Letter Sequence Other |
|---|
CAC:MD5983, Changes to Reflect Revision of 10 CFR 50.55A (Open) CAC:MD5984, Changes to Reflect Revision of 10 CFR 50.55A (Open) |
|
|
|
|---|
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
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 21, 2016 Mr. Scott D. Northard Acting Site Vice President Prairie Island Nuclear Generating Plant Northern States Power Company - Minnesota 1717 Wakonade Drive East Welch, MN 55089
SUBJECT:
PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 -
CORRECTION LETTER FOR AMENDMENTS 185 AND 175 TO RENEWED FACILITY OPERATING LICENSES (CAC NOS. MD5983 AND MD5984)
Dear Mr. Davison:
On June 27, 2008, the U.S. Nuclear Regulatory Commission (NRC or the Commission) issued Amendment No. 185 to Renewed Facility Operating License No. DPR-42 and Amendment No. 175 to Renewed Facility Operating License No. DPR-60 for the Prairie Island Nuclear Generating Plant, Units 1 and 2, respectively (Agencywide Documents Access and Management System (ADAMS) Accession No. ML081650272). The amendments consisted of changes to the technical specification (TSs) regarding incorporation of Technical Specification Task Force (TSTF) industry travelers TSTF-479, -485, and -497.
The amendments revised the wording for TS 5.5.7, "lnservice Testing Program," on page 5.0-12. The amendments did not revise any wording for the TSs on page 5.0-11; however, in the course of issuing the revised TS pages, the word "year" was inadvertently removed from the last sentence in TS 5.5.6, "Reactor Coolant Pump Flywheel Inspection Program," on page 5.0-11: " ... of exposed surfaces of the removed flywheels may be conducted at 20 year intervals."
This letter corrects Amendment Nos. 185 and 175 to restore TS 5.5.6 to the wording as approved in Amendment Nos. 170 and 160 when the inspection interval for TS 5.5.6, "Reactor Coolant Pump Flywheel Inspection Program," was increased from 10 years to 20 years (ADAMS Accession No. ML051510045).
The NRC staff concludes that the error was introduced during the preparation of the license amendments and is entirely editorial in nature. The proposed correction does not change any of the conclusions in the safety evaluation associated with the amendments referenced above and does not affect the associated notices to the public. Enclosed, please find the corrected replacement page.
K. Davison If you have any questions regarding this matter, please call me at (301) 415-3733.
Sincerely, Robert F. Kuntz, nior Project Manager Plant Licensin ranch 111-1 Division of erating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-282 and 50-306
Enclosure:
Corrected Page to Amendment No. 185 to DPR-42 and Amendment No. 175 to DPR-60 cc w/encl: Distribution via ListServ
ENCLOSURE PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 DOCKET NOS. 50-282 AND 50-306 CORRECTED PAGE TO LICENSE AMENDMENT NOS. 185 AND 175 RENEWED FACILITY OPERATING LICENSE NO. DPR-42 RENEWED FACILITY OPERATING LICENSE NO. DPR-60
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.4 Radioactive Effluent Controls Program (continued)
J. Limitations on the annual dose or dose commitment to any member of the public, beyond the site boundary, due to releases of radioactivity and to radiation from uranium fuel cycle sources, conforming to 40 CFR 190.
The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Radioactive Effluent Controls Program surveillance frequency.
5.5.5 Component Cyclic or Transient Limit This program provides controls to track the USAR, Section 4.1.4, cyclic and transient occurrences to ensure that components are maintained within the design limits.
5.5.6 Reactor Coolant Pump Flywheel Inspection Program This program shall provide for the inspection of each reactor coolant pump flywheel per the recommendations of Regulatory Position C.4.b of Regulatory Guide 1.14, Revision 1, August 1975. In lieu of Position C.4.b(l) and C.4.b(2), a qualified in-place UT examination over the volume from the inner bore of the flywheel to the circle one-half of the outer radius or a surface examination (MT or PT) of exposed surfaces of the removed flywheels may be conducted at 20 year intervals.
5.5.7 Inservice Testing Program This program provides controls for inservice testing of ASME Code Class 1, 2, and 3 components. The program shall include the following:
Prairie Island Unit 1 - Amendment No.~ -l-1Q 185 Units 1 and 2 5.0-11 Unit 2 - Amendment No . .f.49-1-e-O 175 Corrected by letter dated June 21, 2016
ML16148A179 OFFICE DORULPL3-1 /PM DORULPL3-1 /LA DORULPL3-1 /BC DORULPL3-1 /PM NAME RKuntz SRohrer DWrona RKuntz DATE 5/31/16 5/31/16 6/21/16 6/21/16
