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Category:INSPECTION REPORT
MONTHYEARIR 05000219/19980121999-03-0404 March 1999 Insp Rept 50-219/98-12 During Periods 981214-18,990106-07 & 20-22.No Violations Identified.Major Areas Inspected: Review of Licensee self-assessment of Plant Environ Qualification Program & Corrective Actions for Open Items IR 05000219/19980091998-11-25025 November 1998 Insp Rept 50-219/98-09 on 980914-1025.Violations Noted. Major Areas Inspected:Operations,Engineering,Maintenance & Plant Support IR 05000219/19980081998-10-20020 October 1998 Insp Rept 50-219/98-08 on 980727-0913.No Violations Noted. Major Areas Inspected:Licensee Operations,Engineering,Maint & Plant Support IR 05000219/19980051998-08-26026 August 1998 Insp Rept 50-219/98-05 on 980614-0726.No Violations Noted. Major Areas Inspected:Plant Operations,Maint,Engineering & Plant Support IR 05000219/19980071998-07-0202 July 1998 Insp Rept 50-219/98-07 on 980615-19.No Violations Noted. Major Areas Inspected:Status of Plant motor-operated Valve Program to Determine Acceptability for Closure of NRC Review Under GL 89-10 ML20217F6641998-04-22022 April 1998 Insp Rept 50-219/98-80 on 980223-0313 & 0330-0402.Violations Noted.Major Areas Inspected:Engineering ML20216H1911998-04-15015 April 1998 Insp Rept 50-219/98-04 on 980226-0318.Violations Noted.Major Areas Inspected:Operations,Maint & Plant Support IR 05000219/19970081997-12-0404 December 1997 Insp Rept 50-219/97-08 on 971020-24.No Violations Noted. Major Areas Inspected:Onsite Emergency Plan IR 05000219/19970041997-07-29029 July 1997 Insp Rept 50-219/97-04 on 970526-0706.Violations Noted. Major Areas Inspected:Aspects of Licensee Operations, Engineering,Maint & Plant Support IR 05000219/19970051997-07-17017 July 1997 Insp Rept 50-219/97-05 on 970407-11.No Violations Noted. Major Areas Inspected:Engineering ML20141G9431997-07-0303 July 1997 Insp Rept 50-219/97-03 on 970414-0525.Violations Noted.Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000219/19970021997-05-19019 May 1997 Insp Rept 50-219/97-02 on 970224-0413.Violations Noted. Major Areas Inspected:Operations,Engineering,Maintenance & Plant Support ML20137E9491997-03-21021 March 1997 Insp Rept 50-219/97-01 on 970113-0223.Violations Noted.Major Areas Inspected:Licensee Operations,Engineering,Maint & Plant Support IR 05000219/19960101996-09-27027 September 1996 Insp Rept 50-219/96-10 on 960923-27.No Violations Noted. Major Areas Inspected:Radiological Source Term Assessment, Results of Exposure Reduction Initiatives & Evidence of Station ALARA Program IR 05000219/19960111996-01-0202 January 1996 Insp Rept 50-219/96-11 on 961021-1201.Violations Noted.Major Areas Inspected:Licensee Operations,Engineering,Maint & Plant Support IR 05000219/19930811993-12-22022 December 1993 Insp Rept 50-219/93-81 on 930927-1015.Violations Noted.Major Areas Inspected:Engineering,Maint,Surveillance & Mgt & Corrective Actions IR 05000219/19930261993-11-18018 November 1993 Insp Rept 50-219/93-26 on 931101-05.No Violations Noted. Major Areas Inspected:Mgt Support,Security Program Plans & Audits,Protected & Vital Area Access Control of Personnel & Packages & Vehicles IR 05000219/19930241993-11-18018 November 1993 Insp Rept 50-219/93-24 on 930921-1101.Violations Noted.Major Areas Inspected:Plant Operations,Maint,Engineering,Plant Support,Including Security & Emergency Preparedness & Safety Assessment/Quality Verification ML20058A3791993-11-12012 November 1993 Insp Rept 50-219/93-23 on 931018-20.Onsite Response to Exercise Scenario Was Good.Major Areas inspected:full- Participation Ingestion Pathway Emergency Preparedness Exercise IR 05000219/19930251993-11-0909 November 1993 Insp Rept 50-219/93-25 on 931018-22.No Violations Noted. Major Areas Inspected:Design Mods & Engineering Support IR 05000219/19930181993-10-28028 October 1993 Insp Rept 50-219/93-18 on 930823-1020.No Violations Noted. Major Areas Inspected:Alara,Rirs,Qa Audits,Air & Swipe Sample Counting Facilities & Radiological Controls Organization Professional Staffing ML20059F6251993-10-28028 October 1993 Insp Rept 50-219/93-22 on 930920-24.No Violations Noted. Major Areas Inspected:Addressed Open Items Associated W/Eop & Reviewed Licensee Actions in Response to Violations Associated W/Recirculation Loop Isolation Event IR 05000219/19930201993-10-19019 October 1993 Insp Rept 50-219/93-20 on 930816-930917.No Violations Noted. Major Areas Inspected:Radioactive Liquid & Gaseous Effluent Control Programs Including Mgt Controls & QA Audits IR 05000219/19930211993-10-15015 October 1993 Insp Rept 50-219/93-21 on 930810-0920.No Violations Noted. Major Areas Inspected:Operations,Maint,Engineering,Plant Support & Safety Assessment/Quality Verification IR 05000219/19930111993-09-10010 September 1993 Insp Rept 50-219/93-11 on 930629-0809.No Violations Noted. Major Areas Inspected:Day Shift & Back Shift Hours of Station Activities IR 05000219/19930191993-09-0909 September 1993 Insp Rept 50-219/93-19 on 930816-20.Violations Noted.Major Areas Inspected:Radiological Environ Monitoring Program & Meteorological Monitoring Program IR 05000219/19930141993-09-0202 September 1993 EP Insp Rept 50-219/93-14 on 930802-05.Concerns Noted. Major Areas Inspected:Epip,Equipment,Instrumentation & Supplies IR 05000219/19930161993-08-27027 August 1993 Insp Rept 50-219/93-16 on 930726-30.Major Areas Inspected: Erosion/Corrosion Insp Program,Per GL 89-08.Program & Program Implementation Generally Good.Staff Responsible for Program Development & Implementation Qualified IR 05000219/19930121993-08-26026 August 1993 Insp Rept 50-219/93-12 on 930706-09.No Violations Noted. Major Areas Inspected:Licensee Progress in Incorporating EQ Component Info Into GMS2 Computer Database IR 05000219/19920221993-03-19019 March 1993 Mobile NDE Lab Insp 50-219/92-22 on 921207-11 & 930111-15. No Violations Noted.Major Areas Inspected:Cs,Css,Sdc,Ms & FW Sys IR 05000219/19920251993-02-10010 February 1993 Insp Rept 50-219/92-25 on 921215-930118.Violations Noted. Major Areas Inspected:Plant Operations,Radiological Control, Maint & Surveillance,Engneering & Technical Support, Emergency Preparedness & Security IR 05000219/19930011993-01-29029 January 1993 Insp Rept 50-219/93-01 on 930104-08.No Radiological Safety Concerns or Violations Noted.Major Areas Inspected:Postings & Other in Plant Radiological Controls,Work in Progress, Housekeeping & Self Reading Dosimeter Use IR 05000219/19920231992-12-24024 December 1992 Insp Rept 50-219/92-23 on 921103-1214.No Violations Noted. Major Areas Inspected:Plant Operations,Security & Safety Assessment/Quality Verification IR 05000219/19910041991-03-0101 March 1991 Partially Withheld Insp Rept 50-219/91-04 on 910204-07.No Violations Noted.Major Areas Inspected:Protected Area Physical Barriers,Isolation Zones & Lighting,Protected Area Access Control of Personnel & Security Training IR 05000219/19900191990-11-16016 November 1990 Insp Rept 50-219/90-19 on 900923-1020.Violations Noted. Areas Inspected:Radiological Protection,Surveillance & Maintenance,Emergency Preparedness,Security,Engineering & Technical Support & Safety Assessment/Quality Verification IR 05000219/19900201990-11-0202 November 1990 Insp Rept 50-219/90-20 on 901022-26.No Violations Noted. Major Areas Inspected:Internal Exposure Control & Review of Procedures for Drywell Occupancy During Fuel Movement IR 05000219/19900161990-10-18018 October 1990 Insp Rept 50-219/90-16 on 900823-0922.Violations Noted.Major Areas Inspected:Observation of Plant Activities,Review of Operational Events,Operation of Turbine Bldg Ventilation Sys & Walkdown of Emergency Diesel Fuel Oil Transfer Sys ML20058F3241990-10-0202 October 1990 Insp Rept 50-219/90-17 on 900918-21.No Violations Noted. Major Areas Inspected:Transportation & Solid Radwaste Programs IR 05000219/19900151990-09-20020 September 1990 Partially Withheld Safeguards Insp Rept 50-219/90-15 on 900820-24 (Ref 10CFR73.21).No Violations Noted.Major Areas Inspected:Support,Security Program Plans,Audits,Protected & Vital Areas Physical Barriers,Power Supply & Testing IR 05000219/19900111990-08-15015 August 1990 Insp Rept 50-219/90-11 on 900610-0711.Noncited Violation Noted.Major Areas Inspected:Observation & Review of Plant Operations,Review of Radiological Controls & Routine Observations of Maint Activities & Surveillance Tests ML20056A6191990-07-19019 July 1990 Insp Rept 50-219/90-09 on 900422-0609.Violations Noted. Major Areas Inspected:Observation & Review of Routine Plant Activities & Operational Events,Site Radiological Controls & Events & Observations of Corrective Maint Activities IR 05000219/19890291990-02-16016 February 1990 Insp Rept 50-219/89-29 on 891203-900106.Major Areas Inspected:Observation & Review of Plant Operational Events, Condenser Vacuum Transient,Unusual Events Due to Low Intake Water Level & Simultaneous Movement of Two Control Rods IR 05000219/19890181989-09-13013 September 1989 Insp Rept 50-219/89-18 on 890724-28.No Violations Noted. Major Areas Inspected:Review of Licensee Actions on Previous NRC Concerns,Atws Rule Implementation,Procurement Control & non-licensed Operators Training IR 05000219/19890201989-09-0707 September 1989 Insp Rept 50-219/89-20 on 890829-30.No Exercise Weaknesses Noted.Major Areas Inspected:Licensee Emergency Preparedness Exercise Conducted on 890829-30 ML20246J6261989-08-18018 August 1989 Insp Rept 50-219/89-16 on 890702-29.Violations Noted.Major Areas Inspected:Plant Operational Events,Control of High Radiation Areas,Evaluation of Plant Operation W/High Canal Water Temps & Security Response to Vital Area Door Problem IR 05000219/19890191989-08-15015 August 1989 Insp Rept 50-219/89-19 on 890802-04.No Violations or Deviations Noted.Major Areas Inspected:Solid Radwaste Sys & Transportation Programs,Including Mgt Controls,Audits,Qa & Implementation of Subj Programs IR 05000219/19890151989-08-0909 August 1989 Insp Rept 50-219/89-15 on 890627-30.No Violations Noted. Major Areas Inspected:Organization & Qualifications of Radiological Controls Personnel in Site Organization IR 05000219/19890141989-08-0303 August 1989 Insp Rept 50-219/89-14 on 890604-0701.No Violations Noted. Major Areas Inspected:Core Spray Booster Pump Trips,Under Voltage Relay Failure,Monthly Surveillance Observations, Emergency Svc Water Pump Operability & Oyster Creek Drawing IR 05000219/19890111989-07-25025 July 1989 Insp Rept 50-219/89-11 on 890606-08.Major Areas Inspected: Emergency Preparedness Insp of full-participation Exercise of Licensee Emergency Plan Conducted on 890607.Exercise Did Not Meet Requirements for Annual Test of Emergency Plan IR 05000219/19890121989-07-21021 July 1989 Insp Rept 50-219/89-12 on 890430-0603.Violations Noted.Major Areas Inspected:Plant Operational Events Including Three Reactor Startups & Licensee Corrective Actions Re Reactor Coolant Pressure Boundary Hangers Being Pinned 1999-03-04
