Insp Repts 50-275/98-11 & 50-323/98-11 on 980526-28.No Violations Noted.Major Areas Inspected:Circumstances, Potential Safety Consequences & Licensee Response & Actions Taken Re Authorization of Tagout W/O Written ProcedureML20236T380 |
Person / Time |
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Site: |
Diablo Canyon |
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Issue date: |
07/22/1998 |
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From: |
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
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To: |
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Shared Package |
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ML20236T345 |
List: |
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References |
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50-275-98-11, 50-323-98-11, NUDOCS 9807280145 |
Download: ML20236T380 (18) |
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Category:INSPECTION REPORT
MONTHYEARIR 05000275/19990121999-09-13013 September 1999 Insp Repts 50-275/99-12 & 50-323/99-12 on 990711-0821. Noncited Violations Noted.Major Areas Inspected:Aspects of Licensee Operations,Maint,Engineering & Plant Support IR 05000275/19990071999-07-27027 July 1999 Insp Repts 50-275/99-07 & 50-323/99-07 on 990503-0714. Apparent Violations Being Considered for Escalated Enforcement Action.Major Areas Inspected:Operations & Engineering IR 05000275/19980161998-11-16016 November 1998 Insp Repts 50-275/98-16 & 50-323/98-16 on 980913-1024.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000275/19980111998-07-22022 July 1998 Insp Repts 50-275/98-11 & 50-323/98-11 on 980526-28.No Violations Noted.Major Areas Inspected:Circumstances, Potential Safety Consequences & Licensee Response & Actions Taken Re Authorization of Tagout W/O Written Procedure IR 05000275/19980081998-04-17017 April 1998 Insp Repts 50-275/98-08 & 50-323/98-05 on 980202-06,23-27 & 0302-18.No Violations Noted.Major Areas Inspected: Engineering IR 05000275/19980031998-01-23023 January 1998 Insp Repts 50-275/98-03 & 50-323/98-03 on 980105-09.No Violations Noted.Major Areas Inspected:Implementation of Solid Radioactive Waste Mgt & Radioactive Matls Transportation IR 05000275/19940271994-12-21021 December 1994 Insp Repts 50-275/94-27 & 50-323/94-27 on 941016-1126. Violations Noted.Major Areas Inspected:Operational Safety Verification,Plant Maint,Surveillance Observation,Plant Support Activities & in-office Review of LERs IR 05000275/19900171990-10-22022 October 1990 Partially Withheld Safeguards Insp Repts 50-275/90-17 & 50-323/90-17 on 900924-1008.Noncited Violations Noted.Major Areas Inspected:Physical Security Program ML20245E9661989-07-31031 July 1989 Partially Withheld Insp Repts 50-275/89-20 & 50-323/89-20 on 890710-18 (Ref 10CFR2.790(d) & 73.21).No Violations Noted.Noncited Violation Noted Re Compensatory Measures. Major Areas Inspected:Physical Security Program IR 05000275/19890121989-04-18018 April 1989 Insp Repts 50-275/89-12 & 50-323/89-12 on 890403-07.No Violations or Deficiencies Noted.Major Areas Inspected: Followup on Previous Insp Findings & Operational Status of Emergency Preparedness Program IR 05000275/19890031989-02-0808 February 1989 Insp Repts 50-275/89-03 & 50-323/89-03 on 890117-26.No Noncompliance Noted.Major Areas Inspected:Nonroutine Events, Followup of Open Items,Radwaste Sys & Radiological Environ Monitoring & Transportation Activities IR 05000323/19870391987-11-17017 November 1987 Insp Rept 50-323/87-39 on 870805-1030.Violations Noted. Major Areas Inspected:Improperly Authorized Flame Heating of RHR Pipe on 870505 IR 05000275/19870321987-09-0101 September 1987 Mgt Meeting Repts 50-275/87-32 & 50-323/87-32 on 870817. Major Areas Discussed:Recent Plant Events & Apparent Problem Areas That Have Developed Since Last Mgt Meeting on 870306 IR 05000275/19870221987-06-23023 June 1987 Insp Rept 50-275/87-22 on 870520-22.Major Areas Inspected: Followup on Allegation File Number RV-87-A-0094 & Followup on Regional Open Items List IR 05000275/19870181987-05-0808 May 1987 Insp Repts 50-275/87-18 & 50-323/87-17 on 870420-24.No Noncompliance or Deviations Noted.Major Areas Inspected: Nonlicensed Staff Training,Followup of Part 21 Repts,Various Vital Areas & Equipment IR 05000275/19870011987-03-25025 March 1987 Insp Repts 50-275/87-01 & 50-323/87-01 on 870202-13. Violation Noted:Failure to Maintain Control Over Lubricants IR 05000275/19860331987-03-17017 March 1987 Insp Repts 50-275/86-33 & 50-323/86-31 on 861215-19. Deficiencies Noted.Major Areas Inspected:Implementation Program for Establishing & Maintaining Environ Qualification of Electrical Equipment Important to Safety IR 05000275/19870091987-03-11011 March 1987 Insp Repts 50-275/87-09 & 50-323/87-08 on 870223-27.No Noncompliance Noted.Major Areas Inspected:Followup of IE Bulletins,Vital Areas & Equipment IR 05000275/19870041987-02-20020 February 1987 Insp Repts 50-275/87-04 & 50-323/87-04 on 861228-870207.No Violations or Deviations Noted.Major Areas Inspected:Plant Operations,Maint & Surveillance Activities & Followup of Onsite Events,Open Items & LERs IR 05000275/19870071987-02-12012 February 1987 Insp Repts 50-275/87-07 & 50-323/87-06 on 870202-06. No Items of Noncompliance or Deviations Identified.Major Areas Inspected:Design,Design Changes & Mods & Followup on IE Notices & Nonconformance Repts IR 05000275/19870061987-02-0606 February 1987 Insp Rept 50-275/87-06 on 870112-13.Violation Noted: Notification of 870102 Emergency Plan Unusual Event Did Not Occur Until 95 Minutes After Declaration IR 05000275/19870031987-01-30030 January 1987 Insp Repts 50-275/87-03 & 50-323/87-03 on 870112-16.No Violations or Deviations Noted.Major Areas Inspected: Previous Insp Items,Transportation,Solid Waste,Licensee Identified Violation & Facility Tours IR 05000275/19860321987-01-30030 January 1987 Insp Repts 50-275/86-32 & 50-323/86-30 on 861109-1227 & 870116.No Violations or Deviations Noted.Major Areas Inspected:Plant Operations,Maint & Surveillance Activities, Followup of Onsite Events & Allegations IR 05000275/19870051987-01-28028 January 1987 Insp Repts 50-275/87-05 & 50-323/87-05 on 870112-16.No Noncompliance or Deviations Noted.Major Areas Inspected: Followup of NRC Technical Audit Branch Rept on Allegation Re Flat Spot on Reactor Coolant Piping in Unit 1 Containment IR 05000275/19860251986-09-17017 September 1986 Insp Rept 50-275/86-25 on 860825-29.No Violations Noted. Major Areas Inspected:Preparation for Refueling Activities IR 05000275/19860151986-06-0505 June 1986 Insp Rept 50-275/86-15 on 860428-0502.No Violations Noted. Major Areas Inspected:Operation,Maint & Surveillance Testing of Auxiliary Feedwater Sys.Unresolved Item Re Automatic Feedwater Sys Operability During Pump Maint Identified IR 05000275/19860141986-05-0909 May 1986 Enforcement Conference Repts 50-275/86-14 & 50-323/86-15 on 860425.Major Area Discussed:Licensee Action Plan to Correct Problem of Missed Tech Spec Surveillances.Noncompliance Noted Re Followup of LERs IR 05000275/19850381985-12-0909 December 1985 Insp Repts 50-275/85-38 & 50-323/85-36 on 851118-22.No Violation or Deviation Noted.Major Areas Inspected:Action on Previous Findings,Transportation Activities,Solid Waste Mgt Program,Low Level Waste Mgt & Licensee Events IR 05000275/19850321985-10-0808 October 1985 Insp Repts 50-275/85-32 & 50-323/85-29 on 850818-0928. Violation Noted:Nrc Inspector,Not on Approved Access List, Entered Class 1 safety-related Matl Storage Area Unescorted IR 05000275/19850241985-08-14014 August 1985 Insp Rept 50-275/85-24 on 850603-07.No Violations or Deficiencies Noted.Major Areas Inspected:Emergency Response Facilities Compliance W/Suppl 1 to NUREG-0737,including Technical Support Ctr & Operational Support Ctr IR 05000275/19850231985-07-30030 July 1985 Insp Rept 50-275/85-23 on 850610-28.Violation Noted: Weaknesses in Implementation of Qa/Qc Program Re Control of Measuring & Test Equipment & Unqualified Individual Assigned as Technician IR 05000323/20050101985-06-12012 June 1985 Insp Rept 50-440/85-17 on 850323-0510.Noncompliance Noted: Failure to Provide Adequate Administrative Procedural Controls & Failure to