Letter Sequence Request |
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Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance...
- Supplement, Supplement, Supplement, Supplement
Results
Other: 05000206/LER-1978-003-01, /01T-0:on 780315,inverters Tripped Causing Loss of Power to Containment Spray Actuation Sys Logic Train & Pressure Sensors.Caused by Failure of Capacitor.One Inverter Reset & One Inverter Removed & Repaired, ML13308A644, ML13308A646, ML13317A193, ML13317A236, ML13317A408, ML13317A411, ML13317A726, ML13317A797, ML13322A549, ML13326A530, ML13326A551, ML13326A553, ML13330A121, ML13330A157, ML13330A207, ML13330A251, ML13330A253, ML13333A308, ML13333A315, ML13333A322, ML13333A323, ML13333A326, ML13333A338, ML13333A348, ML13333A367, ML13333A406, ML13333A423, ML13333A476, ML13333A524, ML13333A762, ML14100A289, ML14119A353, ML19282B877, ML19318H957, ML19318H978, ML19318H981, ML19340D243, ML20136H076
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MONTHYEAR05000206/LER-1978-003-01, /01T-0:on 780315,inverters Tripped Causing Loss of Power to Containment Spray Actuation Sys Logic Train & Pressure Sensors.Caused by Failure of Capacitor.One Inverter Reset & One Inverter Removed & Repaired1978-03-28028 March 1978 /01T-0:on 780315,inverters Tripped Causing Loss of Power to Containment Spray Actuation Sys Logic Train & Pressure Sensors.Caused by Failure of Capacitor.One Inverter Reset & One Inverter Removed & Repaired Project stage: Other ML19318H9571978-05-19019 May 1978 Submits Results of Review of Fire Protection Program for Conformance W/Nrc Guidelines, Nuclear Plant Fire Protection Functional Responsibilities, Admin Controls & QA, Per 770819 Request Project stage: Other ML19318H9781978-07-0303 July 1978 Discusses V Stello Forwarding Manpower Requirements for Operating Reactors. Util Still Maintains That Min Fire Brigade of Three Persons Sufficient.Basis for Position Included in Util Project stage: Other ML19318H9811978-07-0808 July 1978 Forwards Suppl 1 to Fire Protection Program Review..., Providing Addl Info Requested in Encl 1 to NRC & Responses to NRC Positions Identified in Same Ltr Project stage: Other ML13309A5711978-10-18018 October 1978 Forwards Amend 12 to Fsar. Amend Contains Responses to NRC 780726 & 0818 Questions & Includes Corrections & Additions to FSAR Info Project stage: Request ML13333A3081978-10-18018 October 1978 Forwards Info Re Mod to 4,160-volt Switchgear Room for Fire Zone 8 & Mod to Lube Oil Reservoir & Conditioner Area in Fire Zone 9A as Part of Fire Protection Program Project stage: Other ML13333A3141978-10-30030 October 1978 Repts Insertion of Containment Spray Sys Nozzle Insp Requirement in Section 4.2 of Tech Specs, Safety Injection & Containment Spray Sys Periodic Testing Project stage: Request ML13333A3151978-10-30030 October 1978 Advises That Casualty Procedure Re Air Supply for Lube Oil Reservoir & Conditioner Area & Station walk-through Will Be Performed in Response to NRC 781018 Request Re Fire Protection Project stage: Other IR 05000361/19780161978-11-17017 November 1978 IE Inspec Rept 50-361/78-16 on 781030-1103 During Which No Items of Noncompliance Were Noted.Major Areas Inspected Incl:Reactor Internals & Miscellaneous Open Items from Previous Inspecs Project stage: Request ML13333A3221978-11-22022 November 1978 Submits Proposed Mods to Air Supply Sys of Subj Facil.Mods Will Ensure Availability of Air Supply to Req Equip After Loss of Main Air Header Due to Fire in Lube Oil Reservoir & Conditioner Area Project stage: Other ML13333A3231978-11-28028 November 1978 States Util Is Unable to Submit Response to Fire Protec Review Questions by 781127.Will Submit by 781201 Project stage: Other ML13333A3261978-12-0101 December 1978 Responds to NRC Staff Positions Forwarded in 781117 NRC Ltr Re Fire Protec Prog Review.Staff Positions Responded to incl:PF-27A,Cable Spreading Area & PF-51,Containment Project stage: Other ML13333A3381979-01-15015 January 1979 Forwards Conceptual Plan for Safe Unit Shutdown Following Fire in 4160v Switchgear Room or Lube Oil Reserve Area.Also Forwards Related Plant Mod Plan & Implementation Schedule Project stage: Other ML19282B8771979-01-31031 January 1979 Fire Protection in Operating Nuclear Power Stations Project stage: Other ML13326A5301979-01-31031 January 1979 Suggests Mods to Fire Protection Plan,Re Electrical Valve Supervision & Portable Smoke Venting Equipment