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MONTHYEARML0323301462003-10-0202 October 2003 Relief, Re the Fourth and Successive Inservice Inspection and Inservice Testing Program Intervals Project stage: Other 2003-10-02
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Category:Code Relief or Alternative
MONTHYEARML23312A0882023-11-0808 November 2023 Acceptance of Request to Revise Alternatives 1-RR-5-10 and 2-RR-5-10 ML23130A3872023-05-18018 May 2023 Request 1-RR-5-15 and 2-RR-5-15 to Use Later Edition of ASME Section XI Code for Performance of Repair/Replacement Activities ML22270A3252022-09-30030 September 2022 (Prairie Island), Unit 2 - Authorization and Safety Evaluation for Alternative Request No. RR-08 ML20276A0032020-10-0202 October 2020 Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML20135G9922020-05-29029 May 2020 and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Relief from the Requirements of the ASME Code ML19282A5412019-11-0505 November 2019 Relief from the Requirements of the ASME Code L-PI-19-002, 10 CFR 50.55a Requests Nos. 1-RR-5-10 and 2-RR-5-10, Proposed Alternative to Reactor Vessel Inservice Inspection (ISI) Intervals for Prairie Island, Unit 1 and Unit 22019-06-13013 June 2019 10 CFR 50.55a Requests Nos. 1-RR-5-10 and 2-RR-5-10, Proposed Alternative to Reactor Vessel Inservice Inspection (ISI) Intervals for Prairie Island, Unit 1 and Unit 2 ML19046A1662019-02-25025 February 2019 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 ML16246A2002016-10-0404 October 2016 Request for Relief 1RR-4-11 and 2-RR-4-11 Associated with Certain Inservice Inspection of Component Welds for the Fourth 10-Year Interval ML15196A2132015-08-17017 August 2015 Requests 1-RR-4-9 and 2-RR-4-9 Associated with the Fourth Ten-Year Interval for the Inservice Inspection Program ML15196A2272015-08-12012 August 2015 Requests 1-RR-5-3 and 2-RR-5-3 Associated with the Fifth Ten-Year Interval for the Inservice Inspection Program ML15196A2212015-08-12012 August 2015 Requests 1-RR-5-1 and 2-RR-5-1 Associated with the Fifth Ten-Year Interval for the Inservice Inspection Program ML15079A0032015-05-0404 May 2015 Relief Requests 1-RR-5-5 and 2-RR-5-5 for Fifth 10-Year Interval for the Inservice Inspection Program ML15079A0022015-05-0404 May 2015 Relief Requests 1-RR-5-2 and 2-RR-5-2 for Fifth 10-Year Interval for the Inservice Inspection Program ML14329A1852014-12-0505 December 2014 Relief Requests for Fifth 10-Year Inservice Testing Program Interval (Tac Nos. MF3928 and MF3929) L-PI-14-117, Withdrawal of 10 CFR 50.55a Request RR-01 Associated with the Fifth Ten-Year Interval for the Inservice Test Program (TAC Nos. MF3928 and Mf 3929)2014-11-24024 November 2014 Withdrawal of 10 CFR 50.55a Request RR-01 Associated with the Fifth Ten-Year Interval for the Inservice Test Program (TAC Nos. MF3928 and Mf 3929) ML0807905632008-05-0909 May 2008 Relief Request 1-RR-4-6 for Piping Weld Examination Coverage for the Fourth Inservice Inspection Interval 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 ML0617200152006-07-0303 July 2006 Relief, Evaluation of Relief Request 2-RR-4-6 for Reduced Examination Volume for Class 2 RHR Heat Exchanger Shell- to-Flange Weld L-HU-05-028, ASME Section XI, ISI Request for Relief 21 & 222005-12-19019 December 2005 ASME Section XI, ISI Request for Relief 21 & 22 L-PI-05-038, Withdrawal of 4th Ten-Year Inspection Interval Lnservice Lnspection Program Relief Request No. 1-RR-4-12005-05-0505 May 2005 Withdrawal of 4th Ten-Year Inspection Interval Lnservice Lnspection Program Relief Request No. 1-RR-4-1 ML0509601872005-04-27027 April 2005 Evaluation of Relief Request Nos. 1-RR-4-2, 1-RR-4-3, 2-RR-4-3, 1-RR-4-4, and 2-RR-4-4 for the Fourth 10-Year Inservice Inspection Interval ML0507504282005-04-0707 April 2005 Evaluation of Relief Request to Use