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Category:License-Operating (New/Renewal/Amendments) DKT 50
MONTHYEARML24172A2502024-07-29029 July 2024 – Issuance of Amendment No. 233 Adoption of 10 CFR 50.69, “Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors” ML24176A1202024-07-29029 July 2024 Issuance of Amendment 234 Revision to Technical Specifications to Adopt TSTF-505, Revision 2, “Provide Risk-Informed Extended Completion Times – RITSTF Initiative 4b” ML22342B2802022-12-28028 December 2022 Issuance of Amendments Adoption of TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling, Revision 1 ML22104A2222022-05-12012 May 2022 Issuance of Amendments Revise Technical Specifications to Adopt TSTF 554 ML22083A1242022-04-28028 April 2022 Arkansas, Units 1 and 2; Grand Gulf Nuclear Station; River Bend Station; and Waterford Steam Electric Station - Issuance of Amendments Revise Technical Specifications to Adopt TSTF-541, Revision 2 ML21146A0182021-06-0808 June 2021 Issuance of Amendments to Adopt TSTF 563, Revision 0, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program ML21040A2922021-03-0404 March 2021 Issuance of Amendments Adoption of TSTF 501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control ML21019A2192021-02-24024 February 2021 Issuance of Amendment No. 227 Extension of Appendix J Integrated Leakage Test Interval ML21011A0682021-02-0202 February 2021 Issuance of Amendments Adoption of TSTF 439, Revision 2, Eliminate Second Completion Times Limiting Time from Discovery of Failure ML21011A0482021-02-0101 February 2021 Issuance of Amendments Adoption of TSTF-566, Revision 0, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems ML20101G0542020-04-15015 April 2020 Issuance of Amendment No. 224 One Cycle Extension of Appendix J Integrated Leakage Test and Drywell Bypass Test Interval (Exigent Circumstances) ML19308B1072019-12-11011 December 2019 Issuance of Amendments Adoption of Technical Specifications Task Force Traveler TSTF-564, Revision 2, Safety Limit MCPR (Minimum Critical Power Ratio) ML19175A0422019-09-11011 September 2019 Arkansas Units 1 and 2; Grand Gulf, Unit 1; Indian Point 2 and 3; Palisades; River Bend, Unit 1; Waterford Unit 3 - Issuance of Amendments to Adopt TSTF-529, Clarify Use and Application Rules ML19123A0142019-06-18018 June 2019 Issuance of Amendment No. 220, Request to Revise Updated Final Safety Analysis Report to Incorporate Tornado Missile Risk Evaluator Methodology Into Licensing Basis ML19094A7992019-06-11011 June 2019 Issuance of Amendment No. 219 to Revise Technical Specifications to Adopt Technical Specification Task Force Traveler TSTF-425, Relocate Surveillance Frequencies to Licensee Control-RITSTF Initiative 5B ML19084A2182019-05-23023 May 2019 Issuance of Amendment No. 218 to Revise Technical Specification to Adopt Technical Specification Task Force Traveler TSTF-542, Reactor Pressure Vessel Water Inventory Control ML19025A0232019-03-12012 March 2019 Issuance of Amendment No. 216 to Revise Emergency Action Levels to a Scheme Based on NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors ML18215A1962019-03-12012 March 2019 Issuance of Amendment No. 217 to Modify the Updated Safety Analysis Report to Replace Turbine First Stage Pressure Signals with Power Range Neutron Monitoring System Signals ML18306A5132018-11-30030 November 2018 Issuance of Conforming Amendment Nos. 262, 312 and 215 Transfers of Renewed Facility Operating Licenses ML17240A2322017-10-0404 October 2017 Grand Gulf Nuclear Station, Unit 1 - Issuance of Amendment No. 213 for Administrative Name Change to Licensee South Mississippi Electric Power Association (CAC No. MF9588) ML17116A0322017-06-0707 June 2017 Grand Gulf Nuclear Station, Unit 1 - Issuance of Amendment No. 212 to Adopt Technical Specifications Task Force-427, Allowance For Non-Technical Specification Barrier Degradation on Supported System Operability (CAC No. MF8692.) ML16243A0242016-12-0808 December 2016 Record of Decision - License Renewal Application for Grand Gulf Nuclear Station, Unit 1 ML16292A4622016-12-0101 December 2016 Renewed Facility Operating License for Grand Gulf Nuclear Station, Unit 1 ML16140A1332016-08-0404 August 2016 Issuance of Amendment Revision of Technical Specifications to Remove Inservice Testing Program and Clarify Surveillance Requirement Usage Rule Application ML16132A1942016-05-26026 May 2016 Correction to Amendment No. 207, Request for Changing Five Technical Specifications Allowable Levels ML16119A1482016-05-25025 May 2016 Issuance of Amendment No. 210 Re. Cyber Security Plan Milestone 8 Full Implementation Schedule ML16011A2472016-02-17017 February 2016 Issuance of Amendment No. 209 Revision of Technical Specifications for Containment Leak Rate Testing ML15336A2562015-12-17017 December 2015 Issuance of Amendment No. 208 Adoption of Technical Specification Task Force Traveler TSTF-522 ML15229A2192015-08-31031 August 2015 Redacted, Issuance of Amendment Maximum Extended Load Line Limit Analysis Plus License Amendment Request ML15195A3552015-08-31031 August 2015 Issuance of Amendment Request for Changing Five Technical Specifications Allowable Values ML15180A1702015-08-31031 August 2015 Issuance of Amendment Revision to Technical Specification 5.65.B to Add Reference NEDC-33075P-A, GE Hitachi Boiling Water Reactor Detect and Suppress Solution - Confirmation Density ML15229A2132015-08-18018 August 2015 Redacted, Issuance of Amendment Regarding Technical Specification 2.1.1.2 of Technical Specification Section 2.1.1.2, Reactor SLs (Safety Limits) ML15229A2182015-08-18018 August 2015 Redacted, Issuance of Amendment Adoption of Single Fluence Methodology ML15104A6232015-05-12012 May 2015 Issuance of Amendment Adoption of Technical Specifications Task Force Standard Technical Specifications Change Traveler TSTF-523 ML14311A4792014-12-12012 December 2014 Issuance of Amendment No. 200, Revise Operating License Condition for Change to Cyber Security Plan Milestone 8 Full Implementation Date ML14162A3782014-09-25025 September 2014 Redacted, Issuance of Amendment No. 199, Delete Operating License Condition 2.C(32), Partial Feedwater Heating, to Allow Plant to Operate with Final Feedwater Temperature Reduction at End of Fuel Cycle ML14106A1332014-06-30030 June 2014 Issuance of Amendment No. 198, Request to Adopt TSTF-535, Revision 0, Revise Shutdown Margin Definition to Address Advanced Fuel Designs, as Part of Consolidated Line Item Improvement Process ML13343A1092013-12-26026 December 2013 Issuance of Amendment No. 197, Revise Technical Specifications and Surveillance Requirements to Support Operation with 24-Month Fuel Cycle in Accordance with Generic Letter 91-04 ML13261A3492013-09-25025 September 2013 Issuance of Amendment No. 196, Modify Updated Final Safety Analysis Report to Revise the Methodology for Standby Service Water Passive Failure ML13261A2642013-09-25025 September 2013 Redacted Version, Issuance of Amendment No. 195, Revise Criticality Safety Analysis and Technical Specification 4.3.1, Criticality, and Delete Spent Fuel Pool Loading Criteria License Condition ML13157A0292013-08-0505 August 2013 Issuance of Amendment No. 194, Revise TS Table 3.3.6.1-1 to Support Correction of Non-Conservative Allowable Value for Primary Containment and Drywell Isolation Instrumentation ML13025A3062013-03-14014 March 2013 ANO 1 & 2, Big Rock, FitzPatrick, GGNS, Indian Point 1, 2 & 3, Palisades, Pilgrim, RBS, Vermont Yankee, and Waterford - Correction to Amendments Issued on 12/28/12, Revise QA Program Manual and Staff Qualification Technical Specifications ML12240A2392012-12-0505 December 2012 Issuance of Amendment No. 192, Revise Physical Protection License Condition Related to Milestone 6 of the Cyber Security Plan Implementation ML1208601492012-05-11011 May 2012 Issuance of Amendment No. 190, Revise Technical Specification 3.1.7, Standby Liquid Control (SLC) System, to Support Use of Sodium Pentaborate Solution Enriched with Boron-10 Isotope ML1207202832012-04-20020 April 2012 Issuance of Amendment No. 189, Revise Minimum Critical Power Ratio Safety Limit in Technical Specification 2.1.1.2 for Two-Loop and Single Recirculation Loop ML1117306812011-09-12012 September 2011 Issuance of Amendment No. 187, Revise Technical Specifications to Adopt TSTF-514, Revision 3, Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation ML1119401652011-07-27027 July 2011 Issuance of Amendment No. 186, Revise License Condition and Approval of Cyber Security Plan and Associated Implementation Schedule ML1107304022011-04-27027 April 2011 Issuance of Amendment No. 185, Revise Surveillance Requirement Notes in Technical Specifications Associated with Condensate Storage Tank Level-Low as Reflected in TSTF-493 ML0909804292009-04-13013 April 2009 Correction to Amendment No. 182, Surveillance Requirements for Diesel Generator Slow - Start Testing (MD9641) ML0817600232008-10-14014 October 2008 Issuance of Amendment No. 178, Adoption of Technical Specifications Task Force (TSTF) Traveler No. 448, Revision 3, Control Room Envelope Habitability. 2024-07-29