[Table view] Category:NRC-GENERATED
MONTHYEARIR 05000219/19980121999-03-0404 March 1999 Insp Rept 50-219/98-12 During Periods 981214-18,990106-07 & 20-22.No Violations Identified.Major Areas Inspected: Review of Licensee self-assessment of Plant Environ Qualification Program & Corrective Actions for Open Items IR 05000219/19980091998-11-25025 November 1998 Insp Rept 50-219/98-09 on 980914-1025.Violations Noted. Major Areas Inspected:Operations,Engineering,Maintenance & Plant Support IR 05000219/19980081998-10-20020 October 1998 Insp Rept 50-219/98-08 on 980727-0913.No Violations Noted. Major Areas Inspected:Licensee Operations,Engineering,Maint & Plant Support IR 05000219/19980051998-08-26026 August 1998 Insp Rept 50-219/98-05 on 980614-0726.No Violations Noted. Major Areas Inspected:Plant Operations,Maint,Engineering & Plant Support IR 05000219/19980071998-07-0202 July 1998 Insp Rept 50-219/98-07 on 980615-19.No Violations Noted. Major Areas Inspected:Status of Plant motor-operated Valve Program to Determine Acceptability for Closure of NRC Review Under GL 89-10 ML20217F6641998-04-22022 April 1998 Insp Rept 50-219/98-80 on 980223-0313 & 0330-0402.Violations Noted.Major Areas Inspected:Engineering ML20216H1911998-04-15015 April 1998 Insp Rept 50-219/98-04 on 980226-0318.Violations Noted.Major Areas Inspected:Operations,Maint & Plant Support IR 05000219/19970081997-12-0404 December 1997 Insp Rept 50-219/97-08 on 971020-24.No Violations Noted. Major Areas Inspected:Onsite Emergency Plan IR 05000219/19970041997-07-29029 July 1997 Insp Rept 50-219/97-04 on 970526-0706.Violations Noted. Major Areas Inspected:Aspects of Licensee Operations, Engineering,Maint & Plant Support IR 05000219/19970051997-07-17017 July 1997 Insp Rept 50-219/97-05 on 970407-11.No Violations Noted. Major Areas Inspected:Engineering ML20141G9431997-07-0303 July 1997 Insp Rept 50-219/97-03 on 970414-0525.Violations Noted.Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000219/19970021997-05-19019 May 1997 Insp Rept 50-219/97-02 on 970224-0413.Violations Noted. Major Areas Inspected:Operations,Engineering,Maintenance & Plant Support ML20137E9491997-03-21021 March 1997 Insp Rept 50-219/97-01 on 970113-0223.Violations Noted.Major Areas Inspected:Licensee Operations,Engineering,Maint & Plant Support IR 05000219/19960101996-09-27027 September 1996 Insp Rept 50-219/96-10 on 960923-27.No Violations Noted. Major Areas Inspected:Radiological Source Term Assessment, Results of Exposure Reduction Initiatives & Evidence of Station ALARA Program IR 05000219/19960111996-01-0202 January 1996 Insp Rept 50-219/96-11 on 961021-1201.Violations Noted.Major Areas Inspected:Licensee Operations,Engineering,Maint & Plant Support IR 05000219/19930811993-12-22022 December 1993 Insp Rept 50-219/93-81 on 930927-1015.Violations Noted.Major Areas Inspected:Engineering,Maint,Surveillance & Mgt & Corrective Actions IR 05000219/19930261993-11-18018 November 1993 Insp Rept 50-219/93-26 on 931101-05.No Violations Noted. Major Areas Inspected:Mgt Support,Security Program Plans & Audits,Protected & Vital Area Access Control of Personnel & Packages & Vehicles IR 05000219/19930241993-11-18018 November 1993 Insp Rept 50-219/93-24 on 930921-1101.Violations Noted.Major Areas Inspected:Plant Operations,Maint,Engineering,Plant Support,Including Security & Emergency Preparedness & Safety Assessment/Quality Verification ML20058A3791993-11-12012 November 1993 Insp Rept 50-219/93-23 on 931018-20.Onsite Response to Exercise Scenario Was Good.Major Areas inspected:full- Participation Ingestion Pathway Emergency Preparedness Exercise IR 05000219/19930251993-11-0909 November 1993 Insp Rept 50-219/93-25 on 931018-22.No Violations Noted. Major Areas Inspected:Design Mods & Engineering Support IR 05000219/19930181993-10-28028 October 1993 Insp Rept 50-219/93-18 on 930823-1020.No Violations Noted. Major Areas Inspected:Alara,Rirs,Qa Audits,Air & Swipe Sample Counting Facilities & Radiological Controls Organization Professional Staffing ML20059F6251993-10-28028 October 1993 Insp Rept 50-219/93-22 on 930920-24.No Violations Noted. Major Areas Inspected:Addressed Open Items Associated W/Eop & Reviewed Licensee Actions in Response to Violations Associated W/Recirculation Loop Isolation Event IR 05000219/19930201993-10-19019 October 1993 Insp Rept 50-219/93-20 on 930816-930917.No Violations Noted. Major Areas Inspected:Radioactive Liquid & Gaseous Effluent Control Programs Including Mgt Controls & QA Audits IR 05000219/19930211993-10-15015 October 1993 Insp Rept 50-219/93-21 on 930810-0920.No Violations Noted. Major Areas Inspected:Operations,Maint,Engineering,Plant Support & Safety Assessment/Quality Verification IR 05000219/19930111993-09-10010 September 1993 Insp Rept 50-219/93-11 on 930629-0809.No Violations Noted. Major Areas Inspected:Day Shift & Back Shift Hours of Station Activities IR 05000219/19930191993-09-0909 September 1993 Insp Rept 50-219/93-19 on 930816-20.Violations Noted.Major Areas Inspected:Radiological Environ Monitoring Program & Meteorological Monitoring Program IR 05000219/19930141993-09-0202 September 1993 EP Insp Rept 50-219/93-14 on 930802-05.Concerns Noted. Major Areas Inspected:Epip,Equipment,Instrumentation & Supplies IR 05000219/19930161993-08-27027 August 1993 Insp Rept 50-219/93-16 on 930726-30.Major Areas Inspected: Erosion/Corrosion Insp Program,Per GL 89-08.Program & Program Implementation Generally Good.Staff Responsible for Program Development & Implementation Qualified IR 05000219/19930121993-08-26026 August 1993 Insp Rept 50-219/93-12 on 930706-09.No Violations Noted. Major Areas Inspected:Licensee Progress in Incorporating EQ Component Info Into GMS2 Computer Database IR 05000219/19920221993-03-19019 March 1993 Mobile NDE Lab Insp 50-219/92-22 on 921207-11 & 930111-15. No Violations Noted.Major Areas Inspected:Cs,Css,Sdc,Ms & FW Sys IR 05000219/19920251993-02-10010 February 1993 Insp Rept 50-219/92-25 on 921215-930118.Violations Noted. Major Areas Inspected:Plant Operations,Radiological Control, Maint & Surveillance,Engneering & Technical Support, Emergency Preparedness & Security IR 05000219/19930011993-01-29029 January 1993 Insp Rept 50-219/93-01 on 930104-08.No Radiological Safety Concerns or Violations Noted.Major Areas Inspected:Postings & Other in Plant Radiological Controls,Work in Progress, Housekeeping & Self Reading Dosimeter Use IR 05000219/19920231992-12-24024 December 1992 Insp Rept 50-219/92-23 on 921103-1214.No Violations Noted. Major Areas Inspected:Plant Operations,Security & Safety Assessment/Quality Verification IR 05000219/19910041991-03-0101 March 1991 Partially Withheld Insp Rept 50-219/91-04 on 910204-07.No Violations Noted.Major Areas Inspected:Protected Area Physical Barriers,Isolation Zones & Lighting,Protected Area Access Control of Personnel & Security Training IR 05000219/19900191990-11-16016 November 1990 Insp Rept 50-219/90-19 on 900923-1020.Violations Noted. Areas Inspected:Radiological Protection,Surveillance & Maintenance,Emergency Preparedness,Security,Engineering & Technical Support & Safety Assessment/Quality Verification IR 05000219/19900201990-11-0202 November 1990 Insp Rept 50-219/90-20 on 901022-26.No Violations Noted. Major Areas Inspected:Internal Exposure Control & Review of Procedures for Drywell Occupancy During Fuel Movement IR 05000219/19900161990-10-18018 October 1990 Insp Rept 50-219/90-16 on 900823-0922.Violations Noted.Major Areas Inspected:Observation of Plant Activities,Review of Operational Events,Operation of Turbine Bldg Ventilation Sys & Walkdown of Emergency Diesel Fuel Oil Transfer Sys ML20058F3241990-10-0202 October 1990 Insp Rept 50-219/90-17 on 900918-21.No Violations Noted. Major Areas Inspected:Transportation & Solid Radwaste Programs IR 05000219/19900151990-09-20020 September 1990 Partially Withheld Safeguards Insp Rept 50-219/90-15 on 900820-24 (Ref 10CFR73.21).No Violations Noted.Major Areas Inspected:Support,Security Program Plans,Audits,Protected & Vital Areas Physical Barriers,Power Supply & Testing IR 05000219/19900111990-08-15015 August 1990 Insp Rept 50-219/90-11 on 900610-0711.Noncited Violation Noted.Major Areas Inspected:Observation & Review of Plant Operations,Review of Radiological Controls & Routine Observations of Maint Activities & Surveillance Tests ML20056A6191990-07-19019 July 1990 Insp Rept 50-219/90-09 on 900422-0609.Violations Noted. Major Areas Inspected:Observation & Review of Routine Plant Activities & Operational Events,Site Radiological Controls & Events & Observations of Corrective Maint Activities IR 05000219/19890291990-02-16016 February 1990 Insp Rept 50-219/89-29 on 891203-900106.Major Areas Inspected:Observation & Review of Plant Operational Events, Condenser Vacuum Transient,Unusual Events Due to Low Intake Water Level & Simultaneous Movement of Two Control Rods IR 05000219/19890181989-09-13013 September 1989 Insp Rept 50-219/89-18 on 890724-28.No Violations Noted. Major Areas Inspected:Review of Licensee Actions on Previous NRC Concerns,Atws Rule Implementation,Procurement Control & non-licensed Operators Training IR 05000219/19890201989-09-0707 September 1989 Insp Rept 50-219/89-20 on 890829-30.No Exercise Weaknesses Noted.Major Areas Inspected:Licensee Emergency Preparedness Exercise Conducted on 890829-30 ML20246J6261989-08-18018 August 1989 Insp Rept 50-219/89-16 on 890702-29.Violations Noted.Major Areas Inspected:Plant Operational Events,Control of High Radiation Areas,Evaluation of Plant Operation W/High Canal Water Temps & Security Response to Vital Area Door Problem IR 05000219/19890191989-08-15015 August 1989 Insp Rept 50-219/89-19 on 890802-04.No Violations or Deviations Noted.Major Areas Inspected:Solid Radwaste Sys & Transportation Programs,Including Mgt Controls,Audits,Qa & Implementation of Subj Programs IR 05000219/19890151989-08-0909 August 1989 Insp Rept 50-219/89-15 on 890627-30.No Violations Noted. Major Areas Inspected:Organization & Qualifications of Radiological Controls Personnel in Site Organization IR 05000219/19890141989-08-0303 August 1989 Insp Rept 50-219/89-14 on 890604-0701.No Violations Noted. Major Areas Inspected:Core Spray Booster Pump Trips,Under Voltage Relay Failure,Monthly Surveillance Observations, Emergency Svc Water Pump Operability & Oyster Creek Drawing IR 05000219/19890111989-07-25025 July 1989 Insp Rept 50-219/89-11 on 890606-08.Major Areas Inspected: Emergency Preparedness Insp of full-participation Exercise of Licensee Emergency Plan Conducted on 890607.Exercise Did Not Meet Requirements for Annual Test of Emergency Plan IR 05000219/19890121989-07-21021 July 1989 Insp Rept 50-219/89-12 on 890430-0603.Violations Noted.Major Areas Inspected:Plant Operational Events Including Three Reactor Startups & Licensee Corrective Actions Re Reactor Coolant Pressure Boundary Hangers Being Pinned 1999-03-04
[Table view] Category:INSPECTION REPORT
MONTHYEARIR 05000219/19980121999-03-0404 March 1999 Insp Rept 50-219/98-12 During Periods 981214-18,990106-07 & 20-22.No Violations Identified.Major Areas Inspected: Review of Licensee self-assessment of Plant Environ Qualification Program & Corrective Actions for Open Items IR 05000219/19980091998-11-25025 November 1998 Insp Rept 50-219/98-09 on 980914-1025.Violations Noted. Major Areas Inspected:Operations,Engineering,Maintenance & Plant Support IR 05000219/19980081998-10-20020 October 1998 Insp Rept 50-219/98-08 on 980727-0913.No Violations Noted. Major Areas Inspected:Licensee Operations,Engineering,Maint & Plant Support IR 05000219/19980051998-08-26026 August 1998 Insp Rept 50-219/98-05 on 980614-0726.No Violations Noted. Major Areas Inspected:Plant Operations,Maint,Engineering & Plant Support IR 05000219/19980071998-07-0202 July 1998 Insp Rept 50-219/98-07 on 980615-19.No Violations Noted. Major Areas Inspected:Status of Plant motor-operated Valve Program to Determine Acceptability for Closure of NRC Review Under GL 89-10 ML20217F6641998-04-22022 April 1998 Insp Rept 50-219/98-80 on 980223-0313 & 0330-0402.Violations Noted.Major Areas Inspected:Engineering ML20216H1911998-04-15015 April 1998 Insp Rept 50-219/98-04 on 980226-0318.Violations Noted.Major Areas Inspected:Operations,Maint & Plant Support IR 05000219/19970081997-12-0404 December 1997 Insp Rept 50-219/97-08 on 971020-24.No Violations Noted. Major Areas Inspected:Onsite Emergency Plan IR 05000219/19970041997-07-29029 July 1997 Insp Rept 50-219/97-04 on 970526-0706.Violations Noted. Major Areas Inspected:Aspects of Licensee Operations, Engineering,Maint & Plant Support IR 05000219/19970051997-07-17017 July 1997 Insp Rept 50-219/97-05 on 970407-11.No Violations Noted. Major Areas Inspected:Engineering ML20141G9431997-07-0303 July 1997 Insp Rept 50-219/97-03 on 970414-0525.Violations Noted.Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000219/19970021997-05-19019 May 1997 Insp Rept 50-219/97-02 on 970224-0413.Violations Noted. Major Areas Inspected:Operations,Engineering,Maintenance & Plant Support ML20137E9491997-03-21021 March 1997 Insp Rept 50-219/97-01 on 970113-0223.Violations Noted.Major Areas Inspected:Licensee Operations,Engineering,Maint & Plant Support IR 05000219/19960101996-09-27027 September 1996 Insp Rept 50-219/96-10 on 960923-27.No Violations Noted. Major Areas Inspected:Radiological Source Term Assessment, Results of Exposure Reduction Initiatives & Evidence of Station ALARA Program IR 05000219/19960111996-01-0202 January 1996 Insp Rept 50-219/96-11 on 961021-1201.Violations Noted.Major Areas Inspected:Licensee Operations,Engineering,Maint & Plant Support IR 05000219/19930811993-12-22022 December 1993 Insp Rept 50-219/93-81 on 930927-1015.Violations Noted.Major Areas Inspected:Engineering,Maint,Surveillance & Mgt & Corrective Actions IR 05000219/19930261993-11-18018 November 1993 Insp Rept 50-219/93-26 on 931101-05.No Violations Noted. Major Areas Inspected:Mgt Support,Security Program Plans & Audits,Protected & Vital Area Access Control of Personnel & Packages & Vehicles IR 05000219/19930241993-11-18018 November 1993 Insp Rept 50-219/93-24 on 930921-1101.Violations Noted.Major Areas Inspected:Plant Operations,Maint,Engineering,Plant Support,Including Security & Emergency Preparedness & Safety Assessment/Quality Verification ML20058A3791993-11-12012 November 1993 Insp Rept 50-219/93-23 on 931018-20.Onsite Response to Exercise Scenario Was Good.Major Areas inspected:full- Participation Ingestion Pathway Emergency Preparedness Exercise IR 05000219/19930251993-11-0909 November 1993 Insp Rept 50-219/93-25 on 931018-22.No Violations Noted. Major Areas Inspected:Design Mods & Engineering Support IR 05000219/19930181993-10-28028 October 1993 Insp Rept 50-219/93-18 on 930823-1020.No Violations Noted. Major Areas Inspected:Alara,Rirs,Qa Audits,Air & Swipe Sample Counting Facilities & Radiological Controls Organization Professional Staffing ML20059F6251993-10-28028 October 1993 Insp Rept 50-219/93-22 on 930920-24.No Violations Noted. Major Areas Inspected:Addressed Open Items Associated W/Eop & Reviewed Licensee Actions in Response to Violations Associated W/Recirculation Loop Isolation Event IR 05000219/19930201993-10-19019 October 1993 Insp Rept 50-219/93-20 on 930816-930917.No Violations Noted. Major Areas Inspected:Radioactive Liquid & Gaseous Effluent Control Programs Including Mgt Controls & QA Audits IR 05000219/19930211993-10-15015 October 1993 Insp Rept 50-219/93-21 on 930810-0920.No Violations Noted. Major Areas Inspected:Operations,Maint,Engineering,Plant Support & Safety Assessment/Quality Verification IR 05000219/19930111993-09-10010 September 1993 Insp Rept 50-219/93-11 on 930629-0809.No Violations Noted. Major Areas Inspected:Day Shift & Back Shift Hours of Station Activities IR 05000219/19930191993-09-0909 September 1993 Insp Rept 50-219/93-19 on 930816-20.Violations Noted.Major Areas Inspected:Radiological Environ Monitoring Program & Meteorological Monitoring Program IR 05000219/19930141993-09-0202 September 1993 EP Insp Rept 50-219/93-14 on 930802-05.Concerns Noted. Major Areas Inspected:Epip,Equipment,Instrumentation & Supplies IR 05000219/19930161993-08-27027 August 1993 Insp Rept 50-219/93-16 on 930726-30.Major Areas Inspected: Erosion/Corrosion Insp Program,Per GL 89-08.Program & Program Implementation Generally Good.Staff Responsible for Program Development & Implementation Qualified IR 05000219/19930121993-08-26026 August 1993 Insp Rept 50-219/93-12 on 930706-09.No Violations Noted. Major Areas Inspected:Licensee Progress in Incorporating EQ Component Info Into GMS2 Computer Database IR 05000219/19920221993-03-19019 March 1993 Mobile NDE Lab Insp 50-219/92-22 on 921207-11 & 930111-15. No Violations Noted.Major Areas Inspected:Cs,Css,Sdc,Ms & FW Sys IR 05000219/19920251993-02-10010 February 1993 Insp Rept 50-219/92-25 on 921215-930118.Violations Noted. Major Areas Inspected:Plant Operations,Radiological Control, Maint & Surveillance,Engneering & Technical Support, Emergency Preparedness & Security IR 05000219/19930011993-01-29029 January 1993 Insp Rept 50-219/93-01 on 930104-08.No Radiological Safety Concerns or Violations Noted.Major Areas Inspected:Postings & Other in Plant Radiological Controls,Work in Progress, Housekeeping & Self Reading Dosimeter Use IR 05000219/19920231992-12-24024 December 1992 Insp Rept 50-219/92-23 on 921103-1214.No Violations Noted. Major Areas Inspected:Plant Operations,Security & Safety Assessment/Quality Verification IR 05000219/19910041991-03-0101 March 1991 Partially Withheld Insp Rept 50-219/91-04 on 910204-07.No Violations Noted.Major Areas Inspected:Protected Area Physical Barriers,Isolation Zones & Lighting,Protected Area Access Control of Personnel & Security Training IR 05000219/19900191990-11-16016 November 1990 Insp Rept 50-219/90-19 on 900923-1020.Violations Noted. Areas Inspected:Radiological Protection,Surveillance & Maintenance,Emergency Preparedness,Security,Engineering & Technical Support & Safety Assessment/Quality Verification IR 05000219/19900201990-11-0202 November 1990 Insp Rept 50-219/90-20 on 901022-26.No Violations Noted. Major Areas Inspected:Internal Exposure Control & Review of Procedures for Drywell