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MONTHYEARL-PI-11-055, Day Response to NRC Bulletin 2011-01, Mitigating Strategies.2011-06-0909 June 2011 Day Response to NRC Bulletin 2011-01, Mitigating Strategies. Project stage: Request L-PI-11-069, Day Response to NRC Bulletin 2011-01, Mitigating Strategies.2011-07-11011 July 2011 Day Response to NRC Bulletin 2011-01, Mitigating Strategies. Project stage: Request L-PI-11-096, Response to NRC Bulletin 2011-01, Mitigating Strategies, Request for Additional Information (RAI) (TAC Nos. ME6471 and ME64720)2011-12-21021 December 2011 Response to NRC Bulletin 2011-01, Mitigating Strategies, Request for Additional Information (RAI) (TAC Nos. ME6471 and ME64720) Project stage: Request ML12164A8012012-06-15015 June 2012 Closeout of Bulletin 2011-01, Mitigating Strategies Project stage: Other 2011-06-09
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Category:Letter type:L
MONTHYEARL-PI-23-034, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.7.8, Cooling Water (Cl) System,2024-01-0202 January 2024 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.7.8, Cooling Water (Cl) System, L-PI-23-035, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report2023-12-20020 December 2023 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report L-PI-23-033, Supplement to License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 32023-12-0505 December 2023 Supplement to License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 3 L-PI-23-025, License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 32023-09-28028 September 2023 License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 3 L-PI-23-023, Baffle Former Bolts Alternate Aging Management Strategy2023-09-11011 September 2023 Baffle Former Bolts Alternate Aging Management Strategy L-PI-23-018, License Amendment Request to Revise ISFSI Technical Specification 4.4 to Allow Use of a Code Alternative to ASME Code, NB-5130, Examination of Weld Edge Preparation Surfaces, for the TN-40HT2023-07-14014 July 2023 License Amendment Request to Revise ISFSI Technical Specification 4.4 to Allow Use of a Code Alternative to ASME Code, NB-5130, Examination of Weld Edge Preparation Surfaces, for the TN-40HT L-PI-23-006, License Amendment Request to Revise Technical Specification 3.7.8 Required Actions2023-06-22022 June 2023 License Amendment Request to Revise Technical Specification 3.7.8 Required Actions L-PI-23-016, 2022 10 CFR 50.46 LOCA Annual Report2023-06-14014 June 2023 2022 10 CFR 50.46 LOCA Annual Report L-PI-23-010, Annual Report of Individual Monitoring2023-04-27027 April 2023 Annual Report of Individual Monitoring L-PI-23-007, Supplement to Application to Revise Technical Specification Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)2023-03-28028 March 2023 Supplement to Application to Revise Technical Specification Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) L-PI-23-005, CFR 50.55a Requests Nos. 1-RR-5-15 and 2-RR-5-15, Proposed Use of Subsequent ASME Code Edition and Addenda in Accordance with 10 CFR 50.55a(g)(4)(iv)2023-03-0303 March 2023 CFR 50.55a Requests Nos. 1-RR-5-15 and 2-RR-5-15, Proposed Use of Subsequent ASME Code Edition and Addenda in Accordance with 10 CFR 50.55a(g)(4)(iv) L-PI-23-001, Day Steam Generator Tube Inspection Report2023-01-30030 January 2023 Day Steam Generator Tube Inspection Report L-PI-22-047, Resubmittal of Prairie Island Nuclear Generating Plant (PINGP) 2018 Unit 1 180-Day Steam Generator Tube Inspection Report2022-12-21021 December 2022 Resubmittal of Prairie Island Nuclear Generating Plant (PINGP) 2018 Unit 1 180-Day Steam Generator Tube Inspection Report L-PI-22-020, Application to Revise Technical Specification Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)2022-12-0202 December 2022 Application to Revise Technical Specification Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) L-PI-22-040, Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2022-10-0606 October 2022 Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections L-PI-22-037, Updated Approach for Prairie Island Unit 1 and Unit 2 Baffle Former Bolts2022-09-20020 September 2022 Updated Approach for Prairie Island Unit 1 and Unit 2 Baffle Former Bolts L-PI-22-032, CFR 50.46 LOCA Annual Report2022-06-16016 June 2022 CFR 50.46 LOCA Annual Report L-PI-22-033, Response to Request for Additional Information Prairie Island Nuclear Generating Plant, Units 1 and 2, Amendment to Adopt 24-Month Operating Cycles2022-06-10010 June 2022 Response to Request for Additional Information Prairie Island Nuclear Generating