Adequately Accomplish Release for Test pre-test Checklist Verification IR 05000323/20050061985-05-22022 May 1985 Insp Repts 50-424/85-13 & 50-425/85-13 on 850323-0506.No Violations or Deviations Noted.Major Areas Inspected:Qa,Fire Protection/Prevention,Containment Dome Reinforcing Steel & Tendon Sheathing & Cavity Liner Plate Welding IR 05000275/19850141985-04-0303 April 1985 Insp Repts 50-275/85-14 & 50-323/85-02 on 850304-08.No Noncompliance or Deviation Noted.Major Areas Inspected:Area Insp,Licensee Actions on Previously Identified Items,Ie bulletins,10CFR50.55(e) Items & TMI Task Action Items IR 05000275/19840051984-06-0606 June 1984 IE Insp Rept 50-275/84-05 on 840326-30.No Violations or Deviations Noted.Major Areas Inspected:New Chemistry & Radiation Protection Dept Organization,Radiation Protection Training,Followup on Noncompliance & IE Info Notices IR 05000275/19820241982-08-0202 August 1982 IE Insp Rept 50-275/82-24 on 820712-15.No Noncompliance Noted.Major Areas Inspected:Plant Operations,Onsite Review Committee & Independent Insp IR 05000275/19820231982-07-30030 July 1982 IE Insp Repts 50-275/82-23 & 50-323/82-12 on 820721-23.No Noncompliance Noted.Major Areas Inspected:Followup on IE Circulars,Info Notices & Bulletins,Preoperational Testing & Monitoring Calibr IR 05000275/19820121982-07-28028 July 1982 IE Insp Repts 50-275/82-12 & 50-323/82-07 Have Been Canceled IR 05000275/19820221982-07-26026 July 1982 IE Insp Repts 50-275/82-22 & 50-323/82-11 on 820526-28 & 0628-0702.No Noncompliance Noted.Major Areas Inspected: Action on Previous Items,Mods to Piping & Electrical Raceway Supports & Unit 2 Vessel IR 05000275/19820211982-07-19019 July 1982 IE Insp Rept 50-275/82-21 on 820606-0703.No Noncompliance Noted.Major Areas Inspected:Plant Operations,Surveillance Testing,Physical Security,Maint,Ler Followup & Licensee QA Program IR 05000275/19820201982-06-28028 June 1982 IE Insp Repts 50-275/82-20 & 50-323/82-10 on 820506-28.No Noncompliance Noted.Major Areas Inspected:Implementation of Independent Verification Program Including Independence & Qualification of Personnel & Exam of QA Programs IR 05000275/19820191982-06-18018 June 1982 IE Insp Rept 50-275/82-19 on 820502-0604.No Noncompliance Noted.Major Areas Inspected:Plant Operations,Surveillance Testing,Physical Security,Maint,Ler Followup & QA Program IR 05000275/19820181982-06-15015 June 1982 IE Insp Rept 50-275/82-18 on 820426-30.No Noncompliance Noted.Major Areas Inspected:Plant Layout,General Employee Training,Chemistry & Radiation Protection Staff Training & NUREG-0737,Items II.B.3 & II.F.1 IR 05000275/19820161982-06-11011 June 1982 IE Insp Repts 50-275/82-16 & 50-323/82-09 on 820329-0402 & 0510-14.Noncompliance Noted:Class I Matl Released for Const Prior to Satisfying Established Matl Receiving,Handling & Processing QC Procedures IR 05000275/19820151982-06-11011 June 1982 IE Safeguards Insp Rept 50-275/82-15 on 820524-28.No Noncompliance Noted.Major Areas Inspected:Security Plan & Implementing Procedures,Security Organization Mgt & Security Program Audit.Details Withheld (Ref 10CFR73.21) IR 05000275/19780071978-05-26026 May 1978 IE Insp Rept 50-275/78-07 on 780227-0303.No Deviations or Items of Noncompliance Noted.Major Areas Inspected:Emergency Planning.Related Encls Include Various Allegations,Qa Matl & I Yin Notes.Partially Withheld Interviews & Notes Also Encl ML20154D4521971-07-22022 July 1971 Insp Rept 50-275/71-02 on 710723-25 & 30.No Enforcement Action Noted.Major Areas Inspected:Unresolved Items, Unusual Occurrences,Design Changes,Status of Const, Procedures & Records & Review of QC Sys for Components ML20212N7781970-12-30030 December 1970 Div of Compliance Insp Rept 50-275/70-05 on 701201-03.Major Areas Inspected:Status of Previously Identified Items of Concern,Discrepancy Repts & QA Audit Activities ML20212N7771970-11-12012 November 1970 Div of Compliance Insp Rept 50-323/70-02 on 700930,1001 & 13.Major Areas Inspected:Design of Steam Generator Supports. QA Procedures Officially Approved & in Use by Design Groups ML20154D8461970-10-16016 October 1970 Insp Rept 50-275/70-04 on 700915-16.No Nonconformance Noted. Major Areas Inspected:Qa/Qc Review for Fabrication & Erection of Steam Generator Supports & Review Status of Previously Reported Deficiencies 1999-09-13
[Table view] Category:NRC-GENERATED
MONTHYEARIR 05000275/19990121999-09-13013 September 1999 Insp Repts 50-275/99-12 & 50-323/99-12 on 990711-0821. Noncited Violations Noted.Major Areas Inspected:Aspects of Licensee Operations,Maint,Engineering & Plant Support IR 05000275/19990071999-07-27027 July 1999 Insp Repts 50-275/99-07 & 50-323/99-07 on 990503-0714. Apparent Violations Being Considered for Escalated Enforcement Action.Major Areas Inspected:Operations & Engineering IR 05000275/19980161998-11-16016 November 1998 Insp Repts 50-275/98-16 & 50-323/98-16 on 980913-1024.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000275/19980111998-07-22022 July 1998 Insp Repts 50-275/98-11 & 50-323/98-11 on 980526-28.No Violations Noted.Major Areas Inspected:Circumstances, Potential Safety Consequences & Licensee Response & Actions Taken Re Authorization of Tagout W/O Written Procedure IR 05000275/19980081998-04-17017 April 1998 Insp Repts 50-275/98-08 & 50-323/98-05 on 980202-06,23-27 & 0302-18.No Violations Noted.Major Areas Inspected: Engineering IR 05000275/19980031998-01-23023 January 1998 Insp Repts 50-275/98-03 & 50-323/98-03 on 980105-09.No Violations Noted.Major Areas Inspected:Implementation of Solid Radioactive Waste Mgt & Radioactive Matls Transportation IR 05000275/19940271994-12-21021 December 1994 Insp Repts 50-275/94-27 & 50-323/94-27 on 941016-1126. Violations Noted.Major Areas Inspected:Operational Safety Verification,Plant Maint,Surveillance Observation,Plant Support Activities & in-office Review of LERs IR 05000275/19900171990-10-22022 October 1990 Partially Withheld Safeguards Insp Repts 50-275/90-17 & 50-323/90-17 on 900924-1008.Noncited Violations Noted.Major Areas Inspected:Physical Security Program ML20245E9661989-07-31031 July 1989 Partially Withheld Insp Repts 50-275/89-20 & 50-323/89-20 on 890710-18 (Ref 10CFR2.790(d) & 73.21).No Violations Noted.Noncited Violation Noted Re Compensatory Measures. Major Areas Inspected:Physical Security Program IR 05000275/19890121989-04-18018 April 1989 Insp Repts 50-275/89-12 & 50-323/89-12 on 890403-07.No Violations or Deficiencies Noted.Major Areas Inspected: Followup on Previous Insp Findings & Operational Status of Emergency Preparedness Program IR 05000275/19890031989-02-0808 February 1989 Insp Repts 50-275/89-03 & 50-323/89-03 on 890117-26.No Noncompliance Noted.Major Areas Inspected:Nonroutine Events, Followup of Open Items,Radwaste Sys & Radiological Environ Monitoring & Transportation Activities IR 05000323/19870391987-11-17017 November 1987 Insp Rept 50-323/87-39 on 870805-1030.Violations Noted. Major Areas Inspected:Improperly Authorized Flame Heating of RHR Pipe on 870505 IR 05000275/19870321987-09-0101 September 1987 Mgt Meeting Repts 50-275/87-32 & 50-323/87-32 on 870817. Major Areas Discussed:Recent Plant Events & Apparent Problem Areas That Have Developed Since Last Mgt Meeting on 870306 IR 05000275/19870221987-06-23023 June 1987 Insp Rept 50-275/87-22 on 870520-22.Major Areas Inspected: Followup on Allegation File Number RV-87-A-0094 & Followup on Regional Open Items List IR 05000275/19870181987-05-0808 May 1987 Insp Repts 50-275/87-18 & 50-323/87-17 on 870420-24.No Noncompliance or Deviations Noted.Major Areas Inspected: Nonlicensed Staff Training,Followup of Part 21 Repts,Various Vital Areas & Equipment IR 05000275/19870011987-03-25025 March 1987 Insp Repts 50-275/87-01 & 50-323/87-01 on 870202-13. Violation Noted:Failure to Maintain Control Over Lubricants IR 05000275/19860331987-03-17017 March 1987 Insp Repts 50-275/86-33 & 50-323/86-31 on 861215-19. Deficiencies Noted.Major Areas Inspected:Implementation Program for Establishing & Maintaining Environ Qualification of Electrical Equipment Important to Safety IR 05000275/19870091987-03-11011 March 1987 Insp Repts 50-275/87-09 & 50-323/87-08 on 870223-27.No Noncompliance Noted.Major Areas Inspected:Followup of IE Bulletins,Vital