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Category:INSPECTION REPORT
MONTHYEARIR 05000334/19990061999-10-0707 October 1999 Insp Repts 50-334/99-06 & 50-412/99-06 on 990809-13 & 990823-27.Violations Noted.Major Areas Inspected:Licensee Corrective Action Program Implementation IR 05000334/19990051999-09-30030 September 1999 Insp Repts 50-334/99-05 & 50-412/99-05 on 990725-0904.Two Violations Noted & Being Treated as Nvcs.Major Areas Inspected:Aspects of Licensee Operations,Maint,Engineering & Plant Support ML20211Q5791999-09-0707 September 1999 Insp Rept 50-412/99-07 on 990720-29.No Violations Noted. Major Areas Inspected:Operations,Maint & Engineering IR 05000334/19990041999-08-24024 August 1999 Insp Repts 50-334/99-04 & 50-412/99-04 on 990613-0724. Violations Noted.Major Areas Inspected:Licensee Operations, Engineering,Maint & Plant Support IR 05000334/19990031999-07-0707 July 1999 Insp Repts 50-334/99-03 & 50-412/99-03 on 990502-0612.No Violations Noted.Major Areas Inspected:Operations, Engineering,Maintenance & Plant Support.Results of Y2K Readiness Assessment Also Included IR 05000334/19990021999-05-21021 May 1999 Insp Repts 50-334/99-02 & 50-412/99-02 on 990321-0501.No Violations Noted.Major Areas Inspected:Licensee Operations, Engineering,Maint & Plant Support IR 05000334/19990011999-04-22022 April 1999 Insp Rept 50-334/99-01 & 50-412/99-01 on 990207-0320. Violations Noted.Major Areas Inspected:Operations, Maintenance,Engineering & Plant Support.Also Results of Insp by Regional Security & Inservice Insp Specialists IR 05000334/19980111999-02-25025 February 1999 Insp Repts 50-334/98-11 & 50-412/98-11 on 981227-990206. Violations Noted.Major Areas Inspected:Operations,Maint & Plant Support IR 05000334/19980091999-02-0505 February 1999 Insp Repts 50-334/98-09 & 50-412/98-09 on 981115-1217. Violations Noted.Major Areas Inspected:Engineering IR 05000334/19980101999-01-13013 January 1999 Insp Repts 50-334/98-10 & 50-412/98-10 on 981115-1226.No Violations Noted.Major Areas Inspected:Licensee Operations, Engineering,Maint & Plant Support.Matl Condition of Fire Protection Equipment Installed in Plant Was Excellent IR 05000334/19980061998-12-0404 December 1998 Corrected Pages 17 & 18 to Insp Repts 50-334/98-06 & 50-412/98-06,correcting Errors on Subj Pages ML20196H3231998-12-0202 December 1998 Insp Repts 50-334/98-06 & 50-412/98-06 on 981004-1114.No Violations Noted.Major Areas Inspected:Aspects of Licensee Operations,Engineering,Maint & Plant Support ML20196H2951998-12-0202 December 1998 Insp Repts 50-334/98-08 & 50-412/98-08 on 981026-30.No Violations Noted.Major Areas Inspected:Operations & Maint IR 05000334/19980071998-11-0505 November 1998 Insp Repts 50-334/98-07 & 50-412/98-07 on 981006-07.No Violations Noted.Major Areas Inspected:Performance of Emergency Response Organization IR 05000334/19980051998-10-23023 October 1998 Insp Repts 50-334/98-05 & 50-412/98-05 on 980816-1003. Apparent Violations Being Considered for Escalated Enforcement Action.Major Areas Inspected:Operations, Engineering,Maint & Plant Support ML20151Z3231998-09-15015 September 1998 Insp Repts 50-334/98-04 & 50-412/98-04 on 980628-0815. Violation Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000334/19980031998-08-0505 August 1998 Insp Repts 50-334/98-03 & 50-412/98-03 on 980426-0627. Violations Noted.Major Areas Inspected:Aspects of Licensee Operations,Engineering,Maint & Plant Support ML20217F5951998-04-22022 April 1998 Insp Repts 50-334/98-01 & 50-412/98-01 on 980208-0321. Violations Noted.Major Areas Inspected:Operations, Engineering,Maint & Plant Support ML20217B9851998-03-17017 March 1998 Insp Repts 50-334/97-11 & 50-412/97-11 on 971228-980207. Violations Noted.Major Areas Inspected:License Operations, Engineering,Maint & Plant Support.Security Program Was Also Inspected ML20216E8191998-03-0909 March 1998 Insp Repts 50-334/98-80 & 50-412/98-80 on 980105-0212. Violations Noted.Major Areas Inspected:Evaluation of Implementation of 10CFR50.59 SE Program Relating to Changes, Tests or Experiments at Plant ML20202A9691998-02-0404 February 1998 Insp Repts 50-334/97-09 & 50-412/97-09 on 971116-1227. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support.Rept Also Includes Results of Announced Insp in Areas of Emergency Preparedness ML20203D7421997-11-26026 November 1997 Insp Repts 50-334/97-08 & 50-412/97-08 on 971005-1115. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000334/19970071997-11-0707 November 1997 Insp Repts 50-334/97-07 & 50-412/97-07 on 970831-1004. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000334/19970061997-09-18018 September 1997 Insp Repts 50-334/97-06 & 50-412/97-06 on 970720-0830.No Violations Noted.Major Areas Inspected:Operations, Engineering,Maintenance & Plant Support & Licensed Operator Requalification Training Program IR 05000334/19970051997-08-18018 August 1997 Insp Repts 50-334/97-05 & 50-412/97-05 on 970608-0719. Violations Noted.Major Areas Inspected:Operations, Engineering,Maintenance & Plant Support IR 05000334/19970021997-05-23023 May 1997 Insp Repts 50-334/97-02 & 50-412/97-02 on 970316-0426. Violations Noted.Major Areas Inspected:Operations, Engineering,Maintenance & Plant Support ML20141E9451997-04-27027 April 1997 Integrated Insp Repts 50-334/97-04 & 50-412/97-04 on 970427-0607.Violations Noted.Major Areas Inspected:Licensee Operations,Engineering,Maint & Plant Support ML20137Q6851997-04-0707 April 1997 Insp Repts 50-334/97-01 & 50-412/97-01 on 970209-0315.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support ML20135B7781997-02-21021 February 1997 Insp Repts 50-334/96-10 & 50-412/96-10 on 961222-970208. Violations Noted.Major Areas Inspected:Licensee Operations, Engineering,Maint, & Plant Support IR 05000344/19960051997-02-13013 February 1997 Correction to Insp Repts 50-344/96-05 & 72-0017/96-02. Requests That Encl Pages Be Added as Last Two Pages of Listed Insp Rept IR 05000334/19960091997-01-0202 January 1997 Insp Repts 50-334/96-09 & 50-412/96-09 on 961117-1221.No Violations Noted.Major Areas Inspected:Operations, Engineering,Maintenance & Plant Support IR 05000334/19960111996-12-23023 December 1996 Insp Repts 50-334/96-11 & 50-412/96-11 on 961209-12.No Violations Noted.Major Areas Inspected:Authorization Program & Administration Organization ML20135C4081996-11-16016 November 1996 Insp Repts 50-334/96-08 & 50-412/96-08 on 960929-1116.No Violations Noted.Major Areas Inspected:Operations, Maintenance,Engineering & Plant Support IR 05000334/19960071996-11-0808 November 1996 Insp Repts 50-334/96-07 & 50-412/96-07 on 960813-0928. Violations Noted.Major Areas Inspected:Operations, Engineering,Maint & Plant Support ML20058Q0221993-12-15015 December 1993 AIT IR 50-412/93-81 on 931109-19.No Violations Noted. Major Areas Inspected:Detailed Review of Circumstances Surrounding Failure of Both Emergency Diesel Generator Load Sequencers During Routine Surveillance Testing IR 05000334/19930261993-12-0808 December 1993 Insp Repts 50-334/93-26 & 50-412/93-28 on 931026-1127. Violations Noted.Major Areas Inspected:Plant Operations, Maint & Surveillance,Engineering,Plant Support & Safety Assessment/Quality Verification IR 05000412/19930251993-11-29029 November 1993 Insp Rept 50-412/93-25 on 931018-22.Violations Noted. Major Areas Inspected:Adequacy of Repair & Maintenance of Safety Class 1 Valves,Including follow-up of Auxiliary Feedwater (AFW) Water Hammer Issue IR 05000334/19930251993-11-23023 November 1993 Insp Repts 50-334/93-25 & 50-412/93-26 on 931018-22.No Violations Noted.Major Areas Inspected:Organization & Staffing Levels,Staff Qualifications & Training,External & Internal Exposure Control & Radiological Surveys IR 05000334/19930221993-10-29029 October 1993 Insp Repts 50-334/93-22 & 50-412/93-23 on 930928-1025. Violations Noted.Major Areas Inspected:Plant Operations, Maint,Engineering & Plant Support IR 05000334/19930801993-10-27027 October 1993 Insp Repts 50-334/93-80 & 50-412/93-80 on 930830-0903.No Violations Noted.Major Areas Inspected:Adequacy of Programs, Procedures,Training,Equipment & Sys for Implementing SBO IR 05000412/19930211993-10-22022 October 1993 Insp Rept 50-412/93-21 on 930830-0903 & 1004-08.No Violation Noted.Major Areas Inspected:Isi Program,Scope of ISI Work, Eddy Current Exam Program for SG Tubes,Erosion/Corrosion Monitoring Program for High Energy Sys & SG Leakage Program IR 05000334/19930201993-10-21021 October 1993 Insp Repts 50-334/93-20 & 50-412/93-20 on 930907-10.No Violations of Regulatory Requirements Noted.Major Areas Inspected:Bvps Ep,Program Changes,Emergency Facilities, ERO Training & Staff Knowledge ML20057E8331993-09-30030 September 1993 Insp Repts 50-334/93-21 & 50-412/93-22 on 930824-0927. Violations Noted.Major Areas Inspected:Plant Operations, Maint & Surveillance,Engineering,Plant Support & Safety Assessment/Quality Verification IR 05000334/19930161993-09-0808 September 1993 Insp Repts 50-334/93-16 & 50-412/93-17 on Stated Date. Violations Noted,Not Cited.Major Areas Inspected:Plant Operations,Maint & Surveillance,Engineering,Plant Support & Safety Assessment/Quality Verification IR 05000334/19930181993-08-30030 August 1993 Insp Repts 50-334/93-18 & 50-412/93-19 on 930809-13.No Safety Concerns or Violations Noted.Major Areas Inspected: Mgt Support,Audits & Security Program Plans,Protected & Vital Area Physical Barriers & Detection & Assessment Aids IR 05000334/19930151993-08-0606 August 1993 Insp Repts 50-334/93-15 & 50-412/93-16 on 930726-30.No Violations Noted.Major Areas Inspected:Transportation of Radioactive Matls,Radwaste Processing,Staffing Levels,Staff Qualifications,Training & Quality Assurance IR 05000334/19920301993-02-0909 February 1993 Insp Repts 50-334/92-30 & 50-412/92-29 on 921222-930125.No Violations Noted.Major Areas Inspected:Plant Operations, Radiological Controls,Surveillance & Maint,Emergency Preparedness & Security IR 05000334/19920281993-02-0202 February 1993 Insp Repts 50-334/92-28 & 50-412/92-27 on 921215-18.No Violations Noted.Major Areas Inspected:Design Changes,Mods, TER Process,Lers & Status of Previously Identified Open Items IR 05000334/19920261992-12-31031 December 1992 Insp Repts 50-334/92-26 & 50-412/92-26 on 921119-1221.No Violations Noted.Major Areas Inspected:Plant Operations, Radiological Controls,Surveillance & Maint,Emergency Preparedness,Security & Engineering & Technical Support IR 05000334/19920241992-12-0101 December 1992 Insp Repts 50-334/92-24 & 50-412/92-24 on 921013-1118.No Violations Noted.Major Areas Inspected:Plant Operations, Radiological Controls,Surveillance & Maint,Emergency Preparedness,Security & Engineering & Technical Support 1999-09-07
[Table view] Category:NRC-GENERATED
