Letter Sequence Supplement |
---|
|
|
|
|
---|
Category:Letter
MONTHYEARIR 05000282/20230042024-02-0101 February 2024 Integrated Inspection Report 05000282/2023004 and 05000306/2023004 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 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-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-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 IR 07200010/20234012023-12-20020 December 2023 Independent Spent Fuel Storage Installation Security Inspection Report 07200010/2023401 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 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 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 ML23319A3182023-11-15015 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation 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 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 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 ML23262B0372023-09-19019 September 2023 Response to NRC Request for Additional Information Regarding the 2023 Monticello and Prairie Island Plant Decommissioning Funding Status Reports 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 L-PI-23-023, Baffle Former Bolts Alternate Aging Management Strategy2023-09-11011 September 2023 Baffle Former Bolts Alternate Aging Management Strategy IR 05000282/20230052023-08-30030 August 2023 Updated Inspected Plan for Prairie Island Nuclear Generating Plant Report 05000282/2023005 and 05000306/2023005 IR 05000282/20230102023-08-17017 August 2023 NRC Inspection Report 05000282/2023010 and 05000306/2023010 ML23222A0122023-08-10010 August 2023 Independent Spent Fuel Storage Installation and Monticello Nuclear Generating Plant - Changes in Foreign Ownership, Control or Influence IR 05000282/20230022023-08-0303 August 2023 Integrated Inspection Report 05000282/2023002 and 05000306/2023002 ML23214A2032023-08-0202 August 2023 Request for Information for an NRC Quadrennial Comprehensive Engineering Team Inspection: Inspection Report 05000282/2024010; 05000306/2024010 ML23206A2342023-07-25025 July 2023 Independent Spent Fuel Storage Installation, and Monticello Nuclear Generating Plant, Changes in Foreign Ownership, Control or Influence ML23202A0032023-07-21021 July 2023 Independent Spent Fuel and Independent Spent Fuel Storage Installation, Monticello Nuclear Generating Plant, Submittal of Quality Assurance Topical Report (NSPM-1) ML23199A0922023-07-18018 July 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000306/2023004 ML23195A1732023-07-14014 July 2023 Revision of Standard Practice Procedures Plan 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 ML23181A0192023-06-30030 June 2023 Independent Spent Fuel Storage Installation, Revision to Correspondence Service List for Northern States Power - Minnesota ML23178A2422023-06-28028 June 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III 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 IR 05000282/20234202023-06-0101 June 2023 Security Baseline Inspection Report 05000282/2023420 and 05000306/2023420 ML23150A1722023-05-30030 May 2023 Preparation and Scheduling of Operator Licensing Examinations 2024-02-01
[Table view] |
Text
Xcel Energy FEB 0 4 2015 U S Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Prairie Island Nuclear Generating Plant Units 1 and 2 Dockets 50-282 and 50-306 Renewed License Nos. DPR-42 and DPR-60 L-PI-15-0018 10 CFR 50.55a Supplement to 10 CFR 50.55a Requests (RR) 1-RR-5-7 and 2-RR-5-7 (TAGs MF4843 and MF4844) Associated with Prairie Island Nuclear Generating Plant (PINGP) Fifth Ten-Year lntervallnservice Inspection (lSI) Program By letter dated September 15, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 14258A124), Northern States Power Company, a Minnesota corporation, doing business as Xcel Energy (hereafter "NSPM"), submitted for NRC approval10 CFR 50.55a Requests 1-RR-5-7 and 2-RR-5-7 associated with the fifth ten-year interval for the Prairie Island Nuclear Generating Plant (PINGP), Units 1 and 2, lnservice Inspection (lSI) Program. By email dated January 26, 2015 (ML 15030A008), the NRC requested additional information (RAis) to complete the review of these requests.
The enclosure to this letter provides the responses to the NRC Staff RAis for 1-RR-5-7 and 2-RR-5-7.
If there are any questions or if additional information is needed, please contact Mr. Dale Vincent, P.E., at 651-267-1736.