Areas & Equipment IR 05000275/19870041987-02-20020 February 1987 Insp Repts 50-275/87-04 & 50-323/87-04 on 861228-870207.No Violations or Deviations Noted.Major Areas Inspected:Plant Operations,Maint & Surveillance Activities & Followup of Onsite Events,Open Items & LERs IR 05000275/19870071987-02-12012 February 1987 Insp Repts 50-275/87-07 & 50-323/87-06 on 870202-06. No Items of Noncompliance or Deviations Identified.Major Areas Inspected:Design,Design Changes & Mods & Followup on IE Notices & Nonconformance Repts IR 05000275/19870061987-02-0606 February 1987 Insp Rept 50-275/87-06 on 870112-13.Violation Noted: Notification of 870102 Emergency Plan Unusual Event Did Not Occur Until 95 Minutes After Declaration IR 05000275/19870031987-01-30030 January 1987 Insp Repts 50-275/87-03 & 50-323/87-03 on 870112-16.No Violations or Deviations Noted.Major Areas Inspected: Previous Insp Items,Transportation,Solid Waste,Licensee Identified Violation & Facility Tours IR 05000275/19860321987-01-30030 January 1987 Insp Repts 50-275/86-32 & 50-323/86-30 on 861109-1227 & 870116.No Violations or Deviations Noted.Major Areas Inspected:Plant Operations,Maint & Surveillance Activities, Followup of Onsite Events & Allegations IR 05000275/19870051987-01-28028 January 1987 Insp Repts 50-275/87-05 & 50-323/87-05 on 870112-16.No Noncompliance or Deviations Noted.Major Areas Inspected: Followup of NRC Technical Audit Branch Rept on Allegation Re Flat Spot on Reactor Coolant Piping in Unit 1 Containment IR 05000275/19860251986-09-17017 September 1986 Insp Rept 50-275/86-25 on 860825-29.No Violations Noted. Major Areas Inspected:Preparation for Refueling Activities IR 05000275/19860151986-06-0505 June 1986 Insp Rept 50-275/86-15 on 860428-0502.No Violations Noted. Major Areas Inspected:Operation,Maint & Surveillance Testing of Auxiliary Feedwater Sys.Unresolved Item Re Automatic Feedwater Sys Operability During Pump Maint Identified IR 05000275/19860141986-05-0909 May 1986 Enforcement Conference Repts 50-275/86-14 & 50-323/86-15 on 860425.Major Area Discussed:Licensee Action Plan to Correct Problem of Missed Tech Spec Surveillances.Noncompliance Noted Re Followup of LERs IR 05000275/19850381985-12-0909 December 1985 Insp Repts 50-275/85-38 & 50-323/85-36 on 851118-22.No Violation or Deviation Noted.Major Areas Inspected:Action on Previous Findings,Transportation Activities,Solid Waste Mgt Program,Low Level Waste Mgt & Licensee Events IR 05000275/19850321985-10-0808 October 1985 Insp Repts 50-275/85-32 & 50-323/85-29 on 850818-0928. Violation Noted:Nrc Inspector,Not on Approved Access List, Entered Class 1 safety-related Matl Storage Area Unescorted IR 05000275/19850241985-08-14014 August 1985 Insp Rept 50-275/85-24 on 850603-07.No Violations or Deficiencies Noted.Major Areas Inspected:Emergency Response Facilities Compliance W/Suppl 1 to NUREG-0737,including Technical Support Ctr & Operational Support Ctr IR 05000275/19850231985-07-30030 July 1985 Insp Rept 50-275/85-23 on 850610-28.Violation Noted: Weaknesses in Implementation of Qa/Qc Program Re Control of Measuring & Test Equipment & Unqualified Individual Assigned as Technician IR 05000323/20050101985-06-12012 June 1985 Insp Rept 50-440/85-17 on 850323-0510.Noncompliance Noted: Failure to Provide Adequate Administrative Procedural Controls & Failure to Adequately Accomplish Release for Test pre-test Checklist Verification IR 05000323/20050061985-05-22022 May 1985 Insp Repts 50-424/85-13 & 50-425/85-13 on 850323-0506.No Violations or Deviations Noted.Major Areas Inspected:Qa,Fire Protection/Prevention,Containment Dome Reinforcing Steel & Tendon Sheathing & Cavity Liner Plate Welding IR 05000275/19850141985-04-0303 April 1985 Insp Repts 50-275/85-14 & 50-323/85-02 on 850304-08.No Noncompliance or Deviation Noted.Major Areas Inspected:Area Insp,Licensee Actions on Previously Identified Items,Ie bulletins,10CFR50.55(e) Items & TMI Task Action Items IR 05000275/19840051984-06-0606 June 1984 IE Insp Rept 50-275/84-05 on 840326-30.No Violations or Deviations Noted.Major Areas Inspected:New Chemistry & Radiation Protection Dept Organization,Radiation Protection Training,Followup on Noncompliance & IE Info Notices IR 05000275/19820241982-08-0202 August 1982 IE Insp Rept 50-275/82-24 on 820712-15.No Noncompliance Noted.Major Areas Inspected:Plant Operations,Onsite Review Committee & Independent Insp IR 05000275/19820231982-07-30030 July 1982 IE Insp Repts 50-275/82-23 & 50-323/82-12 on 820721-23.No Noncompliance Noted.Major Areas Inspected:Followup on IE Circulars,Info Notices & Bulletins,Preoperational Testing & Monitoring Calibr IR 05000275/19820121982-07-28028 July 1982 IE Insp Repts 50-275/82-12 & 50-323/82-07 Have Been Canceled IR 05000275/19820221982-07-26026 July 1982 IE Insp Repts 50-275/82-22 & 50-323/82-11 on 820526-28 & 0628-0702.No Noncompliance Noted.Major Areas Inspected: Action on Previous Items,Mods to Piping & Electrical Raceway Supports & Unit 2 Vessel IR 05000275/19820211982-07-19019 July 1982 IE Insp Rept 50-275/82-21 on 820606-0703.No Noncompliance Noted.Major Areas Inspected:Plant Operations,Surveillance Testing,Physical Security,Maint,Ler Followup & Licensee QA Program IR 05000275/19820201982-06-28028 June 1982 IE Insp Repts 50-275/82-20 & 50-323/82-10 on 820506-28.No Noncompliance Noted.Major Areas Inspected:Implementation of Independent Verification Program Including Independence & Qualification of Personnel & Exam of QA Programs IR 05000275/19820191982-06-18018 June 1982 IE Insp Rept 50-275/82-19 on 820502-0604.No Noncompliance Noted.Major Areas Inspected:Plant Operations,Surveillance Testing,Physical Security,Maint,Ler Followup & QA Program IR 05000275/19820181982-06-15015 June 1982 IE Insp Rept 50-275/82-18 on 820426-30.No Noncompliance Noted.Major Areas Inspected:Plant Layout,General Employee Training,Chemistry & Radiation Protection Staff Training & NUREG-0737,Items II.B.3 & II.F.1 IR 05000275/19820161982-06-11011 June 1982 IE Insp Repts 50-275/82-16 & 50-323/82-09 on 820329-0402 & 0510-14.Noncompliance Noted:Class I Matl Released for Const Prior to Satisfying Established Matl Receiving,Handling & Processing QC Procedures IR 05000275/19820151982-06-11011 June 1982 IE Safeguards Insp Rept 50-275/82-15 on 820524-28.No Noncompliance Noted.Major Areas Inspected:Security Plan & Implementing Procedures,Security Organization Mgt & Security Program Audit.Details Withheld (Ref 10CFR73.21) IR 05000275/19780071978-05-26026 May 1978 IE Insp Rept 50-275/78-07 on 780227-0303.No Deviations or Items of Noncompliance Noted.Major Areas Inspected:Emergency Planning.Related Encls Include Various Allegations,Qa Matl & I Yin Notes.Partially Withheld Interviews & Notes Also Encl ML20154D4521971-07-22022 July 1971 Insp Rept 50-275/71-02 on 710723-25 & 30.No Enforcement Action Noted.Major Areas Inspected:Unresolved Items, Unusual Occurrences,Design Changes,Status of Const, Procedures & Records & Review of QC Sys for Components ML20212N7781970-12-30030 December 1970 Div of Compliance Insp Rept 50-275/70-05 on 701201-03.Major Areas Inspected:Status of Previously Identified Items of Concern,Discrepancy Repts & QA Audit Activities ML20212N7771970-11-12012 November 1970 Div of Compliance Insp Rept 50-323/70-02 on 700930,1001 & 13.Major Areas Inspected:Design of Steam Generator Supports. QA Procedures Officially Approved & in Use by Design Groups ML20154D8461970-10-16016 October 1970 Insp Rept 50-275/70-04 on 700915-16.No Nonconformance Noted. Major Areas Inspected:Qa/Qc Review for Fabrication & Erection of Steam Generator Supports & Review Status of Previously Reported Deficiencies 1999-09-13
[Table view] Category:TEXT-INSPECTION & AUDIT & I&E CIRCULARS
