Letter Sequence Request |
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MONTHYEARL-MT-16-025, Expedited Seismic Evaluation Process (ESEP) - Augmented Approach to Post-Fukushima Near-Term Task Force (NTTF) 2.1 - Proposed Resolution for Components Requiring Action2016-07-22022 July 2016
Expedited Seismic Evaluation Process (ESEP) - Augmented Approach to Post-Fukushima Near-Term Task Force (NTTF) 2.1 - Proposed Resolution for Components Requiring Action
Project stage: Request
ML16302A2462016-10-28028 October 2016
Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from Fukushima..
Project stage: Supplement
ML16354B4212016-12-12012 December 2016
NEI 12-06, Rev 4, Diverse and Flexible Coping Strategies (Flex) Implementation Guide.
Project stage: Request
L-MT-17-025, High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information Pursuant to 10CFR50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accid2017-04-11011 April 2017
High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information Pursuant to 10CFR50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident
Project stage: Supplement
L-MT-17-047, Notification of Full Compliance of Required Action for NRC Order EA-12-049 Mitigation Strategies for Beyond-Design-Basis External Event2017-07-0606 July 2017
Notification of Full Compliance of Required Action for NRC Order EA-12-049 Mitigation Strategies for Beyond-Design-Basis External Event
Project stage: Other
L-MT-17-055, Seismic Mitigating Strategies Assessment (MSA) Report for the Reevaluated Seismic Hazard Information - NEI 12-06, Revision 4, Appendix H, H.4.4, Path 42017-07-26026 July 2017
Seismic Mitigating Strategies Assessment (MSA) Report for the Reevaluated Seismic Hazard Information - NEI 12-06, Revision 4, Appendix H, H.4.4, Path 4
Project stage: Other
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
Project stage: Approval
2017-12-10
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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
[Table view] |
Text
Monticello Nuclear Generating Plant 2807 W County Road 75 Monticello, MN 55362 July 22, 2016 L-MT-16-025 10 CFR 50.54(f)
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 Monticello Nuclear Generating Plant: Expedited Seismic Evaluation Process (ESEP) -
Augmented Approach to Post-Fukushima Near-Term Task Force (NTTF) 2.1 -
Proposed Resolution for Components Requiring Action
References:
- 1) NRC Letter, Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, dated March 12, 2012. (ADAMS Accession No. ML12056A046)
- 2) Letter from K. Fili (NSPM) to Document Control Desk (NRC),
Monticello Nuclear Generating Plant: Expedited Seismic Evaluation Process (ESEP) - Augmented Approach to Post-Fukushima Near-Term Task Force (NTTF) 2.1, L-MT-14-093, dated December 23, 2014. (ADAMS Accession No. ML14357A280)
- 3) Email from S. Wyman (NRC) to J. Fields (NSPM), Monticello ESEP Report Clarifications, dated April 8, 2015. (ADAMS Accession No. ML16109A151)
- 4) Letter from P. Gardner (NSPM) to Document Control Desk (NRC),
Monticello Nuclear Generating Plant: Expedited Seismic Evaluation Process (ESEP) - Augmented Approach to Post-Fukushima Near-Term Task Force (NTTF) 2.1 - Response to Requests for Additional Information, L-MT-15-030, dated May 22, 2015. (ADAMS Accession No. ML15142A862)
On March 12, 2012, the NRC issued Reference 1 to request seismic profile information associated with Near-Term Task Force (NTTF) Recommendation 2.1 from all NRC power reactor licensees.
In Reference 2, Northern States Power Company, a Minnesota corporation (NSPM),
d/b/a Xcel Energy, the licensee for Monticello Nuclear Generating Plant (MNGP),
Document Control Desk Page 2 responded to the NRC and provided an Expedited Seismic Evaluation Process (ESEP) report. The results indicated that additional action (e.g. evaluation, modification, or other action) was required to assure that sufficient seismic margin is available for a small set of plant equipment.
On April 8, 2015, the NRC sent an email (Reference 3) that contained requests for additional information (RAis) related to the ESEP report provided in Reference 2.
On May 22, 2015 (Reference 4), NSPM responded to the NRC requested information in Reference 3. As part of the response to the NRC, NSPM provided corrections to the ESEP report and provided the following regulatory commitment:
A letter will be provided to the NRC indicating the proposed resolution applicable to each component and the expected timeframe for completion of the resolution when this information has been developed.
The purpose of this letter is to provide the information necessary to satisfy the above commitment. The enclosure contains the necessary information.
If there are any questions or if additional information is needed, please contact John Fields, Fukushima Response Licensing, at 763-271-6707.
Summary of Commitments This letter contains no new commitments and no revisions to existing commitments.
This letter completes and closes a commitment made to the NRC.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on July ft 2016.
Peter A Gardner Site Vice President, Monticello Nuclear Generating Plant Northern States Power Company - Minnesota Enclosure cc: Administrator, Region Ill, USNRC Project Manager, Monticello Nuclear Generating Plant, USNRC Resident Inspector, Monticello Nuclear Generating Plant, USNRC
L-MT-16-025 ENCLOSURE MONTICELLO NUCLEAR GENERATING PLANT COMPONENTS REQUIRING ACTION TO MEET ESEP REVISED SEISMIC CRITERIA
- PROPOSED RESOLUTION AND EXPECTED COMPLETION DATES I. Introduction In Reference 1, Northern States Power Company, a Minnesota corporation (NSPM),
d/b/a Xcel Energy, the licensee for Monticello Nuclear Generating Plant (MNGP),
responded to the NRC and provided an Expedited Seismic Evaluation Process (ESEP) report. The results indicated that additional action (e.g. evaluation, modification, or other action) was required to assure sufficient seismic margin is available for a small set of plant equipment.
