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MONTHYEARML20004B8101981-05-22022 May 1981
Advises That Results of Westinghouse Owners Group Program Addressing Potential Reactor Vessel Integrity Concerns Will Be Provided by End of 1981.Util Will Provide Addl Detail Including Schedule for Reanalysis or Remedial Action
Project stage: Other
ML20030D6551981-08-21021 August 1981
Requests Addl Info Re Pressurized Thermal Shock to Reactor Pressure Vessels,Per Review of PWR Owners Group 810515 & Licensees 810522 Responses to NRC
Project stage: Approval
ML20030C3771981-08-21021 August 1981
Discusses Zeolite Resin Mixture for Use in Processing Reactor Bldg Sump Water.Decision on Vessel Rotation Will Be Made After Acquiring Actual Processing Experience. Breakthrough Curves for Cesium & Strontium Encl
Project stage: Request
ML20031B2141981-09-23023 September 1981
Board Notification 81-26 Re Thermal Shock to PWR Reactor Pressure Vessels
Project stage: Other
ML20031F1401981-10-0101 October 1981
Summary of 810918 Meeting W/Westinghouse Owners Group Re Pressurized Thermal Shock to Reactor Pressure Vessels. Attendance List & Handouts Encl
Project stage: Meeting
ML20069H2221982-05-31031 May 1982
Analysis of Capsule P from Northern States Power Co Prairie Island Unit 1 Reactor Vessel Radiation Surveillance Program
Project stage: Other
ML20069H2051982-10-12012 October 1982
Forwards Analysis of Capsule P from Northern States Power Co Prairie Island Unit 1 Reactor Vessel Radiation Surveillance Program
Project stage: Other
ML20137A0221986-01-10010 January 1986
Provides Projected Values of Pressurized Thermal Shock Ref Temp at Inner Vessel Surface of Reactor Vessel Beltline Matls,Per 10CFR50,Section 50.61(b)(1)
Project stage: Other
ML20202A7321986-06-23023 June 1986
Discusses Projected Values of Matl Properties for Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock (PTS) Events,Per 860110 Response to PTS Rule, 10CFR50.61.Supporting Safety Evaluation Encl
Project stage: Approval
ML20202A7531986-06-23023 June 1986
Safety Evaluation Supporting Projected Values of Matl Properties for Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events
Project stage: Approval
ML20199L4491986-06-23023 June 1986
Safety Evaluation Re Util 860110 Projected Values of Matl Properties for Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events.Response Acceptable
Project stage: Approval
ML20199L4411986-06-23023 June 1986
Forwards Safety Evaluation Re Util 860110 Projected Values of Matl Properties for Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events.Response Acceptable
Project stage: Approval
1981-09-23
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Northern States Power Company 414 Nicollet Vall
%nneapons. Minnesota 55401 Te'ephone v612) 330 5500 May 22, 1981 Director af Nuclear Reactor Regulation US Nuclear Regulatory Cocnission Washington, DC 20555 PRAIRIE ISIAND NUCLEAR GENERATING PIANT Docket Nos. 50-282 License Nos. DPR-42 50-306 DPR-60 Thermal Shock to Reactor pressure Vessels The Westinghouse Owners Group, of which Northern States Power Company is a member, has cocnitted to a program to address potential reactor vessel integrity concerns as identified in NRC Generic Letter 81-19.
That cocnittment, and the description of the program, are contained in Letter 0G-58 dated M1y 14,1981 from Robert W Jurgensen, Chairman, Westinghouse Owners Group, to D G Eisenhut, Director, Division of Licensing, USNRC.
Additionally, as described in the b y 14th letter, all Westinghouse plants including Prairie Island Units One and Two have been shown to safely sustain severe thermal shock transients, including repressurization, to beyond January, 1983 at a minimum.
Specifically, the Westinghouse Owners Group Program to be completed in December, 1981 will identify, for all operating plants as identified in the b y 14th report, if future additional plant specific analysis and/or remedial actions may be required and will provide the time in plant life when these additional actions may be needed.
Based on the results of the program, as will be provided to the NRC at the end c.f 1981, Northern States Power Company will provide additional detail including a schedule for reanalysis and/or remedial action if required and the basis for this reanalysis and remedial action.
t L 0 & yer, PE
& nager of Nuclear Support Services LOM/DMM/dm cc: J G Keppler G Charnoff NRC Resident Inspector si es 010076
