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Category:INSPECTION REPORT
MONTHYEARIR 05000269/19930321994-01-0606 January 1994 Insp Repts 50-269/93-32,50-270/93-32,50-287/93-32, 50-369/93-31,50-370/93-31,50-413/93-35 & 50-414,respectively on 931213-17.Violations Noted.Major Areas Inpected:Licensee Safeguards Info Program to folow-up on Licensee Repts IR 05000269/19930061993-03-22022 March 1993 Partially Withheld Insp Repts 50-269/93-06,50-270/93-06 & 50-287/93-06 on 930222-25 (Ref 10CFR73.21).No Violations or Deviations Noted.Major Areas Inspected:Licensee Physical Security Program for Power Reactors IR 05000269/19930011993-02-0101 February 1993 Safeguards Insp Repts 50-269/93-01,50-270/93-01 & 50-287/93-01 on 930104-07.No Violations Noted.Major Areas Inspected:Physical Security Program.Details Withheld (Ref 10CFR73.21) IR 05000269/19920251992-12-0303 December 1992 Insp Repts 50-269/92-25,50-270/92-25 & 50-287/92-25 on 921102-06.No Violations or Deviations Noted.Major Areas Inspected:Physical Security Program for Power Reactors, Audits,Protected & Vital Area Barriers.Details Withheld IR 05000269/19910081991-04-10010 April 1991 Insp Repts 50-269/91-08,50-270/91-08 & 50-287/91-08 on 910312-15.violations Noted.Major Areas Inspected:Maint, Control Room Operation,Planning & Scheduling Activities, Training & Procedures,Plant Physical Condition & Mgmt IR 05000269/19900321990-11-0505 November 1990 Partially Withheld Insp Repts 50-269/90-32,50-270/90-32 & 50-287/90-32 on 901015-19.No Violations Noted.Major Areas Inspected:Physical Security Program Plans,Mgt Support, Security Program Plans & Protected & Vital Area Barriers IR 05000269/19900221990-07-24024 July 1990 Partially Withheld Safeguard Insp Repts 50-269/90-22, 5-270/90-22 & 50-287/90-22 on 900625-29.No Violations or Deviation Noted.Major Areas Inspected:Core Insp Program for Power Reactors & Safeguards Contingency Plan Implementation IR 05000269/19900181990-06-21021 June 1990 Partially Withheld Insp Repts 50-269/90-18,50-270/90-18 & 50-287/90-18 on 900604-08 (Ref 10CFR2.790 & 73.21).No Violations Noted.Major Areas Inspected:Security Program Audit,Detection & Assessment Aids & Key Control IR 05000269/19890201989-07-25025 July 1989 Partially Withheld Insp Repts 50-269/89-20,50-270/89-20 & 50-287/89-20 on 890626-30 (Ref 10CFR2.790.(d) & 73.21). Violations Noted.Major Areas Inspected:Physical Security Program for Power Reactors & Security Audit IR 05000269/19890101989-05-19019 May 1989 Partially Withheld Insp Repts 50-269/89-10,50-270/89-10 & 50-287/89-10 on 890410-14 (Ref 10CFR2.790 & 73.21). Violations Noted.Major Areas Inspected:Mgt Support,Security Program Plans & Audits & Protected & Vital Area Barriers IR 05000269/19890091989-04-10010 April 1989 Insp Repts 50-269/89-09,50-270/89-09 & 50-287/89-09 on 890306-10.No Violations Noted.Weaknesses Noted Re Data Base Used to Prepare computer-generated Work Requests.Major Areas Inspected:Design Control,Mods & Open Items IR 05000269/19890071989-03-10010 March 1989 Insp Repts 50-269/89-07,50-270/89-07 & 50-287/89-07 on 890213-17.Deviation Noted.Major Areas Inspected:Conformance to Reg Guide 1.97 Re Instrumentation for light-water-cooled Plants to Assess Conditions During & Following Accident IR 05000269/19880051988-03-21021 March 1988 Insp Repts 50-269/88-05,50-270/88-05 & 50-287/88-05 on 880217-0316.No Violations Noted.Major Areas Inspected:Maint, Operations,Surveillance,Physical Security & Design Changes IR 05000269/19870101987-03-17017 March 1987 Insp Repts 50-269/87-10,50-270/87-10 & 50-287/87-10 on 870210-0309.No Violations or Deviations Noted.Major Areas Inspected:Areas of Operations,Surveillance,Maint,Followup of Events & Verification of ESF Lineups IR 05000269/19870091987-03-17017 March 1987 Insp Repts 50-269/87-09,50-270/87-09 & 50-287/87-09 on 870209-13.No Violations Noted.Major Areas Inspected:Onsite Review of Liquid & Gaseous Radwaste Programs & Review of TMI Action Items II.B.3 & II.F.1.2 IR 05000269/19870061987-03-0909 March 1987 Insp Repts 50-269/87-06,50-270/87-06 & 50-287/87-06 on 870126-30.No Violations or Deviations Noted.Major Areas Inspected:Inservice Insp,Ongoing Repairs in Reactor Coolant Pumps & Maint & Welding Activities IR 05000269/19870041987-02-17017 February 1987 Insp Repts 50-269/87-04,50-270/87-04 & 50-287/87-04 on 870113-0209.No Violation or Deviation Noted.Major Areas Inspected:Operations,Surveillance,Maint,Verification of ESF Linups,Followup of Events & Shutdown Work in Progress IR 05000269/19870021987-02-11011 February 1987 Partially Withheld Insp Repts 50-269/87-02,50-270/87-02 & 50-287/87-02 on 870126-30 (Ref 10CFR2.790).Violation Noted Re Inadequate App R Circuit Analysis IR 05000269/19870031987-02-10010 February 1987 Insp Repts 50-269/87-03,50-270/87-03 & 50-287/87-03 on 870112-16.Violation Noted:Failure to Adequately Evaluate Radiological Hazards IR 05000269/19870081987-02-0505 February 1987 Enforcement Conference Repts 50-269/87-08,50-270/87-08 & 50-287/87-08 on 861222.Major Areas Discussed:Safety Sys Functional Insp & Associated Safety Implications IR 05000269/19870071987-02-0505 February 1987 Enforcement Conference Repts 50-269/87-07,50-270/87-07 & 50-287/87-07 on 861222.Major Areas Discussed:Sequence of Events & Corrective Actions Re Emergency Condenser Circulating Water Sys Degradation IR 05000269/19860341987-02-0505 February 1987 Corrected Insp Repts 50-269/86-34,50-270/86-34 & 50-287/86-34 on 861111-870112.Insp Erroneously Reported as Having Been Conducted on 861111-0112 IR 05000269/19870011987-01-30030 January 1987 Insp Repts 50-269/87-01,50-270/87-01 & 50-287/87-01 on 870105-08.Violation Noted:Failure to Provide Procedures W/Appropriate Qualitative or Quantitative Acceptance Criteria for Activities Important to Safety ML20211A0061987-01-23023 January 1987 Insp Repts 50-269/86-34,50-270/86-34 & 50-287/86-34 on 861111-870112.No Violations or Deviations Noted.Major Areas Inspected:Operations,Surveillance,Maint,Verification of ESF Lineups & Emergency Drills IR 05000269/19860351987-01-0707 January 1987 Insp Repts 50-269/86-35,50-270/86-35 & 50-287/86-35 on 861208-12.No Violations or Deviations Noted.Major Areas Inspected:Radiation Protection Program,Including Review of Organization & Mgt of Health Physics Staff ML20212F5511986-12-24024 December 1986 Notice of Violation from Insp on 861103-12 IR 05000269/19860321986-12-10010 December 1986 Insp Repts 50-413/86-44,50-414/86-47,50-369/86-32, 50-370/86-32,50-269/86-32,50-270/86-32 & 50-287/86-32 on 861103-12.Violations Noted:Failure to Follow Procedures for Radiological Sample Analyses & Inadequate Surveys IR 05000269/19860281986-11-0303 November 1986 Partially Withheld Physical Security Insp Repts 50-269/86-28,50-270/86-28 & 50-287/86-28 on 861014-17 (Ref 10CFR2.790 & 73.21).Violation Noted:Inadequate Protected Area Barrier IR 05000269/19860301986-10-23023 October 1986 Partially Withheld Physical Security Insp Rept 50-269/86-30 on 861007-09 (Ref 10CFR2.790 & 73.21).No Violation Noted. Major Areas Inspected:Physical Protection of Irradiated Reactor Fuel During Transportation Between Sites IR 05000269/19860231986-09-23023 September 1986 Insp Repts 50-269/86-23,50-270/86-23 & 50-287/86-23 on 860826-29.No Violation or Deviation Noted.Major Areas Inspected:Inservice Insp,Review of Procedure & Investigation of Techniques Developed for Ultrasonic Exam of Flange IR 05000269/19860241986-09-19019 September 1986 Insp Repts 50-269/86-24,50-270/86-24 & 50-287/86-24 on 860908.No Noncompliance or Deviations Noted.Major Areas Inspected:Operations,Surveillance,Maint,Verification of ESF Lineups & Followup Items IR 05000269/19860211986-08-15015 August 1986 Insp Repts 50-269/86-21,50-270/86-21 & 50-287/86-21 on 860708-0811.No Noncompliance or Deviation Noted.Major Areas Inspected:Operations,Surveillance,Maint,Verification of ESF Lineups & Followup of Events IR 05000269/19860221986-08-0101 August 1986 Partially Withheld Insp Repts 50-269/86-22,50-270/86-22 & 50-287/86-22 on 860711 (Ref 10CFR2.790 & 73.21).Violation Noted:Individual Inside Vital Area Wore Invalid Picture Badge IR 05000269/19860151986-05-28028 May 1986 Insp Rept 50-269/86-15 on 860423-25.No Violations or Deviations Noted.Major Areas Inspected:Ultrasonic Exam of Mockup Reactor vessel-to-flange Weld for Correlation of Reflectors Between Vessel & Mockup IR 05000269/19860071986-05-15015 May 1986 Insp Repts 50-269/86-07,50-270/86-07 & 50-287/86-07 on 860317-0512.No Violations or Deviations Noted.Major Areas Inspected:Low Level Radwaste Burial Site & Startup Review of Low Level Radwaste Incinerator IR 05000269/19860121986-04-25025 April 1986 Insp Repts 50-269/86-12,50-270/86-12 & 50-287/86-12 on 860331-0404.No Violations or Deviations Noted.Major Areas Inspected:Annual Emergency Preparedness Exercise IR 05000269/19860041986-04-0404 April 1986 Insp Repts 50-269/86-04,50-270/86-04 & 50-287/86-04 on 860211-0310.No Violation Noted.Major Areas Inspected: Operations,Surveillance,Maint,Verification of ESF Lineups & Refueling Activities IR 05000269/19860081986-04-0202 April 1986 Insp Repts 50-269/86-08,50-270/86-08 & 50-287/86-08 on 860303-07.No Violation or Deviation Noted.Major Areas Inspected:Unit 1 Sludge Cleaning of once-through Steam Generator by Water Slap Method & IE Bulletin 82-02 ML20199G4451986-03-25025 March 1986 Insp Repts 50-269/86-05,50-270/86-05 & 50-287/86-05 on 860224-28.Violation Noted:Failure to Provide Adequate Respiratory Protective Equipment to Maintain Intakes of Radioactive Matl ALARA IR 05000269/19860091986-03-20020 March 1986 Insp Repts 50-269/86-09,50-270/86-09 & 50-287/86-09 on 860306.No Violation or Deviation Noted.Major Areas Inspected:Steam Generator Cleaning & Maint Re Secondary Water Cycle ML20210H4081986-03-20020 March 1986 Insp Repts 50-269/86-01,50-270/86-01 & 50-287/86-01 on 860114-0210.Violation Noted:Failure to Follow Procedure During Channel C Calibr & Functional Test,Resulting in Reactor Trip from 100% Power IR 05000269/19860061986-03-14014 March 1986 Insp Repts 50-269/86-06,50-270/86-06 & 50-287/86-06 on 860224-27.No Violations or Deviations Noted.Major Areas Inspected:Switchyard Surveillance Testing,Containment Isolation Valve Test Witnessing & Procedure Review IR 05000269/19860031986-03-12012 March 1986 Insp Repts 50-269/86-03,50-270/86-03 & 50-287/86-03 on 860218-21.No Violation or Deviation Noted.Major Areas Inspected:Inservice Insp,Work Observation Data Review & Evaluation & Main Feedwater flow-nozzle Mod IR 05000269/19850421986-02-11011 February 1986 Insp Repts 50-269/85-42,50-270/85-42 & 50-287/85-42 on 851216-20.Violation Noted:Failure to Provide Positive Access Control for Two High Radiation Areas ML20137U5451986-02-11011 February 1986 Insp Repts 50-269/85-41,50-270/85-41 & 50-287/85-41 on 851210-860113.Noncompliance Noted:Failure to Follow Exempt Change Procedure & Failure to Shut Down Reactor within 24 H of Discovery of Excessive Leakage ML20154K8981986-02-0707 February 1986 Insp Repts 50-269/85-39,50-270/85-39 & 50-287/85-39 on 851209-13 & 860114.Violation Identified in Area of Physical Barrier - Protected Area.Rept Details Withheld (Ref 10CFR2.790 & 73.21) IR 05000269/19850401986-01-13013 January 1986 Insp Repts 50-269/85-40,50-270/85-40 & 50-287/85-40 on 851209-13.No Violation or Deviation Identified.Major Areas Inspected:Maint & Surveillance Testing of Main Steam Safety Relief & Pressurizer Code Safety Relief Valves IR 05000269/19850381985-12-13013 December 1985 Insp Repts 50-269/85-38,50-270/85-38 & 50-287/85-38 on 851112-1209.No Noncompliance or Deviations Noted.Major Areas Inspected:Operations,Surveillance,Maint,Startup Testing of Safe Shutdown Facility & LER Review ML20137E4031985-11-21021 November 1985 Insp Repts 50-269/85-37,50-270/85-37 & 50-287/85-37 on 851008-1111.Noncompliance Noted:Failure to Document Malfunctioning Valve 3LP-2 in Reactor Operator & Senior Reactor Operator Log IR 05000269/19850351985-10-28028 October 1985 Insp Repts 50-269/85-35,50-270/85-35 & 50-287/85-35 on 851007-11.No Violation or Deviation Noted.Major Areas Inspected:Review & Witnessing of Pre & post-criticality Tests Following Refueling Outage & Info Notice Followup 1994-01-06
[Table view] Category:NRC-GENERATED