Occupancy During Fuel Movement IR 05000219/19900161990-10-18018 October 1990 Insp Rept 50-219/90-16 on 900823-0922.Violations Noted.Major Areas Inspected:Observation of Plant Activities,Review of Operational Events,Operation of Turbine Bldg Ventilation Sys & Walkdown of Emergency Diesel Fuel Oil Transfer Sys ML20058F3241990-10-0202 October 1990 Insp Rept 50-219/90-17 on 900918-21.No Violations Noted. Major Areas Inspected:Transportation & Solid Radwaste Programs IR 05000219/19900151990-09-20020 September 1990 Partially Withheld Safeguards Insp Rept 50-219/90-15 on 900820-24 (Ref 10CFR73.21).No Violations Noted.Major Areas Inspected:Support,Security Program Plans,Audits,Protected & Vital Areas Physical Barriers,Power Supply & Testing IR 05000219/19900111990-08-15015 August 1990 Insp Rept 50-219/90-11 on 900610-0711.Noncited Violation Noted.Major Areas Inspected:Observation & Review of Plant Operations,Review of Radiological Controls & Routine Observations of Maint Activities & Surveillance Tests ML20056A6191990-07-19019 July 1990 Insp Rept 50-219/90-09 on 900422-0609.Violations Noted. Major Areas Inspected:Observation & Review of Routine Plant Activities & Operational Events,Site Radiological Controls & Events & Observations of Corrective Maint Activities IR 05000219/19890291990-02-16016 February 1990 Insp Rept 50-219/89-29 on 891203-900106.Major Areas Inspected:Observation & Review of Plant Operational Events, Condenser Vacuum Transient,Unusual Events Due to Low Intake Water Level & Simultaneous Movement of Two Control Rods IR 05000219/19890181989-09-13013 September 1989 Insp Rept 50-219/89-18 on 890724-28.No Violations Noted. Major Areas Inspected:Review of Licensee Actions on Previous NRC Concerns,Atws Rule Implementation,Procurement Control & non-licensed Operators Training IR 05000219/19890201989-09-0707 September 1989 Insp Rept 50-219/89-20 on 890829-30.No Exercise Weaknesses Noted.Major Areas Inspected:Licensee Emergency Preparedness Exercise Conducted on 890829-30 ML20246J6261989-08-18018 August 1989 Insp Rept 50-219/89-16 on 890702-29.Violations Noted.Major Areas Inspected:Plant Operational Events,Control of High Radiation Areas,Evaluation of Plant Operation W/High Canal Water Temps & Security Response to Vital Area Door Problem IR 05000219/19890191989-08-15015 August 1989 Insp Rept 50-219/89-19 on 890802-04.No Violations or Deviations Noted.Major Areas Inspected:Solid Radwaste Sys & Transportation Programs,Including Mgt Controls,Audits,Qa & Implementation of Subj Programs IR 05000219/19890151989-08-0909 August 1989 Insp Rept 50-219/89-15 on 890627-30.No Violations Noted. Major Areas Inspected:Organization & Qualifications of Radiological Controls Personnel in Site Organization IR 05000219/19890141989-08-0303 August 1989 Insp Rept 50-219/89-14 on 890604-0701.No Violations Noted. Major Areas Inspected:Core Spray Booster Pump Trips,Under Voltage Relay Failure,Monthly Surveillance Observations, Emergency Svc Water Pump Operability & Oyster Creek Drawing IR 05000219/19890111989-07-25025 July 1989 Insp Rept 50-219/89-11 on 890606-08.Major Areas Inspected: Emergency Preparedness Insp of full-participation Exercise of Licensee Emergency Plan Conducted on 890607.Exercise Did Not Meet Requirements for Annual Test of Emergency Plan IR 05000219/19890121989-07-21021 July 1989 Insp Rept 50-219/89-12 on 890430-0603.Violations Noted.Major Areas Inspected:Plant Operational Events Including Three Reactor Startups & Licensee Corrective Actions Re Reactor Coolant Pressure Boundary Hangers Being Pinned 1999-03-04
[Table view] Category:UTILITY
MONTHYEARIR 05000219/19900201990-11-0202 November 1990 Insp Rept 50-219/90-20 on 901022-26.No Violations Noted. Major Areas Inspected:Internal Exposure Control & Review of Procedures for Drywell Occupancy During Fuel Movement IR 05000219/19900161990-10-18018 October 1990 Insp Rept 50-219/90-16 on 900823-0922.Violations Noted.Major Areas Inspected:Observation of Plant Activities,Review of Operational Events,Operation of Turbine Bldg Ventilation Sys & Walkdown of Emergency Diesel Fuel Oil Transfer Sys IR 05000219/19900111990-08-15015 August 1990 Insp Rept 50-219/90-11 on 900610-0711.Noncited Violation Noted.Major Areas Inspected:Observation & Review of Plant Operations,Review of Radiological Controls & Routine Observations of Maint Activities & Surveillance Tests ML20056A6191990-07-19019 July 1990 Insp Rept 50-219/90-09 on 900422-0609.Violations Noted. Major Areas Inspected:Observation & Review of Routine Plant Activities & Operational Events,Site Radiological Controls & Events & Observations of Corrective Maint Activities IR 05000219/19890291990-02-16016 February 1990 Insp Rept 50-219/89-29 on 891203-900106.Major Areas Inspected:Observation & Review of Plant Operational Events, Condenser Vacuum Transient,Unusual Events Due to Low Intake Water Level & Simultaneous Movement of Two Control Rods IR 05000219/19890181989-09-13013 September 1989 Insp Rept 50-219/89-18 on 890724-28.No Violations Noted. Major Areas Inspected:Review of Licensee Actions on Previous NRC Concerns,Atws Rule Implementation,Procurement Control & non-licensed Operators Training IR 05000219/19890201989-09-0707 September 1989 Insp Rept 50-219/89-20 on 890829-30.No Exercise Weaknesses Noted.Major Areas Inspected:Licensee Emergency Preparedness Exercise Conducted on 890829-30 ML20246J6261989-08-18018 August 1989 Insp Rept 50-219/89-16 on 890702-29.Violations Noted.Major Areas Inspected:Plant Operational Events,Control of High Radiation Areas,Evaluation of Plant Operation W/High Canal Water Temps & Security Response to Vital Area Door Problem IR 05000219/19890191989-08-15015 August 1989 Insp Rept 50-219/89-19 on 890802-04.No Violations or Deviations Noted.Major Areas Inspected:Solid Radwaste Sys & Transportation Programs,Including Mgt Controls,Audits,Qa & Implementation of Subj Programs IR 05000219/19890151989-08-0909 August 1989 Insp Rept 50-219/89-15 on 890627-30.No Violations Noted. Major Areas Inspected:Organization & Qualifications of Radiological Controls Personnel in Site Organization IR 05000219/19890141989-08-0303 August 1989 Insp Rept 50-219/89-14 on 890604-0701.No Violations Noted. Major Areas Inspected:Core Spray Booster Pump Trips,Under Voltage Relay Failure,Monthly Surveillance Observations, Emergency Svc Water Pump Operability & Oyster Creek Drawing IR 05000219/19890111989-07-25025 July 1989 Insp Rept 50-219/89-11 on 890606-08.Major Areas Inspected: Emergency Preparedness Insp of full-participation Exercise of Licensee Emergency Plan Conducted on 890607.Exercise Did Not Meet Requirements for Annual Test of Emergency Plan IR 05000219/19890131989-06-15015 June 1989 Insp Rept 50-219/89-13 on 890522-26.No Violations Noted. Major Areas Inspected:Licensee Liquid & Gaseous Radioactive Effluent Control Programs & Radiological Environ Monitoring Program IR 05000219/19890101989-05-24024 May 1989 Insp Rept 50-219/89-10 on 890402-29.No Violations Noted. Major Areas Inspected:Action of Plant Deficiencies Discovered During Startup,Instrument Air Sys Problems, Surveillance Testing & Control Rod Scram Timing Testing IR 05000219/19890071989-05-17017 May 1989 Insp Rept 50-219/89-07 on 890226-0401.No Violations Noted. Major Areas Inspected:Activities in Progress at Completion of Outage,In Preparation for Startup & Plant Startup Activities IR 05000219/19890061989-05-10010 May 1989 Insp Repts 50-219/89-06 on 890217-24.Violations Noted.Major Areas Inspected:Review of Preliminary Safety Concern Process Including Concerns Involving Standby Gas Treatment Sys, Automatic Depressurization Sys & Containment Spray Sys IR 05000219/19890081989-04-28028 April 1989 Insp Rept 50-219/89-08 on 890313-17.No Violations Noted. Major Areas Inspected:Implementation of Relief & Safety Valve Position Indication Sections of NUREG-0737 & Procedures Re Handling of Emergency Diesel Generator Fuel IR 05000219/19890041989-04-14014 April 1989 Insp Rept 50-219/89-04 on 890115-0225.Violations Noted.Major Areas Inspected:Activities in Progress,Including Air Accumulator Testing,Environ Qualification,Reactor Pressure Vessel Testing,Operations & Physical Security IR 05000219/19882031989-03-13013 March 1989 SSOMI Rept 50-219/88-203 on 881128-1216.Major Areas Inspected:Adequacy of Licensee Mgt & Control of Mods Performed During Major Plant Outage & to Identify Strengths & Weaknesses in Licensee Mod Programs ML20236A5571989-03-0303 March 1989 Safety Insp Rept 50-219/89-03 on 890117-20.No Violations, Deviations or Unresolved Items Noted.Major Areas Inspected: Licensee Emergency Preparedness Program ML20245H9681989-02-21021 February 1989 Insp Rept 50-219/88-38 on 881204-890114.No Violations Noted. Unresolved Items Observed.Major Areas Inspected:Maint & Surveillance Activities,Radiation Control & Physical Security,Including Security Events Re Unauthorized Entry ML20235H2681989-02-0303 February 1989 Insp Rept 50-219/89-02 on 890117-20.Violations Noted.Major Areas Inspected:Licensee Activity Re Info Notice 86-053 (Raychem Splices) IR 05000219/19880311988-11-29029 November 1988 Insp Rept 50-219/88-31 on 881003-07,20 & 1031-1104. Violations Noted.Major Areas Inspected:Status of Outstanding Items,Radiological Controls Re 12R Refueling Outage & Review of Circumstances Concerning Radioactive Spill Incident IR 05000219/19880321988-11-28028 November 1988 Insp Rept 50-219/88-32 on 881017-21.Violation Noted.Major Areas Inspected:Mgt Support,Security Program Plans,Audits, Protected & Vital Area Physical Barriers,Access Control, Detection & Assessment Aids,Testing & Maint & Power Supply IR 05000219/19880281988-11-15015 November 1988 Insp Rept 50-219/88-28 on 880911-1004 & 1014-29.Apparent Violation Noted.Major