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Category:Code Relief or Alternative
MONTHYEARML24222A1822024-08-27027 August 2024 – Proposed Alternative Request VR-09 to the Inservice Testing Requirements of the ASME OM Code for Main Steam Safety Relief Valves ML23248A2092023-09-18018 September 2023 – Proposed Alternative VR-11 to the Requirements of the ASME OM Code Associated with Periodic Verification Testing of MO-2397, Reactor Water Cleanup Inboard Isolation Valve ML23123A4222023-05-16016 May 2023 – Request RR 001 to Use Later Edition of ASME BPV Section XI Code for Cisi Program ML23107A2852023-04-25025 April 2023 Authorization and Safety Evaluation for Alternative Request PR-08 ML23017A2222023-01-13013 January 2023 Verbal Authorization of Proposed Alternative PR-08 Regarding Inservice Testing Requirements of Certain High Pressure Coolant Injection System Components (EPID L-2022-LLR-0088) (Email) ML22314A2162022-11-16016 November 2022 Withdrawal of Alternative Request VR-08 ML22270A2312022-09-30030 September 2022 Authorization and Safety Evaluation for Alternative Request No. VR-10 ML22208A1952022-08-0303 August 2022 Summary of July 26, 2022, Meeting with Northern States Power Company, Doing Business as Xcel Energy, Related to the Alternative Request for Excess Flow Check Valves at Monticello Nuclear Generating Plant ML22126A1052022-06-21021 June 2022 Authorization and Safety Evaluation for Alternative Request No. VR-01 ML22154A5502022-06-0707 June 2022 Authorization and Safety Evaluation for Alternative Request No. PR-02 ML22126A1342022-05-12012 May 2022 Authorization and Safety Evaluation for Alternative Request No. PR-05 ML22130A6562022-05-11011 May 2022 Authorization and Safety Evaluation for Alternative Request No. PR-04 ML22098A1272022-05-0202 May 2022 Authorization and Safety Evaluation for Alternative Request No. VR-02 ML22110A1232022-04-25025 April 2022 Withdrawal of Relief Requests PR-09 and VR-07 (Epids: L 2021 Llr 0095 and L 2022 Llr 0021) ML22018A1772022-01-21021 January 2022 Authorization and Safety Evaluation for Alternative Request No. VR-05 ML20307A0172020-11-0202 November 2020 Request for Alternative for Core Support Structure Weld Examination ML20174A5452020-07-15015 July 2020 Request for Alternative for Pressure Isolation Valve Testing ML20135G9922020-05-29029 May 2020 and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Relief from the Requirements of the ASME Code ML18270A0152018-10-19019 October 2018 and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Relief from the Requirements of the ASME OM Code L-MT-18-023, 10 CFR 50.55a Request RR-012: Inservice Inspection Impracticality in Accordance with 10 CFR 50 .55a(g)(5)(iii) During the Fifth Ten-Year Interval2018-05-11011 May 2018 10 CFR 50.55a Request RR-012: Inservice Inspection Impracticality in Accordance with 10 CFR 50 .55a(g)(5)(iii) During the Fifth Ten-Year Interval ML17122A1572017-05-15015 May 2017 Request for Alternative to Use Code Case OMN-20 for the Fifth 10-Year Inservice Testing Interval ML16208A4622016-08-0303 August 2016 Safety Evaluation for Request for Alternative Associated with Reactor Pressure Vessel Internals and Components Inspection for the Fifth 10-Year Interval L-MT-15-083, 10 CFR 50.55a Request No. RR-010: Request for Approval of an Alternative to Apply the BWRVIP Guidelines in Lieu of Specific ASME Section XI Code Requirements for Reactor Pressure Vessel Internals and Components Inspection2015-11-20020 November 2015 10 CFR 50.55a Request No. RR-010: Request for Approval of an Alternative to Apply the BWRVIP Guidelines in Lieu of Specific ASME Section XI Code Requirements for Reactor Pressure Vessel Internals and Components Inspection ML15028A1522015-02-19019 February 2015 Relief Request RR-009 Regarding Relief from Examination Coverage Requirements of Section XI of the ASME Code for the Fifth 10-Year Inservice Inspection Program Interval ML15013A0362015-01-23023 January 2015 Relief Request RR-008 Alternative to ASME Code, Section XI, Examination Requirements for the Reactor Pressure Vessel Shroud Support Plate Welds H8 and H9 for the Fifth 10-Year ISI Interval ML14223A5812014-08-27027 August 2014 Alternative Request Vr 05 to the Testing Requirements of the ASME OM Code for the Fifth 10-Year Inservice Inspection Program Interval ML12244A2722012-09-26026 September 2012 Relief from the Requirements of ASME OM Code for the Fifth Ten-Year IST Program Interval (TAC Nos. ME8067, ME8088 Through ME8096) ML12180A5882012-07-12012 July 2012 Approval of ISI Relief Request RR-007 for the Fifth 10-year Interval ML1020006722010-07-28028 July 2010 Approval of Alternative to Use ASME Code Case N-705 to Address Cracks at the Standby Liquid Control Tank L-MT-10-014, Request 10 CFR 50.55a Request 17: Extension of Permanent Relief from Volumetric Examination of Reactor Pressure Vessel Circumferential Shell Welds for the Renewed Operating