Letter Sequence Request |
---|
TAC:MF2798, Clarify Application of Setpoint Methodology for LSSS Functions (Approved, Closed) |
|
MONTHYEARGNRO-2013/00012, Maximum Extended Load Line Limit Analysis Plus (Mellla+), License Amendment Request2013-09-25025 September 2013 Maximum Extended Load Line Limit Analysis Plus (Mellla+), License Amendment Request Project stage: Request ML13345A1822013-12-19019 December 2013 Supplemental Information Needed for Acceptance of Licensing Action, Request to Revise Technical Specification to Allow Operation in Expanded Maximum Extended Load Line Limit Analysis Plus (Mellla+) Domain Project stage: Acceptance Review ML13364A2862013-12-30030 December 2013 Maximum Extended Load Mine Limit Analysis Plus (Mella+) License Amendment Request-Responses to Requests for Supplemental Information Project stage: Supplement ML14023A5802014-01-23023 January 2014 NRR E-mail Capture - Acceptance Review of Grand Guld Nuclear Station License Amendment Request Regarding Maximum Extended Load Line Limit Analysis Plus Project stage: Acceptance Review ML14037A1492014-02-0606 February 2014 NRR E-mail Capture - Grand Gulf Nuclear Station Request for Additional Information Regarding Maximun Extended Load Line Limit Plus Amendment Request Project stage: RAI GNRO-2014/00024, Response to Request for Additional Information Regarding Maximum Extended Load Line Limit Plus Amendment Request, Dated 2/6/20142014-03-10010 March 2014 Response to Request for Additional Information Regarding Maximum Extended Load Line Limit Plus Amendment Request, Dated 2/6/2014 Project stage: Response to RAI ML14080A2722014-03-18018 March 2014 NRR E-mail Capture - Grand Gulf Nuclear Station Request for Additional Information Regarding Maximun Extended Load Line Limit Plus Amendment Request Project stage: RAI ML14119A0092014-04-28028 April 2014 NRR E-mail Capture - Grand Gulf Nuclear Station Audit Plan Regarding Maximun Extended Load Line Limit Plus Amendment Request Project stage: Other ML14101A0432014-05-0808 May 2014 Request for Withholding from Public Disclosure - 12/19/2013 Affidavit Executed by L. Dolan, GE-Hitachi Nuclear Energy Americas LLC Related to Responses to Request for Supplemental Information Project stage: Other ML14101A0872014-05-0808 May 2014 Request for Withholding from Public Disclosure - 9/10/2013 Affidavit Executed by P. Yandow, GE-Hitachi Nuclear Energy Americas LLC Related to Nedc - 33612P, Revision 0 Project stage: Other ML14140A3012014-05-19019 May 2014 NRR E-mail Capture - Grand Gulf Nuclear Station, Unit 1, Request for Additional Information Regarding Maximum Load Line Limit Analysis Plus Project stage: RAI ML14211A1362014-07-30030 July 2014 NRR E-mail Capture - Grand Gulf Nuclear Station Request for Additional Information Regarding Maximun Extended Load Line Limit Plus Amendment Request Project stage: RAI GNRO-2014/00051, Response to Request for Additional Information Regarding Maximum Extended Load Line Limit Plus Amendment Request Dated 7/2/20142014-08-14014 August 2014 Response to Request for Additional Information Regarding Maximum Extended Load Line Limit Plus Amendment Request Dated 7/2/2014 Project stage: Response to RAI GNRO-2014/00045, Response to Request for Additional Information Regarding Maximum Extended Load Line Limit Plus Amendment Request, Dated 5/19/20142014-08-26026 August 2014 Response to Request for Additional Information Regarding Maximum Extended Load Line Limit Plus Amendment Request, Dated 5/19/2014 Project stage: Response to RAI GNRO-2014/00064, Superseding Response to Request for Additional Information Regarding Maximum Extended Load Line Limit Plus