MONTHYEARIR 05000334/19990061999-10-0707 October 1999 Insp Repts 50-334/99-06 & 50-412/99-06 on 990809-13 & 990823-27.Violations Noted.Major Areas Inspected:Licensee Corrective Action Program Implementation IR 05000334/19990051999-09-30030 September 1999 Insp Repts 50-334/99-05 & 50-412/99-05 on 990725-0904.Two Violations Noted & Being Treated as Nvcs.Major Areas Inspected:Aspects of Licensee Operations,Maint,Engineering & Plant Support ML20211Q5791999-09-0707 September 1999 Insp Rept 50-412/99-07 on 990720-29.No Violations Noted. Major Areas Inspected:Operations,Maint & Engineering IR 05000334/19990041999-08-24024 August 1999 Insp Repts 50-334/99-04 & 50-412/99-04 on 990613-0724. Violations Noted.Major Areas Inspected:Licensee Operations, Engineering,Maint & Plant Support IR 05000334/19990031999-07-0707 July 1999 Insp Repts 50-334/99-03 & 50-412/99-03 on 990502-0612.No Violations Noted.Major Areas Inspected:Operations, Engineering,Maintenance & Plant Support.Results of Y2K Readiness Assessment Also Included IR 05000334/19990021999-05-21021 May 1999 Insp Repts 50-334/99-02 & 50-412/99-02 on 990321-0501.No Violations Noted.Major Areas Inspected:Licensee Operations, Engineering,Maint & Plant Support IR 05000334/19990011999-04-22022 April 1999 Insp Rept 50-334/99-01 & 50-412/99-01 on 990207-0320. Violations Noted.Major Areas Inspected:Operations, Maintenance,Engineering & Plant Support.Also Results of Insp by Regional Security & Inservice Insp Specialists IR 05000334/19980111999-02-25025 February 1999 Insp Repts 50-334/98-11 & 50-412/98-11 on 981227-990206. Violations Noted.Major Areas Inspected:Operations,Maint & Plant Support IR 05000334/19980091999-02-0505 February 1999 Insp Repts 50-334/98-09 & 50-412/98-09 on 981115-1217. Violations Noted.Major Areas Inspected:Engineering IR 05000334/19980101999-01-13013 January 1999 Insp Repts 50-334/98-10 & 50-412/98-10 on 981115-1226.No Violations Noted.Major Areas Inspected:Licensee Operations, Engineering,Maint & Plant Support.Matl Condition of Fire Protection Equipment Installed in Plant Was Excellent IR 05000334/19980061998-12-0404 December 1998 Corrected Pages 17 & 18 to Insp Repts 50-334/98-06 & 50-412/98-06,correcting Errors on Subj Pages ML20196H3231998-12-0202 December 1998 Insp Repts 50-334/98-06 & 50-412/98-06 on 981004-1114.No Violations Noted.Major Areas Inspected:Aspects of Licensee Operations,Engineering,Maint & Plant Support ML20196H2951998-12-0202 December 1998 Insp Repts 50-334/98-08 & 50-412/98-08 on 981026-30.No Violations Noted.Major Areas Inspected:Operations & Maint IR 05000334/19980071998-11-0505 November 1998 Insp Repts 50-334/98-07 & 50-412/98-07 on 981006-07.No Violations Noted.Major Areas Inspected:Performance of Emergency Response Organization IR 05000334/19980051998-10-23023 October 1998 Insp Repts 50-334/98-05 & 50-412/98-05 on 980816-1003. Apparent Violations Being Considered for Escalated Enforcement Action.Major Areas Inspected:Operations, Engineering,Maint & Plant Support ML20151Z3231998-09-15015 September 1998 Insp Repts 50-334/98-04 & 50-412/98-04 on 980628-0815. Violation Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000334/19980031998-08-0505 August 1998 Insp Repts 50-334/98-03 & 50-412/98-03 on 980426-0627. Violations Noted.Major Areas Inspected:Aspects of Licensee Operations,Engineering,Maint & Plant Support ML20217F5951998-04-22022 April 1998 Insp Repts 50-334/98-01 & 50-412/98-01 on 980208-0321. Violations Noted.Major Areas Inspected:Operations, Engineering,Maint & Plant Support ML20217B9851998-03-17017 March 1998 Insp Repts 50-334/97-11 & 50-412/97-11 on 971228-980207. Violations Noted.Major Areas Inspected:License Operations, Engineering,Maint & Plant Support.Security Program Was Also Inspected ML20216E8191998-03-0909 March 1998 Insp Repts 50-334/98-80 & 50-412/98-80 on 980105-0212. Violations Noted.Major Areas Inspected:Evaluation of Implementation of 10CFR50.59 SE Program Relating to Changes, Tests or Experiments at Plant ML20202A9691998-02-0404 February 1998 Insp Repts 50-334/97-09 & 50-412/97-09 on 971116-1227. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support.Rept Also Includes Results of Announced Insp in Areas of Emergency Preparedness ML20203D7421997-11-26026 November 1997 Insp Repts 50-334/97-08 & 50-412/97-08 on 971005-1115. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000334/19970071997-11-0707 November 1997 Insp Repts 50-334/97-07 & 50-412/97-07 on 970831-1004. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000334/19970061997-09-18018 September 1997 Insp Repts 50-334/97-06 & 50-412/97-06 on 970720-0830.No Violations Noted.Major Areas Inspected:Operations, Engineering,Maintenance & Plant Support & Licensed Operator Requalification Training Program IR 05000334/19970051997-08-18018 August 1997 Insp Repts 50-334/97-05 & 50-412/97-05 on 970608-0719. Violations Noted.Major Areas Inspected:Operations, Engineering,Maintenance & Plant Support IR 05000334/19970021997-05-23023 May 1997 Insp Repts 50-334/97-02 & 50-412/97-02 on 970316-0426. Violations Noted.Major Areas Inspected:Operations, Engineering,Maintenance & Plant Support ML20141E9451997-04-27027 April 1997 Integrated Insp Repts 50-334/97-04 & 50-412/97-04 on 970427-0607.Violations Noted.Major Areas Inspected:Licensee Operations,Engineering,Maint & Plant Support ML20137Q6851997-04-0707 April 1997 Insp Repts 50-334/97-01 & 50-412/97-01 on 970209-0315.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support ML20135B7781997-02-21021 February 1997 Insp Repts 50-334/96-10 & 50-412/96-10 on 961222-970208. Violations Noted.Major Areas Inspected:Licensee Operations, Engineering,Maint, & Plant Support IR 05000344/19960051997-02-13013 February 1997 Correction to Insp Repts 50-344/96-05 & 72-0017/96-02. Requests That Encl Pages Be Added as Last Two Pages of Listed Insp Rept IR 05000334/19960091997-01-0202 January 1997 Insp Repts 50-334/96-09 & 50-412/96-09 on 961117-1221.No Violations Noted.Major Areas Inspected:Operations, Engineering,Maintenance & Plant Support IR 05000334/19960111996-12-23023 December 1996 Insp Repts 50-334/96-11 & 50-412/96-11 on 961209-12.No Violations Noted.Major Areas Inspected:Authorization Program & Administration Organization ML20135C4081996-11-16016 November 1996 Insp Repts 50-334/96-08 & 50-412/96-08 on 960929-1116.No Violations Noted.Major Areas Inspected:Operations, Maintenance,Engineering & Plant Support IR 05000334/19960071996-11-0808 November 1996 Insp Repts 50-334/96-07 & 50-412/96-07 on 960813-0928. Violations Noted.Major Areas Inspected:Operations, Engineering,Maint & Plant Support ML20058Q0221993-12-15015 December 1993 AIT IR 50-412/93-81 on 931109-19.No Violations Noted. Major Areas Inspected:Detailed Review of Circumstances Surrounding Failure of Both Emergency Diesel Generator Load Sequencers During Routine Surveillance Testing IR 05000334/19930261993-12-0808 December 1993 Insp Repts 50-334/93-26 & 50-412/93-28 on 931026-1127. Violations Noted.Major Areas Inspected:Plant Operations, Maint & Surveillance,Engineering,Plant Support & Safety Assessment/Quality Verification IR 05000412/19930251993-11-29029 November 1993 Insp Rept 50-412/93-25 on 931018-22.Violations Noted. Major Areas Inspected:Adequacy of Repair & Maintenance of Safety Class 1 Valves,Including follow-up of Auxiliary Feedwater (AFW) Water Hammer Issue IR 05000334/19930251993-11-23023 November 1993 Insp Repts 50-334/93-25 & 50-412/93-26 on 931018-22.No Violations Noted.Major Areas Inspected:Organization & Staffing Levels,Staff Qualifications & Training,External & Internal Exposure Control & Radiological Surveys IR 05000334/19930221993-10-29029 October 1993 Insp Repts 50-334/93-22 & 50-412/93-23 on 930928-1025. Violations Noted.Major Areas Inspected:Plant Operations, Maint,Engineering & Plant Support IR 05000334/19930801993-10-27027 October 1993 Insp Repts 50-334/93-80 & 50-412/93-80 on 930830-0903.No Violations Noted.Major Areas Inspected:Adequacy of Programs, Procedures,Training,Equipment & Sys for Implementing SBO IR 05000412/19930211993-10-22022 October 1993 Insp Rept 50-412/93-21 on 930830-0903 & 1004-08.No Violation Noted.Major Areas Inspected:Isi Program,Scope of ISI Work, Eddy Current Exam Program for SG Tubes,Erosion/Corrosion Monitoring Program for High Energy Sys & SG Leakage Program IR 05000334/19930201993-10-21021 October 1993 Insp Repts 50-334/93-20 & 50-412/93-20 on 930907-10.No Violations of Regulatory Requirements Noted.Major Areas Inspected:Bvps Ep,Program Changes,Emergency Facilities, ERO Training & Staff Knowledge ML20057E8331993-09-30030 September 1993 Insp Repts 50-334/93-21 & 50-412/93-22 on 930824-0927. Violations Noted.Major Areas Inspected:Plant Operations, Maint & Surveillance,Engineering,Plant Support & Safety Assessment/Quality Verification IR 05000334/19930161993-09-0808 September 1993 Insp Repts 50-334/93-16 & 50-412/93-17 on Stated Date. Violations Noted,Not Cited.Major Areas Inspected:Plant Operations,Maint & Surveillance,Engineering,Plant Support & Safety Assessment/Quality Verification IR 05000334/19930181993-08-30030 August 1993 Insp Repts 50-334/93-18 & 50-412/93-19 on 930809-13.No Safety Concerns or Violations Noted.Major Areas Inspected: Mgt Support,Audits & Security Program Plans,Protected & Vital Area Physical Barriers & Detection & Assessment Aids IR 05000334/19930151993-08-0606 August 1993 Insp Repts 50-334/93-15 & 50-412/93-16 on 930726-30.No Violations Noted.Major Areas Inspected:Transportation of Radioactive Matls,Radwaste Processing,Staffing Levels,Staff Qualifications,Training & Quality Assurance IR 05000334/19920301993-02-0909 February 1993 Insp Repts 50-334/92-30 & 50-412/92-29 on 921222-930125.No Violations Noted.Major Areas Inspected:Plant Operations, Radiological Controls,Surveillance & Maint,Emergency Preparedness & Security IR 05000334/19920281993-02-0202 February 1993 Insp Repts 50-334/92-28 & 50-412/92-27 on 921215-18.No Violations Noted.Major Areas Inspected:Design Changes,Mods, TER Process,Lers & Status of Previously Identified Open Items IR 05000334/19920261992-12-31031 December 1992 Insp Repts 50-334/92-26 & 50-412/92-26 on 921119-1221.No Violations Noted.Major Areas Inspected:Plant Operations, Radiological Controls,Surveillance & Maint,Emergency Preparedness,Security & Engineering & Technical Support IR 05000334/19920241992-12-0101 December 1992 Insp Repts 50-334/92-24 & 50-412/92-24 on 921013-1118.No Violations Noted.Major Areas Inspected:Plant Operations, Radiological Controls,Surveillance & Maint,Emergency Preparedness,Security & Engineering & Technical Support 1999-09-07
[Table view] Category:INSPECTION REPORT
