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| | number = ML062990171 | | | number = ML062990171 |
| | issue date = 11/03/2006 | | | issue date = 11/03/2006 |
| | title = Prairie Island Nuclear Generating Plant Units 1 and 2 Safety Evaluation for Administrative Changes to the Technical Specifications | | | title = Safety Evaluation for Administrative Changes to the Technical Specifications |
| | author name = Kobetz T J | | | author name = Kobetz T |
| | author affiliation = NRC/NRR/ADRO/DIRS/ITSB | | | author affiliation = NRC/NRR/ADRO/DIRS/ITSB |
| | addressee name = Raghavan L | | | addressee name = Raghavan L |
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| =Text= | | =Text= |
| {{#Wiki_filter:November 3, 2006MEMORANDUM TO:L. Raghavan, ChiefPant Licensing Branch E Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationFROM:Timothy J. Kobetz, Chief /RA/Technical Specifications Branch Division of Inspection and Regional Support Office of Nuclear Reactor Regulation | | {{#Wiki_filter:November 3, 2006 MEMORANDUM TO: L. Raghavan, Chief Pant Licensing Branch E Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: Timothy J. Kobetz, Chief /RA/ |
| | Technical Specifications Branch Division of Inspection and Regional Support Office of Nuclear Reactor Regulation |
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| ==SUBJECT:== | | ==SUBJECT:== |
| PRAIRIE ISLAND NUCLEAR GENERATING PLANT (PINGP) UNITS 1AND 2 SAFETY EVALUATION FOR ADMINISTRATIVE CHANGES TO THE TECHNICAL SPECIFICATIONS By the letter dated February 13, 2006, the Nuclear Management Company, LLC (NMC),the licensee, submitted a License Amendment Request to revise the technical specifications(TS) of the Prairie Island Nuclear Generating Plant, Units 1 and 2. The licensee is requesting to revise the page header and capitalizations in TS 3.0, "Surveillance Requirement (SR) | | PRAIRIE ISLAND NUCLEAR GENERATING PLANT (PINGP) UNITS 1 AND 2 SAFETY EVALUATION FOR ADMINISTRATIVE CHANGES TO THE TECHNICAL SPECIFICATIONS By the letter dated February 13, 2006, the Nuclear Management Company, LLC (NMC), |
| Applicability;" and revise format and titles in TS 5.0, "Administrative Controls." The attached Safety Evaluation (SE) addresses the proposed administrative TS changes. Our SE concludes the licensee's administrative TS revisions are acceptable. | | the licensee, submitted a License Amendment Request to revise the technical specifications (TS) of the Prairie Island Nuclear Generating Plant, Units 1 and 2. The licensee is requesting to revise the page header and capitalizations in TS 3.0, Surveillance Requirement (SR) |
| | Applicability; and revise format and titles in TS 5.0, Administrative Controls. The attached Safety Evaluation (SE) addresses the proposed administrative TS changes. Our SE concludes the licensees administrative TS revisions are acceptable. |
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| ==Enclosure:== | | ==Enclosure:== |
| As statedCONTACT: Pete Hearn, NRR/ITSB301-415-1189 pch@nrc.gov
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| ML062990171DOCUMENT NAME: G:\ITSB\Hearn\Paire Island ADMIN Changes.wpdOFFICETSS:IROB:DIPMSC:TSS:IROB:DIPMNAMEPHearnTKobetzDATE10/31/200611/3/2006 EnclosureSAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENTS TO FACILITY OPERATING LICENSE PRAIRIE ISLAND NUCLEAR POWER PLANTS, UNITS 1 AND 2DOCKET N0S. 50-282 AND 50-3061.INTRODUCTIONPursuant to 10 CFR 50.90, on February 13, 2006, the Nuclear Management Company, thelicensee, submitted a License Amendment Request (LAR) to amend the Prairie Island Nuclear Generation Plant (PINGP), Units 1 License. The LAR proposes to revise the PINGP Technical Specifications (TS) to change the wording in TS 3.0 "Surveillance Requirement (SR)
| | As stated CONTACT: Pete Hearn, NRR/ITSB 301-415-1189 pch@nrc.gov |
| Applicability" and change format and titles in Chapter 5.0, "Administrative Controls." The proposed changes improve the TS usability, conformance with the industry standard, NUREG-1431, "Standard Technical Specifications, Westinghouse Plants," Revision 3.0 and accuracy.
