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Category:Letter
MONTHYEARML24025A9362024-01-31031 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0055 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) IR 05000263/20230042024-01-31031 January 2024 Integrated Inspection Report 05000263/2023004 ML24024A0722024-01-24024 January 2024 Independent Spent Fuel Storage Installation, Onticello, Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000263/20244012024-01-22022 January 2024 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000263/2024401 L-MT-23-054, Subsequent License Renewal Application Supplement 82024-01-11011 January 2024 Subsequent License Renewal Application Supplement 8 L-MT-23-047, License Amendment Request: Revision to the MNGP Pressure Temperature Limits Report to Change the Neutron Fluence Methodology and Incorporate New Surveillance Capsule Data2023-12-29029 December 2023 License Amendment Request: Revision to the MNGP Pressure Temperature Limits Report to Change the Neutron Fluence Methodology and Incorporate New Surveillance Capsule Data L-MT-23-056, Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 1 Part 22023-12-18018 December 2023 Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 1 Part 2 ML23349A0572023-12-15015 December 2023 and Independent Spent Fuel Storage Installation, Revision to Correspondence Service List for Northern States Power - Minnesota IR 05000263/20234022023-12-13013 December 2023 Security Baseline Inspection Report 05000263/2023402 L-MT-23-042, 2023 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.462023-12-11011 December 2023 2023 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46 L-MT-23-052, Subsequent License Renewal Application Supplement 72023-11-30030 November 2023 Subsequent License Renewal Application Supplement 7 L-MT-23-051, Update to the Technical Specification Bases2023-11-28028 November 2023 Update to the Technical Specification Bases L-MT-23-049, Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 12023-11-21021 November 2023 Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 1 ML23319A3182023-11-15015 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000263/20230032023-11-13013 November 2023 Integrated Inspection Report 05000263/2023003 and 07200058/2023001 L-MT-23-043, 10 CFR 50.55a(z)(1) Request Regarding OMN-17, Revision 1. VR-092023-11-13013 November 2023 10 CFR 50.55a(z)(1) Request Regarding OMN-17, Revision 1. VR-09 L-MT-23-038, License Amendment Request to Revise Monticello Technical Specification Surveillance Requirement 3.8.6.62023-11-10010 November 2023 License Amendment Request to Revise Monticello Technical Specification Surveillance Requirement 3.8.6.6 L-MT-23-046, Subsequent License Renewal Application Response to Request for Additional Information Round 2 - Set 12023-11-0909 November 2023 Subsequent License Renewal Application Response to Request for Additional Information Round 2 - Set 1 ML23291A1102023-10-23023 October 2023 Environmental Audit Summary and RCIs and RAIs ML23285A3062023-10-12012 October 2023 Implementation of the Fleet Standard Emergency Plan for the Monticello Nuclear Generating Plant and the Prairie Island Nuclear Generating Plant L-MT-23-041, Subsequent License Renewal Application Response to Request for Confirmation of Information Set 22023-10-0303 October 2023 Subsequent License Renewal Application Response to Request for Confirmation of Information Set 2 L-MT-23-037, Subsequent License Renewal Application Response to Request for Additional Information Set 32023-09-22022 September 2023 Subsequent License Renewal Application Response to Request for Additional Information Set 3 ML23262B0372023-09-19019 September 2023 Response to NRC Request for Additional Information Regarding the 2023 Monticello and Prairie Island Plant Decommissioning Funding Status Reports 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 ML23256A1682023-09-13013 September 2023 Independent Spent Fuel Storage Installation and Monticello Nuclear Generating Plant - Voluntary Security Clearance Program 2023 Insider Threat Program Self-Inspection IR 05000263/20230102023-09-0707 September 2023 Commercial Grade Dedication Inspection Report 05000263/2023010 L-MT-23-036, Subsequent License Renewal Application Response to Request for Additional Information Set 2 and Supplement 62023-09-0505 September 2023 Subsequent License Renewal Application Response to Request for Additional Information Set 2 and Supplement 6 ML23214A2412023-08-31031 August 2023 Letter: Aging Management Audit - Monticello Unit 1 - Subsequent License Renewal Application IR 05000263/20230052023-08-30030 August 2023 Updated Inspection Plan for Monticello Nuclear Generating Plant (Report 05000263/2023005) L-MT-23-035, Subsequent License Renewal Application Supplement 52023-08-28028 August 2023 Subsequent License Renewal Application Supplement 5 ML23241A9732023-08-21021 August 2023 Request for Scoping Comments Concerning the Environmental Review of Monticello Nuclear Generating Plant, Unit 1, Subsequent License Renewal Application (Docket No. 50-263) L-MT-23-034, Subsequent License Renewal Application Response to Request for Additional Information Set 12023-08-15015 August 2023 Subsequent License Renewal Application Response to Request for Additional Information Set 1 ML23222A0122023-08-10010 August 2023 Independent Spent Fuel Storage Installation and Monticello Nuclear Generating Plant - Changes in Foreign Ownership, Control or Influence ML23215A1312023-08-0909 August 2023 License Renewal Regulatory Audit Regarding the Environmental Review of the Subsequent License Renewal Application IR 05000263/20230022023-08-0707 August 2023 Plantintegrated Inspection Report 05000263/2023002 L-MT-23-028, 2023 Refueling Outage 90-Day Inservice Inspection (ISI) Summary Report2023-07-31031 July 2023 2023 Refueling Outage 90-Day Inservice Inspection (ISI) Summary Report L-MT-23-032, 10 CFR 50.55a(z)(2) Request Regarding MO-2397, VR-112023-07-31031 July 2023 10 CFR 50.55a(z)(2) Request Regarding MO-2397, VR-11 ML23198A0412023-07-28028 July 2023 LRA Availability Letter ML23206A2342023-07-25025 July 2023 Independent Spent Fuel Storage Installation, and Monticello Nuclear Generating Plant, Changes in Foreign Ownership, Control or Influence ML23201A0352023-07-24024 July 2023 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information ML23202A0032023-07-21021 July 2023 Independent Spent Fuel and Independent Spent Fuel Storage Installation, Monticello Nuclear Generating Plant, Submittal of Quality Assurance Topical Report (NSPM-1) L-MT-23-031, Subsequent License Renewal Application Supplement 4 and Responses to Request for Confirmation of Information - Set 12023-07-18018 July 2023 Subsequent License Renewal Application Supplement 4 and Responses to Request for Confirmation of Information - Set 1 ML23195A1732023-07-14014 July 2023 Revision of Standard Practice Procedures Plan IR 05000263/20235012023-07-13013 July 2023 Emergency Preparedness Inspection Report 05000263/2023501 2024-01-31
[Table view] Category:Safety Evaluation
MONTHYEARML23248A2092023-09-18018 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 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 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 ML15175A0162015-06-30030 June 2015 Staff Evaluation of 10 CFR 50.54(p)(2) Changes to Security Plans ML15072A1412015-06-0505 June 2015 Issuance of Amendment No. 188 Regarding Transition to Areva Atrium 10XM Fuel and Areva Safety Analysis Methods ML15154A4772015-06-0505 June 2015 Safety Evaluation Regarding License Amendment No. 188 Associated with Areva Atrium 10XM Fuel Transition (TAC No. MF2479) - (Redacted) ML14358A0392015-02-20020 February 2015 Northern States Power Company, Minnesota (NSPM) - Monticello Nuclear Generating Plant, Prairie Island Nuclear Generating Plant, Prairie Island ISFSI - Review of Changes to the NSPM Quality Assurance Topical Report 2023-09-18
[Table view] |
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