[Table view] Category:Memoranda
MONTHYEARML24128A2402024-05-0808 May 2024 Entergy Operations, Inc. - Entergy Fleet Project Manager Assignment ML23047A3822023-03-21021 March 2023 Summary of December 15, 2022 Periodic Advanced Reactor Stakeholder Public Meeting ML22147A0932022-06-0606 June 2022 2021 Annual Assessment Public Meeting Summary ML22034A3932022-02-16016 February 2022 Calendar Year 2021 Security Baseline Completion Memo ML21295A0882021-10-21021 October 2021 Fiscal Year 2021 Research and Test Reactors Inspection Program Completion Status ML21181A3352021-07-0101 July 2021 June 23, 2021, Summary of Public Meeting to Discuss Technology Inclusive Content of Application Project ML21158A2232021-06-0808 June 2021 Meeting Summary for Ticap Workshop 3 ML21132A2952021-05-14014 May 2021 Summary of Public Meeting to Discuss Technology Inclusive Content of Application Project ML20150A4212020-11-23023 November 2020 Memo to File: Environmental Assessment and Finding of No Significant Impact and NRC Financial Analysis for Entergy Nuclear Company, LLC Decommissioning Funding Plan Submitted in Accordance with 10 CFR 72.30(b) and (C) for Grand Gulf ISFSI ML20218A7512020-08-0707 August 2020 Summary of June 25, 2020 Teleconference with Grand Gulf Nuclear Station ML19182A3562019-07-23023 July 2019 Quarterly Report on the Status of Public Petitions Under Title 10 of the Code of Federal Regulations, Section 2.206 - April 1 to June 30, 2019 ML19204A1492019-07-16016 July 2019 FEMA Region IV Memo 07-16-19: Hurricane Barry Preliminary Capabilities Assessment ML19204A1482019-07-15015 July 2019 FEMA Region VI Memo 07-15-19: Hurricane Barry Preliminary Capabilities Assessment ML19018A2692019-03-12012 March 2019 Safety Evaluation Input for Grand Gulf Nuclear Station Unit 1, License Amendment Request to Implement Technical Specification Task Force-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control ML18173A0082018-06-20020 June 2018 Cancelling Numerous Inspection Report Numbers ML16287A5902016-11-17017 November 2016 Renewal of Full-Power Operating Licenses for Grand Gulf Nuclear Station Unit 1 (TAC No. ME7493) ML16294A2072016-10-27027 October 2016 Communications Plan Regarding the Renewal of the Grand Gulf Nuclear Station Unit 1, Operating License ML16210A5262016-07-28028 July 2016 License Renewal Application ML16067A2402016-03-31031 March 2016 Advisory Committee on Reactor Safeguards Review of the Grand Gulf Nuclear Station, Unit 1, License Renewal Application - Transmittal of Final Safety Evaluation Report ML16088A2042016-03-28028 March 2016 Memo T Bowers from s Ruffin, Technical Assistance Requests - Review 2015 Tri-Annual Decommissioning Funding Plans for Multiple Independent Spent Fuel Storage Installations W/ Encl 2 (Template) ML16088A2052016-03-28028 March 2016 Enclosure 1 - (72.30 DFP Reviews to Be Completed 2015) - Memo T Bowers from s Ruffin, Technial Assistance Requests - Review 2015 Tri-Annual Decommissioning Funding Plans for Multiple Independent Spent Fuel Storage Installations ML15324A0862015-11-24024 November 2015 Summary of Conference Call Confirming Staff Understanding of Basis for Closing Open Item in Grand Gulf Reevaluated Flood Hazard Staff Assessment of Response to 10 CFR 50.54(f) Information Request- Flood Causing Mechanism Reevaluation ML15195A3552015-08-31031 August 2015 Issuance of Amendment Request for Changing Five Technical Specifications Allowable Values ML14163A7302014-06-12012 June 2014 Supplemental Inspection Charter to Evaluate Licensee Actions Related to Pi for Unplanned Scrams Per 7000 Critical Hours, Which Crossed Green-White Threshold During First Quarter 2013 ML14043A1102014-02-28028 February 2014 01/29/2014 Summary of Public Meetings to Discuss Draft Supplement 50 to the Generic Environmental Impact Statement for License Renewal of Nuclear Plants Regarding Grand Gulf, Unit 1, (TAC Nos ME7385 and ME7386) ML13207A0462013-07-26026 July 2013 EA-13-058 Teleconference Notice ML13182A4262013-07-0202 July 2013 Notice of Forthcoming Meeting with Entergy Operations, Inc., for a Predecisional Enforcement Conference Related to the Grand Gulf Nuclear Station (EA-13-058) ML12334A5862013-01-0303 January 2013 Summary of Telephone Conference Call Held on October 9, 2012, Between the U.S. Nuclear Regulatory Commission and Entergy Operations, Inc., Concerning Requests for Additional Information Pertaining to the Grand Gulf Nuclear Station ML12264A6492012-11-15015 November 2012 Summary of Telephone Conference Call Held on August 29, 2012, Between the NRC and Entergy, Concerning RAI Pertaining to the Grand Gulf Nuclear Station, LRA ML12264A3922012-11-0909 November 2012 Summary of Telephone Conference Call Held on 9/04/12 Between the Us NRC and Entergy Operations, Inc. Concerning Requests for Additional Information Pertaining to the Grand Gulf Nuclear Station, License Renewal Application ML12202A2142012-08-15015 August 2012 5/30/12 Summary of Telephone Conference Call Held Between the U.S. Nuclear Regulatory Commission and Entergy Operations, Inc., Concerning Requests for Additional Information Pertaining to the Grand Gulf Nuclear Station, LRA ML1213804832012-05-22022 May 2012 Memo to File, Verbal Authorization of Relief Request ISI-17, Use of ASME Code Cases N-638-4 and N-504-4 for Alternative Repair of RHR LPCI Weld During Refueling Outage RF-18, Third 10-Year Inservice Inspection Interval ML1201303402012-01-18018 January 2012 1/30/2012-Notice of Forthcoming Meeting with Entergy Operations, Inc., to Discuss Schedule for Completion of Steam Dryer Review Related to Grand Gulf Nuclear Station, Unit 1, Extended Power Uprate ML11362A4332012-01-0606 January 2012 Forthcoming Meeting to Discuss the License Renewal Process and Environmental Scoping for Grand Gulf Nuclear Station, Unit 1, License Renewal Application ML11333A2452011-11-29029 November 2011 Acceptance of License Renewal Application, Grand Gulf Nuclear Station, Unit 1 ML1115704052011-06-0606 June 2011 Notice of Meeting with Entergy Operations, Inc., to Discuss Implementation of Quality Oversight and Verification Programs at Entergy Sites Including Actions Being Taken to Enhance Effectiveness ML1107504052011-03-21021 March 2011 Notice of Meeting with Entergy Operations, Inc., to Discuss Fleetwide Submittal for Proposed Technical Specification and Quality Assurance Program Manual Changes Related to Unit Staff Qualification Requirements ML1029401582010-11-0505 November 2010 Acceptance of License Amendment Request for an Extended Power Uprate (Epu), Grand Gulf Nuclear Station, Unit 1 ML0914701272009-06-0303 June 2009 Memo to Michael T. Lesar from John Goshen Federal Register Notice Publishing an Environmental Assessment and Finding of No Significant Impact for a Request for an Exemption from 10 CFR 72.212(a)(2) and 10 CFR 72.212(b)(7) ML0807400842008-03-14014 March 2008 Draft Regulatory Guide for Comment ML0614505922006-05-26026 May 2006 Wits 200600198 - Actions to Be Taken in Response to Hurricane Lessons Learned Task Report ML0607302642006-03-0707 March 2006 Closure Memorandum: Issue for Resolution 2005-083: Evaluation: Part 21 - Engine Systems - Governor Drive Coupling Element ML0516003452005-06-14014 June 2005 Draft Information Memo - May 6 - May 27, 2005 ML0506104872005-03-23023 March 2005 Draft Information Memo - May 1, 2005 Thru May 27, 2005 ML0429402412004-10-25025 October 2004 Draft Information for June 1, 2004 to June 30, 2004 ML0423804012004-08-27027 August 2004 Draft Information Memo for April 1, 2004 to April 30, 2004 - Marilyn R. Wohl ML0422602762004-08-12012 August 2004 Meeting Summary of the August 8, 2004 Public Workshop - Region IV Operator Licensing Feedback ML0408607972004-03-25025 March 2004 Memo to John Harris Re Correction of License Authority Files for Grand Gulf, Unit 1 ML0402202322004-02-23023 February 2004 Draft Information Report for October 3, 2003, to November 24, 2003 ML0330102972003-11-0707 November 2003 Draft Information for August 4, 2003, to October 2, 2003 2024-05-08