MONTHYEARIR 05000334/19990061999-10-0707 October 1999 Insp Repts 50-334/99-06 & 50-412/99-06 on 990809-13 & 990823-27.Violations Noted.Major Areas Inspected:Licensee Corrective Action Program Implementation IR 05000334/19990051999-09-30030 September 1999 Insp Repts 50-334/99-05 & 50-412/99-05 on 990725-0904.Two Violations Noted & Being Treated as Nvcs.Major Areas Inspected:Aspects of Licensee Operations,Maint,Engineering & Plant Support ML20211Q5791999-09-0707 September 1999 Insp Rept 50-412/99-07 on 990720-29.No Violations Noted. Major Areas Inspected:Operations,Maint & Engineering IR 05000334/19990041999-08-24024 August 1999 Insp Repts 50-334/99-04 & 50-412/99-04 on 990613-0724. Violations Noted.Major Areas Inspected:Licensee Operations, Engineering,Maint & Plant Support IR 05000334/19990031999-07-0707 July 1999 Insp Repts 50-334/99-03 & 50-412/99-03 on 990502-0612.No Violations Noted.Major Areas Inspected:Operations, Engineering,Maintenance & Plant Support.Results of Y2K Readiness Assessment Also Included IR 05000334/19990021999-05-21021 May 1999 Insp Repts 50-334/99-02 & 50-412/99-02 on 990321-0501.No Violations Noted.Major Areas Inspected:Licensee Operations, Engineering,Maint & Plant Support IR 05000334/19990011999-04-22022 April 1999 Insp Rept 50-334/99-01 & 50-412/99-01 on 990207-0320. Violations Noted.Major Areas Inspected:Operations, Maintenance,Engineering & Plant Support.Also Results of Insp by Regional Security & Inservice Insp Specialists IR 05000334/19980111999-02-25025 February 1999 Insp Repts 50-334/98-11 & 50-412/98-11 on 981227-990206. Violations Noted.Major Areas Inspected:Operations,Maint & Plant Support IR 05000334/19980091999-02-0505 February 1999 Insp Repts 50-334/98-09 & 50-412/98-09 on 981115-1217. Violations Noted.Major Areas Inspected:Engineering IR 05000334/19980101999-01-13013 January 1999 Insp Repts 50-334/98-10 & 50-412/98-10 on 981115-1226.No Violations Noted.Major Areas Inspected:Licensee Operations, Engineering,Maint & Plant Support.Matl Condition of Fire Protection Equipment Installed in Plant Was Excellent IR 05000334/19980061998-12-0404 December 1998 Corrected Pages 17 & 18 to Insp Repts 50-334/98-06 & 50-412/98-06,correcting Errors on Subj Pages ML20196H3231998-12-0202 December 1998 Insp Repts 50-334/98-06 & 50-412/98-06 on 981004-1114.No Violations Noted.Major Areas Inspected:Aspects of Licensee Operations,Engineering,Maint & Plant Support ML20196H2951998-12-0202 December 1998 Insp Repts 50-334/98-08 & 50-412/98-08 on 981026-30.No Violations Noted.Major Areas Inspected:Operations & Maint IR 05000334/19980071998-11-0505 November 1998 Insp Repts 50-334/98-07 & 50-412/98-07 on 981006-07.No Violations Noted.Major Areas Inspected:Performance of Emergency Response Organization IR 05000334/19980051998-10-23023 October 1998 Insp Repts 50-334/98-05 & 50-412/98-05 on 980816-1003. Apparent Violations Being Considered for Escalated Enforcement Action.Major Areas Inspected:Operations, Engineering,Maint & Plant Support ML20151Z3231998-09-15015 September 1998 Insp Repts 50-334/98-04 & 50-412/98-04 on 980628-0815. Violation Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000334/19980031998-08-0505 August 1998 Insp Repts 50-334/98-03 & 50-412/98-03 on 980426-0627. Violations Noted.Major Areas Inspected:Aspects of Licensee Operations,Engineering,Maint & Plant Support ML20217F5951998-04-22022 April 1998 Insp Repts 50-334/98-01 & 50-412/98-01 on 980208-0321. Violations Noted.Major Areas Inspected:Operations, Engineering,Maint & Plant Support ML20217B9851998-03-17017 March 1998 Insp Repts 50-334/97-11 & 50-412/97-11 on 971228-980207. Violations Noted.Major Areas Inspected:License Operations, Engineering,Maint & Plant Support.Security Program Was Also Inspected ML20216E8191998-03-0909 March 1998 Insp Repts 50-334/98-80 & 50-412/98-80 on 980105-0212. Violations Noted.Major Areas Inspected:Evaluation of Implementation of 10CFR50.59 SE Program Relating to Changes, Tests or Experiments at Plant ML20202A9691998-02-0404 February 1998 Insp Repts 50-334/97-09 & 50-412/97-09 on 971116-1227. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support.Rept Also Includes Results of Announced Insp in Areas of Emergency Preparedness ML20203D7421997-11-26026 November 1997 Insp Repts 50-334/97-08 & 50-412/97-08 on 971005-1115. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000334/19970071997-11-0707 November 1997 Insp Repts 50-334/97-07 & 50-412/97-07 on 970831-1004. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000334/19970061997-09-18018 September 1997 Insp Repts 50-334/97-06 & 50-412/97-06 on 970720-0830.No Violations Noted.Major Areas Inspected:Operations, Engineering,Maintenance & Plant Support & Licensed Operator Requalification Training Program IR 05000334/19970051997-08-18018 August 1997 Insp Repts 50-334/97-05 & 50-412/97-05 on 970608-0719. Violations Noted.Major Areas Inspected:Operations, Engineering,Maintenance & Plant Support IR 05000334/19970021997-05-23023 May 1997 Insp Repts 50-334/97-02 & 50-412/97-02 on 970316-0426. Violations Noted.Major Areas Inspected:Operations, Engineering,Maintenance & Plant Support ML20141E9451997-04-27027 April 1997 Integrated Insp Repts 50-334/97-04 & 50-412/97-04 on 970427-0607.Violations Noted.Major Areas Inspected:Licensee Operations,Engineering,Maint & Plant Support ML20137Q6851997-04-0707 April 1997 Insp Repts 50-334/97-01 & 50-412/97-01 on 970209-0315.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support ML20135B7781997-02-21021 February 1997 Insp Repts 50-334/96-10 & 50-412/96-10 on 961222-970208. Violations Noted.Major Areas Inspected:Licensee Operations, Engineering,Maint, & Plant Support IR 05000344/19960051997-02-13013 February 1997 Correction to Insp Repts 50-344/96-05 & 72-0017/96-02. Requests That Encl Pages Be Added as Last Two Pages of Listed Insp Rept IR 05000334/19960091997-01-0202 January 1997 Insp Repts 50-334/96-09 & 50-412/96-09 on 961117-1221.No Violations Noted.Major Areas Inspected:Operations, Engineering,Maintenance & Plant Support IR 05000334/19960111996-12-23023 December 1996 Insp Repts 50-334/96-11 & 50-412/96-11 on 961209-12.No Violations Noted.Major Areas Inspected:Authorization Program & Administration Organization ML20135C4081996-11-16016 November 1996 Insp Repts 50-334/96-08 & 50-412/96-08 on 960929-1116.No Violations Noted.Major Areas Inspected:Operations, Maintenance,Engineering & Plant Support IR 05000334/19960071996-11-0808 November 1996 Insp Repts 50-334/96-07 & 50-412/96-07 on 960813-0928. Violations Noted.Major Areas Inspected:Operations, Engineering,Maint & Plant Support ML20058Q0221993-12-15015 December 1993 AIT IR 50-412/93-81 on 931109-19.No Violations Noted. Major Areas Inspected:Detailed Review of Circumstances Surrounding Failure of Both Emergency Diesel Generator Load Sequencers During Routine Surveillance Testing IR 05000334/19930261993-12-0808 December 1993 Insp Repts 50-334/93-26 & 50-412/93-28 on 931026-1127. Violations Noted.Major Areas Inspected:Plant Operations, Maint & Surveillance,Engineering,Plant Support & Safety Assessment/Quality Verification IR 05000412/19930251993-11-29029 November 1993 Insp Rept 50-412/93-25 on 931018-22.Violations Noted. Major Areas Inspected:Adequacy of Repair & Maintenance of Safety Class 1 Valves,Including follow-up of Auxiliary Feedwater (AFW) Water Hammer Issue IR 05000334/19930251993-11-23023 November 1993 Insp Repts 50-334/93-25 & 50-412/93-26 on 931018-22.No Violations Noted.Major Areas Inspected:Organization & Staffing Levels,Staff Qualifications & Training,External & Internal Exposure Control & Radiological Surveys IR 05000334/19930221993-10-29029 October 1993 Insp Repts 50-334/93-22 & 50-412/93-23 on 930928-1025. Violations Noted.Major Areas Inspected:Plant Operations, Maint,Engineering & Plant Support IR 05000334/19930801993-10-27027 October 1993 Insp Repts 50-334/93-80 & 50-412/93-80 on 930830-0903.No Violations Noted.Major Areas Inspected:Adequacy of Programs, Procedures,Training,Equipment & Sys for Implementing SBO IR 05000412/19930211993-10-22022 October 1993 Insp Rept 50-412/93-21 on 930830-0903 & 1004-08.No Violation Noted.Major Areas Inspected:Isi Program,Scope of ISI Work, Eddy Current Exam Program for SG Tubes,Erosion/Corrosion Monitoring Program for High Energy Sys & SG Leakage Program IR 05000334/19930201993-10-21021 October 1993 Insp Repts 50-334/93-20 & 50-412/93-20 on 930907-10.No Violations of Regulatory Requirements Noted.Major Areas Inspected:Bvps Ep,Program Changes,Emergency Facilities, ERO Training & Staff Knowledge ML20057E8331993-09-30030 September 1993 Insp Repts 50-334/93-21 & 50-412/93-22 on 930824-0927. Violations Noted.Major Areas Inspected:Plant Operations, Maint & Surveillance,Engineering,Plant Support & Safety Assessment/Quality Verification IR 05000334/19930161993-09-0808 September 1993 Insp Repts 50-334/93-16 & 50-412/93-17 on Stated Date. Violations Noted,Not Cited.Major Areas Inspected:Plant Operations,Maint & Surveillance,Engineering,Plant Support & Safety Assessment/Quality Verification IR 05000334/19930181993-08-30030 August 1993 Insp Repts 50-334/93-18 & 50-412/93-19 on 930809-13.No Safety Concerns or Violations Noted.Major Areas Inspected: Mgt Support,Audits & Security Program Plans,Protected & Vital Area Physical Barriers & Detection & Assessment Aids IR 05000334/19930151993-08-0606 August 1993 Insp Repts 50-334/93-15 & 50-412/93-16 on 930726-30.No Violations Noted.Major Areas Inspected:Transportation of Radioactive Matls,Radwaste Processing,Staffing Levels,Staff Qualifications,Training & Quality Assurance IR 05000334/19920301993-02-0909 February 1993 Insp Repts 50-334/92-30 & 50-412/92-29 on 921222-930125.No Violations Noted.Major Areas Inspected:Plant Operations, Radiological Controls,Surveillance & Maint,Emergency Preparedness & Security IR 05000334/19920281993-02-0202 February 1993 Insp Repts 50-334/92-28 & 50-412/92-27 on 921215-18.No Violations Noted.Major Areas Inspected:Design Changes,Mods, TER Process,Lers & Status of Previously Identified Open Items IR 05000334/19920261992-12-31031 December 1992 Insp Repts 50-334/92-26 & 50-412/92-26 on 921119-1221.No Violations Noted.Major Areas Inspected:Plant Operations, Radiological Controls,Surveillance & Maint,Emergency Preparedness,Security & Engineering & Technical Support IR 05000334/19920241992-12-0101 December 1992 Insp Repts 50-334/92-24 & 50-412/92-24 on 921013-1118.No Violations Noted.Major Areas Inspected:Plant Operations, Radiological Controls,Surveillance & Maint,Emergency Preparedness,Security & Engineering & Technical Support 1999-09-07
[Table view] Category:UTILITY
MONTHYEARIR 05000334/19900191990-10-0101 October 1990 Insp Repts 50-334/90-19 & 50-412/90-19 on 900917-21.No Violations Noted.Major Areas Inspected:Status of Previously Identified Items,Organization & Training,Internal & External Exposure Controls & ALARA IR 05000334/19900121990-07-24024 July 1990 Insp Repts 50-334/90-12 & 50-412/90-12 on 900505-0622. Violations Noted.Major Areas Inspected:Plant Operations, Radiological Protection,Surveillance & Maint,Emergency Preparedness,Security & Engineering & Technical Support IR 05000334/19900151990-07-13013 July 1990 Insp Repts 50-334/90-15 & 50-412/90-15 on 900611-15.No Violations Noted.Major Areas Inspected:Implementing QA Program in Conformance W/Tech Specs,Regulatory Requirements, Commitments & Industry Guides & Stds IR 05000334/19900161990-07-10010 July 1990 Radiological Controls Insp Repts 50-334/90-16 & 50-412/90-16 on 900604-08.No Violations Noted.Weaknesses Noted.Improvement Noted in Quality of Audits & Appraisals. Major Areas Inspected:Status of Previously Identified Items IR 05000334/19890131989-09-28028 September 1989 Insp Repts 50-334/89-13 & 50-412/89-14 on 890708-0831.No Violations Noted.Major Areas Inspected:Plant Operations, Security,Radiological Controls,Plant Housekeeping & Fire Protection & Fitness for Duty IR 05000334/19890151989-09-22022 September 1989 Insp Rept 50-334/89-15 on 890905-08.No Violations Noted. Major Areas Inspected:Use of Hafa Intl Developed Instrumented Insp Technique as Alternative to Hydrostatic Test Requirements of ASME Section XI IR 05000334/19890141989-09-0808 September 1989 Insp Repts 50-334/89-14 & 50-412/89-15 on 890801-03.No Violations Noted.Major Areas Inspected:Partial Participation in Annual Emergency Preparedness Exercise on 890802 IR 05000334/19890171989-08-24024 August 1989 Insp Repts 50-334/89-17 & 50-412/89-17 on 890731-0810.No Violations or Deviations Noted.Major Areas Inspected: Corporate Engineering Support Program,Including Staffing,Qa, Training,Mgt Support & Communications IR 05000334/19890121989-08-0909 August 1989 Insp Repts 50-334/89-12 & 50-412/89-13 on 890523-0707. Violations Noted.Major Areas Inspected:Plant Operations, Security,Radiological Controls,Plant Housekeeping & Fire Protection,Surveillance Testing & Maint IR 