Summary of Commitments This letter contains no new commitments and no revisions to existing commitments.
?t-'
Kevin Davison Site Vice President, Prairie Island Nuclear Generating Plant Northern States Power Company -Minnesota Enclosures (1) 1717 Wakonade Drive East
651.388.1121 Document Control Desk Page 2 cc: Administrator, Region Ill, USNRC Project Manager, PINGP, USNRC Resident Inspector, PINGP, USNRC Enclosure Supplement to 10 CFR 50.55a Requests (RR) 1-RR-5-7 and 2-RR-5-7 Associated with Prairie Island Nuclear Generating Plant (PINGP) Fifth Ten-Year Interval lnservice Inspection (lSI) Program By letter dated September 15, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 14258A124), Northern States Power Company, a Minnesota corporation, doing business as Xcel Energy (hereafter "NSPM"), submitted for NRC approval10 CFR 50.55a Requests 1-RR-5-7 and 2-RR-5-7 associated with the fifth ten-year interval for the Prairie Island Nuclear Generating Plant (PINGP), Units 1 and 2, lnservice Inspection (lSI) Program. By email dated January 26, 2015 (ML 15030A008), the NRC requested additional information (RAis) to complete the review of these requests.
Responses to these RAis are provided below. NRC RAI1: In the relief request, NSPM states that the bare metal visual examination (VE) for Unit 1 was scheduled for the upcoming Unit 1 refueling outage (1 R29 refueling outage) scheduled to commence in October 2014. Please provide a discussion of the examination results. NSPM response:
A direct visual examination of the Unit 1 reactor vessel head, including the outer surface and 1 00% of the intersection of each nozzle with the head, was performed in accordance with American Society of Mechanical Engineers (ASME) Code Case N-729-1 on October 15, 2014. The examination showed no indications.
However, items to note for future examinations are as follows. There are three rust stains near penetrations 2 to 18, 3 to 19, and 4 to 20. (Only one stain was noted in refueling outage 1R27.) These stains are likely due to water that had dripped onto the head, ran down the head, contacted a penetration, and continued to run down the head. The stains do not show residual boric acid and have no volume. A white mark near the head vent nozzle documented in refueling outage 1 R27 was not observed in refueling outage 1 R29. There is a minimal amount of small debris near the top of the head. The head shows light scattered surface rust typical of unpainted low alloy steel. The surface rust has not noticeably changed since refueling outage 1 R27. None of these items is considered adverse to quality. Page 1 of2 Enclosure-10CFR50.55a Request 1/2-RR-5-7 Supplement NRC RAI2: In Section 6 of the enclosure to the relief request, NSPM states that relief is requested for the duration of the fifth inservice inspection (lSI) interval for PINGP Units 1 and 2. The fifth lSI interval is effective for Units 1 and 2 from December 21, 2014, through December 20, 2024. In Section 5 of the enclosure, NSPM states that this request would extend Unit 2 examinations, currently scheduled for the fall of 2015, to 2025. The Unit 1 examinations would be extended from the fall of 2016 to 2026. The 20 nominal year request would, therefore, fall outside of the fifth lSI interval.
Please provide clarification for the specified duration of the proposed alternative.
NSPM Response:
The intent of the proposed alternative was to request a nominal 20 year inspection interval for each reactor vessel head from the time each head was placed in service as an alternative to the nominal 10 year inspection interval required by ASME Code Case N-729-1. Pursuant to a phone call between the NRC and NSPM on January 29, 2015, NSPM revises the duration of 10 CFR 50.55a Requests 1RR-5-7 and 2-RR-5-7 to a nominal15 year inspection interval from the time each head was placed in service. The duration of the proposed alternative is enveloped by lSI fifth interval.
The fifth lSI interval is effective for Units 1 and 2 from December 21, 2014 through December 20, 2024. The corresponding vessel head examinations are projected to be performed fall of 2019 for Unit 2 and fall of 2020 for Unit 1. In no case would reactor vessel head examinations of either unit be started after December 20, 2020. Page 2 of2