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Category:Letter type:L
MONTHYEARL-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
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
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
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
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
L-MT-23-035, Subsequent License Renewal Application Supplement 52023-08-28028 August 2023
Subsequent License Renewal Application Supplement 5
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
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
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
L-MT-23-030, Subsequent License Renewal Application Supplement 32023-07-0404 July 2023
Subsequent License Renewal Application Supplement 3
L-MT-23-025, Subsequent License Renewal Application Supplement 22023-06-26026 June 2023
Subsequent License Renewal Application Supplement 2
L-MT-23-019, Submittal of 2022 Annual Radiological Environmental Operating Report2023-05-10010 May 2023
Submittal of 2022 Annual Radiological Environmental Operating Report
L-MT-23-020, Submittal of 2022 Annual Radioactive Effluent Release Report2023-05-10010 May 2023
Submittal of 2022 Annual Radioactive Effluent Release Report
L-MT-23-021, Core Operating Limits Report (COLR) for the Monticello Nuclear Generating Plant for Cycle 322023-05-0202 May 2023
Core Operating Limits Report (COLR) for the Monticello Nuclear Generating Plant for Cycle 32
L-MT-23-017, 2022 Annual Report of Individual Monitoring for the Monticello Nuclear Generating Plant (MNGP)2023-04-18018 April 2023
2022 Annual Report of Individual Monitoring for the Monticello Nuclear Generating Plant (MNGP)
L-MT-23-010, Subsequent License Renewal Application Supplement 12023-04-0303 April 2023
Subsequent License Renewal Application Supplement 1
L-MT-23-013, Core Operating Limits Report (COLR) for Cycle 31, Revision 32023-03-28028 March 2023
Core Operating Limits Report (COLR) for Cycle 31, Revision 3
L-MT-23-012, Core Operating Limits Report (COLR) for Monticello Nuclear Generating Plant Cycle 31, Revision 22023-03-17017 March 2023
Core Operating Limits Report (COLR) for Monticello Nuclear Generating Plant Cycle 31, Revision 2
L-MT-23-008, 10CFR50.55a Request to Use Later Edition of ASME Section XI for ISI Code of Record (RR-003)2023-02-0707 February 2023
10CFR50.55a Request to Use Later Edition of ASME Section XI for ISI Code of Record (RR-003)
L-MT-23-004, CFR 50.55a Request RR-001, Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI for the Monticello Third Interval Containment Inservice Inspection Program2023-01-23023 January 2023
CFR 50.55a Request RR-001, Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI for the Monticello Third Interval Containment Inservice Inspection Program
L-MT-23-005, Response to the NRC Request for Additional Information Regarding the 50.55a Request Pr 08, HPCI Pump Quarterly Testing (EPID Number L-2022-LLR-0088)2023-01-0606 January 2023
Response to the NRC Request for Additional Information Regarding the 50.55a Request Pr 08, HPCI Pump Quarterly Testing (EPID Number L-2022-LLR-0088)
L-MT-22-049, Industry Groundwater Protection Initiative Special Report2022-12-15015 December 2022
Industry Groundwater Protection Initiative Special Report
L-MT-22-052, L-MT-22-052 Monticello Nuclear Generating Plant 10 CFR 50.55a Request No. Pr 08, Request for HPCI Pump Quarterly Alternative2022-12-15015 December 2022
L-MT-22-052 Monticello Nuclear Generating Plant 10 CFR 50.55a Request No. Pr 08, Request for HPCI Pump Quarterly Alternative
L-MT-22-046, 2022 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.462022-12-13013 December 2022
2022 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46
L-MT-22-048, Update to the Monticello Technical Specification Bases2022-11-28028 November 2022
Update to the Monticello Technical Specification Bases
L-MT-22-047, Withdrawal of Request for Relief from ASME OM Code for the Sixth Inservice Testing Interval2022-11-10010 November 2022
Withdrawal of Request for Relief from ASME OM Code for the Sixth Inservice Testing Interval
L-MT-22-045, Letter Submitting Post-Exam Package2022-11-0404 November 2022
Letter Submitting Post-Exam Package
L-MT-22-030, Sixth Interval Inservice Testing (1ST) Plan2022-09-0606 September 2022
Sixth Interval Inservice Testing (1ST) Plan
L-MT-22-037, Supplement to 10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval, Alternative VR-10, Excess Flow Check Valve Testing Frequency2022-08-29029 August 2022
Supplement to 10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval, Alternative VR-10, Excess Flow Check Valve Testing Frequency
