Letter Sequence Approval |
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EPID:L-2021-LLR-0063, 10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval VR-05 (L-MT-21-041) (Approved, Closed) |
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Category:Code Relief or Alternative
MONTHYEARML23248A2092023-09-18018 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
2023-09-18
[Table view]
Category:Safety Evaluation
MONTHYEARML23248A2092023-09-18018 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
ML20135G9922020-05-29029 May 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
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
ML15175A0162015-06-30030 June 2015
Staff Evaluation of 10 CFR 50.54(p)(2) Changes to Security Plans
ML15072A1412015-06-0505 June 2015
Issuance of Amendment No. 188 Regarding Transition to Areva Atrium 10XM Fuel and Areva Safety Analysis Methods
ML15154A4772015-06-0505 June 2015
Safety Evaluation Regarding License Amendment No. 188 Associated with Areva Atrium 10XM Fuel Transition (TAC No. MF2479) - (Redacted)
ML14358A0392015-02-20020 February 2015
Northern States Power Company, Minnesota (NSPM) - Monticello Nuclear Generating Plant, Prairie Island Nuclear Generating Plant, Prairie Island ISFSI - Review of Changes to the NSPM Quality Assurance Topical Report
2023-09-18
[Table view] |
Text
January 21, 2022 MONTICELLO NUCLEAR GENERATING PLANT - AUTHORIZATION AND SAFETY EVALUATION FOR ALTERNATIVE REQUEST NO. VR-05 (EPID L-2021-LLR-0063)
LICENSEE INFORMATION Recipients Name and Address: Mr. Thomas A. Conboy Site Vice President Northern States Power Company - Minnesota Monticello Nuclear Generating Plant 2807 West County Road 75 Monticello, MN 55362 Licensee: Northern States Power Company Plant Name: Monticello Nuclear Generating Plant Docket No.: 50-263 APPLICATION INFORMATION Submittal Date: August 31, 2021 Submittal Agencywide Documents Access and Management System (ADAMS) Accession No.: ML21243A299 Alternative Provision: The applicant requested an alternative under Title 10 of the Code of Federal Regulations (10 CFR), paragraph 50.55a(z)(1).
Applicable Code Edition and Addenda: American Society of Mechanical Engineers (ASME),
Operation and Maintenance of Nuclear Power Plants (OM) Code, 2017 Edition with no Addenda.
Applicable Inservice Inspection (ISI) or Inservice Testing (IST) Program Interval and Interval Start/End Dates: Sixth 10-year IST interval currently scheduled to begin on October 1, 2022, and end on May 31, 2032.
IST Requirement: ASME OM Code, Subsection ISTC, paragraph ISTC-3522, Category C, Check Valves, states, in part, Category C check valves shall be exercised as follows: (a)
During operation at power, each check valve shall be exercised or examined in a manner that verifies obturator travel by using the methods in paragraph ISTC-5221 (c) If exercising is not practicable during operation at power and cold shutdown outages, it shall be performed during refueling outages [RFOs]. ASME OM Code, Subsection ISTC, paragraph ISTC-3630, Leakage Rate for Other Than Containment Isolation Valves, states, in part, Category A valves with a leakage requirement not based on an Owner s 10 CFR 50, Appendix J, program, shall be
tested to verify their seat leakages within acceptable limits. Valve closure before seat leakage testing shall be by using the valve operator with no additional closing force applied. ASME OM Code, Subsection ISTC, paragraph ISTC-3630(a), Frequency, states, "Tests shall be conducted at least once every 2 yr."
Brief Description of the Proposed Alternative: Northern States Power Company, a Minnesota corporation, doing business as Xcel Energy (hereafter NSPM or the licensee),
hereby requests the U.S. Nuclear Regulatory Commission (NRC) authorization of this 10 CFR 50.55a request to support the implementation of the sixth IST interval for Monticello Nuclear Generating Plant (Monticello). Proposed Alternative No. VR-05 requests authorization for an alternative to the conduct of pressure isolation valve (PIV) testing each RFO and instead proposes to adopt a performance-based testing approach similar to that established under 10 CFR 50, Appendix J, "Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors," Option B, "Performance-Based Requirements."
For additional details on the licensees request, please refer to the document located at the ADAMS Accession No. identified above.