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| ==2.0REGULATORY EVALUATION==
| | ML062990171 DOCUMENT NAME: G:\ITSB\Hearn\Paire Island ADMIN Changes.wpd OFFICE TSS:IROB:DIPM SC:TSS:IROB:DIPM NAME PHearn TKobetz DATE 10/31/2006 11/3/2006 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENTS TO FACILITY OPERATING LICENSE PRAIRIE ISLAND NUCLEAR POWER PLANTS, UNITS 1 AND 2 DOCKET N0S. 50-282 AND 50-306 |
| Section 182a of the Atomic Energy Act (Act) requires applicants for nuclear power plantoperating licenses to include technical specifications as part of the license. These technical specifications are derived from the plant safety analyses.The staff reviewed the proposed changes for compliance with 10 CFR 50.36 and agreementwith the precedent as established in NUREG-1431. In general, licensees cannot justify technical specification changes solely on the basis of adopting the model STS. To ensure this,the staff makes a determination that proposed changes maintain adequate safety. Changes that result in relaxation (less restrictive condition) of current TS requirements require detailed justification.In general, there are two classes of changes to technical specifications: (1) changes needed toreflect contents of the design basis (technical specifications are derived from the design basis),and (2) voluntary changes to take advantage of the evolution in policy and guidance as to the required content and preferred format of technical specifications over time. This amendment deals with the second class of change; namely, administrative changes that reflect the current configuration of the plant.Licensees may revise the technical specifications to adopt improved standard technicalspecification format and content provided that plant-specific review supports a finding of continued adequate safety because: (1) the change is editorial, administrative or provides clarification (i.e., no requirements are materially altered), (2) the change is more restrictive than the licensee's current requirement, or (3) the change is less restrictive than the licensee's current requirement, but nonetheless still affords adequate assurance of safety when judged against current regulatory standards. The detailed application of this general framework, and additional specialized guidance, are discussed in Section 3.0 in the context of specific proposed changes.
| | : 1. INTRODUCTION Pursuant to 10 CFR 50.90, on February 13, 2006, the Nuclear Management Company, the licensee, submitted a License Amendment Request (LAR) to amend the Prairie Island Nuclear Generation Plant (PINGP), Units 1 License. The LAR proposes to revise the PINGP Technical Specifications (TS) to change the wording in TS 3.0 Surveillance Requirement (SR) |
| | Applicability and change format and titles in Chapter 5.0, Administrative Controls. The proposed changes improve the TS usability, conformance with the industry standard, NUREG-1431, Standard Technical Specifications, Westinghouse Plants, Revision 3.0 and accuracy. |
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| ==3.0 TECHNICAL EVALUATION== | | ==2.0 REGULATORY EVALUATION== |
| The Licensee's TS revision proposes to make changes that are editorial, administrative or provide clarification. In order for these changes to be acceptable the staff must determine that the editorial, administrative and clarification changes do not alter the TS requirements. The licensee proposes to revise the following PINGP TS: | | |
