Letter Sequence Other |
|---|
|
Results
Other: ML13310A751, ML13310A779, ML13310A780, ML13310B398, ML13310B608, ML13317A291, ML13317A428, ML13317A480, ML13317B022, ML13317B078, ML13324A480, ML13324A499, ML13324A528, ML13324A563, ML13324A573, ML13324A584, ML13330A455, ML13333B119, ML13333B121, ML14079A132, ML20197H540, ML20199E827
|
MONTHYEARML14135A2501982-01-12012 January 1982
Forwards Safety Evaluation of SEP Topic VI-3, Containment Pressure & Heat Removal Capability & VI-2.D, Mass & Energy Release for Possible Pipe Break Inside Containment for Facility.Licensee Analysis Acceptable
Project stage: Approval
ML13317B0231982-03-0808 March 1982
Advises That Review of Addl Info Re Environ Qualification of Equipment for Nuclear Power Plants Indicates Enough Detailed Info Has Been Received to Support Justification for Interim Safe Operation.Review Ongoing
Project stage: Approval
ML13317B0221982-03-10010 March 1982
Submits Addl Info Re Environ Qualification Program Beta Radiation Analysis on Equipment Other than Exposed Cable Inside Containment,Per 820201 Request
Project stage: Other
ML13317B0781982-04-0707 April 1982
Advises That Addl Info Per NRC 820223 Request Re Environ Qualification of Equipment Installed as Part of TMI Requirements Will Not Be Submitted Until 820423
Project stage: Other
ML14079A1321982-06-28028 June 1982
Review of Licensees Resolution of Nonproprietary Version of Outstanding Issues from NRC Equipment Environ Qualification SERs (F-11,B-60), Technical Evaluation Rept
Project stage: Other
ML13317A2911982-08-23023 August 1982
Provides Addl Info to Re Beta Radiation Assessment & Environ Qualification of Electrical Equipment. Exposed Cables Are Only Equipment Inside Containment Which Do Not Have Metal Encls
Project stage: Other
ML13317A4281982-11-18018 November 1982
Informs That Peak Temp & Pressure for Main Steam Line Break Inside Containment Recalculated at 391.5 F & 53.3 Psig Per App B of NUREG-0588.Peak Conditions Will Never Be Less Severe than LOCA post-accident Temp & Pressure
Project stage: Other
ML13310A7491982-11-30030 November 1982
Forwards Proprietary & Nonproprietary Review of Licensees Resolution of Outstanding Issues from NRC Equipment Environ Qualification SERs (F-11,B-60). Proprietary Rept Withheld (Ref 10CFR2.790)
Project stage: Approval
ML13310A7511982-11-30030 November 1982
SER Re Environ Qualification of safety-related Electric Equipment.Licensee Must Provide Plans for Qualification or Replacement of Unqualified Equipment & Schedule for Accomplishing Proposed Corrective Action
Project stage: Other
ML13317A4801983-01-18018 January 1983
Discusses Status of Environ Qualification of safety-related Electrical Equipment.Justification for Continued Operation for Auxiliary Feedwater Flow Transmitters & Radiation Monitors Provided,Per NUREG-0737
Project stage: Other
ML13310A7791983-05-20020 May 1983
Provides Status of Actions Requested in 830401 Clarification of 821120 SER on Environ Qualification of safety-related Electrical Equipment. Equipment Environ Qualification, Technical Evaluation Rept No Longer Considered Proprietary
Project stage: Other
ML13310A7801983-05-20020 May 1983
Discusses Status of Activities on Environ Qualification of safety-related Equipment,In Response to 10CFR50.49(g).Review of nonsafety-related Equipment Under 10CFR50.49(b)(2) Planned
Project stage: Other
ML13333B9961984-01-17017 January 1984
Summary of 831220 Meeting W/Util & Impell Corp in Bethesda, MD Re Outstanding Environ Qualification Issues
Project stage: Meeting
ML13310B3981984-05-0909 May 1984
Requests Addl Info Re Environ Qualification of Equipment Important to Safety,Including All Applicable Justifications for Continued Operation.Response Requested by 840615
Project stage: Other
ML13310B6081984-07-30030 July 1984
Requests Extension of Environ Qualification of Electrical Equipment to 851130,per 10CFR50.49(g) & Forwards Nucon Inc Repts, Plant Risk Impact Evaluation of Certain Electrical Equipment & Evaluation of Core Damage Risk..