05000334/19890081989-07-20020 July 1989 Insp Repts 50-334/89-08 & 50-412/89-08 on 890501-05.No Violations Noted.Major Areas Inspected:Evaluation of Effectiveness of Licensed Operator Training Program & Discussions W/Cognizant Training Personnel IR 05000334/19890111989-07-12012 July 1989 Safety Insp Repts 50-334/89-11 & 50-412/89-12 on 890531- 0602.No Violations Noted.Major Areas Inspected:Emergency Preparedness Program Including Review of Previously Identified Insp Findings & Changes to Program IR 05000334/19890101989-06-28028 June 1989 Insp Repts 50-334/89-10 & 50-412/89-11 on 890515-19.No Violations Noted.Major Areas Inspected:Engineering & Maint for Limit & Torque Switch Settings in motor-operated Valves & Corrective Actions from Bulletin 85-003 IR 05000412/19890101989-06-0909 June 1989 Insp Rept 50-412/89-10 on 890515-19.No Violations Noted. Major Areas Inspected:Inservice Insp Activities,Including Observations of NDE in Progress,Implementing NDE Procedures & Review of Inservice Insp Data IR 05000334/19890091989-06-0808 June 1989 Physical Security Insp Repts 50-334/89-09 & 50-412/89-09 on 890508-11.No Violation Noted.Major Areas Inspected:Mgt Support,Security Program Plans & Audit,Protected & Vital Area Physical Barriers & Detection & Assessment Aids IR 05000334/19890051989-06-0606 June 1989 Insp Repts 50-334/89-05 & 50-412/89-05 on 890401-0522.No Violations or Unresolved Items Noted.Major Areas Inspected: Plant Operations,Security,Radiological Controls,Plant Housekeeping & Fire Protection & LERs ML20247K9501989-05-15015 May 1989 Insp Repts 50-334/89-07 & 50-412/89-07 on 890417-21.No Deficiencies Noted.Major Areas Inspected:Licensee Activities in Response to NRC Info Notice 86-053 Re Heat Shrink Tubing IR 05000334/19890061989-05-12012 May 1989 Radiological Controls Insp Repts 50-334/89-06 & 50-412/89-06 on 890410-14.No Violations Identified.Major Areas Inspected: Organization & Staffing,Training & Qualifications, Procedures & Internal & External Exposure Controls IR 05000334/19890041989-04-19019 April 1989 Insp Repts 50-334/89-04 & 50-412/89-04 on 890216-0331. Violations Noted.Major Areas Inspected:Licensee Action on Previous Insp Findings,Plant Operations,Security, Radiological Controls,Plant Housekeeping & Fire Protection IR 05000334/19890011989-03-0202 March 1989 Insp Repts 50-334/89-01 & 50-412/89-01 on 890101-0215.No Violations or Unresolved Items Identified.Major Areas Inspected:Licensee Actions on Previous Insp Findings,Plant Operations,Security,Radiological Controls & Fire Protection IR 05000334/19880271988-11-28028 November 1988 Insp Repts 50-334/88-27 & 50-412/88-21 on 881017-21.No Violations Noted.Major Areas Inspected:Licensee Radioactive Effluent Controls,Radwaste & Transportation & Radiological Environ Monitoring Programs IR 05000334/19880251988-10-31031 October 1988 Insp Repts 50-334/88-25 & 50-412/88-19 on 880901-30.No Violations Noted.Major Areas Inspected:Actions on Previous Insp Findings,Plant Operations,Security,Radiological Controls,Plant Housekeeping & Fire Protection & Maint ML20154F4151988-09-0101 September 1988 Environ Qualification Enforcement Conference Rept on 880812. Major Areas Discussed:Concerns About Environ Qualification Continental Cable & Containment high-range Radiation Monitors & Wiring Inside Limitorque motor-operated Valves IR 05000334/19880221988-08-12012 August 1988 Insp Repts 50-334/88-22 & 50-412/88-16 on 880601-0715. Violations Noted.Major Areas Inspected:Licensee Actions on Previous Insp Findings,Plant Operations,Security & Physical Protection,Radiological Controls & Fire Protection IR 05000334/19880151988-07-14014 July 1988 Insp Repts 50-334/88-15 & 50-412/88-10 on 880606-10.No Violations or Deviations Noted.Major Areas Inspected: Corporate Engineering Support Program Including Organization & Staffing,Qa,Training & Mgt Support & Communications IR 05000334/19880211988-07-14014 July 1988 Insp Rept 50-334/88-21 on 880509-13.Violations Noted.Major Areas Inspected:Licensee Corrective Actions on Concerns Identified in Equipment Qualification Insp 50-334/86-12 Conducted in June 1986 IR 05000334/19880191988-07-0707 July 1988 Insp Repts 50-334/88-19 & 50-412/88-15 on 880516-20.No Violations Noted.Major Areas Inspected:Radioactive Gaseous & Liquid Effluent Controls Program Including Radioactive Discharges & Radiation Monitoring Sys Calibrs & Tests IR 05000334/19880181988-06-20020 June 1988 Insp Repts 50-334/88-18 & 50-412/88-14 on 880509-13. Violations Noted.Major Areas Inspected:Licensee Action on Previous Findings,Organization & Staffing,Audits,Alara, External & Internal Exposure Controls & Startup Testing IR 05000334/19880171988-06-20020 June 1988 Resident Insp Repts 50-334/88-17 & 50-412/88-13 on 8880501-31.No Violations Noted.Major Areas Inspected:Plant Operations,Physical Security,Radiological Controls,Plant Housekeeping & Fire Protection,Surveillance Testing & Maint IR 05000334/19880141988-06-0707 June 1988 Insp Repts 50-334/88-14 & 50-412/88-09 on 880425-29.No Violations Noted.Major Areas Inspected:Unresolved Items,Plan & Implementing Procedures,Organization,Program Audit,Records & Repts,Testing & Maint IR 05000334/19880201988-06-0606 June 1988 Insp Repts 50-334/88-20 & 50-412/88-12 on 880509-13.No Violations Noted.Major Areas Inspected:Actions on Fire Protection Program Activities IR 05000334/19880101988-05-25025 May 1988 Insp Rept 50-334/88-10 on 880222-26.No Violations or Unresolved Items Noted.Major Areas Inspected:Licensee Actions on Previous Insp Findings,Configuration Mgt, Inadequate Core Cooling Sys Installation & Startup Testing IR 05000334/19880131988-05-16016 May 1988 Insp Repts 50-334/88-13 & 50-412/88-08 on 880411-15.No Violations Noted.Major Areas Inspected:Radiological Measurements Program Using NRC I Mobil Radiological Measurements Lab & Lab Assistance by DOE IR 05000334/19880161988-05-16016 May 1988 Insp Repts 50-334/88-16 & 50-412/88-11 on 880401-30.No Violations Noted.Major Areas Inspected:Licensee Actions on Previous Insp Findings,Plant Operation,Physical Security, Radiological Controls,Plant Housekeeping & Fire Protection IR 05000334/19880081988-05-0404 May 1988 Insp Rept 50-334/88-08 on 880321-0401.Violations Noted.Major Areas Inspected:Reliability & Availability of Ac & Dc Power Sys,Diesel Generators,Eccs & Auxiliary Feedwater Sys IR 05000334/19880111988-04-28028 April 1988 Insp Repts 50-334/88-11 & 50-412/88-07 on 880216-0331.No Violations Noted.Major Areas Inspected:Licensee Actions on Previous Insp Findings,Plant Operations,Physical Security, Radiological Controls & Plant Housekeeping ML20151N5061988-04-13013 April 1988 Insp Rept 50-334/88-02 on 880201-05.Deviation Noted.Major Areas Inspected:Licensee Conformance to NRC Approved Procedure Generation Package Re Development & Implementation of Emergency Operating Procedures ML20151G5721988-04-0404 April 1988 Insp Repts 50-334/88-09 & 50-412/88-05 on 880222-26. Violations Noted.Major Areas Inspected:Licensee Solid Radwaste & Transportation Program Including Mgt Control, Shipments of Radioactive Matls,Training & Procedures IR 05000334/19880061988-03-24024 March 1988 Insp Rept 50-334/88-06 on 880208-12.No Violations or Deviations Noted.Major Areas Inspected:Steam Generator Eddy Current Insp,Water Chemistry Controls & Steam Generator Maint Radiological Controls IR 05000334/19880071988-03-10010 March 1988 Insp Repts 50-334/88-07 & 50-412/88-04 on 880208-12.No Violations or Deviations Noted.Major Areas Inspected: Licensee Compliance to NRC Order to Modify Unit 1 License Re Primary Coolant Sys Isolation Valves ML20150B5511988-03-0909 March 1988 Insp Rept 50-334/88-12 on 880303-08.Violation & Deviation Noted.Major Areas inspected:880303 Event Involving Inoperability of Two of Four hi-hi Containment Pressure Channels Due to Placement of Associated Bistables IR 05000334/19880011988-03-0909 March 1988 Insp Repts 50-334/88-01 & 50-412/88-01 on 880101-0215.No Violations Noted.Major Areas Inspected:Plant Operations, Maint Activities,Surveillance Testing,Diesel Generator Air Start Motor Lubrication Followup & Fitness for Duty Program ML20148C4121988-03-0404 March 1988 Insp Rept 50-412/88-03 on 880201-03.No Violations Noted.One Item Remained Unresolved at End of Insp.Major Areas Inspected:Total Loss of Control Room Annunciators on 880128 IR 05000334/19880041988-03-0303 March 1988 Insp Rept 50-334/88-04 on 880201-05.No Violations or Deviations Noted.Major Areas Inspected:Inservice Test Program Implementation of Pumps & Valves,Review of Procedures & Test Results & Test Witnessing ML20150B5401988-03-0202 March 1988 Insp Repts 50-334/88-03 & 50-412/88-02 on 880125-29. Violation Noted.Major Areas Inspected:Licensee Implementation of Radiological Controls Program During Unit 1 Outage,Diving Operations,Posting & Labeling & ALARA IR 05000334/19870191988-02-0808 February 1988 Insp Repts 50-334/87-19 & 50-412/87-69 on 871121-1231.No Violations Noted.Major Areas Inspected:Licensee Actions on Previous Insp Findings,Plant Operations,Physical Security, Radiological Controls & Fire Protection IR 05000334/19870171988-02-0303 February 1988 Partially Withheld Physical Security Insp Repts 50-334/87-17 & 50-412/87-66 on 871123-25 (Ref 10CFR73.21).No Noncompliance Noted.Major Areas Inspected:Plan & Implementing Procedures,Program Audits & Records & Repts IR 05000412/19870671987-12-28028 December 1987 Insp Rept 50-412/87-67 on 871119-25.No Violations Noted. Major Areas Inspected:Startup Test Program,Power Ascension Tests & Test Results ML20238C1151987-12-22022 December 1987 Insp Rept 50-334/87-16 on 871030-1203.No Violations Noted. Major Areas Inspected:Licensee Actions on Previous Insp Findings,Plant Operations,Physical Security,Radiological Controls,House Keeping & Fire Protection IR 05000412/19870681987-12-16016 December 1987 Insp Rept 50-412/87-68 on 871118-21.No Violation Noted. Major Areas Inspected:Root Cause & Safety Significance of 871117 Event & Review of Licensee Corrective Actions, Precursor Events & Potential for Similar Events IR 05000412/19870641987-12-11011 December 1987 Insp Rept 50-412/87-64 on 871010-1120.No Violations Noted. Major Areas Inspected:Licensee Actions on Previous Findings, Site Activities,Followup on Loss of Offsite Power & LER Review 1990-07-24
[Table view] Category:TEXT-INSPECTION & AUDIT & I&E CIRCULARS