Plant, Units 1 and 2, Amendment to Adopt 24-Month Operating Cycles L-PI-22-003, Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2022-06-0707 June 2022 Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections L-PI-22-024, Supplement to Application for License Amendment to Implement 24-Month Operating Cycle2022-03-0707 March 2022 Supplement to Application for License Amendment to Implement 24-Month Operating Cycle L-PI-21-047, Response to Request for Additional Information 24-Month Cycle Amendment Prairie Island Nuclear Generating Plant, Units 1 and 22021-12-0707 December 2021 Response to Request for Additional Information 24-Month Cycle Amendment Prairie Island Nuclear Generating Plant, Units 1 and 2 L-PI-21-045, Response to Request for Additional Information Cooling Water System License Amendment Request2021-11-0404 November 2021 Response to Request for Additional Information Cooling Water System License Amendment Request L-PI-21-029, Exigent License Amendment Request to Revise Technical Specification 3.7.8 to Allow a One-Time Extension of the Completion Time of Required Action B.12021-10-0707 October 2021 Exigent License Amendment Request to Revise Technical Specification 3.7.8 to Allow a One-Time Extension of the Completion Time of Required Action B.1 L-PI-21-006, License Amendment Request to Revise Technical Specification 3.3.1, Reactor Trip System (RTS) Instrumentation, to Incorporate Installed Bypass Test Capability for the Power Range RTS Functions2021-10-0202 October 2021 License Amendment Request to Revise Technical Specification 3.3.1, Reactor Trip System (RTS) Instrumentation, to Incorporate Installed Bypass Test Capability for the Power Range RTS Functions L-PI-21-032, Response to Request for Additional Information Amendment Request to Adopt TSTF-471 and 571-T for Prairie Island2021-09-30030 September 2021 Response to Request for Additional Information Amendment Request to Adopt TSTF-471 and 571-T for Prairie Island L-PI-21-016, Application for License Amendment to Implement 24-Month Operating Cycle2021-08-0606 August 2021 Application for License Amendment to Implement 24-Month Operating Cycle L-PI-21-027, 2020 10 CFR 50.46 LOCA Annual Report2021-06-28028 June 2021 2020 10 CFR 50.46 LOCA Annual Report L-PI-21-023, Independent Spent Fuel Storage Installation - 2020 Annual Radiological Environmental Monitoring Program Report2021-05-14014 May 2021 Independent Spent Fuel Storage Installation - 2020 Annual Radiological Environmental Monitoring Program Report L-PI-21-007, Application to Revise Technical Specifications to Adopt TSTF-471, Eliminate Use of the Term Core Alterations in Actions and Notes2021-04-19019 April 2021 Application to Revise Technical Specifications to Adopt TSTF-471, Eliminate Use of the Term Core Alterations in Actions and Notes L-PI-20-050, Request for a One-Time Exemption from 10 CFR 50, Appendix E, Biennial Emergency Preparedness Exercise Requirements, Due to COVID-19 Pandemic2020-10-0707 October 2020 Request for a One-Time Exemption from 10 CFR 50, Appendix E, Biennial Emergency Preparedness Exercise Requirements, Due to COVID-19 Pandemic L-PI-20-051, Supplement to Application to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position Requirements2020-09-28028 September 2020 Supplement to Application to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position Requirements L-PI-20-026, Response to Request for Additional Information: License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiativ2020-09-0101 September 2020 Response to Request for Additional Information: 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 4 L-PI-20-035, = Request for Revision to Reactor Vessel Material Surveillance Capsule Removal Schedule2020-07-28028 July 2020 = Request for Revision to Reactor Vessel Material Surveillance Capsule Removal Schedule L-PI-20-023, Independent Spent Fuel Storage Installation, Response to Request for Additional Information: License Amendment Request to Expand the Storage Capacity of the Independent Spent Fuel Storage Installation (ISFSI)2020-06-10010 June 2020 Independent Spent Fuel Storage Installation, Response to Request for Additional Information: License Amendment Request to Expand the Storage Capacity of the Independent Spent Fuel Storage Installation (ISFSI) L-PI-20-014, Supplement to License Amendment Request: Expand the Storage Capacity of the Independent Spent Fuel Storage Installation (ISFSI2020-04-29029 April 2020 Supplement to License Amendment Request: Expand the Storage Capacity of the Independent Spent Fuel Storage Installation (ISFSI L-PI-20-004, License