Amendment Request, Dated 3/18/20142014-09-0404 September 2014 Superseding Response to Request for Additional Information Regarding Maximum Extended Load Line Limit Plus Amendment Request, Dated 3/18/2014 Project stage: Response to RAI GNRO-2014/00052, Response to Electronic Request for Additional Information Regarding Maximum Extended Load Line Limit Plus Amendment Request, Dated 7/29/20142014-09-10010 September 2014 Response to Electronic Request for Additional Information Regarding Maximum Extended Load Line Limit Plus Amendment Request, Dated 7/29/2014 Project stage: Request ML14265A4222014-10-23023 October 2014 Request for Withholding from Public Disclosure - 6/25/14 Affidavit Executed by J. Harrison, GE-Hitachi Nuclear Energy Americas LLC Related to Attachment 3 to GNRO-2014/00045 Dated 8/26/14 Project stage: Other ML14265A3842014-10-23023 October 2014 Request for Withholding from Public Disclosure - 6/19/14 Affidavit Executed by P. Yandow, GE-Hitachi Nuclear Energy Americas LLC Related to Attachment 1 to GNRO-2014/00045 Dated 8/26/14 Project stage: Other ML14265A3702014-10-23023 October 2014 Request for Withholding from Public Disclosure - 7/1/14 Affidavit Executed by P. Yandow, GE-Hitachi Nuclear Energy Americas LLC Related to Attachment 1 to GNRO-2014/00064 Dated 9/4/14 Project stage: Other ML14111A0582014-10-23023 October 2014 Request for Withholding from Public Disclosure - 3/4/14 Affidavit Executed by P. Yandow, GE-Hitachi Nuclear Energy Americas LLC Related to Enclosure to GNRO-2014/00024 Responses to Request for Additional Information Project stage: RAI ML14262A3972014-11-12012 November 2014 Request for Withholding from Public Disclosure - 7/22/14 Affidavit Executed by J. Harrison, GE-Hitachi Nuclear Energy Americas LLC Related to Enclosure 1 to GNRO-2014/00051 Dated 8/14/14 Project stage: Other ML14262A3722014-11-12012 November 2014 Request for Withholding from Public Disclosure - 8/20/14 Affidavit Executed by J. Harrison, GE-Hitachi Nuclear Energy Americas LLC Related to Attachment 1 to GNRO-2014/00052 Dated 9/10/14 Project stage: Other ML14260A1302014-11-25025 November 2014 April 23-25, 2014, Audit Report Regarding Maximum Extended Load Line Limit Analysis Plus Amendment Including Minimum Stable Film Boiling Temperature and Quench Model Project stage: Other GNRO-2014/00083, Traversing Incore Probe (TIP) Comparisons TIP Comparisons for Current Operating Conditions in Support of the Grand Gulf Nuclear Station (GGNS) Maximum Extended Load Line Limit Analysis Plus (Mellla+) License Amendment Request2014-12-15015 December 2014 Traversing Incore Probe (TIP) Comparisons TIP Comparisons for Current Operating Conditions in Support of the Grand Gulf Nuclear Station (GGNS) Maximum Extended Load Line Limit Analysis Plus (Mellla+) License Amendment Request Project stage: Request GNRO-2014/00088, Response to Item 20 Request for Additional Information Regarding Maximum Extended Load Line Limit Plus Amendment Request, Dated 5/19/20142015-01-20020 January 2015 Response to Item 20 Request for Additional Information Regarding Maximum Extended Load Line Limit Plus Amendment Request, Dated 5/19/2014 Project stage: Request GNRO-2015/00003, Response to Item 25 Request for Additional Information Regarding Maximum Extended Load Line Limit Plus, Amendment Request, Dated 5/19/20142015-02-0909 February 2015 Response to Item 25 Request for Additional Information Regarding Maximum Extended Load Line Limit Plus, Amendment Request, Dated 5/19/2014 Project stage: Request GNRO-2015/00011, Supplement to License Amendment Request Application to Revise the Current Methodology from 0 EFPY Through the