Letter Sequence Other |
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Results
Other: GNRO-2013/00015, Overall Integrated Plan in Response to March 12,2012, Commission Order to Modify Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049), GNRO-2013/00016, Overall Integrated Plan in Response to March 12, 2012, Commission Order Modifying License with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051), GNRO-2013/00061, Entergy'S First Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051), GNRO-2015/00005, Entergy'S Fourth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Lnstrumentation (Order Number EA-12-051), GNRO-2016/00006, Notification of Full Compliance with NRC Order EA-12-049 Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049), GNRO-2016/00007, Notification of Full Compliance with NRC Order EA-12-051. Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order EA-12-051), ML12305A207, ML14042A297, ML15237A337, ML15308A298
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MONTHYEARML12305A2072012-10-25025 October 2012 Initial Status Report in Response to March 12,2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) Project stage: Other GNRO-2013/00016, Overall Integrated Plan in Response to March 12, 2012, Commission Order Modifying License with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)2013-02-26026 February 2013 Overall Integrated Plan in Response to March 12, 2012, Commission Order Modifying License with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) Project stage: Other GNRO-2013/00015, Overall Integrated Plan in Response to March 12,2012, Commission Order to Modify Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2013-02-27027 February 2013 Overall Integrated Plan in Response to March 12,2012, Commission Order to Modify Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) Project stage: Other ML13207A1242013-07-30030 July 2013 Request for Additional Information, Overall Integrated Plan in Response to 3/12/2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order No. EA-12-051) Project stage: RAI ML13214A0952013-08-0505 August 2013 Correction to July 30, 2013, Request for Additional Information, Overall Integrated Plan in Response to 3/12/2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order No. EA-12-051) Project stage: RAI GNRO-2013/00061, Entergy'S First Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)2013-08-28028 August 2013 Entergy'S First Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) Project stage: Other GNRO-2013/00057, Response to Request for Additional Information Regarding Overall Integrated Plan for Reliable Spent Fuel Pool Instrumentation (Order EA-12-051)2013-08-29029 August 2013 Response to Request for Additional Information Regarding Overall Integrated Plan for Reliable Spent Fuel Pool Instrumentation (Order EA-12-051) Project stage: Response to RAI ML13316B9862013-11-25025 November 2013 Interim Staff Evaluation and Request for Additional Information Regarding Overall Integrated Plan for Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) Project stage: RAI ML14042A2972014-02-12012 February 2014 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Grand Gulf Nuclear Station, Unit 1, TAC No.: MF0954 Project stage: Other ML14007A7182014-02-19019 February 2014 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) Project stage: Acceptance Review GNRO-2015/00005, Entergy'S Fourth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Lnstrumentation (Order Number EA-12-051)2015-02-18018 February 2015 Entergy'S Fourth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Lnstrumentation (Order Number EA-12-051) Project stage: Other ML15237A3372015-08-27027 August 2015 Plan for the Onsite Audit Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Instrumentation Related to Orders EA-12-049 and EA-12-051 Project stage: Other ML15308A2982015-11-24024 November 2015 Report for the Onsite Audit Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 Project stage: Other GNRO-2016/00007, Notification of Full Compliance with NRC Order EA-12-051. Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order EA-12-051)2016-05-24024 May 2016 Notification of Full Compliance with NRC Order EA-12-051. Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order EA-12-051) Project stage: Other GNRO-2016/00006, Notification of Full Compliance with NRC Order EA-12-049 Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2016-05-24024 May 2016 Notification of Full Compliance with NRC Order EA-12-049 Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) Project stage: Other GNRO-2016/00036, Response to Requests for Additional Information (Rais) Regarding Final Integrated Plan for Implementation of Order EA-12-051, Reliable Spent Fuel Pool Instrumentation2016-07-29029 July 2016 Response to Requests for Additional Information (Rais) Regarding Final Integrated Plan for Implementation of Order EA-12-051, Reliable Spent Fuel Pool Instrumentation Project stage: Response to RAI 2013-08-05
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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
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Text
~Entergy Entergy Operations, Inc.