MONTHYEARIR 05000275/19990121999-09-13013 September 1999 Insp Repts 50-275/99-12 & 50-323/99-12 on 990711-0821. Noncited Violations Noted.Major Areas Inspected:Aspects of Licensee Operations,Maint,Engineering & Plant Support IR 05000275/19990071999-07-27027 July 1999 Insp Repts 50-275/99-07 & 50-323/99-07 on 990503-0714. Apparent Violations Being Considered for Escalated Enforcement Action.Major Areas Inspected:Operations & Engineering IR 05000275/19980161998-11-16016 November 1998 Insp Repts 50-275/98-16 & 50-323/98-16 on 980913-1024.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000275/19980111998-07-22022 July 1998 Insp Repts 50-275/98-11 & 50-323/98-11 on 980526-28.No Violations Noted.Major Areas Inspected:Circumstances, Potential Safety Consequences & Licensee Response & Actions Taken Re Authorization of Tagout W/O Written Procedure IR 05000275/19980081998-04-17017 April 1998 Insp Repts 50-275/98-08 & 50-323/98-05 on 980202-06,23-27 & 0302-18.No Violations Noted.Major Areas Inspected: Engineering IR 05000275/19980031998-01-23023 January 1998 Insp Repts 50-275/98-03 & 50-323/98-03 on 980105-09.No Violations Noted.Major Areas Inspected:Implementation of Solid Radioactive Waste Mgt & Radioactive Matls Transportation IR 05000275/19940271994-12-21021 December 1994 Insp Repts 50-275/94-27 & 50-323/94-27 on 941016-1126. Violations Noted.Major Areas Inspected:Operational Safety Verification,Plant Maint,Surveillance Observation,Plant Support Activities & in-office Review of LERs PNO-V-93-013, on 930809,during pre-announced anti-nuclear demonstration,13 Protestors Illegally Entered Plant Access Gate & Immediately Taken Into Custody by Sheriff Deputies. Demonstration Related to CP Recapture Hearings for Plant1993-08-0909 August 1993 PNO-V-93-013:on 930809,during pre-announced anti-nuclear demonstration,13 Protestors Illegally Entered Plant Access Gate & Immediately Taken Into Custody by Sheriff Deputies. Demonstration Related to CP Recapture Hearings for Plant PNO-V-92-033, on 921019,US Geological Survey Notified California Governor Ofc of Significant Likelihood That Earthquake of Magnitude 6 Will Occur on San Andreas Fault Near Parkfield1992-10-20020 October 1992 PNO-V-92-033:on 921019,US Geological Survey Notified California Governor Ofc of Significant Likelihood That Earthquake of Magnitude 6 Will Occur on San Andreas Fault Near Parkfield PNO-V-91-003, on 910307,unit 1 Shutdown for Refueling Operations & Loss of Offsite Power.Licensee Personnel Manually Moved New Module,Still in Mast,Away from Reactor Vessel & Core1991-03-0707 March 1991 PNO-V-91-003:on 910307,unit 1 Shutdown for Refueling Operations & Loss of Offsite Power.Licensee Personnel Manually Moved New Module,Still in Mast,Away from Reactor Vessel & Core IR 05000275/19900171990-10-22022 October 1990 Partially Withheld Safeguards Insp Repts 50-275/90-17 & 50-323/90-17 on 900924-1008.Noncited Violations Noted.Major Areas Inspected:Physical Security Program PNO-V-90-033, on 900726,observed Crack in Charging Pump Suction Header Piping Caused by Boric Acid Crystals on Elbow of Pump.Licensee Considers Piping Operable & to Be Repaired W/O Plant Shut Down.Inspector Monitoring Plant1990-07-27027 July 1990 PNO-V-90-033:on 900726,observed Crack in Charging Pump Suction Header Piping Caused by Boric Acid Crystals on Elbow of Pump.Licensee Considers Piping Operable & to Be Repaired W/O Plant Shut Down.Inspector Monitoring Plant ML20055J2001990-07-13013 July 1990 Notice of Violation from Insp on 900422-0609.Violations Noted:Work Order Which Provided Instructions for Replacement of Plant Turbine Driven Auxiliary Feedwater Pump Speed Governor Not Appropriate to Circumstances ML20245E9661989-07-31031 July 1989 Partially Withheld Insp Repts 50-275/89-20 & 50-323/89-20 on 890710-18 (Ref 10CFR2.790(d) & 73.21).No Violations Noted.Noncited Violation Noted Re Compensatory Measures. Major Areas Inspected:Physical Security Program IR 05000275/19890121989-04-18018 April 1989 Insp Repts 50-275/89-12 & 50-323/89-12 on 890403-07.No Violations or Deficiencies Noted.Major Areas Inspected: Followup on Previous Insp Findings & Operational Status of Emergency Preparedness Program IR 05000275/19890031989-02-0808 February 1989 Insp Repts 50-275/89-03 & 50-323/89-03 on 890117-26.No Noncompliance Noted.Major Areas Inspected:Nonroutine Events, Followup of Open Items,Radwaste Sys & Radiological Environ Monitoring & Transportation Activities PNO-V-88-048, on 880717,unit Manually Tripped & Natural Cooldown Commenced as Result of Ground Fault in 12 Kv non- Vital Buses.Event Investigation Team Formed to Determine Location & Cause of Ground Fault1988-07-18018 July 1988 PNO-V-88-048:on 880717,unit Manually Tripped & Natural Cooldown Commenced as Result of Ground Fault in 12 Kv non- Vital Buses.Event Investigation Team Formed to Determine Location & Cause of Ground Fault ML20196D6151988-01-27027 January 1988 Exam Rept 50-275/OL-87-02 for Units 1 & 2 on 871208-17.Exam Results:Three Senior Reactor Candidates & Twelve Reactor Operator Candidates Passed Operating & Written Exams ML20234E8071987-12-21021 December 1987 Corrected Notice of Violation from Insp on 861215-19. Violation Noted:Qualification Documentation for Limitorque Motorized Valve Actuators Did Not Establish Similarity Between Installed Actuator & Actuator Tested PNO-V-87-083, on 871213,reactor Tripped.Caused by Loss of Feed Water Pump 1-1.Cause of Trip Under Investigation. Variety of Maint Activities to Be Performed Before Restart1987-12-14014 December 1987 PNO-V-87-083:on 871213,reactor Tripped.Caused by Loss of Feed Water Pump 1-1.Cause of Trip Under Investigation. Variety of Maint Activities to Be Performed Before Restart PNO-V-87-082, on 871210,fire Occurred in Temporary Tool Storage Trailer in Vicinity of Unit 2 Main Generator Transformers.Caused by 120 Volt Junction Box,Possibly Overloaded from Portable Space Heater.Fire Put Out1987-12-10010 December 1987 PNO-V-87-082:on 871210,fire Occurred in Temporary Tool Storage Trailer in Vicinity of Unit 2 Main Generator Transformers.Caused by 120 Volt Junction Box,Possibly Overloaded from Portable Space Heater.Fire Put Out IR 05000323/19870391987-11-17017 November 1987 Insp Rept 50-323/87-39 on 870805-1030.Violations Noted. Major Areas Inspected:Improperly Authorized Flame Heating of RHR Pipe on 870505 PNO-V-87-074, on 871110,county Inadvertently Actuated Emergency Notification Sys(Sirens).Caused by Wrong Sequence Being Entered Into Sys While Performing Weekly Silent Test. Corrective Action Under Investigation1987-11-10010 November 1987 PNO-V-87-074:on 871110,county Inadvertently Actuated Emergency Notification Sys(Sirens).Caused by Wrong Sequence Being Entered Into Sys While Performing Weekly Silent Test. Corrective Action Under Investigation PNO-V-87-073, on 871107,unit Trip Manually Initiated.Caused by Failure of motor-operated Disconnect in Main Generator 25 Kv Isophase Bus C.Repair & Unit Outage Will Take Between 2 Wks & 2 Months,Depending on Availability of Parts1987-11-0909 November 1987 PNO-V-87-073:on 871107,unit Trip Manually Initiated.Caused by Failure of motor-operated Disconnect in Main Generator 25 Kv Isophase Bus C.Repair & Unit Outage Will Take Between 2 Wks & 2 Months,Depending on Availability of Parts PNO-V-87-066, on 871006,while Performing Periodic Surveillance Testing of Control Rods at 100% Power,Rod Control Urgent Failure Alarm Received on Shutdown Bank A. Caused by Blown Fuses.Fuses Replaced & Alarm Cleared1987-10-0606 October 1987 PNO-V-87-066:on 871006,while Performing Periodic Surveillance Testing of Control Rods at 100% Power,Rod Control Urgent Failure Alarm Received on Shutdown Bank A. Caused by Blown Fuses.Fuses Replaced & Alarm Cleared IR 05000275/19870321987-09-0101 September 1987 Mgt Meeting Repts 50-275/87-32 & 50-323/87-32 on 870817. Major Areas Discussed:Recent Plant Events & Apparent Problem Areas That Have Developed Since Last Mgt Meeting on 870306 PNO-V-87-053, on 870723,high Radiation Alarm Automatically Diverted Liquid Radwaste Flow to Storage Tank.Licensee Determining Root Cause.Chemical Drain Tank Properly Recirculated & Sampled Prior to Discharge Per Procedure1987-07-24024 July 1987 PNO-V-87-053:on 870723,high Radiation Alarm Automatically Diverted Liquid Radwaste Flow to Storage Tank.Licensee Determining Root Cause.Chemical Drain Tank Properly Recirculated & Sampled Prior to Discharge Per Procedure PNO-V-87-051, on 870714,reactor Trip & Safety Injection from 12% Power Occurred.Caused by turbine-generator Trip Due to High Steam Generator Water Level & Flickering High Steam Flow Bistables,Respectively.Root Causes Under Investigation1987-07-14014 July 1987 PNO-V-87-051:on 870714,reactor Trip & Safety Injection from 