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Category:Letter
MONTHYEARML24283A1192024-10-28028 October 2024 Letter to Shawn Hafen, Re Monticello Subsequent License Renewal Schedule Change L-MT-24-038, Subsequent License Renewal Application Response to Request for Additional Information - 3rd Round RAI2024-10-15015 October 2024 Subsequent License Renewal Application Response to Request for Additional Information - 3rd Round RAI ML24277A0202024-10-0303 October 2024 Operator Licensing Examination Approval Monticello Nuclear Generating Plant, October 2024 ML24199A1752024-10-0101 October 2024 Issuance of Amendment No. 212 Revise Technical Specification 3.8.6, Battery Parameters, Surveillance Requirement 3.8.6.6 IR 05000263/20240112024-10-0101 October 2024 Biennial Problem Identification and Resolution Inspection Report 05000263/2024011 L-MT-24-025, Application to Revise Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements2024-09-26026 September 2024 Application to Revise Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements L-MT-24-029, Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information-Supplement to Set 1 Part 2 and Response to 2ci Round RAI2024-09-13013 September 2024 Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information-Supplement to Set 1 Part 2 and Response to 2ci Round RAI IR 05000263/20240052024-08-30030 August 2024 Updated Inspection Plan and Follow-Up Letter for Monticello Nuclear Generating Plant, Unit 1 (Report 05000263/2024005) L-MT-24-028, Response to RCI for RR-017 ISI Impracticality2024-08-28028 August 2024 Response to RCI for RR-017 ISI Impracticality ML24222A1822024-08-27027 August 2024 – Proposed Alternative Request VR-09 to the Inservice Testing Requirements of the ASME OM Code for Main Steam Safety Relief Valves 05000263/LER-2024-002, Low Pressure Coolant Injection Inoperable Due to Motor Valve Failure2024-08-27027 August 2024 Low Pressure Coolant Injection Inoperable Due to Motor Valve Failure IR 05000263/20244202024-08-21021 August 2024 Security Baseline Inspection Report 05000263/2024420 - Cover Letter IR 05000263/20240022024-08-14014 August 2024 Integrated Inspection Report 05000263/2024002 ML24218A2282024-08-0505 August 2024 Request for Confirmation of Information for Relief Request RR-017, Inservice Inspection Impracticality During the Fifth Ten-Year Interval ML24208A1502024-07-26026 July 2024 Independent Spent Fuel Storage Installation - Submittal of Quality Assurance Topical Report (NSPM-1) ML24215A2992024-07-23023 July 2024 Minnesota State Historic Preservation Office Comments on Monticello SLR Draft EIS ML24198A2372024-07-18018 July 2024 Information Request to Support Upcoming Biennial Problem Identification and Resolution (Pi&R) Inspection at Monticello Nuclear Generating Plant L-MT-24-022, – Preparation and Scheduling of Operator Licensing Examinations2024-07-0909 July 2024 – Preparation and Scheduling of Operator Licensing Examinations ML24164A2402024-06-10010 June 2024 Minnesota State Historic Preservation Office- Comments on Draft Monticello SLR Draft EIS L-MT-24-019, Submittal of ASME Section XI, Section IWB-3720 Analytical Evaluation in Accordance with 10 CFR 50.55a(b)(2)(xliii)2024-06-10010 June 2024 Submittal of ASME Section XI, Section IWB-3720 Analytical Evaluation in Accordance with 10 CFR 50.55a(b)(2)(xliii) L-MT-24-017, Response to Request for Additional Information Regarding License Amendment Request to Revise Monticello Technical Specification Surveillance Requirement 3.8.6.6 (EPID-L-2023-LLA-01602024-06-0404 June 2024 Response to Request for Additional Information Regarding License Amendment Request to Revise Monticello Technical Specification Surveillance Requirement 3.8.6.6 (EPID-L-2023-LLA-0160 ML24137A2792024-06-0303 June 2024 Audit