Letter Sequence Supplement |
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Initiation
- Request, Request, Request, Request, Request, Request, Request
- Acceptance, Acceptance, Acceptance
- Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement
Administration
- Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance
- Meeting, Meeting, Meeting
Results
Other: CNL-16-008, Update on Progress of Facility Modifications for MSIV Leak Rate, CNL-18-112, Extended Power Uprate - Flow Induced Vibration Summary Report, CNL-18-124, Extended Power Uprate - Replacement Steam Dryer Final Load Definition and Stress Reports, CNL-18-134, Extended Power Uprate - Replacement Steam Dryer Revised Analysis and Limit Curves Report, ML16085A301, ML16105A441, ML16168A026, ML16176A316
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MONTHYEARML15282A2352015-09-21021 September 2015 RHR Heat Exchange K-values Utilities in EPU Containment Analyses Project stage: Request ML15282A1812015-09-21021 September 2015 Non-Proprietary - Safety Analysis Report for Browns Ferry, Units 1, 2 and 3, Extended Power Uprate, Attachment 7 Project stage: Request ML15282A1522015-09-21021 September 2015 Submits Proposed Technical Specifications Change TS-505 - Request for License Amendments - Extended Power Uprate Project stage: Request CNL-15-249, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 1, Spent Fuel Pool Criticality Safety Analysis Information2015-12-15015 December 2015 Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 1, Spent Fuel Pool Criticality Safety Analysis Information Project stage: Supplement CNL-15-250, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 2, MICROBURN-B2 Information, Including Enclosures 2, 4, 6, and 72015-12-15015 December 2015 Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 2, MICROBURN-B2 Information, Including Enclosures 2, 4, 6, and 7 Project stage: Supplement CNL-15-261, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 3, Interconnection System Impact Study Information2015-12-18018 December 2015 Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 3, Interconnection System Impact Study Information Project stage: Supplement ML16032A0442016-02-0101 February 2016 FWS to NRC, Updated List of Threatened and Endangered Species that May Occur in Your Proposed Project Location for Browns Ferry EPU Project stage: Request ML16041A3072016-02-18018 February 2016 Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate Project stage: RAI ML16041A0222016-02-25025 February 2016 Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate Project stage: RAI ML16040A2322016-02-25025 February 2016 Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate Project stage: RAI ML16049A4632016-02-29029 February 2016 Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate Project stage: RAI CNL-16-045, Proposed Technical Specifications (Ts)Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 6, Response to Request for Additional Information2016-03-0909 March 2016 Proposed Technical Specifications (Ts)Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 6, Response to Request for Additional Information Project stage: Supplement ML16062A0722016-03-15015 March 2016 Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate Project stage: RAI CNL-16-048, Supplement 7, Responses to Requests for Additional Information, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU)2016-03-24024 March 2016 Supplement 7, Responses to Requests for Additional Information, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) Project stage: Supplement ML16084A3202016-03-25025 March 2016 Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate Project stage: RAI CNL-16-055, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 8, Response to Request for Additional Information2016-03-28028 March 2016 Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 8, Response to Request for Additional Information Project stage: Supplement ML16089A1372016-03-29029 March 2016 NRR E-mail Capture - Correction to Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate Project stage: RAI ML16064A2862016-04-0404 April 2016 Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate Project stage: RAI ML16091A0712016-04-0707 April 2016 Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate Project stage: RAI ML16085A3012016-04-11011 April 2016 Regulatory Audit Plans for April 19 - 21, 2016, Audit at Excel Facility in Rockville, Maryland, in Support of Extended Power Uprate License Amendment Request Project stage: Other ML16085A0792016-04-14014 April 2016 Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate Project stage: RAI ML16102A3392016-04-14014 April 2016 Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate Project stage: RAI CNL-16-069, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 11, Responses to Requests for Additional Information2016-04-14014 April 2016 Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 11, Responses to Requests for Additional Information Project stage: Supplement ML16104A2452016-04-20020 April 2016 Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate Project stage: RAI CNL-16-077, for Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Update (EPU) - Supplement 14, Response to Request for Additional Information2016-04-27027 April 2016 for Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Update (EPU) - Supplement 14, Response to Request for Additional Information Project stage: Supplement ML16105A4412016-04-27027 April 2016 Regulatory Audit Plan for May 10-11, 2016, Audit at Excel Facility in Rockville, Maryland, in Support of Extended Power Uprate License Amendment Request Project stage: Other CNL-16-079, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 15, Responses to Requests for Additional Information2016-05-11011 May 2016 Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 15, Responses to Requests for Additional Information Project stage: Supplement ML16124A9322016-05-12012 May 2016 Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance ML16125A4232016-05-19019 May 2016 Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance CNL-16-008, Update on Progress of Facility Modifications for MSIV Leak Rate2016-05-26026 May 2016 Update on Progress of Facility Modifications for MSIV Leak Rate Project stage: Other CNL-16-091, Brown Ferry, Units 1, 2 & 3, Responses to Requests for Additional Information and Updates Associated with Interconnection System Impact Study Modifications on Proposed Technical Specifications Change TS-505 - Request for License Amendment2016-05-27027 May 2016 Brown Ferry, Units 1, 2 & 3, Responses to Requests for Additional Information and Updates Associated with Interconnection System Impact Study Modifications on Proposed Technical Specifications Change TS-505 - Request for License Amendments Project stage: Response to RAI CNL-16-094, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 20, Responses to Requests for Additional Information2016-06-0909 June 2016 Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 20, Responses to Requests for Additional Information Project stage: Supplement ML16146A6352016-06-13013 June 2016 Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate Project stage: RAI ML16161A0642016-06-15015 June 2016 Notice of Forthcoming Closed Meeting with Tennessee Valley Authority and Its Consultant, GEH, Regarding Steam Dryers Structural Adequacy for Browns Ferry Units 1, 2 & 3 Extended Power Uprate (EPU) License Amendment Request (LAR) Project stage: Meeting CNL-16-093, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate - Supplement 19, Responses to Requests for Additional Information2016-06-17017 June 2016 Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate - Supplement 19, Responses to Requests for Additional Information Project stage: Supplement ML16154A5442016-06-21021 June 2016 Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate Project stage: RAI ML16168A0262016-06-23023 June 2016 Summary Report for the April 19 to 21, 2016 Audit in Support of Replacement Steam Dryer Review Associated to Extended Power Uprate License Amendment Request (CAC Nos. MF6741, MF6742, and MF6743) Project stage: Other CNL-16-105, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 22, Responses to Requests for Additional Information2016-06-24024 June 2016 Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 22, Responses to Requests for Additional Information Project stage: Supplement ML16125A4062016-07-0606 July 2016 Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance ML16127A6092016-07-0606 July 2016 NRC Letter Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance ML16125A0842016-07-0707 July 2016 Approval for Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance ML16130A6002016-07-0707 July 2016 Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance ML16173A0262016-07-0707 July 2016 Approval for Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance ML16176A3162016-07-11011 July 2016 Summary Report for the May 3 to May 5, 2016 Audit in Support Containment Accident Pressure Associated to Extended Power Uprate License Amendment Request Project stage: Other CNL-16-109, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 23, Miscellaneous Updates2016-07-13013 July 2016 Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 23, Miscellaneous Updates Project stage: Supplement CNL-16-119, Brown Ferry Nuclear Plant, Unit 1, 2 and 3 - Proposed Technical Specifications Change TS-505 - Request for License Amendments - Extended Power Uprate - Supplemental Information Related to Replacement Steam Dryers2016-07-13013 July 2016 Brown Ferry Nuclear Plant, Unit 1, 2 and 3 - Proposed Technical Specifications Change TS-505 - Request for License Amendments - Extended Power Uprate - Supplemental Information Related