STAFF EVALUATION ASME OM Code 2017 Edition, paragraph ISTC-3630(a), requires that valves within the scope of the ASME OM Code that have specific leakage criteria (other than containment isolation valves that are tested in accordance with 10 CFR Part 50, Appendix J) are required to be leak rate tested at least once every 2 years. The request proposed an alternative test in lieu of this requirement for the 11 specific pressure isolation valves listed. Specifically, the request proposes to functionally test and verify the leakage rate of 11 valves using a 10 CFR Part 50, Appendix J, Option B, performance-based schedule. Valves would initially be tested at the required interval schedule which is currently every RFO or 2 years as specified by ASME OM Code, Subsection ISTC, paragraph ISTC-3630(a). Valves that have demonstrated good performance for two consecutive cycles may have their test interval extended to 75 months with a permissible extension for non-routine emergent conditions of 9 months (84 months total). Any valve leakage test failure would require the component to return to the initial interval of every 30 months until good performance can again be established.
Regulation 10 CFR Part 50, Appendix J, Option B, is a performance-based containment leakage test program. Guidance for implementation of acceptable leakage rate test methods, procedures, and analyses, is provided in NRC Regulatory Guide (RG) 1.163, Performance Based Containment Leak Test Program (ADAMS Accession No. ML003740058). RG 1.163 endorses Nuclear Energy Institute (NEI) Topical Report (TR) 94-01, Revision 0, Industry Guideline for Implementing Performance Based Option of 10 CFR 50, Appendix J, dated July 26, 1995, with the limitation that Type C components test interval cannot extend greater than 60 months. The current version of NEI 94-01 is Revision 3-A (ADAMS Accession No. ML12221A202), which allows Type C containment isolation valves test intervals to be extended to 75 months with a permissible extension for non-routine emergent conditions of 9 months (84 months total). In letters dated June 8, 2021, and December 6, 2012, the NRC staff found the guidance in NEI 94-01 Revision 3-A, to be acceptable (see ADAMS Accession Nos.
ML121030286 and ML12226A546, respectively) with the following conditions:
- 1) Extended interval for Type C local leak rate tests (LLRTs) may be increased to 75 months with the requirement that a licensees post-outage report include the margin between Type B and Type C leakage rate summation and its regulatory limit. In
addition, a corrective action plan shall be developed to restore the margin to an acceptable level. Extensions of up to 9 months (total maximum interval of 84 months for Type C tests) are permissible only for non-routine emergent conditions. This provision (9-month extension) does not apply to valves that are restricted and/or limited to 30-month intervals in Section 10.2 (such as BWR (boiling-water reactor) main steam isolation valves) or to valves held to the base interval (30 months) due to unsatisfactory LLRT performance.
- 2) When routinely scheduling any LLRT valve interval beyond 60-months and up to 75-months, the primary containment leakage rate testing program trending or monitoring must include an estimate of the amount of understatement in the Type B & C total and must be included in a licensees post-outage report. The report must include the reasoning and determination of the acceptability of the extension, demonstrating that the LLRT totals calculated represent the actual leakage potential of the penetrations.
This same alternative request was recently authorized on July 15, 2020 (ADAMS Accession No. ML20174A545), for the remainder of Monticello fifth IST interval which is currently scheduled to end on September 30, 2022. The NRC staff review completed for the sixth IST interval at Monticello, along with this previous authorization, remains the same with no additional comments or conditions. Based on its review the NRC staff finds that proposed alternative VR-05 for a process to justify an extension of the leakage testing intervals for these PIVs at Monticello provides an acceptable level of quality and safety in accordance with 10 CFR 50.55a(z)(1).
CONCLUSION The NRC staff has determined that the proposed alternative in the licensees request referenced above would provide an acceptable level of quality and safety.
The NRC staff concludes that the licensee has adequately addressed the regulatory requirements set forth in 10 CFR 50.55a(z)(1).
The NRC staff authorizes the use of proposed alternative VR-05 at Monticello for the sixth 10-year IST interval currently scheduled to begin on October 1, 2022, and end on May 31, 2032.
All other ASME OM Code requirements for which an alternative was not specifically requested and approved remain applicable.
Principal Contributor: Michael F. Farnan Digitally signed by Date: January 21, 2022 Joel S. Joel S. Wiebe Date: 2022.01.21 Wiebe 14:19:33 -05'00' Nancy L. Salgado, Chief Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation cc: Listserv
ML22018A177 OFFICE NRR/DORL/LPL3/PM NRR/DORL/LPL3/LA NRR/DEX/EMIB/BC(A) NRR/DORL/LPL3/BC NAME RKuntz SRohrer ITseng NSalgado (JWiebe for)
DATE 1/18/2022 1/19/2022 01/11/2022 1/21/2022