L-MT-22-007, Response to Request for Additional Information for the Monticello Nuclear Generating Plant Alternative Request VR-08 (EPID: L-MT-22-007)2022-07-22022 July 2022
Response to Request for Additional Information for the Monticello Nuclear Generating Plant Alternative Request VR-08 (EPID: L-MT-22-007)
L-MT-22-026, Changes to the Emergency Plan2022-07-19019 July 2022
Changes to the Emergency Plan
L-MT-22-024, Response to a Request for Additional Information for the Monticello Nuclear Generating Plant Related to the Amendment to Adopt Advanced Framatome Methodologies2022-06-0606 June 2022
Response to a Request for Additional Information for the Monticello Nuclear Generating Plant Related to the Amendment to Adopt Advanced Framatome Methodologies
L-MT-22-022, Response to a Request for Additional Information: Monticello Alternative VR-10, Excess Flow Check Valve Testing Frequency2022-05-25025 May 2022
Response to a Request for Additional Information: Monticello Alternative VR-10, Excess Flow Check Valve Testing Frequency
L-MT-22-017, 2021 Annual Radiological Environmental Operating Report2022-05-11011 May 2022
2021 Annual Radiological Environmental Operating Report
L-MT-22-018, 2021 Annual Radioactive Effluent Release Report2022-05-11011 May 2022
2021 Annual Radioactive Effluent Release Report
L-MT-22-016, 2021 Annual Report of Individual Monitoring2022-04-28028 April 2022
2021 Annual Report of Individual Monitoring
L-MT-22-019, Withdrawal of Requests for Relief from ASME OM Code for the Sixth Inservice Testing Interval2022-04-18018 April 2022
Withdrawal of Requests for Relief from ASME OM Code for the Sixth Inservice Testing Interval
L-MT-22-010, License Amendment Request to Revise Technical Specification 3.6.1.8 Residual Heat Removal (RHR) Drywell Spray Header and Nozzle Surveillance Frequency2022-03-18018 March 2022
License Amendment Request to Revise Technical Specification 3.6.1.8 Residual Heat Removal (RHR) Drywell Spray Header and Nozzle Surveillance Frequency
L-MT-22-012, Special Report for the Bypass of the Offgas Treatment Storage System2022-03-15015 March 2022
Special Report for the Bypass of the Offgas Treatment Storage System
L-MT-22-008, 10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval Alternative Related to Excess Flow Check Valve Testing Frequency (L-MT-22-008)2022-03-0707 March 2022
10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval Alternative Related to Excess Flow Check Valve Testing Frequency (L-MT-22-008)
L-MT-22-006, 10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval OMN-26 (L-MT-22-006)2022-02-18018 February 2022
10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval OMN-26 (L-MT-22-006)
2024-01-11
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Xcel Energy@ Monticello Nuclear Generating Plant 2807 W County Road 75 Monticello, MN 55362 June 19, 2013 L-MT-13-052 10 CFR 50.4 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Monticello Nuclear Generating Plant Docket No. 50-263 Renewed Facility Operating License No. DPR-22 Commitment for Implementation of Multi-Source Dose Assessment Capability
References:
- 1. US NRC Fukushima Near-Term Task Force Report, "Recommendations for Enhancing Reactor Safety in the 21 st Century, the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident," dated July 12, 2011 (ADAMS Accession No. ML112510271).
- 2. Nuclear Energy Institute (NEI) letter to NRC, "Industry Implementation of Multi-Unit Dose Assessment Capability," dated January 28,2013 (ADAMS Accession No. ML13028A200).
- 3. NRC letter to NEI dated February 27, 2013 (ADAMS Accession No. ML13029A632).
- 4. NEI letter to NRC, "Commitment for Implementation of Multi-Unit Dose Assessment Capability," dated March 14,2013 (ADAMS Accession No. ML13073A522).
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
Document Control Desk Page 2 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, d/b/a Xcel Energy (hereafter "NSPM") is providing the requested details on behalf of the Monticello Nuclear Generating Plant (MNGP). The enclosure to this letter includes discussion of the current capability to perform multi-source dose assessments, the interim compensatory measures for this capability, and the final permanent solution. Also included is a milestone implementation schedule with target dates that covers both the implementation of the interim measures and the permanent solution.
Please contact Lynne Gunderson, Licensing Engineer, at 612-396-0173, if additional information or clarification is required.
Summary of Commitments:
This letter makes one new commitment and no revisions to existing commitments:
- NSPM commits to having multi-source dose assessment capability for MNGP no later than December 31,2014. This commitment date is contingent upon the release of the revised RASCAL dose assessment model by November 30,2013.