MONTHYEARIR 05000269/19930321994-01-0606 January 1994 Insp Repts 50-269/93-32,50-270/93-32,50-287/93-32, 50-369/93-31,50-370/93-31,50-413/93-35 & 50-414,respectively on 931213-17.Violations Noted.Major Areas Inpected:Licensee Safeguards Info Program to folow-up on Licensee Repts IR 05000269/19930061993-03-22022 March 1993 Partially Withheld Insp Repts 50-269/93-06,50-270/93-06 & 50-287/93-06 on 930222-25 (Ref 10CFR73.21).No Violations or Deviations Noted.Major Areas Inspected:Licensee Physical Security Program for Power Reactors IR 05000269/19930011993-02-0101 February 1993 Safeguards Insp Repts 50-269/93-01,50-270/93-01 & 50-287/93-01 on 930104-07.No Violations Noted.Major Areas Inspected:Physical Security Program.Details Withheld (Ref 10CFR73.21) IR 05000269/19920251992-12-0303 December 1992 Insp Repts 50-269/92-25,50-270/92-25 & 50-287/92-25 on 921102-06.No Violations or Deviations Noted.Major Areas Inspected:Physical Security Program for Power Reactors, Audits,Protected & Vital Area Barriers.Details Withheld IR 05000269/19910081991-04-10010 April 1991 Insp Repts 50-269/91-08,50-270/91-08 & 50-287/91-08 on 910312-15.violations Noted.Major Areas Inspected:Maint, Control Room Operation,Planning & Scheduling Activities, Training & Procedures,Plant Physical Condition & Mgmt IR 05000269/19900321990-11-0505 November 1990 Partially Withheld Insp Repts 50-269/90-32,50-270/90-32 & 50-287/90-32 on 901015-19.No Violations Noted.Major Areas Inspected:Physical Security Program Plans,Mgt Support, Security Program Plans & Protected & Vital Area Barriers IR 05000269/19900221990-07-24024 July 1990 Partially Withheld Safeguard Insp Repts 50-269/90-22, 5-270/90-22 & 50-287/90-22 on 900625-29.No Violations or Deviation Noted.Major Areas Inspected:Core Insp Program for Power Reactors & Safeguards Contingency Plan Implementation IR 05000269/19900181990-06-21021 June 1990 Partially Withheld Insp Repts 50-269/90-18,50-270/90-18 & 50-287/90-18 on 900604-08 (Ref 10CFR2.790 & 73.21).No Violations Noted.Major Areas Inspected:Security Program Audit,Detection & Assessment Aids & Key Control IR 05000269/19890201989-07-25025 July 1989 Partially Withheld Insp Repts 50-269/89-20,50-270/89-20 & 50-287/89-20 on 890626-30 (Ref 10CFR2.790.(d) & 73.21). Violations Noted.Major Areas Inspected:Physical Security Program for Power Reactors & Security Audit IR 05000269/19890101989-05-19019 May 1989 Partially Withheld Insp Repts 50-269/89-10,50-270/89-10 & 50-287/89-10 on 890410-14 (Ref 10CFR2.790 & 73.21). Violations Noted.Major Areas Inspected:Mgt Support,Security Program Plans & Audits & Protected & Vital Area Barriers IR 05000269/19890091989-04-10010 April 1989 Insp Repts 50-269/89-09,50-270/89-09 & 50-287/89-09 on 890306-10.No Violations Noted.Weaknesses Noted Re Data Base Used to Prepare computer-generated Work Requests.Major Areas Inspected:Design Control,Mods & Open Items IR 05000269/19890071989-03-10010 March 1989 Insp Repts 50-269/89-07,50-270/89-07 & 50-287/89-07 on 890213-17.Deviation Noted.Major Areas Inspected:Conformance to Reg Guide 1.97 Re Instrumentation for light-water-cooled Plants to Assess Conditions During & Following Accident IR 05000269/19880051988-03-21021 March 1988 Insp Repts 50-269/88-05,50-270/88-05 & 50-287/88-05 on 880217-0316.No Violations Noted.Major Areas Inspected:Maint, Operations,Surveillance,Physical Security & Design Changes IR 05000269/19870101987-03-17017 March 1987 Insp Repts 50-269/87-10,50-270/87-10 & 50-287/87-10 on 870210-0309.No Violations or Deviations Noted.Major Areas Inspected:Areas of Operations,Surveillance,Maint,Followup of Events & Verification of ESF Lineups IR 05000269/19870091987-03-17017 March 1987 Insp Repts 50-269/87-09,50-270/87-09 & 50-287/87-09 on 870209-13.No Violations Noted.Major Areas Inspected:Onsite Review of Liquid & Gaseous Radwaste Programs & Review of TMI Action Items II.B.3 & II.F.1.2 IR 05000269/19870061987-03-0909 March 1987 Insp Repts 50-269/87-06,50-270/87-06 & 50-287/87-06 on 870126-30.No Violations or Deviations Noted.Major Areas Inspected:Inservice Insp,Ongoing Repairs in Reactor Coolant Pumps & Maint & Welding Activities IR 05000269/19870041987-02-17017 February 1987 Insp Repts 50-269/87-04,50-270/87-04 & 50-287/87-04 on 870113-0209.No Violation or Deviation Noted.Major Areas Inspected:Operations,Surveillance,Maint,Verification of ESF Linups,Followup of Events & Shutdown Work in Progress IR 05000269/19870021987-02-11011 February 1987 Partially Withheld Insp Repts 50-269/87-02,50-270/87-02 & 50-287/87-02 on 870126-30 (Ref 10CFR2.790).Violation Noted Re Inadequate App R Circuit Analysis IR 05000269/19870031987-02-10010 February 1987 Insp Repts 50-269/87-03,50-270/87-03 & 50-287/87-03 on 870112-16.Violation Noted:Failure to Adequately Evaluate Radiological Hazards IR 05000269/19870081987-02-0505 February 1987 Enforcement Conference Repts 50-269/87-08,50-270/87-08 & 50-287/87-08 on 861222.Major Areas Discussed:Safety Sys Functional Insp & Associated Safety Implications IR 05000269/19870071987-02-0505 February 1987 Enforcement Conference Repts 50-269/87-07,50-270/87-07 & 50-287/87-07 on 861222.Major Areas Discussed:Sequence of Events & Corrective Actions Re Emergency Condenser Circulating Water Sys Degradation IR 05000269/19860341987-02-0505 February 1987 Corrected Insp Repts 50-269/86-34,50-270/86-34 & 50-287/86-34 on 861111-870112.Insp Erroneously Reported as Having Been Conducted on 861111-0112 IR 05000269/19870011987-01-30030 January 1987 Insp Repts 50-269/87-01,50-270/87-01 & 50-287/87-01 on 870105-08.Violation Noted:Failure to Provide Procedures W/Appropriate Qualitative or Quantitative Acceptance Criteria for Activities Important to Safety ML20211A0061987-01-23023 January 1987 Insp Repts 50-269/86-34,50-270/86-34 & 50-287/86-34 on 861111-870112.No Violations or Deviations Noted.Major Areas Inspected:Operations,Surveillance,Maint,Verification of ESF Lineups & Emergency Drills IR 05000269/19860351987-01-0707 January 1987 Insp Repts 50-269/86-35,50-270/86-35 & 50-287/86-35 on 861208-12.No Violations or Deviations Noted.Major Areas Inspected:Radiation Protection Program,Including Review of Organization & Mgt of Health Physics Staff ML20212F5511986-12-24024 December 1986 Notice of Violation from Insp on 861103-12 IR 05000269/19860321986-12-10010 December 1986 Insp Repts 50-413/86-44,50-414/86-47,50-369/86-32, 50-370/86-32,50-269/86-32,50-270/86-32 & 50-287/86-32 on 861103-12.Violations Noted:Failure to Follow Procedures for Radiological Sample Analyses & Inadequate Surveys IR 05000269/19860281986-11-0303 November 1986 Partially Withheld Physical Security Insp Repts 50-269/86-28,50-270/86-28 & 50-287/86-28 on 861014-17 (Ref 10CFR2.790 & 73.21).Violation Noted:Inadequate Protected Area Barrier IR 05000269/19860301986-10-23023 October 1986 Partially Withheld Physical Security Insp Rept 50-269/86-30 on 861007-09 (Ref 10CFR2.790 & 73.21).No Violation Noted. Major Areas Inspected:Physical Protection of Irradiated Reactor Fuel During Transportation Between Sites IR 05000269/19860231986-09-23023 September 1986 Insp Repts 50-269/86-23,50-270/86-23 & 50-287/86-23 on 860826-29.No Violation or Deviation Noted.Major Areas Inspected:Inservice Insp,Review of Procedure & Investigation of Techniques Developed for Ultrasonic Exam of Flange IR 05000269/19860241986-09-19019 September 1986 Insp Repts 50-269/86-24,50-270/86-24 & 50-287/86-24 on 860908.No Noncompliance or Deviations Noted.Major Areas Inspected:Operations,Surveillance,Maint,Verification of ESF Lineups & Followup Items IR 05000269/19860211986-08-15015 August 1986 Insp Repts 50-269/86-21,50-270/86-21 & 50-287/86-21 on 860708-0811.No Noncompliance or Deviation Noted.Major Areas Inspected:Operations,Surveillance,Maint,Verification of ESF Lineups & Followup of Events IR 05000269/19860221986-08-0101 August 1986 Partially Withheld Insp Repts 50-269/86-22,50-270/86-22 & 50-287/86-22 on 860711 (Ref 10CFR2.790 & 73.21).Violation Noted:Individual Inside Vital Area Wore Invalid Picture Badge IR 05000269/19860151986-05-28028 May 1986 Insp Rept 50-269/86-15 on 860423-25.No Violations or Deviations Noted.Major Areas Inspected:Ultrasonic Exam of Mockup Reactor vessel-to-flange Weld for Correlation of Reflectors Between Vessel & Mockup IR 05000269/19860071986-05-15015 May 1986 Insp Repts 50-269/86-07,50-270/86-07 & 50-287/86-07 on 860317-0512.No Violations or Deviations Noted.Major Areas Inspected:Low Level Radwaste Burial Site & Startup Review of Low Level Radwaste Incinerator IR 05000269/19860121986-04-25025 April 1986 Insp Repts 50-269/86-12,50-270/86-12 & 50-287/86-12 on 860331-0404.No Violations or Deviations Noted.Major Areas Inspected:Annual Emergency Preparedness Exercise IR 05000269/19860041986-04-0404 April 1986 Insp Repts 50-269/86-04,50-270/86-04 & 50-287/86-04 on 860211-0310.No Violation Noted.Major Areas Inspected: Operations,Surveillance,Maint,Verification of ESF Lineups & Refueling Activities IR 05000269/19860081986-04-0202 April 1986 Insp Repts 50-269/86-08,50-270/86-08 & 50-287/86-08 on 860303-07.No Violation or Deviation Noted.Major Areas Inspected:Unit 1 Sludge Cleaning of once-through Steam Generator by Water Slap Method & IE Bulletin 82-02 ML20199G4451986-03-25025 March 1986 Insp Repts 50-269/86-05,50-270/86-05 & 50-287/86-05 on 860224-28.Violation Noted:Failure to Provide Adequate Respiratory Protective Equipment to Maintain Intakes of Radioactive Matl ALARA IR 05000269/19860091986-03-20020 March 1986 Insp Repts 50-269/86-09,50-270/86-09 & 50-287/86-09 on 860306.No Violation or Deviation Noted.Major Areas Inspected:Steam Generator Cleaning & Maint Re Secondary Water Cycle ML20210H4081986-03-20020 March 1986 Insp Repts 50-269/86-01,50-270/86-01 & 50-287/86-01 on 860114-0210.Violation Noted:Failure to Follow Procedure During Channel C Calibr & Functional Test,Resulting in Reactor Trip from 100% Power IR 05000269/19860061986-03-14014 March 1986 Insp Repts 50-269/86-06,50-270/86-06 & 50-287/86-06 on 860224-27.No Violations or Deviations Noted.Major Areas Inspected:Switchyard Surveillance Testing,Containment Isolation Valve Test Witnessing & Procedure Review IR 05000269/19860031986-03-12012 March 1986 Insp Repts 50-269/86-03,50-270/86-03 & 50-287/86-03 on 860218-21.No Violation or Deviation Noted.Major Areas Inspected:Inservice Insp,Work Observation Data Review & Evaluation & Main Feedwater flow-nozzle Mod IR 05000269/19850421986-02-11011 February 1986 Insp Repts 50-269/85-42,50-270/85-42 & 50-287/85-42 on 851216-20.Violation Noted:Failure to Provide Positive Access Control for Two High Radiation Areas ML20137U5451986-02-11011 February 1986 Insp Repts 50-269/85-41,50-270/85-41 & 50-287/85-41 on 851210-860113.Noncompliance Noted:Failure to Follow Exempt Change Procedure & Failure to Shut Down Reactor within 24 H of Discovery of Excessive Leakage ML20154K8981986-02-0707 February 1986 Insp Repts 50-269/85-39,50-270/85-39 & 50-287/85-39 on 851209-13 & 860114.Violation Identified in Area of Physical Barrier - Protected Area.Rept Details Withheld (Ref 10CFR2.790 & 73.21) IR 05000269/19850401986-01-13013 January 1986 Insp Repts 50-269/85-40,50-270/85-40 & 50-287/85-40 on 851209-13.No Violation or Deviation Identified.Major Areas Inspected:Maint & Surveillance Testing of Main Steam Safety Relief & Pressurizer Code Safety Relief Valves IR 05000269/19850381985-12-13013 December 1985 Insp Repts 50-269/85-38,50-270/85-38 & 50-287/85-38 on 851112-1209.No Noncompliance or Deviations Noted.Major Areas Inspected:Operations,Surveillance,Maint,Startup Testing of Safe Shutdown Facility & LER Review ML20137E4031985-11-21021 November 1985 Insp Repts 50-269/85-37,50-270/85-37 & 50-287/85-37 on 851008-1111.Noncompliance Noted:Failure to Document Malfunctioning Valve 3LP-2 in Reactor Operator & Senior Reactor Operator Log IR 05000269/19850351985-10-28028 October 1985 Insp Repts 50-269/85-35,50-270/85-35 & 50-287/85-35 on 851007-11.No Violation or Deviation Noted.Major Areas Inspected:Review & Witnessing of Pre & post-criticality Tests Following Refueling Outage & Info Notice Followup 1994-01-06
[Table view] Category:INSPECTION REPORT
