Letter Sequence Approval |
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EPID:L-2021-LLR-0060, 10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval PR-04 (L-MT-21-013) (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] |
Text
May 11, 2022 MONTICELLO NUCLEAR GENERATING PLANT - AUTHORIZATION AND SAFETY EVALUATION FOR ALTERNATIVE REQUEST NO. PR-04 (EPID L-2021-LLR-0060)
LICENSEE INFORMATION Recipients Name and Address: Mr. Christopher P. Domingos 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(s) and Unit(s): Monticello Nuclear Generating Plant Docket No(s).: 50-263 APPLICATION INFORMATION Submittal Date: August 25, 2021 Submittal Agencywide Documents Access and Management System (ADAMS) Accession No.: ML21237A372 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 ISTB-3510, General, paragraph (a), Accuracy, states, in part, Instrument accuracy shall be within the limits of Table ISTB-3510-1. ISTB-3510, General, paragraph (b), Range, subparagraph (1), states, The full-scale range of each analog instrument shall be not greater than three times the reference value. Table ISTB-3510-1, Required Instrument Accuracy, contains the required accuracy for
instruments measuring the various pump parameters, including pressure and differential pressure. It lists +/-2 percent for pressure for a Group B test.
Brief Description of the Proposed Alternative: Northern States Power Company, a Minnesota corporation, doing business as Xcel Energy (hereafter, the licensee), requested U.S.
Nuclear Regulatory Commission (NRC) authorization of this 10 CFR 50.55a request to support the implementation of the sixth IST 10-year program interval for Monticello Nuclear Generating Plant (MNGP). Proposed Alternative No. PR-04 requests authorization for an alternative means of determining the instrument range requirements for testing of the high-pressure coolant injection (HPCI) pump P-209 and reactor core isolation cooling (RCIC) pump P-207.
Summary of Commitments: This submittal makes no new commitments and no revisions to existing commitments.
For additional details on the licensees request, please refer to the documents located at the ADAMS Accession No(s) identified above.
STAFF EVALUATION The NRC staff reviewed the licensee's alternative to the Group B tests required under the ASME OM Code to apply three times the reference value to the equivalent range identified in table PR 04-2 in their submittal for instruments PI-23-116, PT-23-100, and PI-13-66. Based upon the proposed alternative ASME OM Code equivalent range, the licensee would apply the accuracy requirement of +/- 2 percent to the established equivalent range (i.e., 3 x 33.7 = 101 pounds per square inch (psi) for the instruments and 3 x 11.8 = 35.4 milliamps (mA) for the transmitter).
The two pressure indicators are calibrated to an accuracy of +/- 2 psi. The pressure transmitter is calibrated to an accuracy of +/- 0.7 mA. The +/- 2 percent ASME OM Code instrument accuracy requirement equates to +/- 2 psi for the pressure indicator and +/- 0.7 mA for the pressure transmitter. The reading given by the licensee's installed instrumentation results in the actual variance having a value essentially equal to the maximum variance in the reading allowed by the ASME OM Code. Therefore, the installed instrumentation has sufficient accuracy because the variance in test results is essentially equal to the variance allowed if the ASME OM Code requirements are met (i.e., up to +/- 6 percent) and, thus, provide an acceptable level of quality and safety.
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 PR-04 for instruments PI-23-116, PT-23-100 and PI-13-66 at Monticello Nuclear Generating Plant, for the sixth 10-year IST program interval, starting October 1, 2022, and scheduled to end May 31, 2032.
All other ASME OM Code requirements for which an alternative was not specifically requested and approved remain applicable.
Principal Contributor: Ian Tseng Date: May 11, 2022 Digitally signed by Scott Scott P. Wall P.Date:
Wall 2022.05.11 15:05:46 -04'00' Nancy L. Salgado Chief Plant Licensing Branch IIII Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation cc: Listserv
ML22130A656 OFFICE NRR/DORL/LPL3/PM NRR/DORL/LPL3/LA NRR/DEX/EMIB/BC NRR/DORL/LPL3/BC NAME RKuntz SRohrer SBailey NSalgado (SWall for)
DATE 05/06/2022 05/10/2022 05/05/2022 05/11/2022
