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Category:Letter type:GNRO
MONTHYEARGNRO-2013/00079, 2013-10-13 (GNRO-2013-00079) Response to RAI Set 49 (Dated Sep-12-2013)2023-10-11011 October 2023 2013-10-13 (GNRO-2013-00079) Response to RAI Set 49 (Dated Sep-12-2013) GNRO-2023/00014, License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2023-06-0606 June 2023 License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b GNRO-2023/00015, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-06-0606 June 2023 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors GNRO-2021/00037, 2021 Annual Report of Changes and Errors to 10 CFR 50.46 Analysis Grand Gulf Nuclear Station, Unit 12021-11-30030 November 2021 2021 Annual Report of Changes and Errors to 10 CFR 50.46 Analysis Grand Gulf Nuclear Station, Unit 1 GNRO-2021/00017, Notification of Readiness for Supplemental Inspection2021-06-22022 June 2021 Notification of Readiness for Supplemental Inspection GNRO-2021/00014, Inservice Testing Program Relief Request VRR-GGNS-2021-1 Pressure Isolation Valve Testing Frequency2021-06-0101 June 2021 Inservice Testing Program Relief Request VRR-GGNS-2021-1 Pressure Isolation Valve Testing Frequency GNRO-2021/00015, Annual Radioactive Effluent Release Report2021-04-28028 April 2021 Annual Radioactive Effluent Release Report GNRO-2021/00011, Revision of Original Report of 10CFR50.59 and Commitments Change Evaluations - July 1, 2018 Through May 21, 20202021-04-19019 April 2021 Revision of Original Report of 10CFR50.59 and Commitments Change Evaluations - July 1, 2018 Through May 21, 2020 GNRO-2021/00012, Annual Report of Individual Monitoring - NRC Form 5 for 2020 Per 10 CFR 20.22062021-04-13013 April 2021 Annual Report of Individual Monitoring - NRC Form 5 for 2020 Per 10 CFR 20.2206 GNRO-2020/00045, 2020 Report of Changes and Errors to 10 CFR 50.46 Analysis2020-12-16016 December 2020 2020 Report of Changes and Errors to 10 CFR 50.46 Analysis GNRO-2020/00034, Notification of Spent Fuel Cask Use2020-10-0808 October 2020 Notification of Spent Fuel Cask Use GNRO-2020/00033, Response to NRC Integrated Inspection Report 05000416/20200022020-09-10010 September 2020 Response to NRC Integrated Inspection Report 05000416/2020002 GNRO-2020/00029, Report of 10 CFR 72.48 Evaluations July 1, 2018 Through June 30, 20202020-08-18018 August 2020 Report of 10 CFR 72.48 Evaluations July 1, 2018 Through June 30, 2020 GNRO-2020/00022, Report of Technical Specification Bases Changes2020-07-21021 July 2020 Report of Technical Specification Bases Changes GNRO-2020/00027, Core Operating Limits Report (COLR) Cycle 23 Revision 1 for Grand Gulf Nuclear Station, Unit 1 (GGNS)2020-07-16016 July 2020 Core Operating Limits Report (COLR) Cycle 23 Revision 1 for Grand Gulf Nuclear Station, Unit 1 (GGNS) GNRO-2020/00023, Response to Request for Additional Information - License Amendment Request for Permanent Extension of Appendix J Type a Integrated Leakage Rate Test Frequencies2020-06-26026 June 2020 Response to Request for Additional Information - License Amendment Request for Permanent Extension of Appendix J Type a Integrated Leakage Rate Test Frequencies GNRO-2020/00020, Core Operating Limits Report (COLR) Cycle 23, and Pressure and Temperature Limits Report (PTLR) Update for Grand Gulf Nuclear Station, Unit 1 (GGNS)2020-05-0505 May 2020 Core Operating Limits Report (COLR) Cycle 23, and Pressure and Temperature Limits Report (PTLR) Update for Grand Gulf Nuclear Station, Unit 1 (GGNS) GNRO-2020/00018, Annual Radiological Effluent Release Report2020-04-30030 April 2020 Annual Radiological Effluent Release Report GNRO-2020/00016, Annual Report of Individual Monitoring -NRC Form 5 for 2019 Per 10 CFR 20.22062020-04-16016 April 2020 Annual Report of Individual Monitoring -NRC Form 5 for 2019 Per 10 CFR 20.2206 GNRO-2020/00015, Response to Request for Additional Information - License Amendment Request for One-Cycle Extension of Appendix J Type a Integrated Leakage Rate Test and Drywell Bypass Leakage Rate Test2020-04-0707 April 2020 Response to Request for Additional Information - License Amendment Request for One-Cycle Extension of Appendix J Type a Integrated Leakage Rate Test and Drywell Bypass Leakage Rate Test GNRO-2020/00007, Spent Fuel Storage Radioactive Effluent Release Report for 20192020-02-20020 February 2020 Spent Fuel Storage Radioactive Effluent Release Report for 2019 GNRO-2020/00006, License Amendment Request for Permanent Extension of Appendix J Type a Integrated Leakage Rate Test Frequencies2020-02-19019 February 2020 License Amendment Request for Permanent Extension of Appendix J Type a Integrated Leakage Rate Test Frequencies GNRO-2019/00052, Report of Changes and Errors to 10 CFR 50.46 Analysis2019-12-13013 December 2019 Report of Changes and Errors to 10 CFR 50.46 Analysis GNRO-2019/00051, Notification of Readiness of 92723 Inspection2019-12-11011 December 2019 Notification of Readiness of 92723 Inspection GNRO-2019/00045, Emergency Plan, Revision 792019-10-29029 October 2019 Emergency Plan, Revision 79 GNRO-2019/00037, Notification of Spent Fuel Cask Use2019-09-20020 September 2019 Notification of Spent Fuel Cask Use GNRO-2019/00036, Correction to Gnro 2019-00017 Emergency Plan Revision 782019-08-0808 August 2019 Correction to Gnro 2019-00017 Emergency Plan Revision 78 GNRO-2019/00027, Notification of Readiness of 95001 Supplemental Inspections2019-07-0303 July 2019 Notification of Readiness of 95001 Supplemental Inspections GNRO-2019/00031, Annual Report of Individual Monitoring - NRC Form 5 for 2018 Per 10 CFR 20.2206 - Corrected Report2019-06-25025 June 2019 Annual Report of Individual Monitoring - NRC Form 5 for 2018 Per 10 CFR 20.2206 - Corrected Report GNRO-2019/00028, Supplement to Revise Technical Specification (TS) 3.3.1.1, Reactor Protection System (RPS) Instrumentation, and TS 3.3.4.1, End of Cycle Recirculation Pump Trip (EOC-RPT) Instrumentation.2019-06-13013 June 2019 Supplement to Revise Technical Specification (TS) 3.3.1.1, Reactor Protection System (RPS) Instrumentation, and TS 3.3.4.1, End of Cycle Recirculation Pump Trip (EOC-RPT) Instrumentation. GNRO-2019/00026, Response to Requests for Additional Information Regarding Relief Request Number GG-ISI-023, Inservice Inspection Impracticality - Limited Coverage Examinations During the Third 10-Year Inservice Inspection Interval2019-05-0606 May 2019 Response to Requests for Additional Information Regarding Relief Request Number GG-ISI-023, Inservice Inspection Impracticality - Limited Coverage Examinations During the Third 10-Year Inservice Inspection Interval GNRO-2019/00024, Annual Radioactive Effluent Release Report2019-04-30030 April 2019 Annual Radioactive Effluent Release Report GNRO-2019/00020, Annual Radiological Operating Report (AREOR)2019-04-30030 April 2019 Annual Radiological Operating Report (AREOR) GNRO-2019/00022, Annual Report of Individual Monitoring - NRC Form 5 for 2018 Per 10 CFR 20.22062019-04-22022 April 2019 Annual Report of Individual Monitoring - NRC Form 5 for 2018 Per 10 CFR 20.2206 GNRO-2019/00017, Emergency Plan, Revision 782019-03-14014 March 2019 Emergency Plan, Revision 78 GNRO-2019/00014, Snubber Testing Program for Fourth Inspection Interval2019-03-13013 March 2019 Snubber Testing Program for Fourth Inspection Interval GNRO-2019/00012, Internal Events Probabilistic Risk Assessment (PRA) Sensitivity Study Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program2019-03-0606 March 2019 Internal Events Probabilistic Risk Assessment (PRA) Sensitivity Study Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program GNRO-2019/00016, Spent Fuel Storage Radioactive Effluent Release Report for 20182019-02-21021 February 2019 Spent Fuel Storage Radioactive Effluent Release Report for 2018 GNRO-2019/00003, Application to Revise Technical Specification (TS) 3.3.1.1, Reactor Protection System (RPS) Instrumentation, and TS 3.3.4.1, End of Cycle Recirculation Pump Trip (EOC-RPT) Instrumentation2019-01-23023 January 2019 Application to Revise Technical Specification (TS) 3.3.1.1, Reactor Protection System (RPS) Instrumentation, and TS 3.3.4.1, End of Cycle Recirculation Pump Trip (EOC-RPT) Instrumentation