Summary for License Amendment Request to Revise Technical Specification 3.8.6, Battery Parameters, Surveillance Requirement 3.8.6.6 ML24141A1292024-05-22022 May 2024 Northern States Power Company - Use of Encryption Software for Electronic Transmission of Safeguards Information ML24141A1782024-05-20020 May 2024 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection L-MT-24-015, Response to Request for Additional Information - Alternative Request VR-09 for OMN-172024-05-16016 May 2024 Response to Request for Additional Information - Alternative Request VR-09 for OMN-17 L-MT-24-013, 2023 Annual Radiological Environmental Operating Report2024-05-14014 May 2024 2023 Annual Radiological Environmental Operating Report ML24135A1902024-05-14014 May 2024 Submittal of 2023 Annual Radioactive Effluent Release Report IR 05000263/20240102024-05-13013 May 2024 Age-Related Degrading Inspection Report 05000263/2024010 ML24128A0042024-05-0909 May 2024 Letter to Minnesota State Historic Preservation Office- Section 106 Consultation Regarding the Monticello Nuclear Generating Plant Subsequent License Renewal Application ML24127A1472024-05-0909 May 2024 Letter to Mille Lacs Band- Section 106 Consultation Regarding the Monticello Nuclear Generating Plant Subsequent License Renew. Application L-MT-24-016, 2023 Annual Report of Individual Monitoring for the Monticello Nuclear Generating Plant (MNGP)2024-05-0808 May 2024 2023 Annual Report of Individual Monitoring for the Monticello Nuclear Generating Plant (MNGP) ML24089A2382024-04-29029 April 2024 Summary of Nuclear Property Insurance IR 05000263/20240012024-04-29029 April 2024 Plan - Integrated Inspection Report 05000263/2024001 ML24115A2902024-04-25025 April 2024 Sec106 Tribal, Jackson-Street, Lonna-Spirit Lake Nation ML24115A2872024-04-25025 April 2024 Sec106 Tribal, Dupuis, Kevin-Fond Du Lac Band of Lake Superior Chippewa ML24115A2932024-04-25025 April 2024 Sec106 Tribal, Johnson, Grant-Prairie Island Indian Community ML24115A3062024-04-25025 April 2024 Sec106 Tribal, Wassana, Reggie-Cheyenne and Arapaho Tribes 05000263/LER-2024-001, Reactor Scram, Containment Isolation, and Cooldown Rate Outside of Limits Following Technician Adjustment of Wrong Component2024-04-25025 April 2024 Reactor Scram, Containment Isolation, and Cooldown Rate Outside of Limits Following Technician Adjustment of Wrong Component ML24115A3032024-04-25025 April 2024 Sec106 Tribal, Taylor, Louis-Lac Courte Oreilles Band of Lake Superior Chippewa Indians ML24115A3002024-04-25025 April 2024 Sec106 Tribal, Rhodd, Timothy-Iowa Tribe of Kansas and Nebraska ML24115A2972024-04-25025 April 2024 Sec106 Tribal, Miller, Cole-Shakopee Mdewakanton Sioux Community ML24115A2962024-04-25025 April 2024 Sec106 Tribal, Larsen, Robert-Lower Sioux Indian Community ML24115A2952024-04-25025 April 2024 Sec106 Tribal, Kakkak, Gena-Menominee Indian Tribe of Wisconsin ML24115A2982024-04-25025 April 2024 Sec106 Tribal, Reider, Anthony-Flandreau Santee Sioux Tribe ML24115A2912024-04-25025 April 2024 Sec106 Tribal, Jacskon, Sr., Faron-Leech Lake Band of Ojibwe ML24115A3052024-04-25025 April 2024 Sec106 Tribal, Vanzile, Jr., Robert-Sokaogon Chippewa Community ML24115A2992024-04-25025 April 2024 Sec106 Tribal, Renville, J. Garret-Sisseton Wahpeton Oyate of the Lake Travers Reservation ML24115A3022024-04-25025 April 2024 Sec106 Tribal, Stiffarm, Jeffrey-Fort Belknap Indian Community ML24115A3072024-04-25025 April 2024 Sec106 Tribal, Williams, Jr., James-Lac Vieux Desert Band of Lake Superior Chippewa Indians ML24115A2892024-04-25025 April 2024 Sec106 Tribal, Fowler, Thomas-St. Croix Chippewa of Wisconsin 2024-09-26
[Table view] Category:Safety Evaluation