Areas Inspected:Activities in Progress,Including Plant Operations,Radiation Control, Physical Security,Maint & Forced Shutdown Activities ML20206D0131988-11-0101 November 1988 Environ Qualification Enforcement Conference Rept 50-219/85-39 on 881020.Major Areas Discussed:Significance of Concerns Re Environ Qualification of PVC Tape Splices & Limit Switches Associated W/Msivs.Related Info Encl ML20205P6101988-10-31031 October 1988 Insp Rept 50-219/88-30 on 880929.Notice of Violation Withdrawn.Major Areas Inspected:Emergency Preparedness Activities Re Licensee Response to Notice of Violation & Inspector Followup Items IR 05000219/19880801988-10-28028 October 1988 Augmented Insp Team Rept 50-219/88-80 on 881005-13.Major Areas Inspected:Circumstances Surrounding Steaming Phenomenon on Both Isolation Condensers in Late Aug & Sept 1988 & Electrical Fault on Diesel Generator 2 on 881002 IR 05000219/19880291988-10-22022 October 1988 Insp Rept 50-219/88-29 on 880914-15.App R Violation Re High & Low Pressure Interface During Design Basis Fire Which Could Cause Loss of Reactor Coolant Noted.Major Areas Inspected:Interviews W/Personnel & Inspector Observations ML20205J7301988-10-11011 October 1988 Insp Rept 50-219/88-26 on 880909 & 0912-15.No Violations Noted.Major Areas Inspected:Licensee Inservice Insp Program to Ascertain That Program Complies W/Applicable ASME Code & Regulatory Requirements & Response to Generic Ltr 88-01 ML20207N2331988-10-0404 October 1988 Insp Rept 50-219/88-25 on 880829-0902.No Violations Noted. Major Areas Inspected:Licensee Actions in Response to NRC Bulletins 79-02 & 79-14,Deficiencies Noted in Some Pipe Support & Pipe Support Base Plates IR 05000219/19880231988-09-27027 September 1988 Insp Rept 50-219/88-23 on 880731-0910.Violation Noted. Major Areas Inspected:Plant Operations & Startup,Radiation Control,Physical Security,Maint & Forced Shutdown Work Activities & Isolation Condenser Sys Operability IR 05000219/19880241988-09-0909 September 1988 Insp Rept 50-219/88-24 on 880715 & 18-0812.No Violation Noted.Unresolved Item Identified.Major Areas Inspected: Failure of MSIV NS03A Stem,Including Sequence of Events, Maint & Surveillance Test History & Stem Matl ML20151Y3081988-08-15015 August 1988 Insp Rept 50-219/88-15 on 880523-0726.Violations Noted. Major Areas Inspected:Licensee Action in Response to Mark I Containment Mod Requirements of NUREG-0661,review of Design Analyses & Plant Unigue Analysis Rept IR 05000219/19880221988-08-12012 August 1988 Insp Rept 50-219/88-22 on 880718-22.No Violations Noted. Major Areas Inspected:Gaseous & Liquid Radioactive Effluent Control Programs,Licensee Action on Previous Insp Findings, Effluents,Instrumentation,Audits & Air Cleaning Sys IR 05000219/19880171988-07-26026 July 1988 Insp Rept 50-219/88-17 on 880613-17.No Violations Noted. Major Areas Inspected:Previously Identified Findings,Spds & Planned Mods to Institute Corrective Measures to Satisfy ATWS IR 05000219/19880181988-07-11011 July 1988 Mgt Meeting Rept 50-219/88-18 on 880609.Major Areas Discussed:Status of Licensee Action/Plans & Schedules for Work Per IE Bulletins 79-02 & 79-14 IR 05000219/19880121988-07-0808 July 1988 Insp Rept 50-219/88-12 on 880425-29.No Violations Noted. Major Areas Inspected:Review of Licensee Program Implementation of 10CFR21 Regulation & Review of Station Procurement Program IR 05000219/19880051988-06-30030 June 1988 Insp Rept 50-219/88-05 on 880511-12.No Violations Noted. Major Areas Inspected:Emergency Exercise Conducted on 880511-12 IR 05000219/19880141988-06-27027 June 1988 Insp Rept 50-219/88-14 on 880516-20.Violation Noted.Major Areas Inspected:Selected Areas of Fire Protection & Electric Power Sys,Including Reviews of Administrative Control, Surveillance & Fire Brigade Procedures IR 05000219/19880131988-06-14014 June 1988 Insp Rept 50-219/88-13 on 880424-0521.One Violation Noted. Major Areas Inspected:Plant Operations,Physical Security, Radiation Control,Housekeeping,Fire Protection & Emergency Preparedness & Annual Emergency Exercise Participation IR 05000219/19880091988-05-26026 May 1988 Insp Rept 50-219/88-09 on 880320-0423.No Violations Noted. Major Areas Inspected:Plant Operations,Radiation Control, Physical Security,Surveillance,Maint & Environ Qualification Files for Reactor Vessel Pressure Switches IR 05000219/19880111988-05-11011 May 1988 Safety Insp Rept 50-219/88-11 on 880411-15.Violations Noted. Major Areas Inspected:Status of Items Identified During 1987 Integrated Performance Assessment Team Insp & Status of Measures to Control Drywell Access IR 05000219/19880041988-05-0606 May 1988 Insp Rept 50-219/88-04 on 880207-0319.Violations Noted.Major Areas Inspected:Activities in Progress,Including Plant Operation,Physical Security,Radiation Control,Housekeeping, Fire Protection & Emergency Preparedness ML20153D8181988-04-29029 April 1988 Insp Rept 50-219/88-06 on 880222-26.Violation Noted.Major Areas Inspected:Emergency Implementing Procedures & Plans, Emergency Facilities,Equipment,Instrumentation & Supplies & Application of IE Info Notices 83-28 & 84-80 IR 05000219/19880081988-04-29029 April 1988 Mgt Meeting Rept 50-219/88-08 on 880308.Major Areas Discussed:Licensee Activities Re NRC Bulletins 79-02 & 79-14.Licensee Presentation Encl IR 05000219/19870421988-03-14014 March 1988 Insp Rept 50-219/87-42 on 871220-880206.No Violations Noted. Major Areas Inspected:Activities in Progress,Including Operations,Radiation Control,Physical Security,Surveillance & Maint IR 05000219/19880021988-02-29029 February 1988 Insp Rept 50-219/88-02 on 880125-29.Violations Noted.Major Areas Inspected:Safety Implications of Freezing Conditions Identified in Reactor Bldg on 880106 & Effectivness of Licensee Corrective Measures IR 05000219/19880011988-02-19019 February 1988 Insp Rept 50-219/88-01 on 880104-08.No Violations or Deviations Noted.Major Areas Inspected:Licensee Actions on Previously Identified NRC Concerns,Util Offsite Review Committee & Organization & Administration & QA Audits IR 05000219/19870401988-01-21021 January 1988 Physical Security Insp Rept 50-219/87-40 on 871106.No Violations Noted.Major Areas Inspected:Three Allegations Re Deficiencies in Security Program.Allegations Were Not Substantiated 1990-08-15
[Table view] Category:TEXT-INSPECTION & AUDIT & I&E CIRCULARS
MONTHYEARPNO-I-99-043, on 990916,Hurricane Floyd Was Approaching Ccnpp,Sgs,Hcgs & Ocnpp.Hurricane Was Centered at Latitude 36.0 North & Longitude 76.6 West & Moving north-northeast at Approx 25 Mph.Plants Remain at Power1999-09-16016 September 1999 PNO-I-99-043:on 990916,Hurricane Floyd Was Approaching Ccnpp,Sgs,Hcgs & Ocnpp.Hurricane Was Centered at Latitude 36.0 North & Longitude 76.6 West & Moving north-northeast at Approx 25 Mph.Plants Remain at Power IR 05000219/19980121999-03-0404 March 1999 Insp Rept 50-219/98-12 During Periods 981214-18,990106-07 & 20-22.No Violations Identified.Major Areas Inspected: Review of Licensee self-assessment of Plant Environ Qualification Program & Corrective Actions for Open Items IR 05000219/19980091998-11-25025 November 1998 Insp Rept 50-219/98-09 on 980914-1025.Violations Noted. Major Areas Inspected:Operations,Engineering,Maintenance & Plant Support ML20196C6071998-11-25025 November 1998 Notice of Violation from Insp on 980914-1025.Violation Noted:On 981014,security Force Vehicle Escort Left Non licensee-designated Vehicle Unattended in Protected Area & Failed to Ensure That Vehicle Ignition Locked & Key Removed IR 05000219/19980081998-10-20020 October 1998 Insp Rept 50-219/98-08 on 980727-0913.No Violations Noted. Major Areas Inspected:Licensee Operations,Engineering,Maint & Plant Support IR 05000219/19980051998-08-26026 August 1998 Insp Rept 50-219/98-05 on 980614-0726.No Violations Noted. Major Areas Inspected:Plant Operations,Maint,Engineering & Plant Support IR 05000219/19980991998-07-17017 July 1998 SALP Rept 50-219/98-99 for 961201-980613 IR 05000219/19980071998-07-0202 July 1998 Insp Rept 50-219/98-07 on 980615-19.No Violations Noted. Major Areas Inspected:Status of Plant motor-operated Valve Program to Determine Acceptability for Closure of NRC Review Under GL 89-10 ML20249B3661998-06-15015 June 1998 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $55,000.Violation Noted:Prior to 980304, Licensee Failed to Establish Adequate Design Control Measures to Verify Adequacy of Design Voltage ML20237E4491998-06-10010 June 1998 EN-98-047:on 980615,notice of Proposed Imposition of Civil Penalty in Amount of $55,000 Issued to Licensee.Action Based on Severity Level III Problem Involving Inoperability of Three of Five Automatic Depressurization Valves ML20217F6641998-04-22022 April 1998 Insp Rept 50-219/98-80 on 980223-0313 & 0330-0402.Violations Noted.Major Areas Inspected:Engineering ML20217F6491998-04-22022 April 1998 Notice of Violation from Insp on 980223-0313 & 0330-0402. Violations Noted:On 980226,seismic Deficiency W/Containment Spray Heat Exchanger,That Had Been Identified in Late 1996 by Licensee,Had Not Been Adequately Corrected ML20216H1911998-04-15015 April 1998 Insp Rept 50-219/98-04 on 980226-0318.Violations Noted.Major Areas Inspected:Operations,Maint & Plant Support ML20216H1701998-04-15015 April 1998 Notice of Violation from Insp on 980226-0318.Violations Noted:Since Initial Plant Operation,Operators Implemented Procedure 307,isolation Condenser Sys,Permitting Fill & Make Up to Isolation Condensers During Normal Plant Operations ML20216J0181998-04-14014 April 1998 Notice of Violation from Insp on 971229-980208.Violation Noted:Written SE Was Not Performed to Provide Bases for Determination That Change in Facility as Described in SAR Did Not Involve USQ IR 05000219/19970081997-12-0404 