to Replacement Steam Dryers Project stage: Supplement ML16193A4602016-07-21021 July 2016 June 23, 2016, Summary of Closed Meeting with Tennessee Valley Authority Regarding the Structural Adequacy of Steam Dryers for Extended Power Uprate License Amendment Request for Browns Ferry Nuclear Plant, Units 1, 2, and 3 (MF6741, MF6742 Project stage: Meeting ML16194A2292016-07-21021 July 2016 Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate Project stage: RAI CNL-16-116, Response to Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 252016-07-27027 July 2016 Response to Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 25 Project stage: Supplement CNL-16-118, Response to Request for Additional Information on Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 272016-07-29029 July 2016 Response to Request for Additional Information on Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 27 Project stage: Supplement 2016-04-07
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Category:Letter
MONTHYEARML24032A4762024-02-0101 February 2024 Final Report of a Part 21 Evaluation Associated with Starter Contactors for the BFN Unit 1 High Pressure Coolant Injection Suppression Pool Inboard Suction Valve ML24023A2802024-01-23023 January 2024 Final Report of a Deviation or Failure to Comply Associated with a Relay in the Reactor Core Isolation Cooling Condensate Pump 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 ML24016A3042024-01-16016 January 2024 Final Report of a Part 21 Evaluation Associated with Check Valve 0-CKV-023-0565 for D1 Residual Heat Removal Service Water Pump CNL-23-071, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-472024-01-11011 January 2024 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-47 ML24022A1732024-01-0303 January 2024 Receipt and Availability of the Subsequent License Renewal Application ML23319A1992024-01-0303 January 2024 Issuance of Amendment Nos. 333, 356, and 316 Regarding the Technical Specification Surveillance Requirements 3.4.3.2 and 3.5.1.11 Regarding Safety Relief Valves ML23355A2062023-12-21021 December 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23348A3942023-12-14014 December 2023 Interim Part 21 Report of a Potential Deviation or Failure to Comply Associated with Starter Contactors for the High Pressure Coolant Injection Suppression Pool Inboard Suction Valve IR 05000259/20230102023-12-11011 December 2023 Commercial Grade Dedication Inspection Report 05000259/2023010 and 05000260/2023010 and 05000296/2023010 ML23335A0722023-12-0101 December 2023 Interim Report of a Deviation or Failure to Comply Associated with a Relay in the Unit 2 Reactor Core Isolation Cooling Condensate Pump ML23334A2492023-11-30030 November 2023 Site Emergency Plan Implementing Procedure Revision CNL-23-070, Submittal of Fifth 10-Year Interval Inservice Testing Program Plan2023-11-29029 November 2023 Submittal of Fifth 10-Year Interval Inservice Testing Program Plan ML23331A2532023-11-27027 November 2023 Summary Report for 10 CFR 50.9 Evaluations, Technical Specifications Bases Changes, Technical Requirement Manual Changes, and NRC Commitment Revisions 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 ML23325A1102023-11-21021 November 2023 Anchor Darling Double Disc Gate Valve Commitment Revision ML23320A2542023-11-16016 November 2023 Interim Part 21 Report of a Deviation or Failure to Comply Associated with Check Valve 0-CKV-023-0565 for D1 Residual Heat Removal Service Water Pump IR 05000259/20230032023-11-13013 November 2023 Integrated Inspection Report 05000259/2023003, 05000260/2023003 and 05000296/2023003 IR 05000259/20230402023-11-0202 November 2023 Supplemental Inspection Supplemental Report 05000259 2023040 and Follow-Up Assessment Letter ML23292A2532023-10-18018 October 2023 BFN 2024-301, Corporate Notification Letter (210-day Ltr) ML23282A0022023-10-0606 October 2023 Interim Part 21 Report of a Deviation or Failure to Comply Associated with Check Valve 0-CKV-023-0565 for D1 Residual Heat Removal Service Water Pump ML23278A0122023-10-0505 October 2023 Updated Final Safety Analysis Report, Amendment 30 ML23271A1702023-09-28028 September 2023 Site Emergency Plan Implementing Procedure Revision ML23270A0702023-09-26026 September 2023 SLRA Pre-Application Meeting Summary 09-13-2023 ML23257A1232023-09-22022 September 2023 Administrative Changes to Technical Specification Pages Issued for License Amendment Nos. 332, 355, and 315 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 ML23263B1042023-09-20020 September 2023 Special Report 260/2023-001 for Inoperable Post Accident Monitoring (PAM) Instrumentation ML23205A2132023-09-0808 September 2023 Issuance of Amendment Nos. 332, 355, and 315 Regarding the Revision of Technical Specifications to Adopt TSTF-566-A and TSTF-580-A, Rev. 1 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 05000259/20230052023-08-29029 August 2023 Updated