MONTHYEARML24199A1752024-10-0101 October 2024 Issuance of Amendment No. 212 Revise Technical Specification 3.8.6, Battery Parameters, Surveillance Requirement 3.8.6.6 ML24222A1822024-08-27027 August 2024 – Proposed Alternative Request VR-09 to the Inservice Testing Requirements of the ASME OM Code for Main Steam Safety Relief Valves ML24138A1212024-07-0202 July 2024 Alternative Request RR-002 ML24077A0012024-03-18018 March 2024 Safety Evaluation to the SLRA of Monticello Nuclear Generating Plant, Unit 1 ML23248A2092023-09-18018 September 2023 – Proposed Alternative VR-11 to the Requirements of the ASME OM Code Associated with Periodic Verification Testing of MO-2397, Reactor Water Cleanup Inboard Isolation Valve ML23107A2852023-04-25025 April 2023 Authorization and Safety Evaluation for Alternative Request PR-08 ML23079A0742023-04-11011 April 2023 Request RR-003 to Use Later Edition of ASME Section XI Code for ISI Code of Record 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 ML23012A1562023-01-13013 January 2023 Issuance of Amendment No. 210 Re Revised Methodologies for Determining the Core Operating Limits (EPID L-2021-LLA-0144) - Non-proprietary ML22318A2152022-12-27027 December 2022 Issuance of Amendment No. 209 Ten-Year Inspection of the Diesel Generator Fuel Oil Storage Tank ML22264A1062022-10-31031 October 2022 Issuance of Amendment No. 208 Residual Heat Removal Drywell Spray Header and Nozzle Surveillance Frequency ML22270A2312022-09-30030 September 2022 Authorization and Safety Evaluation for Alternative Request No. VR-10 ML22154A5502022-06-0707 June 2022 Authorization and Safety Evaluation for Alternative Request No. PR-02 ML22126A1342022-05-12012 May 2022 Authorization and Safety Evaluation for Alternative Request No. PR-05 ML22098A1272022-05-0202 May 2022 Authorization and Safety Evaluation for Alternative Request No. VR-02 ML22018A1772022-01-21021 January 2022 Authorization and Safety Evaluation for Alternative Request No. VR-05 ML21223A2802021-10-15015 October 2021 Issuance of Amendment No. 207 Adoption of TSTF-564 Safety Limit MCPR ML21148A2742021-07-12012 July 2021 Issuance of Amendment No. 206 TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML20352A3492021-01-0808 January 2021 Issuance of Amendment No. 205, Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-582, RPV WIC Enhancements, and TSTF-583-T, TSTF-582 Diesel Generator Variation ML20346A0972020-12-21021 December 2020 Request for Alternative for Examination of Reactor Pressure Vessel Threads in Flange ML20336A1602020-12-0909 December 2020 Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML20307A0172020-11-0202 November 2020 Request for Alternative for Core Support Structure Weld Examination 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 ML20153A8042020-07-31031 July 2020 Co. - Issuance of Amendments Revising Emergency Action RA3 ML20174A5452020-07-15015 July 2020 Request for Alternative for Pressure Isolation Valve Testing 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 ML19255F5822019-10-0101 October 2019 Safety Evaluation Regarding Implementation of Hardened Containment Vents Capable of Operation Under Severe Accident Conditions Related to Order EA-13-109 (CAC No. MF4376; EPID No. L-2014-JLD-0052) ML19162A0932019-07-30030 July 2019 Issuance of Amendment No, 202 Regarding Deletion of the Note Associated with Technical Specification 3.5.1., Erccs - Operating ML19074A2692019-04-22022 April 2019 Non-Proprietary - Issuance of Amendment Revision to Technical Specifications 2.1.2 Safety Limit Minimum Critical Power Ratio ML19052A1422019-03-11011 March 2019 Correction to License Amendment No. 198 Related to Adoption of TSTF-542, Reactor Pressure Vessel Water Inventory Control ML19065A2002019-03-11011 March 2019 Correction to License Amendment No. 200 Related to Adoption of TSTF-425, Relocated Surveillance Frequencies