Project stage: Other
ML13333B1211984-07-31031 July 1984
Evaluation of Core Damage Risk Reduction Associated W/ Seismic Mods at San Onofre Nuclear Generating Station,Unit 1, Executive Summary
Project stage: Other
ML13333B1191984-07-31031 July 1984
Plant Risk Impact Evaluation of Certain Electrical Equipment
Project stage: Other
ML13333B1501984-09-24024 September 1984
Notification of 841002-04 Meetings W/Util Onsite in San Diego County,Ca to Review Records on Environ Qualification of Electrical Equipment
Project stage: Meeting
ML13324A4681984-11-0303 November 1984
Forwards Rev 1 to Hot Safe Shutdown Sys Interaction Review, Per 841019 Request for Addl Info to Complete SER for Restart
Project stage: Request
ML13324A4801984-11-0303 November 1984
Forwards Justification for Continued Operation of Equipment Requiring Environ Qualification,As Part of Efforts to Return Unit 1 to Svc
Project stage: Other
ML13324A4861984-11-0808 November 1984
Summary of 841026 Meeting W/Util in Bethesda,Md Re Environ Qualification of Electrical Equipment Audit Held on 841002-04.List of Attendees Encl
Project stage: Meeting
ML13324A4891984-11-0909 November 1984
Forwards Results of NRC & Inel 841002-04 Audit of Environ Qualification of Electrical Equipment.Revised Justification for Continued Operation for Electrical Equipment Discussed at 841026 Meeting Acceptable
Project stage: Meeting
ML13324A4991984-11-19019 November 1984
Informs of Completion of Environ Qualification of Listed Electrical Equipment,Including Reactor Coolant Temp Detectors & Containment Hydrogen Monitors.Qualification Packages for Equipment Will Be Completed by 850331
Project stage: Other
ML13324A4981984-11-19019 November 1984
Documents Results of 831220 Meeting W/Nrc in Bethesda,Md Re Environ Qualification of safety-related Electrical Equipment.Addl Info Re Environ Qualification Program Encl, Per 840509 Request
Project stage: Meeting
ML13330A4551984-11-26026 November 1984
Grants Extension of Deadline Until 851130 for Installation of Environmentally Qualified Replacement Equipment Important to Safety
Project stage: Other
ML13324A5281984-12-21021 December 1984
Requests Extension for Environ Qualification of Addl Equipment Items Until 851130.Operation of Facility W/Listed Unqualified Equipment Not Risk to Public Health & Safety. Justifications for Continued Operation Encl
Project stage: Other
ML13331A7781985-01-16016 January 1985
Requests Payment of Fee for Review of 841221 Application for Extension of Deadline for Environ Qualification of Certain Electrical Equipment
Project stage: Approval
ML13330A1741985-02-20020 February 1985
Forwards Payment of Fee for 841221 Request for Extension of Environ Qualification Deadline for Certain Equipment Items. Fee Paid
Project stage: Request
ML13324A5631985-02-26026 February 1985
Submits Certification of Compliance Re Environ Qualification of Electrical Equipment Per 10CFR50.49.Environ Qualification of All Equipment Will Be Completed by 850331
Project stage: Other
ML13324A5731985-03-15015 March 1985
Requests Extension Until 851130 for Environ Qualification Documentation Re Westinghouse Motors for Feedwater Pumps & Paul Monroe Actuators Installed on Valves in Containment Isolation,Spray Sys & Recirculation Sys
Project stage: Other
ML13324A5841985-03-27027 March 1985
Advises That Util 850315 Request for Extension of Deadline for Environ Qualification of Equipment to 851130 Granted. Request Deemed Timely,Per 10CFR50.49.Good Cause Demonstrated
Project stage: Other
ML13317B4951986-04-0202 April 1986
