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Category:INSPECTION REPORT
MONTHYEARIR 05000267/19970011997-04-0707 April 1997 Insp Rept 50-267/97-01 on 970310-11.No Violations Noted. Major Areas Inspected:Reviews of Status of Radiation Protection,Environ Monitoring & Radwaste Mgt Programs IR 05000267/19960051996-12-23023 December 1996 Insp Rept 50-267/96-05 on 961203-05.No Violations Noted. Major Areas Inspected:Access Licensees Implementation of Radiation Protection Program & Decommissioning Plan & Included Reviews of Status of Radiation Protection IR 05000267/19900171990-11-29029 November 1990 Insp Rept 50-267/90-17 on 901001-1109.No Violations or Deviations Noted.Major Areas Inspected:Operational Safety, Monthly Surveillance & Maint Observation IR 05000267/19900181990-11-20020 November 1990 Partially Withheld Insp Rept 50-267/90-18 on 901022-26. Violation Noted.Major Areas Inspected:Physical Security Program,Including Protected & Vital Area Barriers,Detection & Assessment Aidscommunications,Testing,Packages & Maint IR 05000267/19900191990-11-16016 November 1990 Insp Rept 50-267/90-19 on 901015-19.No Violations or Deviations Noted.Areas Inspected:Stated Radiological Controls IR 05000267/19900201990-11-14014 November 1990 Insp Rept 50-267/90-20 on 901029-1102.Noncitable Violation Noted.Major Areas Inspected:Insp of Fire Protection/ Prevention Program IR 05000267/19900141990-10-11011 October 1990 Insp Rept 50-267/90-14 on 900801-0930.No Violations or Deviations Noted IR 05000267/19900111990-08-15015 August 1990 Insp Rept 50-267/90-11 on 900601-0728.No Violations Noted. Major Areas Inspected:Onsite Followup of Ler,Operational Safety Verification,Monthly Maint Observation & Monthly Surveillance Observation IR 05000267/19900131990-08-0303 August 1990 Insp Rept 50-267/90-13 on 900709-13.No Violations or Deviations Noted.Major Areas Inspected:Emergency Preparedness Program Including Emergency Detection & Classification,Knowledge & Performance of Duties IR 05000267/19900101990-07-25025 July 1990 Insp Rept 50-267/90-10 on 900611-15.No Violations or Deviations Noted.Major Areas Inspected:Radioactive Matl Transportation Program,Liquid & Gaseous Radwaste Mgt Programs,Including Radiological Effluent Releases IR 05000267/19890191989-10-0202 October 1989 Insp Rept 50-267/89-19 on 890821-26 & 29-30.No Violations or Deviations Noted.Major Areas Inspected:Region 19 CRD Assembly Recovery Activities,Followup on Region 19 CRD Clevis Bolt Failures & Steam Generator Ring Header Problems IR 05000267/19890161989-09-26026 September 1989 Insp Rept 50-267/89-16 on 890716-0831.Violation Noted.Major Areas Inspected:Onsite Followup of Ler,Followup on Violations,Followup of Open Item,Review of Part 21 Repts & Review of Licensee Action of Events IR 05000267/19890131989-08-16016 August 1989 Insp Rept 50-267/89-13 on 890626-30.Violation Noted.No Deviations Noted.Major Areas Inspected:Radwaste Sys IR 05000267/19890141989-08-15015 August 1989 Insp Rept 50-267/89-14 on 890710-14.Violation Noted.Major Areas Inspected:Radiation Protection Program ML20245J5791989-08-10010 August 1989 Insp Rept 50-267/89-17 on 890717-21.Violations Noted.Major Areas Inspected:Licensee Programs for Instrument Calibr & Functional Testing of Diesel Fuel Oil Quality & Storage & Actions on Previously Identified Insp Findings ML20245H3971989-08-0808 August 1989 Insp Rept 50-267/89-12 on 890601-0715.Violation Noted.Major Areas Inspected:Onsite Followup of Lers,Operational Safety Verification & Monthly Surveillance & Maint Observations ML20248E0261989-08-0101 August 1989 Team Insp Rept 50-267/89-08 on 890522-26.Violations Noted. Major Areas Inspected:Maint Activities Re Reactor Water Cooling Sys (Sys 46) IR 05000267/19890151989-07-11011 July 1989 Insp Rept 50-267/89-15 on 890623-27.Violation Noted.Major Areas Inspected:Circumstances & Events Associated W/ Operation of Facility Above Authorized Max Power Level of 82% of Full Power IR 05000267/19890101989-06-15015 June 1989 Insp Rept 50-267/89-10 on 890501-31.No Violations Noted. Major Areas inspected:follow-up of Ler,Licensee Action on Previously Identified Insp Findings,Operational Safety Verification & Monthly Surveillance Observation ML20244C1301989-06-0101 June 1989 Insp Rept 50-267/89-07 on 890319-0430.Violations Noted.Major Areas Inspected:Previously Identified Insp Findings, Operational Safety Verification,Monthly Surveillance Observation & Monthly Maint Observation IR 05000267/19890061989-04-24024 April 1989 Partially Withheld Insp Rept 50-267/89-06 on 890313-17 (Ref 10CFR73.21).Violation Noted.Major Areas Inspected:Physical Security Program,Including Mgt Support & Security Program Plan & Protected & Vital Area Barriers ML20245C8341989-04-13013 April 1989 Insp Rept 50-267/89-03 on 890201-0318.Violations Noted. Major Areas Inspected:Lers,Reserve Shutdown Matl Removal, Operational Safety Verification,Radiological Controls, Monthly Surveillance Observation & Maint Observation IR 05000267/19890051989-04-12012 April 1989 Insp Rept 50-267/89-05 on 890306-10 & 13-17.No Violations Noted.Major Areas Inspected:Previously Identified Insp Items,Surveillance Procedures & Records,Allegation Followup & Preparations