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Category:Letter
MONTHYEARIR 05000282/20230042024-02-0101 February 2024 Integrated Inspection Report 05000282/2023004 and 05000306/2023004 ML24025A9362024-01-31031 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 ML23356A1232024-01-29029 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting) 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 ML24017A0182024-01-19019 January 2024 Confirmation of Initial License Examination ML23356A0032024-01-17017 January 2024 Issuance of Amendments Revise Technical Specification 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) L-MT-23-054, Subsequent License Renewal Application Supplement 82024-01-11011 January 2024 Subsequent License Renewal Application Supplement 8 L-PI-23-034, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.7.8, Cooling Water (Cl) System,2024-01-0202 January 2024 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.7.8, Cooling Water (Cl) System, 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 IR 07200010/20234012023-12-20020 December 2023 Independent Spent Fuel Storage Installation Security Inspection Report 07200010/2023401 L-PI-23-035, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report2023-12-20020 December 2023 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report 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 ML23215A1672023-12-15015 December 2023 Acceptance of Requested Licensing Action Amendment Request to Revise Surveillance Requirement 3.8.1.2 Note 3 IR 05000282/20234012023-12-13013 December 2023 Security Baseline Inspection Report 05000282/2023401 and 05000306/2023401 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-PI-23-033, Supplement to License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 32023-12-0505 December 2023 Supplement to License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 3 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 ML23304A1632023-11-15015 November 2023 Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment Request to Revise SR 3.8.1.2 Note 3 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 IR 05000282/20230032023-11-0808 November 2023 Integrated Inspection Report 05000282/2023003 and 05000306/2023003 ML23311A3572023-11-0707 November 2023 Core Operating Limits Report (COLR) for Prairie Island Nuclear Generating Plant (PINGP) Unit 2. Cycle 33. Revision 0 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 ML23270B9022023-09-29029 September 2023 Review of Reactor Vessel Material Surveillance Program Capsule N Technical Report L-PI-23-025, License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 32023-09-28028 September 2023 License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 3 ML23265A2532023-09-26026 September 2023 Review of Reactor Vessel Material Surveillance Program Capsule N Technical Report 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 2024-02-01
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Xcel Energy October 23, 2013 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Prairie Island Nuclear Generating Plant, Units 1 and 2 Docket Nos. 50-282 and 50-306 Renewed License Nos. DPR-42 and DPR-60 414 Nicollet Mall-MP4 Minneapolis, MN 55401 L-XE-13-014 10 CFR 50.4 Monticello Nuclear Generating Plant Docket No. 50-263 Renewed License No. DPR-22 Supplement to Letters Regarding Commitment for Implementation of Source Dose Assessment Capability for Prairie Island Nuclear Generating Plant and Monticello Nuclear Generating Plant
References:
- 1. US NRC Fukushima Near-Term Task Force Report, "Recommendations for Enhancing Reactor Safety in the 2181 Century, the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident,"
dated July 12, 2011 (ADAMS Accession No. ML 112510271).
- 2. Nuclear Energy Institute (NEI) letter to NRC, "Industry Implementation of Multi-Unit Dose Assessment Capability,"
dated January 28, 2013 (ADAMS Accession No. ML 13028A200).
- 3. NRC letter to NEI dated February 27, 2013 (ADAMS Accession No. ML 13029A632).
- 4. NEIIetter to NRC, "Commitment for Implementation of Multi-Unit Dose Assessment Capability,"
dated March 14, 2013 (ADAMS Accession No. ML 13073A522).
- 5. NSPM letter to NRC, "Commitment for Implementation of Source Dose Assessment Capability,"
dated June 17, 2013 (ADAMS Accession No. ML 13169A351).
Document Control Desk Page 2 6. NSPM letter to NRC, "Commitment for Implementation of Multi-Source Dose Assessment Capability,"
dated June 19, 2013 (ADAMS Accession No. ML13171A011).
- 7. NRC Memorandum, "Summary of September 5, 2013, Public Teleconference to Discuss Licensee Use of Software to Perform Unit/Multi-Source Dose Assessment Related to Near-Term Task Force Recommendation 9.3," dated September 27, 2013 (ADAMS Accession No. ML 13266A390).
The NRC Fukushima Near-Term Task Force (NTTF) Report (Reference
- 1) dated July 12, 2011, discussed the gap in capability for US commercial nuclear power plants to perform multi-unit dose assessments.