Inspection Plan for Browns Ferry Nuclear Plant, Units 1, 2 and 3 - Report 05000259/2023005, 05000260/2023005 and 05000296/2023005 ML23233A0432023-08-18018 August 2023 Enforcement Action EA-22-122 Inspection Readiness Notification ML23219A1542023-08-17017 August 2023 Request to Use Later Edition of ASME Code for Operation and Maintenance and Alternative Requests BFN-IST-01 Through 05 for the Fifth 10-Year Interval Inservice Testing Program ML23228A1642023-08-16016 August 2023 Site Emergency Plan Implementing Procedure Revision ML23228A0202023-08-15015 August 2023 (BFN) Unit 1 - Special Report 259/2023-001 for Inoperable Post Accident Monitoring (PAM) Instrumentation IR 05000259/20230022023-08-10010 August 2023 Integrated Inspection Report 05000259/2023002, 05000260/2023002, 05000296/2023002 and 07200052/2023001 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 CNL-23-055, Tennessee Valley Authority - Emergency Preparedness Department Procedure Revision. Includes EPDP-3, Revision 3, Emergency Plan Exercises and Preparedness Drills2023-07-25025 July 2023 Tennessee Valley Authority - Emergency Preparedness Department Procedure Revision. Includes EPDP-3, Revision 3, Emergency Plan Exercises and Preparedness Drills ML23171A8862023-07-24024 July 2023 Issuance of Amend. Nos. 331, 354, and 314; 365 and 359 Regarding Adoption of TSTF-541-A, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position ML23201A2182023-07-20020 July 2023 Registration of Use of Cask to Store Spent Fuel (MPC-298 and -299) ML23159A2552023-07-20020 July 2023 Proposed Alternative to the Requirements of the ASME Code Regarding Volumetric Inspection of Standby Liquid Control Nozzles ML23199A3072023-07-18018 July 2023 Site Emergency Plan Implementing Procedure Revision CNL-23-053, Tennessee Valley Authority - Radiological Emergency Plan Revisions2023-07-18018 July 2023 Tennessee Valley Authority - Radiological Emergency Plan Revisions IR 05000259/20233012023-07-18018 July 2023 NRC Operator License Examination Report Nos. 05000259/2023301, 05000260/2023301, and 05000296/2023301 2024-02-01
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARCNL-23-071, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-472024-01-11011 January 2024 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-47 CNL-23-037, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request to Use a Later Edition of the American Society of Mechanical Engineers Operation and Maintenance Code and Alternative Request2023-06-0101 June 2023 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request to Use a Later Edition of the American Society of Mechanical Engineers Operation and Maintenance Code and Alternative Requests CNL-23-019, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Request for Alternative BFN-0-ISI-322023-03-11011 March 2023 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Request for Alternative BFN-0-ISI-32 CNL-22-097, Response to Request for Additional Information and Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide .2022-12-0101 December 2022 Response to Request for Additional Information and Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide . CNL-22-075, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Unit 2, Request for Alternative, BFN-21-ISI-02, Alternative to American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section Xi,.2022-09-12012 September 2022 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Unit 2, Request for Alternative, BFN-21-ISI-02, Alternative to American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section Xi,. CNL-22-065, Response to Request for Confirmation of Information and Additional Information and Second Supplement Regarding Application Requesting NRC Prior Approval of a Proposed Chilled-Water Cross-tie.2022-08-0101 August 2022 Response to Request for Confirmation of Information and Additional Information and Second Supplement Regarding Application Requesting NRC Prior Approval of a Proposed Chilled-Water Cross-tie. CNL-22-066, Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for in Support of Atrium 11 Fuel Use Supplement 3, Response to Request for Additional Information2022-07-18018 July 2022 Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for in Support of Atrium 11 Fuel Use Supplement 3, Response to Request for Additional Information CNL-22-064, Response to Request for Additional Information Regarding Tennessee Valley Authority License Amendment Request to Revise Emergency Plan Implementing Procedure Regarding Seismic Event Emergency Action Level Change2022-06-0909 June 2022 Response to Request for Additional Information Regarding Tennessee Valley Authority License Amendment Request to Revise Emergency Plan Implementing Procedure Regarding Seismic Event Emergency Action Level Change CNL-22-007, Supplement to Application Requesting NRC Prior Approval of a Proposed Chilled-Water Cross-tie Modification