MONTHYEARIR 05000269/19930321994-01-0606 January 1994 Insp Repts 50-269/93-32,50-270/93-32,50-287/93-32, 50-369/93-31,50-370/93-31,50-413/93-35 & 50-414,respectively on 931213-17.Violations Noted.Major Areas Inpected:Licensee Safeguards Info Program to folow-up on Licensee Repts IR 05000269/19930061993-03-22022 March 1993 Partially Withheld Insp Repts 50-269/93-06,50-270/93-06 & 50-287/93-06 on 930222-25 (Ref 10CFR73.21).No Violations or Deviations Noted.Major Areas Inspected:Licensee Physical Security Program for Power Reactors IR 05000269/19930011993-02-0101 February 1993 Safeguards Insp Repts 50-269/93-01,50-270/93-01 & 50-287/93-01 on 930104-07.No Violations Noted.Major Areas Inspected:Physical Security Program.Details Withheld (Ref 10CFR73.21) IR 05000269/19920251992-12-0303 December 1992 Insp Repts 50-269/92-25,50-270/92-25 & 50-287/92-25 on 921102-06.No Violations or Deviations Noted.Major Areas Inspected:Physical Security Program for Power Reactors, Audits,Protected & Vital Area Barriers.Details Withheld IR 05000269/19910081991-04-10010 April 1991 Insp Repts 50-269/91-08,50-270/91-08 & 50-287/91-08 on 910312-15.violations Noted.Major Areas Inspected:Maint, Control Room Operation,Planning & Scheduling Activities, Training & Procedures,Plant Physical Condition & Mgmt IR 05000269/19900321990-11-0505 November 1990 Partially Withheld Insp Repts 50-269/90-32,50-270/90-32 & 50-287/90-32 on 901015-19.No Violations Noted.Major Areas Inspected:Physical Security Program Plans,Mgt Support, Security Program Plans & Protected & Vital Area Barriers IR 05000269/19900221990-07-24024 July 1990 Partially Withheld Safeguard Insp Repts 50-269/90-22, 5-270/90-22 & 50-287/90-22 on 900625-29.No Violations or Deviation Noted.Major Areas Inspected:Core Insp Program for Power Reactors & Safeguards Contingency Plan Implementation IR 05000269/19900181990-06-21021 June 1990 Partially Withheld Insp Repts 50-269/90-18,50-270/90-18 & 50-287/90-18 on 900604-08 (Ref 10CFR2.790 & 73.21).No Violations Noted.Major Areas Inspected:Security Program Audit,Detection & Assessment Aids & Key Control IR 05000269/19890201989-07-25025 July 1989 Partially Withheld Insp Repts 50-269/89-20,50-270/89-20 & 50-287/89-20 on 890626-30 (Ref 10CFR2.790.(d) & 73.21). Violations Noted.Major Areas Inspected:Physical Security Program for Power Reactors & Security Audit IR 05000269/19890101989-05-19019 May 1989 Partially Withheld Insp Repts 50-269/89-10,50-270/89-10 & 50-287/89-10 on 890410-14 (Ref 10CFR2.790 & 73.21). Violations Noted.Major Areas Inspected:Mgt Support,Security Program Plans & Audits & Protected & Vital Area Barriers IR 05000269/19890091989-04-10010 April 1989 Insp Repts 50-269/89-09,50-270/89-09 & 50-287/89-09 on 890306-10.No Violations Noted.Weaknesses Noted Re Data Base Used to Prepare computer-generated Work Requests.Major Areas Inspected:Design Control,Mods & Open Items IR 05000269/19890071989-03-10010 March 1989 Insp Repts 50-269/89-07,50-270/89-07 & 50-287/89-07 on 890213-17.Deviation Noted.Major Areas Inspected:Conformance to Reg Guide 1.97 Re Instrumentation for light-water-cooled Plants to Assess Conditions During & Following Accident IR 05000269/19880051988-03-21021 March 1988 Insp Repts 50-269/88-05,50-270/88-05 & 50-287/88-05 on 880217-0316.No Violations Noted.Major Areas Inspected:Maint, Operations,Surveillance,Physical Security & Design Changes IR 05000269/19870101987-03-17017 March 1987 Insp Repts 50-269/87-10,50-270/87-10 & 50-287/87-10 on 870210-0309.No Violations or Deviations Noted.Major Areas Inspected:Areas of Operations,Surveillance,Maint,Followup of Events & Verification of ESF Lineups IR 05000269/19870091987-03-17017 March 1987 Insp Repts 50-269/87-09,50-270/87-09 & 50-287/87-09 on 870209-13.No Violations Noted.Major Areas Inspected:Onsite Review of Liquid & Gaseous Radwaste Programs & Review of TMI Action Items II.B.3 & II.F.1.2 IR 05000269/19870061987-03-0909 March 1987 Insp Repts 50-269/87-06,50-270/87-06 & 50-287/87-06 on 870126-30.No Violations or Deviations Noted.Major Areas Inspected:Inservice Insp,Ongoing Repairs in Reactor Coolant Pumps & Maint & Welding Activities IR 05000269/19870041987-02-17017 February 1987 Insp Repts 50-269/87-04,50-270/87-04 & 50-287/87-04 on 870113-0209.No Violation or Deviation Noted.Major Areas Inspected:Operations,Surveillance,Maint,Verification of ESF Linups,Followup of Events & Shutdown Work in Progress IR 05000269/19870021987-02-11011 February 1987 Partially Withheld Insp Repts 50-269/87-02,50-270/87-02 & 50-287/87-02 on 870126-30 (Ref 10CFR2.790).Violation Noted Re Inadequate App R Circuit Analysis IR 05000269/19870031987-02-10010 February 1987 Insp Repts 50-269/87-03,50-270/87-03 & 50-287/87-03 on 870112-16.Violation Noted:Failure to Adequately Evaluate Radiological Hazards IR 05000269/19870081987-02-0505 February 1987 Enforcement Conference Repts 50-269/87-08,50-270/87-08 & 50-287/87-08 on 861222.Major Areas Discussed:Safety Sys Functional Insp & Associated Safety Implications IR 05000269/19870071987-02-0505 February 1987 Enforcement Conference Repts 50-269/87-07,50-270/87-07 & 50-287/87-07 on 861222.Major Areas Discussed:Sequence of Events & Corrective Actions Re Emergency Condenser Circulating Water Sys Degradation IR 05000269/19860341987-02-0505 February 1987 Corrected Insp Repts 50-269/86-34,50-270/86-34 & 50-287/86-34 on 861111-870112.Insp Erroneously Reported as Having Been Conducted on 861111-0112 IR 05000269/19870011987-01-30030 January 1987 Insp Repts 50-269/87-01,50-270/87-01 & 50-287/87-01 on 870105-08.Violation Noted:Failure to Provide Procedures W/Appropriate Qualitative or Quantitative Acceptance Criteria for Activities Important to Safety ML20211A0061987-01-23023 January 1987 Insp Repts 50-269/86-34,50-270/86-34 & 50-287/86-34 on 861111-870112.No Violations or Deviations Noted.Major Areas Inspected:Operations,Surveillance,Maint,Verification of ESF Lineups & Emergency Drills IR 05000269/19860351987-01-0707 January 1987 Insp Repts 50-269/86-35,50-270/86-35 & 50-287/86-35 on 861208-12.No Violations or Deviations Noted.Major Areas Inspected:Radiation Protection Program,Including Review of Organization & Mgt of Health Physics Staff ML20212F5511986-12-24024 December 1986 Notice of Violation from Insp on 861103-12 IR 05000269/19860321986-12-10010 December 1986 Insp Repts 50-413/86-44,50-414/86-47,50-369/86-32, 50-370/86-32,50-269/86-32,50-270/86-32 & 50-287/86-32 on 861103-12.Violations Noted:Failure to Follow Procedures for Radiological Sample Analyses & Inadequate Surveys IR 05000269/19860281986-11-0303 November 1986 Partially Withheld Physical Security Insp Repts 50-269/86-28,50-270/86-28 & 50-287/86-28 on 861014-17 (Ref 10CFR2.790 & 73.21).Violation Noted:Inadequate Protected Area Barrier IR 05000269/19860301986-10-23023 October 1986 Partially Withheld Physical Security Insp Rept 50-269/86-30 on 861007-09 (Ref 10CFR2.790 & 73.21).No Violation Noted. Major Areas Inspected:Physical Protection of Irradiated Reactor Fuel During Transportation Between Sites IR 05000269/19860231986-09-23023 September 1986 Insp Repts 50-269/86-23,50-270/86-23 & 50-287/86-23 on 860826-29.No Violation or Deviation Noted.Major Areas Inspected:Inservice Insp,Review of Procedure & Investigation of Techniques Developed for Ultrasonic Exam of Flange IR 05000269/19860241986-09-19019 September 1986 Insp Repts 50-269/86-24,50-270/86-24 & 50-287/86-24 on 860908.No Noncompliance or Deviations Noted.Major Areas Inspected:Operations,Surveillance,Maint,Verification of ESF Lineups & Followup Items IR 05000269/19860211986-08-15015 August 1986 Insp Repts 50-269/86-21,50-270/86-21 & 50-287/86-21 on 860708-0811.No Noncompliance or Deviation Noted.Major Areas Inspected:Operations,Surveillance,Maint,Verification of ESF Lineups & Followup of Events IR 05000269/19860221986-08-0101 August 1986 Partially Withheld Insp Repts 50-269/86-22,50-270/86-22 & 50-287/86-22 on 860711 (Ref 10CFR2.790 & 73.21).Violation Noted:Individual Inside Vital Area Wore Invalid Picture Badge IR 05000269/19860151986-05-28028 May 1986 Insp Rept 50-269/86-15 on 860423-25.No Violations or Deviations Noted.Major Areas Inspected:Ultrasonic Exam of Mockup Reactor vessel-to-flange Weld for Correlation of Reflectors Between Vessel & Mockup IR 05000269/19860071986-05-15015 May 1986 Insp Repts 50-269/86-07,50-270/86-07 & 50-287/86-07 on 860317-0512.No Violations or Deviations Noted.Major Areas Inspected:Low Level Radwaste Burial Site & Startup Review of Low Level Radwaste Incinerator IR 05000269/19860121986-04-25025 April 1986 Insp Repts 50-269/86-12,50-270/86-12 & 50-287/86-12 on 860331-0404.No Violations or Deviations Noted.Major Areas Inspected:Annual Emergency Preparedness Exercise IR 05000269/19860041986-04-0404 April 1986 Insp Repts 50-269/86-04,50-270/86-04 & 50-287/86-04 on 860211-0310.No Violation Noted.Major Areas Inspected: Operations,Surveillance,Maint,Verification of ESF Lineups & Refueling Activities IR 05000269/19860081986-04-0202 April 1986 Insp Repts 50-269/86-08,50-270/86-08 & 50-287/86-08 on 860303-07.No Violation or Deviation Noted.Major Areas Inspected:Unit 1 Sludge Cleaning of once-through Steam Generator by Water Slap Method & IE Bulletin 82-02 ML20199G4451986-03-25025 March 1986 Insp Repts 50-269/86-05,50-270/86-05 & 50-287/86-05 on 860224-28.Violation Noted:Failure to Provide Adequate Respiratory Protective Equipment to Maintain Intakes of Radioactive Matl ALARA IR 05000269/19860091986-03-20020 March 1986 Insp Repts 50-269/86-09,50-270/86-09 & 50-287/86-09 on 860306.No Violation or Deviation Noted.Major Areas Inspected:Steam Generator Cleaning & Maint Re Secondary Water Cycle ML20210H4081986-03-20020 March 1986 Insp Repts 50-269/86-01,50-270/86-01 & 50-287/86-01 on 860114-0210.Violation Noted:Failure to Follow Procedure During Channel C Calibr & Functional Test,Resulting in Reactor Trip from 100% Power IR 05000269/19860061986-03-14014 March 1986 Insp Repts 50-269/86-06,50-270/86-06 & 50-287/86-06 on 860224-27.No Violations or Deviations Noted.Major Areas Inspected:Switchyard Surveillance Testing,Containment Isolation Valve Test Witnessing & Procedure Review IR 05000269/19860031986-03-12012 March 1986 Insp Repts 50-269/86-03,50-270/86-03 & 50-287/86-03 on 860218-21.No Violation or Deviation Noted.Major Areas Inspected:Inservice Insp,Work Observation Data Review & Evaluation & Main Feedwater flow-nozzle Mod IR 05000269/19850421986-02-11011 February 1986 Insp Repts 50-269/85-42,50-270/85-42 & 50-287/85-42 on 851216-20.Violation Noted:Failure to Provide Positive Access Control for Two High Radiation Areas ML20137U5451986-02-11011 February 1986 Insp Repts 50-269/85-41,50-270/85-41 & 50-287/85-41 on 851210-860113.Noncompliance Noted:Failure to Follow Exempt Change Procedure & Failure to Shut Down Reactor within 24 H of Discovery of Excessive Leakage ML20154K8981986-02-0707 February 1986 Insp Repts 50-269/85-39,50-270/85-39 & 50-287/85-39 on 851209-13 & 860114.Violation Identified in Area of Physical Barrier - Protected Area.Rept Details Withheld (Ref 10CFR2.790 & 73.21) IR 05000269/19850401986-01-13013 January 1986 Insp Repts 50-269/85-40,50-270/85-40 & 50-287/85-40 on 851209-13.No Violation or Deviation Identified.Major Areas Inspected:Maint & Surveillance Testing of Main Steam Safety Relief & Pressurizer Code Safety Relief Valves IR 05000269/19850381985-12-13013 December 1985 Insp Repts 50-269/85-38,50-270/85-38 & 50-287/85-38 on 851112-1209.No Noncompliance or Deviations Noted.Major Areas Inspected:Operations,Surveillance,Maint,Startup Testing of Safe Shutdown Facility & LER Review ML20137E4031985-11-21021 November 1985 Insp Repts 50-269/85-37,50-270/85-37 & 50-287/85-37 on 851008-1111.Noncompliance Noted:Failure to Document Malfunctioning Valve 3LP-2 in Reactor Operator & Senior Reactor Operator Log IR 05000269/19850351985-10-28028 October 1985 Insp Repts 50-269/85-35,50-270/85-35 & 50-287/85-35 on 851007-11.No Violation or Deviation Noted.Major Areas Inspected:Review & Witnessing of Pre & post-criticality Tests Following Refueling Outage & Info Notice Followup 1994-01-06
[Table view] Category:UTILITY