Amendment Request to Revise Technical Specifications (TS) to Remove Note I from Limiting Condition for Operating (LCO) 3.4.12 and LCO 3.4.132020-03-30030 March 2020 License Amendment Request to Revise Technical Specifications (TS) to Remove Note I from Limiting Condition for Operating (LCO) 3.4.12 and LCO 3.4.13 L-PI-20-001, License Amendment Request to Address Issues Identified in Westinghouse Nuclear Safety Advisory Letter NSAL-09-5, Revision 1, and NSAL-15-12020-01-29029 January 2020 License Amendment Request to Address Issues Identified in Westinghouse Nuclear Safety Advisory Letter NSAL-09-5, Revision 1, and NSAL-15-1 L-PI-19-041, Application to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position Requirements2019-12-23023 December 2019 Application to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position Requirements L-PI-19-031, License Amendment Request: Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2019-12-16016 December 2019 License Amendment Request: Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b L-PI-19-040, License Amendment Request: Revise Technical Specification 5.5.14 to Permanently Extend Containment Leakage Rate Test Frequency2019-10-0707 October 2019 License Amendment Request: Revise Technical Specification 5.5.14 to Permanently Extend Containment Leakage Rate Test Frequency L-PI-19-038, Submittal of Revised Pressure and Temperature Limits Report2019-09-19019 September 2019 Submittal of Revised Pressure and Temperature Limits Report L-PI-19-037, Response to Request for Additional Information: 10 CFR 50.55a Requests Nos. 1-RR-5-10 and 2-RR-5-10, Proposed Alternative to Reactor Vessel Inservice Inspection (ISI) Intervals2019-09-16016 September 2019 Response to Request for Additional Information: 10 CFR 50.55a Requests Nos. 1-RR-5-10 and 2-RR-5-10, Proposed Alternative to Reactor Vessel Inservice Inspection (ISI) Intervals L-PI-19-025, Request to Approve Site-Specific Probabilistic Risk Assessment (PRA) Model for Flowserve N-Seal Abeyance Seal and Dynamic Testing for the Prairie Island Nuclear Generating Plant (PINGP)2019-08-27027 August 2019 Request to Approve Site-Specific Probabilistic Risk Assessment (PRA) Model for Flowserve N-Seal Abeyance Seal and Dynamic Testing for the Prairie Island Nuclear Generating Plant (PINGP) L-PI-19-029, Supplement to Response to Request for Additional Information: Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components For...2019-08-0505 August 2019 Supplement to Response to Request for Additional Information: Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components For... L-PI-19-002, 10 CFR 50.55a Requests Nos. 1-RR-5-10 and 2-RR-5-10, Proposed Alternative to Reactor Vessel Inservice Inspection (ISI) Intervals for Prairie Island, Unit 1 and Unit 22019-06-13013 June 2019 10 CFR 50.55a Requests Nos. 1-RR-5-10 and 2-RR-5-10, Proposed Alternative to Reactor Vessel Inservice Inspection (ISI) Intervals for Prairie Island, Unit 1 and Unit 2 L-PI-19-014, Response to Request for Additional Information: Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2019-04-29029 April 2019 Response to Request for Additional Information: Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors L-PI-19-003, Request for Revision to Reactor Vessel Material Surveillance Capsule Removal Schedule for Prairie Island Nuclear Generating Plant (PINGP)2019-02-0404 February 2019 Request for Revision to Reactor Vessel Material Surveillance Capsule Removal Schedule for Prairie Island Nuclear Generating Plant (PINGP) L-PI-19-006, Emergency License Amendment Request Regarding One-Time Extension for Technical Specification Completion Time Requirements2019-01-29029 January 2019 Emergency License Amendment Request Regarding One-Time Extension for Technical Specification Completion Time Requirements L-PI-19-005, Online Reference Portal for NRC Review of License Amendment Request to Implement 10 CFR 50.692019-01-15015 January 2019 Online Reference Portal for NRC Review of License Amendment Request to Implement 10 CFR 50.69 L-PI-18-063, Response to Request for Additional Information: Revise License Condition Associated with Implementation of NFPA 8052018-12-0606 December 2018 Response to Request for Additional Information: Revise License Condition Associated with Implementation of NFPA 805 2024-01-02
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Xeel Energy DEC 2.1 *2011 L-PI-11-096 10 CFR ,50.54(f)
U S, Nuclear Regulatory Commission ATTN: Document Control Desk 11555 Rockville Pike Rockville, MD 20852 Prairie Island Nuclear Generating Plant, Units 1 and 2 Dockets 50-282 and 50-306 ' .