to Support System Operability (BFN-TS-518)2022-04-0606 April 2022 Supplement to Application Requesting NRC Prior Approval of a Proposed Chilled-Water Cross-tie Modification to Support System Operability (BFN-TS-518) CNL-22-028, Response to Request for Additional Information Regarding License Amendment Request Regarding Criticality Safety Analysis of Spent Fuel Pool Storage of Atrium 11 Fuel (TS-534)2022-03-18018 March 2022 Response to Request for Additional Information Regarding License Amendment Request Regarding Criticality Safety Analysis of Spent Fuel Pool Storage of Atrium 11 Fuel (TS-534) CNL-21-052, Response to Request for Additional Information Regarding License Amendment Request to Modify Technical Specification 3.8.6, Battery Cell Parameters (TS-531)2021-07-21021 July 2021 Response to Request for Additional Information Regarding License Amendment Request to Modify Technical Specification 3.8.6, Battery Cell Parameters (TS-531) CNL-21-033, Response to Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components2021-04-28028 April 2021 Response to Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components CNL-21-017, Response to Request for Additional Information Regarding License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into the Licensing Basis, (L-2020-LLA-0099)2020-12-29029 December 2020 Response to Request for Additional Information Regarding License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into the Licensing Basis, (L-2020-LLA-0099) CNL-20-089, Response to RAI Re Application for Tech. Specification Change Re Risk-Informed Justification for Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (BFN-TS-518)2020-12-21021 December 2020 Response to RAI Re Application for Tech. Specification Change Re Risk-Informed Justification for Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (BFN-TS-518) CNL-20-059, Response to Request for Additional Information Regarding Proposed Alternative Request No. 0-ISI-47 for the Third, Fifth, and Fourth 10-Year Inservice Inspection Intervals2020-08-10010 August 2020 Response to Request for Additional Information Regarding Proposed Alternative Request No. 0-ISI-47 for the Third, Fifth, and Fourth 10-Year Inservice Inspection Intervals CNL-19-122, Seismic Probabilistic Risk Assessment Response to NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights2019-12-17017 December 2019 Seismic Probabilistic Risk Assessment Response to NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights CNL-19-064, Response to NRC Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF)-542, Reactor Pressure Vessel Water...2019-08-0808 August 2019 Response to NRC Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF)-542, Reactor Pressure Vessel Water... CNL-19-052, Response to NRC Request for Additional Information Regarding Re-Submittal of American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Inservice Inspection (ISI) Program and Augmented Program, Second2019-07-19019 July 2019 Response to NRC Request for Additional Information Regarding Re-Submittal of American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Inservice Inspection (ISI) Program and Augmented Program, Second CNL-19-017, Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 7, Response to Requests for Additional Information2019-01-25025 January 2019 Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 7, Response to Requests for Additional Information CNL-19-007, Supplement 5, Response to Requests for Additional Information Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus2019-01-16016 January 2019 Supplement 5, Response to Requests for Additional Information Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus CNL-19-011, Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 6, Additional Operator Training Results2019-01-16016 January 2019 Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 6, Additional Operator Training Results CNL-18-139, Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Information2018-12-14014 December 2018 Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Information CNL-18-140, Response to Request for Additional Information Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 42018-12-13013 December 2018 Response to Request for Additional Information Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 4 CNL-18-117, Response to Request for Additional Information Regarding Browns Ferry Units 1, 2, and 3: Code Case N-702 for Alternative Request ISI-462018-10-17017 October 2018 Response to Request for Additional Information Regarding Browns Ferry Units 1, 2, and 3: Code Case N-702 for Alternative Request ISI-46 CNL-18-120, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant Unit 1, American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Inservice Inspection (ISI) Program, Unit 1 Second Ten-year ..2018-10-11011 October 2018 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant Unit 1, American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Inservice Inspection (ISI) Program, Unit 1 Second Ten-year ... ML18283A8972018-10-10010 October 2018 Enclosure 1: Proposed Changes to Browns Ferry Nuclear Plant Unit 1 Technical Specifications, Attachments 1, 2, & 3 CNL-18-089, Response to Request for Additional Information Regarding Decommissioning Funding Plan Update for Browns Ferry Nuclear Plant and Sequoyah Nuclear Plant Independent Spent Fuel Storage Installations, Docket Nos. 72-052 and 72-0342018-07-23023 July 2018 Response to Request for Additional Information Regarding Decommissioning Funding Plan Update for Browns Ferry Nuclear Plant and Sequoyah Nuclear Plant Independent Spent Fuel Storage Installations, Docket Nos. 72-052 and 72-034 CNL-18-044, Tennessee Valley Authority Response to NRC Request for Additional Information Related to Topical Report TVA-NPG-AWA16, TVA Overall Basin Probable Maximum Precipitation.2018-04-19019 April 2018 Tennessee Valley Authority Response to NRC Request for Additional Information Related to Topical Report TVA-NPG-AWA16, TVA Overall Basin Probable Maximum Precipitation. 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In RAI No. APLA-RAI 09, dated April 14, 2016, the NRG staff requested the licensee to explain how several human error probabilities (HEPs) were quantified for both the extended power uprate (EPU) and CL TP in order to confirm the reasonableness of these calculations and to understand why the increase in some HEPs are much larger than others. In response to APLA-RAI 09 dated April 27, 2016, the licensee discussed the quantification of these HEPs for both the EPU and CLTP. The response stated for human failure event (HFE) HFFAOASD_RCIC that "the dependency levels are higher [a medium dependency was assigned for the CL TP case and a high dependency was assigned for the EPU case] for the abandonment action due to the longer execution time and stress levels." It is not clear why the HEP for HFFAOASD_RCIC is increased by only a factor of 1.15 at the CL TP level to the EPU level, while HEP for HFEs HFA_0002RPV_LVL and HFA_OHCllNIT30 are increased by much larger factors (i.e., a factor of 2.76 and 2.04, respectively). The staff observed that the execution analysis in the Electric Power Research Institute (EPRI) human reliability analysis (HRA) calculation sheet for HFFAOASD_RCIC includes 9 procedure steps, with recovery considered only in procedure step 1. Procedure steps 2 through 9, which are considered "high" stress, did not credit recovery because of an assumption made for the HEP of each step (i.e., "it is better to use item Ref. 8a [that is a HEP value of 2.?E-04] even though it is for normal stress and then not credit a recovery step"). Not crediting recovery in procedure steps 2 through 9 for HFFAOASD_RCIC causes the HEPs associated with these steps to be the same between the CL TP and EPU. This results in a smaller increase in total HEP for HFFAOASD_RCIC, between the CLTP and EPU cases, than that had recovery been credited, potentially leading to underestimating the change in risk. When recovery is credited in each procedure step, the EPU HEP for HFFAOASD_RCIC could be 3 times larger (not 1.15 times larger as currently indicated by Attachment 44 of the EPU LAR) than that for the CL TP case. This issue may also apply to other HFEs considered in the EPU risk evaluation, such as those HFEs identified in Part 1 below. The staff requests the licensee to address the following: a. Provide the detailed HRA calculation sheets (e.g., as generated by the EPRI HRA calculator) for the following HFEs for both the CL TP and EPU cases:
- HFA_0003PMP START ("Operator fails to restart RFW [reactor feedwater] after Level 8 trip")
- HFA_0071 L8RESTART ("Operator fails to restart RCIC [reactor core isolation cooling] after Level 8 trip")
- HFA_0073L8RESTART ("Operator fails to restart HPCI [high pressure coolant injection] after Level 8 trip")
- HFFA_ 1 SHV0760540_35 ("Local action - close 1-SHV-076-0540 (2- and 3- for Units 2 and 3) within 35 minutes")
- HFFA0268480CRSTIE ("Failure to transfer deenergized 480V board to alternate supply (fire)")
- HFFAOASD_RCIC ("Operator fails to start RCIC") b. For each internal events and fire HFE considered in the EPU risk evaluation (i.e., HFEs in Tables 4-4 and 4-9 of Attachment 44 of the EPU LAR) that have a different dependency level between the CL TP and EPU cases, confirm that recovery is appropriately represented in the HFE's cognitive analysis and execution analysis such that the total HEP is realistically estimated for the CL TP and EPU cases. If it is not, then update the associated HEPs for the CL TP and EPU cases to appropriately address recovery, and provide the updated HEPs along with an explanation of how they were changed (provide sufficient detail and numerical values to understand the basis for the updated HEPs).