MONTHYEARPNO-I-99-048, on 991022,operators Initiated Plant Shutdown from 100% Reactor Power,Due to Continued RCS Leakage Through B Pressurizer Code Safety Valve to Primary Relief Tank. Operators Are Reducing Reactor Power at 12% Per H1999-10-22022 October 1999 PNO-I-99-048:on 991022,operators Initiated Plant Shutdown from 100% Reactor Power,Due to Continued RCS Leakage Through B Pressurizer Code Safety Valve to Primary Relief Tank. Operators Are Reducing Reactor Power at 12% Per H ML20217N1491999-10-21021 October 1999 Notice of Violation from Insp on 990720-29.Violation Noted: as of July 1999,licensee Did Not Take Adequate Measures to Assure That Condition Adverse to Quality Involving Macro Biological Fouling of Service Water System Corrected IR 05000334/19990061999-10-0707 October 1999 Insp Repts 50-334/99-06 & 50-412/99-06 on 990809-13 & 990823-27.Violations Noted.Major Areas Inspected:Licensee Corrective Action Program Implementation IR 05000334/19990051999-09-30030 September 1999 Insp Repts 50-334/99-05 & 50-412/99-05 on 990725-0904.Two Violations Noted & Being Treated as Nvcs.Major Areas Inspected:Aspects of Licensee Operations,Maint,Engineering & Plant Support ML20211Q5791999-09-0707 September 1999 Insp Rept 50-412/99-07 on 990720-29.No Violations Noted. Major Areas Inspected:Operations,Maint & Engineering IR 05000334/19990041999-08-24024 August 1999 Insp Repts 50-334/99-04 & 50-412/99-04 on 990613-0724. Violations Noted.Major Areas Inspected:Licensee Operations, Engineering,Maint & Plant Support PNO-I-99-036, on 990718,update to Beaver Valley,Unit 2 Forced Outage Made.Licensee Replaced Suspected Voltage Regulator Control Relays & Satisfactorily Retested EDG 2-2.Resident Inspectors Continue to Monitor Licensee Corrective Action1999-07-26026 July 1999 PNO-I-99-036:on 990718,update to Beaver Valley,Unit 2 Forced Outage Made.Licensee Replaced Suspected Voltage Regulator Control Relays & Satisfactorily Retested EDG 2-2.Resident Inspectors Continue to Monitor Licensee Corrective Action PNO-I-99-033, on 990716,apparent Electrical Fault Occurred During EDG Full Load Test,Which Opened Supply Breaker Between Emergency & Normal 4 Kilovolt Busses.Station Personnel Intend to Resolve & Correct Electrical Fault1999-07-19019 July 1999 PNO-I-99-033:on 990716,apparent Electrical Fault Occurred During EDG Full Load Test,Which Opened Supply Breaker Between Emergency & Normal 4 Kilovolt Busses.Station Personnel Intend to Resolve & Correct Electrical Fault IR 05000334/19990031999-07-0707 July 1999 Insp Repts 50-334/99-03 & 50-412/99-03 on 990502-0612.No Violations Noted.Major Areas Inspected:Operations, Engineering,Maintenance & Plant Support.Results of Y2K Readiness Assessment Also Included IR 05000334/19990021999-05-21021 May 1999 Insp Repts 50-334/99-02 & 50-412/99-02 on 990321-0501.No Violations Noted.Major Areas Inspected:Licensee Operations, Engineering,Maint & Plant Support IR 05000334/19990011999-04-22022 April 1999 Insp Rept 50-334/99-01 & 50-412/99-01 on 990207-0320. Violations Noted.Major Areas Inspected:Operations, Maintenance,Engineering & Plant Support.Also Results of Insp by Regional Security & Inservice Insp Specialists IR 05000412/19993011999-04-20020 April 1999 NRC Operator Licensing Exam Rept 50-412/99-301(including Completed & Graded Tests) for Tests Administered on 990322- 25.All Applicants Passed All Portions of Exams IR 05000334/19980111999-02-25025 February 1999 Insp Repts 50-334/98-11 & 50-412/98-11 on 981227-990206. Violations Noted.Major Areas Inspected:Operations,Maint & Plant Support ML20207E0761999-02-25025 February 1999 Notice of Violation from Insp on 981227-990206.Violation Noted:Licensee Failed to Promptly Identify & Correct Condition Adverse to Quality in That Investigation of Improperly Calibr Channnels Was Incompleted ML20206U3141999-02-0505 February 1999 Notice of Violation from Insp on 981116-1217.Violation Noted:On or Before 981217,design Control Measures Were Not Established to Ensure That Design Basis Closing Voltage Requirements of Circuit Breakers Were Met & Verified IR 05000334/19980091999-02-0505 February 1999 Insp Repts 50-334/98-09 & 50-412/98-09 on 981115-1217. Violations Noted.Major Areas Inspected:Engineering IR 05000334/19980101999-01-13013 January 1999 Insp Repts 50-334/98-10 & 50-412/98-10 on 981115-1226.No Violations Noted.Major Areas Inspected:Licensee Operations, Engineering,Maint & Plant Support.Matl Condition of Fire Protection Equipment Installed in Plant Was Excellent IR 05000334/19980061998-12-0404 December 1998 Corrected Pages 17 & 18 to Insp Repts 50-334/98-06 & 50-412/98-06,correcting Errors on Subj Pages ML20196H2951998-12-0202 December 1998 Insp Repts 50-334/98-08 & 50-412/98-08 on 981026-30.No Violations Noted.Major Areas Inspected:Operations & Maint ML20196H3231998-12-0202 December 1998 Insp Repts 50-334/98-06 & 50-412/98-06 on 981004-1114.No Violations Noted.Major Areas Inspected:Aspects of Licensee Operations,Engineering,Maint & Plant Support IR 05000334/19980071998-11-0505 November 1998 Insp Repts 50-334/98-07 & 50-412/98-07 on 981006-07.No Violations Noted.Major Areas Inspected:Performance of Emergency Response Organization IR 05000334/19980051998-10-23023 October 1998 Insp Repts 50-334/98-05 & 50-412/98-05 on 980816-1003. Apparent Violations Being Considered for Escalated Enforcement Action.Major Areas Inspected:Operations, Engineering,Maint & Plant Support ML20151Z3231998-09-15015 September 1998 Insp Repts 50-334/98-04 & 50-412/98-04 on 980628-0815. Violation Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support ML20151Z3181998-09-15015 September 1998 Notice of Violation from Insp on 980628-0815.Violation Noted:On 980808,inspectors Observed Maint Supervisor Manipulate Outboard Pump Packing Supply Valve & Perform Maint by Adjusting Outboard Packing Gland Nuts IR 05000334/19983011998-08-21021 August 1998 Exam Repts 50-334/98-301OL & 50-412/98-301OL Conducted During Wks of 980803-07 & 17-21.Exam Results:Four Unit 2 SRO Candidates Passed All Portions of Initial Exam.Good Performance Noted During Exam in Area of Crew Communication ML20236X8661998-08-0505 August 1998 Notice of Violation from Insp on 980426-0627.Violation Noted:From 1988 to Sept 1997,licensee Routinely Vented Units 1 & 2 HHSI Piping Prior to Surveillance Testing W/O Proper Controls to Evaluate Amount of Gas.No Response Required IR 05000334/19980031998-08-0505 August 1998 Insp Repts 50-334/98-03 & 50-412/98-03 on 980426-0627. Violations Noted.Major Areas Inspected:Aspects of Licensee Operations,Engineering,Maint & Plant Support ML20236X8631998-08-0505 August 1998 Notice of Violation from Insp on 980426-0627.Violation Noted:During Period of 980428-0608,licensee Failed to Implement Procedures as Evidenced by Listed Examples IR 05000334/19983001998-06-0303 June 1998 Exam Rept 50-334/98-300OL Conducted on 980420-24 & 0518.Exam Results:Three SRO Instant Candidates Passed All Portions of Initial License Exam ML20217F5881998-04-22022 April 1998 Notice of Violations from Insp on 980208-0321.Violations Noted:Conditions Adverse to Quality Were Not Promptly Corrected from Nov 1993 to March 1998,util Failed to Correct Known Unit 1 & 2 TS Deficiency in Timely Manner ML20217F5951998-04-22022 April 1998 Insp Repts 50-334/98-01 & 50-412/98-01 on 980208-0321. Violations Noted.Major Areas Inspected:Operations, Engineering,Maint & Plant Support ML20217B9771998-03-17017 March 1998 Notice of Violation from Insp on 971228-980207.Violations Noted:Repair Activities for 2-1 Station Battery Were Not Properly pre-planned & Implemented ML20217B9851998-03-17017 March 1998 Insp Repts 50-334/97-11 & 50-412/97-11 on 971228-980207. Violations Noted.Major Areas Inspected:License Operations, Engineering,Maint & Plant Support.Security Program Was Also Inspected ML20216E8071998-03-0909 March 1998 Notice of Violation from Insp on 980105-0212.Violations Noted:On 971218 Dl Implemented Change to Temporary Operating Procedure to Allow Operators to Control Cooldown & Heatup Rate of Reactor Coolant by Mean Other than by Regulating ML20216E8191998-03-0909 March 1998 Insp Repts 50-334/98-80 & 50-412/98-80 on 980105-0212. Violations Noted.Major Areas Inspected:Evaluation of Implementation of 10CFR50.59 SE Program Relating to Changes, Tests or Experiments at Plant ML20202A9691998-02-0404 February 1998 Insp Repts 50-334/97-09 & 50-412/97-09 on 971116-1227. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support.Rept Also Includes Results of Announced Insp in Areas of Emergency Preparedness IR 07100116/20120271998-02-0404 February 1998 Notice of Violation from Insp on 971116-1227.Violation Noted:Licensee Had Not Tested 20 of 27 Direct Lines at Alternate EOF in Coraopolis,Pa PNO-I-98-002, on 980130,operators Declared Both Trains of Component Cooling Reactor & Reactor Plant River Water Sys Inoperable Due to Failure to Meet TS Surveillance Testing Requirements.Entered TS 3.0.3 & 4.0.31998-02-0202 February 1998 PNO-I-98-002:on 980130,operators Declared Both Trains of Component Cooling Reactor & Reactor Plant River Water Sys Inoperable Due to Failure to Meet TS Surveillance Testing Requirements.Entered TS 3.0.3 & 4.0.3 IR 05000334/19970101998-01-0909 January 1998 NRC Operator Licensing Exam Rept 50-334/97-10OL (Including Completed & Graded Tests) for Tests Administered on 971215- 18 ML20198K4761998-01-0606 January 1998 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $55,000.Violation Noted:Between 1988 & 970912, Condition Adverse to Quality Existed at Unit 1 & 2,when Excessive Gas Accumulated in HHSI Pumps Suction Lines ML20199A1711997-12-31031 December 1997 EN-97-119:on 980106,notice of Proposed Imposition of Civil Penalty in Amount of $55,000 Issued to Licensee.Action Based on Violation Involving Failure to Take Adequate Action to Correct Significant Condition Adverse to Quality PNO-I-97-077, on 971216,Duquesne Light Co Initiated Unit 2 Reactor Shutdown in Accordance W/Ts 3.0.3.Licensee Plans to Address Unit 2 Design Deficiency for CR Emergency Air Cleanup & Pressurization,During Shutdown1997-12-17017 December 1997 PNO-I-97-077:on 971216,Duquesne Light Co Initiated Unit 2 Reactor Shutdown in Accordance W/Ts 3.0.3.Licensee Plans to Address Unit 2 Design Deficiency for CR Emergency Air Cleanup & Pressurization,During Shutdown ML20203D7421997-11-26026 November 1997 Insp Repts 50-334/97-08 & 50-412/97-08 on 971005-1115. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 07100005/20110151997-11-26026 November 1997 Notice of Violation from Insp on 971005-1115.Violations Noted:Workers,Found in Radiology Controlled Areas,Not Aware of Radiological Conditions in Work or Travel Areas IR 05000334/19970071997-11-0707 November 1997 Insp Repts 50-334/97-07 & 50-412/97-07 on 970831-1004. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support ML20198S6351997-11-0707 November 1997 Notice of Violation from Insp on 970830-1004.Violation Noted:Licensee Changed QA Program Resulting in Reduction in Commitments in QA Program Description Previously Accepted by NRC W/O Prior NRC Approval IR 05000334/19970061997-09-18018 September 1997 Insp Repts 50-334/97-06 & 50-412/97-06 on 970720-0830.No Violations Noted.Major Areas Inspected:Operations, Engineering,Maintenance & Plant Support & Licensed Operator Requalification Training Program ML20217P7731997-08-18018 August 1997 Notice of Violation from Insp on 970608-0719.Violation Noted:Previous Corrective Actions Inadequate in That on 970701,unplanned Engineered Safety Feature Actuation, Occurred During Troubleshooting Activities on Unit 1 IR 05000334/19970051997-08-18018 August 1997 Insp Repts 50-334/97-05 & 50-412/97-05 on 970608-0719. Violations Noted.Major Areas Inspected:Operations, Engineering,Maintenance & Plant Support ML20141G9971997-07-0303 July 1997 Notice of Violation from Insp on 970209-0426.Violation Noted:During EDG Surveillance Tests,Load Test Values Used Were Inadequate to Ensure That EDGs Achieved 2750 Kw Due to Inaccuracies in Kilowatt Meter Instrument Loop 1999-09-07
[Table view] |
See also: IR 05000334/1988002
Text
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U.S. NUCLEAR REGULATORY COMMISSION !
e
Report No.: 50-334/88-02
License No.: DPR - 66 ,
Licensee: Duquesne Light Company ;
P.O. Box 4
Shippingsport, Pennsylvania 15077 ,
- Facility Name
- Beaver Valley Power Station, Unit 1
,
Inspection at: Shippingsport, Pennsylvania ;
Inspection conducted: February 1 - 5, 1988
Inspectors: usM
. BissWtTSenior Operations Specialist
~
k
vate / ;
'o Jdsu.