Code Case N-661. TAC MC3883 and TAC MC3884 ML0422200422004-10-18018 October 2004 Evaluation of Relief Request No. 16 for the Unit 2 3rd 10-year Interval Inservice Inspection Program ML0418902032004-07-27027 July 2004 Code Relief, Evaluation of Relief Request No. 20, Revision 1 - for the Third 10-Year Inservice Inspection Interval ML0411301922004-05-0303 May 2004 Relief, Limited Examinations Associated with the PINGP Unit 1, Third 10-year Inservice Inspection (ISI) Interval, MB7975 ML0409802342004-04-12012 April 2004 Prairie, Units 1 and 2, Relief Request Nos. 19 and 20 Associated with the 10-Year Interval Inservice Inspection Interval L-PI-04-044, Request for Relief No. 20, Revision 0, for Units 1 & 2, 3rd Ten Year Inservice Inspection Interval2004-03-30030 March 2004 Request for Relief No. 20, Revision 0, for Units 1 & 2, 3rd Ten Year Inservice Inspection Interval 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 ML0332806022004-01-13013 January 2004 Prairie, Units 1 and 2, Relief, No. 15, Evaluation of Relief Request No. 15 for the Third 10-Year Interval Inservice Inspection Program ML0323301462003-10-0202 October 2003 Relief, Re the Fourth and Successive Inservice Inspection and Inservice Testing Program Intervals ML0321300802003-08-13013 August 2003 Relief, Re Using VT-1 Visual Examinations During Third 10-Year Interval Inservice Inspection Program ML0320506712003-07-30030 July 2003 Evaluation of Relief Request No. 18 to Perform a Visual Examination in Lieu of Volumetric Examination of Reactor Vessel Nozzle Inner Radius Sections Per Code Case N-648-1, MB8363 and MB8364 ML0316402462003-06-17017 June 2003 Relief Request, Third 10-Year Interval Inservice Inspection Program ML0232905782002-11-16016 November 2002 Request for Relief No. 9 for the Unit 2 Third 10-Year Interval Inservice Inspection Program ML0230102092002-11-0707 November 2002 Relief, Third 10-Year Interval Inservice Inspection Program ML0226202392002-10-0101 October 2002 Relief, Evaluation of Relief Request Associated with the Third 10-Year Interval Inservice Inspection Program (MB5388, 5399, 5390, & 5391) ML0212904282002-06-11011 June 2002 Relief Request, Related to the First Interval Inservice Inspection Program for Metal Containment ML0216105082002-05-31031 May 2002 Request for Relief No. 12 for the Unit 2 3rd 10-Year Interval Inservice Inspection Program 2023-05-18
[Table view] 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
[Table view] Category:Safety Evaluation
MONTHYEARML23356A0032024-01-17017 January 2024 Issuance of Amendments Revise Technical Specification 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) ML23215A1672023-12-15015 December 2023 Acceptance of Requested Licensing Action Amendment Request to Revise Surveillance Requirement 3.8.1.2 Note 3 ML23115A4072023-04-26026 April 2023 Correction of License Amendment Nos. 226 and 214 Adoption of TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control - RITSTF Initiative 5B 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 ML22300A2232022-11-0101 November 2022 Issuance of Amendments 241 and 229 TSTF-577 Revised Frequencies for Steam Generator Tube Inspections ML22270A3252022-09-30030 September 2022 (Prairie Island), Unit 2 - Authorization and Safety Evaluation for Alternative Request No. RR-08 ML22181A0002022-08-17017 August 2022 Issuance of Amendments Reactor Trip System Power Range Instrumentation Channels ML22166A3892022-07-28028 July 2022 Issuance of Amendments 239 and 227 24-Month Operating Cycle ML22061A2062022-04-0101 April 2022 Issuance of Amendments TSTF-471, Rev. 1, TSTF-571-T, and Administrative Changes to Technical Specification Section 5.0 ML21312A0212021-11-23023 November 2021 Issuance of Amendment Nos. 237 and 225 Inoperable Cooling Water System Supply Header ML21008A0012021-03-19019 March 2021 Issuance of Amendment Nos. 