Letter Sequence Other |
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Results
Other: ML13310A751, ML13310A779, ML13310A780, ML13310B398, ML13310B608, ML13317A291, ML13317A428, ML13317A480, ML13317B022, ML13317B078, ML13324A480, ML13324A499, ML13324A528, ML13324A563, ML13324A573, ML13324A584, ML13330A455, ML13333B119, ML13333B121, ML14079A132, ML20197H540, ML20199E827
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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
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Text
Southern California Edison Company P. 0.
BOX 800 2244 WALNUT GROVE AVENUE ROSEMEAD, CALIFORNIA 91770 M. 0. MEDFORD TELEPHONE MANAGER, NUCLEAR LICENSING March 15, 1985 (818) 302-1749 Director of Nuclear Reactor Regulation Attention: J. A. Zwolinski, 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 As part of the Environmental Qualification Program for San Onofre Unit 1, we have been developing the qualification packages for that equipment which is considered qualifiable. As indicated in our February 26, 1985 letter to the NRC, the packages will be completed by March 31, 1985, the 10 CFR 50.49 environmental qualification deadline. All the remaining equipment which can not presently be shown qualifiable will be replaced or qualified by the November 30, 1985 extension deadline or the plant will be shutdown.
The purpose of this letter is to identify additional items in the environmental qualification program which will require an extension in accordance with 10 CFR 50.49(g).
As a result of obtaining the qualification documentation for these items, it was determined that due to extenuating circumstances, additional time would be required to complete the documentation packages.
Details regarding the circumstances are provided below.
The feedwater pumps at San Onofre Unit 1 are utilized for feedwater and safety injection service. These pumps are driven by Westinghouse motors.
In our efforts to complete the qualification of the motors, Westinghouse has been unable to identify a test report which applies to the pump motors.
Westinghouse can correlate the materials of the motors to the materials of
,0 motors which have been tested.
Such a correlation can be used as a basis for qualification of the feedwater pump motors. The Westinghouse schedule for "oa completing this work is estimated at 6 months which is approximately 00 September, 1985.
Depending on the results of the Westinghouse work it will o
take two to eight weeks to develop a qualification documentation package for the Westinghouse motors. Therefore an extension of the qualification deadline rc of the motors to November 30, 1985 is requested.
Paul Munroe actuators are installed on valves in the Containment Isolation System, Containment Spray System and the Recirculation System. The U-)
test report which is being utilized as the basis for qualification of the GO-O..
actuators is for a similar Paul Munroe actuator. It has been determined that the test reports do not directly apply to the actuators designed and installed at San Onofre Unit 1. Paul Munroe is developing a correlation for the
Mr. J. A. Zwolinski
-2 similarity between the installed actuators and the tested actuator such that the test report will also apply to the installed actuators. The schedule for completion of this effort is the end of March 1985. Depending on the results of the correlation it will then take two to eight weeks to develop the qualification documentalon package for the Paul Munroe actuators.
It is therefore anticipated that following the completion of the Paul Munroe correlation the qualification package for the Paul Munroe actuators will be developed and completed prior to November 30, 1985. However, an extension to November 30, 1985 is requested in view of the uncertainty associated with the qualification documentation and to maintain consistency.
In both of the above cases, the justifications for continued operation have been reviewed and modified as necessary. These justifications have been developed in accordance with 10 CFR 50.49(1) and are provided here as an enclosure. They were previously provided to the NRC staff by letter dated November 3, 1984.
If you have any questions regarding this matter, please let me know.
Very truly yours, Enclosures cc: F. R. Huey
Plant Tag No.:
G3A,B Functional Name:
Pump Motors Manufacturer:
Westinghouse Model Number:
CS Type Functional
Description:
These motors service the feedwater pumps and are located outside the containment, under the turbine building on opposite sides of the building.
The pumps are utilized in the safety injection system to provide borated water to the reactor vessel.
Qualification Status:
Qualified, documentation evaluation is in progress.
Justification for Continued Operation:
Westinghouse motors containing similar materials have been tested under simulated accident conditions. Westinghouse will be developing the correlation between the motors materials and the motors tested by Westinghouse with similar materials. These motors are located outside containment (Areas 5, 6) and it is anticipated that all required accident conditions will be enveloped by testing. These components will be considered fully qualified when formal documentation of the plant specific evaluation is completed.
Documentation is scheduled to be completed prior to November 30, 1985.
Until the documentation is completed for the motors, in the event of a high energy line break in the vicinity of one of the motors, the environment will not affect the other motor. This is due to the fact the motors are located on opposite ends of the turbine building. The ECCS analysis for the plant relies on one feedwater pump operating therefore, the ability to provide core cooling is not affected.
This JCO complies with the criteria set forth in 10 CFR 50.49(1)(2) and (5) and ensures that SONGS 1 can be safely operated pending qualification of the pump motors.
Plant Tag No.:
CV515, 516, 517, 518, 525, 526, 527, 528, 737A, 737B Functional Name:
Hydraulic Rotary Valve Operators Manufacturer:
Paul Munroe Model Number:
PD89423, PD89425, P089426 Functional
Description:
These valve operators are located inside and outside containment on valves in systems which require operation following an accident.
Qualification Status:
Qualified, documentation evaluation is in progress.
Justification for Continued Operation:
Paul Munroe qualification test report No. PA87604 has been provided by the vendor as applicable to the installed valve operators.
Paul Munroe is developing a correlation between the tested valve operators and the installed operators.
The test sequence includes normal thermal aging and operating degradation in excess of requirements, based on the manufacturers recommended minimum maintenance schedules.
The test documents a gamma radiation accident exposure of 8.7x10 7 Rads following a minimum normal operation exposure of 1.25x10 7 Rads.
LOCA testing provides a peak temperature and pressure of 350aF and 66 psig, and dwell times that exceed the postulated accident requirements including margins. During LOCA testing, the test specimens were exposed to a chemical spray solution of pH 9.5 which is more severe than the required condition. Functional testing conducted throughout each sequence of the testing provides assurance of operability. These components will be considered fully qualified when formal documentation of the plant specific evaluation is completed.
Documentation is scheduled to be completed prior to November 30, 1985.
This JCO complies with the criteria set forth in 10CFR5O.49(i)(2) and ensures that SONGS-1 can be safely operated pending completion of the qualification documentation.