N. Oudley, Hnior Operations Specialist
y/td88 '
date
Approved by: A '/ / Y ;
P. Eselgroth hief,'FWR Operations Section date l
!
,
Summary: Routine ann unced inspection on February 1-5, 1988
j (Report No. 50-334/88-02)
Areas Inspected: A routine announced inspection was conducted in the area of I
operations to review licensee conformance to the NRC approved Procedure I
Generation Package regarding the development and implementation of their
Emergency Operating Procedures (E0P). Areas examined included the Administra-
tive Program; Technical Adequacy; Writer's Guide conformance; and Independent
Verification of set point values. Temporary Instruction 2515/79, Inspection of
Emergency Operating Procedures was used as inspection guidance.
Results: An apparent deviation of the licensee's commitment to follow its NRC
approved Procedures Generation Package was issued based on the numerous
problems identified during the inspection. The technical content of the
3
licensee's E0P was found to be adequate. However, a number of inconsistencies
,
between the Procedures Generation Package and the E0Ps and Background
j Information documents were found in the areas examined. The basic documents
i
for E0Ps were not controlled, contained errors and were inconsistent with the
, guidance contained in the Procedure Generation Package (paragraph 2.5.1). The
-
! logic terms, branching statements, cautions and sentence structure of the steps
in the E0P did not conform to the guidance in the Procedure Generation Package
4 (paragraph 2.5.3). The nomenclature of plant components and instrumentation
i
'
was not in accordance with the guidance contained in the Procedure Generation
Package and led to operator uncertainty, (paragraphs 2.0.4, 2.5.5 and 2.5.6).
4
The human factor deficiencies in tne E0Ps appear to have been compensated for
{ by the raining and experience of the operators.
8804250315 880413
PDR ADOCK 05000334 l
Q IJCD l
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DETAILS'
-1.0 PERSONS CONTACTED
1.1 DUQUESNF i.IGHT COMPANY
T. Burns DIRECTOR OPERATOR TRAINING -
R. Druga MANAGER TECHNICAL SERVICES
L. Freeland NUCLEAR OPERATIONS SUPERVISOR
K. Grada MANAGER NUCLEAR SAFETY ,
W. Lacey PLANT MANAGER l
F. Lipchick SENIOR LICENSING SUPERVISOR l
A. Mizia SUPERVISOR QA OPERATIONS !
A. Morabito MANAGER NUCLEAR TRAINING l
T. Noonan ASSISTANT PLANT MANAGER
E. Schad SIMULATOR COORDINATOR, TRAINING
F. Schaffner LICENSING ENGINEER
!
8. Sepelak LICENSING ENGINEER
G. Smith PROCEDURES ENGINEER
J. Russell SENIOR QA SPECIALIST
1.2 U.S. NUCLEAR REGULATORY COMMISSION
J. Beall, Senior Resident Inspector
)
S. Pindale, Resident Inspector
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The inspectors also interviewed other licensee personnel during the
,
inspection period.
- Denotes those present at the exit meeting conducted on February 5,
1988. l
2.0 EMERGENCY OPERATING PROCEDURES
!
The purpose of this inspection was to verify that Duquesne Light Company's l
Emergency Operating Procedures (EOPs) were written, verified and validated
in accordance with the licensee's NRC approved Procedures Generation
Package and training was conducted on the use of the procedures.
2.1 REGULATORY REQUIREMENTS / REFERENCES
Regulatory Guide 1.33, Rev. 2 - February 1978, Quality
] Assurance Program Requirements (Operations).
- *
ANSI N18.7-1976, Administrative Controls and Quality
, Assurance for the Operational Phase of Nuclear Power
- Plants,
i
.
.
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j * Westinghouse Owners Group (WOG) - Emergency Response
Guidelines (ERG) - High Pressure Version, Rev.1,
September 1983.
j Requirements for Emergency Response Capability. ~
- NUREG-0899, Guidelines for the Preparation of Emergency [
Operating Procedures.
- Technical Specific ~ations. !
Emergency Operating' Procedures Generation Package,
Revision 1, April 1987. l
2.2 PROGRAM REVIEW
The licensee's program for preparation of E0Ps was reviewed to verify :
J
that: '
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The licensee has developed a Procedure Generation Package which
includes Plant Specific Technical Guidelines, a Plant Specific
- Writers Guide, a description of the program used for verifying
and validating the licensee's E0Ps, and a description of the
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program for training operators on E0Ps. '
i
The licensee has developed Emergency Operating Procedures
,
4
(EOPs) consistent with the guidance of Duquesne Light Company's
and NUREG-0899.
I
- The E0Ps use a consistent format, which was easy to follow and ;
was as defined in their PGP. '
.
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The operators have been trained to use the E0Ps and the E0Ps !
i were useable. !
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- Differences between Westinghouse's Generic Guidelines and the
licensee's specific E0Ps were identified and justifiad. l
The licensee had an administrative program for developing the
E0Ps and controlling changes to them.
The E0Ps were technically adequate and capable of placing the
plant in a safo condition following a reactor trip or actuation
<
of the safety injection system.
9
1
1 2.3 PROGRAM IMPLFMENTATION
Procedures listed in Attachment A were reviewed by the inspectors against
the requirements and committents of paragraph 2.1.
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2.3.1 ADMINISTRATIVE PROGRAM
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The inspectors reviewed the program for controlling Operating
Manual Deficiencies Reports (OMOR) for the E0Ps to ascertain
whether proper controls were being exercised, Several 0MORs
1 were reviewed and the following items verified: !
. ,
' * An adequate description of the procedural change.
An adequate description of the reason for the change.
- Documentation of required authorization.
- The Onsite Safety Committee review and approval of the ,
change.
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Proper final disposition of each change.
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2.3.2 TECHNICAL ADEQUA,CY l
i
The inspectors compared seven E0Ps against the ERGS and also
performed concurrent evaluations of the technical adequacy of the
E0Ps. During this review, the E0Ps were reviewed for consistency ,
, with the ERGS, against the step-by-step verification documenta-
i tion and against the documentation which justified those steps ,
l which deviated from the ERGS.
4 l
2.3.3 HUMAN FACTORS
Five E0Ps were reviewed to determine the extent to which they
followed the format and content instructions committed to in '
the Dr oesne Light Company Writer's Guide and whether they met i
the objectives found in NUREG 0899.
!
{ 2.3.4 VALIDATION / VERIFICATION PROGRAM
Inspectors reviewed sample documentation of the
validation / verification program for adequacy and verified the
j procedures during plant walk through and simulator scenarios,
j 2.3.5 WALK THROUGH
Inspectors conducted a walkthrough of two E0Ps in the main
'
. control room. Comparisons were made between the E0Ps and
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control room main panels, and between valve lineups contained
in the Attachments to the E0Ps and components outside the main
control room, to determine whether:
The controls / displays identified in the E0Ps as being in the
control room were there;
e *
The control / display nomenclature used in the E0Ps was
comparable to that found in the control room;
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- * The control / display to be used to complete a step were
clearly defined; ,
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- The components required to be checked outside the main !
control room were accessible and clearly. marked; and, s
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The displays could be read to the accuracy required by the E0Ps.
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2.3.6 SIMULATOR
An exercise of the E0Ps was conducted on the Beaver Valley
4 Unit 1 simulator. The exercise objectives were:
, *
Tc determine whether the E0Ps are usable for the level
of qualifications, training and experience of the
operating staff, and
- To determine whether the E0Ps are compatible with the !
minimum number of operating staff. i
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l Three simulator exercises were developed to cover the subset of
1
the E0Ps that had been reviewed for the audit. The exercises l
j included:
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Stuck open PORV which is later SHUT; Multiple instrument
. failures
Loss of ALL AC Power
Restoration of one Emergency Bus )
All Steam Generators faulted l
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The scenarios were chosen because they exercised a large
portion of the E0Ps under review, and they covered a variety of
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emergency situations. The scenarios were developed to evaluate the
use of instrumentation, the use of branching statements and the y
use of the critical function status trees.
2.4 OA/QC INVOLVEMENT
The inspectors contacted Quality Assurance (QA) personnel in order to
determine what role QA had in the development and validation of the E0Ps.
- QA management stated that their involvement to date included a review in
March 1987 of the licensee's Procedure Generation Package (PGP) against
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IE Information Notice 86-64 and Appendix B of NUREG 0899, The inspectors
reviewed QAs written comments following this review and the subsequent
resolution to these comments as provided by the Procedures Group. The QA
Supervisor stated that they had not yet performed any audits of the E0P
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program or the E0Ps themselves, however both areas are considered audit- l
able items under the QA program.
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2.5 FINDINGS
2.5.1 ADMINISTRATIVE PROGRAM
Portions of the licensee's procedural change program for E0Ps were
reviewed. The Nuclear Operation Supervisor (N05) is responsible for
approving all discrepancies prior to their incorporation into the E0Ps in
accordance with the Procedure Generation Package, paragraph VI.C.1.g. All
deviations from and additions to the Westinghouse Owner's Group Emergency
Response Guidelines (ERG) are required to be documented on E0P-ERG
Deviation forms in accordance with paragraph VI.B.1.f. No temporary ,
changes to the E0Ps are allowed, and therefore, any procedural changes i
will result in a complete reissue of the affected E0P.
The licensee has a formal program for in'tiating changes to the E0Ps by
using Operating Manual Deficiency Reports (0MDR). The OMDRs are reviewed
by the NOS prior to being given to the E0P writer for resolution. The '
OMDRs are tracked on a computerized system..There is no formal program for
disposition of the OMDRs once they are reviewed by the N05. There is no i
supervisory review of the completed OMDRs or modified E0P-ERG Deviation
fo rms. Only the E0P changes resulting from an OMDR are reviewed by i
supervisory personnel. :
1
A review of the completed E0P-ERG Deviation forms by the inspectors '
identified technical errors. In one case a set point was lined through
and a new set point written in. There was no initial or date for the line
out and the new set point did not correspond to the set point in the E0Ps.
In a second case no E0P-ERG Deviation form existed for E-0 step 29, even
though deviation forms existed for similar steps. All E0P-ERG Deviation
forms are hand written with numerous line outs of technical information
and justifications without explanation or apparent systematic controls.
Changes made to the E0Ps as a result of one Onsite Safety Committee (OSC)
meeting were not documented on the E0P-ERG Deviation forms.
The E0P-ERG Deviation forms did not contain sufficient detail to fully
explain the technical reasons for deviations. In one case, the E0P writer
needed to call the training department in order to explain the intent and
basis for changing E-0 step 1. In a second case, a high head safety
injection pump was secured without a documented engineering basis, l
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Portions of the licensee's Background Information for E0Ps was reviewed.
The background information package for each E0P provides information on
the event symptoms, entry conditions, exit conditions and recovery
techniques used in each E0P. In addition the purpose, basis, actions,
instrumentation, control equipment, knowledge and technical references for
procedural step are provided in Step Description Tables. The majority of
indications presented in the Step Description Tables do not ir.clude the
benchboard identification of the instruments to be used as required in
the Procedure Generation Package Appendix B Section IV.A 4.e. Examples of
indications which were not defined by benchboard identification include
total AFW flow and component cooling flow to RCPs. Many Step Description
Tables did not provide technical references as required by the Procedure
Generation Pr.ckage Appendix B Section IV.A.4.e.
Failurs to include the benchboard identification of the instruments to be
used in the Step Description Tables as required by the Procedures
Generation Package is a part of the deviation identified in paragraph
2.5.7 below.
As part of the review of the E0P-ERG deviation forms, a technical error
was identified in the Procedure Generation Package Section 5, paragraph
11. The paragraph states that the Beaver Valley Unit I component cooling
water (CCW) system is essentially identical to the CCW system of the
reference plant, which is without an appropriate technical basis. The CCW
system of the reference plant cools four components; the RHR heat
i exchanger, the seal water heat exchanger, the containment fan coolers and
the reactor coolant pumps. However, the CCW system at Beaver Valley Unit
I does not cool the RHR heat exchangers nor containment fan coolers, whica
result in differences between steps in the E0P and in the ERG. Review of
Section 5 of the Procedures Generation Package is needed to ensure there
are no other technical errors.