P.o. Box 756 Port Gibson, MS 39150 Kevin Mulligan Site Vice President Grand Gulf Nuclear Station Tel. (601) 437-7500 GNRO-2016/00007 May 24,2016 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001
SUBJECT:
Notification of Full Compliance with NRC Order EA-12-051 Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order EA 051)
Grand Gulf Nuclear Station, Unit 1 Docket No. 50-416 License No. NPF-29
REFERENCES:
- 1. NRC Order Number EA-12-051, Order to Modify Licenses with Regard to Reliable Spent Fuel Pool (SFP) Instrumentation, dated March 12,
- 2. Entergy Letter to NRC, Overall Integrated Plan in Response to March 12, 2012, Commission Order Modifying License with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051), dated February 26, 2013 (GNRO-2013/00016, ML13064A417)
- 3. NRC Letter to Entergy, Grand Gulf Nuclear Station, Unit 1 - Interim Staff Evaluation and Request for Additional Information Regarding Overall Integrated Plan for Reliable Spent Fuel Pool Instrumentation, dated November 25,2013 (Order Number EA-12-051) (TAC NO.
MF0955)
- 4. NRC Letter to Entergy, Grand Gulf Nuclear Station, Unit 1 - Report for the Onsite Audit Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 (TAC Nos. MF0954 and MF0955), dated November 24, 2015 (ML15308A298)
Dear Sir or Madam:
On March 12, 2012, the NRC issued Order EA-12-051, Order Modifying Licenses with Regard to Reliable Spent Fuel Pool (SFP) Instrumentation (Reference 1), to all power reactor licensees, which is applicable to Entergy Operations, Inc. (Entergy).The Order was effective immediately and
GNRO-2016/00007 Page 2 of 3 directed the installation of reliable SFP instrumentation. Reference 2 provided the response to Section C.1.a which requires that the Licensee submit an Overall Integrated Plan (OIP). This letter, along with its enclosures, provides the notification required by Section C.3 of the Order that full compliance with the Order has been achieved. This letter also provides information updates, as necessary, with respect to References 3 and 4.
This letter contains no new regulatory commitments. Should you have any questions regarding this submittal, please contact Mr. James J. Nadeau at 437-2103.
I declare under penalty of perjury that the foregoing is true and correct; executed on May 24,2016.
Sincerely, KJM/sas Attachments: 1. Compliance with Order EA-12-051
- 2. NRC Requests for Information
- 3. Audit Open Item Response cc: next page
'~\
GNRO-2016/00007 Page 3 of 3 cc: U.S. Nuclear Regulatory Commission ATTN: Mr. Jim Kim, NRR/DORL (w/2)
Mail Stop OWFN 8 B1 Rockville, MD 20852-2738 U.S. Nuclear Regulatory Commission ATTN: Mr. Marc Dapas (w/2)
Regional Administrator, Region IV 1600 East Lamar Boulevard Arlington, TX 76011-4511 Mr. B. J. Smith Director, Division of Radiological Health Mississippi State Department of Health Division of Radiological Health 3150 Lawson Street Jackson, MS 39213 NRC Senior Resident Inspector Grand Gulf Nuclear Station Port Gibson, MS 39150 to GNRO-2016/00007 Compliance with Order EA-12-051 to GNRO-2016/00007 Page 1 of 2 Compliance with Order EA-12-051
1. Background
On March 12,2012, the NRC issued Order EA-12-051, Order Modifying Licenses with Regard to Reliable Spent Fuel Pool (SFP) Instrumentation (Reference 1), to all power reactor licensees, which is applicable to Entergy Operations, Inc. (Entergy). The Order was effective immediately and directed the installation of reliable SFP instrumentation.
Grand Gulf Nuclear Station (GGNS) developed an Overall Integrated Plan (Reference 2) documenting the requirements to install reliable spent fuel pool level instrumentation (SFPI).
The information provided herein documents full compliance with the Order for Grand Gulf Nuclear Station, Unit 1.
- 2. Compliance Grand Gulf has installed two independent full-scale level monitors on the Spent Fuel Pool (SFP) in response to Reference 1.
Entergy submitted the Grand Gulf Overall Integrated Plan (OIP) by letter dated February 26, 2013 (Reference 2). By letter dated November 25, 2013 (Reference 3), the NRC provided the interim staff evaluation and requested additional information necessary for completion of the review. The information requested by the NRC is captured in Attachment 2.
Compliance with NRC Order EA-12-051 was achieved using the guidance in Nuclear Energy Institute (NEI) document NEI 12-02 (Reference 4) which has been endorsed by the NRC (Reference 5).