Project stage: Other IR 05000361/19790011979-01-31031 January 1979 IE Insp Repts 50-361/79-01 & 50-362/79-01 on 790108-11. Noncompliance Noted:Discrepancies Noted in Governing Record Used as Calibr Control Project stage: Request ML13333A3481979-03-0101 March 1979 Requests Extension to 790330 in Which to Submit Evaluation, Originally Due 790215,re Effects of Fire in H-seal Unit on Structured Steel of Turbine Bldg Project stage: Other ML13322A5491979-04-13013 April 1979 Requests Licensee Provide Design Mods Which Will Assure Safe Shutdown Can Be Achieved & Maintained Using Onsite Power Source Project stage: Other ML13333A3671979-05-15015 May 1979 Updates Status of Commitments Re Operating Functions & Plant Mods of Fire Protection Program.Discusses Safe Shutdown Casualty Procedure,Spurious Valve Actuation & Hydrogen Seal Oil Area Fire Project stage: Other ML13326A5511979-07-19019 July 1979 Amend 44 to License DPR-13,incorporating Tech Spec Changes Re Fire Protection Sys Operability & Surveillance & Fire Protection Program Responsibility Project stage: Other ML13326A5531979-07-19019 July 1979 Notice of Issuance & Availability of Amend 44 to License DPR-13 Project stage: Other ML13326A5491979-07-19019 July 1979 Forwards Amend 44 to License DPR-13,safety Evaluation & Notice of Issuance & Availability Project stage: Approval ML13326A5521979-07-19019 July 1979 Safety Evaluation Supporting Amend 44 to License DPR-13 Project stage: Approval ML13333A4061979-08-10010 August 1979 Urges Util to Improve Schedules for Completion of Fire Protection Mods Prior to Oct 1980.Requests That Any Outstanding Info Re Open Items & Required Design Details Be Submitted on Expedited Basis Project stage: Other ML13333A4131979-08-27027 August 1979 Forwards 790413 Request for Addl Info Re Safe Shutdown of Facility Project stage: RAI ML14100A2891979-09-14014 September 1979 NRC Position on Safe Shutdown Capability Project stage: Other ML13333A4181979-09-14014 September 1979 Forwards NRC Position on Safe Shutdown Capability,To Help Licensee Prepare Response to Safety Evaluation for Fire Protection.Requests Schedule for Submittal of Revised Safe Shutdown Plan within 30 Days Project stage: Approval ML13333A4231979-10-23023 October 1979 Forwards Addl Design Info Re Fire Protection Program Review in Response to NRC .Revised Plan for Safe Shutdown Following Fire Deferred Pending Completion of Integrated Assessment of SEP Mods Project stage: Other ML13333A4591979-12-26026 December 1979 Forwards Rept Re Analysis Methods to Determine That Fire in Hydrogen Seal Oil Unit Would Not Substantially Impact Structural Integrity of Steel in South End of Turbine Bldg Project stage: Request ML13333A4761980-01-23023 January 1980 Forwards Addl Design Info & Drawings Re Fire Protection Mods to Be Implemented During Next Refueling Outage.Drawings Available in Central Files Only Project stage: Other ML13311B0361980-01-23023 January 1980 Requests Denial of Petitions Under 10CFR2.206.Petitions Fail to Particularize Factual Basis for Conclusions,Fail to Raise Unreviewed Health or Safety Issues & Fail to Seek Proper Reconsideration of Resolved Issues Project stage: Request ML13333A5241980-03-0606 March 1980 Informs NRC That in Situ Testing of Fire Detection Sys Will Be Deferred Until Acceptable Method Is Developed to Ensure That Station Will Not Be Adversely Affected.Util Will Proceed W/Inplace Sensitivity & Loop Voltage Tests Project stage: Other IR 05000206/19800091980-04-16016 April 1980 IE Insp Rept 50-206/80-09 on 800301-0404.Noncompliance Noted:Failure to Follow Emergency Procedure & Operation Outside Limiting Condition for Operation Project stage: Request ML13308A6441980-04-16016 April 1980 Forwards Revision to BNL Re Items 3.1.1(5),3.1.2 (b),3.1.5(d),3.1.6,3.1.7(a),3.1.7(b),3.1.15(b) & 3.2.3. for Fire Protection Review Project stage: Other ML13308A6461980-05-13013 May 1980 Forwards Fire Protection Review Responding to Items 3,7 & 10 & Licensee .Automatic Power Backup Should Be Supplied for Fire Alarm Sys Project stage: Other ML13330A1211980-09-26026 September 1980 Forwards Response to Comments & Recommendations Re BNL Review of Fire Protection Program.Response Includes New Design Change Commitments.Oversize Drawings,Hydraulic Design Info & Calculation Sheets Available in Central Files Project stage: Other IR 05000206/19800251980-09-26026 September 1980 IE Insp Rept 50-206/80-25 on 800811-29.No Noncompliance