sections of the Bondstrand piping both of which serve the Chemistry laboratory drains. In two places, the Bondstrand piping comes within close proximity (less the 5 feet) of the Hemyc, however, the quantity of pipe that comes this close to the wrap is less then 10 feet. The remainder of the materials are typically fiberglass ladders used for fire brigade or maintenance purposes. All of the ladders are stored in excess of 50 feet from the subject wrap.
The equivalent fire severity for the entire zone is approximately 60 minutes (Reference 7). The combustible loading that contributes to this fire severity is spread out over the entire 13,400 square foot area (i.e., the total area of Fire Zone CT-1). The nature and configuration of combustibles in the immediate area of the fire barrier wrap consists of limited combustibility cables in horizontal cable trays. For this reason, the fire severity in the vicinity of the wrap is expected to be significantly below 60 minutes. Transient combustible materials that may be brought into the area are controlled by administrative procedure (Reference 9).
This zone has no significant in-situ ignition sources other than the cables themselves.
Hot work and ignition sources are controlled throughout the site by administrative procedure (Reference 10). The procedure requires that hot work be controlled by issuance of a hot work permit and requires that the work area be inspected prior to the commencement of hot work activities to assure that procedural requirements are satisfied. Furthermore, the procedure requires that the area be cleared of combustible material, including combustible and flammable liquids, within 35 feet of the work area if practical, or that the combustibles be covered with fire resistant cloth. The procedure requires a qualified fire watch, equipped with a suitable fire extinguisher, be present during and for 30 minutes following completion of the hot work activities.
Additional controls are currently required in the West Cable Tunnel due to an existing Appendix R exemption regarding FP-60 raceway fire barrier wrap (Reference 1). The hot work procedure includes controls for introducing hot work or ignition sources within the vicinity of the FP-60 cable wrap, the large fiberglass tank located in the southeast corner, and the Bondstrand piping in proximity to the FP-60 cable wrap. Similar requirements are being added to the procedure to ensure these additional controls are implemented for hot work in the proximity of the Hemyc wrap.
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Enclosure I to JAFP-05-0118 Fire Detection Capabilities The West Cable Tunnel (CT-1) is provided with automatic area-wide early warning smoke detection which is monitored in the Main Control Room. A postulated fire in the zone is expected to involve electrical cable insulation and is expected to be a slowly developing, high smoke-generating event. The smoke detection system is expected to actuate during the incipient stages of a fire involving electrical cable insulation and to provide an alarm in the control room.
The detection system was designed and installed in accordance with National Fire Protection Association (NFPA) standard 72D, 1979 Edition, Proprietary Signaling Systems and NFPA-72E, 1978 Edition, Automatic Detectors. In some cases the installed system does not meet the code of record. These code deviations are related to lack of electrical supervision of circuits, lack of recording of alarms, lack of qualification for environmental conditions, over loading of fire detection signaling lines, some beam pockets lacking detectors, and power supplies not meeting NFPA standards. Completed evaluations (Reference 11) determined that the code deviations do not adversely impact safety performance. The completed engineering evaluations also conclude that the detection system meets the intent of the NFPA standards and that there is no adverse impact on the operability of the system. These evaluations were reviewed and are unchanged by this exemption request.
These code deviations were previously reviewed for an Appendix R exemption and found to be acceptable as they pertain to the protection of the West Cable Tunnel (Reference 1). Additionally, compensatory measures for loss of fire detection systems protecting safety-related areas, including the system protecting the West Cable Tunnel, are established in accordance with the JAF Technical Requirements Manual (TRM).
Fire Suppression Capabilities The West Cable Tunnel (CT-1) is protected by an automatic area-wide wet pipe sprinkler system. The sprinkler system utilizes 1650 F rated sprinklers and is designed to suppress a floor based transient exposure fire. The sprinkler system in the West Cable Tunnel is designed and installed in accordance with NFPA-13, 1991 Edition, Installation of Sprinkler Systems. In addition, an in-tray automatic wet pipe water spray system, utilizing 1350 F spray nozzles, is designed and installed to suppress a tray based fire.
The water spray system meets the design requirements of NFPA-15, 1990 Edition, Water Spray Systems.
The sprinkler system is designed and installed as an Extra Hazard (Group 1) occupancy.
The system is capable of providing 0.3 gpm/ft 2 to the most hydraulically remote 2,500 ft as well as 0.15 gpm/ft 2 of cable tray horizontal area.