for Refueling IR 05000267/19890041989-03-16016 March 1989 Insp Rept 50-267/89-04 on 880227-0303.No Violations or Deviations Noted.Major Areas Inspected:Licensed Operator Training IR 05000267/19890011989-02-16016 February 1989 Partially Withheld Insp Rept 50-267/89-01 on 890109-13 (Ref 10CFR73.21).Violations Noted.Major Areas Inspected: Licensee Physical Security Program Including Mgt Support, Security Program Plan,Audits & Security Training IR 05000267/19890021989-01-17017 January 1989 Insp Rept 50-267/89-02 on 890101-31.Violations Noted.Major Areas Inspected:Licensee Action on Previously Identified Insp Findings,Operational Safety Verification,Monthly Surveillance Observation & Monthly Maint Observation IR 05000267/19880211988-11-21021 November 1988 Insp Rept 50-267/88-21 on 880926-30.Violation & Deviations Noted.Major Areas Inspected:Implementation of & Compliance to Safe Shutdown Requirements of 10CFR50,App R IR 05000267/19880281988-11-18018 November 1988 Insp 50-267/88-28 Canceled & No Insp Rept to Be Issued for Rept Number ML20206M4311988-11-16016 November 1988 Insp Rept 50-267/88-25 on 880911-1022.Violations Noted. Major Areas Inspected:Previously Identified Insp Findings, Licensee Action in Response to NRC Bulletins,Operational Safety Verification & Monthly Maint Observation IR 05000267/19880261988-11-0404 November 1988 Insp Rept 50-267/88-26 on 881017-21.No Violations or Deviations Noted.Major Areas Inspected:Failure of Emergency Diesel Generator Output Breakers to Automatically Close During 881011 Test & Routine Insp of Instrument Calibr IR 05000267/19880241988-10-12012 October 1988 Insp Rept 50-267/88-24 on 880926-30.No Violations or Deviations Noted.Major Areas inspected:safety-related Surveillance Testing & post-mod Testing IR 05000267/19880231988-10-0303 October 1988 Insp Rept 50-267/88-23 on 880912-16.Violations & Deviations Noted.Major Areas Inspected:Refurbishment of Reactor Helium Circulator IR 05000267/19880181988-09-29029 September 1988 Insp Rept 50-267/88-18 on 880829-0902.No Violations or Deviations Noted.Major Areas Inspected:Licensed Operator, Nonlicensed Staff & General Employee Training IR 05000267/19880201988-09-29029 September 1988 Insp Rept 50-267/88-20 on 880801-0910.Violations Noted. Major Areas Inspected:Operational Safety Verification,Ler Review,Monthly Maint Observations,Esf Walkdown,Radiological Protection & Security Observations ML20154N0081988-09-16016 September 1988 Insp Rept 50-267/88-17 on 880724-0802.Violations Noted. Major Areas Inspected:Licensee Radiation Protection Program ML20154E4341988-09-0808 September 1988 Insp Rept 50-267/88-15 on 880711-0805.Violation & Deviation Noted.Major Areas Inspected:Previous Insp Findings,Ler Followup,Control of Design Changes & Mods & Activities Re Refurbishment of Reactor Helium Circulators ML20155B8411988-09-0202 September 1988 Operational Safety Team Insp Rept 50-267/88-200 on 880509-20.Major Areas Inspected:Operations,Maint, Surveillance,Mgt Oversight,Safety Review & QA Programs IR 05000267/19880141988-09-0202 September 1988 Insp Rept 50-267/88-14 on 880725-0805.Violations & Deviations Noted.Major Areas Inspected:Followup of Previous Insp Findings,Status of Reg Guide 1.97 Implementation,Status of Generic Ltr 83-28 Implementation & Followup of LERs IR 05000267/19880191988-08-30030 August 1988 Partially Withheld Insp Rept 50-267/88-19 on 880810-11 (Ref 10CFR73.21).No Violations or Deviations Noted.Major Areas Inspected:Licensee Safeguards Contingency Plan Implementation & Physical Protection of Safeguards Info IR 05000267/19880161988-08-26026 August 1988 Insp Rept 50-267/88-16 on 880701-31.No Violations or Deviations Noted.Major Areas Inspected:Operational Safety Verification,Ler Review,Monthly Maint Observation,Monthly Surveillance & Monthly Security Observation ML20151X4411988-08-11011 August 1988 Insp Rept 50-267/88-13 on 880601-30.Violation Noted.Major Areas Inspected:Licensee Action on NRC Bulletins,Operational Safety Verification,Followup of Allegations,Equipment Qualification Temp Profile & Radiological Protection ML20150C2571988-06-21021 June 1988 Insp Rept 50-267/88-12 on 880501-31.Deviation Noted.Major Areas Inspected:Operational Safety Verification,Ler Review, Monthly Maint Observation,Monthly Surveillance Observation, Radiological Protection & Monthly Security Observation IR 05000267/19880101988-06-0808 June 1988 Insp Rept 50-267/88-10 on 880401-30.Violations Noted.Major Areas Inspected:Followup of Licensee Action on Previously Identified Findings,Followup of Allegation 88-A-01, Operational Safety Verification & Fire Protection IR 05000267/19880111988-05-25025 May 1988 Insp Rept 50-267/88-11 on 880425-29.Violations Noted.Major Areas Inspected:Emergency Response Program,Including Training,Emergency Facilities,Equipment,Instrumentation & Supplies IR 05000267/19880091988-05-13013 May 1988 Insp Rept 50-267/88-09 on 880411-15.No Violations or Deviations Noted.Major Areas Inspected:Licensee Chemistry/ Radiochemistry Program & Water Chemistry & Radiochemistry Confirmatory Measurements IR 05000267/19880071988-05-12012 May 1988 Insp Rept 50-267/88-07 on 880301-31.Violations Noted.Major Areas Inspected:Followup of