Mark A. Schimmel Site Vice President, Monticello Nuclear Generating Plant Northern States Power Company - Minnesota Enclosure cc: Administrator, Region III, USNRC Director of Nuclear Reactor Regulation (NRR), USNRC NRR Project Manager, MNGP, USNRC Senior Resident Inspector, MNGP, USNRC Director, Nuclear Security and Incident Response, USNRC Director, Japan Lessons Learned Project Directorate (NRR), USNRC
ENCLOSURE Monticello Nuclear Generating Plant Commitment for Implementation of Multi-Source Dose Assessment Capability Page 1 of 4
Monticello Nuclear Generating Plant Commitment for Implementation of Multi-Source Dose Assessment Capability 1.0 Introduction 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, the Nuclear Energy Institute (NEI) sent a letter to NRC (Reference 2) that reported survey results regarding licensees' current capabilities to perform multi-unit dose assessments. The NEI letter also discussed licensees' expected implementation time frames and compensatory measures for the interim period. The NRC requested further detailed information (Reference 3) regarding the current and anticipated capabilities of sites to perform multi-unit dose assessments. NEI informed the NRC (Reference 4) that the industry had elected to provide the requested details directly to the NRC staff. The requested details were to include:
- A summary of the current capability to perform multi-unit/multi-source dose assessments.
- The anticipated schedule to establish the capability on an interim and/or permanent basis.
- Due dates associated with each key schedule action or milestone.
- A description of how the implementation schedule will be tracked.
Northern States Power Company, a Minnesota corporation, d/b/a Xcel Energy (hereafter "NSPM") provides the responses below on behalf of the Monticello Nuclear Generating Plant (MNGP).
2.0 Summary of Current Multi-Source Capability NSPM currently has the capability to perform a multi-source dose assessment by performing individual dose assessment runs for each release point and manually summing the results to make estimates. These results could be used for Emergency Action Level (EAL) and Protective Action Recommendation (PAR) determinations. This capability is in line with the compensatory measures described by NEI in the Reference 2 letter.
NSPM currently uses the NRC dose assessment model RASCAL (Radiological Assessment for Consequence Analysis), Version 4.1, for dose assessment at the MNGP. RASCAL is loaded on multiple computers and there is sufficient depth of trained dose assessment personnel in the Emergency Response Organization (ERO) to perform the multiple dose assessment runs.
NSPM evaluated the current procedural guidance and ERO training for multi-source dose assessment capability. It was determined that the current procedural guidance and ERO training for performing dose assessments do not contain the detail necessary to Page 2 of 4
Monticello Nuclear Generating Plant Commitment for Implementation of Multi-Source Dose Assessment Capability ensure combining the multiple dose assessment runs and generating consistent EAL and PAR decision making for multi-source releases.
3.0 Interim Measures Based on the evaluation discussed in Section 2.0 above, NSPM will be revising procedures and ERO training to incorporate multi-source dose assessment as an interim measure until the permanent solution is achieved. The procedure revisions and ERO training for the interim measures are in progress and will be implemented by September 27, 2013.
4.0 Permanent Solution NSPM's permanent solution is to implement the next expected revision of NRC's RASCAL dose assessment model that will be capable of performing the multiple release point modeling. Along with implementation of the revised RASCAL model, the necessary procedure changes will be made and the necessary ERO training will be conducted.
NSPM commits to having multi-source dose assessment capability no later than December 31,2014. This commitment date is contingent upon the release of the revised RASCAL dose assessment model by November 30,2013.
5.0 Schedule The table below contains the schedule milestones for ensuring interim capability and for implementation of the permanent solution. Target dates are provided for each schedule milestone.
NSPM is tracking the schedule milestones below in the MNGP Corrective Action Process (CAP) in Action Request No. 01386448.
Install updated RASCAL software/perform software acceptance. May 30,2014 Complete rocedure revisions and initial ERO trainin . June 27,2014 Implement updated RASCAL dose assessment model. Jul 31,2014 Page 3 of 4
Monticello Nuclear Generating Plant Commitment for Implementation of Multi-Source Dose Assessment Capability 6.0 References
- 1. US NRC Fukushima Near-Term Task Force Report, "Recommendations for Enhancing Reactor Safety in the 21 st Century, the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident," dated July 12, 2011 (ADAMS Accession No. ML112510271).
- 2. NEI letter to NRC, "Industry Implementation of Multi-Unit Dose Assessment Capability," dated January 28,2013 (ADAMS Accession No. ML13028A200).
- 3. NRC letter to NEI dated February 27,2013 (ADAMS Accession No. ML13029A632).
- 4. NEI letter to NRC, "Commitment for Implementation of Multi-Unit Dose Assessment Capability," dated March 14,2013 (ADAMS Accession No. ML13073A522).
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