December 1997 Insp Rept 50-219/97-08 on 971020-24.No Violations Noted. Major Areas Inspected:Onsite Emergency Plan ML20199G7881997-11-17017 November 1997 Notice of Violation from Insp on 970707-970824.Violation Noted:In Oct 1993,vendor Specification for Emergency Svc Water Pump Bowl Assemblies Was Changed from Cast Iron to Stainless Steel PNO-I-97-045, on 970801,electricians Restoring One Set of Main Generator Exciter Brushes,Following Routine Surveillance,When One of Brushes Sparked Excessively & Disintegrated.Electricians Exited Area & Notified CR1997-08-0404 August 1997 PNO-I-97-045:on 970801,electricians Restoring One Set of Main Generator Exciter Brushes,Following Routine Surveillance,When One of Brushes Sparked Excessively & Disintegrated.Electricians Exited Area & Notified CR IR 05000219/19970041997-07-29029 July 1997 Insp Rept 50-219/97-04 on 970526-0706.Violations Noted. Major Areas Inspected:Aspects of Licensee Operations, Engineering,Maint & Plant Support IR 05000219/19970051997-07-17017 July 1997 Insp Rept 50-219/97-05 on 970407-11.No Violations Noted. Major Areas Inspected:Engineering ML20141G9431997-07-0303 July 1997 Insp Rept 50-219/97-03 on 970414-0525.Violations Noted.Major Areas Inspected:Operations,Maint,Engineering & Plant Support ML20141G9401997-07-0303 July 1997 Notice of Violation from Insp on 970414-0525.Violation Noted:On 970423,CROs Placed a & B Loops of Shutdown Cooling Sys in Svc W/O Placing Suction Pressure Interlocks in Svc for a & B Pumps by Opening Ps Isolation Valves IR 05000219/19970021997-05-19019 May 1997 Insp Rept 50-219/97-02 on 970224-0413.Violations Noted. Major Areas Inspected:Operations,Engineering,Maintenance & Plant Support ML20141J5221997-05-19019 May 1997 Notice of Violation from Insp on 970224-0413.Violation Noted:Permanent Change,Dec 95,made to Facility,As Described in SAR Involving Removal of Isolation Condenser Radiation Monitors W/O Considering All Relevant Portions of SAR PNO-I-97-024, on 970422,Oyster Creek Nuclear Generating Station Commenced Controlled Shutdown of Unit Due to Equipment Problems.Unit Expected to Be Shut Down for Six Days for Correction of Diaphram Problem1997-04-23023 April 1997 PNO-I-97-024:on 970422,Oyster Creek Nuclear Generating Station Commenced Controlled Shutdown of Unit Due to Equipment Problems.Unit Expected to Be Shut Down for Six Days for Correction of Diaphram Problem PNO-I-97-022, on 970410,GPU,Inc Announced,Addition to Continued Operation of Oyster Creek & Also Exploring Options of Sale.Util Will Begin Next Wk to Develop Plans to Support Sale of Plant,Decommissioning & Personnel Retention1997-04-10010 April 1997 PNO-I-97-022:on 970410,GPU,Inc Announced,Addition to Continued Operation of Oyster Creek & Also Exploring Options of Sale.Util Will Begin Next Wk to Develop Plans to Support Sale of Plant,Decommissioning & Personnel Retention ML20137E9411997-03-21021 March 1997 Notice of Violation from Insp on 970113-0223.Violation Noted:Procedure 108.7, Lockout/Tagout Procedure, Rev 4, Did Not Include Appropriate Quantitative or Qualitative Acceptance Criteria ML20137E9491997-03-21021 March 1997 Insp Rept 50-219/97-01 on 970113-0223.Violations Noted.Major Areas Inspected:Licensee Operations,Engineering,Maint & Plant Support IR 05000219/19960991997-01-0909 January 1997 SALP Rept 50-219/96-99 for Oyster Creek Nuclear Generating Station for 950625-961130 ML20133D6781997-01-0202 January 1997 Notice of Violation from Insp on 961021-1201.Violation Noted:Written Safety Evaluation Was Not Performed to Provide Bases for Determination That Change to Station Procedure 336.3 Did Not Involve Unreviewed Safety Question PNO-I-96-078, on 961025,licensee Manually Scrammed Reactor Due to Turbine Runback,Resulted from Problem in Stator Cooling Sys.Resident Will Continue to Follow Event1996-10-29029 October 1996 PNO-I-96-078:on 961025,licensee Manually Scrammed Reactor Due to Turbine Runback,Resulted from Problem in Stator Cooling Sys.Resident Will Continue to Follow Event IR 05000219/19960101996-09-27027 September 1996 Insp Rept 50-219/96-10 on 960923-27.No Violations Noted. Major Areas Inspected:Radiological Source Term Assessment, Results of Exposure Reduction Initiatives & Evidence of Station ALARA Program IR 05000219/19960111996-01-0202 January 1996 Insp Rept 50-219/96-11 on 961021-1201.Violations Noted.Major Areas Inspected:Licensee Operations,Engineering,Maint & Plant Support IR 05000219/19920991994-01-26026 January 1994 SALP Rept 50-219/92-99 for Period 920719-931211 ML20059B6331993-12-23023 December 1993 Notice of Violation from Insp on 930927-1015.Violation Noted:All NRC Violations & Ten Licensee Event Repts Issued in 1992 & 1993 Did Not Receive Required Independent Safety Reviews IR 05000219/19930811993-12-22022 December 1993 Insp Rept 50-219/93-81 on 930927-1015.Violations Noted.Major Areas Inspected:Engineering,Maint,Surveillance & Mgt & Corrective Actions IR 05000219/19930261993-11-18018 November 1993 Insp Rept 50-219/93-26 on 931101-05.No Violations Noted. Major Areas Inspected:Mgt Support,Security Program Plans & Audits,Protected & Vital Area Access Control of Personnel & Packages & Vehicles IR 05000219/19930241993-11-18018 November 1993 Insp Rept 50-219/93-24 on 930921-1101.Violations Noted.Major Areas Inspected:Plant Operations,Maint,Engineering,Plant Support,Including Security & Emergency Preparedness & Safety Assessment/Quality Verification ML20058A3791993-11-12012 November 1993 Insp Rept 50-219/93-23 on 931018-20.Onsite Response to Exercise Scenario Was Good.Major Areas inspected:full- Participation Ingestion Pathway Emergency Preparedness Exercise IR 05000219/19930251993-11-0909 November 1993 Insp Rept 50-219/93-25 on 931018-22.No Violations Noted. Major Areas Inspected:Design Mods & Engineering Support ML20059M3211993-11-0909 November 1993 EN-93-081A:on 930812,notice of Proposed Imposition of Civil Penalty in Amount of $75,000 Issued to Licensee.Action Based on Five Radiological Controls Violations ML20059F6251993-10-28028 October 1993 Insp Rept 50-219/93-22 on 930920-24.No Violations Noted. Major Areas Inspected:Addressed Open Items Associated W/Eop & Reviewed Licensee Actions in Response to Violations Associated W/Recirculation Loop Isolation Event IR 05000219/19930181993-10-28028 October 1993 Insp Rept 50-219/93-18 on 930823-1020.No Violations Noted. Major Areas Inspected:Alara,Rirs,Qa Audits,Air & Swipe Sample Counting Facilities & Radiological Controls Organization Professional Staffing IR 05000219/19930201993-10-19019 October 1993 Insp Rept 50-219/93-20 on 930816-930917.No Violations Noted. Major Areas Inspected:Radioactive Liquid & Gaseous Effluent Control Programs Including Mgt Controls & QA Audits ML20059A2201993-10-15015 October 1993 Notice of Violation from Insp on 920719-0825.Violation Noted:Licensee Determined That Records Required to Be Maintained by Commission Regulations or License Conditions Not Complete & Accurate in All Matl Respects IR 05000219/19930211993-10-15015 October 1993 Insp Rept 50-219/93-21 on 930810-0920.No Violations Noted. Major Areas Inspected:Operations,Maint,Engineering,Plant Support & Safety Assessment/Quality Verification IR 05000219/19930171993-09-14014 September 1993 Exam Rept 50-219/93-17OL on 930810-12.Exam Results:All 16 Licensed Operators Passed All Portions of Exam That Was Administered & All Three Crews Performed Satisfactorily in Simulator ML20149D5021993-09-13013 September 1993 Notice of Violation from Insp on 930629-0809.Violation Noted:On 930709,NRC Identified Condition Adverse to Quality That Had Existed Since 920709 IR 05000219/19930111993-09-10010 September 1993 Insp Rept 50-219/93-11 on 930629-0809.No Violations Noted. Major Areas Inspected:Day Shift & Back Shift Hours of Station Activities ML20149D7051993-09-10010 September 1993 Notice of Violation from Insp on 930816-20.Violation Noted: as of 930820,appropriate Measures Were Not Established to Assure Adequate Quality Was Suitably Included in Documents for Procurement of Svcs 1999-09-16
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t U. S. NUCLEAR REGULATORY COMMISSION j REGION I Report N /86-34
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Docket N License N DRP-16 ~ Priority --
Category C
, Licensee: GPU Nuclear Corporation 1 Upper Pond Road Parsip'pany, New Jersey 07054 Facility Name: Oyster Creek Nuclear Generating Station Inspection At: Forked River, New Jersey Inspection Conducted: October 6 - November 16, 1986 i Participating Inspectors: W. H. Bateman J. F. Wechselberger W. H. Baunack P. C. Wen A. E. Finkel Approved by: [CI /MNI/I R. Conte, Chief, Reactor Projects Section IA .
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Inspection Summary:
Routine inspections were conducted by the resident and Region based inspectors (190 hours0.0022 days <br />0.0528 hours <br />3.141534e-4 weeks <br />7.2295e-5 months <br />) of activities in progress including outage management, modifications, radiation control, security, housekeeping, and system pressure testing. The inspectors also made tours of the plant, followed up various events, reviewed l the completion status of Bulletin 80-08, investigated the recirculation system l pump trip system, and further investigated the cause of failed fue Results:
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No violations were identifie Inspection of the cause of failed fuel will be
- completed in a subsequent inspection. The recirculation pump trip inspection,
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a Region I initiative, was completed. The 11R outage continued beyond its originally planned 6-month duration with restart anticipated in late November 198 PDR ADOCK 05000219 .