236 and 224 Low Temperature Overpressure Protection ML20346A0202021-03-15015 March 2021 Issuance of Amendment Nos. 235 and 223, Adoption of Technical Specifications Task Force Traveler TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML20356A0022021-02-0505 February 2021 Issuance of Amendment Nos. 234 and 222, Revise Technical Specifications 3.2.1 and 5.6.5 Identified in Westinghouse Nuclear Safety Advisory Letters NSAL-09-05, Revision 1, and NSAL-15-1 ML20283A3422020-11-18018 November 2020 Issuance of Amendment Nos. 233 and 221 Adoption of Technical Specifications Task Force Traveler TSTF-547, Clarification of Rod Position Requirements ML20217L1852020-10-0202 October 2020 Issuance of Amendment Nos. 232 and 220 Increase the Integrated Leak Rate Test Program Type a and Type C Test Frequency ML20276A0032020-10-0202 October 2020 Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI 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 ML20230A0512020-09-0303 September 2020 Reactor Vessel Material Surveillance Capsule Withdrawal Schedules 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 ML19276F6842019-11-12012 November 2019 Issuance of Amendments 230 and 218 Issuance of Amendments Adoption of 10 CFR 50.69 - Risk Informed Caterization and Treatment of Structure, Systems and Components of Nuclear Power Reactors ML19232A1512019-11-0707 November 2019 Issuance of Amendments Modifying the Design Basis for Quality Classification of Certain Fuel Handling Equipment ML19140A4472019-07-30030 July 2019 Issuance of Amendments Revision to National Fire Protection Association (NFPA) Standard NFPA 805 Modifications ML19177A3802019-07-0303 July 2019 Reactor Vessel Material Surveillance Capsule Withdrawal Schedules ML19128A1332019-06-0606 June 2019 Issuance of Amendments TSTF-439 Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO ML19045A4802019-04-16016 April 2019 Issuance of Amendment Nos. 226 and 214 Adoption of TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control - RITSTF Initiative 5B ML19046A1662019-02-25025 February 2019 Relief from the Requirements of the ASME Code ML19029A0942019-01-29029 January 2019 Issuance of Amendment No. 213, One-Time Technical Specification Change to Extend Completion Time for EDGs D5 and D6 (Emergency Circumstances) ML18270A0152018-10-19019 October 2018 and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Relief from the Requirements of the ASME OM Code ML18100A7882018-05-0101 May 2018 Issuance of Amendment Special Heavy Lifting Device Nondestructive Examination Frequency (CAC Nos. MG0072 and MG0073; EPID L-2017-LLA-0280) ML17346A3612018-03-0606 March 2018 Issuance of Amendment Nos. 224 and 211 to Adopt Changes to the Emergency Plan ML17362A2022018-03-0505 March 2018 Issuance of Amendment Concerning Revision to the Prairie Island Nuclear Generating Plant, Units 1 and 2 Emergency Plan (CAC Nos. MF9345 and MF9346; EPID L-2017-LLA-0175) ML17334A1782017-11-30030 November 2017 Issuance of Amendment Request Related to Spent Fuel Pool Criticality Technical Specification Changes (CAC Nos. MF7121 and MF7122, EPID L-2015-LLA-0002) Non-Proprietary 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) ML17163A0272017-08-0808 August 2017 Issuance of Amendments Transition to NFPA-805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants ML17130A7162017-06-20020 June 2017 Issuance of Amendments Technical Specification 3.8.7 Inverters-Operating ML17110A2752017-05-0404 May 2017 Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 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 ML16256A5142016-10-13013 October 2016 Issuance of Amendment One-Time Extension for Technical Specification Surveillance Requirement 3.8.4.3. DC Sources - Operating ML16246A2002016-10-0404 October 2016 Request for Relief 1RR-4-11 and 2-RR-4-11 Associated with Certain Inservice