MONTHYEARIR 05000269/19900321990-11-0505 November 1990 Partially Withheld Insp Repts 50-269/90-32,50-270/90-32 & 50-287/90-32 on 901015-19.No Violations Noted.Major Areas Inspected:Physical Security Program Plans,Mgt Support, Security Program Plans & Protected & Vital Area Barriers IR 05000269/19900221990-07-24024 July 1990 Partially Withheld Safeguard Insp Repts 50-269/90-22, 5-270/90-22 & 50-287/90-22 on 900625-29.No Violations or Deviation Noted.Major Areas Inspected:Core Insp Program for Power Reactors & Safeguards Contingency Plan Implementation IR 05000269/19900181990-06-21021 June 1990 Partially Withheld Insp Repts 50-269/90-18,50-270/90-18 & 50-287/90-18 on 900604-08 (Ref 10CFR2.790 & 73.21).No Violations Noted.Major Areas Inspected:Security Program Audit,Detection & Assessment Aids & Key Control IR 05000269/19890201989-07-25025 July 1989 Partially Withheld Insp Repts 50-269/89-20,50-270/89-20 & 50-287/89-20 on 890626-30 (Ref 10CFR2.790.(d) & 73.21). Violations Noted.Major Areas Inspected:Physical Security Program for Power Reactors & Security Audit IR 05000269/19890091989-04-10010 April 1989 Insp Repts 50-269/89-09,50-270/89-09 & 50-287/89-09 on 890306-10.No Violations Noted.Weaknesses Noted Re Data Base Used to Prepare computer-generated Work Requests.Major Areas Inspected:Design Control,Mods & Open Items IR 05000269/19890071989-03-10010 March 1989 Insp Repts 50-269/89-07,50-270/89-07 & 50-287/89-07 on 890213-17.Deviation Noted.Major Areas Inspected:Conformance to Reg Guide 1.97 Re Instrumentation for light-water-cooled Plants to Assess Conditions During & Following Accident IR 05000269/19880051988-03-21021 March 1988 Insp Repts 50-269/88-05,50-270/88-05 & 50-287/88-05 on 880217-0316.No Violations Noted.Major Areas Inspected:Maint, Operations,Surveillance,Physical Security & Design Changes IR 05000269/19870101987-03-17017 March 1987 Insp Repts 50-269/87-10,50-270/87-10 & 50-287/87-10 on 870210-0309.No Violations or Deviations Noted.Major Areas Inspected:Areas of Operations,Surveillance,Maint,Followup of Events & Verification of ESF Lineups IR 05000269/19870091987-03-17017 March 1987 Insp Repts 50-269/87-09,50-270/87-09 & 50-287/87-09 on 870209-13.No Violations Noted.Major Areas Inspected:Onsite Review of Liquid & Gaseous Radwaste Programs & Review of TMI Action Items II.B.3 & II.F.1.2 IR 05000269/19870061987-03-0909 March 1987 Insp Repts 50-269/87-06,50-270/87-06 & 50-287/87-06 on 870126-30.No Violations or Deviations Noted.Major Areas Inspected:Inservice Insp,Ongoing Repairs in Reactor Coolant Pumps & Maint & Welding Activities IR 05000269/19870041987-02-17017 February 1987 Insp Repts 50-269/87-04,50-270/87-04 & 50-287/87-04 on 870113-0209.No Violation or Deviation Noted.Major Areas Inspected:Operations,Surveillance,Maint,Verification of ESF Linups,Followup of Events & Shutdown Work in Progress IR 05000269/19870021987-02-11011 February 1987 Partially Withheld Insp Repts 50-269/87-02,50-270/87-02 & 50-287/87-02 on 870126-30 (Ref 10CFR2.790).Violation Noted Re Inadequate App R Circuit Analysis IR 05000269/19870031987-02-10010 February 1987 Insp Repts 50-269/87-03,50-270/87-03 & 50-287/87-03 on 870112-16.Violation Noted:Failure to Adequately Evaluate Radiological Hazards IR 05000269/19860341987-02-0505 February 1987 Corrected Insp Repts 50-269/86-34,50-270/86-34 & 50-287/86-34 on 861111-870112.Insp Erroneously Reported as Having Been Conducted on 861111-0112 IR 05000269/19870071987-02-0505 February 1987 Enforcement Conference Repts 50-269/87-07,50-270/87-07 & 50-287/87-07 on 861222.Major Areas Discussed:Sequence of Events & Corrective Actions Re Emergency Condenser Circulating Water Sys Degradation IR 05000269/19870081987-02-0505 February 1987 Enforcement Conference Repts 50-269/87-08,50-270/87-08 & 50-287/87-08 on 861222.Major Areas Discussed:Safety Sys Functional Insp & Associated Safety Implications IR 05000269/19870011987-01-30030 January 1987 Insp Repts 50-269/87-01,50-270/87-01 & 50-287/87-01 on 870105-08.Violation Noted:Failure to Provide Procedures W/Appropriate Qualitative or Quantitative Acceptance Criteria for Activities Important to Safety ML20211A0061987-01-23023 January 1987 Insp Repts 50-269/86-34,50-270/86-34 & 50-287/86-34 on 861111-870112.No Violations or Deviations Noted.Major Areas Inspected:Operations,Surveillance,Maint,Verification of ESF Lineups & Emergency Drills IR 05000269/19860351987-01-0707 January 1987 Insp Repts 50-269/86-35,50-270/86-35 & 50-287/86-35 on 861208-12.No Violations or Deviations Noted.Major Areas Inspected:Radiation Protection Program,Including Review of Organization & Mgt of Health Physics Staff IR 05000269/19860321986-12-10010 December 1986 Insp Repts 50-413/86-44,50-414/86-47,50-369/86-32, 50-370/86-32,50-269/86-32,50-270/86-32 & 50-287/86-32 on 861103-12.Violations Noted:Failure to Follow Procedures for Radiological Sample Analyses & Inadequate Surveys IR 05000269/19860281986-11-0303 November 1986 Partially Withheld Physical Security Insp Repts 50-269/86-28,50-270/86-28 & 50-287/86-28 on 861014-17 (Ref 10CFR2.790 & 73.21).Violation Noted:Inadequate Protected Area Barrier IR 05000269/19860301986-10-23023 October 1986 Partially Withheld Physical Security Insp Rept 50-269/86-30 on 861007-09 (Ref 10CFR2.790 & 73.21).No Violation Noted. Major Areas Inspected:Physical Protection of Irradiated Reactor Fuel During Transportation Between Sites IR 05000269/19860231986-09-23023 September 1986 Insp Repts 50-269/86-23,50-270/86-23 & 50-287/86-23 on 860826-29.No Violation or Deviation Noted.Major Areas Inspected:Inservice Insp,Review of Procedure & Investigation of Techniques Developed for Ultrasonic Exam of Flange IR 05000269/19860241986-09-19019 September 1986 Insp Repts 50-269/86-24,50-270/86-24 & 50-287/86-24 on 860908.No Noncompliance or Deviations Noted.Major Areas Inspected:Operations,Surveillance,Maint,Verification of ESF Lineups & Followup Items IR 05000269/19860211986-08-15015 August 1986 Insp Repts 50-269/86-21,50-270/86-21 & 50-287/86-21 on 860708-0811.No Noncompliance or Deviation Noted.Major Areas Inspected:Operations,Surveillance,Maint,Verification of ESF Lineups & Followup of Events IR 05000269/19860221986-08-0101 August 1986 Partially Withheld Insp Repts 50-269/86-22,50-270/86-22 & 50-287/86-22 on 860711 (Ref 10CFR2.790 & 73.21).Violation Noted:Individual Inside Vital Area Wore Invalid Picture Badge IR 05000269/19860151986-05-28028 May 1986 Insp Rept 50-269/86-15 on 860423-25.No Violations or Deviations Noted.Major Areas Inspected:Ultrasonic Exam of Mockup Reactor vessel-to-flange Weld for Correlation of Reflectors Between Vessel & Mockup IR 05000269/19860121986-04-25025 April 1986 Insp Repts 50-269/86-12,50-270/86-12 & 50-287/86-12 on 860331-0404.No Violations or Deviations Noted.Major Areas Inspected:Annual Emergency Preparedness Exercise IR 05000269/19860041986-04-0404 April 1986 Insp Repts 50-269/86-04,50-270/86-04 & 50-287/86-04 on 860211-0310.No Violation Noted.Major Areas Inspected: Operations,Surveillance,Maint,Verification of ESF Lineups & Refueling Activities IR 05000269/19860081986-04-0202 April 1986 Insp Repts 50-269/86-08,50-270/86-08 & 50-287/86-08 on 860303-07.No Violation or Deviation Noted.Major Areas Inspected:Unit 1 Sludge Cleaning of once-through Steam Generator by Water Slap Method & IE Bulletin 82-02 ML20199G4451986-03-25025 March 1986 Insp Repts 50-269/86-05,50-270/86-05 & 50-287/86-05 on 860224-28.Violation Noted:Failure to Provide Adequate Respiratory Protective Equipment to Maintain Intakes of Radioactive Matl ALARA IR 05000269/19860091986-03-20020 March 1986 Insp Repts 50-269/86-09,50-270/86-09 & 50-287/86-09 on 860306.No Violation or Deviation Noted.Major Areas Inspected:Steam Generator Cleaning & Maint Re Secondary Water Cycle ML20210H4081986-03-20020 March 1986 Insp Repts 50-269/86-01,50-270/86-01 & 50-287/86-01 on 860114-0210.Violation Noted:Failure to Follow Procedure During Channel C Calibr & Functional Test,Resulting in Reactor Trip from 100% Power IR 05000269/19860061986-03-14014 March 1986 Insp Repts 50-269/86-06,50-270/86-06 & 50-287/86-06 on 860224-27.No Violations or Deviations Noted.Major Areas Inspected:Switchyard Surveillance Testing,Containment Isolation Valve Test Witnessing & Procedure Review IR 05000269/19860031986-03-12012 March 1986 Insp Repts 50-269/86-03,50-270/86-03 & 50-287/86-03 on 860218-21.No Violation or Deviation Noted.Major Areas Inspected:Inservice Insp,Work Observation Data Review & Evaluation & Main Feedwater flow-nozzle Mod IR 05000269/19850421986-02-11011 February 1986 Insp Repts 50-269/85-42,50-270/85-42 & 50-287/85-42 on 851216-20.Violation Noted:Failure to Provide Positive Access Control for Two High Radiation Areas ML20137U5451986-02-11011 February 1986 Insp Repts 50-269/85-41,50-270/85-41 & 50-287/85-41 on 851210-860113.Noncompliance Noted:Failure to Follow Exempt Change Procedure & Failure to Shut Down Reactor within 24 H of Discovery of Excessive Leakage ML20154K8981986-02-0707 February 1986 Insp Repts 50-269/85-39,50-270/85-39 & 50-287/85-39 on 851209-13 & 860114.Violation Identified in Area of Physical Barrier - Protected Area.Rept Details Withheld (Ref 10CFR2.790 & 73.21) IR 05000269/19850401986-01-13013 January 1986 Insp Repts 50-269/85-40,50-270/85-40 & 50-287/85-40 on 851209-13.No Violation or Deviation Identified.Major Areas Inspected:Maint & Surveillance Testing of Main Steam Safety Relief & Pressurizer Code Safety Relief Valves IR 05000269/19850381985-12-13013 December 1985 Insp Repts 50-269/85-38,50-270/85-38 & 50-287/85-38 on 851112-1209.No Noncompliance or Deviations Noted.Major Areas Inspected:Operations,Surveillance,Maint,Startup Testing of Safe Shutdown Facility & LER Review ML20137E4031985-11-21021 November 1985 Insp Repts 50-269/85-37,50-270/85-37 & 50-287/85-37 on 851008-1111.Noncompliance Noted:Failure to Document Malfunctioning Valve 3LP-2 in Reactor Operator & Senior Reactor Operator Log IR 05000269/19850351985-10-28028 October 1985 Insp Repts 50-269/85-35,50-270/85-35 & 50-287/85-35 on 851007-11.No Violation or Deviation Noted.Major Areas Inspected:Review & Witnessing of Pre & post-criticality Tests Following Refueling Outage & Info Notice Followup IR 05000269/19850341985-10-24024 October 1985 Insp Repts 50-269/85-34,50-270/85-34 & 50-287/85-34 on 850930-1004.No Violation or Deviation Noted.Major Areas Inspected:Fire Protection/Prevention & Followup on Previously Identified Items IR 05000269/19850321985-10-23023 October 1985 Insp Repts 50-269/85-32,50-270/85-32 & 50-287/85-32 on 850910-1007.No Noncompliance or Deviation Noted.Major Areas Inspected:Operations,Surveillance,Maint,Offsite Review Committee & Startup from Refueling IR 05000269/19850331985-10-17017 October 1985 Insp Repts 50-269/85-33,50-270/85-33 & 50-287/85-33 on 850923-26.No Violation or Deviation Noted.Major Areas Inspected:Unit 3 Inservice Insp,Review & Record Evaluation & Main Feedwater Flow Nozzle post-weld Heat Treatment IR 05000269/19850311985-10-11011 October 1985 Insp Repts 50-269/85-31,50-270/85-31 & 50-287/85-31 on 850923-27.No Violation or Deviation Noted.Major Areas Inspected:Reactor Bldg Tendon Surveillance Program & Surveillance of Pipe Support & Restraints ML20138M5601985-10-0808 October 1985 Insp Repts 50-269/85-30,50-270/85-30 & 50-287/85-30 on 850916-20.Violation Noted:Failure to Label Containers of Radioactive Matl ML20141A0191985-10-0202 October 1985 Insp Repts 50-269/85-28,50-270/85-28 & 50-287/85-28 on 850903-06.Violation Noted:Inadequate Procedure for Documentation of Vital Area Barrier Insp.Details Withheld (Ref 10CFR2.790(d) & 73.21) ML20133C7481985-09-24024 September 1985 Insp Repts 50-269/85-27,50-270/85-27 & 50-287/85-27 on 850903-06.Violations Noted:Failure to Use Qualified Weld Procedures & to Obtain Final QA Approval on Reactor Coolant Pump Replacement Bolts Prior to Startup ML20132C2821985-09-13013 September 1985 Insp Repts 50-269/85-26,50-270/85-26 & 50-287/85-26 on 850813-0909.Violation Noted:Failure to Follow Procedures for E-bar Determination 1990-07-24
[Table view] Category:TEXT-INSPECTION & AUDIT & I&E CIRCULARS