GNRO-2018/00057, Submittal of Revision 17 to the Grand Gulf Nuclear Station Physical Security, Safeguards Contingency, and Training and Qualification Plan2018-12-0404 December 2018 Submittal of Revision 17 to the Grand Gulf Nuclear Station Physical Security, Safeguards Contingency, and Training and Qualification Plan GNRO-2018/00055, Response to Request for Additional Information for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a ...2018-11-30030 November 2018 Response to Request for Additional Information for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a ... GNRO-2018/00054, Relief Request No. GG-ISI-023, Inservice Inspection Impracticality: Limited Coverage Examination During the Third 10-Year Inservice Inspection Interval2018-11-30030 November 2018 Relief Request No. GG-ISI-023, Inservice Inspection Impracticality: Limited Coverage Examination During the Third 10-Year Inservice Inspection Interval GNRO-2018/00052, License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into Licensing Basis - Partial Response to Request for Additional Information and Extension of Response to Request for Additional Information2018-10-24024 October 2018 License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into Licensing Basis - Partial Response to Request for Additional Information and Extension of Response to Request for Additional Information GNRO-2018/00051, Supplement to Revise Technical Specifications to Adopt Technical Specification Task Force Traveler TSTF-542, Reactor Pressure Vessel Water Inventory Control2018-10-23023 October 2018 Supplement to Revise Technical Specifications to Adopt Technical Specification Task Force Traveler TSTF-542, Reactor Pressure Vessel Water Inventory Control GNRO-2018/00046, Submittal of 2018 Report of Changes and Errors to 10CFR50.462018-10-16016 October 2018 Submittal of 2018 Report of Changes and Errors to 10CFR50.46 GNRO-2018/00047, Submittal of 2018 Inservice Inspection Summary Report2018-10-16016 October 2018 Submittal of 2018 Inservice Inspection Summary Report GNRO-2018/00048, Response to Request for Additional Information License Amendment Request, Adoption of Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 62018-10-10010 October 2018 Response to Request for Additional Information License Amendment Request, Adoption of Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6 GNRO-2018/00042, Core Operating Limits Report Cycle 22, Revision 12018-09-18018 September 2018 Core Operating Limits Report Cycle 22, Revision 1 GNRO-2018/00043, Revised Offsite Dose Calculation Manual2018-09-18018 September 2018 Revised Offsite Dose Calculation Manual GNRO-2018/00039, Report of Technical Specification Bases Changes2018-08-20020 August 2018 Report of Technical Specification Bases Changes 2023-06-06
[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
[Table view] |
Text
Entergy Operations, Inc.
P. O. Box 756 Port Gibson, MS 39150 Michael A. Krupa Director, Extended Power Uprate Grand Gulf Nuclear Station Tel. (601) 437-6694 GNRO-2012/00014 March 21, 2012 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
SUBJECT:
Supplemental Information Pertaining to License Amendment Request for Standby Liquid Control System (TAC No. ME7860)
Grand Gulf Nuclear Station, Unit 1 Docket No. 50-416 License No. NPF-29
REFERENCE:
Entergy Operations, Inc. letter to the NRC (GNRO-2012/00001), License Amendment Request - Standby Liquid Control System, January 23, 2012 (ADAMS Accession No. ML12023A242)
Dear Sir or Madam:
In the referenced letter, Entergy Operations, Inc. (Entergy) requested approval of an amendment to Grand Gulf Nuclear Station, Unit 1 (GGNS) Technical Specification (TS) 3.1.7, Standby Liquid Control (SLC) System. The proposed license amendment request (LAR) reflects the enrichment of the boron-10 (B-10) isotope in the sodium pentaborate (SPB) solution, which is the credited neutron absorber. Increasing the enrichment of the B-10 isotope in the SPB solution effectively increases the available negative reactivity inserted by the SLC system without having to increase the systems storage capacity.