[Table view] Category:Safety Evaluation
MONTHYEARML24172A2502024-07-29029 July 2024 – Issuance of Amendment No. 233 Adoption of 10 CFR 50.69, “Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors” ML24176A1202024-07-29029 July 2024 Issuance of Amendment 234 Revision to Technical Specifications to Adopt TSTF-505, Revision 2, “Provide Risk-Informed Extended Completion Times – RITSTF Initiative 4b” ML23270B9932023-09-29029 September 2023 Request to Update ASME Boiler & Pressure Vessel Code Relief Request SE with NRC-Approved Revision of Bwrip Guidelines (GG-ISI-020 & RBS-ISI-019) (EPID L-2022-LLR-0090) - Non-Proprietary ML23117A2172023-05-0101 May 2023 Safety Evaluation for Quality Assurance Program Manual Reduction in Commitment ML22342B2802022-12-28028 December 2022 Issuance of Amendments Adoption of TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling, Revision 1 ML22104A2222022-05-12012 May 2022 Issuance of Amendments Revise Technical Specifications to Adopt TSTF 554 ML22083A1242022-04-28028 April 2022 Arkansas, Units 1 and 2; Grand Gulf Nuclear Station; River Bend Station; and Waterford Steam Electric Station - Issuance of Amendments Revise Technical Specifications to Adopt TSTF-541, Revision 2 ML22007A3172022-01-18018 January 2022 1, River Bend Station 1, and Waterford Steam Electric Station 3 - Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI ML21294A0672021-10-28028 October 2021 Inservice Testing Program Relief Request VRR-GGNS-2021-1, Alternative Request for Pressure Isolation Valve Testing Frequency ML21258A4082021-09-21021 September 2021 Request to Update ASME Code Relief Request Safety Evaluations with NRC-Approved Revision of Boiling Water Reactor Vessel and Internals Project Guidelines ML21146A0182021-06-0808 June 2021 Issuance of Amendments to Adopt TSTF 563, Revision 0, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program ML21040A2922021-03-0404 March 2021 Issuance of Amendments Adoption of TSTF 501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control ML21019A2192021-02-24024 February 2021 Issuance of Amendment No. 227 Extension of Appendix J Integrated Leakage Test Interval ML21011A0682021-02-0202 February 2021 Issuance of Amendments Adoption of TSTF 439, Revision 2, Eliminate Second Completion Times Limiting Time from Discovery of Failure ML21011A0482021-02-0101 February 2021 Issuance of Amendments Adoption of TSTF-566, Revision 0, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems ML20226A2722020-08-18018 August 2020 Request to Use a Provision of a Later Edition of the ASME BPV Code, Section XI ML20101G0542020-04-15015 April 2020 Issuance of Amendment No. 224 One Cycle Extension of Appendix J Integrated Leakage Test and Drywell Bypass Test Interval (Exigent Circumstances) ML19308B1072019-12-11011 December 2019 Issuance of Amendments Adoption of Technical Specifications Task Force Traveler TSTF-564, Revision 2, Safety Limit MCPR (Minimum Critical Power Ratio) ML19266A5862019-10-11011 October 2019 Relief Request GG-ISI-023, Examination Coverage of Class 1 Piping and Vessel Welds ML19254A6032019-09-19019 September 2019 Units 2 and 3; Palisades Nuclear Plant; River Bend; and Waterford Steam Electric Station, Unit 3 - Relief Request No. EN-19-RR-1, Use of ASME Code Case N-831-1 ML19175A0422019-09-11011 September 2019 Arkansas Units 1 and 2; Grand Gulf, Unit 1; Indian Point 2 and 3; Palisades; River Bend, Unit 1; Waterford Unit 3 - Issuance of Amendments to Adopt TSTF-529, Clarify Use and Application Rules ML19123A0142019-06-18018 June 2019 Issuance of Amendment No. 220, Request to Revise Updated Final Safety Analysis Report to Incorporate Tornado Missile Risk Evaluator Methodology Into Licensing Basis ML19094A7992019-06-11011 June 2019 Issuance of Amendment No. 219 to Revise Technical Specifications to Adopt Technical Specification Task Force Traveler TSTF-425, Relocate Surveillance Frequencies to Licensee Control-RITSTF Initiative 5B ML19084A2182019-05-23023 May 2019 Issuance of Amendment No. 218 to Revise Technical Specification to Adopt Technical Specification Task Force Traveler TSTF-542, Reactor Pressure Vessel Water Inventory Control ML19018A2692019-03-12012 March 2019 Safety Evaluation Input for Grand Gulf Nuclear Station Unit 1, License Amendment Request to Implement Technical Specification Task Force-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control ML19025A0232019-03-12012 March 2019 Issuance of Amendment No. 216 to Revise Emergency Action Levels to a Scheme Based on NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors ML18215A1962019-03-12012 March 2019 Issuance of Amendment No. 217 to Modify the Updated Safety Analysis Report to Replace Turbine First Stage Pressure Signals with Power Range Neutron Monitoring System Signals ML18128A0672018-06-0808 June 2018 Arkansas, Units 1 and 2; Grand Gulf, Unit 1; Indian Point Unit Nos. 2 and 3; Palisades; Pilgrim; River Bend Station, Unit 1; and Waterford, Unit-3 Relief Request No. EN-17-RR-1, Alternative to Use ASME Code Case N-513-4 ML17285A7942017-10-30030 October 2017 Grand Gulf Nuclear Station, Unit 1 - Relief Request GG-ISI-021 Proposing An Alternative For Fourth Ten Year Inservice Inspection Program (CAC NO. MF9752; EPID L-2017-LLR-0031) ML17240A2322017-10-0404 October 2017 Grand Gulf Nuclear Station, Unit 1 - Issuance of Amendment No. 213 for Administrative Name Change to Licensee South Mississippi Electric Power Association (CAC No. MF9588) ML17235A5332017-08-31031 August 2017 Relief Request GG-ISI-022 to Allow Use of Later Editions and Addenda of American Society of Mechanical Engineers Code for Inservice Inspection ML17116A0322017-06-0707 June 2017 Grand Gulf Nuclear Station, Unit 1 - Issuance of Amendment No. 212 to Adopt Technical Specifications Task Force-427, Allowance For Non-Technical Specification Barrier Degradation on Supported System Operability (CAC No. MF8692.) ML16278A0172016-10-19019 October 2016 Entergy Fleet Relief Request RR-EN-ISI-15-1, Alternative to Maintain Inservice Inspection Related to Activities to the 2001 Edition/2003 Addendum of ASME Section XI Code ML16253A3222016-09-27027 September 2016 Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 ML16251A6202016-09-13013 September 2016 Entergy Fleet Request for Approval of Change to the Entergy Quality Assurance Program Manual (CAC Nos. MF7086 - MF7097) ML16140A1332016-08-0404 August 2016 Issuance of Amendment Revision of Technical Specifications to Remove Inservice Testing Program and Clarify Surveillance Requirement Usage Rule Application ML16160A0922016-06-16016 June 2016 Relief Request GG-IST-2015-1 Related to the Inservice Testing Program ML16096A2692016-06-0606 June 2016 Arkansas; Grand Gulf; James A. Fitzpatrick; Indian Point; Palisades; Pilgrim; River Bend; and Waterford - Relief Request RR-EN-15-2, Proposed Alternative to Use ASME Boiler and Pressure Vessel Code Case N-786-1 ML16093A0282016-05-31031 May 2016 Entergy Services, Inc., Proposed Alternative to Utilize ASME Code Case N-789-1, Relief Request RR-EN-15-1, Revision 1 ML16119A1482016-05-25025 May 2016 Issuance of Amendment No. 210 Re. Cyber Security Plan Milestone 8 Full Implementation Schedule ML16011A2472016-02-17017 February 2016 Issuance of Amendment No. 209 Revision of Technical Specifications for Containment Leak Rate Testing ML15336A2562015-12-17017 December 2015 Issuance of Amendment No. 208 Adoption of Technical Specification Task Force Traveler TSTF-522 ML15195A3552015-08-31031 August 2015 Issuance of Amendment Request for Changing Five Technical Specifications Allowable Values ML15229A2192015-08-31031 August 2015 Redacted, Issuance of Amendment Maximum Extended Load Line Limit Analysis Plus License Amendment Request ML15180A1702015-08-31031 August 2015 Issuance of Amendment Revision to Technical Specification 5.65.B to Add Reference NEDC-33075P-A, GE Hitachi Boiling Water Reactor Detect and Suppress Solution - Confirmation Density ML15229A2132015-08-18018 August 2015 Redacted, Issuance of Amendment Regarding Technical Specification 2.1.1.2 of Technical Specification Section 2.1.1.2, Reactor SLs (Safety Limits) ML15229A2182015-08-18018 August 2015 Redacted, Issuance of Amendment Adoption of Single Fluence Methodology ML15104A6232015-05-12012 May 2015 Issuance of Amendment Adoption of Technical Specifications Task Force Standard Technical Specifications Change Traveler TSTF-523 ML14311A4792014-12-12012 December 2014 Issuance of Amendment No. 200, Revise Operating License Condition for Change to Cyber Security Plan Milestone 8 Full Implementation Date ML14162A3782014-09-25025 September 2014 Redacted, Issuance of Amendment No. 199, Delete Operating License Condition 2.C(32), Partial Feedwater Heating, to Allow Plant to Operate with Final Feedwater Temperature Reduction at End of Fuel Cycle 2024-07-29
