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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-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
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
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
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-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
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-PI-23-023, Baffle Former Bolts Alternate Aging Management Strategy2023-09-11011 September 2023
Baffle Former Bolts Alternate Aging Management Strategy
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-23-032, 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-23-028, 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-23-031, 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-PI-23-018, License Amendment Request to Revise ISFSI Technical Specification 4.4 to Allow Use of a Code Alternative to ASME Code, NB-5130, Examination of Weld Edge Preparation Surfaces, for the TN-40HT2023-07-14014 July 2023
License Amendment Request to Revise ISFSI Technical Specification 4.4 to Allow Use of a Code Alternative to ASME Code, NB-5130, Examination of Weld Edge Preparation Surfaces, for the TN-40HT
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-PI-23-006, License Amendment Request to Revise Technical Specification 3.7.8 Required Actions2023-06-22022 June 2023
License Amendment Request to Revise Technical Specification 3.7.8 Required Actions
L-PI-23-016, 2022 10 CFR 50.46 LOCA Annual Report2023-06-14014 June 2023
2022 10 CFR 50.46 LOCA Annual Report
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-PI-23-010, Annual Report of Individual Monitoring2023-04-27027 April 2023
Annual Report of Individual Monitoring
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-PI-23-007, Supplement to Application to Revise Technical Specification Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)2023-03-28028 March 2023
Supplement to Application to Revise Technical Specification Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)
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-PI-23-005, CFR 50.55a Requests Nos. 1-RR-5-15 and 2-RR-5-15, Proposed Use of Subsequent ASME Code Edition and Addenda in Accordance with 10 CFR 50.55a(g)(4)(iv)2023-03-0303 March 2023
CFR 50.55a Requests Nos. 1-RR-5-15 and 2-RR-5-15, Proposed Use of Subsequent ASME Code Edition and Addenda in Accordance with 10 CFR 50.55a(g)(4)(iv)
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-PI-23-001, Day Steam Generator Tube Inspection Report2023-01-30030 January 2023
Day Steam Generator Tube Inspection Report
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-PI-22-047, Resubmittal of Prairie Island Nuclear Generating Plant (PINGP) 2018 Unit 1 180-Day Steam Generator Tube Inspection Report2022-12-21021 December 2022
Resubmittal of Prairie Island Nuclear Generating Plant (PINGP) 2018 Unit 1 180-Day Steam Generator Tube Inspection Report
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-PI-22-020, Application to Revise Technical Specification Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)2022-12-0202 December 2022
Application to Revise Technical Specification Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)
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
2024-01-02
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Text
Cornmitied to Nuclear Excellence 1 Nuclear Management Company, LLC July 3, 2007 L-HU-07-020 GL 2003-01 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Prairie Island Nuclear Generating Plant Monticello Nuclear Generating Plant Units 1 and 2 Docket No. 50-263 Dockets 50-282 and 50-306 License No. DPR-22 License Nos. DPR-42 and DPR-60 Generic Letter 2003-01, "Control Room Habitabilitv", Commitment Change
References:
- 1) NRC Issuance of Generic Letter 2003-01, Control Room Habitability, dated June 12, 2003.
- 2) NMC to NRC, Generic Letter 2003-01, Design Bases, Licensing Bases and In-leakage Testing Results for Monticello Nuclear Generating Plant, dated November 18, 2004.
- 3) NMC to NRC, Response to Generic Letter 2003-01, "Control Room Habitability" for Prairie Island Nuclear Generating Plant.
On June 12,2003, the U.S. Nuclear Regulatory Commission (NRC) issued Generic Letter (GL) 2003-01, "Control Room Habitability," requesting information on this subject (Reference 1). In response to this NRC request, NMC submitted the requested information for Monticello Nuclear Generating Plant on November 18, 2004 (L-MT-4-049) (Reference 2) and for Prairie Island Nuclear Generating Plant on December 9,2003 (L-PI-03-114) (Reference 3). As part of these responses, NMC committed to submit corresponding Technical Specification (TS) changes to incorporate a Control Room Integrity Program within 180 days from the NRC issuance of TSTF-448 for adoption.
