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Category:Letter type:L
MONTHYEARL-PI-24-044, Application to Revise Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program2024-10-21021 October 2024 Application to Revise Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program L-PI-24-040, Post-Submittal Package Letter2024-08-23023 August 2024 Post-Submittal Package Letter L-PI-24-036, – Preparation and Scheduling of Operator Licensing Examinations2024-06-28028 June 2024 – Preparation and Scheduling of Operator Licensing Examinations L-PI-24-031, Independent Spent Fuel Storage Installation, Supplement to License Amendment Request to Revise Independent Spent Fuel Storage Installation (ISFSI) License Conditions 23(a), 24(A)(2), and 24(B)(2)2024-06-0505 June 2024 Independent Spent Fuel Storage Installation, Supplement to License Amendment Request to Revise Independent Spent Fuel Storage Installation (ISFSI) License Conditions 23(a), 24(A)(2), and 24(B)(2) L-PI-24-014, License Amendment Request to Revise the Technical Specification Definition of Reactor Trip System (RTS) Response Time and Apply Response Time Testing to RTS Trip Functions with Time Delay Assumption2024-06-0303 June 2024 License Amendment Request to Revise the Technical Specification Definition of Reactor Trip System (RTS) Response Time and Apply Response Time Testing to RTS Trip Functions with Time Delay Assumption L-PI-24-030, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.8.12024-05-22022 May 2024 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.8.1 L-PI-24-012, Independent Spent Fuel Storage Installation - License Amendment Request: Revise Independent Spent Fuel Storage Installation (ISFSI) License Conditions 23(a), 24(A)(2), and 24(B)(2)2024-04-0202 April 2024 Independent Spent Fuel Storage Installation - License Amendment Request: Revise Independent Spent Fuel Storage Installation (ISFSI) License Conditions 23(a), 24(A)(2), and 24(B)(2) L-PI-24-004, Independent Spent Fuel Storage Installation - Annual Effluent Report, January Through December 20232024-02-29029 February 2024 Independent Spent Fuel Storage Installation - Annual Effluent Report, January Through December 2023 L-PI-24-009, Response to Request for Additional Information Prairie Island Nuclear Generating Plant, Unit 2, Alternative RR-09 Safety Injection System and Volume Control System Category C Check Valve Quarterly Testing2024-02-13013 February 2024 Response to Request for Additional Information Prairie Island Nuclear Generating Plant, Unit 2, Alternative RR-09 Safety Injection System and Volume Control System Category C Check Valve Quarterly Testing L-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-23-027, Revision to 10 CFR 50.55a Requests Nos. 1-RR-5-10 and 2-RR-5-10, Proposed Alternative to Reactor Vessel Inservice Inspection (ISI) Intervals2023-10-0303 October 2023 Revision to 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-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 2024-08-23
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Xcel Energy@ Prairie Island Nuclear Generating Plant 1717 Wakonade Drive East Welch, MN 55089 JUN 17 2013 L-PI-13-046 10 CFR 50.4 u.s. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Prairie Island Nuclear Generating Plant Units 1 and 2 Docket Nos. 50-282 and 50-306 Renewed License Nos. DPR-42 and DPR-60 Commitment for Implementation of Multi-UnitlMulti-Source Dose Assessment Capability
References:
- 1. us NRC Fukushima Near-Term Task Force Report, "Recommendations for Enhancing Reactor Safety in the 21 st Century, the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident," dated July 12, 2011 (ADAMS Accession No. ML112510271).
- 2. Nuclear Energy Institute (NEI) letter to NRC, "Industry Implementation of Multi-Unit Dose Assessment Capability," dated January 28,2013 (ADAMS Accession No. ML13028A200).
- 3. NRC letter to NEI dated February 27, 2013 (ADAMS Accession No. ML13029A632).
- 4. NElletter to NRC, "Commitment for Implementation of Multi-Unit Dose Assessment Capability," dated March 14,2013 (ADAMS Accession No. ML13073A522).
The NRC Fukushima Near-Term Task Force (NTTF) Report (Reference 1) dated July 12, 2011, discussed the gap in capability for US commercial nuclear power plants to perform multi-unit dose assessments. In January 2013, NEI provided to the NRC (Reference 2) survey results regarding licensees' capabilities to perform multi-unit dose assessments, implementation time frames to obtain multi-unit dose assessment capability, and compensatory measures for the interim period. The NRC requested further detailed information (Reference 3) regarding the current and the anticipated
Document Control Desk Page 2 capabilities of sites to perform multi-unit dose assessment. NEI informed the NRC (Reference 4) that the industry had elected to provide the requested details directly to the NRC staff.
Northern States Power Company, a Minnesota corporation, d/b/a Xcel Energy (hereafter "NSPM") is providing the requested details on behalf of the Prairie Island Nuclear Generating Plant (PINGP). The enclosure to this letter includes discussion of the current capability to perform multi-unitlmulti-source dose assessments, the interim compensatory measures for this capability, and the final permanent solution. Also included is a milestone implementation schedule with target dates that covers both the implementation of the interim measures and the permanent solution.
Please contact Lynne Gunderson, Licensing Engineer, at 612-396-0173, if additional information or clarification is required.
Summary of Commitments:
This letter makes one new commitment and no revisions to existing commitments:
- NSPM commits to having multi-unitlmulti-source dose assessment capability for PINGP no later than December 31,2014. This commitment date is contingent upon the release of the revised RASCAL dose assessment model by November 30, 2013.