License Term2010-03-12012 March 2010 Request 10 CFR 50.55a Request 17: Extension of Permanent Relief from Volumetric Examination of Reactor Pressure Vessel Circumferential Shell Welds for the Renewed Operating License Term ML0617103642006-07-0303 July 2006 Monticello Nuclear Generating Plant, Palisades Nuclear Plant, Point Beach Nuclear Plant Units 1 and 2, Prairie Island Nuclear Generating Plant, Units 1 and 2 - Use of ASME Code Case N-513-2 L-MT-05-074, Request to Use Subsequent Edition and Addenda of ASME Code for Inservice Testing2005-07-29029 July 2005 Request to Use Subsequent Edition and Addenda of ASME Code for Inservice Testing ML0505600492005-03-0808 March 2005 Fourth 10-Year Inservice Inspection Interval Request for Relief to Use Code Case N-661 ML0436300192005-01-0606 January 2005 Relief, Fourth 10-year Inservice Inspection Interval Request for Relief No. 4, MC2222 ML0407004152004-03-25025 March 2004 Third 10-Year Interval Inservice Inspection Request for Relief RR-17, Involving Repair/Replacement Activity on the Topworks of Main Steam Safety Relief Valve (SRV) G ML0401607382004-02-26026 February 2004 Prairie, Units 1 and 2, Kewaunee, Point Beach, Units 1 and 2, Palisades, Re Request for Alternatives to ASME Section XI, Appendix Viii, Supplement 10 ML0320401572003-10-0303 October 2003 Relief Request No. 7, Fourth 10-Year Interval Inservice Inspection Program Plan L-MT-03-045, Request for Approval of Inservice Inspection Program Third 10-Year Interval Relief Request No. 172003-08-27027 August 2003 Request for Approval of Inservice Inspection Program Third 10-Year Interval Relief Request No. 17 ML0320605802003-08-0707 August 2003 Relief, Fourth 10-Year Interval Inservice Testing Program ML0317002092003-07-17017 July 2003 Relief Request, Nos. PR-01, PR-02, PR-03, PR-04, PR-05, and VR-02 Related to the Fourth 10-Year Interval Inservice Testing Program L-MT-03-048, Request for Authorization of Inservice Inspection Program Fourth 10-Year Interval Relief Request No. 82003-06-12012 June 2003 Request for Authorization of Inservice Inspection Program Fourth 10-Year Interval Relief Request No. 8 ML0316008642003-06-0909 June 2003 Relief Request, Fourth 10-Year Interval Inservice Inspection Program Plan Relief Request No. 5, TAC No. MB6956 ML0314001192003-05-19019 May 2003 Relief, Third 10-Year Interval Inservice Inspection Relief Request No 16, Parts a, B, and C L-MT-03-001, Relief Request No. Pr 06 for Fourth 10-Year Inservice Testing Interval - High Pressure Coolant Injection Pump Testing2003-05-0606 May 2003 Relief Request No. Pr 06 for Fourth 10-Year Inservice Testing Interval - High Pressure Coolant Injection Pump Testing 2024-08-27
[Table view] Category:Letter
MONTHYEARML24283A1192024-10-28028 October 2024 Letter to Shawn Hafen, Re Monticello Subsequent License Renewal Schedule Change L-MT-24-038, Subsequent License Renewal Application Response to Request for Additional Information - 3rd Round RAI2024-10-15015 October 2024 Subsequent License Renewal Application Response to Request for Additional Information - 3rd Round RAI ML24277A0202024-10-0303 October 2024 Operator Licensing Examination Approval Monticello Nuclear Generating Plant, October 2024 ML24199A1752024-10-0101 October 2024 Issuance of Amendment No. 212 Revise Technical Specification 3.8.6, Battery Parameters, Surveillance Requirement 3.8.6.6 IR 05000263/20240112024-10-0101 October 2024 Biennial Problem Identification and Resolution Inspection Report 05000263/2024011 L-MT-24-025, Application to Revise Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements2024-09-26026 September 2024 Application to Revise Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements L-MT-24-029, Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information-Supplement to Set 1 Part 2 and Response to 2ci Round RAI2024-09-13013 September 2024 Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information-Supplement to Set 1 Part 2 and Response to 2ci Round RAI IR 05000263/20240052024-08-30030 August 2024 Updated Inspection Plan and Follow-Up Letter for Monticello Nuclear Generating Plant, Unit 1 (Report 05000263/2024005) L-MT-24-028, Response to RCI for RR-017 ISI Impracticality2024-08-28028 August 2024 Response to RCI for RR-017 ISI Impracticality ML24222A1822024-08-27027 August 2024 – Proposed Alternative Request VR-09 to the Inservice Testing Requirements of the ASME OM Code for Main Steam Safety Relief Valves 05000263/LER-2024-002, Low Pressure Coolant Injection Inoperable Due to Motor Valve Failure2024-08-27027 August 2024 Low Pressure Coolant Injection Inoperable Due to Motor Valve Failure IR 05000263/20244202024-08-21021 August 2024 Security Baseline Inspection Report 05000263/2024420 - Cover Letter IR 05000263/20240022024-08-14014 August 2024 Integrated Inspection Report 05000263/2024002 ML24218A2282024-08-0505 August 2024 Request for Confirmation of Information for Relief