| 3.1 TS 3.0, "Surveillance Requirement (SR) Applicability" The current page header for TS 3.0, "Surveillance Requirement (SR) Applicability" is "LCO[Limiting Condition for Operation] Applicability." This header is not consistent with the contents of this TS section and is not consistent with the format guidance of NUREG-1431. The LAR proposes to replace the current page header with "SR Applicability." In the last paragraph of Section 3.0.4, "MODES," which is a TS defined term, is incorrectlyspelled with a lower case "s." This is not consistent with the format guidance of NUREG-1431 which capitalizes defined terms. These changes are acceptable since they are administrative and conform with the guidance of NUREG-1431.3.2 TS 5.0, "Administrative Controls" Sections 5.5 and 5.6The LAR proposes to delete the underline under "(continued)" on page 5.0-10. Furthermore, inTS 5.6.5, "P" is deleted from the number for reference 1 which becomes "NSPNAD-8101-A"; | | Section 182a of the Atomic Energy Act (Act) requires applicants for nuclear power plant operating licenses to include technical specifications as part of the license. These technical specifications are derived from the plant safety analyses. |
| "-P-A" is added to number for reference 9 which becomes "WCAP-13677-P-A," and an extra space is removed prior to the document number for references 24 and 26. These changes are acceptable because they are administrative and improve the accuracy of the TS.4.0 ConclusionThe licensee's proposed changes in this LAR are editorial in nature, reflect the currentconfiguration of the plant and do not change the TS requirements. The staff finds the proposed changes are technically justified, comply with 10 CFR 50.36 and are consistent with the standard technical specifications. On this basis, the NRC staff concludes that the proposedchanges to the TS of the Perry Nuclear Power Plant are acceptable.The Commission has concluded, on the basis of considerations discussed above, that: (1)there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner; (2) such activities will be conducted in compliance with the Commission's regulations; and, (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.}}
| | The staff reviewed the proposed changes for compliance with 10 CFR 50.36 and agreement with the precedent as established in NUREG-1431. In general, licensees cannot justify technical specification changes solely on the basis of adopting the model STS. To ensure this, the staff makes a determination that proposed changes maintain adequate safety. Changes that result in relaxation (less restrictive condition) of current TS requirements require detailed justification. |
| | In general, there are two classes of changes to technical specifications: (1) changes needed to reflect contents of the design basis (technical specifications are derived from the design basis), |
| | and (2) voluntary changes to take advantage of the evolution in policy and guidance as to the required content and preferred format of technical specifications over time. This amendment deals with the second class of change; namely, administrative changes that reflect the current configuration of the plant. |
| | Licensees may revise the technical specifications to adopt improved standard technical specification format and content provided that plant-specific review supports a finding of continued adequate safety because: (1) the change is editorial, administrative or provides clarification (i.e., no requirements are materially altered), (2) the change is more restrictive than the licensees current requirement, or (3) the change is less restrictive than the licensees current requirement, but nonetheless still affords adequate assurance of safety when judged against current regulatory standards. The detailed application of this general framework, and additional specialized guidance, are discussed in Section 3.0 in the context of specific proposed changes. |
| | Enclosure |
| | |
| | ==3.0 TECHNICAL EVALUATION== |
| | |
| | The Licensees TS revision proposes to make changes that are editorial, administrative or provide clarification. In order for these changes to be acceptable the staff must determine that the editorial, administrative and clarification changes do not alter the TS requirements. |
| | The licensee proposes to revise the following PINGP TS: |
| | 3.1 TS 3.0, Surveillance Requirement (SR) Applicability The current page header for TS 3.0, Surveillance Requirement (SR) Applicability is LCO |