During development of these license amendment requests (LARs), NMC identified several issues that will require additional time to allow for discussions with industry peers and NRC staff to resolve. Via this correspondence, NMC is notifying the NRC staff of a revised commitment date for the respective LAR submittals for MNGP and PINGP. The revised commitment is to submit the TSTF-448 related LARs following the guidance of the consolidated line item improvement process (CLIIP) by November 16, 2007. The revised commitment is within the timeframe typically requested (one year) for TS changes published in the Federal Register using the CLllP process. This change in commitment has been discussed with Mahesh Chawla, NRR Project Manager for PINGP, Peter Tam, Project Manager for MNGP and Bill Cartwright, NRR TSTF-448 technical reviewer.
700 First Street Hudson, Wisconsin 54016 Telephone: 715.377.3300
Document Control Desk Page 2 Summary of Commitments This letter contains one revised commitment for PlNGP and MNGP.
"NMC will submit License Amendment Requests based on TSTF-448, Rev.3 and the associated CLllP for MNGP and PlNGP by November 16,2007".
Sincerely, dward J. Weinkam Director, Nuclear Licensing and Regulatory Services Nuclear Management Company, LLC cc: Regional Administrator, USNRC Region Ill Project Manager, Monticello Nuclear Generating Plant, USNRC, NRR Resident Inspector, Monticello Nuclear Generating Plant, USNRC Project Manager, Prairie Island Nuclear generating Plant, USNRC, NRR Resident Inspector, Prairie Island Nuclear Generating Plant, USNRC
Text
Cornmitied to Nuclear Excellence 1 Nuclear Management Company, LLC July 3, 2007 L-HU-07-020 GL 2003-01 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Prairie Island Nuclear Generating Plant Monticello Nuclear Generating Plant Units 1 and 2 Docket No. 50-263 Dockets 50-282 and 50-306 License No. DPR-22 License Nos. DPR-42 and DPR-60 Generic Letter 2003-01, "Control Room Habitabilitv", Commitment Change
References:
- 1) NRC Issuance of Generic Letter 2003-01, Control Room Habitability, dated June 12, 2003.
- 2) NMC to NRC, Generic Letter 2003-01, Design Bases, Licensing Bases and In-leakage Testing Results for Monticello Nuclear Generating Plant, dated November 18, 2004.
- 3) NMC to NRC, Response to Generic Letter 2003-01, "Control Room Habitability" for Prairie Island Nuclear Generating Plant.
On June 12,2003, the U.S. Nuclear Regulatory Commission (NRC) issued Generic Letter (GL) 2003-01, "Control Room Habitability," requesting information on this subject (Reference 1). In response to this NRC request, NMC submitted the requested information for Monticello Nuclear Generating Plant on November 18, 2004 (L-MT-4-049) (Reference 2) and for Prairie Island Nuclear Generating Plant on December 9,2003 (L-PI-03-114) (Reference 3). As part of these responses, NMC committed to submit corresponding Technical Specification (TS) changes to incorporate a Control Room Integrity Program within 180 days from the NRC issuance of TSTF-448 for adoption.
During development of these license amendment requests (LARs), NMC identified several issues that will require additional time to allow for discussions with industry peers and NRC staff to resolve. Via this correspondence, NMC is notifying the NRC staff of a revised commitment date for the respective LAR submittals for MNGP and PINGP. The revised commitment is to submit the TSTF-448 related LARs following the guidance of the consolidated line item improvement process (CLIIP) by November 16, 2007. The revised commitment is within the timeframe typically requested (one year) for TS changes published in the Federal Register using the CLllP process. This change in commitment has been discussed with Mahesh Chawla, NRR Project Manager for PINGP, Peter Tam, Project Manager for MNGP and Bill Cartwright, NRR TSTF-448 technical reviewer.
700 First Street Hudson, Wisconsin 54016 Telephone: 715.377.3300
Document Control Desk Page 2 Summary of Commitments This letter contains one revised commitment for PlNGP and MNGP.
"NMC will submit License Amendment Requests based on TSTF-448, Rev.3 and the associated CLllP for MNGP and PlNGP by November 16,2007".
Sincerely, dward J. Weinkam Director, Nuclear Licensing and Regulatory Services Nuclear Management Company, LLC cc: Regional Administrator, USNRC Region Ill Project Manager, Monticello Nuclear Generating Plant, USNRC, NRR Resident Inspector, Monticello Nuclear Generating Plant, USNRC Project Manager, Prairie Island Nuclear generating Plant, USNRC, NRR Resident Inspector, Prairie Island Nuclear Generating Plant, USNRC
