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MONTHYEARML0315604532003-06-17017 June 2003 Safety Evaluation Regarding Unit Staff Qualification Requirements for Prairie Island Nuclear Generating Plant Project stage: Approval ML0319101362003-07-22022 July 2003 License Amendment, Regarding Staff Qualification Requirements (TAC Nos. MB8059 & MB8060) Project stage: Other ML0320900472003-07-22022 July 2003 Tech Spec Page for Amendments 159 & 150, Regarding Staff Qualification Requirements (TAC Nos. MB8059 & MB8060) Project stage: Other 2003-06-17
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Category:Memoranda
MONTHYEARML24043A0952024-02-21021 February 2024 Summary of January 31, 2024, Public Meeting with Xcel Energy to Discuss Amendment Application for Prairie Island Independent Spent Fuel Storage Installation ML23184A0862023-07-11011 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 Summary of Telephone Conference Call Held on December 9, 2008, Between the U. S. Nuclear Regulatory Commission and Northern States, Power, Concerning Follow Up Questions Pertaining to the SAMA RAI for Pings, Units 1 and 2, (TAC MD8528 & MD8 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 2024-02-21
[Table view] Category:Safety Evaluation
MONTHYEARML24221A3622024-09-27027 September 2024 Issuance of Amendment Nos. 245 and 233 Revise Technical Specification 3.8.1, AC Sources-Operating, Surveillance Requirement 3.8.1.2, Note 3 ML24071A1162024-05-0101 May 2024 Issuance of Amendment Nos. 244 and 232 Revise TS 3.7.8, Cooling Water (Cl) System ML24100A8042024-04-24024 April 2024 – Alternative Request RR-09 for Safety Injection and Volume Control System Category C Check Valve Inservice Testing ML24060A1232024-03-27027 March 2024 to Request 1-RR-5-10 and 2-RR-5-10 Regarding Reactor Pressure Vessel Welds and Nozzle Welds ML23356A0032024-01-17017 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 ML20134H9582020-05-29029 May 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 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 2024-09-27
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Text
June 17, 2003 MEMORANDUM TO: Lakshminaras Raghaven, Section Chief Project Directorate III-1 Division of Licensing and Project Management, NRR
/RA/
FROM: David C. Trimble, Section Chief Operator Licensing and Human Performance Section Equipment and Human Performance Branch (IEHB)
Division of Inspection Program Management, NRR
SUBJECT:
SAFETY EVALUATION REGARDING UNIT STAFF QUALIFICATION REQUIREMENTS FOR PRAIRIE ISLAND NUCLEAR GENERATING PLANT (MB8059 AND MD8060)
Plant Name: Prairie Island Nuclear Generating Plant Utility: Nuclear Management Company, LLC Docket Nos. 50-282, 50-306 TAC No.: MB8059, MB8060 Operating License: DPR-42, DPR-60 Project Manager: J. Lamb Review Branch: IEHB Review Status: Complete In a work request dated March 24, 2003, the Equipment and Human Performance Branch (IEHB) was asked to review the Nuclear Management Company, LLC (NMC) request to revise the Prairie Island Nuclear Generating Plant, Unit 1 and 2 requirements regarding Unit Staff Qualifications for the licensed operator training program. The change revises requirements that have been superseded based on licensed operator training programs being accredited by the Institute of Nuclear Power Operations and promulgation of the revised 10 CFR Part 55, Operators Licenses, which became effective on May 26, 1987.
The IEHB staff concludes that NMCs request is consistent with and meets the relevant review criteria and is acceptable. The staff's safety evaluation is attached.
The principal reviewer for this assessment was Richard Pelton. If you have any questions he can be reached at 415-1028. IEHB considers its efforts on TAC Nos. MB8059 and MB8060 to be complete.
Attachment:
As stated
June 17, 2003 MEMORANDUM TO: Lakshminaras Raghaven, Section Chief Project Directorate III-1 Division of Licensing and Project Management, NRR
/RA/
FROM: David C. Trimble, Section Chief Operator Licensing and Human Performance Section Equipment and Human Performance Branch (IEHB)
Division of Inspection Program Management, NRR
SUBJECT:
SAFETY EVALUATION REGARDING UNIT STAFF QUALIFICATION REQUIREMENTS FOR PRAIRIE ISLAND NUCLEAR GENERATING PLANT (MB8059 AND MD8060)
Plant Name: Prairie Island Nuclear Generating Plant Utility: Nuclear Management Company, LLC Docket Nos. 50-282, 50-306 TAC No.: MB8059, MB8060 Operating License: DPR-42, DPR-60 Project Manager: J. Lamb Review Branch: IEHB Review Status: Complete In a work request dated March 24, 2003, the Equipment and Human Performance Branch (IEHB) was asked to review the Nuclear Management Company, LLC (NMC) request to revise the Prairie Island Nuclear Generating Plant, Unit 1 and 2 requirements regarding Unit Staff Qualifications for the licensed operator training program. The change revises requirements that have been superseded based on licensed operator training programs being accredited by the Institute of Nuclear Power Operations and promulgation of the revised 10 CFR Part 55, Operators Licenses, which became effective on May 26, 1987.