In January 2013, NEI provided to the NRC (Reference
- 2) survey results regarding licensees' capabilities to perform multi-unit dose assessments, implementation time frames to obtain multi-unit dose assessment capability, and compensatory measures for the interim period. The NRC requested further detailed information (Reference
- 3) regarding the current and the anticipated capabilities of sites to perform multi-unit dose assessment.
NEI informed the NRC (Reference
- 4) that the industry had elected to provide the requested details directly to the NRC staff. Northern States Power Company, a Minnesota corporation, doing business as Xcel Energy (hereafter "NSPM"),
provided the requested information on behalf of the Prairie Island Nuclear Generating Plant (PINGP) and the Monticello Nuclear Generating Plant (MNGP) in References 5 and 6. During a public meeting on September 5, 2013, (Reference
- 7) the NRC requested that licensees supplement or supersede the original submittals to describe a plan to update their software to have the capability to conduct multi-unit/multi-source dose assessment capability without reliance on the next revision of NRC's RASCAL dose assessment model. The purpose of this letter is to update the Reference 5 and 6 responses to address the Reference 7 request regarding the permanent solution and to revise the regulatory commitments made in References 5 and 6. Updated responses:
- Section 4.0, "Permanent Solution,"
of the enclosure to both References 5 and 6, made the statement that the permanent solution is to implement the next expected revision of NRC's RASCAL dose assessment model. As agreed to in the September 5, 2013, conference call (Reference 7), NSPM changes the permanent solution described in References 5 and 6 from the use of RASCAL to Document Control Desk Page 3 the use of new or modified software that will ensure multi-unit/multi-source dose assessment capability.
- The regulatory commitment described in the cover letter and Section 4.0, "Permanent Solution,"
of the enclosure to References 5 and 6, stated that the NSPM commitment date was contingent upon the release of the revised RASCAL dose assessment model by November 30, 2013. As agreed to in the September 5, 2013, conference call (Reference 7), NSPM removes the reliance on the release of the revised RASCAL dose assessment model from the commitment.
NSPM remains committed to implementing the source dose assessment capability by December 31, 2014. The revised commitment statements for PINGP and MNGP are included below under, "Summary of Commitments."
of the enclosure to both References 5 and 6, provided schedule milestones for the permanent solution that included reference to the updated revision of RASCAL Updated schedule milestones that incorporate the changes to NSPM's permanent solution are provided below. The updates remove the reference to RASCAL, revise the target dates, and separate the milestone for procedures and training into two milestones with separate target dates. The schedule milestones are target dates provided to help with understanding NSPM's internal implementation schedule developed to meet the December 31, 2014 regulatory commitment.
The target dates are not considered regulatory commitments but rather planning dates that are administratively controlled by NSPM. Therefore, target dates may be changed by NSPM without NRC notification as long as the target date change does not exceed the regulatory commitment date of December 31, 2014. Schedule Milestones Target Date Permanent Solution Install new or modified software/perform software May 30,2014 acceptance.
Complete procedure markups.
June 30, 2014 Complete initial ERO training.
September 30, 2014 Implement new or modified software for multi-unit/multi-December 31, 2014 source dose assessment.
NSPM continues to track these schedule milestones in PINGP Corrective Action Program (CAP) Action Request 01386421 and in MNGP CAP Action Request 01386448.
Document Control Desk Page4 Please contact Lynne Gunderson, Licensing
- Engineer, at 612-396-0173, if additional information or clarification is required.
Summary of Commitments:
This letter makes revision to two existing commitments that were provided in References 5 and 6. The revision removes the reliance on the release of the revised RASCAL dose assessment model from the commitment.
The revised commitments for PINGP and MNGP are provided below. Reference 5 (PINGP):
- NSPM commits to having multi-unit/multi-source dose assessment capability for PINGP no later than December 31, 2014. Reference 6 (MNGP):
- NSPM commits to having multi-source dose assessment capability for MNGP no later than December 31, 2014. 1uf Martin C. Murphy Director, Nuclear Licensing and Regulatory Affairs Northern States Power Company -Minnesota cc: Administrator, Region Ill, USNRC Director of Nuclear Reactor Regulation (NRR), USNRC Project Manager, Monticello Nuclear Generating Plant, USNRC Project Manager, Prairie Island Nuclear Generating Plant, USNRC Resident Inspector, Monticello Nuclear Generating Plant, USNRC Resident Inspector, Prairie Island Nuclear Generating Plant, USNRC Director, Nuclear Security and Incident
- Response, USNRC Director, Japan Lessons Learned Project Directorate (NRR), USNRC