Following communication with the NRC staff, Entergy is supplementing its LAR with additional information provided in Attachment 1. Attachments 2 and 3 provide revised marked-up and clean pages of TS 3.1.7, respectively. Attachment 4 provides a markup of the related changes to the TS Bases for information only.
The No Significant Hazards Determination and the Environmental Consideration provided in the referenced letter are not impacted by this supplemental information.
This letter contains no new commitments.
If you have any questions or require additional information, please contact Guy Davant at (601) 368-5756.
GNRO-2012/00014 Page 2 of 2 I declare under penalty of perjury that the foregoing is true and correct; executed on March 21, 2012.
Sincerely, MAK/ghd Attachments:
- 1. Supplemental Information Pertaining to License Amendment Request - Standby Liquid Control System
- 2. Proposed Technical Specification Changes (Mark-up)
- 3. Proposed Technical Specification Changes (Clean Pages)
- 4. Changes to Technical Specification Bases Pages - For Information Only cc: Mr. Elmo E. Collins, Jr.
Regional Administrator, Region IV U. S. Nuclear Regulatory Commission 1600 East Lamar Blvd.
Arlington, TX 76011-4511 U. S. Nuclear Regulatory Commission ATTN: Mr. A. B. Wang, NRR/DORL (w/2)
ATTN: ADDRESSEE ONLY ATTN: Courier Delivery Only Mail Stop OWFN/8 G14 11555 Rockville Pike Rockville, MD 20852-2378 State Health Officer Mississippi Department of Health P. O. Box 1700 Jackson, MS 39215-1700 NRC Senior Resident Inspector Grand Gulf Nuclear Station Port Gibson, MS 39150
Attachment 1 GNRO-2012/00014 Grand Gulf Nuclear Station, Unit 1 SUPPLEMENTAL INFORMATION PERTAINING TO LICENSE AMENDMENT REQUEST STANDBY LIQUID CONTROL SYSTEM to GNRO-2012/00014 Page 1 of 3 SUPPLEMENTAL INFORMATION PERTAINING TO LICENSE AMENDMENT REQUEST STANDBY LIQUID CONTROL SYSTEM By application dated January 23, 2012, Entergy Operations, Inc. (Entergy) submitted a license amendment request (LAR) for NRC staff approval to amend the Grand Gulf Nuclear Station, Unit 1 (GGNS) Technical Specification (TS) 3.1.7, Standby Liquid Control (SLC)
System.1 This LAR supports the use of a sodium pentaborate (SPB) solution that has been enriched with the boron-10 (B-10) isotope.
Following communication with the NRC staff, Entergy is supplementing its LAR with additional information provided below. This supplemental information results in revisions to the proposed TS. Attachments 2 and 3 contain revised marked-up and clean TS pages, respectively. Attachment 4 contains revised marked-up TS Bases pages for information only.
Request for Information #1 Please define C and E in TS 3.1.7.
Supplemental Information Entergy proposes to revise Condition A, SR 3.1.7.5, and SR 3.1.7.9 to read as follows:
- Condition A Product of Sodium Pentaborate concentration in weight percent (C) times Boron-10 enrichment in atom percent (E) < 420.
- SR 3.1.7.5 Verify the percent weight of sodium pentaborate in solution (C) is < 9.5%.
- SR 3.1.7.9 Determine Boron-10 enrichment (E) in atom percent.
Request for Information #2 Please address actions to ensure pump suction piping is not blocked in the event the temperature of the sodium pentaborate solution decreases below the minimum allowed temperature.
Supplemental Information Entergy proposes a new Surveillance Requirement (SR) 3.1.7.10, which requires verifying the piping between the storage tank and the pump suction is not blocked on a frequency of once within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after the temperature of the sodium pentaborate solution is restored to > 45°F.