Request RR-017, Inservice Inspection Impracticality During the Fifth Ten-Year Interval ML24208A1502024-07-26026 July 2024 Independent Spent Fuel Storage Installation - Submittal of Quality Assurance Topical Report (NSPM-1) ML24215A2992024-07-23023 July 2024 Minnesota State Historic Preservation Office Comments on Monticello SLR Draft EIS ML24198A2372024-07-18018 July 2024 Information Request to Support Upcoming Biennial Problem Identification and Resolution (Pi&R) Inspection at Monticello Nuclear Generating Plant L-MT-24-022, – Preparation and Scheduling of Operator Licensing Examinations2024-07-0909 July 2024 – Preparation and Scheduling of Operator Licensing Examinations ML24164A2402024-06-10010 June 2024 Minnesota State Historic Preservation Office- Comments on Draft Monticello SLR Draft EIS L-MT-24-019, Submittal of ASME Section XI, Section IWB-3720 Analytical Evaluation in Accordance with 10 CFR 50.55a(b)(2)(xliii)2024-06-10010 June 2024 Submittal of ASME Section XI, Section IWB-3720 Analytical Evaluation in Accordance with 10 CFR 50.55a(b)(2)(xliii) L-MT-24-017, Response to Request for Additional Information Regarding License Amendment Request to Revise Monticello Technical Specification Surveillance Requirement 3.8.6.6 (EPID-L-2023-LLA-01602024-06-0404 June 2024 Response to Request for Additional Information Regarding License Amendment Request to Revise Monticello Technical Specification Surveillance Requirement 3.8.6.6 (EPID-L-2023-LLA-0160 ML24137A2792024-06-0303 June 2024 Audit Summary for License Amendment Request to Revise Technical Specification 3.8.6, Battery Parameters, Surveillance Requirement 3.8.6.6 ML24141A1292024-05-22022 May 2024 Northern States Power Company - Use of Encryption Software for Electronic Transmission of Safeguards Information ML24141A1782024-05-20020 May 2024 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection L-MT-24-015, Response to Request for Additional Information - Alternative Request VR-09 for OMN-172024-05-16016 May 2024 Response to Request for Additional Information - Alternative Request VR-09 for OMN-17 L-MT-24-013, 2023 Annual Radiological Environmental Operating Report2024-05-14014 May 2024 2023 Annual Radiological Environmental Operating Report ML24135A1902024-05-14014 May 2024 Submittal of 2023 Annual Radioactive Effluent Release Report IR 05000263/20240102024-05-13013 May 2024 Age-Related Degrading Inspection Report 05000263/2024010 ML24128A0042024-05-0909 May 2024 Letter to Minnesota State Historic Preservation Office- Section 106 Consultation Regarding the Monticello Nuclear Generating Plant Subsequent License Renewal Application ML24127A1472024-05-0909 May 2024 Letter to Mille Lacs Band- Section 106 Consultation Regarding the Monticello Nuclear Generating Plant Subsequent License Renew. Application L-MT-24-016, 2023 Annual Report of Individual Monitoring for the Monticello Nuclear Generating Plant (MNGP)2024-05-0808 May 2024 2023 Annual Report of Individual Monitoring for the Monticello Nuclear Generating Plant (MNGP) ML24089A2382024-04-29029 April 2024 Summary of Nuclear Property Insurance IR 05000263/20240012024-04-29029 April 2024 Plan - Integrated Inspection Report 05000263/2024001 ML24115A2902024-04-25025 April 2024 Sec106 Tribal, Jackson-Street, Lonna-Spirit Lake Nation ML24115A2872024-04-25025 April 2024 Sec106 Tribal, Dupuis, Kevin-Fond Du Lac Band of Lake Superior Chippewa ML24115A2932024-04-25025 April 2024 Sec106 Tribal, Johnson, Grant-Prairie Island Indian Community ML24115A3062024-04-25025 April 2024 Sec106 Tribal, Wassana, Reggie-Cheyenne and Arapaho Tribes 05000263/LER-2024-001, Reactor Scram, Containment Isolation, and Cooldown Rate Outside of Limits Following Technician Adjustment of Wrong Component2024-04-25025 April 2024 Reactor Scram, Containment Isolation, and Cooldown Rate Outside of Limits Following Technician Adjustment of Wrong Component ML24115A3032024-04-25025 April 2024 Sec106 Tribal, Taylor, Louis-Lac Courte Oreilles Band of Lake Superior Chippewa Indians ML24115A3002024-04-25025 April 2024 Sec106 Tribal, Rhodd, Timothy-Iowa Tribe of Kansas and Nebraska ML24115A2972024-04-25025 April 2024 Sec106 Tribal, Miller, Cole-Shakopee Mdewakanton Sioux Community ML24115A2962024-04-25025 April 2024 Sec106 Tribal, Larsen, Robert-Lower Sioux Indian Community ML24115A2952024-04-25025 April 2024 Sec106 Tribal, Kakkak, Gena-Menominee Indian Tribe of Wisconsin ML24115A2982024-04-25025 April 2024 Sec106 Tribal, Reider, Anthony-Flandreau Santee Sioux Tribe ML24115A2912024-04-25025 April 2024 Sec106 Tribal, Jacskon, Sr., Faron-Leech Lake Band of Ojibwe ML24115A3052024-04-25025 April 2024 Sec106 Tribal, Vanzile, Jr., Robert-Sokaogon Chippewa Community ML24115A2992024-04-25025 April 2024 Sec106 Tribal, Renville, J. Garret-Sisseton Wahpeton Oyate of the Lake Travers Reservation ML24115A3022024-04-25025 April 2024 Sec106 Tribal, Stiffarm, Jeffrey-Fort Belknap Indian Community ML24115A3072024-04-25025 April 2024 Sec106 Tribal, Williams, Jr., James-Lac Vieux Desert Band of Lake Superior Chippewa Indians ML24115A2892024-04-25025 April 2024 Sec106 Tribal, Fowler, Thomas-St. Croix Chippewa of Wisconsin 2024-09-26