End of Extended Operations to a Single Fluence Method2015-02-18018 February 2015 Supplement to License Amendment Request Application to Revise the Current Methodology from 0 EFPY Through the End of Extended Operations to a Single Fluence Method Project stage: Supplement ML15050A0772015-02-19019 February 2015 Request to Convert Regulatory Commitments for Time Critical Operator Actions Listed in Letter GNRO-2015/00003, Response to Item 25 Request for Additional Information Regarding Maximum Extended Load Line Limit. Project stage: Request ML15040A1262015-03-19019 March 2015 Request for Withholding Information from Public Disclosure - 10/30/14 Affidavit Executed by James F. Harrison, GE-Hitachi Nuclear Energy Americas LLC, Related to Attachment 1 to GNRO-2014/00088 Dated 1/20/15 (TAC MF27 Project stage: Withholding Request Acceptance ML15085A2272015-04-14014 April 2015 October 15, 2014, Onsite Audit Report Regarding Maximum Extended Load Line Limit Analysis Plus Project stage: Other ML15040A0932015-06-24024 June 2015 Request for Withholding Information from Public Disclosure-10/12/14 Affidavit Executed by James F. Harrison, GE-Hitachi Nuclear Energy Amenricas LLC Related to Attachment 1 to GNRO-2014/00083 Dated 12/15/2014 (MF2798) Project stage: Withholding Request Acceptance 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 Project stage: Request ML15229A2192015-08-31031 August 2015 Redacted, Issuance of Amendment Maximum Extended Load Line Limit Analysis Plus License Amendment Request Project stage: Approval 2014-05-08
[Table View] |
|
---|
Category:Letter type:GNRO
MONTHYEARGNRO-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 GNRO-2018/00040, Report of 10CFR50.59 Evaluations and Commitment Change Evaluations - July 1, 2016 Through June 30, 20182018-08-20020 August 2018 Report of 10CFR50.59 Evaluations and Commitment Change Evaluations - July 1, 2016 Through June 30, 2018 2023-06-06
[Table view] |
Text
~
~Entergy Entergy Operations, Inc.
P. O. Box 756 Port Gibson, MS 39150 Kevin Mulligan Site Vice President Grand Gulf Nuclear Station Tel. (601) 437-7400 GNRO-2015/00003 February 9, 2015 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001
SUBJECT:
Response to Item 25 Request for Additional Information Regarding "Maximum Extended Load Line Limit Plus" Amendment Request, dated 5/19/2014.
Grand Gulf Nuclear Station, Unit 1 Docket No. 50-416 License No. NPF-29
REFERENCES:
1 Electronic Request for Additional Information Regarding "Maximum Extended Load Line Limit Plus" Amendment Request Dated 5/19/2014 (TAC MF2798) 2 Entergy Letter, "Maximum Extended Load Line Limit Analysis Plus (MELLLA+) License Amendment Request," GNRO-2013/00012, dated September 25,2013 (ADAMS Accession No. ML13269A140).
3 Entergy Letter, "Response to Request for Additional Information Regarding Maximum Extended Load Line Limit Plus Amendment Request," GNRO-2014/00045, dated 8/27/14 (ADAMS Accession No. ML14239A184).
4 Entergy Letter, "Response to Item 20 Request for Additional Information Regarding MELLLA+ Amendment Request, (GNRO-2014/00088).
Dear Sir or Madam:
Entergy Operations, Inc. is providing in the Attachments a response to the Reference 1 Request for Additional Information (RAI) 25, Item 2. RAI 25, Item 2 discusses Operator Training status and schedule for operating in the MELLLA+ operating domain. All other items with regard to this RAI were previously answered via References 3 & 4.
GNRO-2015-00003 Page 1 of 1 This letter contains new commitments, which are identified in Attachment 2. If you have any questions or require additional information, please contact Mr. James Nadeau at 601-437-2103.