12% Power Occurred.Caused by turbine-generator Trip Due to High Steam Generator Water Level & Flickering High Steam Flow Bistables,Respectively.Root Causes Under Investigation IR 05000275/19870221987-06-23023 June 1987 Insp Rept 50-275/87-22 on 870520-22.Major Areas Inspected: Followup on Allegation File Number RV-87-A-0094 & Followup on Regional Open Items List ML20215F9001987-06-17017 June 1987 PNS-V-87-005:on 870617,American Protective Svc Notified Util That Security Personnel on Strike Over Monetary Benefits. Licensee Capable to Meet Security Staffing Requirements Through Use of Proprietary Security Personnel PNO-V-87-041, on 870602,engineer in Containment Noted Weepage from RHR Sys Line While RHR in Svc.Cause of Effect Undetermined.Licensee Preparing Work Orders to Isolate, Examine & Repair Weld1987-06-0303 June 1987 PNO-V-87-041:on 870602,engineer in Containment Noted Weepage from RHR Sys Line While RHR in Svc.Cause of Effect Undetermined.Licensee Preparing Work Orders to Isolate, Examine & Repair Weld IR 05000275/19870181987-05-0808 May 1987 Insp Repts 50-275/87-18 & 50-323/87-17 on 870420-24.No Noncompliance or Deviations Noted.Major Areas Inspected: Nonlicensed Staff Training,Followup of Part 21 Repts,Various Vital Areas & Equipment ML20209D5131987-04-23023 April 1987 Updated PNO-V-87-030B:on 870421,onsite Phase of AIT Team Special Insp Into 870410 Loss of Suction to RHR Sys While in half-loop Concluded W/Meeting at Site PNO-V-87-030A, on 870415,Region V Augmented Insp Team Commenced Insp Activities Re 870410 Loss of Suction to RHR While at Half Loop.Team Expects to Stay Onsite Through 870421.Summary of Sequence of Event Encl1987-04-20020 April 1987 PNO-V-87-030A:on 870415,Region V Augmented Insp Team Commenced Insp Activities Re 870410 Loss of Suction to RHR While at Half Loop.Team Expects to Stay Onsite Through 870421.Summary of Sequence of Event Encl PNO-V-87-030, on 870410,RHR Sys Capability Lost for Approx 90 Minutes.Caused by Entrainment of Air within RHR Pumps When RCS Water Level Dropped Due to Water Leakage Through Two Valves.Augmented Insp Team Dispatched1987-04-13013 April 1987 PNO-V-87-030:on 870410,RHR Sys Capability Lost for Approx 90 Minutes.Caused by Entrainment of Air within RHR Pumps When RCS Water Level Dropped Due to Water Leakage Through Two Valves.Augmented Insp Team Dispatched PNO-V-87-028, on 870403,reactor Tripped from 12% Power During Shut Down for First Refueling Outage.Caused by Flicker of High Steam Flow Bistables Coincident w/lo-lo T Average.Investigation Continuing1987-04-0606 April 1987 PNO-V-87-028:on 870403,reactor Tripped from 12% Power During Shut Down for First Refueling Outage.Caused by Flicker of High Steam Flow Bistables Coincident w/lo-lo T Average.Investigation Continuing ML20215G3021987-03-26026 March 1987 Notice of Violation from Insp on 870202-13.App B Re Areas Inspected & Results Encl IR 05000275/19870011987-03-25025 March 1987 Insp Repts 50-275/87-01 & 50-323/87-01 on 870202-13. Violation Noted:Failure to Maintain Control Over Lubricants PNO-V-87-025, on 870321,facility Experienced Safety Injection,Reactor Trip & Unit Trip.Caused by Coincidence of High Steam Flow & Low Steam Generator Pressure Signals Due to Closure of MSIV FCV 41.Piping & Valve Switches Inspected1987-03-23023 March 1987 PNO-V-87-025:on 870321,facility Experienced Safety Injection,Reactor Trip & Unit Trip.Caused by Coincidence of High Steam Flow & Low Steam Generator Pressure Signals Due to Closure of MSIV FCV 41.Piping & Valve Switches Inspected IR 05000275/19860331987-03-17017 March 1987 Insp Repts 50-275/86-33 & 50-323/86-31 on 861215-19. Deficiencies Noted.Major Areas Inspected:Implementation Program for Establishing & Maintaining Environ Qualification of Electrical Equipment Important to Safety IR 05000275/19870091987-03-11011 March 1987 Insp Repts 50-275/87-09 & 50-323/87-08 on 870223-27.No Noncompliance Noted.Major Areas Inspected:Followup of IE Bulletins,Vital Areas & Equipment PNO-V-87-018, on 870301,1-2 Mw/Min Shutdown Initiated to Investigate & Repair Main Generator Hydrogen Coolant Leak. Vibration,Induced by Main Generator,Caused Cracking in Welds of Stator Cooling Water Sys Which Occurred on 8702171987-03-0202 March 1987 PNO-V-87-018:on 870301,1-2 Mw/Min Shutdown Initiated to Investigate & Repair Main Generator Hydrogen Coolant Leak. Vibration,Induced by Main Generator,Caused Cracking in Welds of Stator Cooling Water Sys Which Occurred on 870217 PNO-V-87-016, on 870221,shutdown Commenced Due to Train B of Solid State Protection Sys Not Returning to Svc within 2 H. Caused by High Steam Generator Level on Generator 1-4 & Feedwater Flow Instabilities & Valve Position Problem1987-02-23023 February 1987 PNO-V-87-016:on 870221,shutdown Commenced Due to Train B of Solid State Protection Sys Not Returning to Svc within 2 H. Caused by High Steam Generator Level on Generator 1-4 & Feedwater Flow Instabilities & Valve Position Problem IR 05000275/19870041987-02-20020 February 1987 Insp Repts 50-275/87-04 & 50-323/87-04 on 861228-870207.No Violations or Deviations Noted.Major Areas Inspected:Plant Operations,Maint & Surveillance Activities & Followup of Onsite Events,Open Items & LERs PNO-V-87-014, on 870217,slow Shutdown from 100% Power Initiated to Investigate & Repair Main Generator Hydrogen Coolant Leak.Caused by Cracking in Stator Water Cooling Vent Line Due to Vibration.Outage Expected to Last Approx 1 Wk1987-02-18018 February 1987 PNO-V-87-014:on 870217,slow Shutdown from 100% Power Initiated to Investigate & Repair Main Generator Hydrogen Coolant Leak.Caused by Cracking in Stator Water Cooling Vent Line Due to Vibration.Outage Expected to Last Approx 1 Wk IR 05000275/19870071987-02-12012 February 1987 Insp Repts 50-275/87-07 & 50-323/87-06 on 870202-06. No Items of Noncompliance or Deviations Identified.Major Areas Inspected:Design,Design Changes & Mods & Followup on IE Notices & Nonconformance Repts ML20211M1701987-02-10010 February 1987 Notice of Violation from Insp on 870112-13 IR 05000275/19870061987-02-0606 February 1987 Insp Rept 50-275/87-06 on 870112-13.Violation Noted: Notification of 870102 Emergency Plan Unusual Event Did Not Occur Until 95 Minutes After Declaration IR 05000275/19860321987-01-30030 January 1987 Insp Repts 50-275/86-32 & 50-323/86-30 on 861109-1227 & 870116.No Violations or Deviations Noted.Major Areas Inspected:Plant Operations,Maint & Surveillance Activities, Followup of Onsite Events & Allegations IR 05000275/19870031987-01-30030 January 1987 Insp Repts 50-275/87-03 & 50-323/87-03 on 870112-16.No Violations or Deviations Noted.Major Areas Inspected: Previous Insp Items,Transportation,Solid Waste,Licensee Identified Violation & Facility Tours 1999-09-13
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ENCLOSURE 1 l
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U.S. NUCLEAR REGULATORY COMMISSION
REGION IV
Docket Nos.: 50-275 l
50-323 License Nos.: DPR-80 l DPR-82 I
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Report No.: 50-275/98-11 50-323/98-11 Licensee: Pacific Gas and Electric Company J
Facility: Diablo Canyon Nuclear Power Plant, Units 1 and 2 Location: 7 % miles NW of Avila Beach Avila Beach, California i
Dates: May 26-28,1998 Inspectors: Dyle G. Acker, Resident inspector Ryan Lantz, Reactor Inspector Approved By: Howard J. Wong, Chief, Reactor Projects Branch E Attachment: Supplemental Information 9807280145 980722 I PDR ADOCK 05000275 G PDR ,
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l EXECUTIVE SUMMARY i
Diablo Canyon Nuclear Power Plant, Units 1 and 2 NRC Inspection Report 50-275/98-11; 50-323/98-11 This special, announced inspection addressed the circumstances, potential safety consequences, and licensee response and corrective actions associated with actions taken on December 15,1997, by a Unit 2 Shift Foreman, with concurrence of the Shift Supervisor, to authorize a tagout without a written procedur Ooerations )
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The inspectors concluded that Quality Evaluation (OE) Q0011991 determined that the Shift Foreman and Shift Supervisor deviated from program documents (despite knowing that they had no authority to do so) (Section 2.4).
