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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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414 Nicollet Mall - MP4 Minneapolis, MN 55401 January 27,2009 United States Nuclear Regulatory Commission Cynthia A Carpenter, Director of the Office of Enforcement MS 04 A15A White Flint North 11555 Rockville Pike Rockville, Maryland 20852 Prairie Island Nuclear Generating Plant, Monticello Nuclear Generating Plant Units 1 and 2 Docket 50-263 Dockets 50-282, 50-306 Renewed License No. DPR-22 License Nos. DPR-42 and DPR-60 Northern States Power Companv - Minnesota Confirmation of Compliance with Confirmatow Order EA-06-178
Reference:
Letter from C. Carpenter (NRC) to D. Cooper (NMC), "Confirmatory Order (Effectively Immediately) (Office of Investigation Report No. 3-2005-01O)",
dated January 3,2007 Pursuant to the requirements contained in Section IV of the referenced Confirmatory Order ("Order") issued by the Nuclear Regulatory Commission (NRC) regarding Nuclear Management Company, LLC (NMC)(now Northern States Power Company, a Minnesota corporation (NSPM)) on January 3, 2007, this correspondence constitutes NSPM1swritten notice that it has successfully fulfilled each of the applicable requirements contained in Section IV of the Order for the above listed plants. In compliance with the instructions contained in Section Ill of the Order, the enclosure to this letter summarizes the specific actions taken by NSPM to comply with the applicable requirements in Section IV of the Order. As NSPM now only owns and operates the Monticello Nuclear Generating Plant and Prairie Island Nuclear Generating Plant, this response is therefore limited to the actions taken in regards to these two sites. The licensees of the remaining plants affected by the Order will be responsible for submitting separate responses1
Document Control Desk Page 2 Summarv of Commitments The letter makes no new commitments or revisions to existing commitments.
Michael Werner General Manager, Nuclear Oversight Northern States Power Company-Minnesota Enclosure cc: Administrator, USNRC, Region Ill USNRC NRR Project Manager, PlNGP USNRC Senior Resident Inspector, PlNGP USNRC NRR Project Manager MNGP USNRC Senior Resident Inspector, MNGP
Enclosure Section IV, ltem One (1) of the Order required that by no later than nine (9) months after the issuance of the Order, [Nuclear Management Company, LLC] NMC review, revise, and communicate to NMC employees and managers its policy relating to the writing of corrective action program (CAP) reports, and provide training to NMC employees and managers to clarify management's expectation regarding the use of the program with the goal to ensure employees are not discouraged, retaliated against, or perceived to be retaliated against, for using the CAP.
NSPM Response:
Corporate Directive 3.3, "Performance Assessment Program" was revised on I ~ a r c h8, 2007 to provide more explicit expectations on how to write corrective action process requests (CAPS).
In addition, fleet procedure FP-PA-ARP-01, "CAP Action Request Process" was revised on February 26, 2007 to include specific expectations on what should be included, and what should be avoided in the CAP description. Training for most managers and employees to clarify management's expectation regarding the use of the CAP program was completed by July 26, 2007. During validation of training records, one employee was identified as having missed the initial training and has since received the required training.
Section IV, ltem Two (2) of the Order required that by no later than June 30, 2007, NMC shall communicate its safety culture policy (including safety conscious work environment (SCWE))
to NMC employees, providing employees with the opportunity to ask questions in a live forum.
NSPM Response:
Safety Culture Meetings with most NSPM employees was completed by August 3, 2007. A small group of individuals was found to have not completed the initial training by the required due date. Those individuals received remedial training upon being identified.
Section IV, ltem Three (3) of the Order required that by no later than nine (9) months after the issuance of this Confirmatory Order, NMC shall train its employees holding supervisory positions and higher who have not had formal training on SCWE principles within the previous two years of the confirmatory order. NMC agrees to use a qualified training instructor (internal or external) for such training. NMC shall review and enhance, if necessary, its refresher SCWE training consistent with NMC's refresher training program and provide such refresher training to its employees. New employees holding supervisory positions and higher shall be trained on SCWE principles within nine (9) months of their hire dates unless within the previous two years of their hire dates, they've had the same or equivalent SCWE training.