I declare under penalty of perjury that the foregoing is true and correct; executed on February 9, 2015.
Sincerely, KJM/ras Attachments: 1. Response to RAI 25, Item 2 of the 5/19/14 MELLLA+ LAR Request for Additional Information
- 2. List of Regulatory Commitments cc: with Attachments u.S. Nuclear Regulatory Commission ATTN: Mr. Marc L. Dapas Regional Administrator, Region IV 1600 East Lamar Boulevard Arlington, TX 76011-4511 u.S. Nuclear Regulatory Commission ATTN: Mr. A. Wang, NRR/DORL Mail Stop OWFN/8 B1 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Grand Gulf Nuclear Station Port Gibson, MS 39150 State Health Officer Mississippi Department of Health P. O. Box 1700 Jackson, MS 39215-1700
Attachment 1 to GNRO-2015/00003 Response to RAI 25, Item 2 of the 5/19/14 MELLLA+ LAR Request for Additional Information GNRO-2015-00003 Page 1 of 1 RA125.0 Simulator Update
- 2. Provide the schedule when the GGNS Simulator will be completely ,updated for operators' training in the MELLLA+ operating domain.
Response: The GGNS Simulator is currently completely updated for operator's training in the MELLLA+ operating domain. Prior to final MELLLA+ implementation, Grand Gulf Nuclear Station (GGNS) will train all active operating crews to perform all three time-critical operator actions which will be validated prior to MELLLA+ operations. GGNS will test and confirm the operating crew's ability to perform the most time-constrained operator action in less than 90 seconds to ensure that there is time margin available. The results of the simulator testing will be reported to the NRC within 60 days of the completion of testing and will include the full range of response times for each time-critical action, and the average times for each crew. Any failures will be reported to the NRC with a plan for resolution of the discrepancy. Any identified discrepancies will be resolved with the NRC staff before MELLLA+ implementation can start. Additionally, if GGNS decides to make some or all of the time-critical actions "immediate actions", it should be reported to the NRC along with the results of the simulator testing.
Attachment 2 to GNRO-2015/00003 List of Regulatory Commitments GNRO-2015-00003 Page 1 of 2 LIST OF REGULATORY COMMITMENTS This table identifies actions discussed in this letter for which Entergy commits to perform. Any other actions discussed in this submittal are described for the NRC's information and are not commitments.
GGNS will train all active operating crews to perform the following three MELLLA+ time-critical operator actions:
Initiate Reactor Water Level Reduction (90 seconds following failure to scram concurrent Prior to Operation in with no reactor recirculation pumps in service the MELLLA+
and CTP > 5%).
domain Initiate Standby Liquid Control Injection (300 seconds if CTP > 5% or before Suppression Pool Temperature reaches 110 degrees F).
Initiate Residual Heat Removal Suppression Pool Coolin 660 seconds.
ATWSllnstability Mitigation - Reactor Water Level Reduction Delay:
GGNS will train all active operating crews to Prior to Operation in initiate reactor water level reduction within 90 the MELLLA+
seconds (as opposed to current GEH analysis of 4 domain 120 seconds) of recognition of failure to SCRAM concurrent with no reactor recirculation pumps in service and CTP > 5%.
GGNS will validate that all active operating Prior to Operation in crews have met the time requirements for the the MELLLA+
three MELLLA+ time-critical operator actions domain durin evaluated scenarios.
The results of the three MELLLA+ time-critical Within 60 days of the operator actions training will be reported to the completion of training NRC.
GNRO-2015-00003 Page 2 of 2 The NRC reported results of the MELLLA+ time-critical operator action training will include the Within 60 days of the full range of response times for each time-critical completion of training action, and the avera e times for each crew.
Any ATWS time-critical operator training failures Within 60 days of the during evaluated scenarios will be reported to completion of training the NRC with a Ian for resolution.
GGNS will report any ATWS time-critical actions Within 60 days of any that are converted to "immediate actions" to the conversions NRC.