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The inspectors concluded that the actions and decisions of the Shift Foreman, Shift Supervisor, Senior Reactor Operator, and maintenance personnelin Unit 2 on {
December 15,1997, to perform the work using personnel standing by equipment, plus a j caution tag, instead of the clearance package described by the work order, without I modifying the work order, were contrary to the requirements of licensee procedures IDAP AD2.lD1, OP2.lD2, and AD7.lD1, and Technical Specification (TS) 6. (eel 50-323/98011-01) (Section 2.4).
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The inspectors concluded that there was little safety difference between the required '
work and the performed work in that both methods used single valve isolation (Section 2.4).
- The inspectors concluded that there was no measurable savings of person-rem or time at elevated temperatures between the method of work actually used and the method of 1 l
work allowed by licensee procedures (Section 2.4).
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The inspectors concluded that the formal root cause analysis, provided in QE 00011991 on February 25,1998, was self-critical and effectively identified the primary causes. The inspectors also concluded that the licensee's subsequent corrective actions to date have been extensive (Section 2.6).
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The inspectors concluded that the corrective actions for this December 15,1997, event were not prompt in that: (1) while the need for a QE was immediately identified, a QE was not formalized until December 30,1997, and no action was initiated to reso!ve the
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, OE until February 13,1998; and (2) written communication to operations personnel of l management's expectations with regard to this event was not accomplished until February 17,1998, in addition, failure to take corrective action to add to existing instructions of the man-on-line (MOL) tag resolution of Action Request (AR) A0411400, may have contributed to the event. These are three examples of an apparent violation of 10 CFR Part 50, Appendix B, Criterion XVI (eel 50-275;323/98011-02) (Section 2.6). )
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The delays in communicating the intentional nature of the event to operations personnel i was not consistent with licensee management's stated significant concern over the event (Section 2.6). l
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Report Details 1 Introduction 1.1 Puroose and Scooe of insoection (71707)
A special inspection team was initiated to review the circumstances surrounding the i actions taken on December 15,1997, by a Unit 2 Shift Foreman, with concurrence of the
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Shift Supervisor, to authorize a tagout without a written procedure. The issue was identified as an unresolved item (50-275;323/98008-01) in NRC inspection Report 50-275;323/98-0 The special inspection team consisted of two NRC personnel, including the team leader and a specialist in operations. The team's objectives included the following:
- Develop a sequence of events, including the licensee's corrective action * Determine which, if any, licensee procedures were not followe e Assess the safety significance of the even * Evaluate past actions taken in response to repair similar equipmen * Determine if the licensee's corrective actions were appropriate and timel * Review operations and nuclear quality services (NQS) assessments and trending for procedure adherence in operation In keeping with the NRC's emphasis on encouraging licensee self-assessment and corrective actions, the team utilized the licensee's sequence of events and investigations to the maximum extent possible. In addition, interviews between the NRC Office of Investigation and licensee personnel involved in the event were utilize Event Description (71707,92901)
2.1 Seauence of Events Date Description 12/11/97 AR A0449092 initiated to repair a steam leak on an instrument line for Steam Generator 2-4 level indication downstream of Valve MS-2-400 /15/97 Work Order (WO) C0155758 and associated Clearance 00057155 brought to control room (day shift) for review and approval to commence steam leak repair downstream of Valve MS-2-400 Operations and Maintenance personnel on shift agree to deviate from WO C0155758.
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-2-Shift Foreman initiates AR A0449239, " Intentional Procedure Deviation."
Repair is complete /16/97 Operations management leams of AR A0449239. Operations Director verbally informs Shift Supervisor and Shift Foreman that their actions were unacceptable. Operations services manager requests a QE be issue /16-22/97 Operations Director discusses events with remaining shift supervisor /23/97 Licensee AR review team determined that a QE should be issue /30/97 QE Q0011991 initiated and assigned to Operation /01/-
02/01/98 Operations Manager discussed event in requalification training sessions.
t 01/29/98 NRC Senior Resident inspector reviews QE 00011991 and requests from Operations information on corrective action /13/98 Root cause analysis assigned for action to NOS personne I 02'il/98 Operations shift order issued with an incident summary on this even l 02/20/98 Draft root cause given to Operations Services Manage /21-23/98 Positive discipline given to Shift Supervisor and Shift Foreman. Both are l removed from licensed dutie /25/98 Root cause analysis issue /26/98 Operations Services Manager sends written expectations regarding intentional procedure deviations to all Operations personne l 03/04/98 Remedial training plans issued for the Shift Supervisor and the Shift l Foreman.
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2.3. Discussion of Licensee Actions on December 15.1997 The Shift Foreman discussed WO C0155758 and Clearance 00057155 with the shift crew, maintenance technicians, and the maintenance foreman. The WO and clearance required that Valve MS-2-4008 be closed, independently verified, and tagged by Operations personnel, using the licensee normal clearance procedure. During the prejob l
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-3-discussion (tailboard) in the control room, shift personnel decided that performing the work as directed by the WO would result in unnecessary radiation exposure and time working in an elevated temperature, believed to be between 105'F and 130*F. This was because Valve MS-2-4008 and the actualleak were inside containment, high alongside the steam generator, and required climbing a 26-foot ladder, which traversed through a 165 mr per hour radiation field. Shift personnel stated that they believed that the WO required too many trips up and down the ladde As noted in AR A0449239, the Shift Foreman considered that seven trips up and down the ladder would be required to perform the work as written. However, statements made by the on shift personnel present at the talboard indicated that these personnel considered that 13 trips up the ladder would be required because a radiation protection (RP) technician was required to accompany personnel on every trip. The following is representative of the trips they believed to be required:
An operator to close Valve MS-2-4008 and hang a MOL tag Second operator to independently verify valve and tag j Two maintenance personnel to perform the repair l An operator to remove tag, open Valve MS-2-4008, and report complete Second operator to independently verify the valve position A maintenance person to verify leak repair was adequate i After discussions with on shift personnel, the Shift Foreman decided not to use the prepared clearance. The Shift Foreman decided to have the work isolated by having an operator close Valve MS-2-4008 and stand by the valve during the repair to ensure the valve remained closed. Maintenance personnel would perform independent verification of valve position, install a maintenance caution tag, perform the repair, and then remove I the caution tag. The operator would then open Valve MS-2-4008 and maintenance personnel would verify satisfactory retest. The operator, two maintenance technicians, ;
and an RP technician would all go up the ladder together, remain at the job site until the i work was completed, and then all exit togethe The Shift Foreman called the Shift Supervisor to join the tailboard near the end of the l discussion. The Shift Supervisor concurred with the plan as discussed in the tai! boar i The Shift Foreman, with input from other personnel attending the tailboard, decided to write an AR to describe why the clearance was not used and document the method of ,
system isolation actually use l l The Shift Foreman wrote AR A0449239 while two maintenance technicians, a senior reactor operator, and an RP technician entered containment, ascended the ladder, and performed the agreed upon work. The leak was successfully repaired using this metho ,
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-4- Review of Licensee Actions on December 15.1997 Insoection Scooe i
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The inspector reviewed licensee documentation associated with the December 15,1997, event, discussed the event with licensee management and quality assurance personnel, reviewed records of statements made by cognizant licensee personnel related to the event, and reviewed licensee procedures related to isolation of systems and components in support of maintenance wor Observations and Findinos Root Cause i
The licensee's cause analysis summary, Nuclear Safety Engineer Log 98-03, associated with QE Q0011991, concluded that the Shift Foreman knew that the plan used to insolate the work for WO C0155758 deviated from the requirements of Interdepartmental l Administrative Procedure (IDAP) OP2.lD1, " Clearances and Administrative Tagouts,"
Revision 8, and IDAP OP2.lD2, *DCPP Tagging Requirements," Revision 6. The cause analysis also determined that crew management circumvented the requirements of IDAP 1 AD2.lD1, " Procedure Use and Adherence," Revision 5, that did not allow intentional I deviations. The cause analysis summary also concluded that the Shift Foreman knew that he did not have authority to deviate from the procedures and that the Shift Supervisor acknowledged the procedure deviations and concurred with the proposed d pla WO Requirements I TS 6.8.1.a states, in part, that written procedures shall be established, implemented, and maintained coverin0 the applicable procedures recommended in Regulatory Guide 1.33, Revision 2, February 1978, Appendix A. Regulatory Guide 1.33, Appendix Section 9.e, requires procedures for the control of maintenance that include methods for obtaining permission and clearance for operation personnel to work and for logging such wor IDAP AD7.lD1, "Use of PIMS WO Module," Revision 2, Step 4.7.2, stated that work shall be performed in accordance with the instructions provided by the WO. Step 4.7.9 stated that WO steps shall be signed off, initialed, and dated as soon as practicable after completion, but not to delay signing off a completed activity beyond the end of the work shift in which the activity was complete Taooino Requirements IDAP OP2.lD2, Step 2.1, stated that red and MOL tags were used to mark working area boundaries, defined through a clearance process, prior to performing work on installed equipment. Step 5.3.2 further stated that MOL tags shall only be used to identify devices i