MONTHYEARPNO-II-97-065, on 971228,initiated Controlled Shutdown of Unit Due to Exceeding TS Leakage Limit of 150 Gpd.Licensee Continuing W/Plant Depressurization & Cooldown & Outage Planned of Several Days to Investigate & Repair SG1997-12-29029 December 1997 PNO-II-97-065:on 971228,initiated Controlled Shutdown of Unit Due to Exceeding TS Leakage Limit of 150 Gpd.Licensee Continuing W/Plant Depressurization & Cooldown & Outage Planned of Several Days to Investigate & Repair SG ML20211K9431997-09-26026 September 1997 Notice of Violation from Insp on 970721-26.Violation Noted: Licensee Failed to Follow Procedures for Security Badges & Access Control of Facility ML20210S0391997-08-27027 August 1997 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $330,000.Violation Noted:Between 970501-02,w/ Fuel in Oconee Unit 3 Core & RCS Temp Greater than 350 F, Licensee Failed to Maintain HPI Sys Operable as Required PNO-II-97-034, on 970613,extended Shutdown to Meet CAL 2-97-03 Commitments to Shutdown Unit 1 No Later than 970614 & to Implement Actions Re HPI Sys.Nrc Resident Inspector Will Followup on Unit 1 Shutdown & Recovery Activities1997-06-13013 June 1997 PNO-II-97-034:on 970613,extended Shutdown to Meet CAL 2-97-03 Commitments to Shutdown Unit 1 No Later than 970614 & to Implement Actions Re HPI Sys.Nrc Resident Inspector Will Followup on Unit 1 Shutdown & Recovery Activities IR 05000269/19930321994-01-0606 January 1994 Insp Repts 50-269/93-32,50-270/93-32,50-287/93-32, 50-369/93-31,50-370/93-31,50-413/93-35 & 50-414,respectively on 931213-17.Violations Noted.Major Areas Inpected:Licensee Safeguards Info Program to folow-up on Licensee Repts PNO-II-93-039, on 930823,reactor Trip Occurred Due to Loss of Power to Vital Panelboard.Investigation Team Dispatched to Site to Review Root Cause & Plant Response.State & Local Authorities Notified1993-08-24024 August 1993 PNO-II-93-039:on 930823,reactor Trip Occurred Due to Loss of Power to Vital Panelboard.Investigation Team Dispatched to Site to Review Root Cause & Plant Response.State & Local Authorities Notified IR 05000269/19930061993-03-22022 March 1993 Partially Withheld Insp Repts 50-269/93-06,50-270/93-06 & 50-287/93-06 on 930222-25 (Ref 10CFR73.21).No Violations or Deviations Noted.Major Areas Inspected:Licensee Physical Security Program for Power Reactors IR 05000269/19930011993-02-0101 February 1993 Safeguards Insp Repts 50-269/93-01,50-270/93-01 & 50-287/93-01 on 930104-07.No Violations Noted.Major Areas Inspected:Physical Security Program.Details Withheld (Ref 10CFR73.21) IR 05000269/19920251992-12-0303 December 1992 Insp Repts 50-269/92-25,50-270/92-25 & 50-287/92-25 on 921102-06.No Violations or Deviations Noted.Major Areas Inspected:Physical Security Program for Power Reactors, Audits,Protected & Vital Area Barriers.Details Withheld PNO-II-92-070, on 921019,several Circuit Breakers Failed in 230KV Switchyard to Open Position for Unknown Reasons. Licensee Has Inititated Investigation to Review Event to Determine Cause & Determine Why Certain Equipment Failed1992-10-20020 October 1992 PNO-II-92-070:on 921019,several Circuit Breakers Failed in 230KV Switchyard to Open Position for Unknown Reasons. Licensee Has Inititated Investigation to Review Event to Determine Cause & Determine Why Certain Equipment Failed PNO-II-91-074B, on 911123,unit Remained in Cold Shutdown,Per Declaration of Alert at 0214 Due to Leak in Rcs.As of 911126,total of 7,800 Gallons of Treated Water Released from Plant to Lake Hartwell1991-11-26026 November 1991 PNO-II-91-074B:on 911123,unit Remained in Cold Shutdown,Per Declaration of Alert at 0214 Due to Leak in Rcs.As of 911126,total of 7,800 Gallons of Treated Water Released from Plant to Lake Hartwell ML20134D2581991-06-0404 June 1991 Notice of Violation from Insp on 910312-15.Violations Noted:Station Was Not Maintained According to Main Procedure MP/0/A/1800/105,Section 6.5,which Clearly Identified That Flange Was to Be Installed on Valve 3LP19 IR 05000269/19910081991-04-10010 April 1991 Insp Repts 50-269/91-08,50-270/91-08 & 50-287/91-08 on 910312-15.violations Noted.Major Areas Inspected:Maint, Control Room Operation,Planning & Scheduling Activities, Training & Procedures,Plant Physical Condition & Mgmt PNO-II-90-070, on 901108,unit Commenced Controlled Shutdown from 60% Power Due to Tube Leak in Steam Generator a1990-11-0808 November 1990 PNO-II-90-070:on 901108,unit Commenced Controlled Shutdown from 60% Power Due to Tube Leak in Steam Generator a IR 05000269/19900321990-11-0505 November 1990 Partially Withheld Insp Repts 50-269/90-32,50-270/90-32 & 50-287/90-32 on 901015-19.No Violations Noted.Major Areas Inspected:Physical Security Program Plans,Mgt Support, Security Program Plans & Protected & Vital Area Barriers IR 05000269/19900241990-10-0202 October 1990 SALP Repts 50-269/90-24,50-270/90-24,50-287/90-24 & 72-0004/90-24 for Feb 1989 - Jul 1990 IR 05000269/19900221990-07-24024 July 1990 Partially Withheld Safeguard Insp Repts 50-269/90-22, 5-270/90-22 & 50-287/90-22 on 900625-29.No Violations or Deviation Noted.Major Areas Inspected:Core Insp Program for Power Reactors & Safeguards Contingency Plan Implementation IR 05000269/19900181990-06-21021 June 1990 Partially Withheld Insp Repts 50-269/90-18,50-270/90-18 & 50-287/90-18 on 900604-08 (Ref 10CFR2.790 & 73.21).No Violations Noted.Major Areas Inspected:Security Program Audit,Detection & Assessment Aids & Key Control IR 05000269/19890201989-07-25025 July 1989 Partially Withheld Insp Repts 50-269/89-20,50-270/89-20 & 50-287/89-20 on 890626-30 (Ref 10CFR2.790.(d) & 73.21). Violations Noted.Major Areas Inspected:Physical Security Program for Power Reactors & Security Audit IR 05000269/19890101989-05-19019 May 1989 Partially Withheld Insp Repts 50-269/89-10,50-270/89-10 & 50-287/89-10 on 890410-14 (Ref 10CFR2.790 & 73.21). Violations Noted.Major Areas Inspected:Mgt Support,Security Program Plans & Audits & Protected & Vital Area Barriers IR 05000269/19890091989-04-10010 April 1989 Insp Repts 50-269/89-09,50-270/89-09 & 50-287/89-09 on 890306-10.No Violations Noted.Weaknesses Noted Re Data Base Used to Prepare computer-generated Work Requests.Major Areas Inspected:Design Control,Mods & Open Items IR 05000269/19890071989-03-10010 March 1989 Insp Repts 50-269/89-07,50-270/89-07 & 50-287/89-07 on 890213-17.Deviation Noted.Major Areas Inspected:Conformance to Reg Guide 1.97 Re Instrumentation for light-water-cooled Plants to Assess Conditions During & Following Accident IR 05000269/19880051988-03-21021 March 1988 Insp Repts 50-269/88-05,50-270/88-05 & 50-287/88-05 on 880217-0316.No Violations Noted.Major Areas Inspected:Maint, Operations,Surveillance,Physical Security & Design Changes PNO-II-88-013, on 880211,two Workers Slightly Contaminated W/ Radioactive Water.Caused by Approx 1,000 Gallon Leak of Radioactive Water Occurring During Maint on Valve.Workers Showered to Remove Contamination1988-02-12012 February 1988 PNO-II-88-013:on 880211,two Workers Slightly Contaminated W/ Radioactive Water.Caused by Approx 1,000 Gallon Leak of Radioactive Water Occurring During Maint on Valve.Workers Showered to Remove Contamination ML20237B2261987-12-15015 December 1987 EN-87-017A:informs That 870309 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $25,000 Withdrawn Due to Determination That Violation Did Not Occur. Violation Based on Failure of Emergency Feedwater Pumps ML20235T5821987-09-18018 September 1987 Exam Rept 50-269/OL-87-02 on 870713-23.Exam Results:Seven of Ten Reactor Operator (RO) & Eight of Nine Senior Reactor Operator (SRO) Candidates Passed Written Exam.All RO & SRO Candidates Passed Operating Exam ML20238F7081987-09-0909 September 1987 Exam Rept 50-269/OL-87-01 for Units 1,2 & 3 on 870713-17. Exam results:7 of 10 Reactor Operators & 3 of 6 Senior Reactor Operators Passed ML20236E5111987-07-14014 July 1987 EN-86-056:on 870717,notice of Violation & Proposed Imposition of Civil Penalty in Amount of $25,000 Will Be Issued to Licensee.Action Based on Failure to Properly Implement Startup Procedure Causing Trains to Fail IR 05000269/19870091987-03-17017 March 1987 Insp Repts 50-269/87-09,50-270/87-09 & 50-287/87-09 on 870209-13.No Violations Noted.Major Areas Inspected:Onsite Review of Liquid & Gaseous Radwaste Programs & Review of TMI Action Items II.B.3 & II.F.1.2 IR 05000269/19870101987-03-17017 March 1987 Insp Repts 50-269/87-10,50-270/87-10 & 50-287/87-10 on 870210-0309.No Violations or Deviations Noted.Major Areas Inspected:Areas of Operations,Surveillance,Maint,Followup of Events & Verification of ESF Lineups ML20207T5431987-03-12012 March 1987 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $25,000.Noncompliance Noted:Measures Not Established to Assure That Regulatory Requirements & Design Bases Correctly Translated Into Specs,Drawings & Procedures IR 05000269/19870061987-03-0909 March 1987 Insp Repts 50-269/87-06,50-270/87-06 & 50-287/87-06 on 870126-30.No Violations or Deviations Noted.Major Areas Inspected:Inservice Insp,Ongoing Repairs in Reactor Coolant Pumps & Maint & Welding Activities ML20207R4851987-03-0909 March 1987 EN-87-017:on 870312,notice of Violation & Proposed Imposition of Civil Penalty in Amount of $25,000 Will Be Issued to Util Based on Failure to Provide Adequate Design Control to Ensure Emergency Feedwater Pump Operability IR 05000269/19870041987-02-17017 February 1987 Insp Repts 50-269/87-04,50-270/87-04 & 50-287/87-04 on 870113-0209.No Violation or Deviation Noted.Major Areas Inspected:Operations,Surveillance,Maint,Verification of ESF Linups,Followup of Events & Shutdown Work in Progress IR 05000269/19870021987-02-11011 February 1987 Partially Withheld Insp Repts 50-269/87-02,50-270/87-02 & 50-287/87-02 on 870126-30 (Ref 10CFR2.790).Violation Noted Re Inadequate App R Circuit Analysis ML20211A4991987-02-11011 February 1987 Notice of Violation from Insps on 870112-16 IR 05000269/19870031987-02-10010 February 1987 Insp Repts 50-269/87-03,50-270/87-03 & 50-287/87-03 on 870112-16.Violation Noted:Failure to Adequately Evaluate Radiological Hazards ML20210U3211987-02-0505 February 1987 Notice of Violation from Insp on 861015-1110.Violation Noted:For Periods in 1978,1981 & 1986 When Lake Keowee Elevation Less than 792 Ft,Emergency Condenser Cooling Water Sys Inoperable & Unable to Provide Sustained Siphon Flow IR 05000269/19870071987-02-0505 February 1987 Enforcement Conference Repts 50-269/87-07,50-270/87-07 & 50-287/87-07 on 861222.Major Areas Discussed:Sequence of Events & Corrective Actions Re Emergency Condenser Circulating Water Sys Degradation IR 05000269/19870081987-02-0505 February 1987 Enforcement Conference Repts 50-269/87-08,50-270/87-08 & 50-287/87-08 on 861222.Major Areas Discussed:Safety Sys Functional Insp & Associated Safety Implications IR 05000269/19860341987-02-0505 February 1987 Corrected Insp Repts 50-269/86-34,50-270/86-34 & 50-287/86-34 on 861111-870112.Insp Erroneously Reported as Having Been Conducted on 861111-0112 ML20211A0871987-02-0303 February 1987 Notice of Violation from Insp on 870105-08 IR 05000269/19870011987-01-30030 January 1987 Insp Repts 50-269/87-01,50-270/87-01 & 50-287/87-01 on 870105-08.Violation Noted:Failure to Provide Procedures W/Appropriate Qualitative or Quantitative Acceptance Criteria for Activities Important to Safety ML20211A0061987-01-23023 January 1987 Insp Repts 50-269/86-34,50-270/86-34 & 50-287/86-34 on 861111-870112.No Violations or Deviations Noted.Major Areas Inspected:Operations,Surveillance,Maint,Verification of ESF Lineups & Emergency Drills ML20210U9961987-01-22022 January 1987 Exam Rept 50-269/OL-86-03 on 861215.Exam Results:Two Reactor Operator Candidates Passed Written Reexam.Written Exam Questions & Answer Key Encl IR 05000269/19860351987-01-0707 January 1987 Insp Repts 50-269/86-35,50-270/86-35 & 50-287/86-35 on 861208-12.No Violations or Deviations Noted.Major Areas Inspected:Radiation Protection Program,Including Review of Organization & Mgt of Health Physics Staff ML20212F5511986-12-24024 December 1986 Notice of Violation from Insp on 861103-12 PNO-II-86-092, on 861218,licensee Shut Down Unit to Begin Scheduled Refueling Outage 6 Wks Early.Caused by Excessive Vibrations in Reactor Coolant Pump 3B2.During Outage,Reactor Coolant Pumps 3B1,3B2 & 3A1 Will Be Modified1986-12-18018 December 1986 PNO-II-86-092:on 861218,licensee Shut Down Unit to Begin Scheduled Refueling Outage 6 Wks Early.Caused by Excessive Vibrations in Reactor Coolant Pump 3B2.During Outage,Reactor Coolant Pumps 3B1,3B2 & 3A1 Will Be Modified IR 05000269/19860321986-12-10010 December 1986 Insp Repts 50-413/86-44,50-414/86-47,50-369/86-32, 50-370/86-32,50-269/86-32,50-270/86-32 & 50-287/86-32 on 861103-12.Violations Noted:Failure to Follow Procedures for Radiological Sample Analyses & Inadequate Surveys IR 05000269/19860281986-11-0303 November 1986 Partially Withheld Physical Security Insp Repts 50-269/86-28,50-270/86-28 & 50-287/86-28 on 861014-17 (Ref 10CFR2.790 & 73.21).Violation Noted:Inadequate Protected Area Barrier 1997-09-26
[Table view] |
See also: IR 05000729/2008002
Text
DD080u UNITED STATES
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Report Nos.: 50-269/85-21, 50-270/85-21, and 50-287/85-21
Licensee: Duke Power Company
422 South Church Street
Charlotte, NC 28242
Docket Nos.: 50-269, 50-270, and.50-287 License Nas.- DPR-38, DPR-47, and
DPR-55
Facility Name: Oconee 1, 2, and 3
Inspection Conducted: July 29 - August 2, 1985
Inspectors: N38
L. E. Foster, Team Leader 'Date Signed
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N. Merr weather Y
L- _f Date
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M. J. Davi s
& ')ff .3/ff
Date Signed
Consultant: P. M. Chan, Lawrence Livermore National Laboratory
Approved by a; 7 d/-P(
T. E. Conlon, Section Chief Date Signed
Division of Reactor Safety
SUMMARY
Scope: This special, announced inspection entailed 124 inspector-hours on site
