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MONTHYEARML11236A1342011-07-31031 July 2011 Westinghouse WCAP-17400-NP, Rev. 0, Prairie Island, Units 1 and 2 Spent Fuel Pool Criticality Safety Analysis, Enclosure 4 Project stage: Request L-2011-409, Revision to Extended Power Uprate License Amendment Request Proposed Technical Specification Regarding Fuel Loading Curve and Areal Density Criteria for Metamic Inserts2011-10-14014 October 2011 Revision to Extended Power Uprate License Amendment Request Proposed Technical Specification Regarding Fuel Loading Curve and Areal Density Criteria for Metamic Inserts Project stage: Request ML1125602172011-10-25025 October 2011 Request for Withholding of Proprietary Information from Public Disclosure Project stage: Withholding Request Acceptance ML1206203892012-03-20020 March 2012 Request for Additional Information Related to License Amendment Request for Spent Fuel Pool Criticality Changes Project stage: RAI L-2012-132, Extended Power Uprate License Amendment Request - Supplement to Proposed Technical Specification Changes Related to Spent Fuel Storage Requirements and Core Operating Limits Report (COLR) References2012-03-31031 March 2012 Extended Power Uprate License Amendment Request - Supplement to Proposed Technical Specification Changes Related to Spent Fuel Storage Requirements and Core Operating Limits Report (COLR) References Project stage: Supplement L-PI-12-038, Westinghouse, Affidavit - CE-12-3 16, Revision 1, Westingliouse Suggested Responses to the Requests for Additional Information Presented in ML120620389.2012-05-0303 May 2012 Westinghouse, Affidavit - CE-12-3 16, Revision 1, Westingliouse Suggested Responses to the Requests for Additional Information Presented in ML120620389. Project stage: Other ML12139A1982012-05-16016 May 2012 Response to Requests for Additional Information (RAI) Associated with Spent Fuel Pool Criticality Changes (TAC Nos. ME6984 and ME69851) Project stage: Response to RAI ML12215A2522012-08-0707 August 2012 Request for Additional Information Related to License Amendment Request for Spent Fuel Pool Criticality Changes Project stage: RAI L-PI-12-066, Enclosure 2 to L-PI-12-066 - Westinghouse Affidavit, Application for Withholding Proprietary Information from Public Disclosure2012-08-27027 August 2012 Enclosure 2 to L-PI-12-066 - Westinghouse Affidavit, Application for Withholding Proprietary Information from Public Disclosure Project stage: Request ML12249A0692012-09-0404 September 2012 Response to Requests for Additional Information (RAI) Associated with Spent Fuel Pool Criticality Changes Project stage: Response to RAI ML13011A3162013-01-22022 January 2013 Request for Additional Information Related to License Amendment Request for Spent Fuel Pool Criticality Changes Project stage: RAI L-PI-13-002, Response to Request for Additional Information (RAI) Associated with Spent Fuel Pool Criticality Changes2013-02-0808 February 2013 Response to Request for Additional Information (RAI) Associated with Spent Fuel Pool Criticality Changes Project stage: Response to RAI ML13197A3972013-06-25025 June 2013 NRR E-mail Capture - Prairie Island Ngp - Sfpc LAR Draft RAI Project stage: Draft Other L-PI-13-067, Response to Request for Additional Information (RAI) Associated with Spent Fuel Pool Criticality Changes2013-07-17017 July 2013 Response to Request for Additional Information (RAI) Associated with Spent Fuel Pool Criticality Changes Project stage: Response to RAI ML13241A3832013-08-29029 August 2013 Issuance of Amendments Spent Fuel Pool Criticality Changes Project stage: Approval 2012-08-27
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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 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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 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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: 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February 8, 2013 L-PI-13-002 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 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 Request for Additional Information (RAI) Associated with Spent Fuel Pool Criticality Changes (TAC Nos. ME6984 and ME6985)
In a letter to the U.S. Nuclear Regulatory Commission (NRC) dated August 19, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML11236A133), the Northern States Power Company, a Minnesota corporation doing business as Xcel Energy (hereafter NSPM), requested an amendment to the Technical Specifications (TS) regarding Spent Fuel Pool (SFP) criticality for the Prairie Island Nuclear Generating Plant (PINGP).
To complete their review, the NRC staff requested additional information by letter dated January 22, 2013 (ADAMS Accession No. ML13011A316). Enclosure 1 to this letter provides the NSPM response to the January 22, 2013 request for additional information.
NSPM submits this supplement in accordance with the provisions of 10 CFR 50.90.
The supplemental information provided in this letter does not impact the conclusions of the Determination of No Significant Hazards Consideration and Environmental Assessment presented in the August 19, 2011 submittal.
In accordance with 10 CFR 50.91, NSPM is notifying the State of Minnesota of this License Amendment Request (LAR) supplement by transmitting a copy of this letter to the designated State Official.