Ia:t::-
Site Vice President, Prairie Island Nuclear Generating Plant Northern States Power Company - Minnesota Enclosure cc: Administrator, Region III, USNRC Director of Nuclear Reactor Regulation (NRR), USNRC NRR Project Manager, PINGP, USNRC Senior Resident Inspector, PINGP, USNRC Director, Nuclear Security and Incident Response, USNRC Director, Japan Lessons Learned Project Directorate (NRR), USNRC
ENCLOSURE Prairie Island Nuclear Generating Plant Units 1 and 2 Commitment for Implementation of Multi-UnitlMulti-Source Dose Assessment Capability Page 1 of 4
Prairie Island Nuclear Generating Plant Units 1 and 2 Commitment for Implementation of Multi-UnitlMulti-Source Dose Assessment Capability 1.0 Introduction The NRC Fukushima Near-Term Task Force (NTTF) Report (Reference 1) dated July 12, 2011, discussed the gap in capability for US commercial nuclear power plants to perform multi-unit dose assessments. In January 2013, the Nuclear Energy Institute (NEI) sent a letter to NRC (Reference 2) that reported survey results regarding licensees' current capabilities to perform multi-unit dose assessments. The NEI letter also discussed licensees' expected implementation time frames and compensatory measures for the interim period. The NRC requested further detailed information (Reference 3) regarding the current and anticipated capabilities of sites to perform multi-unit dose assessments. NEI informed the NRC (Reference 4) that the industry had elected to provide the requested details directly to the NRC staff. The requested details were to include:
- A summary of the current capability to perform multi-unitlmulti-source dose assessments.
- The anticipated schedule to establish the capability on an interim and/or permanent basis.
- Due dates associated with each key schedule action or milestone.
- A description of how the implementation schedule will be tracked.
Northern States Power Company, a Minnesota corporation, d/b/a Xcel Energy (hereafter "NSPM") provides the responses below on behalf of the Prairie Island Nuclear Generating Plant (PINGP).
2.0 Summary of Current Multi-UnitlMulti-Source Capability NSPM currently has the capability to perform a multi-unitlmulti-source dose assessment by performing individual dose assessment runs for each release point and manually summing the results to make estimates. These estimates could be used for Emergency Action Level (EAL) and Protective Action Recommendation (PAR) determinations. This capability is in line with the compensatory measures described by NEI in the Reference 2 letter.
NSPM currently uses the NRC dose assessment model RASCAL (Radiological Assessment for Consequence Analysis), Version 4.1, for dose assessment at the PINGP. RASCAL is loaded on multiple computers and there is sufficient depth of trained dose assessment personnel in the Emergency Response Organization (ERO) to perform the multiple dose assessment runs.
NSPM evaluated the current procedural guidance and ERO training for multi-unitlmulti-source dose assessment capability at PINGP. Current procedures contain generic statements regarding combining multi-unit/multi-source release rates. However, it was determined that the current procedural guidance and ERO training for performing dose Page 2 of 4
Prairie Island Nuclear Generating Plant Units 1 and 2 Commitment for Implementation of Multi-UnitlMulti-Source Dose Assessment Capability assessments does not contain the detail necessary to ensure combining the multiple dose assessment runs and generating consistent EAL and PAR decision making for multi-unitlmulti-source releases.
3.0 Interim Measures Based on the evaluation discussed in Section 2.0 above, NSPM will be updating procedures and ERO training to clarify and enhance the multi-unit/multi-source dose assessment capability as an interim measure until the permanent solution is achieved.
The procedure enhancements and ERO training for the interim measures are in progress and will be implemented by September 27,2013.
4.0 Permanent Solution NSPM's permanent solution is to implement the next expected revision of NRC's RASCAL dose assessment model that will be capable of performing the multiple release point modeling. Along with implementation of the revised RASCAL model, the necessary procedure changes will be made and the necessary ERO training will be conducted.
NSPM commits to having multi-unitlmulti-source dose assessment capability no later than December 31, 2014. This commitment date is contingent upon the release of the revised RASCAL dose assessment model by November 30,2013.
5.0 Schedule The table below contains the schedule milestones for ensuring interim capability and for implementation of the permanent solution. Target dates are provided for each schedule milestone.
NSPM is tracking the schedule milestones below in the PINGP Corrective Action Program (CAP) Action Request No. 01386421.
Schedule Milestones Target Date Interim Actions Complete procedure revisions for enhancing multi-unitlmulti- September 27, 2013 source dose assessment.
Complete ERO training regarding multi-unitlmulti-source dose September 27,2013 assessment.
Permanent Solution "
Install updated RASCAL software/perform software acceptance. May 30,2014 Complete procedure revisions and initial ERO training. June 27,2014 Implement updated RASCAL dose assessment model. July 31,2014 Page 3 of 4
Prairie Island Nuclear Generating Plant Units 1 and 2 Commitment for Implementation of Multi-UnitlMulti-Source Dose Assessment Capability 6.0 References
- 1. US NRC Fukushima Near-Term Task Force Report, "Recommendations for Enhancing Reactor Safety in the 21 st Century, the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident," dated July 12,2011 (ADAMS Accession No. ML112510271).
- 2. NElletter to NRC, "Industry Implementation of Multi-unit Dose Assessment Capability," dated January 28, 2013 (ADAMS Accession No. ML13028A200).
- 3. NRC letter to NEI dated February 27,2013 (ADAMS Accession No. ML13029A632).
- 4. NEI letter to NRC, "Commitment for Implementation of Multi-Unit Dose Assessment Capability," dated March 14, 2013 (ADAMS Accession No. ML13073A522).
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