Licensee Action on Previously Identified Findings,Operational Safety Verification,Review of 10CFR50.59 Safety Evaluations & Radiological Protection IR 05000267/19880081988-04-19019 April 1988 Insp Rept 50-267/88-08 on 880321-25.Violations Noted.Major Areas Inspected:Qa Program,Implementation of 10CFR21,LER Followup & Actions on Previous Insp Findings ML20151R7491988-04-0808 April 1988 Partially Withheld Insp Rept 50-267/88-05 on 880229-0304 (Ref 10CFR73.21).Major Areas Inspected:Insp of Previously Identified Items,Security Plan & Procedures,Security Organization,Locks,Keys & Combinations & Protected Areas IR 05000267/19880041988-03-30030 March 1988 Insp Rept 50-267/88-04 on 880222-26.No Violations or Deviations Noted.Major Areas Inspected:Fire Protection/ Prevention Program & Implementation IR 05000267/19880061988-03-25025 March 1988 Insp Rept 50-267/88-06 on 880229-0304.No Violations Noted. Major Areas Inspected:Licensee Actions Re IE Bulletin 85-003 1997-04-07
[Table view] Category:NRC-GENERATED
MONTHYEARIR 05000267/19970011997-04-0707 April 1997 Insp Rept 50-267/97-01 on 970310-11.No Violations Noted. Major Areas Inspected:Reviews of Status of Radiation Protection,Environ Monitoring & Radwaste Mgt Programs IR 05000267/19960051996-12-23023 December 1996 Insp Rept 50-267/96-05 on 961203-05.No Violations Noted. Major Areas Inspected:Access Licensees Implementation of Radiation Protection Program & Decommissioning Plan & Included Reviews of Status of Radiation Protection IR 05000267/19900171990-11-29029 November 1990 Insp Rept 50-267/90-17 on 901001-1109.No Violations or Deviations Noted.Major Areas Inspected:Operational Safety, Monthly Surveillance & Maint Observation IR 05000267/19900181990-11-20020 November 1990 Partially Withheld Insp Rept 50-267/90-18 on 901022-26. Violation Noted.Major Areas Inspected:Physical Security Program,Including Protected & Vital Area Barriers,Detection & Assessment Aidscommunications,Testing,Packages & Maint IR 05000267/19900191990-11-16016 November 1990 Insp Rept 50-267/90-19 on 901015-19.No Violations or Deviations Noted.Areas Inspected:Stated Radiological Controls IR 05000267/19900201990-11-14014 November 1990 Insp Rept 50-267/90-20 on 901029-1102.Noncitable Violation Noted.Major Areas Inspected:Insp of Fire Protection/ Prevention Program IR 05000267/19900141990-10-11011 October 1990 Insp Rept 50-267/90-14 on 900801-0930.No Violations or Deviations Noted IR 05000267/19900111990-08-15015 August 1990 Insp Rept 50-267/90-11 on 900601-0728.No Violations Noted. Major Areas Inspected:Onsite Followup of Ler,Operational Safety Verification,Monthly Maint Observation & Monthly Surveillance Observation IR 05000267/19900131990-08-0303 August 1990 Insp Rept 50-267/90-13 on 900709-13.No Violations or Deviations Noted.Major Areas Inspected:Emergency Preparedness Program Including Emergency Detection & Classification,Knowledge & Performance of Duties IR 05000267/19900101990-07-25025 July 1990 Insp Rept 50-267/90-10 on 900611-15.No Violations or Deviations Noted.Major Areas Inspected:Radioactive Matl Transportation Program,Liquid & Gaseous Radwaste Mgt Programs,Including Radiological Effluent Releases IR 05000267/19890191989-10-0202 October 1989 Insp Rept 50-267/89-19 on 890821-26 & 29-30.No Violations or Deviations Noted.Major Areas Inspected:Region 19 CRD Assembly Recovery Activities,Followup on Region 19 CRD Clevis Bolt Failures & Steam Generator Ring Header Problems IR 05000267/19890161989-09-26026 September 1989 Insp Rept 50-267/89-16 on 890716-0831.Violation Noted.Major Areas Inspected:Onsite Followup of Ler,Followup on Violations,Followup of Open Item,Review of Part 21 Repts & Review of Licensee Action of Events IR 05000267/19890131989-08-16016 August 1989 Insp Rept 50-267/89-13 on 890626-30.Violation Noted.No Deviations Noted.Major Areas Inspected:Radwaste Sys IR 05000267/19890141989-08-15015 August 1989 Insp Rept 50-267/89-14 on 890710-14.Violation Noted.Major Areas Inspected:Radiation Protection Program ML20245J5791989-08-10010 August 1989 Insp Rept 50-267/89-17 on 890717-21.Violations Noted.Major Areas Inspected:Licensee Programs for Instrument Calibr & Functional Testing of Diesel Fuel Oil Quality & Storage & Actions on Previously Identified Insp Findings ML20245H3971989-08-0808 August 1989 Insp Rept 50-267/89-12 on 890601-0715.Violation Noted.Major Areas Inspected:Onsite Followup of Lers,Operational Safety Verification & Monthly Surveillance & Maint Observations ML20248E0261989-08-0101 August 1989 Team Insp Rept 50-267/89-08 on 890522-26.Violations Noted. Major Areas Inspected:Maint Activities Re Reactor Water Cooling Sys (Sys 46) IR 05000267/19890151989-07-11011 July 1989 Insp Rept 50-267/89-15 on 890623-27.Violation Noted.Major Areas Inspected:Circumstances & Events Associated W/ Operation of Facility Above Authorized Max Power Level of 82% of Full Power IR 05000267/19890101989-06-15015 June 1989 Insp Rept 50-267/89-10 on 890501-31.No Violations Noted. Major Areas inspected:follow-up of Ler,Licensee Action on Previously Identified Insp Findings,Operational Safety Verification & Monthly Surveillance Observation ML20244C1301989-06-0101 June 1989 Insp Rept 50-267/89-07 on 