Letter Sequence Request |
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Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance...
Results
Other: ML13317A118, ML13317A130, ML13317A340, ML13317A420, ML13317A423, ML13317A483, ML13317A615, ML13317A681, ML13317A725, ML13317B114, ML13317B116, ML13333B737, ML14133A353
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MONTHYEARML13302B0031981-03-0606 March 1981 Notification of 810309 Meeting W/Util in Bethesda,Md to Discuss Facility Emergency Plan Project stage: Request ML13303A4651981-05-14014 May 1981 Forwards Fes.W/O Encl Project stage: Request ML13317A6151981-05-18018 May 1981 Fulfills Commitment Made in Response to NRC 810331 Request Re Vessel Integrity & Responds Further to NRC 810429 Requests & Clarifications Re Reactor Vessel Pressurized Thermal Shock Issue.Discusses Proposed Program Project stage: Other ML14133A3531981-05-22022 May 1981 Discusses Commitment to Develop Program Re Potential Reactor Vessel Integrity Concerns Identified in NRC . Program Will Identify Whether Future Addl Plant Specific Analyses &/Or Remedial Actions Will Be Required Project stage: Other IR 05000206/19810161981-05-22022 May 1981 IE Insp Rept 50-206/81-16 on 810512-15.No Noncompliance Noted.Major Areas Inspected:Welding Activities Associated W/Mods to Auxiliary Feedwater Sys & Repair of Circumferential Welds on Main Steam Piping Project stage: Request ML13317A6591981-06-0202 June 1981 Safety Evaluation Re Environ Qualification of safety-related Electrical Equipment Finding No Outstanding Items That Require Immediate Corrective Action.Deficient Items Replaced.Equipment Qualified for Low Probability Events Project stage: Request ML20030A7701981-07-20020 July 1981 Notification of 810728,29 & 30 Meetings W/B&W,Westinghouse & C-E Owners Groups in Bethesda,Md to Discuss Thermal Shock to Reactor Pressure Vessel Issue Project stage: Meeting ML13330A3941981-08-21021 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 IR 05000361/19810171981-08-21021 August 1981 IE Insp Rept 50-361/81-17 on 810715-31.No Noncompliance Noted.Major Areas Inspected:Preoperational Test Program & Procedures,Maint,Plant Tours & Licensee Action on Previously Identified Items Project stage: Request 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 ML13317A6811981-10-0505 October 1981 Responds to Requesting Addl Action Re Pressurized Thermal Shock to Reactor Pressure vessels.Sixty-day Response Schedule Cannot Be Met.Partial Response Will Be Provided by 811104 Project stage: Other ML13317A7251981-10-23023 October 1981 Discusses Proposed Response to NRC 810821 Request Re Pressurized Thermal Shock to Reactor Pressure Vessels. Requests Available Portions of Response at Time Provided in ,To Avoid Needless Conservatisms Project stage: Other ML13323A2601981-10-31031 October 1981 Operating Instructions for SSH-3/FBA-13 Seismic Scram & Trip Sys Project stage: Request ML13317A7201981-11-0404 November 1981 Forwards Partial Response to NRC 810821 Request for Addl Info Re Pressurized Thermal Shock to Reactor Pressure Vessels Per Project stage: Request ML13309A0791981-11-0404 November 1981 Forwards Responses to Safety Evaluation of Environ Qualification of safety-related Electrical Equipment,Addl Info Not Addressed in Safety Evaluation & Revised Pages to Project stage: Request ML13317A8361982-01-25025 January 1982 Forwards Util 150-day Response to 810821 Request for Addl Info Re Pressurizer Thermal shock.Plant-specific Analyses Indicate That Vessel Integrity Will Be Maintained,Therefore Remedial Actions Not Warranted Project stage: Request ML13310A3761982-01-26026 January 1982 Forwards Amend 28 to Fsar,Reissuing Facility Emergency Plan & Offsite Emergency Response Plans (Filed in PDR Category K), & Amend 10 