[Table view] Category:Technical Specifications
MONTHYEARML23348A3572023-12-14014 December 2023 Application to Revise Technical Specifications to Use Online Monitoring Methodology Slides and Affidavit for Pre-Submittal Meeting ML22342B2802022-12-28028 December 2022 Issuance of Amendments Adoption of TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling, Revision 1 ML22104A2222022-05-12012 May 2022 Issuance of Amendments Revise Technical Specifications to Adopt TSTF 554 ML22073A1752022-03-0808 March 2022 Updated Final Safety Analysis Report, Chapter 16, Technical Specifications ML21279A2312021-10-0606 October 2021 Application to Revise Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements Using the Consolidated Line-Item Improvement ML21019A2192021-02-24024 February 2021 Issuance of Amendment No. 227 Extension of Appendix J Integrated Leakage Test Interval ML21011A0482021-02-0101 February 2021 Issuance of Amendments Adoption of TSTF-566, Revision 0, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems ML21039A3292021-01-27027 January 2021 Updated Final Safety Analysis Report, Chapter 16, Technical Specifications ML21039A2642021-01-27027 January 2021 Updated Final Safety Analysis Report, Chapter 16, Technical Specifications ML19308B1072019-12-11011 December 2019 Issuance of Amendments Adoption of Technical Specifications Task Force Traveler TSTF-564, Revision 2, Safety Limit MCPR (Minimum Critical Power Ratio) ML19175A0422019-09-11011 September 2019 Arkansas Units 1 and 2; Grand Gulf, Unit 1; Indian Point 2 and 3; Palisades; River Bend, Unit 1; Waterford Unit 3 - Issuance of Amendments to Adopt TSTF-529, Clarify Use and Application Rules ML17240A2322017-10-0404 October 2017 Grand Gulf Nuclear Station, Unit 1 - Issuance of Amendment No. 213 for Administrative Name Change to Licensee South Mississippi Electric Power Association (CAC No. MF9588) ML16011A2472016-02-17017 February 2016 Issuance of Amendment No. 209 Revision of Technical Specifications for Containment Leak Rate Testing GNRO-2015/00091, Supplemental Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications for Containment Leak Rate Testing/2015-12-10010 December 2015 Supplemental Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications for Containment Leak Rate Testing/ GNRO-2015/00077, Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt Technical Specification Task Force (TSTF) TSTF-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours.2015-11-24024 November 2015 Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt Technical Specification Task Force (TSTF) TSTF-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours. GNRO-2015/00037, Application to Revise the Technical Specifications to Remove the Inservice Testing Program and to Clarify SR Usage Rule Application to Section 5.5 Testing2015-09-15015 September 2015 Application to Revise the Technical Specifications to Remove the Inservice Testing Program and to Clarify SR Usage Rule Application to Section 5.5 Testing ML15180A1702015-08-31031 August 2015 Issuance of Amendment Revision to Technical Specification 5.65.B to Add Reference NEDC-33075P-A, GE Hitachi Boiling Water Reactor Detect and Suppress Solution - Confirmation Density ML15195A3552015-08-31031 August 2015 Issuance of Amendment Request for Changing Five Technical Specifications Allowable Values ML15229A2192015-08-31031 August 2015 Redacted, Issuance of Amendment Maximum Extended Load Line Limit Analysis Plus License Amendment Request ML15229A2132015-08-18018 August 2015 Redacted, Issuance of Amendment Regarding Technical Specification 2.1.1.2 of Technical Specification Section 2.1.1.2, Reactor SLs (Safety Limits) ML15229A2182015-08-18018 August 2015 Redacted, Issuance of Amendment Adoption of Single Fluence Methodology GNRO-2015/00059, Submits Corrected Technical Specification Pages Regarding Maximum Extended Load Line Limit Plus License Amendment Request, Dated 9/25/20132015-08-14014 August 2015 Submits Corrected Technical Specification Pages Regarding Maximum Extended Load Line Limit Plus License Amendment Request, Dated 9/25/2013 GNRO-2015/00026, Application to Revise Technical Specifications for Permanent Extension of Type C Leak Rate Testing Frequency and Reduction of Type B and C Grace Intervals2015-05-27027 May 2015 Application to Revise Technical Specifications for Permanent Extension of Type C Leak Rate Testing Frequency and Reduction of Type B and C Grace Intervals ML15104A6232015-05-12012 May 2015 Issuance of Amendment Adoption of Technical Specifications Task Force Standard Technical Specifications Change Traveler TSTF-523 GNRO-2014/00078, Application to Revise Technical Specifications to Adopt TSTF-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month2014-12-15015 December 2014 Application to Revise Technical Specifications to Adopt TSTF-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month ML14311A4792014-12-12012 December 2014 Issuance of Amendment No. 200, Revise Operating License Condition for Change to Cyber Security Plan Milestone 8 Full Implementation Date GNRO-2014/00068, License Amendment Request to Revise Technical Specification 2.1.1.22014-11-21021 November 2014 License Amendment Request to Revise Technical Specification 2.1.1.2 ML14162A3782014-09-25025 September 2014 Redacted, Issuance of Amendment No. 199, Delete Operating License Condition 2.C(32), Partial Feedwater Heating, to Allow Plant to Operate with Final Feedwater Temperature Reduction at End of Fuel Cycle ML14106A1332014-06-30030 June 2014 Issuance of Amendment No. 198, Request to Adopt TSTF-535, Revision 0, Revise Shutdown Margin Definition to Address Advanced Fuel Designs, as Part of Consolidated Line Item Improvement Process ML13343A1092013-12-26026 December 2013 Issuance of Amendment No. 197, Revise Technical Specifications and Surveillance Requirements to Support Operation with 24-Month Fuel Cycle in Accordance with Generic Letter 91-04 CNRO-2012-00009, Entergy Responses to Request for Additional Information Regarding Changes to the Quality Assurance Program Manual & Associated Plant Technical Specifications Re Staff Qualifications2012-11-20020 November 2012 Entergy Responses to Request for Additional Information Regarding Changes to the Quality Assurance Program Manual & Associated Plant Technical Specifications Re Staff Qualifications GNRO-2012/00132, License Amendment Request for Revision of Technical Specification Allowable Value for Primary Containment and Drywell Isolation Instrumentation Function 3.c RCIC Steam Supply Line Pressure - Low.2012-11-0909 November 2012 License Amendment Request for Revision of Technical Specification Allowable Value for Primary Containment and Drywell Isolation Instrumentation Function 3.c RCIC Steam Supply Line Pressure - Low. GNRO-2012/00124, Response to NRC Request for Additional Information - GGNS Criticality Safety Analysis License Amendment Request2012-10-22022 October 2012 Response to NRC Request for Additional Information - GGNS Criticality Safety Analysis License Amendment Request ML1207202832012-04-20020 April 2012 Issuance of Amendment No. 189, Revise Minimum Critical Power Ratio Safety Limit in Technical Specification 2.1.1.2 for Two-Loop and Single Recirculation Loop GNRO-2012/00014, Supplemental Information Pertaining to License Amendment Request for Standby Liquid Control System2012-03-21021 March 2012 Supplemental Information Pertaining to License Amendment