| | [Limiting Condition for Operation] Applicability. This header is not consistent with the contents of this TS section and is not consistent with the format guidance of NUREG-1431. The LAR proposes to replace the current page header with SR Applicability. |
| | In the last paragraph of Section 3.0.4, MODES, which is a TS defined term, is incorrectly spelled with a lower case s. This is not consistent with the format guidance of NUREG-1431 which capitalizes defined terms. These changes are acceptable since they are administrative and conform with the guidance of NUREG-1431. |
| | 3.2 TS 5.0, Administrative Controls Sections 5.5 and 5.6 The LAR proposes to delete the underline under (continued) on page 5.0-10. Furthermore, in TS 5.6.5, P is deleted from the number for reference 1 which becomes NSPNAD-8101-A; |
| | -P-A is added to number for reference 9 which becomes WCAP-13677-P-A, and an extra space is removed prior to the document number for references 24 and 26. These changes are acceptable because they are administrative and improve the accuracy of the TS. |
| | 4.0 Conclusion The licensees proposed changes in this LAR are editorial in nature, reflect the current configuration of the plant and do not change the TS requirements. The staff finds the proposed changes are technically justified, comply with 10 CFR 50.36 and are consistent with the standard technical specifications. On this basis, the NRC staff concludes that the proposed changes to the TS of the Perry Nuclear Power Plant are acceptable. |
| | The Commission has concluded, on the basis of considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner; (2) such activities will be conducted in compliance with the Commission's regulations; and, (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public. |
| | }} |
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Category:Memoranda
MONTHYEARML23184A0862023-07-11011 July 2023
6/23/2023 Summary of Pre Application Public Meeting with Xcel Energy on Prairie Island ISFSI Amendment Application
ML23044A3662023-02-15015 February 2023
Calendar Year 2022 Reactor Oversight Process Baseline Inspection Program Completion - Region III
ML21055A5972021-03-25025 March 2021
Final Environmental Assessment and Finding of No Significant Impact for the Northern States Power Company'S Initial and Updated Decommissioning Funding Plans Submitted in Accordance with 10 CFR 72.30(B) and (C)
ML20022A1982020-01-17017 January 2020
Summary of the Public Open House to Discuss NRC Activities and the 2018 End-of-Cycle Performance Assessment
ML19136A0272019-05-15015 May 2019
Memorandum to C. Regan Summary of March 28, 2019, Public Meeting with Xcel Energy to Discuss Seismic Consideration for a Proposed License Amendment Increasing the Amount of Special Nuclear Material Authorized for Storage at Prairie Island I
ML19071A0372019-03-0707 March 2019
Summary of Meeting with Xcel Energy to Discuss Increasing the Amount of Special Nuclear Material Authorized for Storage at the Prairie Island ISFSI (W/Enclosures 1 and 2)
ML15181A0202015-07-0101 July 2015
July 9, 2015 Forthcoming Closed Meeting to Discuss Dam Failure Analysis for Monticello Nuclear Generating Plant and Prairie Island Nuclear Generating Plant, Units 1 and 2
ML15107A4932015-04-23023 April 2015
Memo C K Bladey, Notice of Issuance of Exemption, Northern States Power Company, Prairie Island Nuclear Generating Plant Independent Spent Fuel Storage Installation (50-282, 50-306, 72-10)
ML14220A2832014-09-0808 September 2014
Summary of August 5, 2014, Closed Meeting Between Representatives of the U.S. Army Corps of Engineers, NRC, and Northern States Power Company - Minnesota to Discuss Flooding Analysis Associated with Monticello and Prairie Island Nuclear Gen
ML14205A5242014-07-24024 July 2014
August5, 2014 Notice of Forthcoming Closed Meeting to Discuss Dam Failure Analysis for Monticello Nuclear Generating Plant and Prairie Island Nuclear Generating Plant, Units 1 and 2
ML14027A2312014-02-0505 February 2014
Notice of Pre-Application Meeting with Xcel Energy Concerning Prairie Island Nuclear Generating Plant, Units 1 and 2, to Discuss Licensee'S Proposed Changes to the Emergency Diesel Generator Voltage and Frequency Limits