to Fire Hazards Analysis (Filed in Category F) Project stage: Request ML13333B8091982-03-0808 March 1982 Summary of 820224 Meeting W/Westinghouse Owners Group, Southern CA Edison,Cp&L & Fl Power & Light in Bethesda,Md Re Pressurized Thermal Shock Project stage: Meeting IR 05000361/19820101982-03-15015 March 1982 IE Insp Rept 50-361/82-10 on 820119-0212.No Noncompliance Noted.Major Areas Inspected:Preoperational Test Program,Tmi Mods,Followup on IE Bulletin 80-06,safety Committee Activities & Independent Insp Effort Project stage: Request ML13310A7011982-03-15015 March 1982 Forwards Request for Addl Info Re Pressurized Thermal Shock.Info Should Be Submitted by 820430 Project stage: RAI ML13317B1141982-04-15015 April 1982 Forwards NRC Staff Audit of Robinson 2 Procedures & Training for Pressurized Thermal Shock, Conducted During 820405-07 Site Visit.Control Room Emergency Procedures Weighted Toward Core Cooling Project stage: Other ML13317B1161982-04-15015 April 1982 NRC Staff Audit of Robinson 2 Procedures & Training for Pressurized Thermal Shock Project stage: Other ML13317B1111982-04-22022 April 1982 Forwards NRC Task Force on Pressurized Thermal Shock Audit Rept Re Adequacy of Robinson 2 in-plant Training Programs & Operating Procedures.Similar Audit Will Be Performed at San Onofre 1 in Near Future Project stage: Approval ML13317B1101982-04-27027 April 1982 Advises That Response to NRC 820407 Request for Info Re Emergency Procedures Upgrade Will Be Deferred Until Wk of 820517.Reanalysis of Large Number of Transients Required for plant-specific Guidelines Necessitates Deferral Project stage: Request ML13317A1181982-05-0303 May 1982 Advises That Addl Info Requested 820315 for Pressurized Thermal Shock Will Be Provided by 820515 Project stage: Other ML13317A1241982-05-26026 May 1982 Forwards Partial Response to 820315 Request for Addl Info Re Pressurized Thermal Shock Issue.Other Responses to Be Included in Westinghouse Owners Group Submittals on 820528 & in June 1982 Project stage: Request ML13317A1301982-06-0101 June 1982 Informs That Audit on Pressurized Thermal Shock Will Be Conducted During Wk of 820614,per .Audit Will Review Completion of Revised Operator Training Procedures Project stage: Other ML13317A1951982-06-18018 June 1982 Forwards Corrections to 820526 Response to NRC Request for Addl Info Re Pressurized Thermal Shock.Corrected Pages Indicating 14X14 Core Design & Correct Vol Fractions Encl. Changes Do Not Affect Analysis or Conclusions of Submittal Project stage: Request ML13333B7371982-07-12012 July 1982 Trip Rept of 820603-04 Site Visit to Evaluate Emergency Procedures & Operator Training Re Pressurized Thermal Shock. Procedures Revised Based on Westinghouse Owners Group Guidelines on plan-specific Analyses Project stage: Other ML13317A3401982-09-20020 September 1982 Forwards Rept for 820603-04 Audit of Operator Training & Emergency Procedures Re Pressurized Thermal Shock.Response Addressing Action Being Taken Re Section 5 Recommendations Requested within 45 Days of Ltr Receipt Project stage: Other ML13317A4231982-10-15015 October 1982 To Operator Requalification Re Pressurized Thermal Shock Project stage: Other ML13317A4201982-11-19019 November 1982 Responds to Recommendations Resulting from Audit Concerning Adequacy of Operator Training & Emergency Procedures Re Pressurized Thermal Shock.Operator Requalification Program Revised to Include More Emphasis on Past Events Project stage: Other ML13317A4831983-01-19019 January 1983 Advises That 821119 Response to Audit of Procedures & Training for Pressurized Thermal Shock Acceptable Project stage: Other 1982-01-26
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U.S. N CLEAR REGULATORY COPEISSION OFFICE OF~ INSPECTION AND ENFORCEM.ENT.