890319-0430.Violations Noted.Major Areas Inspected:Previously Identified Insp Findings, Operational Safety Verification,Monthly Surveillance Observation & Monthly Maint Observation IR 05000267/19890061989-04-24024 April 1989 Partially Withheld Insp Rept 50-267/89-06 on 890313-17 (Ref 10CFR73.21).Violation Noted.Major Areas Inspected:Physical Security Program,Including Mgt Support & Security Program Plan & Protected & Vital Area Barriers ML20245C8341989-04-13013 April 1989 Insp Rept 50-267/89-03 on 890201-0318.Violations Noted. Major Areas Inspected:Lers,Reserve Shutdown Matl Removal, Operational Safety Verification,Radiological Controls, Monthly Surveillance Observation & Maint Observation IR 05000267/19890051989-04-12012 April 1989 Insp Rept 50-267/89-05 on 890306-10 & 13-17.No Violations Noted.Major Areas Inspected:Previously Identified Insp Items,Surveillance Procedures & Records,Allegation Followup & Preparations for Refueling IR 05000267/19890041989-03-16016 March 1989 Insp Rept 50-267/89-04 on 880227-0303.No Violations or Deviations Noted.Major Areas Inspected:Licensed Operator Training IR 05000267/19890011989-02-16016 February 1989 Partially Withheld Insp Rept 50-267/89-01 on 890109-13 (Ref 10CFR73.21).Violations Noted.Major Areas Inspected: Licensee Physical Security Program Including Mgt Support, Security Program Plan,Audits & Security Training IR 05000267/19890021989-01-17017 January 1989 Insp Rept 50-267/89-02 on 890101-31.Violations Noted.Major Areas Inspected:Licensee Action on Previously Identified Insp Findings,Operational Safety Verification,Monthly Surveillance Observation & Monthly Maint Observation IR 05000267/19880211988-11-21021 November 1988 Insp Rept 50-267/88-21 on 880926-30.Violation & Deviations Noted.Major Areas Inspected:Implementation of & Compliance to Safe Shutdown Requirements of 10CFR50,App R IR 05000267/19880281988-11-18018 November 1988 Insp 50-267/88-28 Canceled & No Insp Rept to Be Issued for Rept Number ML20206M4311988-11-16016 November 1988 Insp Rept 50-267/88-25 on 880911-1022.Violations Noted. Major Areas Inspected:Previously Identified Insp Findings, Licensee Action in Response to NRC Bulletins,Operational Safety Verification & Monthly Maint Observation IR 05000267/19880261988-11-0404 November 1988 Insp Rept 50-267/88-26 on 881017-21.No Violations or Deviations Noted.Major Areas Inspected:Failure of Emergency Diesel Generator Output Breakers to Automatically Close During 881011 Test & Routine Insp of Instrument Calibr IR 05000267/19880241988-10-12012 October 1988 Insp Rept 50-267/88-24 on 880926-30.No Violations or Deviations Noted.Major Areas inspected:safety-related Surveillance Testing & post-mod Testing IR 05000267/19880231988-10-0303 October 1988 Insp Rept 50-267/88-23 on 880912-16.Violations & Deviations Noted.Major Areas Inspected:Refurbishment of Reactor Helium Circulator IR 05000267/19880181988-09-29029 September 1988 Insp Rept 50-267/88-18 on 880829-0902.No Violations or Deviations Noted.Major Areas Inspected:Licensed Operator, Nonlicensed Staff & General Employee Training IR 05000267/19880201988-09-29029 September 1988 Insp Rept 50-267/88-20 on 880801-0910.Violations Noted. Major Areas Inspected:Operational Safety Verification,Ler Review,Monthly Maint Observations,Esf Walkdown,Radiological Protection & Security Observations ML20154N0081988-09-16016 September 1988 Insp Rept 50-267/88-17 on 880724-0802.Violations Noted. Major Areas Inspected:Licensee Radiation Protection Program ML20154E4341988-09-0808 September 1988 Insp Rept 50-267/88-15 on 880711-0805.Violation & Deviation Noted.Major Areas Inspected:Previous Insp Findings,Ler Followup,Control of Design Changes & Mods & Activities Re Refurbishment of Reactor Helium Circulators ML20155B8411988-09-0202 September 1988 Operational Safety Team Insp Rept 50-267/88-200 on 880509-20.Major Areas Inspected:Operations,Maint, Surveillance,Mgt Oversight,Safety Review & QA Programs IR 05000267/19880141988-09-0202 September 1988 Insp Rept 50-267/88-14 on 880725-0805.Violations & Deviations Noted.Major Areas Inspected:Followup of Previous Insp Findings,Status of Reg Guide 1.97 Implementation,Status of Generic Ltr 83-28 Implementation & Followup of LERs IR 05000267/19880191988-08-30030 August 1988 Partially Withheld Insp Rept 50-267/88-19 on 880810-11 (Ref 10CFR73.21).No Violations or Deviations Noted.Major Areas Inspected:Licensee Safeguards Contingency Plan Implementation & Physical Protection of Safeguards Info IR 05000267/19880161988-08-26026 August 1988 Insp Rept 50-267/88-16 on 880701-31.No Violations or Deviations Noted.Major Areas Inspected:Operational Safety Verification,Ler Review,Monthly Maint Observation,Monthly Surveillance & Monthly Security Observation ML20151X4411988-08-11011 August 1988 Insp Rept 50-267/88-13 on 880601-30.Violation Noted.Major Areas Inspected:Licensee Action on NRC Bulletins,Operational Safety Verification,Followup of Allegations,Equipment Qualification Temp Profile & Radiological Protection ML20150C2571988-06-21021 June 1988 Insp Rept 50-267/88-12 on 880501-31.Deviation Noted.Major Areas Inspected:Operational Safety Verification,Ler Review, Monthly Maint Observation,Monthly