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 Issue dateTitleTopic
ML23248A20918 September 2023Proposed Alternative VR-11 to the Requirements of the ASME OM Code Associated with Periodic Verification Testing of MO-2397, Reactor Water Cleanup Inboard Isolation ValveIncorporated by reference
Locked High Radiation Area
Scaffolding
ML23123A42216 May 2023Request RR 001 to Use Later Edition of ASME BPV Section XI Code for Cisi ProgramNondestructive Examination
Incorporated by reference
ML23107A28525 April 2023Authorization and Safety Evaluation for Alternative Request PR-08Incorporated by reference
Grace period
ML23017A22213 January 2023Verbal Authorization of Proposed Alternative PR-08 Regarding Inservice Testing Requirements of Certain High Pressure Coolant Injection System Components (EPID L-2022-LLR-0088) (Email)Incorporated by reference
Grace period
ML22314A21616 November 2022Withdrawal of Alternative Request VR-08
ML22270A23130 September 2022Authorization and Safety Evaluation for Alternative Request No. VR-10Incorporated by reference
Surveillance Frequency Control Program
ML22208A1953 August 2022Summary 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 PlantSurveillance Frequency Control Program
ML22126A10521 June 2022Authorization and Safety Evaluation for Alternative Request No. VR-01Stroke time
Scram Discharge Volume
ML22154A5507 June 2022Authorization and Safety Evaluation for Alternative Request No. PR-02
ML22126A13412 May 2022Authorization and Safety Evaluation for Alternative Request No. PR-05
ML22130A65611 May 2022Authorization and Safety Evaluation for Alternative Request No. PR-04
ML22098A1272 May 2022Authorization and Safety Evaluation for Alternative Request No. VR-02Stroke time
ML22110A12325 April 2022Withdrawal of Relief Requests PR-09 and VR-07 (Epids: L 2021 Llr 0095 and L 2022 Llr 0021)
ML22018A17721 January 2022Authorization and Safety Evaluation for Alternative Request No. VR-05
ML20307A0172 November 2020Request for Alternative for Core Support Structure Weld ExaminationIncorporated by reference
ML20174A54515 July 2020Request for Alternative for Pressure Isolation Valve TestingIncorporated by reference
ML20135G99229 May 2020and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Relief from the Requirements of the ASME CodeLiquid penetrant
ML18270A01519 October 2018and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Relief from the Requirements of the ASME OM CodeIncorporated by reference
Through-Wall Leak
Through-Wall Leakage
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 Interval11 May 201810 CFR 50.55a Request RR-012: Inservice Inspection Impracticality in Accordance with 10 CFR 50 .55a(g)(5)(iii) During the Fifth Ten-Year IntervalNondestructive Examination
VT-2
Aging Management
Pressure Boundary Leakage
ML17122A15715 May 2017Request for Alternative to Use Code Case OMN-20 for the Fifth 10-Year Inservice Testing IntervalGrace period
ML16208A4623 August 2016Safety Evaluation for Request for Alternative Associated with Reactor Pressure Vessel Internals and Components Inspection for the Fifth 10-Year IntervalIncorporated by reference
EVT-1
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 Inspection20 November 201510 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 InspectionAging Management
EVT-1
ML15028A15219 February 2015Relief Request RR-009 Regarding Relief from Examination Coverage Requirements of Section XI of the ASME Code for the Fifth 10-Year Inservice Inspection Program IntervalNon-Destructive Examination
Nondestructive Examination
VT-2
Pressure Boundary Leakage
ML15013A03623 January 2015Relief 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 IntervalIncorporated by reference
EVT-1
ML14223A58127 August 2014Alternative Request Vr 05 to the Testing Requirements of the ASME OM Code for the Fifth 10-Year Inservice Inspection Program IntervalPacking leak
Stroke time
ML12244A27226 September 2012Relief from the Requirements of ASME OM Code for the Fifth Ten-Year IST Program Interval (TAC Nos. ME8067, ME8088 Through ME8096)Stroke time
Scram Discharge Volume
Fuel cladding
Grace period
ML12180A58812 July 2012Approval of ISI Relief Request RR-007 for the Fifth 10-year Interval
ML10200067228 July 2010Approval 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 Term12 March 2010Request 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
ML0617103643 July 2006Monticello 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-513-2Incorporated by reference
L-MT-05-074, Request to Use Subsequent Edition and Addenda of ASME Code for Inservice Testing29 July 2005Request to Use Subsequent Edition and Addenda of ASME Code for Inservice TestingIncorporated by reference
ML0505600498 March 2005Fourth 10-Year Inservice Inspection Interval Request for Relief to Use Code Case N-661Weld Overlay
Incorporated by reference
ML0436300196 January 2005Relief, Fourth 10-year Inservice Inspection Interval Request for Relief No. 4, MC2222Boric Acid
Incorporated by reference
ML04070041525 March 2004Third 10-Year Interval Inservice Inspection Request for Relief RR-17, Involving Repair/Replacement Activity on the Topworks of Main Steam Safety Relief Valve (SRV) GHydrostatic
VT-2
Incorporated by reference
ML04016073826 February 2004Prairie, Units 1 and 2, Kewaunee, Point Beach, Units 1 and 2, Palisades, Re Request for Alternatives to ASME Section XI, Appendix Viii, Supplement 10Nondestructive Examination
Incorporated by reference
Dissimilar Metal Weld
ML0320401573 October 2003Relief Request No. 7, Fourth 10-Year Interval Inservice Inspection Program PlanIncorporated by reference
L-MT-03-045, Request for Approval of Inservice Inspection Program Third 10-Year Interval Relief Request No. 1727 August 2003Request for Approval of Inservice Inspection Program Third 10-Year Interval Relief Request No. 17Hydrostatic
VT-2
ML0320605807 August 2003Relief, Fourth 10-Year Interval Inservice Testing ProgramIncorporated by reference
ML03170020917 July 2003Relief Request, Nos. PR-01, PR-02, PR-03, PR-04, PR-05, and VR-02 Related to the Fourth 10-Year Interval Inservice Testing ProgramStroke time
Power-Operated Valves
L-MT-03-048, Request for Authorization of Inservice Inspection Program Fourth 10-Year Interval Relief Request No. 812 June 2003Request for Authorization of Inservice Inspection Program Fourth 10-Year Interval Relief Request No. 8VT-2
Pressure Boundary Leakage
ML0316008649 June 2003Relief Request, Fourth 10-Year Interval Inservice Inspection Program Plan Relief Request No. 5, TAC No. MB6956Boric Acid
Hydrostatic
VT-2
Incorporated by reference
ML03140011919 May 2003Relief, Third 10-Year Interval Inservice Inspection Relief Request No 16, Parts a, B, and CVT-2
Incorporated by reference
L-MT-03-001, Relief Request No. Pr 06 for Fourth 10-Year Inservice Testing Interval - High Pressure Coolant Injection Pump Testing6 May 2003Relief Request No. Pr 06 for Fourth 10-Year Inservice Testing Interval - High Pressure Coolant Injection Pump Testing