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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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414 Nicollet Mad Minneapons. Mannesota 55401 Telephone (612) 330-5500 October 12, 1982 Director, Office of Nuclear Reactor Regulation Attention: Document Control Desk U S Nuclear Regulatory Commission Washington, DC 20555 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket Nos. 50-282 License Nos. DPR-42 l
l Summary Technical Report of Analysis of Capsule from Unit No.1 Reactor Vessal Radiation Surveillance Program Submitted for your review is one copy of the report, " Analysis of Capsule P
{
from Northern States Power Company Prairie Island Unit 1 Reactor Vessel Radiation Surveillance Program", WCAP-10102, dated May,1982. This report is submitted in accordance with 10CFR50, Appendix H, Section IV.
The report notes the following:
a) The measured fast neutton fluence of 1.25E19 n/cm closely 2
matches the predicted value for the capsule of 1..T 19 n/cm.
b) The limiting material in the core region exhibited a 65'F increase in the 50 ft. :.b. trans measuredfluenceof1.25E19n/cm{tiontemperatureatthe This shift is well within the design curve prediction of Regulatory Guide 1.99.
c) The reactor pressure vessel beltline material is not very sensitive to radiation.
d) The projecteg end of life fluence at h thickness is 2.78E19 n/cm.
Please contact us if you have any questions related to this report.
M Dc.vid Musolf i
Manager of Nuclear rt Services DMM/bd cc: Regional Administrator-III, NRC NRR Project Manager, NRC NRC Resident Inspector ph G Charnoff Attachment
~ 8210190422 821012 PDR ADOCK 05000282 P
PDR