Surveillance Observation, Radiological Protection & Monthly Security Observation IR 05000267/19880101988-06-0808 June 1988 Insp Rept 50-267/88-10 on 880401-30.Violations Noted.Major Areas Inspected:Followup of Licensee Action on Previously Identified Findings,Followup of Allegation 88-A-01, Operational Safety Verification & Fire Protection IR 05000267/19880111988-05-25025 May 1988 Insp Rept 50-267/88-11 on 880425-29.Violations Noted.Major Areas Inspected:Emergency Response Program,Including Training,Emergency Facilities,Equipment,Instrumentation & Supplies IR 05000267/19880091988-05-13013 May 1988 Insp Rept 50-267/88-09 on 880411-15.No Violations or Deviations Noted.Major Areas Inspected:Licensee Chemistry/ Radiochemistry Program & Water Chemistry & Radiochemistry Confirmatory Measurements IR 05000267/19880071988-05-12012 May 1988 Insp Rept 50-267/88-07 on 880301-31.Violations Noted.Major Areas Inspected:Followup of Licensee Action on Previously Identified Findings,Operational Safety Verification,Review of 10CFR50.59 Safety Evaluations & Radiological Protection IR 05000267/19880081988-04-19019 April 1988 Insp Rept 50-267/88-08 on 880321-25.Violations Noted.Major Areas Inspected:Qa Program,Implementation of 10CFR21,LER Followup & Actions on Previous Insp Findings ML20151R7491988-04-0808 April 1988 Partially Withheld Insp Rept 50-267/88-05 on 880229-0304 (Ref 10CFR73.21).Major Areas Inspected:Insp of Previously Identified Items,Security Plan & Procedures,Security Organization,Locks,Keys & Combinations & Protected Areas IR 05000267/19880041988-03-30030 March 1988 Insp Rept 50-267/88-04 on 880222-26.No Violations or Deviations Noted.Major Areas Inspected:Fire Protection/ Prevention Program & Implementation IR 05000267/19880061988-03-25025 March 1988 Insp Rept 50-267/88-06 on 880229-0304.No Violations Noted. Major Areas Inspected:Licensee Actions Re IE Bulletin 85-003 1997-04-07
[Table view] Category:INSPECTION REPORT
MONTHYEARIR 05000267/19970011997-04-0707 April 1997 Insp Rept 50-267/97-01 on 970310-11.No Violations Noted. Major Areas Inspected:Reviews of Status of Radiation Protection,Environ Monitoring & Radwaste Mgt Programs IR 05000267/19960051996-12-23023 December 1996 Insp Rept 50-267/96-05 on 961203-05.No Violations Noted. Major Areas Inspected:Access Licensees Implementation of Radiation Protection Program & Decommissioning Plan & Included Reviews of Status of Radiation Protection IR 05000267/19900171990-11-29029 November 1990 Insp Rept 50-267/90-17 on 901001-1109.No Violations or Deviations Noted.Major Areas Inspected:Operational Safety, Monthly Surveillance & Maint Observation IR 05000267/19900181990-11-20020 November 1990 Partially Withheld Insp Rept 50-267/90-18 on 901022-26. Violation Noted.Major Areas Inspected:Physical Security Program,Including Protected & Vital Area Barriers,Detection & Assessment Aidscommunications,Testing,Packages & Maint IR 05000267/19900191990-11-16016 November 1990 Insp Rept 50-267/90-19 on 901015-19.No Violations or Deviations Noted.Areas Inspected:Stated Radiological Controls IR 05000267/19900201990-11-14014 November 1990 Insp Rept 50-267/90-20 on 901029-1102.Noncitable Violation Noted.Major Areas Inspected:Insp of Fire Protection/ Prevention Program IR 05000267/19900141990-10-11011 October 1990 Insp Rept 50-267/90-14 on 900801-0930.No Violations or Deviations Noted IR 05000267/19900111990-08-15015 August 1990 Insp Rept 50-267/90-11 on 900601-0728.No Violations Noted. Major Areas Inspected:Onsite Followup of Ler,Operational Safety Verification,Monthly Maint Observation & Monthly Surveillance Observation IR 05000267/19900131990-08-0303 August 1990 Insp Rept 50-267/90-13 on 900709-13.No Violations or Deviations Noted.Major Areas Inspected:Emergency Preparedness Program Including Emergency Detection & Classification,Knowledge & Performance of Duties IR 05000267/19900101990-07-25025 July 1990 Insp Rept 50-267/90-10 on 900611-15.No Violations or Deviations Noted.Major Areas Inspected:Radioactive Matl Transportation Program,Liquid & Gaseous Radwaste Mgt Programs,Including Radiological Effluent Releases IR 05000267/19890191989-10-0202 October 1989 Insp Rept 50-267/89-19 on 890821-26 & 29-30.No Violations or Deviations Noted.Major Areas Inspected:Region 19 CRD Assembly Recovery Activities,Followup on Region 19 CRD Clevis Bolt Failures & Steam Generator Ring Header Problems IR 05000267/19890161989-09-26026 September 1989 Insp Rept 50-267/89-16 on 890716-0831.Violation Noted.Major Areas Inspected:Onsite Followup of Ler,Followup on Violations,Followup of Open Item,Review of Part 21 Repts & Review of Licensee Action of Events IR 05000267/19890131989-08-16016 August 1989 Insp Rept 50-267/89-13 on 890626-30.Violation Noted.No Deviations Noted.Major Areas Inspected:Radwaste Sys IR 05000267/19890141989-08-15015 August 1989 Insp Rept 50-267/89-14 on 890710-14.Violation Noted.Major Areas Inspected:Radiation Protection Program ML20245J5791989-08-10010 August 1989 Insp Rept 50-267/89-17 on 890717-21.Violations Noted.Major Areas Inspected:Licensee Programs for Instrument Calibr & Functional Testing of Diesel Fuel Oil Quality & Storage & Actions on Previously Identified Insp Findings