[Table view] Category:Safety Evaluation
MONTHYEARML24199A1752024-10-0101 October 2024 Issuance of Amendment No. 212 Revise Technical Specification 3.8.6, Battery Parameters, Surveillance Requirement 3.8.6.6 ML24222A1822024-08-27027 August 2024 – Proposed Alternative Request VR-09 to the Inservice Testing Requirements of the ASME OM Code for Main Steam Safety Relief Valves ML24138A1212024-07-0202 July 2024 Alternative Request RR-002 ML24077A0012024-03-18018 March 2024 Safety Evaluation to the SLRA of Monticello Nuclear Generating Plant, Unit 1 ML23248A2092023-09-18018 September 2023 – Proposed Alternative VR-11 to the Requirements of the ASME OM Code Associated with Periodic Verification Testing of MO-2397, Reactor Water Cleanup Inboard Isolation Valve ML23107A2852023-04-25025 April 2023 Authorization and Safety Evaluation for Alternative Request PR-08 ML23079A0742023-04-11011 April 2023 Request RR-003 to Use Later Edition of ASME Section XI Code for ISI Code of Record ML22357A1002023-03-31031 March 2023 And Prairie Island Nuclear Generating Plant, Units 1 and 2 - Issuance of Amendments Standard Emergency Plan and Consolidated Emergency Operations Facility ML23012A1562023-01-13013 January 2023 Issuance of Amendment No. 210 Re Revised Methodologies for Determining the Core Operating Limits (EPID L-2021-LLA-0144) - Non-proprietary ML22318A2152022-12-27027 December 2022 Issuance of Amendment No. 209 Ten-Year Inspection of the Diesel Generator Fuel Oil Storage Tank ML22264A1062022-10-31031 October 2022 Issuance of Amendment No. 208 Residual Heat Removal Drywell Spray Header and Nozzle Surveillance Frequency ML22270A2312022-09-30030 September 2022 Authorization and Safety Evaluation for Alternative Request No. VR-10 ML22154A5502022-06-0707 June 2022 Authorization and Safety Evaluation for Alternative Request No. PR-02 ML22126A1342022-05-12012 May 2022 Authorization and Safety Evaluation for Alternative Request No. PR-05 ML22098A1272022-05-0202 May 2022 Authorization and Safety Evaluation for Alternative Request No. VR-02 ML22018A1772022-01-21021 January 2022 Authorization and Safety Evaluation for Alternative Request No. VR-05 ML21223A2802021-10-15015 October 2021 Issuance of Amendment No. 207 Adoption of TSTF-564 Safety Limit MCPR ML21148A2742021-07-12012 July 2021 Issuance of Amendment No. 206 TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML20352A3492021-01-0808 January 2021 Issuance of Amendment No. 205, Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-582, RPV WIC Enhancements, and TSTF-583-T, TSTF-582 Diesel Generator Variation ML20346A0972020-12-21021 December 2020 Request for Alternative for Examination of Reactor Pressure Vessel Threads in Flange ML20336A1602020-12-0909 December 2020 Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML20307A0172020-11-0202 November 2020 Request for Alternative for Core Support Structure Weld Examination ML20210M0142020-09-0808 September 2020 and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Issuance of Amendment Nos. 204, 231, and 219 TSTF-529 Clarify Use and Application Rules ML20153A8042020-07-31031 July 2020 Co. - Issuance of Amendments Revising Emergency Action RA3 ML20174A5452020-07-15015 July 2020 Request for Alternative for Pressure Isolation Valve Testing ML20153A4012020-06-0101 June 2020 and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Relief from the Requirements of the ASME Code ML20134H9582020-05-29029 May 2020 and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Relief from the Requirements of the ASME Code ML20135G9922020-05-29029 May 2020 and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Relief from the Requirements of the ASME Code ML19255F5822019-10-0101 October 2019 Safety Evaluation Regarding Implementation of Hardened Containment Vents Capable of Operation Under Severe Accident Conditions Related to Order EA-13-109 (CAC No. MF4376; EPID No. L-2014-JLD-0052) ML19162A0932019-07-30030 July 2019 Issuance of Amendment No, 202 Regarding Deletion of the Note Associated with Technical Specification 3.5.1., Erccs - Operating ML19074A2692019-04-22022 April 2019 Non-Proprietary - Issuance of Amendment Revision to Technical Specifications 2.1.2 Safety Limit Minimum Critical Power Ratio ML19052A1422019-03-11011 March 2019 Correction to License Amendment No. 198 Related to Adoption of TSTF-542, Reactor Pressure Vessel Water Inventory Control ML19065A2002019-03-11011 March 2019 Correction to License Amendment No. 200 Related to Adoption of TSTF-425, Relocated Surveillance Frequencies to Licensee Control - RITSTF Initiative 5B ML19007A0902019-01-28028 January 2019 Issuance of Amendment Adoption of TSTF-425, Relocate