- 3. References
- 1. NRC Order Number EA-12-051, Order to Modify Licenses with Regard to Reliable Spent Fuel Pool (SFP) Instrumentation, dated March 12, 2012 (ML12054A682)
- 2. Entergy Letter to NRC, Overall Integrated Plan in Response to March 12, 2012, Commission Order Modifying License with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051), dated February 26,2013 (GNRO-2013/00016, ML13064A417)
- 3. NRC Letter to Entergy, Grand Gulf Nuclear Station, Unit 1 - Interim Staff Evaluation and Request for Additional Information Regarding Overall Integrated Plan for Reliable Spent Fuel Pool Instrumentation, dated November 25, 2013 (Order Number EA-12-051) (TAC NO. MF0955)
- 4. NEI 12-02, Rev. 1, Industry Guidance for compliance with NRC Order EA-12-051, "To Modify Licenses with Regard to Reliable Spent Fuel Pool Instrumentation" August, 2012 (ADAMS Accession No. ML12240A307)
- 5. NRC Interim Staff Guidance, JLD-ISG-2012-03, Compliance with Order EA-12-051, Reliable Spent Fuel Pool Instrumentation, August 29, 2012 (ADAMS Accession No. ML12054A682) to GNRO-2016/00007 Page 2 of 2
- 6. Grand Gulf Nuclear Station, Unit 1 - Request for Additional Information Regarding Overall Integrated Plan for Reliable Spent Fuel Pool Instrumentation (Order EA 051) (TAC No. MF0955), dated July 30, 2013 (GNRI-2013/00129)
- 7. Response to Request for Additional Information Regarding Overall Integrated Plan for Reliable Spent Fuel Pool Instrumentation (Order EA-12-051), dated August 29, 2013 (GNRO-2013/00057)
- 8. Grand Gulf Nuclear Station, Unit 1 - Interim Staff Evaluation and Request for Additional Information Regarding Overall Integrated Plan for Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) (TAC NO. MF0955), dated November 25, 2013 (GNRI-2013/00178)
- 9. Entergy Letter to NRC, Entergy's Third Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying License with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051), dated August 27,2014 (GNRO-2014/00055)
- 10. Entergy Letter to NRC, Entergy's Fourth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying License with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051), dated February 18, 2015 (GNRO-2015/00005)
- 11. Grand Gulf Nuclear Station, Unit 1 - Report for the Onsite Audit Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 AND EA-12-051 (TAC NOS, MF0954 AND MF0955), dated November 24, 2015 (ML15308A298).
to GNRO-2016/00007 NRC Requests for Information to GNRO-2016/00007 Page 1 of 2 NRC Requests for Information As stated in Attachment 1, Entergy submitted the Overall Integrated Plan (OIP) for Grand Gulf Nuclear Station (GGNS) by Reference 2 of this attachment.
By Reference 6 of Attachment 1, the NRC provided requests for additional information (RAls) for the OIP. Entergy provided responses to the RAls by Reference 7.
By Reference 8 of Attachment 1, the NRC provided its interim staff evaluation (ISE) and requested additional information necessary for completion of the review. Entergy provided responses to the nineteen (19) ISE RAls by References 9 and 10 of Attachment 1, with Reference 10 containing the design bridging document.
New RAls #20-23 were received prior the onsite audit. RAls #20,21 and 22 were closed during the audit (Reference 11) and responses to these are provided below. RAI #23 was listed as an open item in the audit report and the response is presented in Attachment 3.
RAI #20 EMCcompliance: Please make available for staff review an assessment of potential susceptibilities of EMI/RFI in the areas where the SFP instruments are located and how to mitigate those susceptibilities MOHR reports 1-0410-4 and 1-0410-4-51 demonstrate the new SFPI satisfies the EMI/RFI compliance guidelines of Revision 3 of EPRI TR-102323 in accordance with Entergy Engineering Standard EN-IC-S-004-MULTI. As demonstrated in the SFPI Vendor's (MOHR)
System EMC Test Report and Supplemental Information, the SFPI system passed the High Frequency Radiated and Conducted Emissions testing.
The Lower Cable Room where the displays are located is already a radio exclusion zone. New 3.5 foot exclusion zones around the probes have been painted to prevent radio usage near the pool. Furthermore, FSG-11 governs the use of the SFPI and include a cautionary statement to preclude radio usage within close proximity to the displays.
RAI #21 Please provide further information describing the maintenance and testing program the licensee will establish and implement to ensure that regular testing and calibration is performed and verified by inspection and audit to demonstrate conformance with design and system readiness requirements. Include a description of plans to ensure necessary channel checks, functional tests, periodic calibration, and maintenance will be conducted for the level measurement system and its supporting equipment.