Request for Standby Liquid Control System GNRO-2012/00001, License Amendment Request - Standby Liquid Control System2012-01-23023 January 2012 License Amendment Request - Standby Liquid Control System GNRO-2011/00064, License Amendment Request to Revise Technical Specification 2.1.1.22011-10-28028 October 2011 License Amendment Request to Revise Technical Specification 2.1.1.2 GNRO-2011/00004, License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-514, Revision 3, Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation.2011-04-0606 April 2011 License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-514, Revision 3, Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation. ML1026604032010-09-0808 September 2010 License Amendment Request Extended Power Uprate ML0931404632009-11-0303 November 2009 License Amendment Request Regarding Power Range Neutron Monitoring System Upgrade GNRO-2009/00042, Supplement to ENOC-09-00009, License Amendment Request; Proposed Adoption of TSTF-511 Regarding Elimination of Technical Specification Work Hour Restrictions, Letter Dated April 27, 20092009-07-10010 July 2009 Supplement to ENOC-09-00009, License Amendment Request; Proposed Adoption of TSTF-511 Regarding Elimination of Technical Specification Work Hour Restrictions, Letter Dated April 27, 2009 ML0909804292009-04-13013 April 2009 Correction to Amendment No. 182, Surveillance Requirements for Diesel Generator Slow - Start Testing (MD9641) ML0817600232008-10-14014 October 2008 Issuance of Amendment No. 178, Adoption of Technical Specifications Task Force (TSTF) Traveler No. 448, Revision 3, Control Room Envelope Habitability. GNRO-2008/00049, Supplemental No. 2 to Information for Licensing Amendment Request Pertaining to Control Room Envelope Habitability TSTF-4482008-09-0202 September 2008 Supplemental No. 2 to Information for Licensing Amendment Request Pertaining to Control Room Envelope Habitability TSTF-448 ML0724900082007-10-24024 October 2007 Technical Specifications, Issuance of Amendment No. 177 Changes to Technical Specifications Surveillance Requirement 3.3.1.1.7, the Local Power Range Monitor Calibration Frequency ML0734401152007-09-30030 September 2007 NEDC-33383, Revision 0, GEXL97 Correlation Applicable to ATRIUM-10 Fuel, (Non-Proprietary), Attachment 2 ML0721905072007-08-24024 August 2007 Tech Spec Pages for Amendment 176 Change to Technical Specifications to Allow Certain Types of Relief Valves to Be Used as Isolation Devices ML0712900082007-05-30030 May 2007 Technical Specifications, Issuance of Amendment 175 Re Technical Specifications Change Regarding Mode Change Limitations (TSTF-359) Using Consolidated Line Item Improvement Process, & Correct Example 1.4-1 (TSTF-485) ML0705306542007-03-16016 March 2007 Tech Spec Pages for Amendment No. 174 a Technical Specification Change to Allow Use of Control Rod Assemblies with Different Control Material GNRO-2007/00011, License Amendment Request, Change to Technical Specifications to Allow Certain Types of Relief Valves to Be Used as Isolation Devices2007-03-0101 March 2007 License Amendment Request, Change to Technical Specifications to Allow Certain Types of Relief Valves to Be Used as Isolation Devices 2023-12-14
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Vice President, Operations Entergy Operations, Inc. Grand Gulf Nuclear Station P.O. Box 756 Port Gibson, MS 39150 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August 31, 2015
SUBJECT:
GRAND GULF NUCLEAR STATION, UNIT 1 -ISSUANCE OF AMENDMENT RE: REQUEST FOR CHANGING FIVE TECHNICAL SPECIFICATIONS ALLOWABLE VALUES (TAC NO. MF4693)
Dear Sir or Madam:
The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment No. 207 to Facility Operating License No. NPF-29 for the Grand Gulf Nuclear Station, Unit 1 (GGNS). This amendment consists of changes to the technical specifications (TSs) in response to your application dated August 1, 2014, as supplemented by letters dated March 3 and June 30, 2015. The amendment revises five non-conservative Technical Specification Allowable Values in the GGNS TSs. The values changed are:
- Division 1 and 2 Degraded 4.16 KV Bus Voltage (TS Table 3.3.8.1-1)
- Division 3 Degraded 4.16 kiloVolt (KV) Bus Voltage (TS Table 3.3.8.1-1)
- Division 3 Degraded 4.16 KV Bus Voltage Time Delay-LOCA (Loss of Coolant Accident)
(TS Table 3.3.8.1-1) A copy of our related Safety Evaluation is also enclosed.
The Notice of Issuance will be included in the Commission's next biweekly Federal Register notice. Docket No. 50-416
Enclosures:
- 1. Amendment No. to NPF-29 2. Safety Evaluation cc: Distribution via Listserv Sincerely, Alan B. Wang, Project Manager Plant Licensing IV-2 and Decommissioning Transition Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 ENTERGY OPERATIONS.
INC. SYSTEM ENERGY RESOURCES.
INC. SOUTH MISSISSIPPI ELECTRIC POWER ASSOCIATION ENTERGY MISSISSIPPI.
INC. DOCKET NO. 50-416 GRAND GULF NUCLEAR STATION.
UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 207 License No. NPF-29 1. The Nuclear Regulatory Commission (the Commission) has found that: A. The application for amendment by Entergy Operations, Inc. (the licensee),
dated August 1, 2014, as supplemented by letters dated March 3, and June 30, 2015, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
Enclosure 1 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 2.C.(2) of Facility Operating License No. NPF-29 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 207 are hereby incorporated in the license.
Entergy Operations, Inc. shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan. 3. This license amendment is effective as of its date of issuance and shall be implemented within 90 days from the date of issuance.
Attachment:
Changes to the Facility Operating License No. NPF-29 and the Technical Specifications FOR THE NUCLEAR REGULATORY COMMISSION Meena K. Khanna, Chief Plant Licensing IV-2 and Decommissioning Transition Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Date of Issuance:
August 31, 2015 ATTACHMENT TO LICENSE AMENDMENT NO. 207 FACILITY OPERATING LICENSE NO. NPF-29 DOCKET NO. 50-416 Replace the following pages of the Facility Operating License No. NPF-29 and the Appendix A, Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change. Facility Operating License Remove -4-Technical Specifications Remove Insert 3.3-42 3.3-42 3.3-43 3.3-43 3.3-66 3.3-66 3.3-79 3.3-79 (b) SERI is required to notify the NRC in writing prior to any change in (i) the terms or conditions of any new or existing sale or lease agreements executed as part of the above authorized financial transactions, (ii) the GGNS Unit 1 operating agreement, (iii) the existing property insurance coverage for GGNS Unit 1 that would materially alter the representations and conditions set forth in the Staff's Safety Evaluation Report dated December 19, 1988 attached to Amendment No. 54. In addition, SERI is required to notify the NRC of any action by a lessor or other successor in interest to SERI that may have an effect on the operation of the facility.
C. The license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below: (1) Maximum Power Level Entergy Operations, Inc. is authorized to operate the facility at reactor core power levels not in excess of 4408 megawatts thermal (100 percent power) in accordance with the conditions specified herein. (2) Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 207 are hereby incorporated into this license.
Entergy Operations, Inc. shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan. During Cycle 19, GGNS will conduct monitoring of the Oscillation Power Range Monitor (OPRM). During this time, the OPRM Upscale function (Function 2.f of Technical Specification Table 3.3.1.1-1) will be disabled and operated in an "indicate only" mode and technical specification requirements will not apply to this function.
During such time, Backup Stability Protection measures will be implemented via GGNS procedures to provide an alternate method to detect and suppress reactor core thermal hydraulic instability oscillations.
Once monitoring has been successfully completed, the OPRM Upscale function will be enabled and technical specification requirements will be applied to the function; no further operating with this function in an "indicate only" mode will be conducted.
