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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:Operating Report
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Text
- ~?Entergy Entergy Operations, Inc.
P.O. Box756 Port Gibson, Mississippi 39150 Eric A. Larson Site Vice President Grand Gulf Nuclear Station Tel: 601-437-7500 GNR0-2018/00040 August 20, 2018 10CFR50.59(d)(2)
U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001
SUBJECT:
Report of 10CFR50.59 Evaluation.s and Commitment Change Evaluations - July 1, 2016 through June 30, 2018 '
Grand Gulf Nuclear Station, Unit 1 Docket No. 50-416 License No. NPF-29
Dear Sir or Madam:
Pursuant to 10CFR50.59(d)(2), Entergy Operations, Inc. hereby submits a summary of 50.59 Evaluations and Commitment Change Evaluations for the period of July 1, 2016 through June 30, 2018 in this letter. Attachment 1 contains the 50.59 Evaluation Summary Report, and Attachment 2 contains the Commitment Change Evaluation Summary Report.
If you have any questions or require additional information, please contact Douglas Neve at 601-437-2103.
This letter does not contain any new commitments.
Sincerely, Z:r;;t__
-Eric A. -Larson Site Vice President Grand Gulf Nuclear Station EAL/tdf
Attachment:
- 1. 10CFR50.59 Evaluation Summary Report
- 2. Commitment Change Evaluation Summary Report cc: (See Next Page)
GNR0-2018/00040 Page 2 of 2 cc: NRC Senior Resident Inspector Grand Gulf Nuclear Station Port Gibson, MS 39150 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 U.S. Nuclear Regulatory Commission ATTN: Ms. Jennifer Bridges 1600 East Lamar Boulevard Arlington, TX 76011-4511
GNR0-2018/00040 Attachment 1 to GNRO 2018-00040 10CFRS0.59 Evaluation Summary Report
GNR0~2018/00040 p*age 1 of 1 Grand Gulf Nuclear Station 10CFR50.59 Evaluation Summary Report Evaluation# lnitiatinQ Document 50.59 Summary SE 2016-002 EC 64185-/ Evaluate potential impact of negative pressure in the reactor ROO LBDCR 2016-039 vessel during startup. Since the resulting negative pressure
)
meets the requirements of ASME Section Ill, Subsection NB-3133.3 and 3133.4, prior NRG approval is not required.
SE 2016-005 EC 66685 I Bypass Division 111 emergency diesel engine high crankcase R01 LBDCR 2016-280 pressure trip for 60 seconds on a diesel sta_rt, and bypass all non-critical trips during a bus undervoltage event. Since the result of an actual non-critical condition would be the same with or without the trips in service (i.e., diesel engine shut down to prevent further damage), there is no adverse impact and prior NRG approval is not required.
SE 2016-006 EC 64812 Bypass Standby Service Water (SSW) start upon Residual ROO Temporary Heat Removal Pump manual start_ to provide a_method to*
Modification control SSW basin temperature by controlling SSW fans manually instead of automatically during cold weather conditions. Since automatic operation of SSW upon an ECCS signal remains operable, prior NRG approval is not .
required. \
SE 2017-001 EC 75259 Increase the Reactor Core Isolation Cooling (RCIC) Room ROO High Temperature Isolation time delay from 1 to 10 seconds I
to prevent spurious actuations. Since any increase in offsite dose from ,a RCIC line break would continue to be bounded by a main steam line break, prior NRG approval is not required.
SE 2017-002 EC71136 Evaluate manual operator action to restart Division I & 11 ROO emergency diesels as a compensatory measure upon a high
. crankcase pressure trip in a tornadq.event. Based on actions put in place and a conclusion that potential operator errors *'
would not be detrimental, prior NRG approval is not required.
SE 2017-003 EC 70732 I Install welded blind flange and change Penetration 73 from a
ROO LBDCR 2017-059 Local Leak Rate Test (LLRT) to an Integrated Leak Rate Test (ILRT). Since the design functio~-of the penetration is unaffected, and testing complies with 10CFR50 Appendix J, prror NRG approval is not required.
SE 2017-004 EC 71314 I Designates restricting orifice between makeup water and ROO LBDCR 2017-036 .Standby Liquid Control system as ASME Class~ I 831.1 Piping Boundary. Based on compliance with ANS 52.1 and ReQ Guide 1.26, prior NRG approval is not required.
SE 2018-002 EC 77707 I Cycle 22 Core Operating Limits Report. Base on meeting ROO LBDCR 2018-051 GESTAR II acceptance criteria, there is no impact on fuel LBDCR 2018-057 operating limits or licensing analyses and prior NRG approval is not required.
SE 2018-004 EC 41518 Evaluates using sand bags and operator action as a ROO CR-GGN-2018-4101 compensatory measure for inoperable seals on external doors. The evaluation concluded, based on criteria in NEI 96-70, that prior NRG approval is not required.
GNR0-2018/00040 Attachment 2 to GNRO 2018-00040 Commitment Change Evaluation Summary Report
GNR0-2018/00040 Page 1' of 1 Grand.Gulf Nuclear Station Commitment Change Eyaluation Summary Report Com.mitment
- Date of Original Commitment Justifi.cation of Change Number Commitment A-36142 July 27, 2012 Grand Gulf will follow the generic schedule The due date is revised to provided in the Industry Open Phase Condition 12/31/2018 consistent with NEI NRC Bulletin Initiative. Full Implementation will be achieved document "Industry Initiative on 2012-001 by 12/31/2017 Open Phase Condition, Revision 1,"
dateq March 16, 2015.
A-36209 June 11, 2015 Entergy will confirm that future C/M (calculated- The due date is revised to to-measured) fluence values at the dosimetry November 30, 2018, consistent with GNRO- sample locations are reasonably close to one. NRC Safety Evaluation dated 2015/00038 Due November 30, 2016. August18,2015 A-36210 June 11, 2015 Entergy will include the definition of 11 reasonably The due date *is revised to close to one 11 regarding C/M fluence values at November 30, 2018; consistent with GNRO- .. the dosimetry sample locations. Due November NRC Safety Evaluation dated 2015/00038 30, 2016. August~ 8, 2015 A-36211 June 11, 2015 Entergy will provide plans to address if future The due date is revised to C/M -fluence values at the dosimetry sample December 30, 2018, consistent with GNRO- locations are not reasonably close to one. Due NRG Safety Evaluation dated 2015/00038 December 30, 2016. August18,2015 P-35183 March 15, 2002 B.3.E - Develop and Institute Duress Guidance This commitment is being updated Training by August 31, 2002 to historic. The commitment has GNRO- been implemented and tracked for 2002/00029 more than ten years.
P-24027 June. 28, 1985 Salem ATWS - Equiprnent Classification This commitment is being updated Program for all safety-related Components to historic. The commitment has AECM-85/0201 been implemented and tracked for more than ten years.
P-32713 June 16, 1988 .Plant Procedures will be revised to reference** This commitment is being updated the "COB" [Component Database] for to historic. The commitment has AECM-88/0121
- determining equipment classification been implemented and tracked for more than ten years