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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
MONTHYEARIR 05000282/20230042024-02-0101 February 2024 Integrated Inspection Report 05000282/2023004 and 05000306/2023004 ML23356A1232024-01-29029 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting) ML24024A0722024-01-24024 January 2024 Independent Spent Fuel Storage Installation, Onticello, Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML24017A0182024-01-19019 January 2024 Confirmation of Initial License Examination ML23356A0032024-01-17017 January 2024 Issuance of Amendments Revise Technical Specification 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) 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 IR 07200010/20234012023-12-20020 December 2023 Independent Spent Fuel Storage Installation Security Inspection Report 07200010/2023401 ML23349A0572023-12-15015 December 2023 and Independent Spent Fuel Storage Installation, Revision to Correspondence Service List for Northern States Power - Minnesota ML23215A1672023-12-15015 December 2023 Acceptance of Requested Licensing Action Amendment Request to Revise Surveillance Requirement 3.8.1.2 Note 3 IR 05000282/20234012023-12-13013 December 2023 Security Baseline Inspection Report 05000282/2023401 and 05000306/2023401 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 ML23304A1632023-11-15015 November 2023 Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment Request to Revise SR 3.8.1.2 Note 3 ML23319A3182023-11-15015 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000282/20230032023-11-0808 November 2023 Integrated Inspection Report 05000282/2023003 and 05000306/2023003 ML23311A3572023-11-0707 November 2023 Core Operating Limits Report (COLR) for Prairie Island Nuclear Generating Plant (PINGP) Unit 2. Cycle 33. Revision 0 ML23285A3062023-10-12012 October 2023 Implementation of the Fleet Standard Emergency Plan for the Monticello Nuclear Generating Plant and the Prairie Island Nuclear Generating Plant ML23270B9022023-09-29029 September 2023 Review of Reactor Vessel Material Surveillance Program Capsule N Technical Report 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 ML23265A2532023-09-26026 September 2023 Review of Reactor Vessel Material Surveillance Program Capsule N Technical Report ML23262B0372023-09-19019 September 2023 Response to NRC Request for Additional Information Regarding the 2023 Monticello and Prairie Island Plant Decommissioning Funding Status Reports ML23256A1682023-09-13013 September 2023 Independent Spent Fuel Storage Installation and Monticello Nuclear Generating Plant - Voluntary Security Clearance Program 2023 Insider Threat Program Self-Inspection L-PI-23-023, Baffle Former Bolts Alternate Aging Management Strategy2023-09-11011 September 2023 Baffle Former Bolts Alternate Aging Management Strategy IR 05000282/20230052023-08-30030 August 2023 Updated Inspected Plan for Prairie Island Nuclear Generating Plant Report 05000282/2023005 and 05000306/2023005 IR 05000282/20230102023-08-17017 August 2023 NRC Inspection Report 05000282/2023010 and 05000306/2023010 ML23222A0122023-08-10010 August 2023 Independent Spent Fuel Storage Installation and Monticello Nuclear Generating Plant - Changes in Foreign Ownership, Control or Influence IR 05000282/20230022023-08-0303 August 2023 Integrated Inspection Report 05000282/2023002 and 05000306/2023002 ML23214A2032023-08-0202 August 2023 Request for Information for an NRC Quadrennial Comprehensive Engineering Team Inspection: Inspection Report 05000282/2024010; 05000306/2024010 ML23206A2342023-07-25025 July 2023 Independent Spent Fuel Storage Installation, and Monticello Nuclear Generating Plant, Changes in Foreign Ownership, Control or Influence ML23202A0032023-07-21021 July 2023 Independent Spent Fuel and Independent Spent Fuel Storage Installation, Monticello Nuclear Generating Plant, Submittal of Quality Assurance Topical Report (NSPM-1) ML23199A0922023-07-18018 July 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000306/2023004 ML23195A1732023-07-14014 July 2023 Revision of Standard Practice Procedures Plan 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 ML23181A0192023-06-30030 June 2023 Independent Spent Fuel Storage Installation, Revision to Correspondence Service List for Northern States Power - Minnesota ML23178A2422023-06-28028 June 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III 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 IR 05000282/20234202023-06-0101 June 2023 Security Baseline Inspection Report 05000282/2023420 and 05000306/2023420 ML23150A1722023-05-30030 May 2023 Preparation and Scheduling of Operator Licensing Examinations 2024-02-01
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1717 Wakonade Drive East Welch, Minnesota 55089-9642 Telephone: 651.388.1121 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
Enclosure
1 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
Enclosure
1 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 licensee's 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:
Enclosure
1 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.