Surveillance Frequencies to Licensee Control-RITSTF Initiative 5B ML18291B2142018-11-26026 November 2018 Issuance of Amendment Adoption of TSTF-551 Revise Secondary Containment Surveillance Requirements ML18250A0752018-10-29029 October 2018 Issuance of Amendment Adoption of TSTF-542, Reactor Pressure Vessel Water Inventory Control ML18270A0152018-10-19019 October 2018 and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Relief from the Requirements of the ASME OM Code ML17345A0462018-03-0606 March 2018 Issuance of Amendment No. 197 to Adopt Changes to the Emergency Plan (CAC No. MF9560; EPID L-2017-LLA-0184) ML17319A5912017-12-10010 December 2017 Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 ML17310B2392017-11-28028 November 2017 and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Issuance of Amendment Unit Staff Qualifications (CAC Nos. MF9545, MF9546, and MF9547; EPID L-2017-LLA-0195) ML17123A3212017-06-16016 June 2017 Issuance of Amendment Adoption of TSTF-545, Revision 3, TS Inservice Testing Program Removal and Clarify SR Usage Rule Application to Section 5.5 Testing ML17122A1572017-05-15015 May 2017 Request for Alternative to Use Code Case OMN-20 for the Fifth 10-Year Inservice Testing Interval ML17103A2352017-04-25025 April 2017 Issuance of Amendment Technical Specification 5.5.11 Primary Containment Leakage Rate Testing Program ML17013A4352017-02-27027 February 2017 Issuance of Amendment Revision to Technical Specification Surveillance Requirement 3.8.4.2 ML17054C3942017-02-23023 February 2017 Non-Proprietary Issuance of Amendment Extended Flow Window ML16320A0212016-11-28028 November 2016 and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Review of Changes to the Northern States Power Company Quality Assurance Topical Report ML16244A1202016-09-0606 September 2016 Generation Plant - Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Phase 2 of Order EA-13-109 (Severe Accident Capable Hardened Vents) ML16208A4622016-08-0303 August 2016 Safety Evaluation for Request for Alternative Associated with Reactor Pressure Vessel Internals and Components Inspection for the Fifth 10-Year Interval ML16196A3032016-08-0101 August 2016 Issuance of Amendment Technical Specifications Surveillance Requirement 3.5.1.3 B to Correct Alternative Nitrogen System Pressure (Cac. No. MF6704) ML16125A1652016-06-21021 June 2016 Issuance of Amendment Technical Specifications Task Force (TSTF) Standard Technical Specifications (STS) Change Traveler TSTF-523, Revision 2 Generic Letter 2008-01, Managing Gas Accumulation 2024-08-27
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 May 15, 2017 Mr. Peter A. Gardner Site Vice President Monticello Nuclear Generating Plant Northern States Power Company - Minnesota (NSPM) 2807 West County Road 75 Monticello, MN 55362-9637
SUBJECT:
MONTICELLO NUCLEAR GENERATING PLANT - REQUEST FOR ALTERNATIVE TO USE CODE CASE OMN-20 FOR THE FIFTH 10-YEAR INSERVICE TESTING INTERVAL (CAC NO. MF8216)
Dear Mr. Gardner:
By letter dated July 28, 2016, as supplemented by letter dated January 4, 2017, the Northern States Power Company- Minnesota (NSPM or the licensee) submitted Request for Alternative PR 07 for the fifth 10-year inservice testing (IST) interval for Monticello Nuclear Generating Plant (MNGP) to use American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance (OM) 2004 Edition through the 2006 Addenda, Code Case OMN-20, "lnservice Test Frequency." The proposed duration of this alternative is for the current 10-year IST interval or until the Code Case OMN-20 is incorporated in Title 10 of the Code of Federal Regulations (10 CFR) 50.55a.
Specifically, pursuant to 10 CFR 50.55a(z)(2), the licensee requested to use the proposed alternative, Code Case OMN-20, on the basis that it provides reasonable assurance that the components are operationally ready and that compliance with the ASME OM Code requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
The U.S. Nuclear Regulatory Commmission (NRC) staff reviewed the proposed alternative and determined, as set forth in the enclosed safety evaluation, that for request PR 07 (use Code Case OMN-20), the proposed alternative provides reasonable assurance that the affected components are operationally ready, and complying with the ASME OM Code requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety. Accordingly, the NRC staff concludes that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(z)(2).
Therefore, the NRC staff authorizes alternative request PR 07 for the MNGP current 10-year IST interval which ends May 31, 2022, or until Code Case OMN-20 is incorporated into 10 CFR 50.55a. All other ASME OM Code requirements for which relief was not specifically requested and approved in the subject request remain applicable.
P. Gardner If you have any questions, please contact Robert Kuntz at 301-415-3733, or via e-mail at Robert. Kuntz@nrc.gov.