2.5.2 TECHNICAL ADEQUACY
The E0Ps compare well technically with the ERGS. Minor discrepancies were
found that were needed to compensate for the specific plant design and/or
the technical specifications. Many instances were noted where additional
steps were added over and above what was called for in the ERG. The
majority of these additional steps were to provide further clarification
and direction to the operators. E0P-ERG Deviation forms were generated
as necessary, however as stated in paragraph 2.5.1, many forms did not
contain sufficient detail to fully explain the technical basis for
deviations.
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In one instance the licensee deviated from a directive in the ERGS and did
not provide a written technical justification for the deviation. The ERGS
require that additional steps for verification of other essential equip-
ment as required by the specific plant design, should be placed after E-0
step 12. The facility's E0Ps ccntain seven additional steps prior to E-0
step 12 of the ERGS and no E0P-ERG Deviation form has been written. The
licensee stated that the EDPs contained the additional steps because the
supersedea event based reactor trip procedure contained the same step
sequences and in order to minimize the amount of operator retraining
required to implement the new E0Ps, the steps of the superseded trip
procedures were retained. Training concerns are not considered to be a
sufficient technical basis for deviating from the ERGS.
A problem was noted during the review of ECA 0.0, "Loss of all AC Power."
Several actions, such as operation of valves and pumps, are required
during the time period when attempts are being made to restore AC emer-
gency oower to these components. Many of these steps will be impossible
to couplete as long as power is unavailable. ECA 0.0 requires further
review to ensure that power would be available to all components which are
required to be coerated.
2.5.3 HUMAN FACTORS
The human factors review involved a comparison of the E0P with the
Writer's Guide and with NUREG 0899. Discrepancies were grouped into five
main areas. A summary of the major issues for each of the areas is
provided beloe. Specific comments and examples of the major istues are
provided in Attachment B.
Lcgic Terms The Writer's Guide presents definitiens and format
instructions regarding the writing of conditional statements using the
logic terms. While the instructions provided were incomplete, those which
were provided were not applied correctly within the E0Ps. Four major
areas of concern were identified:
- The use of AND and OR (together and sepsrately) within action
statements.
The inappropriate structuring of IF, THEN statements.
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The use of the implicit IF NOT in the Response Not Obtained (RNO)
column.
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The use in the RNO column, of an IF NOT statement witnout an initial '
l' statement.
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_ Referencing and Branching
The E0Ps contained a number of transition terms which were undefined in
the Writer's Guide and inconsistent with the guldance provided.
Notes and Cautions Cautions and Notes in the E0Ps were often misused by
their structure as directives or inclusions of inappropriate information
(i.e., non-critical information in Cautions).
Sentence Structure The E0Ps utilized inconsistent structural methods for
similar types of statements, conflicting not only with the guidance
provided in the Writer's Guide, but utilizing a number of different
structures for one type of statement within a single E0P. In addition,
action statements included two to three directives within one step.
Miscellaneous Other problems were found in the E0Ps including
use of vague terminology and inconsistent use of abbreviations and
acronyms.
The licensee's failure to follow the Writer's Guide is discussed in a
deviation identified in paragraph 2.5.7.
2.5.4 VERIFICATION / VALIDATION
Verification: The licensee's Procedure Generation Package described the
verification of the E0Ps for correctness, using the Writer's Guide as a
basis for evaluation. The program is described as being carried out by a
team of personnel from Operations, Training and Procedures groups. A
checklist is used as a guide to the process and discrepancies are
forwarded to the EOP writer for correction. A decision is made by the NOS
whether a follow-up verification or validation of the draft E0P is needed.
Verification activities at Beaver Valley were carried out by Duquesne
Light Company personnel with assistance from a human factor consultant
during the initial verification.
A control room and plant walk through by inspectors to verify selected
E0P steps identified a number of examples where the nomenclature of
instrumentation in the E0Ps was inconsistent with the nomenclature found
in the control room and the plant. Some examples where the nomenclature in
the E0Ps was different than that found on the name plate data are:
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is now in position A5-9.
- E-0, Attachment 2 refers to MOV-RW-1130 "River Water to D.G.
Heat Exch." which must be checked locally. Due to a design
change MOV-RW-1130 has been replaced by MOV-RW-11301 which is in
a different room.
E-0 Attachment 2 refers to four valves which should be checked
locally at the Diesel Generators, as "River Water to D.G. Heat
Exch." The valves at the generator are labelled "RAW Water
Valves #1 and #2."
The licensee had identified that the nomenclature in the main
control room does not meet the requirements of the Writer's
Guide.
Subsequent observation by the inspectors of the use of the E0Ps on
the simulator indicated that the nomenclature disparity between the
E0Ps and the control room panels presented no confusion to the
operators. However, during the simulator scenarios the lack of
detailed sper.ifications of instrumentation resulted in the operators
using instrumentation which was not in accordance with the licensee's
plant specific background document. Some examples where incorrect
instrumentation was used during the simulator scenarios are:
E-0 step 6.a. the operator used breaker position and an
annunciator window to verify an AC emergency bus was energized.
The background document requires that the voltmeter be used.
E-0 step 9.1, the operator used an annunciator to verify
the turbine-driven AFV pump running. The background
document does not provide an instrument to check for
completing this step. It was .he consensus of the operators
that the position of steam valves are checked for ensuring
the turbine-driven AFW pump is running.
1
Appendix F of the Procedure Generation Package, paragraph II. A.2.b, ;
requires that the E0Ps be reviewed for technical accuracy of
"Operator Instrumentation and Control Needs." Failure to correctly ,
translate control room and plant switch and indicator nomenclature !
into the E0Ps as part of the verification program is a part of the I
deviation Identified in paragraph 2.5.7 below, l
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Validation: The validation process is described in the licensee's
Procedure Generation Package as a demonstration that the operating
staff can manage the emergency condition through the use of the
procedures and that the E0Ps are operationally correct in respoct to
usability, technical correctness, operational correctness and
effectiveness. The Procedure Generation Package indicates that table
top reviews, control room walk through, or simulator exercises will
be used to validate E0Ps. The documentation for the validation of
procedure E-0 was reviewed and found to be adequate for the table top
review, simulator and control room walk through. However , the
inspectors identified discrepancies in procedure E-0 during the plani.
walk through, as described below.
2.5.5 WALK THROUGH
The walk through of procedures in the main control room
and in the plant identified deviations of E0P procedural steps and
the recommendations in the Procedures Generation Package. The Weiter's l
Guide in paragraph V.B.g states that "identification of components i
and parts should be complete." An example of a step which did not i
satisfy this requirement is:
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E-0 Symptomatic Response / Unexpected Conditions, 1 a. CRR flow to
RCP's - NO FLOW INDICATED.
The operator was uncertain what readings would be e a ptable, and the
basis document does not indicate the required ins. ..+nt.
The Writer's Guide in paragraph VI.E.1.d states that "users should .
not be required to add or subtract nembers to determine acceptable i
values." Contrary to this: l
E-0 step 17, Verify Total AFW Flow - GREATER THAN 350 GPM; l
requires the operator to sum the values from three flow
instruments.
- E-0 step 21.a.2,a, RCS/ Highest D/P - LESS THAN 150 PSIO;
requires the operator to select the highest reading from
one of nine pressure instruments and to subtract it from
the reading of a tenth pressure instrument.
- E-0 step 12. a, Steam line pressure high rate of change -
99 PSIG DECREASE IN 50 SECONDS; requires the operator to
calculate a rate of change.
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The walk through in the plant was performed to assess the acequacy of
various factors involved in the performance of ECA 0.0 "Loss of All
AC Peter." Areas reviewed which included equipment identification, acces-
sibility of equipment, and the availability of emergency lighting and-
communications equipment (dedicated Appendix R phone service line)
were found to be adequate. Valves and breakers were for the most-
part readily accessible, with the exception of a few instances'where
temporary scaf folding was in place (e.g., IA-90). Valves TV-CC-107E2
and 02 were difficult to access primarily because of piping confi-
guration.
Valve identification tags were considered inadequate, esptcially when
considering a loss of lighting, when a valve might have to be located
and subsequently operated. Identification tag deficiencies, observed
by the inspector, include tags that were missing, damaged or bareac-
able. The licensee utilizes a lightweight thin metal strip embossed
wi'.h the letters / numbers of the appropriate valve. The dimensions of
the tag are approximately 5" x 1/2" and the tag is normally attached
at one end to the valve body. The inspector found it difficult, in a
nuber of instances, to read the 10 tag, even under normal lighting
conditions. Valves TV-CC-107E2 and 02 are examples in which diffi-
culty was experienced in reading the valve identification tag
numbers. The 10 tags had to be "in-hand" in order to accurately read
them. The readability of the 10 tags presently in use is question-
able. Other examples of 10 tag discrepancies include:
1 MOV-IN-1558 - 10 tag missing
- 1 MOV-IN-ISSA - 10 tag damaged ,
MSIVs vent panel valves - 10 tags missing
1 MOV- N-151 volves - 10 ;ags missing or damaged
Dedicated A W pump valves - missing 10 tags
The licensee >tated that efforte have been underway to ensure that tag ids
are accurate ar.d in place, h: wever it is an ongoing program. Those areas
where pump, valve and breaker manipulations might be called for under loss
of lighting conditions require escalatt.d action.
- _ _ _ _ - _ _ _ _ - _ - - _
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2.5.6 SIMULATOR
No procedural deficiencies were observed during the simulator portion
of the audit. Problems identified during the walk through were con-
firmed in observations and discussions with the operators in-the
simulator. Operator actions were taken in accordance with the-
E0Ps. However, the requirements contained in the ERG Users Guide
were not followed during the development of the E0Ps. For. example:
- E-0 step 1, the operator transitions to FR-S.1 prior to
checking reactor power decreasing. The ERG requires that power
be checked prior to the transition.
E-0 step 6.a, the operator reported power to the AC Emergency
Bus even though the voltmeter indicated zero volts. The ERG
requires the use of the voltmeter.
- E-0 step 24, the operator diu not check the containment
sump level recorder as required by the basis document.
Operator actions were slowed due to the wording of some procedural
steps. ECA 0.0 step 32.a contained an "AND/0R" step which t'ne
operator had to reread several times before proceeding. The operator
experienced difficulty determining subcooling margin requirements
prior to transitioning out of ECA 0.0 "Loss of All AC Power," and
finally referred to a pressure temperature graph which was not part.
of the E0Ps. From observations of operators in the simulator and
from discussions with the licensee, deficiencies identified in the
wording, structure and format of the procedural steps appear to have
been compensated for by operator training and experience instead of
rewriting the steps to correspond to the Writer's Guide,
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2.5.7 SUMMARY
The technical content of the licensee's E0Ps was reviewed in detail
and determined to be consistent with the Westinghouse Owners Group l
Emergency Response Guidelines and the licensee's Procedure Generation
Package. A human factors review of the Writer's Guida, revealed ;
numerous deficiencies including, but not limited to the incorrect and i
inconsistent use of logic statements in the E0Ps. The documentation l
of the deviations identified by the validation program was found to I
be deficient. The basis document for the E0Ps do not include 1
detailed instrument specifications nor references in accordance with
the Procedures Generation Package. The verification program failed
to correctly translate control room and plant switch and indicator
nomenclature into the E0Ps.
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There has been no human factors or quality assurance involvement in l
the validation of the latest revision of the E0Ps. Numerous human
factors issues, related to the Writer's Guide, and numerous
deficiencies identified in the E0P-ERG Deviation Forms and the
Background Information documents indicate deviations from the
Procedures Generation Package. Based upon the above and the detailed
discussions in paragraph 2.5.1, 2.5.3, 2.5.4, 2.5.5, and Attachment
B, this is an apparent deviation of the licensee's commitment to
follow the NRC approved Procedures Generation Package
(50-334/88-02-01).
3. INDEPENDENT VERIFICATION
The inspectors independently verified that various levels and values given
in the E0Ps were consistent with the indicators found in the control room
and that the operators were knowledgeable of where various switches were
located. The inspectors reviewed the documentation of five plant specifi'c
setpoints and determined that the engineering analysis to support the
plant specific setpoints were not referenced in all cases. This failure
to reference supporting documentation contributed to the apparent
deviation summarized in paragraph 2.5.7.
4. EXIT INTERVIEW l
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An exit meeting was held February 5, 1988, to discuss the inspection scope !
and findings, as detailed in this report (see paragraph 1.0 for !
attendees).
At no time was written material given to the licensee. The inspector !
determined that no proprietary information was utilized during the !
inspection. !