4 Amendment No. 207 ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 4 of 5) Emergency Core Cooling System Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER REQUIRED SURVEILLANCE ALLOWABLE FUN CT ION CONDITIONS FUNCTION ACTION A. l REOU I REMENTS VALUE 4. Automatic De.gessurization System (A S) Trip System A a. Reactor Vessel 1,2( d),3( d) 2 F SR 3.3.5.1.1 2: -152.5 inches Water Level c Low SR 3.3.5.1.2 Low Low, Level 1 SR 3.3.5.1.3 SR 3.3.5.1.5 SR 3.3.5.1.6
- b. Dry well Pressure C l ,2(d),3(d) 2 F SR 3.3.5.1.1
- S 1.44 psig High SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.5 SR 3.3.5.1.6
- c. ADS Initiation 1,2( d),3( d) G SR 3.3.5.1.2
- S 115 seconds Timer SR 3.3.5.1.4 SR 3.3.5.1.6
- d. Reactor Vessel l ,2(d),3(d)
F SR 3.3.5.1.1 2: 10.8 inches Water Level c Low, SR 3.3.5.1.2 Level 3 SR 3.3.5.1.3 (Confirmatory)
SR 3.3.5.1.5 SR 3.3.5.1.6
- e. LPCS Pump l ,2(d),3(d) 2 G SR 3.3.5.1.1 2: 125 psig and Discharge ressure SR 3.3.5.1.2
- S 165 psig CHigh SR 3.3.5.1.3 SR 3.3.5.1.5 SR 3.3.5.1.6
- f. LPCI l ,2(d),3(d) 2 G SR 3.3.5.1.1 2: 115 psig and Discharge ressure SR 3.3.5.1.2
- S 135 psig CHigh SR 3.3.5.1.3 SR 3.3.5.1.5 SR 3.3.5.1.6
- g. ADS Bo;pass Timer 1,2( d),3( d) 2 G SR 3.3.5.1.2
- S 9 .4 minutes rywell SR 3.3.5.1.4 ressure)
SR 3.3.5.1.6
- h. Manual Initiation 1,2( d),3( d) 2/system G SR 3.3.5.1.6 NA (continued)
(d) With reactor steam dome pressure>
150 psig GRAND GULF 3.3-42 Amendment No. +w, 207 ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 5 of 5) Emergency Core Cooling System Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS FUNCTION ACTION A .1 REQUIREMENTS VALUE 5. ADS Trip System B a. Reactor Vessel Water I,2(d),3(d) 2 F SR 3.3.5.1.1 2: -152.5 Level C Low Low Low, SR 3.3.5.1.2 inches Level 1 SR 3.3.5.1.3 SR 3.3.5.1.5 SR 3.3.5.1.6
- b. Drywell Pressure C High I,2(d),3(d) 2 F SR 3.3.5.1.1 s; 1.44 psig SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.5 SR 3.3.5.1.6
- c. ADS Initiation Timer 1,2(d),3(d)
G SR 3.3.5.1.2 s; 115 second, SR 3.3.5.1.4 SR 3.3.5.1.6
- d. Reactor Vessel Water 1,2( d),3( d) F SR 3.3.5.1.1 2: I 0.8 inches Level C Low, Level 3 SR 3.3.5.1.2 (Confirmatory)
SR 3.3.5.1.3 SR 3.3.5.1.5 SR 3.3.5.1.6
- e. LPCI Pumps B & C I ,2(d),3(d) 2 per pump G SR 3.3.5.1.1 2: 115 psig and Discharge SR 3.3.5.1.2 s; 135 psig Pressure C High SR 3.3.5.1.3 SR 3.3.5.1.5 SR 3.3.5.1.6
- f. ADS Timer (High I,2(d),3(d) 2 G SR 3.3.5.1.2 s; 9.4 minutes Drywel ressure)
SR 3.3.5.1.4 SR 3.3.5.1.6
- g. Manual Initiation I ,2(d),3(d) 2/system G SR 3.3.5.1.6 NA (d) With reactor steam dome pressure
> 150 psig GRAND GULF 3.3-43 Amendment No. W, 207 Table RHR Containment Spray System Instrumentation 3.3.6.3 3.3.6.3-1 (page 1 of 1) RHR Containment Spray System Instrumentation CONDITIONS REQUIRED REFERENCED CHANNELS FROM PER TRIP REOU I RED SURVEILLANCE ALLOWABLE FUNCTION SYSTEM ACTION A. 1 REQUIREMENTS VALUE I. Drywell Pressure C High 2 B SR 3.3.6.3.1
- S I .44 psig SR 3.3.6.3.2 SR 3.3.6.3.3 SR 3.3.6.3.5 SR 3.3.6.3.6
- 2. Containment Pressure C c SR 3.3.6.3. I :S 8.34 psig High SR 3.3.6.3.2 SR 3.3.6.3.3 SR 3.3.6.3.5 SR 3.3.6.3.6
- 3. Reactor Vessel Water Level 2 B SR 3.3.6.3.1
.'.::: -I 52.5 inches C Low Low Low, Level I SR 3.3.6.3.2 SR 3.3.6.3.3 SR 3.3.6.3.5 SR 3.3.6.3.6
- 4. System A and System B c SR 3.3.6.3.2
.'.::: I 0.6 minutes and Timers SR 3.3.6.3.4
- S I I. I minutes SR 3.3.6.3.6 GRAND GULF 3.3-66 Amendment No. -+/--2-9-,
207 I. 2. Table 3.3.8.1-1 (page 1 of 1) Loss of Power Instrumentation FUNCTION Divisions 1 and 2 C 4.16 kV Emergency Bus Undervoltage
- a. Loss of Voltage c 4.16 kV basis b. Loss of Voltage C Time Delay c. Degraded Voltage C4.16 kV basis d. Degraded Voltage C Time Delay Division 3 C 4.16 kV Emergency Bus Undervoltage
- a. Loss of Voltage c 4.16 kV basis b. Loss of Voltage C Time Delay c. Degraded Voltage c 4.16 kV basis d. Degraded Voltage C Time Delay, No LOCA e. Degraded Voltage C Time Delay, LOCA REQUIRED CHANNELS PER DIVISION SURVEILLANCE REQUIREMENTS 4 SR 3.3.8.1.
I SR 3.3.8.1.2 SR 3.3.8.1.3 2 SR 3.3.8.1.2 SR 3.3.8.1.3 4 SR 3.3.8.1.l SR 3.3.8.1.2 SR 3.3.8.1.3 2 SR 3.3.8.1.2 SR 3.3.8.1.3 4 SR 3.3.8.1.2 SR 3.3.8.1.3 2 SR 3.3.8.1.2 SR 3.3.8.1.3 4 SR 3.3.8.1.2 SR 3.3.8.1.3 2 SR 3.3.8.1.2 SR 3.3.8.1.3 4 SR 3.3.8.1..2 SR 3.3.8.1.3 GRAND GULF 3.3-79 LOP Instrumentation 3.3.8.1 ALLOWABLE VALUE 2: 2621 V and S 2912 V 2: 0.4 seconds and S 1.0 seconds 2: 3764.25 V and S 3837.6 V 2: 8.5 seconds and S 9.5 seconds 2: 2984 V and S 3106 V 2: 2.0 seconds and S 2.5 seconds 2: 3605 V and S 3763.5 V 2: 4.5 minutes and S 5.5 minutes 2: 3.85 seconds and S 4.4 seconds Amendment No. -+/--2-G-.
207 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 207 TO FACILITY OPERATING LICENSE NO. NPF-29 ENTERGY OPERATIONS.
INC .. ET AL.
1.0 INTRODUCTION
GRAND GULF NUCLEAR STATION.
UNIT 1 DOCKET NO. 50-416 By application dated August 1, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 14216A383),
as supplemented by letters dated March 3 and June 30, 2015 (ADAMS Accession Nos. ML 15063A279 and ML 15181A152, respectively),
Entergy Operations, Inc. (Entergy, the licensee),
requested changes to the technical specifications (TSs) for Grand Gulf Nuclear Station, Unit 1 (GGNS). The supplemental letters dated March 3 and June 30, 2015, provided additional information that clarified the application, did not expand the scope of the application as originally
- noticed, and did not change the statrs original proposed no significant hazards consideration determination as published in the Federal Register on November 25, 2014 (79 FR 70214). The proposed changes would revise five non-conservative TS Allowable Values (AVs). The AVs being changed are:
- Division 1and2 Degraded 4.16 kiloVolt (KV) Bus Voltage (TS Table 3.3.8.1-1)
- Division 3 Degraded 4.16 KV Bus Voltage (TS Table 3.3.8.1-1)
- Division 3 Degraded 4.16 KV Bus Voltage Time Delay-LOCA (Loss of Coolant Accident)
(TS Table 3.3.8.1-1) 2.0 REGULATORY EVALUATION The US Nuclear Regulatory Commission (NRC) staff used the following regulatory bases and guidance documents for the evaluation of this license amendment request (LAR):
- Title 10 of the Code of Federal Regulations (10 CFR) 50.36, "Technical specifications,"
requires that TSs include limiting conditions for operation (LCOs) for any structure, system, or component which operating experience or probabilistic risk assessment has Enclosure 2 shown to be significant to public health and safety. Section 50.36 also requires that TS Surveillance Requirements (SRs) be related to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the LCO will be met.
requires that "[i]nstrumentation shall be provided to monitor variables and systems over their anticipated ranges for normal operation, for anticipated operational occurrences, and for accident conditions as appropriate to ensure adequate safety, including those variables and systems that can affect the fission process, the integrity of the reactor core, the reactor coolant pressure
- boundary, and the containment and its associated systems.