ML13169A2442013-06-17017 June 2013
Memorandum S. Wastler Technical Assistant Request - Review the Prairie Island Nuclear Generating Plant Independent Spent Fuel Storage Installation Request for Exemption from Physical Security Requirements (TAC L24750)
ML13154A4702013-06-0404 June 2013
Rai'S Following Ifib Analysis 2013 Decommissioning Funding Status Report for Prairie Island 1 and 2 and Monticello
ML13101A0292013-04-12012 April 2013
K. Hsueh Memo Site Visit Summary Regarding the Prairie Island ISFSI License Renewal
ML12363A1722012-12-14014 December 2012
CFR 50 Appendix E Evacuation Time Estimate Study
ML12326A9702012-11-21021 November 2012
Summary of October 24, 2012, Meeting with the Northern States Power Company, D/B/A Excel Energy Regarding Security Requirements and Changes Pertaining to Prairie Island TAC L24689 W/ Encl 1 (Attendees) and Encl 2 (Agenda)
ML12318A0572012-11-13013 November 2012
12/6/2012 - Rescheduled Notice of Meeting with Xcel Energy Concerning Prairie Island Nuclear Generating Plant, Units 1 and 2
ML12306A3222012-11-0101 November 2012
Notice of Forthcoming Meeting with Xcel Energy Concerning Prairie Island Nuclear Generating Plant, Units 1 and 2
ML12291A7792012-10-17017 October 2012
S. Wastler Memorandum Technical Assistance Request - Review of Physical Security Plan of Prairie Island Nuclear Generating Plant Independent Spent Fuel Storage Installation (TAC No. L24689)
ML12249A2702012-09-11011 September 2012
Notice of Forthcoming Pre-Application Meeting with Xcel Energy, Inc. Concerning Prairie Island Nuclear Generating Plant
ML12223A4772012-08-0606 August 2012
10/4/2012 Notice of Significant NRC Meeting with Northern States Power Company to Discuss Prairie Island Nuclear Generating Plant, Unit 2
ML1121505252011-08-0404 August 2011
Notice of Forthcoming Pre-Application Meeting with Licensee for Prairie Island Nuclear Generating Plant, Units 1 and 2 to Discuss Extended Power Uprate License Amendment Request
ML1113703982011-05-20020 May 2011
Notice of Forthcoming Pre-Application Meeting with Licensee for Prairie Island Nuclear Generation Plant, Units 1 and 2, to Discuss Proposed Technical Specification and Licensing Basis Changes to Diesel Fuel Oil System
ML1104702792011-02-16016 February 2011
Notice of Forthcoming Meeting with Licensee for Prairie Island Nuclear Generating Plant, Unit 1 to Discuss License Amendment Request to Revise Surveillance Requirement Footnote in Technical Specification 3.8.1, AC Sources - Operating.
ML1100502702011-01-0505 January 2011
Notice of Closed Pre-Application Meeting NSPM Staff to Discuss Proposed Physical Security Plan Changes That Will Be Submitted for NRC Review and Approval Via License Amendment Request
ML1032603272010-11-24024 November 2010
Notice of Pre-Application Meeting with Licensee for Prairie Island Nuclear Generating Plant, Units 1 and 2 to Discuss Spent Fuel Pool Criticality and Extended Power Uprate
ML1011601402010-04-22022 April 2010
Summary of Meeting with Northern States Power Company - Minnesota Corporation, Formerly Nuclear Management Company and Transnuclear Regarding License Amendment Request for the TN-40HT Cask Design
ML0928900052009-10-15015 October 2009
Meeting Meeting Minutes of the the Plant License Renewal Subcommittee Meeting, July 7, 2009
ML0921204292009-09-0202 September 2009
Summary of Meeting with Northern States Power Company to Discuss License Amendment Request Concerning Unit 2 Emergency Diesel Generator Surveillance Test Loads
ML0921005482009-08-0606 August 2009
Notice of Meeting with Licensee for Prairie Island Nuclear Generating Plant, Units 1 and 2 (PINGP) to Discuss Their Proposed Alternate Source Term License Amendment
ML0918708182009-07-0808 July 2009
Meeting Notice, Meeting with Licensee for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Ping) to Discuss License Amendment Request Submitted on 11/04/2008
ML0914608092009-07-0101 July 2009
Issuance of Amendments Technical Specifications Changes to Allow Use of Westinghouse 0.422-Inch OD 14X14 Vantage + Fuel