Water hose lines and portable fire extinguishers are available in the zone to support manual suppression activities. In the unlikely event access to hose stations within the West Cable Tunnel are blocked due to the effects of fire, hose stations located on the 272' elevation of the Administration Building could be utilized for manual suppression.
Compensatory measures are established in accordance with the TRM in the event the automatic or manual suppression systems protecting the West Cable Tunnel are out of service.
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Enclosure 1 to JAFP-05-01 18 Plant Risk The total core damage frequency for a fire in Fire Zone CT-1 was estimated as 7.21 x 1007 /yr (Reference 12). This low value is due in part to the limited amounts of transient combustibles that are brought into the zone and their low heat release rates. A review of the JAF Fire PRA database shows that neither the air handling unit (72AHU-30B), nor the cable supplying it (lABVBBKO55), are risk significant.
JUSTIFICATION FOR EXEMPTION The requested exemption satisfies the 10 CFR 50.12 criteria as stated below:
- 1. The requested exemption is authorized by law 10 CFR 50.12(a) authorizes the Nuclear Regulatory Commission to grant this exemption.
- 2. The requested exemption does not present an undue risk to the public health and safety Although the Hemyc fire barrier wrap installed in the West Cable Tunnel has less than a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> fire endurance rating, it will provide a reasonable level of resistance to fire (at least 30 minutes). The area where the fire barrier wrap is located has no significant ignition sources other than cables, has available manual suppression capability, and is equipped with automatic fire suppression and fire detection. In addition, administrative controls limit the presence of transient combustible materials and transient ignition sources. Under these circumstances, there is an adequate level of fire safety such that there is reasonable assurance that at least one means of achieving and maintaining safe shutdown conditions will remain available during and after any postulated fire in the plant.
Additionally, as discussed in the Safe Shutdown Capabilities section of this request, Air Handling Unit 72AHU-30B is required to provide proper ventilation of Battery Room B, however, loss of the AHU will not cause the immediate loss of any safety function. Per calculation (Reference 3), it will take two hours for the B Battery Room to heat up to the point it will exceed the manufacturer's qualification of the batteries.
Based on the determination that safe shutdown can be achieved with the current configuration, the requested exemption does not present an undue risk to the public health and safety. In addition, an Appendix R exemption currently exists for a fire barrier wrap located in the same vicinity of the West Cable Tunnel. Nothing in this fire area has changed since the prior exemption was reviewed and approved (Reference 1).
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Enclosure 1 to JAFP-05-0118 Similar Exemptions James A. FitzPatrick By letter dated May 29, 2001 (Reference 1) the NRC issued an exemption to JAF which permitted the use of a fire barrier wrap (FP-60) with a fire endurance rating of less than one-hour. The criteria for granting the exemption and concluding that the exemption would not pose an undue risk to the public health and safety was based on the availability of automatic detection, automatic suppression, limited fire hazards, and administrative controls.
The protected cable in question is located in the same vicinity of the West Cable Tunnel as the FP-60 cable wrap which was approved for exemption in 2001. Although the confirmatory testing results of the Hemyc ERFBS indicated that the wrap did not provide the level of protection expected for a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> fire barrier, the thermal performance exhibited by the Hemyc wrap is equivalent to the thermal performance credited in the FP-60 exemption (30 minutes).
Three Mile Island Unit I The NRC issued an exemption dated April 20, 1999 (Reference 13) which permitted the use of a fire barrier wrap with a fire endurance rating of less than one-hour. The criteria for granting the exemption and concluding that the exemption would not pose an undue risk to the public health and safety was based on the availability of automatic detection, automatic suppression, and limited fire hazards in the zone.
- 3. The requested exemption is consistent with the common defense and security The common defense and security are not affected by this exemption request.
- 4. Special circumstances are present as defined in 10 CFR 50.12(a)(2) 10 CFR 50.12(a)(2) states, in part:
T he commission will not consider granting an exemption unless special circumstances are present. Special circumstances are present whenever... (ii) Application of the regulation in the particular circumstances would not serve the underlying purpose of the rule or is not necessary to achieve the underlying purpose of the rule;..."