Appropriate controls shall be provided to maintain these variables and systems within prescribed operating ranges."
Revision 3, dated December 1999 (ADAMS Accession No. ML993560062) describes a method that the NRC staff finds acceptable for use in complying with the NRC's regulations for ensuring that setpoints for safety-related instrumentation are initially within, and will remain within, the TS limits. RG 1.105 endorses Part I of Instrument Society of America (ISA) Standard 67.04-1994, "Setpoints for Nuclear Safety-Related Instrumentation,"
subject to NRC staff clarifications.
The staff used this guide to establish the adequacy of the licensee's setpoint calculation methodologies and the related plant surveillance procedures.
Regarding Limiting Safety System Settings During Periodic Testing and Calibration of Instrument Channels,"
dated August 24, 2006 (ADAMS Accession No. ML051810077),
discusses the requirements of 10 CFR 50.36 related to Limiting Safety System Settings (LSSS) and provides an approach acceptable to the NRC to address LSSS issues. The LSSSs are settings for automatic protective devices related to those variables having significant safety functions.
3.0 TECHNICAL EVALUATION 3.1 Background While updating the setpoint calculations for the functions identified in the LAR, the licensee determined the current TS AVs identified in the LAR were non-conservative.
The licensee provided the revised setpoint calculations in the LAR. In an email dated January 11, 2015 (ADAMS Accession No. ML 15013A343),
the NRC staff requested additional information (RAI) about the setpoint methodology used to ensure that the methodology applied was consistent with NRC regulations.
The licensee provided its response in a submittal dated March 3, 2015 (ADAMS Accession No. ML 15063A279).
Additionally, as summarized below, Entergy provided the reasons for why the AVs were determined to be non-conservative:
- ADS Initiation Timer and System A and B Containment Spray Timers -When the AVs were originally derived by General Electric (GE), they assumed a 2 percent reference accuracy (RA). Entergy then authorized the replacement of obsolete FTR model relays that have a 2 percent RA (normal environment) with ETR model relays that have a 5 percent RA (normal environment).
While performing the replacement, Entergy did not address the RA difference and the impact on the associated setpoint calculations JC-Q1 B21-K114, "Instrument Uncertainty and Setpoint Determination for the System IB21-ADS System Initiation Time Delay," or JC-01E12-K093, "Instrument Uncertainty and Setpoint Determination for System E12 Containment Spray Actuation Timer." The revised calculations conservatively assume a 5 percent repeatability/accuracy for the ETR relays, specifically.
o ADS Initiation Timer -Calculation JC-Q1 B21-K114 was revised to incorporate the correct repeatability/accuracy and resulted in a conservative AV of 115 seconds being proposed for the ADS initiation timer. o System A and B Containment Spray Timers -Calculation JC-Q1E12-K093 was revised to incorporate the correct repeatability/accuracy and resulted in a conservative lower AV of 10.6 minutes being proposed for the containment spray timers.
- Division 1 and 2 Degraded 4.16 KV Bus Voltage -Calculation JC-01 R21-90024-1, "Division 1 and 2 Degraded Voltage Setpoint Validation,"
did not include an allowance for loop uncertainty between the 3744 volt (V) lower analytic limit and the lower AV, currently specified in TS Table 3.3.8.1-1, for the 4160 Volts alternating current (VAC) Division 1 and 2 degraded voltage setpoint.
Based on the revised calculation, a conservative AV of 3764.25 VAC is being proposed for the Division 1 and 2 Degraded 4.16 KV Bus Voltage.
- Division 3 Degraded 4.16 KV Bus Voltage -In calculation JC-Q1 P81-90024, "Division Ill Degraded Bus Voltage Setpoint Validation (T/S 3.3.8.1 )," the 3558.8 VAC lower AV currently specified for the Division 3 degraded voltage setpoint, is slightly non-conservative.
Based on the revised calculation, a conservative lower AV of 3605 VAC is being proposed for the Division 3 Degraded 4.16 KV Bus Voltage.
- Division 3 Degraded 4.16 KV Bus Voltage Time Delay -LOCA [loss-of-coolant accident]
-In calculation JC-Q1P81-90024, "Division Ill Degraded Bus Voltage Setpoint Validation (T/S 3.3.8.1 ),"the 3.6 second lower AV, currently specified for the Division 3 degraded voltage setpoint time delay, is slightly non-conservative.
Based on the revised calculation, a conservative lower AV of 3.68 seconds is being proposed for the Division 3 Degraded 4.16 KV Bus Voltage time delay. Entergy provided GGNS calculation JS-09, Revision 1 (JS-09),
"Methodology for the Generation of Instrument Loop Uncertainty
& Setpoint Calculations,"
for NRC staff review. This calculation was used to determine the loop uncertainties and setpoints for this amendment request.
The licensee noted that the methodology used for these calculations was the GE Topical Report NEDC-31336-P-A, "General Electric Instrument Setpoint Methodology,"
dated September 1996 (Proprietary information, not publicly available).
By letter dated November 6, 1995, this topical report was approved by the NRC staff for calculation of setpoints.
In this method, the independent, random, and normally distributed variables/uncertainties were combined by the square root of the sum of the squares (SRSS) to determine the total loop uncertainty (TLU), which the licensee used to calculate the new AV. In the sections below, the uncertainties considered to calculate the TLU for each of the five AV changes is discussed.
The GE Setpoint Methodology is designed to result in a 95 percent probability of providing a channel trip before the process variable reaches the analytical limit, considering drift and assuming a one-sided normal distribution.
The GE Setpoint Methodology utilizes single-sided distributions in the development of trip setpoints and A Vs. During the review of the LAR, the NRC staff noted that the term 1.645/n (n normally 2), which is part of the GE setpoint methodology, was not included in 3 of the 4 impacted calculations.
Having this term omitted results in a more conservative AV. In the RAI response, GGNS stated that they would be updating all of the calculations to revise the TS AVs that are referenced.
In a letter dated June 30, 2015 (ADAMS Accession No. ML 15181A152),
GGNS agreed to also add a statement that will identify the term that was omitted and explain that leaving out the term results in a more conservative allowable value, to the following calculations:
- Calculation JC-Q1E12-K093, "Instrument Uncertainty and Setpoint Determination for System E12 Containment Spray Actuation Timer
- Calculation JC-01 R21-90024-1, "Division 1 & 2 Degraded Voltage Setpoint Validation"
[ECCS]" (Items 4.c and 5.c)) This AV is being changed from S117 seconds to S115 seconds.
- 2) System A and B Containment Spray Timers (TS Table 3.3.6.3-1, "RHR [Residual Heat Removal]
Containment Spray System Instrumentation" (Item 4)) This AV is being changed from minutes and S11.44 minutes to minutes and S11.1 minutes.
- 3) Division 1 and 2 Degraded 4.16 KV Bus Voltage (TS Table 3.3.8.1-1, "Loss of Power Instrumentation" (Item 1 c)) This AV is being changed from 44 V to V. 4) Division 3 Degraded 4.16 KV Bus Voltage (TS Table 3.3.8.1-1 (Item 2c)) This AV is being changed from V to V. 5) Division 3 Degraded 4.16 KV Bus Voltage Time Delay-LOCA (TS Table 3.3.8.1-1 (Item 2.e)) This AV is being changed from seconds to seconds.
3.3 ADS Initiation Timer In the LAR, Entergy proposed to revise the AV contained in GGNS TS 3.3.5.1, "Emergency Core Cooling System [ECCS] Instrumentation,"
Table 3.3.5.1-1, Items 4.c and 5.c, for the ADS Initiation Timer. The licensee is revising this value to correct the accuracy term used in the loop uncertainty.
The ADS system uses select safety/relief valves to depressurize the reactor vessel in the event of a LOCA to allow the low pressure ECCSs to activate if the high pressure ECCSs cannot maintain reactor water level. The ADS Initiation Timer delays initiation of the ADS to allow the operator to terminate the ADS action if the initiations of the high pressure ECCSs and acceptable reactor water level have been confirmed.
Attachment 4 of the LAR provides the calculation for instrument uncertainties and setpoint determination.
This calculation was based on the GGNS methodology documented in JS-09. In addition, the RAI response provided vendor data for the FTR and ETR model relays necessary for the calculation of instrument uncertainty and the calculation of the new AV. The NRC staff reviewed the revised setpoint calculation and confirmed that the input data for all uncertainties were appropriately identified and carried throughout the calculation of the new AV. The licensee determined a new AV of s 115 seconds.