Inspection of Component Welds for the Fourth 10-Year Interval ML16133A4062016-06-16016 June 2016 Issuance of Amendment Nos. 217 and 205, Adoption of Technical Specifications Task Force TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation (CAC Nos. MF6449 and MF6450) ML15264A2092015-11-30030 November 2015 Issuance of Amendment Nos. 216 and 204 Regarding Revisions to Technical Specification 3.3.3 and Renewed Facility Operating License ML15229A1762015-08-26026 August 2015 Issuance of Amendment Nos. 215 and 203 Regarding Revision to Licensing Basis Analysis for a Waste Gas Decay Tank Rupture ML15196A2132015-08-17017 August 2015 Requests 1-RR-4-9 and 2-RR-4-9 Associated with the Fourth Ten-Year Interval for the Inservice Inspection Program ML15196A2412015-08-12012 August 2015 Requests 1-RR-5-6 and 2-RR-5-6 Associated with the Fifth Ten-Year Interval for the Inservice Inspection Program ML15196A2272015-08-12012 August 2015 Requests 1-RR-5-3 and 2-RR-5-3 Associated with the Fifth Ten-Year Interval for the Inservice Inspection Program ML15196A2212015-08-12012 August 2015 Requests 1-RR-5-1 and 2-RR-5-1 Associated with the Fifth Ten-Year Interval for the Inservice Inspection Program ML15196A4322015-08-0606 August 2015 Requests 1-RR-4-11 and 2-RR-4-11 Associated with the Fourth Ten-Year Interval for the Inservice Inspection Program ML15196A1952015-08-0606 August 2015 Request 2-RR-4-10 Associated with the Fourth Ten-Year Interval for the Inservice Inspection Program 2024-01-17
[Table view] |
Text
October 2, 2003 Mr. Joseph M. Solymossy Site Vice President Prairie Island Nuclear Generating Plant Nuclear Management Company, LLC 1717 Wakonade Drive East Welch, MN 55089
SUBJECT:
PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNIT 11 - EVALUATION OF RELIEF REQUEST ASSOCIATED WITH EXTENDING UNIT 1 IST/ISI INTERVAL TO ALIGN THE FOURTH 10-YEAR INTERVAL WITH UNIT 2 (TAC NOS. MB7564 AND MB7565)
Dear Mr. Solymossy:
By letter dated January 24, 2003, the Nuclear Management Company, LLC (NMC), submitted a Relief Request concerning the fourth and successive inservice inspection (ISI) and inservice testing (IST) program intervals for the Prairie Island Nuclear Generating Plant, Unit 1.
Specifically, NMC proposed extending the third IST/ISI program intervals for Unit 1 so that the fourth IST/ISI program intervals would begin on December 21, 2004, which is the same start date as the fourth IST/ISI program intervals for Unit 2.
The enclosure provides the U. S. Nuclear Regulatory Commission (NRC) staffs safety evaluation (SE) for this request. As noted in the SE, the NRC staff concludes that NMCs proposed start date of December 21, 2004, for the Unit 1 fourth IST/ISI program intervals provide an acceptable level of quality and safety. Therefore, pursuant to 10 CFR 50.55a(a)(3)(i), the NRC staff authorizes NMCs proposed change in the Unit 1 fourth and successive IST/ISI program interval start dates.
Sincerely,
/RA/
L. Raghavan, Chief, Section 1 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-282
Enclosure:
Safety Evaluation cc w/encl: See next page 1
In its January 24, 2003, letter, NMC referenced the docket and license numbers for both Prairie Island Unit 1 and Unit 2. However, relief was requested only for Unit 1.
ML032330146 *Provided SE input by memo OFFICE PDIII-1/PM PDIII-1/LA EMCB/SC* OGC PDIII-1/SC NAME AMcMurtray RBouling DTerao RHoefling LRaghavan DATE 09/09/03 09/08/03 08/13/03 09/17/03 10/02/03 Prairie Island Nuclear Generating Plant, Units 1 and 2 cc:
Jonathan Rogoff, Esquire Tribal Council General Counsel Prairie Island Indian Community Nuclear Management Company, LLC ATTN: Environmental Department 700 First Street 5636 Sturgeon Lake Road Hudson, WI 54016 Welch, MN 55089 Manager, Regulatory Affairs Nuclear Asset Manager Prairie Island Nuclear Generating Plant Xcel Energy, Inc.