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5-that are positioned to prevent the flow of liquids, steam, or electrical power in order to place equipment in a safe condition for maintenance, repair, or testing. Step 2.2 stated that caution tags were used to identity or administratively control the operating status, position, or condition ofinstalled equipment. Step 5.5.3 stated that caution tags shall be used to identify plant equipment that shall not be operated for reasons other than those requiring use of a MOL ta Instructions on the licensee's MOL tags read "A MOL tag must be attached to the control i or operating mechanism of all switches or valves that control the supply of electricity, gas, steam, or water to the line or apparatus before men are permitted to work . . . "
instructions on the licensee's cautions tags read " . . This tag is not to be used in place of MOL NONTEST tags where men are working on lines or equipment." The inspectors observed that the clearance process was the only method authorized by licensee procedures for tagging of Operation's controlled equipment, for the purpose of personnel safet As discussed in Section 2.6 below, the licensee, in early 1997, had determined that personnel standing by equipment were not to be used as a substitute for required MOL tag Work Performance The inspectors observed that repair of the steam leak on December 15,1997, was being performed in accordance with WO C0155758. Steps 6,7, and 9 of this WO required that: operators initiate a clearance and hang a MOL tag; maintenance verify the clearance and hang a red tag; and personnel remove the tags and report off (verify work complete) when the job was finished. The clearance required isolation was to shut Valve MS-2-4008, which provided single valve isolation from steam generator pressur Steps 6,7, and 9 were not initialed and dated until December 17,1997, with a reference provided to AR A0449239, which indicated that these steps were not performed as required. Operations and Maintenance personnel failed to initiate the clearance, including hanging the required MOL and red tags specified in licensee tagging procedures to ensure personnel safety, which was required by WO C015575 j During discussions with licensee personnel, these personnel indicated that RP requirements would not have required an RP technician to accompany individuals up the l 26-foot ladder for each evolution. In addition, Administrative Procedure OP1.DC2, i " Verification of Operating Activities," Revision 7, allowed the Shift Foreman to waive
! independent verification of Valve MS-2-4008 for reasons that included person-rem l exposure and elevated temperatures or to assign the independent verification to maintenance personnel, as was actually done. The inspectors considered that, with only one trip by the RP technician and independent verification by a maintenance technician for valve position and tagging, only six trips up the ladder would have been necessar The inspectors considered that there would have been little or no person-rem savings, or time in the high temperature area, if the specified clearance had been used. The ,
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-6-inspectors observed that a similar steam leak on an instrument line off of a steam generator had been repaired at power in 1996, using the normal clearance procedure proces The inspectors also reviewed the actual method used by the licensee to ensure the safety of personnel working on a steam leak downstream of Valve MS-2-4008. Although this was a single valve isolation from a steam generator at full power, with the leak as the only vent, the inspectors considered that the methods actually used by licensee personnel on December 15,1997, provided essentially the same personnel protection as indicated in WO C0155758. There was no difference in the safety of plant equipmen Therefore, the inspectors considered that there was little safety difference between the required and the performed wor Taoaina and Clearance Procedures During review oilicensee procedures, the inspectors identified an apparent inconsistency in licensee procedures for control of work. Administrative Procedure OP1.DC18, Revision 3, " Authorization for Equipment Operation and Maintenance," Step 5.3, provides guidelines for removal of equipment from service. One method for approval was Shift Foreman signature approval on a clearance. Another method was Shift Foreman signature approval on a WO. During discussions with licensee personnel, some personnel told the inspectors that they believed that the Shift Foreman approval authority to remove equipment from service per OP1.DC18, Step 5.3, also constituted approval to perform work. Thus, the Shift Foreman, by signing WO C0155758, which was done on December 15,1997, had complied with licensee procedures for authorizing work. The inspectors did not agree. The inspectors noted that approval of removing equipment from service did not constitute authority to allow work on equipment outside the licensee's procedures for ensuring personnel safety. As noted above, the clearance procedure is the licensee's only defined process where protection of personnel is required. Since some licensee personnel appeared to believe that shift foremen had the authority to waive the clearance process, the inspectors considered that Procedure OP1.DC18 was inconsistent with the licensee tagging program contained in Program Directive OP2, " Tagging Programs," Revision 1, which stated that the clearance process defines and controls a safe working boundary using appropriate tag During their review, the inspectors noted that Procedure OP1.DC2 provided no clear guidance or training requirements for assignment of personnel to perform independent verifications. The inspectors discussed Procedure OP1.DC2 with licensee managemen Licensee management noted that they were considering developing a formal training program for qualification of site personnel who could perform independent verifications
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c. .Cnoclusions The inspectors concluded that QE 00011991 determined that the Shift Foreman and Shift Supervisor deviated from program documents (despite knowing that they had no authority to do so).
The inspectors concluded that the actions and decisions of the Shift Foreman, Shift Supervisor, Senior Reactor Operator, and maintenance personnelin Unit 2 on December 15,1997, to perform the work using personnel standing by equipment, plus a caution tag, instead of the clearance package described by the work order, without modifying the work order, was contrary to the requirements of licensee Procedures IDAP AD2.lD1, OP2.lD2, and AD7.lD1, as described above. This was an apparent violation of TS 6.8.1 (eel 50-323/98011-01).
The inspectors concluded that there was little safety difference between the required work and the performed work in that both methods used single valve isolatio The inspectors concluded that there were weaknesses in the licensee's program documents for control of work and independent verificatio The inspectors concluded that there was no measurable savings of person-rem or time at elevated temperatures between the method of work actually used and the method of work allowed by licensee procedure .5 Licensee Corrective Actions On December 16,1997, site management reviewed AR A0449239. The Operations Services Manager stated that he directed that a OE be initiated. The Acting Operations Director stated that he informed the involved Shift Supervisor and the Shift Foreman that the procedural deviation was unacceptable. The Acting Operations Director stated that he discussed the event with the remaining Shift Supervisors between December 16-22, 199 On December 23,1997, the licensee committee that reviews ARs determined that
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AR A0449239 met the criteria for a OE. The licensee defined a QE as a mechanism for processing a quality problem that did not rise to the level of a nonconformance report.
The QE process contained provisions for documenting a problem, specifying immediate
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corrective actions, determining the cause of the problem, and determining corrective actions to prevent recurrence. On December 30,1997, OE Q0011991, " Intentional Procedural Deviation," was initiated to investigate AR A0449239.
( During January 1998, the Operations Services Manager stated that he reviewed the event with his staff during Friday requalification training session On February 13,1998, OE Q0011991 was assigned to an individual in the NOS organization for action. On February 17,1998, the operations day shift supervisor
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-8-issued an incident Summary as part of the operations shift orders which discussed the December 15,1997, occurrence and discussed the need to follow procedures. On February 20,1998, NQS personnel briefed the Operations Services Manager on their preliminary cause analysis. Based on this information, management initiated positive discipline for the Shift Supervisor and the Shift Foreman, and both were temporarily removed from licensed activities for remediation. On February 25,1997, NQS formally issued the cause analysis. This analysis concluded that the primary cause of the event was an intentional violation of administrative procedures in that both the Shift Foreman and Shift Supervisor knew that they did not have the authority to take the actions they took. The analysis determined that a contributing cause was the belief of the Shift Foreman involved that the clearance process was complex and cumbersom Recommended actions included positive discipline at the formal written reminder level for selected individuals, reinforced management expectations with regard to the use of clearances for WOs, and measuring crew and management understanding of expectations with regard to procedure adherence in self-assessment activitie On February 26,1998, the Operations Services Manager issued a memorandum to all operations personnel concerning intentional deviations. Remedial training requirements were issued to the Shift Supervisor and Shift Foreman on March 4,199 In addition, the licensee stated that they had issued a nonconformance report to review past human performance to identify previous intentional procedure deviations. The licensee reported that their review did not identify any previous intentional deviations.
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resolve problems with procedure compliance errors, was updated to include the issues associated with compliance with the clearance proces The licensee stated that they planned to perform the self-assessment recommended in QE Q0011991 by NOS and to have NOS perform a followup assessment. During presentations to the inspectors at the beginning of this inspection, the licensee stated that the event was significant because of the intentional nature of the deviation and the lack of timely followup, including root cause analysis. In addition, the licensee provided the inspectors with trending information on operations procedure aoherence errors, l which indicated that there was no increasing trend in this are .6 Review of Licensee Corrective Actions
! Inscection Scoce The inspectors discussed the corrective actions taken with licensee personnel, reviewed related licensee procedure requirements and records, reviewed past procedure compliance records, and reviewed previous statements made by licensee personnel associated with corrective actions.