ML0910701602009-04-27027 April 2009
Draft Clarifications Concerning a Request for Additional Information Regarding Loss-of-Coolant/Mainstream Line Break Accident Dose Consequence Analyses License Amendment Request (Tac Nos. MD9141)
ML0904400352009-02-24024 February 2009
Draft Request for Additional Information Regarding the Irradiated Fuel Management Plan and Preliminary Decommissioning Cost Estimates
ML0900608522009-02-0404 February 2009
12/03/08 Summary of Telephone Conference Call Held Between . NRC & Northern States Power, Concerning Follow-Up Question Pertaining to the Pings, Units 1& 2, License Renewal Environmental Review and Site Audit
ML0836600692009-01-23023 January 2009
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ML0832203772008-09-22022 September 2008
Scoping Comments from Kristen Eide-Tollefson
ML0826102742008-09-15015 September 2008
Draft Pages of Amendment to Facility Operating Licenses DPR-42, DPR-060, & Materials License SNM-2506
ML0812007742008-05-0808 May 2008
Review of Revision 29 to the Updated Safety Analysis Report (Tac No. MD5651 and MD5652)
ML0807400842008-03-14014 March 2008
Draft Regulatory Guide for Comment
ML0720000662007-08-0101 August 2007
Notice of Meeting with Nuclear Management Company, Llc., to Discuss Proposed Changes to PINGP Security Plan
ML0710701822007-05-0202 May 2007
Memo Transmitting Prairie Island Nuclear Generating Plant: Report on Results of Staff Audit of Corrective Actions to Address Generic Letter 2004-02
ML0634003252006-12-0707 December 2006
Notice of Presubmittal Conference for Proposed Emergency Plan Changes
ML0629901712006-11-0303 November 2006
Safety Evaluation for Administrative Changes to the Technical Specifications
ML0629000372006-10-20020 October 2006
Summary of 09/21/2006 Teleconference Re Extension of Relief Requests 2 & 3 for the Fourth 10-Year Inservice Testing Program Interval
ML0624904012006-09-0808 September 2006
Notice of Meeting with Nuclear Management Company, LLC Regarding Extension of Completion Time for Emergency Diesel Generators for Prairie Island Units 1 and 2
ML0617805592006-07-10010 July 2006
Revised Closeout Letter for Bulletin 2003-01, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors.
ML0602502942006-01-25025 January 2006
Canceled Notice of Meeting with Nuclear Management Company Regarding Fleet Transition to NFPA Standard 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants
ML0601101052006-01-12012 January 2006
Meeting Notice - Prairie Island, Units 1 and 2 - Forthcoming Meeting with Nuclear Management Company, LLC (NMC) to Discuss Extension of Completion Time for Emergency Diesel Generators
ML0421003322004-06-30030 June 2004
Close-out of Tacs Relating to the Review of 35-day Letters Submitted in Response to the April 29, 2003, Orders Revising the Design Basis and Security Guard Force Training Enhancements and Physical Fitness Requirements
2023-07-11
[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
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November 3, 2006 MEMORANDUM TO: L. Raghavan, Chief Pant Licensing Branch E Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: Timothy J. Kobetz, Chief /RA/
Technical Specifications Branch Division of Inspection and Regional Support Office of Nuclear Reactor Regulation
SUBJECT:
PRAIRIE ISLAND NUCLEAR GENERATING PLANT (PINGP) UNITS 1 AND 2 SAFETY EVALUATION FOR ADMINISTRATIVE CHANGES TO THE TECHNICAL SPECIFICATIONS By the letter dated February 13, 2006, the Nuclear Management Company, LLC (NMC),
the licensee, submitted a License Amendment Request to revise the technical specifications (TS) of the Prairie Island Nuclear Generating Plant, Units 1 and 2. The licensee is requesting to revise the page header and capitalizations in TS 3.0, Surveillance Requirement (SR)
Applicability; and revise format and titles in TS 5.0, Administrative Controls. The attached Safety Evaluation (SE) addresses the proposed administrative TS changes. Our SE concludes the licensees administrative TS revisions are acceptable.