to Licensee Control - RITSTF Initiative 5B ML19007A0902019-01-28028 January 2019 Issuance of Amendment Adoption of TSTF-425, Relocate Surveillance Frequencies to Licensee Control-RITSTF Initiative 5B ML18291B2142018-11-26026 November 2018 Issuance of Amendment Adoption of TSTF-551 Revise Secondary Containment Surveillance Requirements ML18250A0752018-10-29029 October 2018 Issuance of Amendment Adoption of TSTF-542, Reactor Pressure Vessel Water Inventory Control ML18270A0152018-10-19019 October 2018 and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Relief from the Requirements of the ASME OM Code ML17345A0462018-03-0606 March 2018 Issuance of Amendment No. 197 to Adopt Changes to the Emergency Plan (CAC No. MF9560; EPID L-2017-LLA-0184) ML17319A5912017-12-10010 December 2017 Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 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) ML17123A3212017-06-16016 June 2017 Issuance of Amendment Adoption of TSTF-545, Revision 3, TS Inservice Testing Program Removal and Clarify SR Usage Rule Application to Section 5.5 Testing ML17122A1572017-05-15015 May 2017 Request for Alternative to Use Code Case OMN-20 for the Fifth 10-Year Inservice Testing Interval ML17103A2352017-04-25025 April 2017 Issuance of Amendment Technical Specification 5.5.11 Primary Containment Leakage Rate Testing Program ML17013A4352017-02-27027 February 2017 Issuance of Amendment Revision to Technical Specification Surveillance Requirement 3.8.4.2 ML17054C3942017-02-23023 February 2017 Non-Proprietary Issuance of Amendment Extended Flow Window 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 ML16244A1202016-09-0606 September 2016 Generation Plant - Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Phase 2 of Order EA-13-109 (Severe Accident Capable Hardened Vents) ML16208A4622016-08-0303 August 2016 Safety Evaluation for Request for Alternative Associated with Reactor Pressure Vessel Internals and Components Inspection for the Fifth 10-Year Interval ML16196A3032016-08-0101 August 2016 Issuance of Amendment Technical Specifications Surveillance Requirement 3.5.1.3 B to Correct Alternative Nitrogen System Pressure (Cac. No. MF6704) ML16125A1652016-06-21021 June 2016 Issuance of Amendment Technical Specifications Task Force (TSTF) Standard Technical Specifications (STS) Change Traveler TSTF-523, Revision 2 Generic Letter 2008-01, Managing Gas Accumulation 2024-08-27
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Text
January 5, 2006 Mr. John T. Conway Site Vice President Monticello Nuclear Generating Plant Nuclear Management Company, LLC 2807 West County Road 75 Monticello, MN 55362-9637
SUBJECT:
MONTICELLO NUCLEAR GENERATING PLANT, UNIT NO. 1 - REVISION TO EMERGENCY PLAN EMERGENCY ACTION LEVELS (TAC NO. MC5017)
Dear Mr. Conway:
By letter dated October 22, 2004, as supplemented by letters dated December 22, 2004, June 24, November 22, and December 20, 2005, Nuclear Management Company, Inc. (NMC),
requested changes to the Emergency Action Levels (EALs) for Monticello Nuclear Generating Plant (MNGP). The proposed changes revise the MNGP EALs using the guidance provided in Nuclear Energy Institute document NEI 99-01, Revision 4, Methodology for Development of Emergency Action Levels, which was endorsed by the Nuclear Regulatory Commission (NRC) in Regulatory Guide 1.101, Revision 4, Emergency Planning and Preparedness for Nuclear Power Reactors.
The NRC staff has completed its review of the proposed EAL scheme change and supporting documentation, and has concluded that the proposed revision meets the standards set forth in 10 CFR 50.47(b) and the requirements of Appendix E to 10 CFR Part 50, and therefore, is acceptable. Details of the review are delineated in the enclosed safety evaluation.