1 Entergy letter to the NRC, License Amendment Request - Standby Liquid Control System, January 23, 2012 to GNRO-2012/00014 Page 2 of 3 The frequency of performing SR 3.1.7.10 once within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after the temperature of the sodium pentaborate solution is restored to > 45°F is acceptable in light of the daily temperature verification required by new SR 3.1.7.2 and the low probability that the piping will be blocked due to precipitation of the boron from solution.
Request for Information #3 Please revise Condition C to reflect the temperature being observed is the sodium pentaborate solution temperature.
Supplemental Information Entergy proposes to revise Condition C to read as follows:
Sodium pentaborate solution temperature < 45°F or 150°F Request for Information #4 Please provide additional information pertaining to suppression pool pH control discussed in Section 4.1.3 of the SLC system LAR.
Supplemental Information In Grand Gulfs license amendment application of NUREG-1465, Accident Source Terms for Light-Water Nuclear Power Plants,2 Entergy provided a method and associated calculation that showed the SPB solution from the SLC system was capable of controlling and maintaining long-term suppression pool water pH level at or above 7.0 throughout the entire 30-day period of a postulated accident. The NRC staff agreed with this determination, as documented in their Safety Evaluation for the amendment.3 Using the same methodology, Entergy has calculated the pH of the suppression pool water when enriched SPB is injected into the reactor core following an accident. This evaluation considered inputs that reflect extended power uprate conditions (i.e., operating at 4408 MWt),
which are conservative to conditions when operating at the current licensed thermal power (3898 MWt). Furthermore, the calculation assumes approximately 1,400 lbs. of SPB is in the pool, which conservatively models the SLC storage tank solution at minimum volume and minimum concentration.
Thus, it can be concluded that injecting an amount of SPB solution required by the proposed TS to satisfy the shutdown requirement also is sufficient to maintain suppression pool pH greater than 7.0 for at least 30 days post-accident.
2 Entergy letter to the NRC, GGNS Pilot Full-Scope Application of NUREG-1465 Alternative Source Term Insights, LDC 1999-082, January 21, 2000 3
NRC letter to Entergy, Grand Gulf Nuclear Station (GGNS), Unit 1 - Issuance of Amendment Re:
Full-Scope Implementation of an Alternative Accident Source Term (TAC No. MA8065),
March 14, 2001 to GNRO-2012/00014 Page 3 of 3 In addition, GGNS has a variety of means of introducing aqueous pH control chemicals from outside sources into the containment in the event they are necessary. GGNS Emergency Procedures currently contain instructions on how to mix up a batch of sodium pentaborate in the condensate storage tank (CST) with chemicals available in the warehouse and inject this solution into the reactor vessel with the High Pressure Core Spray (HPCS) system or the Reactor Core Isolation Cooling (RCIC) system. The HPCS system can also be aligned to inject this solution directly into the suppression pool. Entergy maintains over 7,000 lbs. each of anhydrous borax and boric acid onsite, which produces approximately 11,000 lbs. of SPB for use if needed.
Attachment 2 GNRO-2012/00014 Grand Gulf Nuclear Station, Unit 1 PROPOSED TECHNICAL SPECIFICATION CHANGES (MARK-UP)
Attachment 2 to SLC System GNRO-2012/00014 3.1.7 Page 1 of 4 3.1 REACTIVITY CONTROL SYSTEMS 3.1.7 Standby Liquid Control (SLC) System LCO 3.1.7 Two SLC subsystems shall be OPERABLE.
Product of Sodium Pentaborate concentration APPLICABILITY: MODES 1 and 2. in weight percent (C) times Boron-10 enrichment in atom percent (E) < 420 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Concentration of boron A.1 Restore concentration 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in solution in Limited of boron in solution Operation region. to Normal Operation 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> region.
AND Restore (C)(E) > 420 A.2 Perform SR 3.1.7.2. Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> B. One SLC subsystem B.1 Restore SLC subsystem 7 days D. inoperable. to OPERABLE status.
D.1 E.1 E. C. Two SLC subsystems C.1 Restore one SLC 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> inoperable. subsystem to OPERABLE status.
for reasons other than Conditions A, B or C.