concerning _liccusee response to Generic Letter 83-28, Required Actions Based on
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Generic Implications of Salem Anticipated Transient Without Scram (ATWS) Events.
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Areas inspected included: post-trip review; equipraent classification; vendor
interface and manual control; post-maintenance testing; and reactor trip system
reliability.
Results: Two violations were identified: Failure to Follow Procedure During
Classification of Work Request, paragraph 7 and Inadequacies in Development and .
Implementation of Procedure MP/0/A?2001/4, CRD _ Breaker Inspection. and
Maintenance, paragraph 9.
8509260482 850913
PDR ADOCK 05000269
G PDR
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REPORT *0ETAILS
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1. Persons Contacted
Licensee Employees
- J. Pope, Superintendent of Operations
- T. Owen, Superintendent of Maintenance
- W. McAlister, Instrumentation and Electrical (I&E) Engineer
! *T. Glenn, I&E Support Engineer
1
- T. Matthew, Compliance Technical Specialist
D. Clardy, Planning and Scheduling Supervisor.
, *R. Bond, Compliance Engineer
D. Phillips, Electrical Foreman
D. Gibson, Vendor Manual Group Clerk
- G..Edens, Support Engineer .
i G. Davenport, Performance Engineer _
j B. McKinney, Electrician >
- L. Evans, Electrician
T.-Graham, I&E Specialist
S.-Henderson, Document. Control
R. Murrell, I&E Specialist ,
M. Roach, Administrative Supervisor
B. Loftis, I&E Engineer
D. Larson, Planning'& Scheduling
! C. Phouletter, Planner and Scheduler
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A. Green, Planner and Scheduler L
- P. Waltman, Quality Assurance
- F. Siurua, I&E Associate Engineer
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C. Parsons, Performance' Engineer .
.
L. Staggers, Document Control Clerk-
! Other -licensee employees contacted included engineers, technicians,
! operators, mechanics, security force members, and office personnel.
NRC Resident Inspectors
j *J. C. Bryant, Senior Resident Inspector
,
- L. King, Resident Inspector.
j * Attended exit interview
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2. Exit Interview.
l The inspection scope and fin' dings were summarized on August 2,1985, with
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those persons. indicated-in paragraph 1 above. . The inspector described the
- areas inspected and . discussed in detail the inspection x findings. No
- dissenting comments were received from the licensee.
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Violation 50-269/85-21-01, Failure to Follow Procedure During Classifi-
cation of Work Requests, paragraph 7.
I- Inspector Followup Item 50-269,270,287/85-21-02, Review of Purchase
Orders for Undervoltage Devices, paragraph 3. '
Violation 50-269,270,287/85-21-03, Inadequacies in Development and .
Implementation of Procedure MP/0/A/2001/4, CR0 Breaker Inspection and
Maintenance, paragraph 9. ;
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- The licensee did not identify as proprietary any of the materials provided
! to or reviewed by the inspectors during this inspection.
3. Licensee Action on Previous Enforcement Matters
f This subject was not addressed in the inspection.
, 4. Unresolved Items ;
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$ No unresolved items were identified during this inspection.
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i 5. Background
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In February'1983, the Sal'em' Nuclear Power Station experienced two failures
of the reactor trip system upon the receipt of trip signals. These failures
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were attributed to Westinghcuse - Type DB-50 reactor . trip system (RTS)
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circuit breakers. The failures.at Salem on . February 22 'and 25,1983, were
believed to have been caused by a binding action within the undervoltage
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trip attachment (UVTA) located inside the breaker-cubicle. Due to problems
! of -the circuit breakers at Salem and 'at othar plants, NRC issued Generic
!
Letter 83-28, Required Actions Based on Generic Implications of . Salem
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ATWS Events, dated July 8, 1983. This letter required the . licensees to
respond on immediate-term actions to ensure reliability of the RTS. Actions
- to be performed included development of programs to provide for post-trip
review, classification of equipment, vendor interface, post-maintenance
.' testing, and RTS reliability improvement. The licensee responded to Generic
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Letter 83-28 by correspondence with the following dates: November 4,1983;
i December 30, '1983, January 17, . 1984; February 2, 1984; July 5, 1984; ,
! August 10,1984; March 20,1985; March 29,1985; and April 25, 1985. This !
! inspection was performed to review :the licensee's current program, planned
i program improvements, and implementation of present . procedures associated
with post-trip review, equipment - classi fication, vendor interface, post-
main.tenance testing, and reactor- trip system reliability' for Oconee Unit
Nos. 1,-2, and 3.
6. Post-Trip Review
The : licensee was requested in {GL 83-28 to describe .their program, proce-
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dures,- and data collection capability to assure -that the causes for
unscheduled- reactor shutdowns, as' well as the . response of safety-related
i equipment, are fully understood prior to. plant re s ta rt'. The licensee's.
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response to GL 83-28 gives a description of the program and procedures
2 pertinent to performing post-trip reviews. The inspector reviewed their
- response, appropriate procedures, and interviewed r.esponsible licensee
} personnel to assess the adequacy of the licensee's program for post-trip
- reviews. .
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The' licensee has prepared and revised procedures to define responsibilities,
authorities, methods of assessment, training, and equipment needed to
perform a timely technical post trip review. Their program and implementa-
tion observed are discussed below:
.
The Oconee post-trip review program is addressed and implemented by
- Performance Manual Chapte'r 4.7, " Support of Reactor Trips -
- Performance" and by Operations Management Procedure 1-8, " Investigation.
- of Reactor Trips".
!
'The Shift Supervisor, Operations Unit Engineer, and Operations Duty
Engineer are responsible for' determining the cause of any reactor trip.
j The Performance Duty Eng.neer is responsible for conducting an indepen-
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dent evaluation of the reactor trip event. These activities are
- documented by the completion of the " Post-Trip Review Report", which is
, an attachment to Performance Manual Chapter 4.7.
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ny unplanned manual or automatic trip will require a full post trip
review report and the assembly of plant data which may include events .
j recorder printout, alarm typer printout, Transient Monitor Computer
. output in graph or table form, strip charts, operator interviews, and
logbooks.
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! Prior to restart of the unit,-operations personnel must ensure that:
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The immediate cause of the reactor trip is known or has been
iavestigated to the fullest extent possible while remaining in the '
shutdown condition.
Plant transient behavior did not identify unresolved problems that .
, could impact the ability of the unit to be safely restarted and operated.
Any malfunction or failures in equipment - or components subject to
Technical Specifications requirements are-evaluated and corrected prior
to restart.
Operations shall ensure that 'the Reactor Engineer's recommendations are
resolved prior to restart and shall obtain his/her concurrence with restart-
as indicated by . the Reactor Engineer's signature on the trip recoveiy
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operating - procedure or documented in the SR0 log. The Station' Manager, or
his designee, is required to resolve disagreements between Operations. and
the Reactor Engineer regarding necessary corrective action.
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If the immediate cause of the reactor trip cannot be determined, or if any
unresolved safety issues exist, or if compliance with licensing requirements
is in question, then an independent review is performed by a group of
knowledgeable individuals identified by the Station -Manager. This group
makes a recommendation on restart to the Station Manager, or his designee,
who then resolves the restart decision.
Each reactor trip is subsequently evaluated by the Compliance Section in
accordance with Compliance Manual Section 5.1, "Non-Routine ~ Events
Reporting". An incident investigation report is prepared that includes the
following:
Information and data collected during the Post-Trip Review.
A Sequence of Events describing all action taken and system / equipment
performance curing the event that materially affected the course of the
event.
An assessment of the plant transient behavior that identifies any
deviations from expected plant performance and that documents the
behavior of key plant parameters.
An assessment of the performance of protection and Engineered Safety
systems during the transient, identifying any malfunctions or failure
to perform as expected.
An assessment of other equipment failures that contributed to the
event.
An assessment of personnel performance and procedure adequacy relevant
to the event.
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A description of corrective actions taken or planned as a result of the
event.
Post-Trip Review packages are maintained in fire-resistant file cabinets in
'tne Performance Engineering Office.
The inspector reviewed post-trip data review packages generated for eight
reactor trips that occurred in 1985 and and seven reactor trips that
occurred in 1984. The packages were thorough and adequately documented the
events.
The inspector conducted p review of licensee procedures to verify that they
were consistent with licensee responses to GL 83-28. The following proce-
dures were reviewed:
Compliance Manual Section 5.1, Non-Routine Events Reporting, 11/9/84
Operations Management Procedure 2-1, Duties of the Reactor Operators on
the Control Board, the SRO in the Control Room, and the STA, 4/17/85
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Operations Management Procedure 1-8, Investigation of Reactor Trips,
11/1/84
Performance Manual Section 4-7, Support of Reactor Trips - Performance,
9/21/84
Operations Management Procedure 1-3, Operations Duty Engineer, 3/13/85 ,
Operations Management Procedure 1-1, Administration of Operations
Management Procedures, 12/3/84
Performance Manual Section 3.1, Procedures - Performance, 3/26/85 -
Operations Management Procedure 3-1, Operations Training, 11/1/84
c Station Directive 4.5.1, Non-Routine Events Reporting, 12/1/84
The licensee is preparing to replace the General Electric (GE) PAC 4020
- plant computer systems with the Honeywell 45000 computer systems over the
j next three years. The alarm typer output device is associated .with the
plant computer. Digital alarms and change of status indications of safety-
{ related pumps, valves, and motors are printed on the typer to the nearest
secon,d . This device is powered by. a non-class IE, non-interruptible AC
- source.
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The Transient Manitor System is a dedicated computer system. Data is
received .via hardwired inputs one per second and stored on a hard disk. ,
Data output can be in either graph or table form. The parameters recorAd
by the transient monitor document the pre-trip and post-trip behavior of the
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primary system, secondary system, important Balance of Plant (BOP) systems,
and safety systems. The transient monitor is powered by a non-class IE AC
source which is interruptible but will automatically transfer to the onsite
- AC backup on loss of power.