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ATTACHMENT A
DUQUESNE LIGHT COMPANY, BEAVER VALLEY UNIT 1, PROCEDURES REVIEW
E-0 Reactor Trip or Safety Injection, Issue 1, Rev. 1
E-3 Steam Generator Tube Rupture, Issue 1, Rev. 1 l
ES-1.1 SI Termination, Issue 1, Rev.1
ES-3.1 SGTR With Loss of Reactor Coolant - Subcooled Recovery l
Desired ECA - 3.1, Issue 1, Rev. 1 l
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ECA 0.0 Loss af All AC Power, Issue 1, Rev. 1
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ECA 0.1 Loss of All AC Power Recovery Without SI Required, Issue 1,
Rev. 1
ECA 2.1 Uncontrolled Depressurization of All Steam Generators,
Issue 1, Rev. 1
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ATTACHMENT B
REVIEW 0F WRITER'S GUIDE
1. The Writer's Guide,Section V.E., presents definitions and format
instructions regarding the writing of conditional statements using logic
terms. The instructions provided are not applied consistently within the
E0Ps. The following problem areas were identified,
a. When used as conjunctions, "and" and "or" join lists, multiple
actions or alternatives. When used as logic terms, they indicate
decision points. It is important that appropriate emphasis be used
when these words are being used in a conditional statement, to signal
to the operator that a decision point has been reached. When used to
indicate multiple actions, alternatives or a list, "and" and "or"
should not be emphasized as logic terms. The Writer's Guide does not
provide explicit direction on the different use and formatting of
"and" and "or". The E0Ps contain different types of formatting for
these words which are not consistent with the Writer's Guide.
Example: E-0, step 25.b and c.
25.b. Secondary heat sink: ,
Total feed flow to intact SGs - GREATER THAN 300 GPM
- OR -
- Narrow range level in at least one intact SG -
GREATER THAN 57.
25.c. RCS pressure - STABLE OR INCREASING
This step uses the conjunction "or" in two different formats. Because
"or" is functioning as a conjunction in both uses, it should be formatted
consistently. While the Writer's Guide lacks format information for the
use of "or" as a conjunction, neither use of "or" within the above step is
consistent with the guidance provided in Section V.E of the' Writer's i
Guide for the emphasis of the logic term OR.
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_ _ . _ . _ . , _ . - _. _ _ . , _ . .., - . _ . _ - - - _ . . . - . . , - . .
- , . .- .-- __ -- _. _ .. ___ .
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Attachment B 2
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Other examples of this type of problem found in the E0Ps
sampled include:
E0P STEP PROBLEMS
E-0 35 -or-
E-0 36.b -AND-
ES-1.1 2 RNO AND (not a conditional statement)
E-0 13. a and
E-0 3 RNO or
E-0 13.a -or-
E-0 13.b RNO ANO (not a conditional statement)
E-0 22.a RNO and (a conditional statement)
b. The Writer's Guide provides direction on the use of the logic
sequence IF, THEN in paragraph V.E.
There are a number of IF NOT, THEN statements which-are not
formatted consistently with the guidance provided.
P
Example:
'
E-0 Step 7 RNO
Check if SI is required: ...
IF SI required, THEN manually actuate.
'
IF SI is NOT required, THEN GO TO ES-0.1, i
W '
Reactor Trip Response," Step 1.
This step conflicts with the format directions in the Writer's
Guide, which indicates that the term IF NOT will not be split.
Other examples of this problem found in the E0Ps sampled include:
E0P STEP
E-0 6.a RNO i
9.f RNO !
>
20.a RNO j
20.b RNO
Example: I
<
ECA-0.0 step 7.a.3 RNO
Verify proper emergency alignment of AFW valves. IF NOT properly aligned,
THEN manually align AFW valves [MOV-FW-151A-F] as necessary
The step does not contain the first conditional IF.
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Attachment B 3
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Other examples of this type of problem found in E0Ps sampled include:
E0P STEP
E-0 13.a.1 RNO
E-0 13.a.2 RNO
E-3 21.a.2 RNO
ECA-0.0 20.c RNO
ECA-0.0 21.b RNO
ECA-0.0 33.a RNO
ECA-1.1 13.f RNO
ECA-2.1 15.b.2 RNO
c. The two column format used in the E0Ps is structured so that
the right hand column includes an implicit "if not" relation- !
ship to the left hand column. In a number of statements in the
E0Ps, the "if not" has been repeated in the right hand column, l
unnecessarily cluttering and complicating the procedure, and not !
taking advantage of the RNO structure.
Examples: l
)
E-0 step 4.b RNO
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IF reheater flow control block valves will NOT close, THEN
manually close main steam line trip, bypass and non-return
valves.
E-0 step 11.a RNO
a. IF CIA has NOT actuated
THEN manually actuate CIA
-0R-
Manually align CIA valves
Other examples of this type of problem found in the E0Ps
sampled include:
E0P STEP
E-0 12.b RNO
E-0 23.d
E-0 23.d RNO
E-0 25.b RNO
ES-1.1 9 RNO
ES-1.1 11 RNO
E-3 17.d RNO
E-3 23.b RNO
E-3 26
ECA-0.0 14 RNO
ECA-0.0 24 RNO
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Attachment B 4
2. The Writer's Gu'ide Section V.H. 2. defines "go to" as the transition term 'l
to be used within the E0Ps and provides format instructions. The EOPs, I
however, use a number of different' terms to indicate movement within and- l
between E0Ps. The Writer's Guide does not define the minimum number of
terms necessary for clear instruction to operators on transitions.
Examples:
E-0, Step 23 RNO
GO TO E-3 "Steam Generator Tube Rupture," Step 1 AND in. i
conjunction complete only Steps 23b through 23d.
,
This step contains two transition terms which is not in accordance with ;
the Writer's Guide and one of the terms is not defined in the Writer's
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Guide.
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ES-1.1 Step 15 RNO !
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a. WHEN PRZR level greater than 18% THEN perform Step 16.
Other examples of this type of problem four.d in the E0Ps !
sampled: ;
E0P STEP TRANSITION TERM OSED
1
ES-1.1 27.a RNO "do" l
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E-3 3 RNO "do"
E-3 30.b RNO "do"
ECA-0.0 18 RNO "perform"
ECA-0.0 16.b RNO "do" l
ECA-0.0 26.a RNO "G0 TO...THEN do"
ECA-2.1 7.f.2 RNO "do"
3. Cautions are used to describe a hazardous condition which can cause
injury or equipment damage and should describe the consequences of the
hazard. Notes are intended to provide supplemental information to the
operator. Neither Cautions nor Notes are to include action statements.
The human factors review revealed several problem areas related to
Cautions and Notes:
Caution (s) and Note (s) in the E0Ps sampled were found to contain ,
directives and references which are action statements. Some Cautions lack -
I
a statement of the hazard at hand and possible consequences. Following
are instances of improper use and structure of Caution (s) and Note (s): I
_ . _ _ - _ - _ _ - - - _ _ _ _ _ _ _ _ _ _ - - _ _ _ _ _ - - - _ - - _ _ _ _ - _ _ - _ _ _ _ _ _ _ _ _ _ _ _ - _ - . _ _ _ _ _ _ - - _ _ _ - _ - - - _ _ - _ _ - - _ _ _ _ .
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Attachment B 5
E-0, page 23
CAUTION: RCS pressure should be monitored. If RCS
pressure decreases to less than 250 PSIG, the LHSI
pumps must be manually restarted to supply water to
the RCS.
This Caution lacks identification of the hazard and consequences
related to a low RCS pressure. The Caution also contains a
directive which more appropriately is an action statement.
Other examples of these types of problems found in the E0Ps
sampled include:
E0P PAGE PROBLEM
E-0 13 Note contains action statement.
E-0 14 Note contains action statement.
ES-1.1 10 Caution lacks identification of the
consequences of the hazard. Caution
contains action statements. i
E-3 7 Caution lacks identification of hazard
or consequence.
E-3 7 Caution contains branching statements.
E-3 14 Caution contains logic statement.
Caution lacks identification of hazard I
or consequence.
E-3 30 Caution lacks identification of i
consequence.
ECA 0.0 17 Note contains action statement,
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ECA 0.1 16 Caution contains logic statement. I
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4. Sentence structure is an important factor in the presentation of clear l
and understandable instructions. The inspector's review identified several
problem areas related to sentence structure in the E0Ps.
a. The Writer's Guide, paragraph V.B.1 indicates that steps are to
be written concisely, describing .just the task to be performed and
that complex evolutions are to be broken down. The following step
includes more than one action:
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- Attachment B 6
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E-3.1 step 5.C
Trend RCS temperature and pressure on the main
computer at 10 minute intervals. Initial the trend
every half hour to ensure that-cooldown does not
exceed 100F/hr in RCS cold legs.
Other examples of these type of problems found in the E0Ps
sampled include:
E0P STEP
ECA-0.0 11
ECA-0.0 26.b RNO
ES-1.1 2
ES-1.1 5.b.3
ES-1.1 22.a
ES-3'.1 5.e
ES-3.1 9.b
ES-3.1 9.e
ES-3.1 11.a
ES-3.1 33
ES-3.1 35 b.3
b. A system of step numbering and identification can assist the operator
j in moving through procedures without confusion. The review of the
E0Ps revealed an inconsistency in the use of bullets which indicate
no preferred order of completing action s ;eps. In some steps where a
check is made of multiple indications, bullets are used, in other 1
steps AND is placed between the indications; and in other steps
'
individual letters are used.
Examples;
E-0 step 3 i
Verify Turbine Trip
'
a. Throttle and governor valves - CLOSED
b. Reheat steps and intercepters - CLOSED
'
E-0 step 22 <
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Check If SGs Are Not Faulted !
4
NO SG PRESSURE DECREASING IN AN UNCONTROLLED
MANNER
'
N0 SG COMPLETELY DEPRESSURIZED
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Attachment B 7
E-0 step 36
Veri fy CNMT Instrument Air - AVAILABLE . . .
b. CNMT instrument air receiver pressure -
GREATER THAN 95 PSIG
- AND -
Annunciator A6-110, "CNMT
Instrument Air System - Pressure
Low" - NOT LIT
Other examples of these types of inconsistencies found in
the E0F; sampled include:
E_0P STEP METHOD
ES-1.1 1 Letters
ES-1.1 2 Bullets
ES-1.1 7 - AND -
ES-1.1 13.d.1 Single bullet
ES-1.1 14 Letters
ES-1.1 24 Single bullet
E-3 17.g AND
ES-3.1 2.a Bullets
ES-3.1 9.a Numbers
ES-3.1 10.a Bullets separated by - or -
5. A number of statements in the E0Ps are vague and do not describe specific
operator behaviors. For example, the operators are instructed to perform
an action "maintain" with no criteria provided as to what the requirements
are. In order to ensure that procedures are understood, directions should
be defined quantitatively. The following are examples of the use of vague
terms noted in the E0Ps:
TERM E0P STEP
Stable (without desired range) E-0 25.c
ES-1.1 21
Maintain (without requirements) ES-1.1 11
ES-1.1 31.b
E-3 5.a
As necess&ry ES-1.1 14.a l
ES-1.1 31.a
E-3 25.b
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6. Other weaknesses identified during the review are noted below:
a. The Writer's Guide includes Table 2, "Abbreviations used in Proce-
dures," yet the E0Ps include a number of abbreviations and acronyms
which are not included in Table 2 or are included in Table 2 in
another form. In addition, the E0Ps include multiple forms of a
number of abbreviations. In order to minimize confusion and ensure
consistently prepared procedures, all acronyms and abbreviations to
be used in the E0Ps should be listed in the PGP.
NOT INCLUDED IN TABLE 2
IA
NCO
NSA
PID
R
Rad Con
R/hr
V
INCONSISTENT WITH TABLE 2
AMPS vice Amp
amps vice Amp
Ft vice FT
D/P vice dP
S/G vice SG
gpm vice GPM
b. The Writer's Guide paragraph V.E.2 states, "the use of AND and OR
within the same action should be avoided." ECA-0.0 steps 32.a aWd b
both contain an AND/0R logic term.
c. The Writer's Guide paragraph V.F.2 states, "the contingency actions
will be specified for each circumstance in which the expected results
or actions might be achieved." ECA-0.0 step 22.a contains tiie
response not obtained action in the left hand column. Other
verification or monitoring steps which do not include response not
obtained actions include:
E0P STEP
ECA-0.0 1.c
ECA-0.0 8
ECA-0.1 15.c
ECA-2.1 31.c
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'd. The Writer's Guide paragraph V.C.1.a states that expected indications
should be presented in the left hand column. ECA-0.0 step 22.b
which checks for DC Bus Loads does not specify the expected
indications,
e. The use of the words OR and AND.in the example in section V.A.3 and 6
1
of the Writer's Guide is inconsistent with the section VI.C.1 of .the .
Writer's Guide which allows underlining of OR and AND only if they'
are used as logic terms. The use of lower case letters for the
expected response in section V.A.7 of the Writer's Guide is
inconsistant with the section VI.B.1.f.3 statement that "any
condition following a hyphen in the left-hand column should be
capitalized." '
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