Letter Sequence Acceptance Review |
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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
February 8, 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 - DENIAL OF ALTERNATIVE FOR VISUAL EXAMINATION ILLUMINATION LEVELS FOR THE FOURTH 10-YEAR INSERVICE INSPECTION INTERVAL (TAC NO. MC8102)
Dear Mr. Conway:
By letter dated August 11, 2005, you requested authorization for a proposed alternative regarding visual examination illumination levels in accordance with Title 10 of the Code of Federal Regulations (10 CFR) Section 50.55a(a)(3)(i) for the fourth 10-year inservice inspection interval at Monticello Nuclear Generating Plant.
The Nuclear Regulatory Commission (NRC) staff completed its review of your request, and concluded that, even though there is no safety concern, the proposed alternative cannot be approved because 10 CFR 50.55a(a)(3) does not provide for retroactively approving an alternative. The enclosed safety evaluation documents the NRC staff's evaluation of the regulatory and safety aspects of your proposed alternative concluding that, even though there is no safety concern, it cannot be approved.
If you have any questions, please call the Project Manager, Mr. Peter Tam at 301-415-1451.
Sincerely,
\RA\
Timothy J. Kobetz, Acting Chief Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-263
Enclosure:
As stated cc w/encl: See next page
ML060090504 *Concurrence on modification of 10/4/06 SE.
OFFICE NRR/LPL3-1/PM NRR/LPL3-1/LA EMCB/SC OGC NRR/LPL3-1/BC(A)
NAME PTam THarris TChan* MSpencer TKobetz DATE 02/07/06 02/07/06 02/01/06 2/2/06 02/08/06 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION DENIAL OF INSERVICE INSPECTION PROGRAM RELIEF REQUEST NO. 12 MONTICELLO NUCLEAR GENERATING PLANT (MNGP)
NUCLEAR MANAGEMENT COMPANY, LLC DOCKET NO. 50-263
1.0 INTRODUCTION
By letter dated August 11, 2005 (Agencywide Document Access and Management System (ADAMS) Accession No. ML052280277), Nuclear Management Company, LLC, (the licensee) submitted a request for relief from certain inservice inspection (ISI) requirements specified in the American Society of Mechanical Engineers (ASME), Boiler and Pressure Vessel Code (Code); specifically, the relief request is regarding post-visual examination verification of adequate illumination when using a battery-powered portable light required by ASME Code Section XI, IWA-2210(f). The relief request is a one-time submittal for the fourth 10-year ISI interval, which began March 9, 2003, and ends May 31, 2012, at MNGP. Furthermore, the relief request does not pertain to any prospective action the licensee plans to take, but only to five particular examinations performed in the 2003 and 2004 time frame.
2.0 REGULATORY EVALUATION
The Commission's regulation at Title 10 of the Code of Federal Regulations (10 CFR), Section 50.55a(g), specifies that ISI of nuclear power plant components shall be performed in accordance with the requirements of the ASME Code,Section XI, except where specific written relief has been granted by the Nuclear Regulatory Commission (NRC) pursuant to 10 CFR 50.55a(g)(6)(i). In addition, 10 CFR 50.55a(a)(3) states that alternatives to the requirements of paragraph (g) may be used, when authorized by the NRC, if (i) the proposed alternatives would provide an acceptable level of quality and safety, or (ii) compliance with the specified requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
Pursuant to 10 CFR 50.55a(g)(4), ASME Code Class 1, 2, and 3 components (including supports) will meet the requirements, except the design and access provisions and the preservice examination requirements, set forth in the ASME Code,Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components," to the extent practical within the limitations of design, geometry, and materials of construction of the components. The regulations require that inservice examination of components and system pressure tests conducted during the first 10-year interval and subsequent intervals comply with the requirements in the latest edition and addenda of Section XI of the ASME Code incorporated by reference in 10 CFR 50.55a(b) 12 months prior to the start of the 120-month interval, subject to the limitations and modifications listed therein. The components (including supports) may meet ENCLOSURE
the requirements set forth in subsequent editions and addenda of the ASME Code incorporated by reference in 10 CFR 50.55a(b) subject to the limitations and modifications listed therein and subject to Commission approval. Accordingly, the ISI Code of record and the applicable Code for repair and replacement activities for Monticello, for the fourth 10-year ISI interval, is the 2001 Edition of Section XI of the ASME Code with no Addenda as approved by the NRC staff on October 3, 2003 (ADAMS Accession No. ML032040157).