The' Events Recorder is a dedicated computer system which monitors equipment
and components pertinent to reactor trip investigations. Output is on a
paper tape and the time of each event is recorded, with' discrimination down
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to one-millisecond, along with the parameter number. This de'vice is powered
by a non-class IE AC source which is interruptible but will automatically-
transfer to the onsite AC backup on loss of power. Additionally, 'a safety-
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related non-interruptible DC backup power supply is provided.
, The licensee is -i_n the process ~ of installing the Safety Parameter Display
System (SPDS) ~ data collection and processing system associated with the
NUREG 0737. upgrade of Emergency Response-facilities. Although, the current
. data. and information collection . systems are adequate for the evaluation of
unplannedr ' eactor trips, the new system should enhance the plants' data
colledtion capabilities.
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Interviews revealed that plant personnel preparing and/or reviewing the
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, post-trip documentation were familiar with plant systems, equipment, and
plant operation.
Within the areas examined, no violations or deviations were identified.
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7. Equipment Classification
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-The licensee was requested in Sections 2.1 and 2.2 of GL 83-28 to confirm
that all components of the reactor trip system whose function is required to
trip the reactor are identified as safety-related. This identification was
i to be on documents,-procedures, and information handling systems used in the
i plant to control safety-related activities including maintenance, work !
, orders, and parts replacement. In addition, the licensee was requested to i
- describe their program for ensuring that all components of otSer safety-
i related systems necessary for accomplishing required safety functions are
also identified as safety related on informa' tion handling systems used at '
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the plant. The licensee's response to Sections 2.1 and 2.2 of GL 83-28
. gives a detailed description of the program and procedures for safety-
. related equipment classificatio.n. The licensee makes the following state-
ments in-their respon:e dated November 4, 1983:
i " Station specific documents provide the mechanism for the determination
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of whether or not a given station structure, system, or component is
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safety-related. This document is provided to appropriate station and
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general office personnel and is entitled, "0conee Nuclear Station
Safety-Related Structures, Systems, and Components Manual".
The ' inspector reviewed their response, appropriate procedures, and inter-
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viewed responsible licen'see personnel to verify if the licensee's program
i for equipment classification was adequate and consistent with the above
response. During this inspection, the inspector- reviewed the following'
i procedures and documents listed below:
Oconee Nuclear Station Maintenance Directive III.8, Work Request
Planning, Revision dated April 16, 1984
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Oconee Nuclear Station Directive 3.2.1, Work Request,. Revision dated
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July 8,;1985
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Quality Standards fer Structures, Systems, and Components
Oconee Nuclear - Station Directive 4.5.4, QA Condition Det'erminations,
- Revision dated December 1, 1984
Technical Specification 6.'4, Station Operating Procedures
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Duke Power Company Steam Production Department Administrative Policy l
Manual for Nuclear-Stations- '
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As stated above, the licensee has developed the Quality Standards Manual for
Structures, Systems, and Components which identifies safety-related
components. The intent of this procedure is to identify both mechanical and
electrical safety-related components. The inspector reviewed the procedure
and found it to be somewhat general in identifying safety-related
components. Interviews with planning department personnel pointed out a
weakness with the piping drawings in identifying safety-related instruments.
The licensee acknowledged that the Q-Lists are to general and that they are
considering improving the Q-Lists with more detail. Section 4 of this
procedure also includes an instruction for making component classifications.
The inspectar reviewed four equipment classification evaluations for the
following plant components:
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Inlet and Outlet Thermometers on SSF AC Unit
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Valve 250-325
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3MS - 140
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Filters on SSF HVAC Equipment
No concerns were identified with the equipment classification evaluations
reviewed.
The inspector randomly selected several work requests (WRs) for examination
to verify that work activities were being properly, classified as safety-
related or non-safety-related as required by the above procedures. The work
requests reviewed and associated classifications assigned are identified
below:
Work Request No. Classification
225188 Nonsafety
56263 Safety-Related
56890 Safety-Related
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56888 Safety-Related
22840B Nonsafety
83761B Nonsafety
22790B Nonsafety
22549B Nonsafety
51724D Nonsafety
23178B Safety-Related
23030B Safety-Related
22827B Nonsafety
22843B Nonsafety
50197C Nonsafety
50196C Nonsafety
23070B Nonsafety
228388 Nonsafety
23071B Nonsafety
230698 Nonsafety
23068B Nonsafety
54666C Safety-Related'
23108C Nonsafety
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!~ In reviewing the above WRs, the inspector identified a discrepancy in the
way the licensee was classifying the calibration of the power range instru-
mentation channels 5, 6, 7 and 8 (channels A, B, C, and D respectively af
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Reactor Protection) on WR 22790B, dated July 17, 1985. The licensee
identified this WR as non-safety-related. Subsequent to this WR on July 20,
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1985, the licensee identified WR 23020B as safety-related QA condition 1.
Tne inspector reviewed the Quality Standards' Manual for Structures, Systems,
and Components and determined that the power. range nuclear instrumentation
! is classified as safety-related. The work required by the work sequence on ' '
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both work requests required the calibration of the NIs using Instrument
Procedure IP/0/A/301/3T, Reactor Protective System ?ower Range Calibration '
at Power. This procedure is con'sidered to be safety-related; however, the
reviews required prior to performing a non-safety WR are not the same
reviews required for a safety-related work request. QA condition WRs are
require'd by Station Maintenance Directive III.E to be reviewed by the
- Station QA Section. The licensee was informed of the above discrepancy with
the safety classification of WR 227908. The licensee considered this to be
, an isolated case of failing to properly classify 'a safety-related WR for
l nuclear instrument (NI) calibrations. At-the request of the inspector, the
licensee ran a computer sort of the work history for power ~ range nuclear
instruments for calendar years 84 and 85 to determine if this wa s ' an
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isolated case. The results of this computer . sort indicated that the .
licensee had misclassified five (5) work requests as non-safety. The five
WRs which were misclassified are~ identified below:
WR No. Date Work Description
020835B 04/28/85 Perform NI Calibration
. 018401B 01/19/85 Please Calibrate NIs s
~0227908 07/17/85 Calibrate NIs as Required on Power
Escalation
10/30/84 Perform.NI Calibration
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016545B-
020141B 03/29/85' Reset RPS Channels #A, B, C, D to
-Hi Pwr Trip
10 CFR 50, Appendix B', Criterion V requires activities affecting quali~ty to
' be performed in accordance with instructions, procedures, or drawings.
Station Directive 2.2.1 implements the requirements of 10 CFR 50,
Appendix B, Criterion V as it requires activities to be. conducted in
accordance~with the provisions of the applicable procedure.
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Station Of rective 5.4.5 defines how to use the Quality Standards Manual for
Structures, Systems, and Components (QSMSSC) in the determination of QA
condition classifications on Maintenance . Work Requests (MWRs), material
requisitions, and procedures. This directive states that "the Quality
Standards Manual for Structures, . Systems, and Components shall be used to
' determine QA condition level." The _ QSMSSC identi.fies power range nuclear
instruments as safety-related.
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Contrary to the above, WR 22790B was improperly classified as non-safety-
related. Consequently, the WR had not been reviewed by the station QA
section. This constitutes Violation 50-269/85-21-01, Failure to Follow
Procedure on Classification of Work Requests. This problem may be generic
to safety-related components at Oconee since the Q-List is very gener al .
Therefore, the licensee should consider auditing other WRs to verify that
they have been properly classified. In addition, the licensee should review
the training provided plant personnel responsible for classifying safety-
related work activities to ensure that personnel perform correct classifica-
tions.
8. Vendor Interface and Manual Control
The inspector reviewed the licensee's response to GL 83-28 which described
their program for vendor interface and control of vendor technical informa-
tion. Their response described the following program:
Licensee response dated November 4,1983, stated that the Reactor Trip
System components were originally supplied by Babcock and Wilcox (B&W)
and that current updates to this equipment were being supplied by the
B&W Owners Group. The licensee acknowledges receipt of the information
by written confirmation. All technical information received which has
an impact on plant design, maintenance, and safe operation is distri-
buted to appropriate ' licensee organizations for review, approval, and
incorporation into plant procedures as applicable. The licensee has
procedures to assure that vendor information is controlled.
Procedure OEMA/IM-1, Receipt and Distribution of Operating Experience
Information, describes how technical information will be properly received,
screened, and distributed to licensee personnel. Review of this procedure
confirmed that the licensee has a method to receive and use operating
experience information and, if properly imp ~lemented, will be an asset to
plant operation and maintenance activities.
-The licensee's procedure, Nuclear Steam Supply System (NSSS) Vendor Informa-
tion Letters, identifies responsibilities, describes the activities, and
summarizes the process used for attaining resolution to vendor information
letters. The procedure also states that revisions to station procedures and
vendor manuals will be implemented through the station procedure change
process and through the vendor manual change process. The Nuclear Technical
Services Group is responsible for assessing the applicability of tFa vendor
information letters and implementing necessary corrective actions. The
inspector could not find, nor did the licensee identify, a list, log, or
status report of vendor information letters received and resultant review
aad implementation actions being performed by the different Duke departments
as described in the procedure. The reactor trip breaker maintenance
procedure did not contain all recommendations specified in GE Advisory
Letters TAB 175-9.3 and 175-9.3S, nor did ~the licensee provide justification
why the recommendations were not included in the licensee's procedure. The
failure to include vendor recommendations in procedures or justification for
not including is discussed further in paragraph 9 of this report. The
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licensee has completed some modifications and i s in the process of
completing the modifications concerning the shunt trip, undervoltage device, ,
and replacement of bearings with ones that contain Mobil 28 lubricant. !
Licensee's response dated March 29, 1985, specified that their preventative
- maintenance program had been structured to be .in ' accordance with GE
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Maintenance Instruction GEI-50299EI; however, Revision E was not referenced
in the procedure and was n'ot in document control. Licensee referenced
GEI-50299A and the Master Copy'was 50299A instead of 50299EI. The inspector
loaned the technical support group his copy 'of GEI-50299E so they could
compare it with 50299A.
Information obtained during. reactor trip breaker performance is bcing
transmitted by. the licensee to the B&W Owners Group for tre'nding purposes.
The B&W Owners Group will provide recommendations resulting from evaluation
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of performance data received from other plants.
The licensee has started a program to review all vendor manuals associated
with safety-related equipment. The licensee has a special Vendor Manual
j Group assigned full time to review onsite vendor manuals and to prepare a
j Master Copy of each manual. The Master Copy will include all up-to-date
- technical information. .After completion of the update, controlled copies of
J" the manuals are being redistributed to approved satellite files per inter-
station memo which require recipients to transmit an ' acknowledgement
receipt. The licensee also utilizes a formal form (18527) for transmittal
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of documents to the Master File. A Record of Verification Form (02665 of
3-83) is being used by the Vendor Manual Group to verify that the manuals
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l. have been proofread and corrections have been included. The use of this
form wea discussed with the Administrative Supervisor. Other forms such as
Insertion Control Form (01045) and Design Engineering Transmittal Form
(01190) are also being used to control vendor information. 'The Vendor
Manual Group maintains a " Station Backfit Log" which lists' the documents
reviewed, corrective action needed, and date. of final review. A monthly
- audit '(status) report is being continually updated to show-'the number of
manuals updated and discrepancies resolved. The inspector discussed the
program with licensee personnel, observed the verification in process and
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examined manuals in the' Document. Control Area. The licensee has several-
procedures to help assure that- technical information is properly received,
reviewed, and controlled. The licensee appears f to be extending an all out
effort on . updating and controlling vendor manuals.
The inspector reviewed the licensee's Procedure MP/0/A/2001/4 dated June 6,
1985, CRD Breaker Inspection and Maintenance. The procedure review revealed
the following concerns: GE Technical Manuals were incorrectly referenced;
GE Advisory Letters were not referenced; approved cleaning solvents were not
- - specified; repair..as necessary statement does not provide for control of
work or require maintenance personnel to document findings; engineering was
not required to evaluate damage and evaluate causative factors; item 11.4
} does not specify the trip method (electrical or mechanical); item 11.5 does
not reference where the 50 and 80 msec. c< '
-rom; cautions on ~ using
cleaning agents are not specified; pressur '
compressed air is not
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specified; how to replace or repair arc chutes was not specified or
i . referenced; paragraph 11.8 allows equivalent lube to be used, although the
type of lubricant previously used was partly the cause of poor operation;
the latest tests by the. vendor requires Mobil 28 lubricant for the bearing,
therefore, it is presumed the breakers are qualified if Mobil 28 is used,
, yet the procedure allows an equilivant lube to be used; paragraph 11.15 does
- not specify that a special tool is required to manually trip the breaker;
l' paragraph 11.16 does not follow GE recommendations as GE recommends that the
. pickup voltage be checked three quick times, however, the procedure only
specifies one time; QA/QC personnel have minimal involvement throughout.the
repair and maintenance activity, except for verifying certain hold points;
the caution note on Mobil 28 should be located prior to paragraph 11.14; the ,
text of the procedure does not require the recording of as-found informa-
tion, however, Enclosures ~13.3a and 3b (Reliability Data Sheets) have spaces
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for as-found and as-left data; paragraph 11.16 requirds the UV device be
! near room temperature prior ' to testing, however, the procedure does not
specify a minimum or maximum room temperature; the procedure does not .
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specify disassembly of UV devices, however, the licensee was disassembling.
the UV devices, inspecting, and reassembling; GE Service Advice Letters
Nos. 175-9.20, 175-9.3, and 9.3S were not referenced, although some informa-' i
tion from these was used. The above comments on the procedure were discuss- t
ed with licensee personnel. Some of-the above comments are further discussed-
2
in paragraph 9 and contribute to the violation.