The new value is more conservative than the previous value of s 117 seconds for the ADS initiation timer. Based on its evaluation of the information
- provided, the NRC staff concludes that the licensee appropriately applied its setpoint methodology to calculate the new AV, using the corrected accuracy term. In addition, the staff found that the licensee's methodology appropriately used the criteria in RG 1.105 and meets the intent of RIS 2006-17.
Therefore, the proposed TS change satisfies the requirements of 10 CFR 50.36. 3.4 System A and B Containment Spray Timers In the LAR, Entergy proposed to revise the AVs in GGNS TS 3.3.6.3, "RHR Containment Spray System Instrumentation,"
contained in Table 3.3.6.3-1, Item 4, for the System A and System B Timers. The licensee is revising this value to correct the accuracy term used in the loop uncertainty.
Containment Spray is an operating mode of the residual heat removal (RHR) system wherein water discharged from the RHR pumps is directed through heat exchangers to spray headers located near the top of the containment.
This spray passes down through the containment atmosphere condensing steam, removing energy from the atmosphere to limit containment pressure rise resulting from a LOCA or high energy line break (HELB) inside containment, and promoting removal of iodine from the containment atmosphere. Containment Spray "A" is initiated by low-pressure core spray initiation (high drywell pressure or low water level) after about a 1 O minute time delay to permit the residual heat removal (RHR)
- system to operate in low-pressure coolant injection (LPCI) mode to recover core water level in the event of a LOCA. Containment Spray "B" is initiated by a LOCA detection (high drywell pressure or low water level in the reactor) coincident with high containment pressure after about a 1 O minute time delay followed by a short time delay of less than 5 seconds.
Attachment 5 of the LAR provides the calculation for instrument uncertainties and setpoint determination.
This calculation was based on the GGNS methodology documented in JS-09. In addition, the licensee's RAI response provided vendor data for the ETR model relays necessary for the calculation of instrument uncertainty and calculation of the new AV. The NRC staff confirmed that the input data for all uncertainties identified in the AV calculation were appropriately identified and carried throughout the calculation.
The licensee calculated the following values: upper AV of s 11.1 min and lower AV 10.6 min. These new values are more conservative than the previous values of s 11.44 min for the upper AV and 10.26 min for the lower AV. Based on its evaluation of the information
- provided, the NRC staff concludes the licensee appropriately applied its setpoint methodology to calculate the new AV using the corrected accuracy term. In addition, the staff found that the licensee's methodology appropriately used the criteria in RG 1.105 and meets the intent of RIS 2006-17.
Therefore, the proposed TS change satisfies the requirements of 10 CFR 50.36. 3.5 Division 1 and 2 Degraded 4.16 KV Bus Voltage In the LAR, Entergy proposed to revise the lower AV in GGNS TS 3.3.8.1, "Loss of Power (LOP) Instrumentation,"
Table 3.3.8.1-1, Item 1.c, for the Divisions 1 and 2, 4.16 KV Emergency Bus Undervoltage Degraded Voltage -4.16 KV Basis. The current AV calculation did not include an allowance for loop uncertainty.
Therefore, the licensee revised the calculation of the AV to include the loop uncertainty. As identified in the LAR, the second level of bus undervoltage is defined as degraded bus conditions, as signified by the sensing of the components monitoring the 4160 V buses. This second level bus undervoltage function protects equipment/motors from any adverse effects of sustained degraded
- voltage, and prevents spurious separation of offsite power sources from Class 1 E loads, due to normal power transients (e.g., starting large motors) or from short duration power system disturbances.
Voltage sensing is performed by potential transformers located within the 4160 V switchgear for each division.
Each potential transformer has a 4200 V/120 V ratio. Attachment 6 of the LAR provides the calculation for instrument uncertainties and setpoint determination.
This calculation was based on the GGNS methodology documented in JS-09. In addition, the licensee's RAI response provided the vendor data necessary for the calculation of instrument uncertainty and the calculation of the new AV. The NRC staff confirmed that the input data for all uncertainties identified in the AV calculation were appropriately identified and carried throughout the calculation.
The allowance for loop uncertainty was incorporated into the new AV calculation resulting in a new AV 3764.25 V. Based on its evaluation of the information
- provided, the NRC staff concludes the licensee appropriately applied its setpoint methodology to calculate the new AV, including the loop uncertainty.
In addition, the staff found that the licensee's methodology appropriately used the criteria in RG 1.105 and meets the intent of RIS 2006-17.
Therefore, the proposed TS change satisfies the requirements of 10 CFR 50.36. 3.6 Division 3 Degraded 4.16 KV Bus Voltage In the LAR, Entergy proposed to revise the lower AV in GGNS TS 3.3.8.1, "Loss of Power (LOP) Instrumentation,"
Table 3.3.8.1-1, Item 2.c, for the Division 3, 4.16 KV Emergency Bus Undervoltage Degraded Voltage -4.16 KV Basis. The licensee is correcting a conservative AV that resulted from using incorrect terms in the uncertainty calculation.
As identified in the LAR, the second level of bus undervoltage is defined as degraded bus conditions, as signified by the sensing of the components monitoring the 4160 V buses. This second level bus undervoltage function protects equipment/motors from any adverse effects of sustained degraded
- voltage, and prevents spurious separation of offsite power sources from Class 1 E loads, due to normal power transients (e.g., starting large motors) or from short duration power system disturbances.
Voltage sensing is performed by potential transformers located within the 4160 V switchgear for each division.
Each potential transformer has a 4200 V/120 V ratio. Attachment 7 of the LAR provides calculation for instrument uncertainties and setpoint determination.
This calculation was based on the GGNS methodology documented in JS-09. The NRC staff confirmed that the input data for all uncertainties identified in the AV calculation were appropriately identified and carried throughout the calculation.
Once the corrected uncertainties were incorporated, the AV was adjusted 3558.8 V 3605 V, which provides a more conservative value .. Based on its evaluation of the information
- provided, the NRC staff concludes the licensee appropriately used its setpoint methodology to calculate the new AV, using the corrected uncertainty terms. In addition, the staff found that the licensee's methodology appropriately used the criteria in RG 1.105 and meets the intent of RIS 2006-17.
Therefore, the proposed TS change satisfies the requirements of 1 O CFR 50.36. 3. 7 Division 3 Degraded 4.16 KV Bus Voltage Time Delay -LOCA In the LAR, Entergy proposed to revise the lower AV in GGNS TS 3.3.8.1, "Loss of Power (LOP) Instrumentation,"
Table 3.3.8.1-1, Item 2.e, for the Division 3, 4.16 KV Emergency Bus Undervoltage Degraded Voltage -Time Delay, LOCA. The licensee is correcting a conservative AV that resulted from using incorrect terms in the uncertainty calculation.
Attachment 7 of the LAR provides a calculation for instrument uncertainties and setpoint determination.
This calculation was based on the GGNS methodology documented in JS-09. The NRC staff confirmed that the input data for all uncertainties identified in the AV calculation were appropriately identified and carried throughout the calculation.
The corrected uncertainties were incorporated into the new AV calculation, resulting in a new AV 3.68 seconds from the previous value 3.6 seconds.
The new AV resulted in a more conservative value. Based on its evaluation of the information
- provided, the NRC staff concludes the licensee appropriately used its setpoint methodology to calculate the new AV using the corrected uncertainty terms. In addition, the staff found that the licensee's methodology appropriately used the criteria in RG 1.105 and meets the intent of RIS 2006-17.
Therefore, the proposed TS change satisfies the requirements of 10 CFR 50.36. 3.8 Technical Conclusion The NRC staff reviewed the licensee's application related to the modification of the 5 conservative allowable values in the TSs. The NRC staff concludes that the licensee adequately addressed the corrected uncertainty terms within the allowable value calculations, establishing appropriate new allowable values for these functions, to meet the requirements of 10 CFR 50.36. Furthermore, the NRC staff concludes that the systems will continue to meet the requirements of Appendix A to 1 O CFR 50, Criterion 13, as well as the guidance within RG 1.105 and RIS 2006-17.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Mississippi State official was notified of the proposed issuance of the amendment.
The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released
- offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure.
The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding published in the Federal Register on November 25, 2014 (79 FR 70214). Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Pursuant to 10 CFR 51.22(b),
no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) there is reasonable assurance that such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public. Principal Contributor:
D. Warner A. Wang Date: August 31, 2015 Vice President, Operations A copy of our related Safety Evaluation is also enclosed.
The Notice of Issuance will be included in the Commission's next biweekly Federal Register notice. Docket No. 50-416
Enclosures:
Sincerely, IRA/ Alan B. Wang, Project Manager Plant Licensing IV-2 and Decommissioning Transition Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
- 1. Amendment No. 207 to NPF-29 2. Safety Evaluation cc w/enclosures:
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