The IEHB staff concludes that NM3Cs request is consistent with and meets the relevant review criteria and is acceptable. The staff's safety evaluation is attached.
The principal reviewer for this assessment was Richard Pelton. If you have any questions he can be reached at 415-1028. IEHB considers its efforts on TAC No. MB8059 and MB8060 to be complete.
Attachment:
As stated DISTRIBUTION:
Licensing Action/Admin Changes folder Generic Operator Licensing/License Eligibility John Lamb ACCESSION #: ML031560453 OFFICE IOHS/DIPM N IOHS/DIPM NAME R. Pelton D. Trimble DATE 06/10 /03 06/17/03 OFFICIAL RECORD COPY
SAFETY EVALUATION REGARDING UNIT STAFF QUALIFICATION REQUIREMENTS FOR PRAIRIE ISLAND NUCLEAR GENERATING PLANT DOCKET NOS. 50-282 and 50-306
- 1. INTRODUCTION By letter dated March 19, 2003, Nuclear Management Company, LLC (NMC) submitted a technical specification change request for Prairie Island Nuclear Generating Plant (Prairie Island) to the NRC for approval.
- 2. REGULATORY EVALUATION On March 20, 1985, the NRC issued the Commission Policy Statement on Training and Qualification of Nuclear Power Plant Personnel which endorsed the National Academy for Nuclear Training (NANT) and the training accreditation process. In Generic Letter 87-07, "Information Transmittal of Final Rulemaking for Revisions to Operator Licensing - 10 CFR 55 and Conforming Amendments," dated March 19,1987, and in NUREG-1262, "Answers to Questions at Public Meetings Regarding Implementation of Title 10, Code of Federal Regulations, Part 55 on Operators Licenses," published November 1987, the NRC indicated it would accept a facilitys licensed operator training program if the facility certified in writing that the program was accredited and based on a systems approach to training (SAT). This certification would supersede the requirements of ANSI N18.1-1971, "Selection and Training of Nuclear Power Plant Personnel," and ANSI/ANS-3.1-1978, "Selection, Qualification and Training of Personnel for Nuclear Power Plants." Facility licensees were advised to submit a request to the NRC for an administrative change to their licensing documents to revise or delete, as appropriate, the requirements that had been superseded.
In 1992 the NRC published its proposed rule 10 CFR 50.120, "Training and Qualification of Nuclear Power Plant Personnel." The proposed rule stated that, if adopted, the rule would supersede the Policy Statement on Training and Qualification of Nuclear Power Plant Personnel and would not result in any change to accredited programs. The Commission concluded that accredited programs, implemented consistent with industry objectives and criteria would be in compliance with this regulation. In April 1993, the NRC published its final rule on training and qualification of nuclear power plant personnel. The rule requires nuclear power plant licensees to establish, implement, and maintain SAT-based training programs for nine non-licensed positions. Accreditation of these nine training programs is an acceptable means of meeting the requirements of 10 CFR 50.120.
On January 18, 2001, the NRC published NRC Regulatory Issue Summary (RIS) 2001-01, Eligibility of Operator License Applicants," to familiarize licensees with the NRC's current guidelines for the qualification and training of reactor operator and senior operator license applicants. RIS 2001-01 acknowledged that 10 CFR 55.31(a)(4) allows the NRC to accept an application for an operators license if the facility licensee certifies that the applicant has successfully completed a Commission-approved training program that is based on a systems approach to training. In addition, RIS 2001-01 stated that: (1) a training program would be considered approved by the NRC when it receives or renews accreditation from the National Nuclear Accrediting Board (NNAB); (2) accreditation of operator training programs suggests Attachment
that facilities are implementing the education and experience guidelines endorsed by the NNAB; (3) NANT guidelines for education and experience (those in effect in 1987 or those issued in January 2000) outline acceptable methods for implementing the Commissions regulations; and (4) the staff encourages all facility licensees to review their requirements and commitments related to licensed operator and senior operator education and experience and to update their documentation (e.g., Final Safety Analysis Report, Technical Specifications, and training program descriptions) to enhance consistency and minimize confusion."
- 3. TECHNICAL EVALUATION The revision proposed by NMC will revise Prairie Island Unit 1 and 2 Technical Specification (TS) Section 5.3, Plant Staff Qualifications. The requested revision will update requirements that have been outdated based on licensed operator training programs being accredited by the National Academy for Nuclear Training and promulgation of the revised 10 CFR 55, Operators Licenses. TS Section 5.3 describes the requirements for plant staff qualifications. These changes conform to the current requirements of 10 CFR 55. The TS requirements for all other plant staff qualifications remain unchanged.
The NRC staff concludes that the revised qualification requirements in TS Section 5.3 are adequate as they conform with the reactor operator and senior reactor operator license eligibility criteria and standards acceptable to the NRC. In addition, the changes will not affect the 10 CFR 50.36(c)(5) requirement to ensure the licensee maintains administrative controls that assure the operation of the facility in a safe manner.
- 4. CONCLUSION Based on the above discussion, the proposed revision to Prairie Island Unit 1 and 2 TS Section 5.3, Plant Staff Qualifications is consistent with 10 CFR Part 55 and does not adversely affect nuclear safety or plant operations.
The Commission has concluded, based on the 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 Commissions 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.