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DETAILS
, Investigation Into Cycle 10 Fuel Failures 1.1 Cycle 10 Fuel Failure Meeting On October 9, 1986 a meeting was held with the licensee to discuss the causes of the fuel failures and the licensee's corrective action The results of this meeting are summarized belo During the current 11R refueling outage, the licensee identified 47 failed fuel assemblies out of the 536 fuel assemblies sipped. All failed fuel assemblies were Exxon type VB fuel: 1 failed assembly was loaded at the beginning of Cycle 10 (80C-10), 34 failed assemblies were loaded at 80C-9, and 12 failed assemblies were loaded at BOC- Based on the available plant operating data, the licensee attributed the cause of the majority of these fuel failures to be a Pellet-Clad-Interaction (PCI) which caused cracks in the clad and allowed leakage of fission products into the reactor coolant syste The Cycle 10 operation was from November 1984 through April 198 In January 1985, a large offgas activity increase (from 45,000 micro ci/sec to 92,000 micro ci/sec) was noted. A review of the failed fuel locations, the control rod manipulations (A-1 Group 14 and A-1 Group 9) and the associated power distribution changes performed dur-ing this period, indicated that the preconditioning envelope recom-mendations had been exceeded. The fact that the maximum allowable nodal powers as established by the fuel vendor's precondition envelope were exceeded is related to some problems with the Power Shape Monitor-
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ing System (PSMS). This is further described in Section From March to mid-December 1985, the offgas activity increased at a
fairly uniform rate to approximately 110,000 micro ci/sec. This in-dicated that some fuel failure existed during this perio In mid-December 1985, the offgas activity sharply increased to 240,000 micro ci/sec. The fuel clad integrity further deteriorated during this perio Fuel failure related to this sharp increase in offgas activity was attributed to plant startup activities on December 18, 1985 when rod group 17 was pulled during high power operation. The subsequent large increase in recirculation flow and, thus, nodal power inadvertently resulted in exceeding the precondi-tioning recommendations. The safety analysis performed to support Cycle 10 operation was based on the GE supplied rod line which i required more manipulation at high power to obtain and maintain the l target rod pattern. However, the plant procedures, specifically i
Procedure 202.1, " Plant Operation," and Procedure 1001.22, " Power Distribution Control During Power Operation," did not provide ade-quate guidance on the limit of ramp rate and maximum recirculation flow increase.
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1.2 PSMS Problems The licensee used PSMS to monitor and predict the power distribution during Cycle 10 operation. Given the plant operating conditions, such as core thermal power, core pressure, core flow, control rod positions, feedwater flow, and feedwater temperature, the PSMS program calculates the margin to the PCI envelope and Technical Specification required parameters such as MCPR, MLHGR, and MAPLHG The accuracy of this calculation is periodically verified by the traversing incore probe (TIP). Various provisions are available to fine tune the model and perform TIP/LPRM calibrations. When there is a significant discrepancy between the predicted (by PSMS) and measured values (by TIP), an LPRM feedback option is availabl This option allows the measured LPRM readings to be included in the calculatio A software error in the PSMS program resulted in the nodal power exceeding the recommended PCI envelope limits during the beginning of Cycle 10 operation. During January 1985 plant operation, when measured and predicted flux values showed an unusually large discrepancy, the LPRM feedback option was turned on. However, this option did not function properly. A software error in the PSMS subroutine TRIGGER prevented the LPRM feedback option from being engaged when called for by the program. Although the option did not function, the display gave the user false indication that the option was being executed. Thus for some time the core engineer was misled by the erroneous PSMS indicatio It was not until later that the error in the software was identified and corrected. When the core engineer realized that the plant was approaching the MAPLHGR limit, they quickly reduced power by inserting control rods. This abrupt rod manipulation shifted the flux peak to a higher position and did not allow proper preconditioning of the new flux peak area and resulted in exceeding the recommended PCI envelope limit The Cycle 10 reload was the first reload cycle utilizing mixed vendor fuel, i.e., GE P8X8R and Exxon Type VB fuel. The PSMS requires basic inputs to the code such as nodal model normalization constants. These constants were subjected to change after actual cycle operating data became available. It appeared that, because of the mixed vendor core, large uncertainties existed in the initial set or normalization constants, as used in the beginning of Cycle operation. This coupled with the software errors in TRIGGER subroutine described above, caused the fuel assembly nodal power to exceed the recommended preconditioning limit Traditionally, Preconditioning Interim Operating Management Recommendations (PCIOMR) is a fuel vendor recommended practice to preclude PCI fuel failur It is not a TS related surveillance and, thus received less scrutin PSMS Revision 1 was used for most of the time during Cycle 10 operation. The type of information displayed for the core engineer's use was insufficient to adequately
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monitor the PCIOM Specifically, the calculation was performed on a pointwise basis, from one power level to the next power level; no ramp rate calculation was include PSMS Revision 2 corrected these deficiencies, however, Revision 2 was not implemented until the end of Cycle 1 .3 Licensee Corrective Actions The licensee preliminary plans as discussed in the October 9, 1986 meeting are as follows:
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Implement a formal fuel performance monitoring progra Trend performance of non-failed GE and Exxon fuel which were previously located at the symmetric locations of the failed fue Revise plant Procedures 202.1 and 1001.22 to provide a more clear guidance on the PCIOMR subjec Enhance PCIOMR training for Core Engineering and Operations staf Improve predictive capability of PSMS model to include consequence predictions of rod movements and Xenon effect The inspector will follow up the licensee's corrective actions.
l Recirculation Pump Trip (RPT) System A special inspection was performed to determine the details of the RPT feature that was installed by the licensee as a result of NRC concerns of an anticipated transient without a scram (ATWS) event. The requirement for the trip was specified in 10 CFR 50.62. The following paragraphs detail the inspection result .1 Design The Oyster Creek RPT is an energize-to-operate system with logic arranged so that two out of two taken once will trip the GE 4160 volt breaker ( AM-4.16-250-6). The 4160 volt breaker has a dual trip coil for the ATWS signals. The trip coil circuits are powered from the 125 VDC safety related power source.
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The pressure and level sensors (Barksdale Fressure Switch and Static-0-Ring differential pressure switch) are environmentally qualifie The logic and control for the RPT can be tested on line. The breakers are tested and serviced when the reactor is off line or during a refueling cycle. The selection of trip set points, procedures, instructions and personnel training are such that RPT inadvertent actuations should be minima The facility station procedure, EMG-3200.02, "RPV Control Level,"
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provides the necessary guidance to the operators in the event the recirculation pump fails to trip on the high pressure or low-low water level trip signal The emergency operating procedure instructs the operator to manually trip the recirculation pump The transients for the tripping of the recirculating pumps are analyzed in the facility Final Safety Analysis Report (FSAR). The consequences of these transients are well within the limiting transient analysis in the FSA (Note: the licensee does not have a PRA or Reliability No. for this system.)
The reactor protection trip system at Oyster Creek is consistent with applicable requirements of 10 CFR 50.62 (ATWS Rule). This design and operating procedures are based on guidance developed by General Electric and submitted to the NR .2 GE 4160 Volt Breakers (AM - 4.16-250-6)
- The breaker that provides power to the Recirculating pump motors is i
a GE magna blast 4160 breaker. This breaker has a dual ATWS coil which is activated from the low-low water level or high pressure ATWS signal. The licensee has no history of failures with these breaker A review of the maintenance history cards for these breakers verified that no major failures of these breakers have occurred at this sit The five RPT 4160 volt breakers have been rebuilt by the General
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Electric Company over the last five years.
i 2.3 Surveillance The RPT surveillance testing requirements are listed in the licensee's station Procedure No. 116, " Surveillance Test Program." The system testing is performed once every refueling cycle while the surveillance testing of the instrumentation and logic components is performed on a quarterly basis. There have been no RPT failures of sensors or breakers in this system to date.
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2.4 Maintenance The licensee has a formal maintenance program which includes both corrective and preventive maintenance activitie This program is defined in Station Procedure No. 116, " Surveillance Test Program,"
and specific component procedures such as Station Procedure N .4.001, " Recirculation Pumps Trip Circuity Test." The component history is maintained on maintenance component test file card This data will be part of the data bank that will be used for trending program when it is operationa The component procedures have test data sheets which when completed and signed are located in the data file system at this site. This data plus the component history cards maintained by the maintenance organization, will be part of the data source that will be used in the trending program data bank .5 Reliability The licensec has not performed a reliability analysis of the RPT system nor have they performed a PRA of this syste The breakers (4160 volt) have redundant trip coils. The RPT component history to date indicates that they have had no failure in this syste .6 Quality Assurance A quality assurance program in conformance with the requirements of
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10 CFR 50, Appendix B, was applied to the RPT design and components from the sensors to the input of the coils of the 4160 volt breaker .7 Equipment Qualifications The sensors, instrumentation, relays, cables, and switches have been qualified to assure that the RPT will perform its functional operability under conditions relevant to the postulated ATWS. The instrumentation racks are seismically installed and meet the design requirements for this site locatio .8 Channel Independence i
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To maintain the reliability of the system, the licansee' has the components of the RPT system in the preventive and corrective maintenance program with the data going into the trending program ,
when it is operational. There is no enhancement of the RPT planned at this time by the license .10 Recorded Failure Rates for the RPT System
The licensee has not issued failure rates nor do they have a Probabilistic Safety Study for the RPT syste .11 Increasing Reliability *
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There have been no design changes issued to increase the reliability '
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s 3. Follow Up of IE Bulletin 80-08, Examination of Containment Liner s Penetration Welds . . 1
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Backgrcund information regarding concerns that' arose during NRC inspection of licensee action to address this Bullettr. appears in NRC Inspection Report 85-29. The Bulletin was left open pending volumetric inspection of field welds in Isolation Condenser system un,Wnrent ,
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penetrations X-SA and X-5B and a shop weld in Liquid Poison systam containment penetration X-6. During this report period, the NRC inspector questioned the licensee regarding.the status of the volumetric inspection of the Isolation Condenser penetration welds because of concerns involving the potential for overstressing penetration welds during a hypothetical rupture of the process pipe in the penetratio The inspector determined that a NDE request had been initiated in May 1986 but had not been acted on. Following discussions between the NRC and the licensee, scaffolding was erected to the "t'wo Isolation Condenser '
condensate return penetrations X-SA and X-58, insulation was removed, and weids FW 5567A and FW 5575A were ultrasonically inspected. The inspection results were reviewed and approved by Tech Function '
This Bulletin will remain open until the Liquid Poison containment penetration shop weld is volumetrically inspecte . Licensee Action on Previous Inspection Findings (Closed) Inspector Follow-up Item (219/86-29-01): Review results of methyl iodine removal efficiency of charcoal in Standby Gas _ Treatment System B The results of the test indicated a methyl iodine removal efficiency of 96%. The Tech Spec acceptance criteria is equal to or greater than 90%.