Renewed License Nos, DPR-42 and DPR-60 Response to NRC Bulletin 2011-01, "Mitigating Strategies", Request for Additional Information (RAil (TAG Nos. ME6471 and ME6472)
On May 11,2011, the U.S. Nuclear Regulatory Commission (NRC) issued Bulletin 2011-01, "Mitigating strategies", .(Agencywide Docu.ments Access and Management System (ADAMS) ML111250360). The NRC issued this Bulletin to achieve the following objectives:
- 1. To require that addressees provide a comprehensive verification of their compliance with the regulatory requirements of Title 10 ofthe Code of Federal Regulations (10 CFR) Section 50.54(hh)(2),
- 2. To notify addressees about the NRC staff's need for information associatect.with
. licensee mitigating strategies under 10 CFR 50.54(hh)(2) il! light of the recent events at Japan's FUkushima-Daiichi facility in order to determine if 1) additional assessment of program implementation is needed, 2) the current inspection program should be .enhanced, or 3) further regulatory action is warranted, and
- 3. To require that addressees provide a written response to the NRC in accordance with 10 CFR 50.54(f). '
The Bulletin requested each licensee to submit a written response within 30 days and 60 days of the date of the Bulletin. The 3~-day and 60 day response letters were prC?vided by Northern States Power Company, a Minnesota corporation, doing business as Xcel Energy (hereafter "NSPM"), on June 9, 2011, (ADAMS Accession No. ML111610510) and July 11, 2011, (ADAMS Accession No. ML111930159) respectively.
By letter dated November 28, 2011, ADAMS Accession No. ML 1"13220222) NRC Staff 1717 Wakonade Drive East
- Welch, Minnesota 55089*9642 Telephone: 651.388.1121
Document Control Desk Page 2 requested additional information to support their review of th~ July 11, 2011, (ADAMS Accession No. ML111930159) submittal.
The enclosure to this letter provides the response to the NRC Staff RAI for the Prairie Island Nuclear Generating Plant (PINGP) .. NSPM submits this supplement in accordance with the provisions of 10 CFR 50.54(f).
If there are any questions or if additional information is needed, please contact Mr. Dale Vincent, P.E., at 651-388-1121.
Summary of Commitments This letter contains no new commitmen~s and no revisions to existing commitments I declare under penalty of perjury that the foregoing is true and correct.
- h Mark A. Schimmel Site Vice President, Prairie Island Nuclear Generating Plant Northern States Power Company - Minnesota Enclosures (1) cc
- Administrator, Region III, USNRC Project Manager, PINGP, USNRC Resident Inspector, PINGP, USNRC
ENCLOSURE Response to Request for Additional Information (RAt) on NRC Bulletin 2011 ~01, IIMitigating Strategies", An'swers This enClosure provides the response from the Northern Stat~s Power Company, a Minnesota corporation, doing business as Xcel Energy (hereafter "NSPM"), to a Nuclear Regulatory 90mmission (NRC) RAl'provided by letter dated November 28, 2011, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML113220222) regarding the NSPM answers to NRC Bulletin 2011~01 for the Prairie Island Nuclear Gener~ting Plant (PINGP).