F. D. Required Action and D.1 Be in MODE 3. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Completion Time not met. F.1 B. Sodium pentaborate solution volume < 4,200 gallons. B.1 Restore Volume to > 4,200 gallons. 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> C. Sodium pentaborate solution temperature < 45oF or C.1 Restore temperature >45oF and <150oF. 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />
> 150oF.
GRAND GULF 3.1-21 Amendment No. 120
Attachment 2 to SLC System GNRO-2012/00014 3.1.7 Page 2 of 4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.7.1 Verify available volume of sodium 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> pentaborate solution is within the limits of Figure 3.1.7-1.
> 4,200 gallons.
SR 3.1.7.2 Verify temperature of sodium pentaborate 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> solution is within the limits of Figure 3.1.7-2.
>45oF and <150oF.
SR 3.1.7.3 Verify temperature of pump suction piping 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> is 75EF and 130EF.
31 days SR 3.1.7.4 Verify continuity of explosive charge. 31 days SR 3.1.7.5 Verify the concentration of boron in 31 days solution is within the limits of Figures 3.1.7-1 and 3.1.7-2. AND Verify the percent weight of sodium pentaborate in solution (C) is < 9.5%. Once within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after water or boron is added to solution AND Once within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after solution temperature is restored to
NOTE----------------------------------- 75EF Sodium pentaborate concentration (C), in weight percent, is determined by the performance of SR 3.1.7.5. Boron-10 45oF enrichment (E), in atom percent, is determined by the performance of SR 3.1.7.9. (continued)
Verify SLC System satisfies the following equation:
(C)(E) > 420 GRAND GULF 3.1-22 Amendment No. 120 to SLC System GNRO-2012/00014 3.1.7 Page 3 of 4 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.1.7.6 Verify each SLC subsystem manual, power 31 days operated, and automatic valve in the flow path that is not locked, sealed, or otherwise secured in position, is in the correct position, or can be aligned to the correct position.
SR 3.1.7.7 Verify each pump develops a flow rate In accordance 41.2 gpm at a discharge pressure with the 1300 psig. Inservice Testing Program 1340 SR 3.1.7.8 Verify flow through one SLC subsystem from 18 months on a pump into reactor pressure vessel. STAGGERED TEST BASIS SR 3.1.7.9 Verify all heat traced piping between 18 months storage tank and pump suction is unblocked.
AND Determine Boron-10 enrichment in atom percent (E). Once within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after pump suction piping temperature is Once within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> restored to after boron is added 75EF to the solution.
INSERT A - New SR 3.1.7.10 GRAND GULF 3.1-23 Amendment No. 120 Next page is 3.1-26.
to GNRO-2012/00014 Page 4 of 4 INSERT A - New SR 3.1.7.10 SR 3.1.7.10 Verify piping between the storage tank and pump suction is not Once within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> blocked. after solution temperature is restored to > 45°F
Attachment 3 GNRO-2012/00014 Grand Gulf Nuclear Station, Unit 1 PROPOSED TECHNICAL SPECIFICATION CHANGES (CLEAN PAGES)
SLC System 3.1.7 3.1 REACTIVITY CONTROL SYSTEMS 3.1.7 Standby Liquid Control (SLC) System LCO 3.1.7 Two SLC subsystems shall be OPERABLE.
APPLICABILITY: MODES 1 and 2.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Product of Sodium A.1 Restore (C)(E) 420 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Pentaborate concentration in weight percent(C) times Boron-10 enrichment in atom percent (E) < 420 B. Sodium pentaborate B.1 Restore volume to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> solution volume 4,200 gallons.
< 4,200 gallons.
C. Sodium pentaborate C.1 Restore temperature 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> solution temperature to 45°F and 150°F.
< 45°F or > 150°F.
D. One SLC subsystem D.1 Restore SLC subsystem 7 days inoperable for reasons to OPERABLE status.
other than Conditions A, B or C.
E. Two SLC subsystems E.1 Restore one SLC 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> inoperable for reasons subsystem to OPERABLE other than Conditions status.
A, B or C.
F. Required Action and F.1 Be in MODE 3. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Completion Time not met.
GRAND GULF 3.1-21 Amendment No. 120
SLC System 3.1.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.7.1 Verify available volume of sodium 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> pentaborate solution is 4,200 gallons.