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, Observations and Findinos Licensee Corrective Actions for December 15.1997. Event As noted in Section 2.5 above, licensee operations management stated that they had verbally informed the operations staff in various briefings by February 1,1997, that failure to follow written requirements was unacceptable. However, a review of the statements made by members of the operations staff present in the control room on December 15,1997, conceming the verbal briefings provided by management personnel after the event, indicated these personnel had not completely understood management's concern with the difference between the subject event and previous procedure violations, which were the results of errors. The inspectors, therefore, considered that these
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briefings were not entirely effectiv As noted in Section 2.1 above, the licensee did not initiate formal action to investigate the event until December 30,1997, or over two weeks after the event occurre Although licensee procedures indicate that QEs should normally be resolved in 30 days, the assigned organization (operations) took almost 45 days to assign an investigator, in this case a member of the NOS staff. Members of the NOS staffinformed the inspectors that, after a 30-day period, unresolved QEs were marked and discussed daily by NOS personnel with the assigned organization. NQS personnel stated that they reminded operations personnel of the need to resolve QE Q0011991 after the 30-day period expired at the end of January 1998. In addition, on January 29,1998, the NRC senior resident inspector, during routine review of active QEs, reviewed QE Q0011991 and j requested information on licensee planned corrective action After February 20,1998, when NOS informally briefed operations management on their root cause analysis for AR A0449239, the inspectors noted that the licensee began to address the issue formally. The inspectors observed that licensee actions based on this root cause analysis were prompt and focused, including temporarily removing the Shift Supervisor and Shift Foreman from licensed duties. The memorandum ser:t by the Operations Services Manager to the staff on February 26,1998, clearly defined the need to follow procedures and that the actions taken on December 15,1997, were i unacceptable. However, the inspectors noted that the memorandum did not specifically address the inappropriate use of an operator and caution tag in place of a MOL tag. The inspectors reviewed the remediation plans for the Shift Supervisor and Shift Foreman and considered that they were adequate. The plans clearly reinforced to these individuals the consequences of willful violations of requirements contained in 10 CFR ;
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! Part 50.5 and 10 CFR Part 55.61. During the inspection period, both individuals had not been returned to shift dutie )
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The inspectors observed that the licensee's definitions for QE's and nonconformance reports were similar. Although the licensee used nonconformance reports to document the most significant problems, both document types required formal root cause analysis l l
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-10-and corrective actions. The inspectors considered that use of a QE for documenting resolution of AR A0449239, in lieu of a nonconformance report, was within the licensee's guideline Previous Procedure Comoliance Records and Corrective Actions The inspectors observed that, during 1993 and 1994, the licensee had experienced a number of problems with procedure compliance. Based on NRC violations and self-assessments, the licensee issued Nonconformance Report DCO-93-PG-N048,
" Procedural Adherence / Noncompliance," with corrective actions dated October 2,199 The licensee concluded that a contributing cause was a programmatic weakness in conveying management expectations for procedure compliance to the workforc Licensee corrective actions included administrative changes to more aggressively emphasize procedural adherence expectations, lowering of the threshold for problems receiving management attention, enhanced personal accountability, and improved trending to assure corrective actions were effectiv In October 1995, operators attempted to energize a 4160 volt load center with a grounding buggy still installed, resulting in the immediate transformer failure and fire. As noted in NRC Inspection Report 50-275;323/95-17, one of the major contributing causes of this event was widespread failure of operations and maintenance personnel to follow clearance procedural requirements for installation and removal of ground buggie Licensee self-assessments determined that the failure to follow procedures was not limited to the event. Licensee corrective actions included a series of Town Hall Meetings with all site personnel concerning procedure compliance, a meeting of all site supervisors with senior management concerning procedure compliance, selection of procedure error reduction as an area of focus for all site directors, supervisory workshops on procedure adherence, and improvements in the trending of procedure noncomplianc The inspectors reviewed the recent data provided by the licensee on procedure compliance errors and agreed with the licensee that there was not an increasing tren In addition, the inspectors reviewed recent operations self-assessments and NOS assessments. These assessments did not identify any potentialissues with intentionally not following procedures and did not identify any significant or widespread problems with procedure compliance within the operations organization. However, the inspectors noted that the licensee had identified a number of errors associated with the clearance and tagging process. The licensee was addressing clearance errors in an active i nonconformance report.
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l The inspectors noted that AR A0449239 stated that, in place of a MOL tag, the Shift Foreman, with concurrence of the Shift Supervisor, decided to use an operator standing by Valve MS-2-4008. The inspectors observed that AR A0411400, issued on August 16, 1996, indicated that NOS had identified several occasions where operators standing by l
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-11-circuit breakers and valves had previously been used in place of the required MOL tag NOS requested the management eva!uate and formally document this practice. On February 7,1997, management resolved AR A0411400 by directing that the practice of using operators as MOL tags be stopped until procedures were revised to allow for this practice. The inspectors reviewed current licensee clearance and tagging procedures and determined that they had not been modified to either allow or prohibit the practice of using operators standing by equipment in place of MOL tag The inspectors considered that failure to update tagging and clearance procedures, as indicated in AR A0411400, required operations personnel to remember the AR resolution and was a potential contributing cause to the event. Hao the tagging and/or clearance procedures clearly indicated management's expectations with regard to human observation replacing MOL tags, the onshift staff may not heve chosen the course of action they decided upo c. Conclusions The inspectors concluded that the formal root cause analysis, provided in QE Q0011991 on February 25,1998, was self-critical and effectively identified the primary causes. The inspectors also concluded that the licensee's subsequent corrective actions to date have been extensiv However, the inspectors concluded that these corrective actions for this December 15, 1997, event were not prompt in that: (1) while the need for a QE was immediately identified, a QE was not formalized until December 30,1997, and no action was initiated to resolve the QE until February 13,1998; and (2) written communication to operations personnel of management's expectations with regard to this event was not accomplished until February 17,1998. In addition, failure to take corrective action to add to existing instructions the MOL tag resolution of AR A0411400, may have contributed to the even These are three examples of an apparent violation of 10 CFR Part 50, Appendix B, Criterion XVI, which states, in part, that measures shall be established to assure that conditions adverse to quality, such as deficiencies and deviations, are promptly identified and corrected (eel 50-275;323/98011-02).
The delays in communicating the intentional nature of the event to operations personnel was not consistent with licensee management's stated significant concern over the event. In addition, the inspectors considered that the licensee missed an opportunity to have initiated corrective actions immediately after January 30,1998, due to: (1) failure of personnel who observed that QE Q0011991 had not been resolved within the 30-day target to elevate the problem to higher management; and (2) the licensee's
! administrative control system for OEs, which required no specific action for QEs identified as having gone 30 days without resolution.
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-12-2.7 (Closed) Unresolved item 50-275:323/98009-01: review of licensee's determination that personnel failed to comply with the clearance procedure while being fully knowledgeable of the requirements, This item is closed by the apparent violations discussed above in this repor Management Meetings 3.1 Exit Meetino summarv The inspectors presented the inspection results to members of licensee management at the conclusion of the inspection on July 2. The licensee acknowledged the findings presente The inspectors asked the licensee whether any materials examined during the inspection should be considered proprietary. No proprietary information was identifie l
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AlTACHMENT SUPPLEMENTAL INFORMATION PARTIAL LIST OF PERSONS CONTACTED Licensee B. Blunt, Nuclear Quality Services J. Dye, Shift Supervisor, Operations Scheduling B. Garrett, Director Learning Services S. Heitt, Acting Director, Operations J. Molden, Manager, Operations Services R. Powers, Vice President and Plant Manager
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INSPECTION PROCEDURES (IP) USED IP 71707 Plant Operations IP 92901 Followup - Operations l
ITEMS OPENED AND CLOSED Opened 50-323/98011-01 eel Intentional failure to follow WO and clearance procedures 50-275;323/98011- eel Untimely corrective actions for intentional failure to follow 02 procedures l l
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l Closed 50-275;323/98009- URI Review of licensee's determination that personnel failed to 01 comply with procedures l
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t LIST OF ACRONYMS USED
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IDAP Interdepartmental Administrative Procedure IP inspection procedure MOL man-on-line NOS Nuclear Quality Services QE Quality Evaluation t- RP' radiation protection TS Technical Specification WO work order
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Enclosure 2
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SYNOPSIS This investigation was initiated'on February 10. 1998, by the Nuclear-Regulatory Commission (NRC). Office of Investigations (01). Region IV to determine if a shift foreman at Pacific Gas and Electric Company's (PG&E)
Diablo Canyon Nuclear Power Plant (Diablo), willfully violated a clearance procedure.
I Based on the evidence developed during this investigation, including a review of PG&E documents and interviews of PG&E personnel, the allegation that a l shift foreman willfully violated a clearance procedure was substantiated. '
l Additionally, it was determined a PG&E shift supervisor willfully approved the violation of a clearance procedure and a senior reactor operator willfully participated in the violation of a procedure.
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