Forwards Rev 2 to Vols I & II of San Onofre Nuclear Generating Station,Unit 1,Evaluation of Refueling Water Storage Tank..., Updating Seismic Reevaluation of Tank,Per SEP Topic III-6, Seismic Design Considerations
Project stage: Request
ML20197H5401986-05-0909 May 1986
Responds to NRC Re Violations Noted in Insp Repts 50-206/85-30,50-361/85-29 & 50-362/85-28.Corrective Actions: Environ Qualification Document Packages Revised Re Cable Insulation,Solenoid Valves & Honeywell Transducers
Project stage: Other
ML20199E8271986-05-0909 May 1986
Responds to NRC Re Violations Noted in Insp Repts 50-206/85-30,50-361/85-29 & 50-362/85-28.Corrective Actions: Environ Qualification Packages Will Be Revised to Include Addl Mfg Info Re Galite & Prestolite Processes
Project stage: Other
1984-11-03
[Table View] |
Text
A0 Southern California Edison Company P. 0. BOX 800 2244 WALNUT GROVE AVENUE ROSEMEAD, CALIFORNIA 91770 K. P. BASKIN November 18, 1982 TELEPHONE MANAGER OF NUCLEAR ENGINEERING, (213) 572-1401 SAFETY, AND LICENSING Director of Nuclear Reactor Regulation Attention:
D. M. Crutchfield, Chief Operating Reactors Branch No. 5 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Gentlemen:
Subject:
Docket No. 50-206 Environmental Qualification San Onofre Nuclear Generating Station Unit 1 By letter dated March 6, 1981 the NRC was provided with the MSLB pressure and temperature analysis inside the San Onofre Unit 1 containment.
That analysis indicated a peak temperature and pressure of 406 0F and 53.0 psig. The NRC staff's assessment of SEP Topics VI-2.D, Mass and Energy Release for Possible Pipe Break Inside Containment, and VI-3, Containment Pressure and Heat Removal Capability, included these values and concluded that the MSLB temperature profile was acceptable for use in equipment qualification.
This letter is to inform you that the peak temperature and pressure for the MSLB inside containment has been recalculated.
The analysis utilized an 8% revaporization of condensate in a superheated atmosphere. This was done in accordance with Appendix B of NUREG-0588, Interim Staff Position on Environmental Qualification of Safety Related Electrical Equipment. The results of the analysis indicate a peak temperature and pressure of 391.50F and 53.3 psig.
In our June 30, 1982 letter, we demonstrated that the LOCA post-accident temperature and pressure was more severe than the MSLB conditions. For a large break MSLB inside containment, we calculated the equipment surface temperature utilizing the assumption of wet steam and the peak surface temperatures were less than the LOCA peak temperature. In addition, analyses were done assuming smaller breaks for the MSLB inside containment based on a mechanistic fracture evaluation and this more credible break for a main steam pipe resulted in a peak temperature less than the LOCA peak temperature.
Based on the analyses provided in our June 30, 1982 letter, we indicated that the LOCA conditions would continue to be utilized for the qualification of original equipment identified in our October 31, 1980 letter and equipment installed as part of TMI modifications. In addition, as 8211240252 821118 PDR ADOCK 05000206 f
P PDR
09 Mr. D.
November 18, 1982 indicated in our June 30, 1982 letter, all new equipment will be qualified utilizing the peak MSLB conditions of 391.5 0F and 53.3 psig unless such equipment is unavailable in which case a surface temperature analysis will be performed to determine the peak conditions to be utilized for qualification.
However, in no case will the peak conditions be less severe than the LOCA post-accident temperature and pressure.
Very truly yours,