SR 3.1.7.2 Verify temperature of sodium pentaborate 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> solution is 45°F and 150°F.
SR 3.1.7.3 -------------------NOTE-------------------- 31 days Sodium Pentaborate Concentration (C), in weight percent is determined by the performance of SR 3.1.7.5. Boron-10 enrichment (E), in atom percent is determined by the performance of SR 3.1.7.9.
Verify SLC System satisfies the following equation: (C)(E) 420 SR 3.1.7.4 Verify continuity of explosive charge. 31 days SR 3.1.7.5 Verify the percent weight of sodium 31 days pentaborate in solution (C) is 9.5%.
AND Once within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after water or boron is added to solution AND Once within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after solution temperature is restored to 45°F (continued)
GRAND GULF 3.1-22 Amendment No. 120
SL System 3.1.7 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.1.7.6 Verify each SLC subsystem manual, power 31 days operated, and automatic valve in the flow path that is not locked, sealed, or otherwise secured in position, is in the correct position, or can be aligned to the correct position.
SR 3.1.7.7 Verify each pump develops a flow rate In accordance 41.2 gpm at a discharge pressure with the 1340 psig. Inservice Testing Program SR 3.1.7.8 Verify flow through one SLC subsystem from 18 months on a pump into reactor pressure vessel. STAGGERED TEST BASIS SR 3.1.7.9 Determine Boron-10 enrichment in atom Once within 24 percent (E). hours after boron is added to the solution.
SR 3.1.7.10 Verify piping between the storage tank and Once within 24 the pump suction is not blocked. hours after solution temperature is restored to >
45°F GRAND GULF 3.1-23 Amendment No. 120 Next page is 3.1-26.
Attachment 4 GNRO-2012/00014 Grand Gulf Nuclear Station, Unit 1 CHANGES TO TECHNICAL SPECIFICATION BASES PAGES FOR INFORMATION ONLY
Attachment 4 to GNRO-2012/00014 SLC System B 3.1.7 Page 1 of 1 BASES SURVEILLANCE SR 3.1.7.8 and SR 3.1.7.9 (continued)
REQUIREMENTS Enriched sodium Demonstrating that all heat traced piping between the boron pentaborate solution is solution storage tank and the suction inlet to the injection made by mixing granular, pumps is unblocked ensures that there is a functioning flow enriched sodium path for injecting the sodium pentaborate solution. An pentaborate with water. acceptable method for verifying that the suction piping is Isotopic tests on the unblocked is to pump from the storage tank to the test tank sodium pentaborate and then draining and flushing the piping with demineralized solution to determine the water. The 18 month Frequency is acceptable since there is actual B-10 enrichment a low probability that the subject piping will be blocked must be performed once due to precipitation of the boron from solution in the heat within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after boron traced piping. This is especially true in light of the is added to the solution in daily temperature verification of this piping required by order to ensure that the SR 3.1.7.3. However, if, in performing SR 3.1.7.3, it is B-10 enrichment is determined that the temperature of this piping has fallen adequate. Enrichment below the specified minimum, SR 3.1.7.9 must be performed testing is only required once within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after the piping temperature is when boron addition is restored $ 75EF after the piping temperature has been made since enrichment < 75EF.
change cannot occur by any other processes.
REFERENCES 1. 10 CFR 50.62.
- 2. UFSAR, Section 9.3.5.3.
- 3. GNRI-91/00153, Issuance of Amendment No. 79 to Facility Operating License No. NPF Grand Gulf Nuclear Station, Unit 1, Regarding Standby Liquid Control System Technical Specifications, dated July 30, 1991.
SR 3.1.7.10 Demonstrating that the piping between the boron solution tank and the suction inlet to the injection pumps is not blocked ensures there is a functioning flow path for injecting the sodium pentaborate solution. An acceptable method for verifying the suction piping is not blocked is to pump from the storage tank to the test tank and then drain and flush the piping with demineralized water. If in performing SR 3.1.7.2, the temperature of the sodium pentaborate solution is found to have fallen below the specified minimum of 45°F, SR 3.1.7.10 must be performed once within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after the temperature is restored > 45°F.
GRAND GULF B 3.1-44 Revision No. 1