The N~C RAI stated:
Background
, Bulletin 2011 ~01, "Mitigating Strategies," requested that each licensee describe ,in detail the maintenance and testing on equipment procured to support the mitigating strategies to ensure that it will be functional when needed. In the' context of the mitigating strategies, these devices are commonly used for '
firefighting, spent fuel pool spray strategies, and as a means to reduce the magnitude of fission product rel~ases. The NRC staff could not determine if you performed activities to ensure that these devices will be functional when needed.
Request for Additional Information Describe in detail the maintenElnce or testing of monitor nozzles, spray nozzles, or similar devices to ensure that they will be functional when needed.
- NSPM response:
A review of the surveillance and test procedures (SPs and TPs) associat~d with the Extensive Damage Mitigating Guidelines (EDMG) determined that the monitor and spray nozzles a'ra inventoried quarterly in accordance with the EDMG equipment Inventory procedur~. Currently the procedure does not r~quire a functional check or inspection to be performed on this equipment.
The industry standard applicable to this equipment, National Fire Protection Association Standard 1962 (NFPA 1962), "Standard for the Inspection, Care, and Use,of Fire Hose, Couplings, and Nozzles and the Service Testing of Fire Hose", 2008 Edition, Section 6.1 uNoz?:les", requires this equipment to be fnspected after each use and at lea~t annually. Specific inspection acceptance criteria are provided in NFPA 1962 Section 6.1. A functional cheqk (performance in~use test) is not required for nozzles.
Page 1 of2
Response to BL 11 01 RAI w
Since current plant procedural requirements do not meet th.e applicable industry standard, an action request was documented and a procedure change initiated in the NSPM Corrective Action Program. The existing quarterly EDMG equipment inventory procedure will be revised to require documentation of inspection results on the Inventory sheet for each nozzle.
The following inspection acceptance criteria, which are provided in NFPA 1962, Section
.6.1, will be listed in the procedure:
- 1. The waterway is clear of obstructions.
- 2. There is no damage to the tip.
- 3. All controls and adjustments operate as designed.
- 4. The shutoff valve, ifso equipped, 'operates as designed and closes off the flow completely. .
- 5. There are no missing or broken parts.
- 6. The thread gasket is in good condition in accordance with Section 6.3 (which requires gaskets to be inspected for presence, fit, and deterioration, and shall not protrude into waterway).
When these proposed changes are completed, the NSPM quarterly EDMG equipment inventory for PINGP will meet orexceed the inspection requirements of NFPA 1962, the applicable ilidustry standard.
Page 2 of 2
Text
Xeel Energy DEC 2.1 *2011 L-PI-11-096 10 CFR ,50.54(f)
U S, Nuclear Regulatory Commission ATTN: Document Control Desk 11555 Rockville Pike Rockville, MD 20852 Prairie Island Nuclear Generating Plant, Units 1 and 2 Dockets 50-282 and 50-306 ' .
Renewed License Nos, DPR-42 and DPR-60 Response to NRC Bulletin 2011-01, "Mitigating Strategies", Request for Additional Information (RAil (TAG Nos. ME6471 and ME6472)
On May 11,2011, the U.S. Nuclear Regulatory Commission (NRC) issued Bulletin 2011-01, "Mitigating strategies", .(Agencywide Docu.ments Access and Management System (ADAMS) ML111250360). The NRC issued this Bulletin to achieve the following objectives:
- 1. To require that addressees provide a comprehensive verification of their compliance with the regulatory requirements of Title 10 ofthe Code of Federal Regulations (10 CFR) Section 50.54(hh)(2),
- 2. To notify addressees about the NRC staff's need for information associatect.with
. licensee mitigating strategies under 10 CFR 50.54(hh)(2) il! light of the recent events at Japan's FUkushima-Daiichi facility in order to determine if 1) additional assessment of program implementation is needed, 2) the current inspection program should be .enhanced, or 3) further regulatory action is warranted, and
- 3. To require that addressees provide a written response to the NRC in accordance with 10 CFR 50.54(f). '
The Bulletin requested each licensee to submit a written response within 30 days and 60 days of the date of the Bulletin. The 3~-day and 60 day response letters were prC?vided by Northern States Power Company, a Minnesota corporation, doing business as Xcel Energy (hereafter "NSPM"), on June 9, 2011, (ADAMS Accession No. ML111610510) and July 11, 2011, (ADAMS Accession No. ML111930159) respectively.