Discussions with personnel and observation of maintenance activities reveal-
ed that during the preventative maintenance (PM) on a reactor trip breaker,
the licensee has been disassembling the undervoltage trip device and examin-
ing the parts for damage as previously reported. The licensee informed the
inspector that the following discrepancies were found: sharp burrs existed
on the edges of the armature (where measurements are made) that contact the
,
rivet; indentation of the area of the armature that contacts with the rivet;
sharp edges where the armature pivoted against the magnet; rubbing between
the armature trip paddle and the heads of the two screws that attach the
trip device to the. mechanism frame; plus some wearing of the paint coatings
around the bearing area of the armature. The licensee has issued several
letters to the NRC (February 14, 1985, April 22, 1985, August 17, 1984, and
- August 27, 1984) concerning problems found with Oconee breaker front frame
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assemblies. These problems were also reported to 'the vendor. The basic
, problem appeared to be with the trip shaft bearing lubrication which is
being corrected by installing . bearings which have been lubricated with
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Mobil ~28 lubricant. The licensee is in the process of replacing all the
front frames of Oconee RTS ' breakers.
The- licensee reported on July 22, 1985 that during o'n-line testing of a
- reactor trip breaker (CB-1 on Channel C), the breaker took 1738 milliseconds
to open instead of the 80 milliseconds allowed. The licensee replaced the
breaker with a ~ spare and examined the faulty breaker. They suspected
interference between .the heads' of the UV mounting screws and the armature
trip paddle.
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The inspector examined a UV trip device to determine if the armature trip
paddle could interfere with the heads of the two attachment screws.. A
minimum clearance of approximately~ 0.025 ' inches was obtained with the
armature in its worst position. The licensee stated that this UV device was
an "old" one and that one of the two "new" ones (replacement for old UV
devices) actually had a rubbing condition and they had filed approximately
1/32 inch off the side of the screw heads to eliminate the rubbing condi-
tion. The licensee stated that the breaker passed its test prior to his
filing the screw heads. No detail drawings were available for review;
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therefore, it could not be determined if the rubbing could be the result of
design deficiencies.
The inspector examined another UV device which the licensee stated was an
"old" device. The inspector .noted that the location of the armature trip
paddle in relation to the attaching screw heads was different (had more
clearance) than the UV device previously examined. ;
-The. licensee stated that they had recently installed two new undervoltage
devices. Upon questioning whether these two new devices' were the same part
number as the old.UV devices, the licensee was unsure and could not confirm
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as the purchase order and receiving information was not readily available.
The . licensee stated that they would contact GE and resolve the part number 1
discrepancy .and the possible rubbing problem. . The purchase order and
] receiving information for 18 reactor trip breaker front frames were not
readily available for the inspectors' review; however, this information on
the front frames was reviewed by the NRC Resident Inspector on August 5,
1985 and was satisfactory. Until the licensee obtains information on the UV
4
device-part numbers at the site, this is considered Inspector Followup Item
50-269, 270, 287/85-21-02, Review of Purchase Orders for Undervoltage
Devices.
.
Within the area . examined, no violations or' deviations were iden'ti fied;
however, some of the findings contribute to the violation discussed in
l paragraph 9.
9. Post Maintenance Testing (Reactor Trip System Components)
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The Oconee Nuclear Station (ONS), Units 1, 2, and 3, have a total of 18 GE' ,
AK-2 low voltage power circuit breakers' (and 'four spares) in the Reactor
- Trip System (RTS). There are two AC breakers and four DC breakers in each -
Oconee unit. Since Units 2 and 3 were wired differently from Unit-1, two of- !
the. spare breakers (one AC and one DC) are for. Units 2 and 3, and the other 1
two spare breakers (one AC and one DC) are for Unit 1.
The inspector reviewed Maintenance _ Procedure MP/0/A/2001/4, CRD Breaker
Inspection and Maintenance and observed the performance of this procedure on i
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breaker Nos. U2 & 3-DC-9 and U2 & 3-AC-1. The maintenance being performed !
on the breakers was a regularly scheduled preventive - maintenance activity.
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'It involved checking out the two sp'ar'e breakers for Units 2 and 3 and <
! preparing them for replacing two Control Rod Drive (CRD) breakers that were
- scheduled to be removed from service for preventive maintenance.
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The work was performed by electricians trained on the job. Duke Power
Company (DPC), the licensee, maintains and renovates' circuit breakers,
including CRD breakers, with the -licensee's own staff. There is no formal
< training. program for electricians assigned to CRD breaker maintenance. _. The
electrical foreman leading the maintenance work on the CRD breakers stated
that "new" electricians with less ,than three years' experience are not
allowed -to do- CRD breaker maintenance work on their own. They work along-
- side electricians with more experience while receiving on-the-job training. '
Duke Power Company, the licensee, responded in their letter, dated April 25,
, 1985, st,ating that the requirement of GL 83-28, Section 3.1.2, had been
completely met by March 31, 1985. The inspector reviewed 'the licensee's
effort in meeting this GL 83-28 requirement and noted that the licensee had
i issued a revision to their maintenance procedure Mp/0/A/2001/4 for the
maintenance of'RTS circuit breakers. The inspector checked to see if the
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vendor' s recommendation.(in this case, GE's) were properly incorporated into
the licensee's maintenance procedure. GE had previously ' issued Service
Advice Tab 175, No. 9.3, and also a supplement No. 9.3S, dated April 15,
1983, which augmented and clarified some of the areas in the maintenance
check of the RTS breakers. The inspector noted that there were differences
in the licensee's maintenance manual when compared with the GE Service
Advisories. These items were discussed with the licensee's personnel and '
are enumerated below:
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a. The inspector observed'that the licensee personnel were performing the
maintenance and calibration-work on the RTS circuit breakers in a room
, adjacent to the hot and humid turbine generator high bay area. The
electrician's room was small and crowded, and the room temperature was
not being monitored. This is contrary to the licensee's procedure
where Section 11.16 required some assurance be made that the UV device
was near~ room temperature. It is contrary to the GE service advisory
which stated that, " Calibration should be. done at . room temperature
(approximately 20-25 C) after the device has been de-energized for
about one (1) hour."
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b. GE Service Advisory 9.3S stated that after the electricians administer
the three quick test trips, they should wait one hour-for-the UV device
to stabilize back to. room temperature' prior to recording additional
i pick-up and drop-out voltages. ' The GE advisory also states that . care
- should be taken on calibration checks to ensure that the coil temper-
ature remains close to room temperature. Contrary -to this,
Section 11.17 of the licensee's procedure does not require this wait
q period or a check of coil temperature. Further, the writer of the
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licensee's procedure: stated that he -intended the trip tests be done
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. electrically, whereas the electricians performing the work stated that
they had performed .the trip both ways: electrically, as well as
mechanically. Misinterpretation of requirements could result in
misadjustments and other malfunctions.
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c. Another incidence of misinterpretation between the intention of the
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procedure writer and the practice of the electricians occurred during
performance of Section 1~1.17a. The procedure writer intended that the -
UV pick-up voltage be measured again in that section. However, the
-inspector noted that the electricians did not re perform the pick-up
- voltage measurement. Instead, the electrician recorded the pick-up
voltage that was set in the calibration process in previous Section
No. 11.16. Misinterpretations of this nature are exemplary lof the
looseness allowed during the implementation of this procedure. It also
indicates' a possible lack of communication between the different
departments in the licensee's organization. The inspector discussed
the importance of resolving misinterpretations prior to performing
maintenance activities and why QA/QC personnel should be more involved.
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d. The inspector noted that Section 9.0, Acceptance Requirements, contains
l- the limits and criteria for acceptance of all the parameters except the -
UV coil drop-out voltage. A review of the GE service ' advisory showed
that the manufacturer's recommendation for drop-out voltage is 30-60%
of nominal ' voltage. Inasmuch as the UV drop-out voltage was measured
and recorded as per procedure, there was no specified acceptance
criteria listed in the procedure. This is contrary to Criterion V of
10 CFR 50, Appendix B, which. requires that procedures contain accep-
tance criteria. However, examination of previous tests revealed that
the drop-out voltage was within the vendors recommendation of 30-60% of
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nominal voltage.
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e. The inspector noted that in the performance of Section No. 11.12 of the
procedure, the electricians removed the UV- device and completely
, disassembled it, thoroughly examined it,~ and carefully reassembled it.
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.However, Section No.11.12 of the procedure does not direct the elec -
! tricians to disassemble the UV device in the first place. The licensee
! responded that the practice of ' disassembling the UV device was under-
taken in the current cycle of RTS circuit breaker maintenance and that
. they intended to stop the practice once all 22 RTS circuit breakers in
the licensee's possession have received this.one-time scrutiny on their
, UV devices. The - inspector pointed out that procedures were developed
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to control activities and any deviation from procedure be documented in
the form of_a temporary procedure change with-all the additional steps
included in the proper sequence and that inspection results be record-
- -ed. Station Directive 2.2.1 (TS) dated December 1, 1984, describes the >
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licensee's methods to ' prepare, change, reissue, and de.lete procedures. '
, The. directive also provides guidance in the areas .of procedural adhe- ,
rence and use.
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Section 11.5 of the procedure referenced the FSAR for selection of the
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80 msec. limit specified; however, the . inspectors could not find the
specified 80 msec. limit in the FSAR. Upon discussion with the
licensee-_and further inspection, the 80. msec. limit was .found. in the
i Technical Specifications.
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The above findings, plus the additional items discussed in paragraph 8 i
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constitute Violation 50-269,270,287/85-21-03, Inadequacies in Development
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and ' Implementation of Procedure MP/0/A/2001/4, CRD Breaker. Inspection and
Maintenance. In summary, the inspectors concluded the following:
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The procedure did not include vendor recommendations as specified . in
advisory letters, and all were not referenced
The technical review.of this procedure appeared to be lacking due to
the number of discrepancies found by the inspectors.
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The ~importance of . having clear understandable procedures without
misinterpretation and the importance of strictly adhering to procedures
- appeared to be lacking.
Auditing of RTS maintenance activities, including observation of work,
to assure -that all activities are performed in a quality manner and
according to procedure was not apparent.
i The requirement to. perform post-maintenance testing and on-line sur-
veillance testing will help assure that ' equipment will function when
and required; however, ' procedures properly prepared, technically
rev.iewed, approved, , and properly implemented further assures that
equipment will function when needed,
g. To further evaluate the licensee's program, the inspector reviewed the
latest complete set of MWRs associated with work on the 22 RTS circuit ,
breakers. The WR numbers reviewed were: 54318C, 54315C, 56776,.56774,
56597, 56598, 56771, .56772, and 56773. The inspector examined the
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documents for consistency in the data taken, completeness in the
records, the type of preventive or corrective measures required, and
evidence of post-maintenance testing. No problems were -identified
. during review of these WRs.
! h. The following licensee procedures and documents were reviewed:
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Station Directive 3.2.1, Work Request, dated July 8,' 1985 !
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Instrument Procedure IP/2/A/305/3D, Instrument Procedure Data
1 Package for RPS Channel "D" Calibration and Functional. Test,; dated
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May 22, 1985
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Maintenance Directive III.D, Work . Request Completion', dated
May 14,-1984
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Maintenance Directive - III.8, . Work Request -Planning,. dated
April 16, 1985-
Maintenance Procedure MP/0/A/2001/4, CRD Breaker Inspection and
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-Maintenance, dated May.31, 1985
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Instrument Procedure IP/0/B/330/9, CRD System Check of CRD System
i Before Test Tripping of CRD Breakers
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Instrument Procedure IP/2/A/305/3, Nuclear Instrument and Reactor
, Protection System RP Channel Calibration,and Functional Test
i. The inspector also reviewed completed WRs on other safety-related
components to determine if post-maintenance testing was being im-
plemented. Seven WRs were selected for inspection . and are listed
below:
Work Request No. Work-Description
23178B Relay Repair
23030B Power Range Calibration
55052A. E/S System Test
057948 Repair Pump Leak
4
90153C Valve Repair
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50277C Valve-Repair
- 29055A1 Valve Repair
Except' for the findings discussed in items a-thru f, no other violations or
deviations were identified in this area.
Reactor Trip System Reliability
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10.
The. licensee stated in their responses to GL 83-28 that on-line functional
surveillance testing of individual Reactor Protection System Channelsw ' ill
be performed once per month. The licensee also stated that diverse. ' trip
features, including the breaker undervoltage'and shunt trip features will be
tested on a regular basis and that vendor recommendations would be evaluated
- and used where deemed applicable. - The~ licensee-had ordered and .had install-
ed some new reactor trip- breaker front frties which contained bearings
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] lubricated with Mobil 28 lubricant. Shunt trip ~and undervoltage devices
were being installed and tested,'plus preventive maintenance and testing of
- the-reactor trip-breakers was being implemented as discussed in paragraphs 8
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and.9. Data taken during' surveillance testing 'and maintenance inspection
are being transmitted to B&W Owners Group for trending purposes. The
l'- inspector observed the on-line testing of a reactor trip' breaker. Licensee
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. personnel . performed the operations as required by procedure. The inspector
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verified that the periodic maintenance program to ensure reliability describ-
ed in their. March 29, 1985 response was being implemented. Based on review
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of procedures and observation of work, -the licensee is implementing a
{ program to help ensure reactor trip ~ system reliability.
2
The following documents were reviewed:
PT/0/A/305/01, Reactor Manual Trip Test, approved October 11, 1984
Documentation Package for WR 972108, Addition of Shunt Trip Feature on
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CRD AC and DC breakers dated February 14, 1985.
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Procedure TN/2/A/2288, Ad'dition of Shunt Trip Feature, Revision 0
Document Package for Purchase Order No. K13589-76 for 22 Front Frames
for GE breakers dated March 6, 1984 (included receipt inspection
reports and certificates of conformance). Reviewed by Resident
Inspector on August 5, 1985 and in Region II office on August 16, 1985.
Purchase Order J20388-70 for Coil, Shunt Trip Devices dated April 26,
1983
Various Purchase Orders to B&W for Reactor Trip System Equipment and
Parts
Within the areas inspected, no violations or deviations were identified.
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