Noted.Major Areas Inspected:Plant Operations During long-term Outage,Monthly Maint & Surveillance Observations & Review of LERs Project stage: Request ML13330A1571980-11-0606 November 1980 Informs of Recently Approved Revised 10CFR50.48 Containing Schedules for Completion of All Fire Protection Mods.No Present Implementation Required as Necessary Addl Info Has Not Yet Been Approved Project stage: Other ML19340D2431980-11-24024 November 1980 Forwards Revised 10CFR50.48 & App R to 10CFR50 Re Five Protection Features of Nuclear Power Plants.Rules Take Effect 810217.Summary Listing of Open Items Re Fire Protection Features of Facility Encl Project stage: Other ML13302A8701980-11-24024 November 1980 Summary of 801020 Meeting W/Fema in Los Angeles,Ca Re Emergency Planning Project stage: Request ML20136H0761981-02-0404 February 1981 Marked-up Sser 1 Supporting Fire Protection Project stage: Other ML13302A1651981-02-0404 February 1981 LOCA, Emergency Operating Instruction Project stage: Request ML13330A2191981-02-0404 February 1981 Forwards Suppl 1 to 790719 Fire Protection Safety Evaluation Rept.Items Reviewed:Control Room Fire Detection Sys,Smoke Detectors in Lube Oil Area,Fire Pump Test Features & Turbine Bldg Structure Project stage: Approval ML13330A2071981-02-10010 February 1981 Requests Extension to 811117 for Completion of Fire Protection Features Re Water Suppression Sys,Fire Barriers, Fire Dampers,Fire Barrier Penetrations & Water Damage Protection Project stage: Other ML13330A2531981-02-13013 February 1981 Notice of Extension of Completion Dates of Fire Protection Mods from 800719 to 811117 Project stage: Other ML13330A2511981-02-13013 February 1981 Forwards Fr Notice Re Extension of Time for Completion of Fire Protection Mods from 800719 to 811117.Description of Mods Encl Project stage: Other ML14119A3531981-03-19019 March 1981 Provides Info Required by New Fire Protection Regulations 10CFR50.48.Installation of Smoke Detectors,Emergency Lighting,Reactor Coolant Pump Lube Oil Collection Sys & Provision of Safe Shutdown Capability Discussed Project stage: Other ML13330A9081981-11-0404 November 1981 Application for Exemption from Deadline to Install Certain Fire Safety Measures Project stage: Request ML13330A9121981-11-0404 November 1981 Affidavit Re Support of Application for Exemption from Deadline to Submit Fire Safety Plans & Schedules.Proof of Svc by Mail Encl Project stage: Request ML13330A9101981-11-0505 November 1981 Affidavit Re Support of Application for Exemption from Deadline to Install Certain Fire Safety Measures.Proof of Svc by Mail Encl Project stage: Request 1979-05-15
[Table View] |
Text
U. NUCLEAR REGULATORY COMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION V
Report N /80-25 Docket N License N DPR-13 Safeguards Group Licensee:
Southern California Edison Company 2244 Walnut Grove Avenue Rosemead, California 91770 Facility Name:
San Onofre Nuclear Generating Station #1 Inspection at:
San Onofre, California Inspection conducted:. Aogust 11-29, 1980 Inspectors: (_
_
__
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L. MilleV, Resident Inspector Date Signed Date Signed
/Z Date Signed Approved By:
/
j9
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Dat in B. H. Fau1 kenberry, Ghief, Reactor-Projects Section 2, Date Signed Reactpr Operations and Nuclear Support Branch Summary:
Inspection on August 11-29, 1980 (Report No. 50-206/80-25)
Areas Inspected:
Routine, resident inspection of plant operations during long term outage, monthly maintenance and surveillance observations, and review of licensee event reports. The inspection involved 60 inspector hours by one NRC inspecto Results:
No items of noncompliance or deviations were identifie RV Form 219 (2)
8o o1200S
DETAILS 1..Persons Contacted
- R. Brunet, Superintendent,.Unit 1 M. Wharton, Supervising Engineer, Unit 1
- D. Dunn, Project Quality Assurance Supervisor
- J. Tate, Supervisor of Plant Operations F. Gerardine, Westinghouse Project Manager F. Christopher, Westinghouse Project Supervisor J. Reilly, Nuclear Engineer, Unit 1
- G. McDonald, Unit 1 Quality Assurance Supervisor B. Allen, Consultant (Southern California Edison)
B. Reisling, Radiation Protection Technician The inspector also interviewed other licensee employees on the maintenance, security and operations staffs during this inspectio *Denotes those attending the Exit Interview on August 29, 198.