Summary of Commitments This letter revises commitment number 2 listed in Enclosure 7 of the original LAR. The revised commitment reads as follows:
- 2. In conjunction with implementation of the proposed TS, procedures will be revised to require an assessment of a fuel assembly's exposure to rodded power operation in 1717 Wakonade Drive East
- Welch, Minnesota 55089-9642 Telephone: 651.388.1121
L-PI-13-002 Page 1 of 3 ENCLOSURE 1 Spent Fuel Pool Criticality Analysis Response to Requests for Addition Information (RAI)
In a letter to the U.S. Nuclear Regulatory Commission (NRC) dated August 19, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML11236A133), the Northern States Power Company, a Minnesota corporation doing business as Xcel Energy (hereafter NSPM), requested an amendment to the Technical Specifications (TS) regarding Spent Fuel Pool (SFP) criticality for the Prairie Island Nuclear Generating Plant (PINGP).
To complete their review, the NRC staff requested additional information by letter dated January 22, 2013 (ADAMS Accession No. ML13011A316).
For clarity, the NRC RAI information is provided below in italics font and the NSPM response is provided in plain font.
(1) Regarding the sensitivity analysis provided in response to RAI-SRXB-1 in the May 16, 2012, submittal, please confirm whether the un-poisoned cases assumed a uniform U-235 enrichment loading across all pins at the U-235 enrichments analyzed.
Response: All un-poisoned cases used in the sensitivity analysis provided in response to RAI-SRXB-1 assumed a uniform U-235 enrichment loading across all pins at the values of enrichment presented in the May 16, 2012 submittal.
(2) Confirm that the actual fuel assemblies at PINGP contain lower enrichments in Gd-bearing pins.
Response: In every cycle of operation except Unit 1 Cycle 5, the U-235 enrichment of the gadolinia bearing pins is lower than the pins without gadolinia.
In Unit 1 Cycle 5, the gadolinia bearing pins were of the same enrichment as the pins without gadolinia. This was the first cycle of operation using gadolinia and the gadolinia enrichment was only 1 weight percent. Note that even in Unit 1 Cycle 5, the gadolinia bearing pins contain fewer grams of U-235 than the pins without gadolinia because the gadolinia displaces uranium in the fuel matrix.
(3) It is not clear from Section 3.3.3.1 of WCAP-17400-P, enclosed in the August 19, 2011, application, if the database used to determine the axial burnup profile considered extended power uprate (EPU) cycle designs. Please confirm whether operation in an EPU cycle has been considered in determining the limiting axial shape.
Response: NSPM confirms that EPU fuel management cycles were reviewed and considered in selecting the limiting axial burnup profiles. A thorough review of the L-PI-13-002 Page 2 of 3 uprate fuel management calculations was performed including the axial burnup profiles associated with the uprate fuel management studies and it was concluded that the uprate fuel axial burnup profiles do not need to be explicitly included in the criticality safety analysis.
Notwithstanding the above, as discussed in a telephone conference on December 19, 2012, NSPM has decided to withdraw consideration of the EPU fuel management cycles from the proposed criticality safety analysis. NSPM has chosen to not submit a license amendment request to increase its licensed thermal power limit in conjunction with an EPU. Therefore, NSPM requests that NRC withdraw consideration of the EPU axial burnup profiles from the proposed criticality safety analysis.
(4) The licensees criticality analysis provides some assurance that the proposed design basis analysis bounds previous rodded operation of up to 1 gigawatt day per metric ton uranium (GWD/MTU) of depletion. However, since future rodded operation could initiate at or near the other depletion parameters in the proposed design basis analysis, the analysis does not bound future operation. Therefore, the NRC staff requests that the licensee either:
(a) Provide an analysis for rodded operation that initiates from the other depletion parameters used in the proposed design basis analysis, or (b) Propose an alternate method of controlling fuel assemblies that have experienced rodded operation.
Response: For all assemblies discharged into the spent fuel pool after approval of this license amendment request, NSPM proposes the following alternate method of controlling fuel assemblies that have experienced full-power rodded operation:
Any fuel assembly that experiences more than 100 MWD/MTU of core average full-power rodded operation exposure in the cycle immediately prior to discharge to the spent fuel pool will not be permitted to credit any full-power rodded exposure experienced during that cycle (i.e., that burnup will not be credited when determining the coefficients used to categorize fuel assemblies as described in WCAP-17400-P).
This threshold is applied only to the cycle immediately prior to discharge. Any rodded operation experienced in a previous cycle of operation will not be applied because subsequent operation in an unrodded condition will mitigate the impacts of rodded operation (i.e., axial burnup profiles tend to return to that of an equivalently burned unrodded assembly as well as the reactivity changes due to fission products as a result of spectral hardening while rodded).
To address this alternate method of controlling fuel assemblies that have experienced rodded operation, NSPM has modified Commitment 2 as follows:
L-PI-13-002 Page 3 of 3
- 2. In conjunction with implementation of the proposed TS, procedures will be revised to require an assessment of a fuel assembly's exposure to rodded power operation in the core prior to moving that fuel assembly into the spent fuel pool (SFP) storage racks. If an assembly experiences more than 100 megawatt day per metric ton uranium (MWd/MTU) of core average full-power rodded operation exposure in the cycle immediately prior to discharge to the spent fuel pool, this exposure experienced while rodded will not be credited for determining the coefficients used to categorize fuel assemblies as described in WCAP-17400-P. In addition, if an assembly experiences more than 1 gigawatt day per metric ton uranium (GWd/MTU) of core average rodded operation lifetime exposure, the assembly shall either be treated as Fuel Category 1 or evaluated to determine which Fuel Category is appropriate for safe storage of the assembly.