ML20245H3971989-08-0808 August 1989 Insp Rept 50-267/89-12 on 890601-0715.Violation Noted.Major Areas Inspected:Onsite Followup of Lers,Operational Safety Verification & Monthly Surveillance & Maint Observations ML20248E0261989-08-0101 August 1989 Team Insp Rept 50-267/89-08 on 890522-26.Violations Noted. Major Areas Inspected:Maint Activities Re Reactor Water Cooling Sys (Sys 46) IR 05000267/19890151989-07-11011 July 1989 Insp Rept 50-267/89-15 on 890623-27.Violation Noted.Major Areas Inspected:Circumstances & Events Associated W/ Operation of Facility Above Authorized Max Power Level of 82% of Full Power IR 05000267/19890101989-06-15015 June 1989 Insp Rept 50-267/89-10 on 890501-31.No Violations Noted. Major Areas inspected:follow-up of Ler,Licensee Action on Previously Identified Insp Findings,Operational Safety Verification & Monthly Surveillance Observation ML20244C1301989-06-0101 June 1989 Insp Rept 50-267/89-07 on 890319-0430.Violations Noted.Major Areas Inspected:Previously Identified Insp Findings, Operational Safety Verification,Monthly Surveillance Observation & Monthly Maint Observation IR 05000267/19890061989-04-24024 April 1989 Partially Withheld Insp Rept 50-267/89-06 on 890313-17 (Ref 10CFR73.21).Violation Noted.Major Areas Inspected:Physical Security Program,Including Mgt Support & Security Program Plan & Protected & Vital Area Barriers ML20245C8341989-04-13013 April 1989 Insp Rept 50-267/89-03 on 890201-0318.Violations Noted. Major Areas Inspected:Lers,Reserve Shutdown Matl Removal, Operational Safety Verification,Radiological Controls, Monthly Surveillance Observation & Maint Observation IR 05000267/19890051989-04-12012 April 1989 Insp Rept 50-267/89-05 on 890306-10 & 13-17.No Violations Noted.Major Areas Inspected:Previously Identified Insp Items,Surveillance Procedures & Records,Allegation Followup & Preparations for Refueling IR 05000267/19890041989-03-16016 March 1989 Insp Rept 50-267/89-04 on 880227-0303.No Violations or Deviations Noted.Major Areas Inspected:Licensed Operator Training IR 05000267/19890011989-02-16016 February 1989 Partially Withheld Insp Rept 50-267/89-01 on 890109-13 (Ref 10CFR73.21).Violations Noted.Major Areas Inspected: Licensee Physical Security Program Including Mgt Support, Security Program Plan,Audits & Security Training IR 05000267/19890021989-01-17017 January 1989 Insp Rept 50-267/89-02 on 890101-31.Violations Noted.Major Areas Inspected:Licensee Action on Previously Identified Insp Findings,Operational Safety Verification,Monthly Surveillance Observation & Monthly Maint Observation IR 05000267/19880211988-11-21021 November 1988 Insp Rept 50-267/88-21 on 880926-30.Violation & Deviations Noted.Major Areas Inspected:Implementation of & Compliance to Safe Shutdown Requirements of 10CFR50,App R IR 05000267/19880281988-11-18018 November 1988 Insp 50-267/88-28 Canceled & No Insp Rept to Be Issued for Rept Number ML20206M4311988-11-16016 November 1988 Insp Rept 50-267/88-25 on 880911-1022.Violations Noted. Major Areas Inspected:Previously Identified Insp Findings, Licensee Action in Response to NRC Bulletins,Operational Safety Verification & Monthly Maint Observation IR 05000267/19880261988-11-0404 November 1988 Insp Rept 50-267/88-26 on 881017-21.No Violations or Deviations Noted.Major Areas Inspected:Failure of Emergency Diesel Generator Output Breakers to Automatically Close During 881011 Test & Routine Insp of Instrument Calibr IR 05000267/19880241988-10-12012 October 1988 Insp Rept 50-267/88-24 on 880926-30.No Violations or Deviations Noted.Major Areas inspected:safety-related Surveillance Testing & post-mod Testing IR 05000267/19880231988-10-0303 October 1988 Insp Rept 50-267/88-23 on 880912-16.Violations & Deviations Noted.Major Areas Inspected:Refurbishment of Reactor Helium Circulator IR 05000267/19880181988-09-29029 September 1988 Insp Rept 50-267/88-18 on 880829-0902.No Violations or Deviations Noted.Major Areas Inspected:Licensed Operator, Nonlicensed Staff & General Employee Training IR 05000267/19880201988-09-29029 September 1988 Insp Rept 50-267/88-20 on 880801-0910.Violations Noted. Major Areas Inspected:Operational Safety Verification,Ler Review,Monthly Maint Observations,Esf Walkdown,Radiological Protection & Security Observations ML20154N0081988-09-16016 September 1988 Insp Rept 50-267/88-17 on 880724-0802.Violations Noted. Major Areas Inspected:Licensee Radiation Protection Program ML20154E4341988-09-0808 September 1988 Insp Rept 50-267/88-15 on 880711-0805.Violation & Deviation Noted.Major Areas Inspected:Previous Insp Findings,Ler Followup,Control of Design Changes & Mods & Activities Re Refurbishment of Reactor Helium Circulators ML20155B8411988-09-0202 September 1988 Operational Safety Team Insp Rept 50-267/88-200 on 880509-20.Major Areas Inspected:Operations,Maint, Surveillance,Mgt Oversight,Safety Review & QA Programs IR 05000267/19880141988-09-0202 September 1988 Insp Rept 50-267/88-14 on 880725-0805.Violations & Deviations Noted.Major Areas Inspected:Followup of Previous Insp Findings,Status of Reg Guide 1.97 Implementation,Status of Generic Ltr 83-28 Implementation & Followup of LERs IR 05000267/19880191988-08-30030 August 1988 