Inspection of Plant Operations During Long-Terni Outage The inspector observed control roo m operations and manning, discussed plans for steam generating repairs, reviewed logs and instrumentation, and followed changes in plant statu He frequently toured throughout the-facility, includ ing the controlled area Housekeeping throughout the facility was adequate, with management attention to improving a few weaker areas noted in a prior report being apparen The inspector reviewed the Temporary Modifications Log (lifted leads and jumpers) and the active "CLearances." Selected lifted leads, jumpers and
"CLearance" tags were verified to be in place as indicated by the record In particular, yellow "Caution' tags contained appropriate informatio (This closes inspector item 80-16-05.)
The inspector walked down portions of the temporary steam generator tube brazing equipment and verified the lineup of the emergency diesel generator air start syste The inspector observed that the physical security plan continues to appear to be properly implemented, and that existing radiation protection proce dures were being observe During this inspection period, the licensee reported the potential overexposure of 73 workers due to inadequate dosime try during steam generator wor This event and the adequacy of the licensee's radiation protection, program continues, to be an area of concer A management meeting to review the licensee's performance in this area has been scheduled for September 5,. 198 S
.No items of noncompliance or deviations were identifie. Monthly Maintenance Observation The inspector observed portions of the following maintenance:
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Steam generator tube test brazin.
Spent fuel cask quality and straightness measurement.
South Charging pump repai.
Spent resin return filter replacemen The maintenance activities observed appeared to be conducted in accordance with the applicable written procedure or technical manua The limiting conditions for operation were met as required; clearances to perform the work were obtained where necessary; records of the work performance were made; qualified personnel performed the work; and appropriate radiological and fire prevention measures were observe The inspector also observed that operators identified malfunctionin equipment promptly to the maintenance department for repai However, while inspecting the repair of the south charging pump, the inspector observed that both charging pumps seal injection lines had several welds which both appeared to have excessive surface roughness, slag and porosity. The north charging pump had two such welds, and the:south charging pump had three. A licensee representative stated that prior to the present outage, these pumps had not been repaired since 1973. Therefore, the previous repairs were made before the licensee's commitment to the present Quality Assurance Program. He further stated that the lines in question would be replaced during the current outage. (80-20-01)
The inspector reviewed the licensee's records of the charging pump repair performed June 6, 1980, S-XII-1.10, "Inspection and Repair of Charging Pumps."
The procedure used in the performance of this repair work did not address any requirement to sever a charging pump seal water injection line to remove the pump for repair, nor any requirement to reweld the severed line upon reinstal lation of the pump. Furthermore, it did not discuss the welding process, materials, and inspections which would be required. Licensee personnel were unable to determine at the time of this inspection, the procedural require ments which had been imposed, if any, on these two steps at the charging pump repair. This matter will be examined further during a later inspection to determine application of quality assurance requirements on the work performe. Monthly Surveillance Observations The inspector observed licensee personnel obtain and measure boron concentrations, perform portable radiation detector calibrations, and perform area radiation
-3 monitoring system checks. Surveillance activity was relatively low. The activities observed were performed in accordance with the appropriate procedures. Limiting conditions for operation were met where applicabl Logs and records of these tests were kept, and were reviewed independentl The licensee's records indicate that all surveillances required to be completed during this period were completed. No test deficiencies were identified by the license No items of noncompliance or deviations were identifie. Review of Licensee Event Reports (LERs)
The inspector reviewed several of the licensee's recent event reports with a licensee representative, verified that the conditions observed had been correctly reported, and discussed the completed and in progress corrective action The licensee's corrective action had been satisfactorily completed on LER Nos. 80-17, 80-21, 80-23, 80-24, 80-25, 80-27, and 80-29. The licensee representative stated that the radiographs obtained in connection with LER 80-27 (indications in main feedwater welds) would be retained for future reference, and the Westinghouse'report of reactor coolant pump flywheel repairs, LER 80-25, would be provided to the inspector when it became availabl The inspector noted that the licensee had completed its review of the diesel vault drainage system design in connection with LER 80-1 However, correc tive action to repair the inadequate waste removal capability of the vault during the rainy season had not been undertaken. A licensee representative stated that corrective action to prevent recurrence of this flooding would be performe (80-25-03)
6. Exit Interview An exit interview (Paragraph 1) was held on August 29, 1980, to summarize the scope and findings of this inspection. The inspector observed that the steam generator repair work by contractor personnel was still somewhat disorganized on the steam generator platform from an ALARA point of view, with personnel observed waiting to work in higher radiation areas than necessary during the test brazing operations. The licensee representative stated that the licensee was concerned about minimizing unnecessary radiation exposure and would continue to attempt to keep it as low as reasonably achievable.