Sincerely,
/RA/
Peter S. Tam, Senior Project Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-263
Enclosure:
Safety Evaluation cc w/encl: See next page
January 5, 2006 Mr. John T. Conway Site Vice President Monticello Nuclear Generating Plant Nuclear Management Company, LLC 2807 West County Road 75 Monticello, MN 55362-9637
SUBJECT:
MONTICELLO NUCLEAR GENERATING PLANT, UNIT NO. 1 - REVISION TO EMERGENCY PLAN EMERGENCY ACTION LEVELS (TAC NO. MC5017)
Dear Mr. Conway:
By letter dated October 22, 2004, as supplemented by letters dated December 22, 2004, June 24, November 22, and December 20, 2005, Nuclear Management Company, Inc. (NMC),
requested changes to the Emergency Action Levels (EALs) for Monticello Nuclear Generating Plant (MNGP). The proposed changes revise the MNGP EALs using the guidance provided in Nuclear Energy Institute document NEI 99-01, Revision 4, Methodology for Development of Emergency Action Levels, which was endorsed by the Nuclear Regulatory Commission (NRC) in Regulatory Guide 1.101, Revision 4, Emergency Planning and Preparedness for Nuclear Power Reactors.
The NRC staff has completed its review of the proposed EAL scheme change and supporting documentation, and has concluded that the proposed revision meets the standards set forth in 10 CFR 50.47(b) and the requirements of Appendix E to 10 CFR Part 50, and therefore, is acceptable. Details of the review are delineated in the enclosed safety evaluation.
Sincerely,
/RA/
Peter S. Tam, Senior Project Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-263
Enclosure:
Safety Evaluation cc w/encl: See next page DISTRIBUTION:
PUBLIC LPLIII-1 R/F TKobetz KWilliams DBarss PTam THarris BBurgess, RIII OGC ACRS DORL DPR ADAMS Accession Number: ML060040437 *Safety evaluation transmitted by memo of this date.
OFFICE NRR/LPL3-1/PM NRR/LPL3-1/LA NSIR/LRIS/BC* NRR/LPL3-1/BC (A)
NAME PTam THarris EWeiss TKobetz DATE 1/5/06 1/5/06 1/5/06 1/5/06 OFFICIAL RECORD COPY
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO PROPOSED UPGRADED EMERGENCY ACTIONS LEVELS (EALs)
MONTICELLO NUCLEAR GENERATING PLANT (MNGP)
NUCLEAR MANAGEMENT COMPANY, LLC DOCKET NO. 50-263
1.0 INTRODUCTION
By letter dated October 22, 2004, (Agencywide Document Access and Management System (ADAMS) Accession No. ML053420669) and as supplemented by letters dated December 22, 2004 (ADAMS Accession No. ML043650186); June 24, 2005 (ADAMS Accession No. ML051820559); November 22, 2005 (ADAMS Accession No. 053320282); and December 20, 2005 (ADAMS Accession number ML053560091) Nuclear Management Company, Inc. (the licensee, NMC), requested changes to the EALs for the MNGP. The proposed changes revise the MNGP EALs using the guidance provided in Nuclear Energy Institute (NEI) document, NEI 99-01, Revision 4, Methodology for Development of Emergency Action Levels, which was endorsed by the Nuclear Regulatory Commission (NRC) in Regulatory Guide (RG) 1.101, Revision 4, Emergency Planning and Preparedness for Nuclear Power Reactors.
2.0 REGULATORY EVALUATION
The applicable regulations and guidance that the NRC staff used to review the licensees proposed EAL revision are discussed in the following sections.