On April 8, 2015, the NRC sent an email (Reference 2) that contained requests for additional information (RAIs) related to the ESEP report provided in Reference 2.
On May 22, 2015 (Reference 3), NSPM responded to the NRC requested information in Reference 2. As part of the response to the NRC, NSPM provided corrections to the ESEP report and provided the following regulatory commitment:
A letter will be provided to the NRC indicating the proposed resolution applicable to each component and the expected timeframe for completion of the resolution when this information has been developed.
This enclosure provides the information necessary to satisfy the above commitment.
II. Requested Information In Reference 3, NSPM provided Table 7-1, which identified 24 components requiring further evaluation and/or modification to meet the revised seismic capacity (i.e. to withstand the Review Level Ground Motion (RLGM)) applicable MNGP. Table 1 below, provides the proposed resolution for each of the 24 components previously identified and the expected timeframe for completion of the proposed resolutions.
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L-MT-16-025 Table 1 - Proposed Resolution with Expected Completion Schedule Component ID Proposed Resolution Schedule to Implement Resolution E-200B - bolts on heat No further action required. See Note 1. N/A exchanger supports HGA Relay 13A-K3 No further action required. See Note 2. N/A HGA Relay 13A-K5 No further action required. See Note 2. N/A HGA Relay 13A-K13 No further action required. N/A See Notes 2 and 3.
HGA Relay 13A-K14 No further action required. See Note 2. N/A HGA Relay 13A-K17 No further action required. See Note 2. N/A HGA Relay 13A-K28 No further action required. N/A See Notes 2 and 4.
HGA Relay 13A-K29 No further action required. See Note 2. N/A HGA Relay 13A-K30 No further action required. See Note 2. N/A Agastat Relay K102B No further action required. See Note 4. N/A dPIS-13-83 Replace with greater seismic capacity Startup from 2017 RFO component.
dPIS-13-84 Replace with greater seismic capacity Startup from 2017 RFO component.
PS-13-87A Replace with greater seismic capacity Startup from 2017 RFO component.
PS-13-87B Replace with greater seismic capacity Startup from 2017 RFO component.
PS-13-87C Replace with greater seismic capacity Startup from 2017 RFO component.
PS-13-87D Replace with greater seismic capacity Startup from 2017 RFO component.
LIS-2-3-672A No further action required. N/A See Notes 2 and 5.
LIS-2-3-672B No further action required. N/A See Notes 2 and 5.
LIS-2-3-672C No further action required. N/A See Notes 2 and 5.
LIS-2-3-672D No further action required. N/A See Notes 2 and 5.
LS-2-3-672E No further action required. N/A See Notes 2 and 6.
LS-2-3-672F No further action required. N/A See Notes 2 and 6.
LS-23-74 No further action required. See Note 7. N/A LS-23-75 No further action required. See Note 7. N/A Page 2 of 3
L-MT-16-025 Notes:
- 1) Component bolting was reevaluated and found to meet ESEP requirements (i.e.
High Confidence of a Low Probability of Failure (HCLPF) exceeds RLGM).
Therefore, no further action is required.
- 2) Device was evaluated in greater detail to determine seismic capacity for the contact and coil states that are expected during the seismic event. The device was found to have sufficient seismic capacity to withstand the seismic demand.
Therefore, no further action is required.
- 3) Circuit analysis has determined that this device does not create a seal-in condition as previously thought. Therefore, this device was removed from the scope of the ESEP and no further action is required.
- 4) Chatter of contacts in relays 13A-K28 or K102B would be blocked by relay K102A, which has been determined not to chatter. Therefore, these relays are not applicable to ESEP and no further action is required.
- 5) Contact chatter was determined to create a desired response (initiation of the Reactor Core Isolation Cooling (RCIC) system). Therefore, no further action is required.
- 6) Contact chatter was determined to have no effect on the controlled components (RCIC valves). Therefore, no further action is required.
- 7) Contact chatter of LS-23-74 and LS-23-75 would transfer RCIC pump suction from the Condensate Storage Tank to the Torus. This is a desired response for FLEX implementation. Therefore, no further action is required.
III. References
- 1) Letter from K. Fili (NSPM) to Document Control Desk (NRC), Monticello Nuclear Generating Plant: Expedited Seismic Evaluation Process (ESEP) - Augmented Approach to Post-Fukushima Near-Term Task Force (NTTF) 2.1, L-MT-14-093, dated December 23, 2014. (ADAMS Accession No. ML14357A280)
- 2) Email from S. Wyman (NRC) to J. Fields (NSPM), Monticello ESEP Report Clarifications, dated April 8, 2015. (ADAMS Accession No. ML16109A151)
- 3) Letter from P. Gardner (NSPM) to Document Control Desk (NRC), Monticello Nuclear Generating Plant: Expedited Seismic Evaluation Process (ESEP) -
Augmented Approach to Post-Fukushima Near-Term Task Force (NTTF) 2.1 -
Response to Requests for Additional Information, L-MT-15-030, dated May 22, 2015. (ADAMS Accession No. ML15142A862)
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