Sincerely, c)~J 9 v* I David J. Wrona, Chief Plant Licensing Branch Ill Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-263
Enclosure:
Safety Evaluation cc w/enclosure: Distribution via ListServ
ML17122A157 *by e-mail OFFICE DORL/LPL3/PM DORL/LPL 1-1/LA DE/EVIB/BC DORL/LPL3-1 /PM NAME RKuntz SRohrer DAiiey* DWrona DATE 05/02/17 05/02/17 04/26/17 05/15/17 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION REQUEST FOR ALTERNATIVE PR 07 TO USE CODE CASE OMN-20 FOR THE FIFTH 10-YEAR INSERVICE TESTING INTERVAL NORTHERN STATES POWER COMPANY - MINNESOTA MONTICELLO NUCLEAR GENERATING PLANT DOCKET NO. 50-263
1.0 INTRODUCTION
By letter dated July 28, 2016 (Agencywide Documents and Access Management System (ADAMS) Accession No. ML 1621 OA030), as supplemented by letter dated January 4, 2017 (ADAMS Accession No. ML17004A208), Northern States Power Company (NSPM, or the licensee), doing business as Xcel Energy, submitted request for relief to the U.S. Nuclear Regulatory Commission (NRC), proposing alternatives to certain requirements of the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code), for the current inservice testing (IST) programs at Monticello Nuclear Generating Plant (MNGP).
Request No. PR 07 proposes an alternative for the fifth 10-year IST interval for MNGP to use ASME OM Code 2004 Edition through the 2006 Addenda, Code Case OMN-20, "lnservice Test Frequency." The proposed duration of this alternative is for the current 10-year IST interval or until the Code Case OMN-20 is incorporated in Title 1O of the Code of Federal Regulations (10 CFR) 50.55a.
Specifically, pursuant to 10 CFR 50.55a(z)(2), the licensee requested to use the proposed alternative Code Case OMN-20 in Relief Request No. PR 07 on the basis that it provides reasonable assurance that the components are operationally ready and that compliance with the ASME OM Code requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
2.0 REGULATORY EVALUATION
10 CFR 50.55a(f), "lnservice Testing Requirements," requires, in part, that the IST of certain ASME Code Class 1, 2, and 3 components must meet the requirements of the ASME OM Code Enclosure
and applicable addenda, except where alternatives have been authorized by the NRC pursuant to 10 CFR 50.55a(z)(1) or 10 CFR 50.55a(z)(2).
The regulations in 10 CFR 50.55a(z), state, in part, that alternatives to the requirements of 10 CFR 50.55a(f) may be authorized by the NRC if the licensee demonstrates that: (1) the proposed alternative provides an acceptable level of quality and safety (10 CFR 50.55a(z)(1 )),
or (2) compliance with the specified requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety (10 CFR 50.55a(z)(2)).
Based on the above, and subject to the following technical evaluation, the NRC staff finds that regulatory authority exists for the licensee to request and the NRC to grant the relief requested by the licensee.
3.0 TECHNICAL EVALUATION
3.1 Licensee's Alternative Request No. PR 07 for the Use of Code Case OMN-20 3.1.1 Applicable Code Requirements This request applies to the frequency specifications of the ASME OM Code. The frequencies for tests given in the ASME OM Code include the following but do not include a tolerance band:
ISTA-3120, "lnservice Test Interval," (a) states, 'The frequency for inservice testing shall be in accordance with the requirements of Section IST."
ISTB-3400, "Frequency of lnservice Tests," states, "An inservice test shall be run on each pump as specified in Table ISTB-3400-1."
Table ISTB-3400-1, "lnservice Test Frequency," notes that Group A and Group B pump tests are to be conducted quarterly and comprehensive pump tests are to be conducted biennially.
ISTC-3510, "Exercising Test Frequency," states, "Active Category A, Category B, and Category C check valves shall be exercised nominally every 3 months, except as provided by ISTC-3520, ISTC-3540, ISTC-3550, ISTC-3570, ISTC-5221, and ISTC-5222. Power-operated relief valves shall be exercise tested once per fuel cycle."
ISTC-3540, "Manual Valves," states, "Manual valves shall be full-stroke exercised at least once every 2 years, except where adverse conditions may require the valve to be tested more frequently to ensure operational readiness. Any increased testing frequency shall be specified by the Owner. The valve shall exhibit the required change of obturator position."
ISTC-3630, "Leakage Rate for Other Than Containment Isolation Valves," (a) "Frequency,"
states, "Tests shall be conducted at least once every 2 years."
ISTC-3700, "Position Verification Testing," states, in part, "Valves with remote position indicators shall be observed locally at least once every 2 years to verify that valve operation is accurately indicated."
ISTC-5221, "Valve Obturator Movement," (c)(3), states, "At least one valve from each group shall be disassembled and examined at each refueling outage; all valves in each group shall be disassembled and examined at least once every 8 years."
Mandatory Appendix I, "lnservice Testing of Pressure Relief Devices in Light-Water Reactor Nuclear Power Plants," 1-1320, "Test Frequencies, Class 1 Pressure Relief Valves," (a), "5-Year Test Interval," states, in part, "Class 1 pressure relief valves shall be tested at least once every 5 years, starting with initial electric power generation."
Mandatory Appendix I, 1-1330, "Test Frequency, Class 1 Nonreclosing Pressure Relief Devices,"
states, "Class 1 nonreclosing pressure relief devices shall be replaced every 5 years unless historical data indicates a requirement for more frequent replacement."