The following is a list of Preventative Maintenance (PM) tasks documenting the Entergy Fleet PM Strategy for the MOHR instrumentation system:
to GNRO-2016/00007 Page 2 of 2 Task Name Objective Frequency of Occurrence Channel Calibration Check To validate that the MOHR 10 (Operator Rounds) instruments (both channels) are displaying the correct spent fuel pool level within the accuracy of the instruments and that the date stamp on the display is indicating correctly.
Channel Check / Panel To check each channel against 1Y Functional Check each other for comparison and to perform functional assessments of each panel.
Signal Processor Clock To prevent failure of the onboard 10Y Battery Replacement clock battery and adverse impact to the signal processor operating system.
By checking each channel to be within the accuracy requirement of 3 inches from actual pool level on a daily frequency, validating all panel indications to be proper and functional on this same frequency including battery power status, and validating functional transfer of AC to DC power yearly, these checks meet or exceed the 6 month and 2 year recommendations of the vendor and will prevent level calibration from falling out of the accuracy requirements of the instrumentation.
RAI #22 Please describe the impact of recent MOHR's SFPI equipment failures (failure of the filter coil (or choke) in particular) on the Grand Gulf's SFP level instrument. Also, any actions/measures to address this equipment failure. The equipment qualifications need to be reevaluated as resulted of changes made to the equipment configurations.
The vendor MOHR has determined the source of the failures is a miniature surface mount common-mode choke component used on the Video and Digicomp printed circuit boards (PCB's) within the EFP-IL Signal Processor. The new boards have equivalent substitute components that are less susceptible to transient electrical events. The substitute components have equivalent size, mass, and solder attachment technique as the original component such that there isno impact to the system mechanical characteristics. The components demonstrate equivalent electrical performance such that EMC characteristics are not significantly changed.
The vendor recommended repair has been implemented on the GGNS system per CR-HQN-2015-0345. Proprietary Mohr Report 1-1010-2: EFP-IL MOD 1 Modification Package addresses continued equipment qualification following the repair.
to GNRO-2016/00007 Audit Open Item Response to GNRO-2016/00007 Page 1 of 1 Audit Open Item Response (RAI #23)
RAI #23 During the onsite audit, the NRC staff noted that the metal conduits for the two SFP level channels were routed within 3 feet of each other (and sometimes less than that) on the north and west walls of the SFP operating floor in the auxiliary building. This does not appear to meet the requirements of Order EA-12-051 that:
"The spent fuel pool level instrument channels shall be arranged in a manner that provides reasonable protection of the level indication function against missiles that may result from damage to the structure over the spent fuel pool. This protection may be provided by locating the primary instrument channel and fixed portions of the backup instrument channel, if applicable, to maintain instrument channel separation within the spent fuel pool
\
area, and to utilize inherent shielding from missiles provided by existing recesses and corners in the spent fuel pool structure."
In the GGNS NRC audit report the NRC documented the need to provide additional protection or separation of some SFPI conduit on the 208 elevation of the auxiliary building refuel floor.
Based on further discussion with the NRC changes to the audited configuration of the SFPI conduit were determined to be unnecessary. This documents the acceptability of the as audited conduit configuration at GGNS.
Unlike a typical BWR Mark I or II refuel floor, a Mark III (GGNS) has a concrete enclosed, seismic qualified structure surrounding the SFP. Given the location inside a robust structure and the evaluated absence of credible internal missiles, GGNS used a minimum of 3'-0" separation between Channel-A and Channel-B Spent Fuel Pool Instrumentation (SFPI) conduits with one exception. The exception is a short run in the elevator area where intervening structures are credited. A minimum 3'-0" distance is considered to maintain reasonable separation to meet the requirements of NRC Order EA-12-051. This is based on the conduit separation meeting the plant design basis for missile hazards for safety related circuits because there are no credible missile hazards in the area that could affect these conduits. The specific reasons a minimum of 3'-0" separation is acceptable is because:
- The conduits a're installed on the inside walls of a Seismic Category I concrete structure providing protection from all external hazards.
- Permanently installed equipment located on the refuel floor has been evaluated for internal missile hazards.
o No credible internal hazards exist due to the location of installed equipment on the refuel floor.
o Overhead cranes in the area of interest are seismically qualified.
- Procedural guidance provides reasonable assurance that there will be no transient missile hazards in the area.
Additionally, in the area of concern where minimum separation is used, i.e. 3'-0", intervening structures provide additional assurance that randomly postulated missiles will not simultaneously damage both redundant channels of instrumentation. Also, this area is a narrow pathway next to the SFP that is not conducive to its use as an equipment storage/work area.