Nuclear Management Company, LLC 414 Nicollet Mall, R.S. 8 1717 Wakonade Drive East Minneapolis, MN 55401 Welch, MN 55089 John Paul Cowan Manager - Environmental Protection Division Executive Vice President & Chief Nuclear Minnesota Attorney Generals Office Officer 445 Minnesota St., Suite 900 Nuclear Management Company, LLC St. Paul, MN 55101-2127 700 First Street Hudson, WI 54016 U.S. Nuclear Regulatory Commission Resident Inspector's Office Mano K. Nazar 1719 Wakonade Drive East Senior Vice President Welch, MN 55089-9642 Nuclear Management Company, LLC Prairie Island Nuclear Generating Plant Regional Administrator, Region III 1717 Wakonade Drive East U.S. Nuclear Regulatory Commission Welch, MN 55089 801 Warrenville Road Lisle, IL 60532-4351 Administrator Goodhue County Courthouse Box 408 Red Wing, MN 55066-0408 Commissioner Minnesota Department of Commerce 121 Seventh Place East Suite 200 St. Paul, MN 55101-2145 September 2003
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO PROPOSED ALTERNATIVE TO ALIGN UNIT 1 AND UNIT 2 IST/ISI PROGRAMS NUCLEAR MANAGEMENT COMPANY, LLC PRAIRIE ISLAND NUCLEAR GENERATION PLANT, UNIT 1 DOCKET NO. 50-282
1.0 INTRODUCTION
By letter dated January 24, 2003, the Nuclear Management Company, LLC (the licensee),
submitted a Relief Request concerning the fourth and successive inservice inspection (ISI) and inservice testing (IST) program intervals for the Prairie Island Nuclear Generating Plant (PINGP), Unit 1. Specifically, NMC proposed extending the third IST/ISI program intervals for Unit 1 so that the fourth IST/ISI program intervals would begin on December 21, 2004, which is the same start date as the fourth IST/ISI program intervals for Unit 2.
2.0 REGULATORY EVALUATION
Title 10 of the Code of Federal Regulations (10 CFR), Section 50.55a, requires that IST of certain American Society of Mechanical Engineers (ASME) "Boiler and Pressure Vessel Code (Code) Class 1, 2, and 3 pumps and valves and ISI of certain ASME Code Class 1, 2, and 3 components (including supports) be performed at 120-month (10-year) IST/ISI program intervals. This is in accordance with the ASME Code for Operation and Maintenance of Nuclear Power Plants (OM Code) and ASME Code,Section XI, Rules for Inservice Inspection (ISI) of Nuclear Power Plant Components, and applicable addenda, except where alternatives have been proposed or relief has been requested by the licensee and authorized or granted by the Commission pursuant to paragraphs (a)(3)(i), (a)(3)(ii),or (f)(6)(i) of 10 CFR 50.55a. In accordance with 10 CFR 50.55a(f)(4)(ii) and 10 CFR 50.55a(g)(4)(ii), licensees are required to comply with the requirements of the latest edition and addenda of the ASME Code incorporated by reference in the regulations 12 months prior to the start of each 10-year IST/ISI program interval. In proposing alternatives or requesting relief, the licensee must demonstrate that:
(1) the proposed alternatives provide an acceptable level of quality and safety; (2) compliance would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety; or (3) conformance is impractical for the facility. The regulation at 10 CFR 50.55a allows the Commission to authorize alternatives to and grant relief from ASME Code requirements upon making necessary findings. Nuclear Regulatory Commission (NRC) guidance contained in Generic Letter (GL) 89-04, Guidance on Developing Acceptable Inservice Testing Programs, provides alternatives to Code requirements which are acceptable.
Further guidance is given in GL 89-04, Supplement 1, and NUREG-1482, Guidance for Inservice Testing at Nuclear Power Plants.
ENCLOSURE
3.0 TECHNICAL EVALUATION
3.1 Code Requirements The licensee proposed alternatives to the IST/ISI program update frequency and interval requirements of 10 CFR 50.55a(f)(4)(ii), 10 CFR 50.55a(g)(4)(ii), ASME Code,Section XI, paragraph IWA-2430(b), and ASME Code,Section XI, paragraph IWA-2432.