Enclosure:
As stated CONTACT: Pete Hearn, NRR/ITSB 301-415-1189 pch@nrc.gov
ML062990171 DOCUMENT NAME: G:\ITSB\Hearn\Paire Island ADMIN Changes.wpd OFFICE TSS:IROB:DIPM SC:TSS:IROB:DIPM NAME PHearn TKobetz DATE 10/31/2006 11/3/2006 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENTS TO FACILITY OPERATING LICENSE PRAIRIE ISLAND NUCLEAR POWER PLANTS, UNITS 1 AND 2 DOCKET N0S. 50-282 AND 50-306
- 1. INTRODUCTION Pursuant to 10 CFR 50.90, on February 13, 2006, the Nuclear Management Company, the licensee, submitted a License Amendment Request (LAR) to amend the Prairie Island Nuclear Generation Plant (PINGP), Units 1 License. The LAR proposes to revise the PINGP Technical Specifications (TS) to change the wording in TS 3.0 Surveillance Requirement (SR)
Applicability and change format and titles in Chapter 5.0, Administrative Controls. The proposed changes improve the TS usability, conformance with the industry standard, NUREG-1431, Standard Technical Specifications, Westinghouse Plants, Revision 3.0 and accuracy.
2.0 REGULATORY EVALUATION
Section 182a of the Atomic Energy Act (Act) requires applicants for nuclear power plant operating licenses to include technical specifications as part of the license. These technical specifications are derived from the plant safety analyses.
The staff reviewed the proposed changes for compliance with 10 CFR 50.36 and agreement with the precedent as established in NUREG-1431. In general, licensees cannot justify technical specification changes solely on the basis of adopting the model STS. To ensure this, the staff makes a determination that proposed changes maintain adequate safety. Changes that result in relaxation (less restrictive condition) of current TS requirements require detailed justification.
In general, there are two classes of changes to technical specifications: (1) changes needed to reflect contents of the design basis (technical specifications are derived from the design basis),
and (2) voluntary changes to take advantage of the evolution in policy and guidance as to the required content and preferred format of technical specifications over time. This amendment deals with the second class of change; namely, administrative changes that reflect the current configuration of the plant.
Licensees may revise the technical specifications to adopt improved standard technical specification format and content provided that plant-specific review supports a finding of continued adequate safety because: (1) the change is editorial, administrative or provides clarification (i.e., no requirements are materially altered), (2) the change is more restrictive than the licensees current requirement, or (3) the change is less restrictive than the licensees current requirement, but nonetheless still affords adequate assurance of safety when judged against current regulatory standards. The detailed application of this general framework, and additional specialized guidance, are discussed in Section 3.0 in the context of specific proposed changes.
Enclosure
3.0 TECHNICAL EVALUATION
The Licensees TS revision proposes to make changes that are editorial, administrative or provide clarification. In order for these changes to be acceptable the staff must determine that the editorial, administrative and clarification changes do not alter the TS requirements.
The licensee proposes to revise the following PINGP TS:
3.1 TS 3.0, Surveillance Requirement (SR) Applicability The current page header for TS 3.0, Surveillance Requirement (SR) Applicability is LCO
[Limiting Condition for Operation] Applicability. This header is not consistent with the contents of this TS section and is not consistent with the format guidance of NUREG-1431. The LAR proposes to replace the current page header with SR Applicability.
In the last paragraph of Section 3.0.4, MODES, which is a TS defined term, is incorrectly spelled with a lower case s. This is not consistent with the format guidance of NUREG-1431 which capitalizes defined terms. These changes are acceptable since they are administrative and conform with the guidance of NUREG-1431.
3.2 TS 5.0, Administrative Controls Sections 5.5 and 5.6 The LAR proposes to delete the underline under (continued) on page 5.0-10. Furthermore, in TS 5.6.5, P is deleted from the number for reference 1 which becomes NSPNAD-8101-A;
-P-A is added to number for reference 9 which becomes WCAP-13677-P-A, and an extra space is removed prior to the document number for references 24 and 26. These changes are acceptable because they are administrative and improve the accuracy of the TS.
4.0 Conclusion The licensees proposed changes in this LAR are editorial in nature, reflect the current configuration of the plant and do not change the TS requirements. The staff finds the proposed changes are technically justified, comply with 10 CFR 50.36 and are consistent with the standard technical specifications. On this basis, the NRC staff concludes that the proposed changes to the TS of the Perry Nuclear Power Plant are acceptable.
The Commission has concluded, on the basis of considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner; (2) such activities will be conducted in compliance with the Commission's regulations; and, (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.