Mandatory Appendix I, 1-1340, Test Frequency, Class 1 Pressure Relief Valves That Are Used for Thermal Relief Application," states, "Tests shall be performed in accordance with 1-1320, Test Frequencies, Class 1 Pressure Relief Valves."
Mandatory Appendix I, 1-1350, "Test Frequency, Classes 2 and 3 Pressure Relief Valves," (a),
"10-YearTest Interval," states, in part, "Class 2 and 3 pressure relief valves, with the exception of PWR [pressurized water reator] main steam safety valves, shall be tested every 10 years, starting with initial electric power generation."
Mandatory Appendix I, 1-1360, "Test Frequency, Classes 2 and 3 Nonreclosing Pressure Relief Devices," states, "Classes 2 and 3 nonreclosing pressure relief devices shall be replaced every 5 years, unless historical data indicates a requirement for more frequent replacement."
Mandatory Appendix I, 1-1370, Test Frequency, Classes 2 and 3 Primary Containment Vacuum Relief Valves," states, "(a) Tests shall be performed on all Classes 2 and 3 containment vacuum relief valves at each refueling outage or every 2 years, whichever is sooner, unless historical data requires more frequent testing. (b) Leak tests shall be performed on all Classes 2 and 3 containment vacuum relief valves at a frequency designated by the Owner in accordance with Table ISTC-3500-1."
Mandatory Appendix I, 1-1380, Test Frequency, Classes 2 and 3 Vacuum Relief Valves, Except for Primary Containment Vacuum Relief Valves," states, "All Classes 2 and 3 vacuum relief valves shall be tested every 2 years, unless performance data suggest the need for a more appropriate test interval."
Mandatory Appendix I, 1-1390, "Test Frequency, Classes 2 and 3 Pressure ReliefDevices That Are Used for Thermal Relief Application," states, "Tests shall be performed on all Classes 2 and 3 relief devices used in thermal relief application every 10 years, unless performance data indicate more frequent testing is necessary. In lieu of tests the Owner may replace the relief devices at a frequency of every 10 years, unless performance data indicate more frequent replacements are necessary."
Mandatory Appendix 11, "Check Valve Condition Monitoring Program," 11-4000, "Condition-Monitoring Activities," (a), "Performance Improvement Activities," (1 ), states, in part, "If sufficient information is not currently available to complete the analysis required in 11-3000, or if this analysis is inconclusive, then the following activities shall be performed at sufficient intervals over an interim period of the next 5 years or two refueling outages, whichever is less, to determine the cause of failure or the maintenance patterns."
Mandatory Appendix II, 11-4000, (b), "Optimization of Condition-Monitoring Activities," (1 )(e),
states, "Identify the interval of each activity. Interval extensions shall be limited to one fuel cycle per extension. Intervals shall not exceed the maximum intervals shown in Table 11-4000-1. All valves in a group sampling plan must be tested or examined again, before the interval can be extended again, or until the maximum interval would be exceeded. The requirements of ISTA-120, lnservice Test Interval, do not apply."
In summary, ASME OM Code, Division 1, Section IST, 2009 Edition through OMa-2011 Addenda and all earlier editions and addenda specify component (pump and valve) test frequencies based either on elapsed time periods (e.g., quarterly, 2 years, etc.) or on the occurrence of plant conditions or events (e.g., cold shutdown, refueling outage, upon detection of a sample failure, following maintenance, etc.) without any tolerance.
3.1.2 Applicable Code Edition and Addenda The Code of Record for MNGP fifth 10-year IST program is the 2004 Edition through 2006 Addenda of ASME OM Code. The MNGP current (fifth) 10-year IST interval ends May 31, 2022.
3.1.3 Components for which Alternative Relief is Requested All pumps and valves contained within the MNGP IST program's scope.
3.1.4 Licensee's Reason for Requesting Relief ASME OM Code Section IST establishes the inservice test frequency for all components within the scope of the code. The frequencies (e.g., quarterly) have always been interpreted as "nominal" frequencies (generally as defined in the Table 3.2 of NUREG-1482, Revision 2) and owners routinely applied the surveillance extension time period (i.e., grace period) contained in the plant technical specification (TS) surveillance requirements (SRs). The TSs typically allow for a less than or equal to 25 percent extension of the surveillance test interval to accommodate plant conditions that may not be suitable for conducting a TS surveillance (SR 3.0.2). However, Regulatory Issue Summary (RIS) 2012-10, "NRC Staff Position on Applying Surveillance Requirements 3.0.2 and 3.0.3 to Administrative Controls Program Tests," states that SRs 3.0.2 and 3.0.3 cannot be applied to TS 5.5, "Programs and Manuals," for tests that are not associated with a TS SR The lack of a tolerance band on the ASME OM Code IST frequency restricts operational flexibility. The NRC recognized this potential issue in the TSs by allowing a frequency tolerance as described in TS SR 3.0.2. The lack of a similar tolerance applied to the ASME OM Code
testing places an unusual hardship on the plant to adequately schedule work tasks without operational flexibility.
With the TS-required surveillance testing, some tolerance is needed to allow adjusting ASME OM Code testing intervals to suit the plant conditions and other maintenance and testing activities. This assures operational flexibility when scheduling IST that would minimize the conflicts between the need to complete the testing and plant conditions.