3.0 DISCUSSION 3.1 System/Components for which Relief is Requested The components affected by this relief request are listed below:
Component and System ASME Code Class Control Rod Drive (CRD) System Hydraulic Control Unit (HCU) 2 26-27 Residual Heat Removal - Service Water (RHRSW) System Pump 3 12 RHRSW System Pump 14 3 Emergency Diesel Generator - Emergency Service Water (EDG- 3 ESW) System Pump 11 EDG-ESW System Pump 12 3 3.2 Code Requirements from which Relief is Requested The licensee is requesting relief from the 2001 Edition with no Addenda, ASME Code,Section XI, IWA-2210(e) and IWA-2210(f) requirements for verification of the adequacy of illumination levels from battery powered portable lights before each examination or series of examinations for the five components listed above. This relief request will be analyzed under 10 CFR 50.55a(a)(3)(i).
3.3 Proposed Alternative and Basis for Relief The licensee proposed that the five components post-repair activity VT-2 examinations remain as acceptable examinations even though the portable lighting used to assist the examiners was not verified both before and after the series of examinations due to a procedural inadequacy.
According to the licensee, these examinations cannot be re-performed because they were associated with pre-service testing required by IWA-4540 and the relevant components and systems have since been restored to service. The licensee also stated that the procedural inadequacy is being tracked and will be corrected under the Monticello Corrective Action Program. The licensee stated three factors justifying that the existing VT-2 examinations provide an acceptable level of quality and safety:
(1) The use of qualified VT-2 examiners, who stated that there was sufficient lighting to perform the examinations, (2) The examiners used battery powered portable lights which provided additional illumination beyond ambient, and, (3) The site Nondestructive Examination (NDE) Level III performed a walkdown of the components and determined that the areas containing the components had sufficient ambient lighting to meet the lighting requirements under IWA-2210(e).
4.0 EVALUATION IWA-2210(f) states:
The adequacy of the illumination levels from battery powered portable lights shall be checked before and after each examination or series of examinations, not to exceed four hours between checks. In lieu of using a light meter, these checks may be made by verifying that the illumination is adequate (i.e., no discernable degradation in the visual examination resolution of the procedure demonstration test chart characters.
IWA-2210(e) allows the deferral of the verification of illumination levels when the same portable light source or similar installed lighting equipment is demonstrated to provide the illumination specified in Table IWA-2210-1. The subject Table provides acceptance standards for minimum illumination and procedure demonstration lower-case character height.
Based on the information provided by the licensee, the site NDE Level III went back to the subject areas and measured the ambient lighting after the examinations were performed.
The results were that the ambient lighting (from similarly installed lighting equipment) was sufficient for the VT-2 examinations as required under IWA-2210(e). Based on the information that the ambient lighting alone provided sufficient lighting, and the examiners used portable lighting which was over and above what was necessary to perform the examinations, the NRC staff agrees that the examinations performed would have identified any leakage during the VT-2 examinations. Therefore, the NRC staff concludes that the existing examinations without verification of portable battery-powered lighting illumination for these five components provide an acceptable level of quality and safety
5.0 CONCLUSION
- DENIAL OF PROPOSED ALTERNATIVE The NRC staff has concluded that, for the above identified components, VT-2 examination verification of lighting levels of installed lighting equipment in lieu of the 4-hour check of portable battery-powered illumination levels did provide an acceptable level of quality and safety. However, the NRC staff determined that, even though there is no safety concern, 10 CFR 50.55a(a)(3) does not provide for retroactive approval of an alternative. Accordingly, the proposed alternative is denied.
Principal Contributor: Timothy Steingass Date: February 8, 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