c. If changes were made to the HEPs in Part b of this RAI, then provide: 1. Updated risk results in Sections 5.1 ("Internal Event Results"), 5.2 ("Fire Risk Results"), and 5.6 ("Total Risk") in Attachment 44 of the EPU LAR, as applicable. If Regulatory Guide (RG) 1.17 4 risk acceptance guidelines are exceeded, then please provide a detailed justification to support the conclusion that no "special circumst.ances" are created by the proposed EPU, include a discussion of which metrics are exceeded and the conservatisms in the analysis and the risk significance of these conservatisms.
2. Updated risk results in Table 8-1 ("Summary Risk Results for the Combined Sensitivity Study") of the response to APLA-RAI 08, dated April 27, 2016. If RG 1.17 4 risk acceptance guidelines are exceeded, then provide a detailed justification to support the conclusion that no "special circumstances" are created by the proposed EPU, include a discussion of which metrics are exceeded and the conservatisms in the analysis and the risk significance of these conservatisms.
HFA_0003PMP_START-CLTP, OPERATOR FAILS TO RESTART RFW AFTER LEVEL 8 TRIP
Notes/Assumptions: Notes/Assumptions: Workload would be expected to be relatively high due to attempts to restore some source of HPI. Action primarily triggered based on monitoring RPV level, which is indicated by a variety of displays and meters.
Notes/Assumptions: Notes/Assumptions:
Notes/Assumptions: Since a transition among three procedures might be required, and the unit supervisor would be following multiple paths through the EOIs, this is treated as a case of multiple procedures. Placekeeping aids are used in the form of a bracket in which the unit supervisor initials the steps as they are reached.Notes/Assumptions:
Notes/Assumptions: Logic is straightforward, and this is a well-practiced scenario.Notes/Assumptions: There is no reason to expect other than verbatim compliance with this instruction.
HFA_0003PMP_START-EPU, OPERATOR FAILS TO RESTART RFW AFTER LEVEL 8 TRIP
Notes/Assumptions:
Notes/Assumptions: Workload would be expected to be relatively high due to attempts to restore some source of HPI. Action primarily triggered based on monitoring RPV level, which is indicated by a variety of displays and meters.Notes/Assumptions:
Notes/Assumptions: Notes/Assumptions: Since a transition among three procedures might be required, and the unit supervisor would be following multiple paths through the EOIs, this is treated as a case of multiple procedures. Placekeeping aids are used in the form of a bracket in which the unit supervisor initials the steps as they are reached.
Notes/Assumptions: Notes/Assumptions: Logic is straightforward, and this is a well-practiced scenario.
Notes/Assumptions: There is no reason to expect other than verbatim compliance with this instruction.
HFA_0071L8RESTART-CLTP, Operator fails to restart RCIC after Level 8 trip
Notes/Assumptions:
Notes/Assumptions: Workload would be expected to be relatively high due to attempts to restore some source of HPI. Action primarily triggered based on monitoring RPV level, which is indicated by a variety of displays and meters.Notes/Assumptions:
Notes/Assumptions: Notes/Assumptions: Since a transition among three procedures might be required, and the unit supervisor would be following multiple paths through the EOIs, this is treated as a case of multiple procedures. Placekeeping aids are used in the form of a bracket in which the unit supervisor initials the steps as they are reached.
Notes/Assumptions: Notes/Assumptions: Logic is straightforward, and this is a well-practiced scenario.
Notes/Assumptions: There is no reason to expect other than verbatim compliance with this instruction.
HFA_0071L8RESTART-EPU, Operator fails to restart RCIC after Level 8 trip
Notes/Assumptions:
Notes/Assumptions: Workload would be expected to be relatively high due to attempts to restore some source of HPI. Action primarily triggered based on monitoring RPV level, which is indicated by a variety of displays and meters.Notes/Assumptions:
Notes/Assumptions: Notes/Assumptions: Since a transition among three procedures might be required, and the unit supervisor would be following multiple paths through the EOIs, this is treated as a case of multiple procedures. Placekeeping aids are used in the form of a bracket in which the unit supervisor initials the steps as they are reached.