3.1.5 Licensee's Proposed Alternative The licensee proposed to perform IST per ASME OM Code Case OMN-20, repeated below, for determining acceptable tolerances for pump and valve test frequencies. This Code Case was approved by the ASME OM Code Standards Committee in February 2012, and subsequently published in the 2012 Edition through 2015 Edition of the ASME OM Code. The proposed alternative will be used for the current 10-year IST intervals at MNGP and will apply to the various frequency specifications of the ASME OM Code for all pumps and valves contained within the IST Program scope.
ASME OM Code Case OMN-20, "lnservice Test Frequency" ASME OM Code Case OMN-20 states the following:
ASME OM, Division 1, Section IST and all earlier editions and all addenda [of ASME OM Code] specify component test frequencies based either on elapsed time periods (e.g., quarterly, 2 yr [years], etc.) or on the occurrence of plant conditions or events (e.g., cold shutdown, refueling outage, upon detection of a sample failure, following maintenance, etc.).
(a) Components whose test frequencies are based on elapsed time periods shall be tested at the frequencies specified in Section IST with a specified time period between tests as shown in the Table 1. The specified time period between tests may be reduced or extended as follows:
(1) For periods specified as less than 2 yr, the period may be extended by up to 25% for any given test.
(2) For periods specified as greater than or equal to 2 yr, the period may be extended by up to 6 months for any given test.
(3) All periods specified may be reduced at the discretion of the owner (i.e.,
there is no minimum period requirement).
Period extension is to facilitate test scheduling and considers plant operating conditions that may not be suitable for performance of the required testing (e.g.,
performance of the test would cause an unacceptable increase in the plant risk profile due to transient conditions or other ongoing surveillance, test, or maintenance activities). Period extensions are not intended to be used
repeatedly but merely as an operational convenience to extend test intervals beyond those specified.
Period extensions may also be applied to accelerated test frequencies (e.g.,
pumps in alert range) and other fewer than 2-yr test frequencies not specified in Table 1.
Period extensions may not be applied to the test frequency requirements specified in Subsection ISTD, Preservice and lnservice Examination and Testing of Dynamic Restraints (Snubbers) in Light-water Reactor Nuclear Power Plants, as Subsection ISTD contains its own rules for period extensions.
(b) Components whose test frequencies are based on the occurrence of plant conditions or events may not have their period between tests extended except as allowed by the ASME OM Code.
Table 1 Specified Test Frequencies Frequency Specified Time Period Between Tests Quarterly 92 days (or everv 3 months)
Semiannually 184 days (or everv 6 months)
Annually 366days (or everv vear}
x calendar years x Years where 'x' is a whole number of vears :.:: 2 3.1.5 NRC Staff Evaluation Historically, licensees have applied and the NRC staff has accepted, the standard TS definitions for IST intervals (including allowable interval) extensions to ASME OM Code required testing (reference NUREG-1482 Revision 2, Section 3.1.3). Recently, the NRC staff reconsidered the allowance of the TS testing intervals and interval extensions for IST not associated with TS SRs. As noted in RIS 2012-10, the NRC determined that programmatic test frequencies can't be extended in accordance with the TS SR 3.0.2. This includes all IST described in the ASME OM Code not specifically required by the TS SRs.
The lack of a tolerance band on the ASME OM Code IST frequency restricts operational flexibility. The NRC staff recognized that, just as with TS required surveillance testing, some tolerance is needed to allow adjusting ASME OM Code testing intervals to suit the plant conditions and other maintenance and testing activities. To provide operational flexibility when scheduling an IST that minimize the conflicts between the need to complete the testing and plant conditions, the NRC staff sponsored and co-authored an ASME OM Code inquiry and Code Case to modify the ASME OM Code to include TS-like test interval definitions and interval extension criteria. The resultant ASME-Approved Code Case OMN-20, as shown above, was
approved by the ASME Operation and Maintenance Standards Committee on February 15, 2012, with the NRC representative voting in the affirmative. Code Case OMN-20 was subsequently published in conjunction with the 2012 Edition through 2015 Edition of the ASME OM Code.
Requiring the licensee to meet the ASME OM Code requirements, without an allowance for defined frequency and frequency extensions for IST of pumps and valves, results is a hardship without a compensating increase in the level of quality and safety. Based on the licensee's proposal to adopt the ASME-Approved Code Case OMN-20 in its entirety and prior acceptance of the similar TS test interval definitions and interval extension criteria, the NRC staff finds that implementation of the ASME-approved OM Code Case OMN-20 provides reasonable assurance of operational readiness of pumps and valves subject to the IST requirements of ASME OM Code.
4.0 CONCLUSION
As set forth above, the NRC staff determines that for request PR 07 (use Code Case OMN-20),
the proposed alternative provides reasonable assurance that the affected components are operationally ready, and complying with the ASME OM Code requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
Accordingly, the NRC staff concludes that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(z)(2).
Therefore, the NRC staff authorizes alternative request PR 07 for the MNGP current 10-year IST interval which ends May 31, 2022, or until Code Case OMN-20 is incorporated into 10 CFR 50.55a. All other ASME OM Code requirements for which relief was not specifically requested and approved in the subject request remain applicable.
Principal Contributor: Gurjendra S. Bedi Date of issuance: May 15, 2017