3.2 Licensees Basis for Proposed Alternative (as stated)
PINGP, Units 1 and 2 commenced commercial operation on December 16, 1973, and December 21, 1974, respectively. These dates are approximately one year apart (370 days). Since the ISI and IST Program interval dates are dictated by the commercial operating dates, the Editions of ASME Section XI and OM Codes effective during the 370 days between the unit updates will be different. When the next update becomes effective, PINGP Unit 1 will be using the latest ASME Section XI Edition and OM Code referenced in 10 CFR 50.55a (1998 Edition with 2000 Addenda), while PINGP Unit 2 will still be using the 1989 Edition. Updating an ISI or IST program to a new Code edition requires a significant amount of work on the part of many personnel to ensure compliance, and requires the updating of numerous documents, procedures and processes including training.
Having both units on the same edition of the ASME Codes and schedule has distinct advantages without a reduction in the level of quality and safety.
- 1. Site procedures will be meeting the requirements of one edition of the Code, instead of two different editions
- 2. The ISI and IST Programs can be written as one document covering both units.
- 3. A reduction in the probability of applying a wrong inspection and/or test requirement.
- 4. Having one set of procedures and documents reduces the administrative burden of complying with the ISI and IST requirements without a reduction in the level of quality of the ISI and IST Programs.
With the proposed alternative schedule for Unit 1, the required 3rd Ten-Year Interval (and following) examinations and tests will be completed. There will be no reduction in the number of ISI examinations or IST testing as a result of the date change.
3.3 Licensees Proposed Alternative to Code Requirements The licensee proposes adjusting the Unit 1 fourth 10-year IST/ISI program interval start dates to December 21, 2004, to coincide with the Unit 2 fourth 10-year IST/ISI program interval start dates.
3.4 NRC Staff Evaluation The regulation at 10 CFR 50.55a(f)(4)(ii) and 10 CFR 50.55a(g)(4)(ii) requires that IST of ASME Code Class 1, 2, and 3 pumps and valves and ISI of certain ASME Code Class 1, 2, and 3 components (including supports) conducted during successive 10-year program intervals comply with the requirements of the latest edition and addenda of the ASME Code prior to the start of the 10-year IST/ISI program interval. Furthermore, the ASME Code,Section XI, paragraph IWA-2432, requires that successive program intervals be 10 years after the previous inspection interval. The licensee proposed an alternative to updating the IST/ISI programs on the timetable required by the ASME Code,Section XI. The licensee proposed that the start date for the Unit 1 fourth 10-year IST/ISI program intervals be aligned with the Unit 2 fourth 10-year IST/ISI program intervals, scheduled to commence on December 21, 2004.
The ASME Code,Section XI, paragraph IWA-2430, allows inspection intervals to be extended or decreased by as much as 1 year (365 days). Invoking the 1-year extension allowed by the ASME Code would result in a 5-day difference between the Code-allowed start date for the Unit 1 fourth 10-year IST/ISI program intervals, and the start date requested by the licensee.
With the proposed alternative schedule for Unit 1, the required third 10-year IST/ISI program intervals, (and following) tests and examinations will be completed. There would be no reduction in the number of IST/ISI tests or examinations as a result of extending the Unit 1 fourth 10-year IST/ISI program interval date and the licensee will be using the latest applicable ASME Code edition for both units fourth 10-year IST/ISI program intervals.
As noted in the licensees basis for the proposed alternative, the editions of the ASME Code for the IST/ISI programs are not the same and are approximately 1 year apart (370 days) due to the different commercial operating dates. This results in a significant amount of work on the part of the licensee and having both units on the same edition of the ASME Code and schedule has distinct advantages. There are fewer procedures to maintain, and the licensees procedures will meet the requirements of one edition of the Code. Also, the IST/ISI programs will be written as one document covering both units reducing the chance of the licensee applying the wrong IST/ISI requirements. Finally, maintaining one set of procedures and documents reduces the administrative burden in complying with IST/ISI requirements and does not reduce the quality of the IST/ISI programs.
Based on the above, the NRC staff concludes that the licensees proposed alternative provides an acceptable level of quality and safety 3.5 Conclusion Based on the licensees proposed alternative providing an acceptable level of quality and safety, the NRC staff authorizes the proposed alternative to align the Unit 1 IST/ISI program intervals with the Unit 2 IST/ISI program intervals, pursuant to 10 CFR 50.55a(a)(3)(i).
Principal Contributor: W. Poertner Date: October 2, 2003