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(0 pen) Unresolved Item (219/86-24-01): Core Spray System I Full Flow Test Valve V-20-27 <
Inspection Reports 86-21 and 86-24 discussed the failure of V-20-27 during a routina surveillance tes In discussions with the licensee, they agreed to determine the cause of the motor operator failure, who is responsible to review and approve M0 VATS data before operability determination is made, and why significant changes have occurred in TDR 623, Torque Switch Settings, which provides a list of Torrey Pines Technology calculated thrust load The licensee determined the motor operator failure for V-20-27 to be the setting of the torque switch to 3 1/2, which allowed the motor to continue to drive the valve disc into its seat. This occurred as the motor was not able to generate sufficient torque to actuate the torque switch and deactivate the closing circuitry. The vendor motor operator technical manual does not recommend exceeding a torque switch setting of 3 and installs a block plate at this torque switch setting to prevent exceeding it. The repeatability of the torque switch is not reliable when set greater than three. This block plate must be physically removed to set the torque switch at 3 1/2. Presently the motor operator has been ,
sent to the vendor for failure analysis and adjustment of the spring pack to achieve a torque switch setting of 2 at the desired thrust value as specified by TDR 623. In the future to address this concern, the .
licensee will either adjust the spring pack or replace the standard spring pack with the appropriate spring pack to achieve the required torque switch setting and thrust value In addition, the licensee stated that for this direct replacement motor operator, the particular application required the motor operator to perform at greater than its design thrust value in comparison to the Torrey Pine requirements. When questioned if other motor operated valves may be operating in similar conditions, the licensee committed to reviewing all operators to identify those operating outside the manufacturer's design recommendations. These will then be evaluated before plant startup to ensure their operating
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condition is acceptable.
Regarding the change in the thrust values delineated in TDR 623, the licensee explained that a field questionnaire had been improperly
, evaluated and dispositioned which resulted in the erroneous TDR 623
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thrust values. Presently, TDR 623 thrust values for V-20-27 have been correctly implemented. The inspector will review TDR 623 thrust value changes in a future inspectio The licensee clarified the responsible organization for approving and dispositioning motor operated valve test data and is planning to make '
procedure revisions to 700.2.010, Motor Operated Valve Removal Installation or Inspection (Elect), to reflect this. The procedure revision will clarify motor operated valve acceptance criteria with regard to block plate position and torque switch settings and will formally require Plant Engineering acceptance of deviations from this criteri .-.
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This unresolved item will remain open pending the determination if other motor operated valves in the plant are operating outside the manufacturer's design recommendations and implementation of the revised procedure. Open Item 86-21-03, is redundant to this item and is therefore closed for record purpose . Pressure Testing of Recirculation System Piping Weld Overlays As a result of NDE performed on Recirculation System piping welds, the licensee decided to weld overlay welds NG-C-17 and NG-C-23 in the 'C'
recirc loop. Post weld NDE inspection of both welds disclosed rejectable indications. Rework of these indications continued past the period in time when the Tech Spec and ASME Section XI Code required system pressure test was performed. The NRC in:pectors questioned the licensee as to when post-weld repair pressure test of the weld overlays would be performed. The licensee's response was that neither the Tech Specs nor the ASME Code required a pressure test of weld overlays. The resident inspectors disagreed with this interpretation and initiated further discussion of the question between NRC Licensing and the licensee. The discussions revolved around the fact that the ASME Codes do not address weld overlays and, therefore, cannot be used as a reference to determine test requirements. The NRC does, however, recognize weld overlays as an acceptable method to temporarily repair weld joints that exhibit intergranular stress corrosion cracking. NRC guidance on weld overlays does not address pressure test requirements. This was apparently an oversight that NRC Licensing intends to address. To resolve the question at Oyster Creek, NRC Licensing required the licensee to inspect the weld overlays at normal operating pressure after satisfactory completion of all repairs. The need for a hydrostatic test at some higher pressure was not considered necessary. The licensee completed the weld repairs of the overlays and performed an inspection at system operating pressure. The results were satisfactory and the inspectors had no further question . Questionable Practices Involving Qualification of a Welder to Perform Not Important to Safety Welding The licensee informed the NRC inspectors of questionable practices identified during the welder qualification process of a contractor welde Schneider Power Corp. was contracted by the licensee to perform miscellaneous work on "not important to safety" heating, ventilating, and air conditioning system Some of the work involved welding. Schneider transferred a qualified welder from another power plant to Oyster Creek and hired a new welder locally who they had to qualify. The welding code involved was AWS D1.1, Structural Welding. The questionable practice identified involved lack of any type of oversight or supervision of the locally hired welder during the qualification process. This was brought to light when a contractor foreman claimed he saw the qualified welder welding on the test coupons of the welder undergoing qualification. The onsite Schneicer manager could not confirm or deny the claim because he failed to meet the intent of the AWS Code to ensure the qualification
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process was properly carried out. Specifically, he failed to control the qualification process in that there was no oversight to ensure tne new r
welder properly welded his test coupon When the licrasee learned of this incident, they informed the contractor's home office who, in turn, proceeded to investigate the incident. The in- -
vestigation resulted in the contractor discharging both welders, although there was no conclusive proof of wrongdoing on the part of either welder.
, Additionally, the contractor committed to control the welder qualification process for all future welder qualification activitie The NRC inspectors were concerned about this disregard for control of welder qualification by the contractor because of the transferability of the qualification. In particular, if a welder had been improperly quali-fied by Schneider at Oyster Creek, he could then be transferred by Schneider to another site as a qualified welder. At Oyster Creek the improper quali-fication would have impacted only "not important to safety" work, but at another site, could impact "important to safety" work. The action taken to discharge the welders precluded this problem. The inspectors had no additional concern . Radiation Protection During entry to and exit from the RCA, the inspectors verified that proper warning signs were posted, personnel entering were wearing proper dosimetry, personnel and materials leaving were properly monitored for radioactive contamination, and monitoring instruments were functional and in calibration. Posted extended Radiation Work Permits (RWPs) and survey status boards were reviewed to verify that they were current and accurate. The inspector observed activities in the RCA to verify that personnel complied with the requirements of applicable RWPs and that workers were aware of the radiological conditions in the are An Unusual Event was declared at 1638 on October 7, 1986 when a contaminated worker was transported to Community Memorial Hospital. The worker had tripped and fallen while working at the bottom of the reactor seal cavity. He sustained multiple injuries and could not be fully decontaminated prior to leaving the site. The decontamination was completed at the hospital and the Unusual Event terminated approximately an hour and a half later at 181 On October 23, 1986 the licensee detected that an individual working in the reactor vessel seal cavity had inhaled Cobalt 60 (C0-60). This was detected when the individual set off the alarm on a PCM-1 frisker when leaving the RCA. A subsequent frisk using a RM-14 determined the indivi-dual read 50-60 cpm above background and was not externally contaminate He was given a whole body count at which time it was determined he had an uptake of CO-60. The amount was estimated at slightly greater than 200 nano curies. The individual had been properly protected with a powered air purifying respirator (PAPR) while working in the seal cavity and subsequent investigation determined the uptake occurred after he had left
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the area and was helping a fellow worker remove his protective clothing in the change area. The protective clothing was contaminated with CO-6 The individual passed the particle duri,ig a bowel movement within a day and a half, thereby minimizing his exposur . Hydraulic Control Unit (HCU) Valves EP 101 (Drive Insert Riser Isolation Valve) and EP 102 (Drive Withdrawal Riser Isolation Valve)
During this outage, the licensee has examined all HCU 101 and 102 valves for intergranular stress corrosion cracking in the wedge (valve disc) of the valves. After completing this work and vessel operational pressure test, the licensee detected bonnet gasket leaks on some of the valve This will require a freeze seal on the line to each valve to be repaire This is another example of a maintenance task being reworked prior to final acceptance by the plant. The licensee should evaluate rework items as part of their end of outage evaluation to determine root cause. The inspector discussed this with the licensee at the exit meetin . Reactor Coolant System (RCS) Operational Pressure Test During the post refueling operacional pressure test of the RCS, the licensee experienced leakage problems with the vessel head flange inner l 0-ring seal, 'A' recirculation pump flange seal, 'D' recirculation pump l inner seal, and 'E' recirculation pump shaft seal. The vessel flange k
0-ring inner seal leaked as a result of snsp rings, used to hold the 0-ring in place, dislodging and preventing the head flange from making
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metal to metal contact. The licensee removed the vessel head and replaced both vessel flange 0-ring seals. During a subsequent operational pressure test, the inner vessel 0 ring seal leaked agai Because of the recirculation pump seal failures during the Cycle 10 operating cycle, the licensee decided to replace 'D' and 'E'
recirculation pump seals. Upon completion of the seal replacement and the vessel operational system pressure test, the seals leaked as indicated above. The licensee replaced the 'D' recirculation pump seal and was about to complete reassembly of the pump when metal filings were discovered in the seal leakoff. This led to further pump work to determine the source of the metal filings, which was eventually determinad to be an anti-rotation pin that had sheared. The licensee as a result had to replace some of the pump internals, including the impeller, auxiliary impeller, and bearing housing. Apparently, the seal damage was caused by the spacer ring striking the bottom of the seal cartridge. The reassembly process was somewhat protracted as numerous assembly problems arose including the inability to obtain the proper lift on the auxiliary impeller and the pump impeller. The 'E' recirculation pump was also disassembled to verify the pump did not have the same problem as the 'D' recirculation pump. The licensee found that one anti-rotation pin had been dragged and could shear at a later date and that the bearing retainer / spacer ring anti-rotation pin had been wor The licensee repaired the anti-rotation pin locating it 180 degrees from the original position and replaced the bearing retainer, spacer ring and
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bearing. Work continued on the 'A' recirculation pump. The licensee will determine if the 'B' and 'C' recirculation pump seal and pump internals need to be inspected prior to plant startup. The inspectors will continue to follow the licensee's activities in this area and report subsequent findings in future inspection report . Observation of Physical Security During daily tours, the inspector verified access controls were in accordance with the Security Plan, security posts were properly manned, protected area gates were locked or guarded, and isolation zones were free of obstructions. The inspectors examined vital area access points to verify that they were W operly locked or guarded and that access control was in accordance with the Security Pla The licensee reported a moderate loss of security on November 3, 198 The event involved a personnel error where a security guard failed to reset all vital barrier access points in the security computer after a problem with a vital barrier. All other security personnel responded appropriatel . Technical Specifications The licensee has committed to submit a Technical Specification Change Request (TSCR) to clarify Table 3.1.1 of the Oyster Creek Technical Specification by November 1987 in advance of the Cycle 12 refueling outage. Table 3.1.1 needs to be revised to clarify the action requirement for maintaining the reactor shutdown during rod time testin This will remain an open item pending the licensee TSCR submitta (219/86-34-01)
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1 Plant Engineering Meeting The resident inspectors met with the Plant Engineering Director to discuss Plant Engineering work assignments and Technical Functions tasking request The Director described the Operations and Maintenance (0 & M) programs that Plant Engineering performs. He characterized Plant Engineering work assign-l ments as comprising a larger number of functional tasks in comparison to
- capital budget activities. He stated that Technical Functions work requests
do not request technical functions design work that is Plant Engineering's responsibility.
j 13. Exit Interview A summary of the results of the inspection activities performed during this report period were made at meetings with senior licensee management at the end of the inspection. The licensee stated that, of the subjects discussed at the exit interview, no proprietary information was included.