By letter dated November 28, 2011, ADAMS Accession No. ML 1"13220222) NRC Staff 1717 Wakonade Drive East
- Welch, Minnesota 55089*9642 Telephone: 651.388.1121
Document Control Desk Page 2 requested additional information to support their review of th~ July 11, 2011, (ADAMS Accession No. ML111930159) submittal.
The enclosure to this letter provides the response to the NRC Staff RAI for the Prairie Island Nuclear Generating Plant (PINGP) .. NSPM submits this supplement in accordance with the provisions of 10 CFR 50.54(f).
If there are any questions or if additional information is needed, please contact Mr. Dale Vincent, P.E., at 651-388-1121.
Summary of Commitments This letter contains no new commitmen~s and no revisions to existing commitments I declare under penalty of perjury that the foregoing is true and correct.
- h Mark A. Schimmel Site Vice President, Prairie Island Nuclear Generating Plant Northern States Power Company - Minnesota Enclosures (1) cc
- Administrator, Region III, USNRC Project Manager, PINGP, USNRC Resident Inspector, PINGP, USNRC
ENCLOSURE Response to Request for Additional Information (RAt) on NRC Bulletin 2011 ~01, IIMitigating Strategies", An'swers This enClosure provides the response from the Northern Stat~s Power Company, a Minnesota corporation, doing business as Xcel Energy (hereafter "NSPM"), to a Nuclear Regulatory 90mmission (NRC) RAl'provided by letter dated November 28, 2011, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML113220222) regarding the NSPM answers to NRC Bulletin 2011~01 for the Prairie Island Nuclear Gener~ting Plant (PINGP).
The N~C RAI stated:
Background
, Bulletin 2011 ~01, "Mitigating Strategies," requested that each licensee describe ,in detail the maintenance and testing on equipment procured to support the mitigating strategies to ensure that it will be functional when needed. In the' context of the mitigating strategies, these devices are commonly used for '
firefighting, spent fuel pool spray strategies, and as a means to reduce the magnitude of fission product rel~ases. The NRC staff could not determine if you performed activities to ensure that these devices will be functional when needed.
Request for Additional Information Describe in detail the maintenElnce or testing of monitor nozzles, spray nozzles, or similar devices to ensure that they will be functional when needed.
- NSPM response:
A review of the surveillance and test procedures (SPs and TPs) associat~d with the Extensive Damage Mitigating Guidelines (EDMG) determined that the monitor and spray nozzles a'ra inventoried quarterly in accordance with the EDMG equipment Inventory procedur~. Currently the procedure does not r~quire a functional check or inspection to be performed on this equipment.
The industry standard applicable to this equipment, National Fire Protection Association Standard 1962 (NFPA 1962), "Standard for the Inspection, Care, and Use,of Fire Hose, Couplings, and Nozzles and the Service Testing of Fire Hose", 2008 Edition, Section 6.1 uNoz?:les", requires this equipment to be fnspected after each use and at lea~t annually. Specific inspection acceptance criteria are provided in NFPA 1962 Section 6.1. A functional cheqk (performance in~use test) is not required for nozzles.
Page 1 of2
Response to BL 11 01 RAI w
Since current plant procedural requirements do not meet th.e applicable industry standard, an action request was documented and a procedure change initiated in the NSPM Corrective Action Program. The existing quarterly EDMG equipment inventory procedure will be revised to require documentation of inspection results on the Inventory sheet for each nozzle.
The following inspection acceptance criteria, which are provided in NFPA 1962, Section
.6.1, will be listed in the procedure:
- 1. The waterway is clear of obstructions.
- 2. There is no damage to the tip.
- 3. All controls and adjustments operate as designed.
- 4. The shutoff valve, ifso equipped, 'operates as designed and closes off the flow completely. .
- 5. There are no missing or broken parts.
- 6. The thread gasket is in good condition in accordance with Section 6.3 (which requires gaskets to be inspected for presence, fit, and deterioration, and shall not protrude into waterway).
When these proposed changes are completed, the NSPM quarterly EDMG equipment inventory for PINGP will meet orexceed the inspection requirements of NFPA 1962, the applicable ilidustry standard.
Page 2 of 2