2.1 Regulations Part 50 of Title 10 of the Code of Federal Regulations, Section 50.47 (10 CFR 50.47),
Emergency plans, states that no operating license for a nuclear power reactor will be issued unless a finding is made by the NRC that the state of onsite and offsite emergency preparedness provides reasonable assurance that adequate protective measures can and will be taken in the event of a radiological emergency. This regulation also establishes requirements that must be met by the onsite and offsite emergency response plans for the NRC staff to make a positive finding that there is reasonable assurance that adequate protective measures can and will be taken in the event of a radiological emergency. Paragraph 50.47(b)(4) of 10 CFR stipulates that emergency plans include a standard emergency classification and action level scheme.
ENCLOSURE
Appendix E,Section IV.B, Emergency Planning and Preparedness for Production and Utilization Facilities, of 10 CFR 50 provides that emergency plans are to include EALs, which are to be used as criteria for determining the need for notification and participation of local and State agencies and which are to be used for determining when and what type of protective measures should be considered, both onsite and offsite, to protect public health and safety.
EALs are to be based on in-plant conditions and instrumentation, and onsite and offsite monitoring.Section IV.B of Appendix E provides that initial EALs shall be discussed and agreed on by the applicant and State and local authorities, be approved by the NRC, and reviewed annually thereafter with State and local authorities. In addition,Section IV.B states that an EAL revision must be approved by the NRC before implementation if: (1) the licensee is changing from one EAL scheme to another EAL scheme (e.g., a change from an EAL scheme based on NUREG-0654 (see below for title) to a scheme based upon NUMARC/NESP-007 (see below for title) or NEI-99-01); (2) the licensee is proposing an alternate method for complying with the regulations; or (3) the EAL revision decreases the effectiveness of the emergency plan.
2.2 Guidance As stated in Section 1.0, for developing EALs required by 10 CFR Part 50, Appendix E, Section IV.B and 10 CFR Paragraph 50.47(b)(4), NRC RG 1.101, Revision 4, endorses the guidance provided in NEI 99-01, Revision 4, as acceptable alternative methods to those described in the following documents:
- Appendix 1 to NUREG-0654/Federal Emergency Management Agency-REP-1, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants (November 1980), and
- Nuclear Utilities Management Council document NESP-007, Methodology for Development of Emergency Action Levels (Revision 2, January 1992).
NRC's Regulatory Issue Summary (RIS) 2003-18, Use of NEI 99-01, Methodology for Development of Emergency Action Levels, dated October 8, 2003, and as supplemented on July 13, 2004, and December 12, 2005, provides guidance for developing or changing a standard emergency classification and action level scheme. In addition, this RIS provided recommendations to assist licensees, consistent with Part 50, Appendix E,Section IV.B, in determining whether to seek prior NRC approval of deviations from the new guidance.
3.0 TECHNICAL EVALUATION
3.1 Scope The licensee's proposed revision updates the existing MNGP EALs, based on NUREG-0654, to implement the NEI 99-01, Revision 4, EALs.
The NRC staffs evaluation of the proposed revisions to initiating conditions (ICs) and EAL threshold values is based on the licensees letters referenced in Section 1 above. ICs, entitled Defueled Station Malfunctions, and listed under Category D in NEI 99-01 (Revision 4), are not applicable since Monticello has a current operating license, and therefore, were not considered during this technical evaluation.
Proposed deviations or differences from the guidance in NEI 99-01 (Revision 4), other than
minor differences, such as station-specific terminology, system and component names, or formatting, were identified in the justification matrix provided in Enclosure 4 to the licensees letter dated November 22, 2005, which provided a specific evaluation for each.
By its letter of December 20, 2005, the licensee provided a complete, revised version of the EAL Bases document, including EAL Matrix, ICs, and associated EAL threshold values. This EAL Bases document reflects the changes made to EAL Matrix, ICs, EAL threshold values, and Bases provided by the licensee's letter dated October 22, 2004, as supplemented by letters dated December 22, 2004, June 24, and November 22, 2005.
3.2 Approval by State and Local Authorities As stated in Section 2.1,Section IV.B of Appendix E to 10 CFR Part 50 states that initial EALs shall be discussed and agreed on by the applicant and State and local authorities, be approved by the NRC, and reviewed annually thereafter with State and local authorities.