- 5. Underlying purpose of the rule Achieve and Maintain Hot Shutdown - IlI.G.2.c The underlying purpose of the rule is to provide reasonable assurance that at least one means of achieving and maintaining safe shutdown conditions will remain' available during and after any postulated fire. Based on the existing fire protection features in the West Cable Tunnel and the issuance of a prior Appendix R exemption (Reference 1), it can be concluded that the underlying purpose of the rule is satisfied. Accordingly, the request for an exemption from the requirements of 10 CFR Part 50, Appendix R, Section IlI.G.2.c with respect to Fire Area 1C/Fire Zone CT-1 meets the special circumstances delineated in 10 CFR Part 50.12(a)(2)(ii), i.e., the application of the regulation in these particular circumstances is not necessary to achieve the underlying purpose of the rule.
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Enclosure 1 to JAFP-05-0118 CONCLUSION The defense-in-depth objectives of the Fire Protection Program are, 1) to prevent fires from starting, 2) to detect rapidly, control and extinguish promptly those that do occur, and 3) to provide protection for structures, systems, and components important to safety so that a fire that is not promptly extinguished by the fire suppression activities will not prevent the safe shutdown of the plant. The fire hazards analysis of Fire Zone CT-1 and the existing protection of the fire wrapped cable in question show that these objectives are adequately met. Supporting the first objective is that there are no in-situ ignition sources other than cables in the area and transient ignition sources are controlled. The second objective is supported by the fact that there is a smoke detection system, general area wet pipe sprinkler system, in-tray wet pipe water spray system, and manual suppression capability. The third objective is supported by the fire wrap which provides protection from fire damage for at least 30 minutes.
This exemption request is warranted under the provisions of 10 CFR 50.12, in that it is authorized by law, does not present an undue risk to the public health and safety and is consistent with the common defense and security.
This exemption request is consistent with the objective of Appendix R, which is the ability to achieve and maintain safe shutdown during a fire. There is no need to, or safety benefit associated with, meeting the performance requirements of a one-hour fire rated barrier wrap since the use of the installed fire barrier wrap with a fire endurance rating less than one-hour has been shown to be a safe and effective means of protecting the cable and thereby achieving safe shutdown.
The information contained in this exemption request will permit the staff to complete its review of the FitzPatrick Appendix R fire protection program and issue a Safety Evaluation Report documenting their approval of the use of the installed fire barrier wrap to protect the safe shutdown capability of the plant.
The Appendix R exemptions issued by the NRC for JAF have been reviewed. The bases of these exemptions are not affected by this exemption request and will remain valid if the exemption is granted.
REFERENCES
- 1. NRC Letter and SER, Guy S. Vissing to M. Kansler (Entergy), James A. FitzPatrick Nuclear Power Plant - Exemption From Certain Requirements of Section IlI.G.2.c of Appendix R to 10 CFR Part 50 (TAC No. MB0395), May 29, 2001
- 2. JAF-RPT-FPS-01975, Safe Shutdown Analysis Report, Revision 1
- 3. Calculation 02268.5004-US(N)-005, Charger Room BR4 and Battery Room BR-3 Temperatures Based Upon Appendix R Fire in Corridor BR-5, Revision 1
- 4. NRC Memorandum from Mark H. Salley to David C. Lew, Preliminary Hemyc 1-Hour Fire Rated Electrical Raceway Fire Barrier Systems Test Data, April 6, 2005
- 5. NRC Information Notice 2005-07, Results of Hemyc Electrical Raceway Fire Barrier System Full Scale Fire Testing, April 1, 2005 8 of 10
Enclosure 1 to JAFP-05-0118
- 6. APO-76, Specification for Furnishing and Delivery of 600V Power Cable, Revision 1
- 7. JAF-RPT-04-00478, JAF Fire Hazards Analysis, Revision 0
- 8. Ebasco Letter RVR-92-11 R from R. V. Rebbapragada, Evaluation of the Flame Retardant Characteristics of Cables Installed at JAFNPP, November 20, 1992
- 9. ENN-DC-161, Transient Combustible Program, Revision 1
- 10. ENN-DC-127, Control of Hot Work and Ignition Sources, Revision 1
- 11. JAF-RPT-FPS-01532, NFPA Code Conformance Review Project Summary of Open Items, Revision 10
- 12. JAF-RPT-MISC-02211, JAF Individual Plant Examination for External Events, Revision 0
- 13. NRC Letter and SER, T. Colburn to J. Langenbach (TMI), Three Mile Island Nuclear Generating Station, Unit 1, 10 CFR Part 50 Appendix R Exemption Request (TAC No.
M97747), April 20, 1999 9 of 10
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