Notes/Assumptions: Notes/Assumptions: Logic is straightforward, and this is a well-practiced scenario.
Notes/Assumptions: There is no reason to expect other than verbatim compliance with this instruction.
HFA_0073L8RESTART-CLTP, Operator fails to restart HPCI after Level 8 trip
Notes/Assumptions:
Notes/Assumptions: Workload would be expected to be relatively high due to attempts to restore some source of HPI. Action primarily triggered based on monitoring RPV level, which is indicated by a variety of displays and meters.Notes/Assumptions:
Notes/Assumptions: Notes/Assumptions: Since a transition among three procedures might be required, and the unit supervisor would be following multiple paths through the EOIs, this is treated as a case of multiple procedures. Placekeeping aids are used in the form of a bracket in which the unit supervisor initials the steps as they are reached.
Notes/Assumptions: Notes/Assumptions: Logic is straightforward, and this is a well-practiced scenario.
Notes/Assumptions: There is no reason to expect other than verbatim compliance with this instruction.
HFA_0073L8RESTART-EPU, Operator fails to restart HPCI after Level 8 trip
Notes/Assumptions:
Notes/Assumptions: Workload would be expected to be relatively high due to attempts to restore some source of HPI. Action primarily triggered based on monitoring RPV level, which is indicated by a variety of displays and meters.Notes/Assumptions:
Notes/Assumptions: Notes/Assumptions: Since a transition among three procedures might be required, and the unit supervisor would be following multiple paths through the EOIs, this is treated as a case of multiple procedures. Placekeeping aids are used in the form of a bracket in which the unit supervisor initials the steps as they are reached.
Notes/Assumptions: Notes/Assumptions: Logic is straightforward, and this is a well-practiced scenario.
Notes/Assumptions: There is no reason to expect other than verbatim compliance with this instruction.
HFFA_1SHV0760540_35-CLTP, Local action - close 1-SHV-076-0540 (2- and 3- for Units 2 and 3) within 35 minutes
Notes/Assumptions: Notes/Assumptions:
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HFFA_1SHV0760540_35-EPU, Local action - close 1-SHV-076-0540 (2- and 3- for Units 2 and 3) within 35 minutes
Notes/Assumptions: Notes/Assumptions:
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HFFA0268480CRSTIE-CLTP, FAILURE TO TRANSFER DEENERGIZED 480V BOARD TO ALTERNATE SUPPLY (FIRE)
Notes/Assumptions: Notes/Assumptions: Workload would be expected to be relatively high, but response should be triggered by alarm, and does not require monitoring over time.
Notes/Assumptions: Notes/Assumptions:
Notes/Assumptions: As the operators are in the fire procedures and the ARP's, multiple procedures always apply to fire scenarios. The step in the ARP is not graphically distinct, but there is a checkbox as a placekeeping aid.Notes/Assumptions:
Notes/Assumptions: Logic is straightforward, and should lead to a clear decision to restore power.Notes/Assumptions: There is no reason to expect other than verbatim compliance with this instruction.
HFFA0268480CRSTIE-EPU, FAILURE TO TRANSFER DEENERGIZED 480V BOARD TO ALTERNATE SUPPLY (FIRE)
Notes/Assumptions: Notes/Assumptions: Workload would be expected to be relatively high, but response should be triggered by alarm, and does not require monitoring over time.
Notes/Assumptions: Notes/Assumptions:
Notes/Assumptions: As the operators are in the fire procedures and the ARP's, multiple procedures always apply to fire scenarios. The step in the ARP is not graphically distinct, but there is a checkbox as a placekeeping aid.Notes/Assumptions:
Notes/Assumptions: Logic is straightforward, and should lead to a clear decision to restore power.Notes/Assumptions: There is no reason to expect other than verbatim compliance with this instruction.
HFFA0ASD_RCIC-CLTP , OPERATOR FAILS TO START RCIC
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HFFA0ASD_RCIC-EPU, OPERATOR FAILS TO START RCIC
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