In its letter dated October 22, 2004, the licensee stated that the proposed EALs had been discussed and agreed to by the applicable State and local government officials. Enclosure 3 to the licensees letter dated October 22, 2004, contained documentation of these discussions with the following offsite agencies:
- Division of Homeland Security and Emergency Management
- Sherburne County Emergency Management
- Wright County Emergency Management 3.3 List of Commitments The licensees letter dated June 24, 2005, contains no new commitments, and withdraws the commitment made in its letter dated October 22, 2004, to provide the NRC a supplemental submittal for the MNGP security EALs. In its June 24, 2005, letter, the licensee states:
This letter contains no new commitments; it revises the commitment made in Reference 1. NMC will not provide a supplement to reflect updated security EALs for MNGP. Instead, NMC will evaluate revised security EALs at MNGP in accordance with the distribution guidance using 10 CFR 50.54(q) and will provide an additional submittal only if the final guidance requires it.
3.4 Evaluation Based on the review of the information provided in the licensees letters referenced above, the NRC staff finds that the proposed changes to ICs, EAL threshold values, and EAL Bases are consistent with the guidance in NEI 99-01, Revision 4, or provide an acceptable alternative.
Hence, the proposed changes to the MNGP EALs and EAL Bases as reflected in the licensees letter dated December 20, 2005, are acceptable.
Changes to the MNGP security EALs based on the guidance provided in Attachment 1 to NRC Bulletin 2005-02, Emergency Preparedness and Response Actions for Security-Based Events, dated July 18, 2005, were not evaluated as part of this review. As indicated in Section 3.3 above, the licensee intends to implement changes to its security EALs under 10 CFR
50.54(q), which is acceptable under the guidance provided in Bulletin 2005-02.
4.0 CONCLUSION
S The NRC staff has performed a review of the proposed changes to the MNGP EALs and EAL Bases, as submitted by letters referenced above, using the guidance in NEI 99-01, Revision 4. The NRC staff finds that the proposed MNGP EAL revision and EAL Bases, provided in the licensees letter dated December 20, 2005, is consistent with the guidance in NEI 99-01, Revision 4, or provides an acceptable alternative as discussed in Section 3.0 above.
The NRC staff also finds that the proposed MNGP EAL revision meet the requirements of 10 CFR Paragraph 50.47(b) and Appendix E to 10 CFR Part 50, Section IV.B and is, therefore, acceptable.
Principal Contributor: Kevin Williams Date: January 5, 2006
Monticello Nuclear Generating Plant cc:
Jonathan Rogoff, Esquire Commissioner Vice President, Counsel & Secretary Minnesota Department of Commerce Nuclear Management Company, LLC 85 7th Place East, Suite 500 700 First Street St. Paul, MN 55101-2198 Hudson, WI 54016 Manager - Environmental Protection Division U.S. Nuclear Regulatory Commission Minnesota Attorney Generals Office Resident Inspector's Office 445 Minnesota St., Suite 900 2807 W. County Road 75 St. Paul, MN 55101-2127 Monticello, MN 55362 Michael B. Sellman Manager, Regulatory Affairs President and Chief Executive Officer Monticello Nuclear Generating Plant Nuclear Management Company, LLC Nuclear Management Company, LLC 700 First Street 2807 West County Road 75 Hudson, MI 54016 Monticello, MN 55362-9637 Nuclear Asset Manager Robert Nelson, President Xcel Energy, Inc.
Minnesota Environmental Control 414 Nicollet Mall, R.S. 8 Citizens Association (MECCA) Minneapolis, MN 55401 1051 South McKnight Road St. Paul, MN 55119 Commissioner Minnesota Pollution Control Agency 520 Lafayette Road St. Paul, MN 55155-4194 Regional Administrator, Region III U.S. Nuclear Regulatory Commission Suite 210 2443 Warrenville Road Lisle, IL 60532-4351 Commissioner Minnesota Department of Health 717 Delaware Street, S. E.
Minneapolis, MN 55440 Douglas M. Gruber, Auditor/Treasurer Wright County Government Center 10 NW Second Street Buffalo, MN 55313 November 2005