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~ REGION V
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Report No. 50-361/81-17
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Docket No. SC-361 Licensee: Southern California Edison Company P,O. Rox 800 2244 Walnut Grove Avenue Rosemead, California 91770,
Facility Name: San Onofre Unit 2 Inspection at:
San Onofre, California Inspection conducted: July 15 - 31, 1981 Inspector:
b4.2 /, /N LGar) Johnstod,1, Resident Inspector DWte Sfgned Approved By:
b8),21, j W/
G1 ZwetW g, CU ef, Reactor Projects DatF Sighed Section 1, Reactor Operations Projects Branch Summary:
Inspection on July 15 to July 31, 1981 (Report No. 50-361/81-18)
Areas Inspected:
Routine, resident inspection of preoperational test pro 5 ram and procedures, maintenance, plant tours, licensee actions on inspector-identified items, and independent inspection effort. The inspection involved 80 inspector-hours by one NRC inspector.
Results: Of the five areas inspected, no items of noncompliance or deviations were identified.
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RV Form 219 (2)
5109180250 810824
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PDR ADOCK 05000361 G
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DETAILSkj}_,
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Persons Contacted
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Southern California' Edison Company (SCE)J
- C. R. Horton, Startup Quality Assurark:e Supervisor
- P. A. Croy, Site Project saality As'urance Supervisor s
J. J. Pantaleo, Startup Quality Assurance Engineer
W. M. Schwab, Unit 3 Startup Supervisor
K. A. Slagel, Startup Management Supervisor
R. Gray, Startup Maintenance Supervisor K. Johnson, Engineer A. Martel, Engineer A. Neill, Engineer T. Gray, Quality Assurance Engineer D. Stonecipher, Operations-Quality Assurance Supervisor b.
Bechtel Power Corporation-
- L. W. Hurst, Project Quality Assurance Manager In addition, operatint personnel, craftsmen and engineers were also contacted-during the course of.the inspection.
- Denotes attendees of Management tieeting on July. 31,1981.
2.
Plant Status The licensee reported that Unit 2 construction was 99 percent complete as of July 29, 1981.
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3.
Preoperational Test Observation Selected portions of the followir.g tests conducted under the Preoperational Test Program were observed by the inspector, a.
Diesel Generator Load Sequencing - 2PE-472-03.
b.
Main Steam System Valves and Traps (Valve closure time for main steam isolation valves) - 2PE-350-01.
c.
High_ Pressure Safety Injection - 2PE-225-01.
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l During the conduct of the tests, the inspector observed that the personnel conducting the tests were using the latest revision of the test procedure and were following the procedure. The inspector also verified by observation that the test prerequisites were met; that proptr lineup of plant systems required for the test were complete; and that test equipment was calibrated and in service prior to comencement of the test.
No items of noncompliance or deviations were identified.
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Maintenance The inspector examined records of maintenance activities performed on equipment turned over to_ the startup organization to verify that regular preventive maintenance was being perfomed and documented. The inspector also discussed the turnover of~ maintenance activities to the station operations mainte%)ce organization. The inspector emphasized that prior to fuel load the; maintenance being perfonned should _ conform to the operations maintenance program..
No items of noncompliance or ' deviations were identified.
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5.
Plant Tour
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The inspector toured Unit 2 several ti.nes during the report period. During these tours, the inspector directed attention toward housekeeping, equipment preservation, maintenance-activities, and work on completed systems. During a tour of the containment, the inspector observed that reactor vessel studs stored vertically on a support stand h W the threaded portions covered only with very lightweight polyethylene plastic sheeting. The following day, the inspector noted that the studs were covered with a more suitable heavy rubberized canvas material. During the management meeting, the inspector expressed the concern that greater attention be paid to the condition of equipment and the use of adequate protective measures.
No items of noncompliance or deviations were identified.
6.
Licensee Action on Previous Inspection Finding The inspector examined the action taken by the licensee on a previously inspector-identified concern.
(Closed) Followup Item (50-361/81-09/2). The licensee'was requested to provide a means to assure that permanent plant instrumentation used for preoperational test acceptance criteria is in calibration prior to use in such tests.
In response to this request, the licensee has agreed to conduct a three point calibration, within 30 days of the performance of a preoperational test, on all permanent plant instrumentation to be used in that 30-day period prior to the test, the Startup Engineer will initiate a Test Exception Report to resolve the question of the acceptability of the test data received from that instrumentation.
(01 50-361/81-17-01)
7.
Management Interview On July 31, 1981, the inspector met with licensee representatives (identified in Paragraph 1) to discuss the scope and findings of the inspection.