NSPM Response:
Training for all employees and contractors at the supervisor level who had not attended a SCWE class since January 3, 2005 completed training by July 26, 2007 with the exception of one individual who was subsequently identified during the validation of training records. That individual has since completed training. The class material was presented by senior managers using material developed by an industry recognized subject matter expert. In addition, computer-based refresher training on SCWE principles was developed by May 31, 2007 and will be provided annually to employees and supervisors. Training for new supervisors and Page 1 of 3
temporary maintenance supervisors on SCWE principles has been developed and is required to be completed within six months of their hire dates.
Section IVYltem Four (4) of the Order required that by no later than March 30, 2007, NMC shall develop action plans to address significant issues identified as needing management attention in the NMC 2004 and 2006 Comprehensive Cultural Assessments at [Point Beach Nuclear Plant] PBNP; to conduct focus group interviews with Priority I& 2 organizations to understand the cause of the survey results; and to review and, as appropriate, reflect nuclear industry best practices in its conduct of focus groups and action plans to address the issues at PBNP. As part of the development of the action plans, NMC shall also assess and address any legacy issues identified in prior safety culture assessments (i.e. CAP report ,AR00510074 and Synergy Safety Culture Assessment) that impact the safety culture at PBNP. The executive summary, analysis, and contemplated action plans shall also be submitted to the NRC.
NSPM Response:
~NSPMno longer operates the Point Beach Nuclear Plant (PBNP)(now "Point Beach Nuclear Generating Station") and therefore cannot provide a response.
Section IVYltem Five (5) of the Order required that by no later than December 31, 2008, NMC shall perform another survey at PBNP comparable to the 2004 and 2006 surveys to assess trends of the safety culture at the site and the overall effectiveness of corrective actions taken in response to prior year assessments (i.e. CAP report AR00510074 and 2006 Synergy survey).
NSPM Response:
NSPM no longer operates the Point Beach Nuclear Plant (PBNP)(now "Point Beach Nuclear Generating Station") and therefore cannot provide a response.
Section IV, ltem Six (6) of the Order required that by no later than 3 months after the receipt of the next cultural survey results at PBNP, NMC shall submit the executive summary, analysis of the results, and the contemplated corrective actions to the NRC.
NSPM Response:
NSPM no longer operates the Point Beach Nuclear Plant (PBNP)(now "Point Beach Nuclear Generating Station") and therefore cannot provide a response.
Section IVYltem Seven (7) of the Order required that NMC shall continue to implement a process which ensures that adverse employment actions are in compliance with NRC employee protection regulations and principles of SCWE.
NSPM Response:
Policy CP0087, "Material Employment Action Review" was issued on July 2, 2007 that outlines the review of pending adverse employee actions against NRC employee protection regulations. This policy includes a panel consisting of the site Human Resources Manager, Legal Counsel, a representative of line management and the Site or Corporate Vice President.
This policy also extends to each project or outage contract employee upon termination (unless the contracting company's contract has been completed or because the affected individual Page 2 of 3
violated a safety policy or rule) to ensure that NRC employee protection regulations are satisfied.
Section IV, ltem Eight (8) of the Order required that in the event of the transfer of the operating license of any NMC operated facility to another entity, the commitments shall survive for the NMC fleet generally and PBNP specifically.
NSPM Response:
NSPM is committed to meeting and maintaining the obligations of this Order for the Monticello Nuclear Generating Plant and Prairie Island Nuclear Generating Plant.
Section IV, ltem Nine (9) of the Order required that by any reference to NMC employees includes all NMC employees fleet wide. The Director, Office of Enforcement, may relax or rescind, in writing, any of the above conditions upon a showing by the Licensee of good cause.
NSPM Response:
NSPM has interpreted this requirement to include all station and non-station personnel located at a site or in the corporate offices, including contractors. NSPM is not requesting relaxation or rescission of this requirement.
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