Partially Withheld Insp Rept 50-267/88-19 on 880810-11 (Ref 10CFR73.21).No Violations or Deviations Noted.Major Areas Inspected:Licensee Safeguards Contingency Plan Implementation & Physical Protection of Safeguards Info IR 05000267/19880161988-08-26026 August 1988 Insp Rept 50-267/88-16 on 880701-31.No Violations or Deviations Noted.Major Areas Inspected:Operational Safety Verification,Ler Review,Monthly Maint Observation,Monthly Surveillance & Monthly Security Observation ML20151X4411988-08-11011 August 1988 Insp Rept 50-267/88-13 on 880601-30.Violation Noted.Major Areas Inspected:Licensee Action on NRC Bulletins,Operational Safety Verification,Followup of Allegations,Equipment Qualification Temp Profile & Radiological Protection ML20150C2571988-06-21021 June 1988 Insp Rept 50-267/88-12 on 880501-31.Deviation Noted.Major Areas Inspected:Operational Safety Verification,Ler Review, Monthly Maint Observation,Monthly Surveillance Observation, Radiological Protection & Monthly Security Observation IR 05000267/19880101988-06-0808 June 1988 Insp Rept 50-267/88-10 on 880401-30.Violations Noted.Major Areas Inspected:Followup of Licensee Action on Previously Identified Findings,Followup of Allegation 88-A-01, Operational Safety Verification & Fire Protection IR 05000267/19880111988-05-25025 May 1988 Insp Rept 50-267/88-11 on 880425-29.Violations Noted.Major Areas Inspected:Emergency Response Program,Including Training,Emergency Facilities,Equipment,Instrumentation & Supplies IR 05000267/19880091988-05-13013 May 1988 Insp Rept 50-267/88-09 on 880411-15.No Violations or Deviations Noted.Major Areas Inspected:Licensee Chemistry/ Radiochemistry Program & Water Chemistry & Radiochemistry Confirmatory Measurements IR 05000267/19880071988-05-12012 May 1988 Insp Rept 50-267/88-07 on 880301-31.Violations Noted.Major Areas Inspected:Followup of Licensee Action on Previously Identified Findings,Operational Safety Verification,Review of 10CFR50.59 Safety Evaluations & Radiological Protection IR 05000267/19880081988-04-19019 April 1988 Insp Rept 50-267/88-08 on 880321-25.Violations Noted.Major Areas Inspected:Qa Program,Implementation of 10CFR21,LER Followup & Actions on Previous Insp Findings ML20151R7491988-04-0808 April 1988 Partially Withheld Insp Rept 50-267/88-05 on 880229-0304 (Ref 10CFR73.21).Major Areas Inspected:Insp of Previously Identified Items,Security Plan & Procedures,Security Organization,Locks,Keys & Combinations & Protected Areas IR 05000267/19880041988-03-30030 March 1988 Insp Rept 50-267/88-04 on 880222-26.No Violations or Deviations Noted.Major Areas Inspected:Fire Protection/ Prevention Program & Implementation IR 05000267/19880061988-03-25025 March 1988 Insp Rept 50-267/88-06 on 880229-0304.No Violations Noted. Major Areas Inspected:Licensee Actions Re IE Bulletin 85-003 1997-04-07
[Table view] Category:UTILITY
MONTHYEARIR 05000267/19900201990-11-14014 November 1990 Insp Rept 50-267/90-20 on 901029-1102.Noncitable Violation Noted.Major Areas Inspected:Insp of Fire Protection/ Prevention Program IR 05000267/19900141990-10-11011 October 1990 Insp Rept 50-267/90-14 on 900801-0930.No Violations or Deviations Noted IR 05000267/19900111990-08-15015 August 1990 Insp Rept 50-267/90-11 on 900601-0728.No Violations Noted. Major Areas Inspected:Onsite Followup of Ler,Operational Safety Verification,Monthly Maint Observation & Monthly Surveillance Observation IR 05000267/19900131990-08-0303 August 1990 Insp Rept 50-267/90-13 on 900709-13.No Violations or Deviations Noted.Major Areas Inspected:Emergency Preparedness Program Including Emergency Detection & Classification,Knowledge & Performance of Duties IR 05000267/19900101990-07-25025 July 1990 Insp Rept 50-267/90-10 on 900611-15.No Violations or Deviations Noted.Major Areas Inspected:Radioactive Matl Transportation Program,Liquid & Gaseous Radwaste Mgt Programs,Including Radiological Effluent Releases IR 05000267/19890191989-10-0202 October 1989 Insp Rept 50-267/89-19 on 890821-26 & 29-30.No Violations or Deviations Noted.Major Areas Inspected:Region 19 CRD Assembly Recovery Activities,Followup on Region 19 CRD Clevis Bolt Failures & Steam Generator Ring Header Problems IR 05000267/19890161989-09-26026 September 1989 Insp Rept 50-267/89-16 on 890716-0831.Violation Noted.Major Areas Inspected:Onsite Followup of Ler,Followup on Violations,Followup of Open Item,Review of Part 21 Repts & Review of Licensee Action of Events IR 05000267/19890131989-08-16016 August 1989 Insp Rept 50-267/89-13 on 890626-30.Violation Noted.No Deviations Noted.Major Areas Inspected:Radwaste Sys IR 05000267/19890141989-08-15015 August 1989 Insp Rept 50-267/89-14 on 890710-14.Violation Noted.Major Areas Inspected:Radiation Protection Program ML20245J5791989-08-10010 August 1989 Insp Rept 50-267/89-17 on 890717-21.Violations Noted.Major Areas Inspected:Licensee Programs for Instrument Calibr & Functional Testing of Diesel Fuel Oil Quality & Storage & Actions on Previously Identified Insp Findings ML20245H3971989-08-0808 August 1989 Insp Rept 50-267/89-12 on 890601-0715.Violation Noted.Major Areas Inspected:Onsite Followup of Lers,Operational Safety Verification & Monthly Surveillance & Maint Observations ML20248E0261989-08-0101 August 1989 Team Insp Rept 50-267/89-08 on 890522-26.Violations Noted. Major Areas Inspected:Maint Activities Re Reactor Water Cooling Sys (Sys 46) IR 05000267/19890151989-07-11011 July 1989 Insp Rept 50-267/89-15 on 890623-27.Violation Noted.Major Areas Inspected:Circumstances & Events Associated W/ Operation of Facility Above Authorized Max Power Level of 82% of Full Power IR 05000267/19890101989-06-15015 June 1989 Insp Rept 50-267/89-10 on 890501-31.No Violations Noted. Major Areas inspected:follow-up of Ler,Licensee Action on Previously Identified Insp Findings,Operational Safety Verification & Monthly Surveillance Observation ML20244C1301989-06-0101 June 1989 Insp Rept 50-267/89-07 on 890319-0430.Violations Noted.Major Areas Inspected:Previously Identified Insp Findings, Operational Safety Verification,Monthly Surveillance Observation & Monthly Maint Observation IR 05000267/19890061989-04-24024 April 1989 Partially Withheld Insp Rept 50-267/89-06 on 890313-17 (Ref 10CFR73.21).Violation Noted.Major Areas Inspected:Physical Security Program,Including Mgt Support & Security Program Plan & Protected & Vital Area Barriers ML20245C8341989-04-13013 April 1989 Insp Rept 50-267/89-03 on 890201-0318.Violations Noted. Major Areas Inspected:Lers,Reserve Shutdown Matl Removal, Operational Safety Verification,Radiological Controls, Monthly Surveillance Observation & Maint Observation IR 05000267/19890051989-04-12012 April 1989 Insp Rept 50-267/89-05 on 890306-10 & 13-17.No Violations Noted.Major Areas Inspected:Previously Identified Insp Items,Surveillance Procedures & Records,Allegation Followup & Preparations for Refueling IR 05000267/19890041989-03-16016 March 1989 Insp Rept 50-267/89-04 on 880227-0303.No Violations or Deviations Noted.Major Areas Inspected:Licensed Operator Training IR 05000267/19890011989-02-16016 February 1989 Partially Withheld Insp Rept 50-267/89-01 on 890109-13 (Ref 10CFR73.21).Violations Noted.Major Areas Inspected: Licensee Physical Security Program Including Mgt Support, Security Program Plan,Audits & Security Training IR 05000267/19890021989-01-17017 January 1989 Insp Rept 50-267/89-02 on 890101-31.Violations Noted.Major Areas Inspected:Licensee Action on Previously Identified Insp Findings,Operational Safety Verification,Monthly Surveillance Observation & Monthly Maint Observation IR 05000267/19880211988-11-21021 November 1988 Insp Rept 50-267/88-21 on 880926-30.Violation & Deviations Noted.Major Areas Inspected:Implementation of & Compliance to Safe Shutdown Requirements of 10CFR50,App R IR 05000267/19880281988-11-18018 November 1988 Insp 50-267/88-28 Canceled & No Insp Rept to Be Issued for Rept Number ML20206M4311988-11-16016 November 1988 Insp Rept 50-267/88-25 on 880911-1022.Violations Noted. Major Areas Inspected:Previously Identified Insp Findings, Licensee Action in Response to NRC Bulletins,Operational Safety Verification & Monthly Maint Observation IR 05000267/19880261988-11-0404 November 1988 Insp Rept 50-267/88-26 on 881017-21.No Violations or Deviations Noted.Major Areas Inspected:Failure of Emergency Diesel Generator Output Breakers to Automatically Close During 881011 Test & Routine Insp of Instrument Calibr IR 05000267/19880241988-10-12012 October 1988 Insp Rept 50-267/88-24 on 880926-30.No Violations or Deviations Noted.Major Areas inspected:safety-related Surveillance Testing & post-mod Testing IR 05000267/19880231988-10-0303 October 1988 Insp Rept 50-267/88-23 on 880912-16.Violations & Deviations Noted.Major Areas Inspected:Refurbishment of Reactor Helium Circulator IR 05000267/19880181988-09-29029 September 1988 Insp Rept 50-267/88-18 on 880829-0902.No Violations or Deviations Noted.Major Areas Inspected:Licensed Operator, Nonlicensed Staff & General Employee Training IR 05000267/19880201988-09-29029 September 1988 Insp Rept 50-267/88-20 on 880801-0910.Violations Noted. Major Areas Inspected:Operational Safety Verification,Ler Review,Monthly Maint Observations,Esf Walkdown,Radiological Protection & Security Observations ML20154N0081988-09-16016 September 1988 Insp Rept 50-267/88-17 on 880724-0802.Violations Noted. Major Areas Inspected:Licensee Radiation Protection Program ML20154E4341988-09-0808 September 1988 Insp Rept 50-267/88-15 on 880711-0805.Violation & Deviation Noted.Major Areas Inspected:Previous Insp Findings,Ler Followup,Control of Design Changes & Mods & Activities Re Refurbishment of Reactor Helium Circulators ML20155B8411988-09-0202 September 1988 Operational Safety Team Insp Rept 50-267/88-200 on 880509-20.Major Areas Inspected:Operations,Maint, Surveillance,Mgt Oversight,Safety Review & QA Programs IR 05000267/19880141988-09-0202 September 1988 Insp Rept 50-267/88-14 on 880725-0805.Violations & Deviations Noted.Major Areas Inspected:Followup of Previous Insp Findings,Status of Reg Guide 1.97 Implementation,Status of Generic Ltr 83-28 Implementation & Followup of LERs IR 05000267/19880191988-08-30030 August 1988 Partially Withheld Insp Rept 50-267/88-19 on 880810-11 (Ref 10CFR73.21).No Violations or Deviations Noted.Major Areas Inspected:Licensee Safeguards Contingency Plan Implementation & Physical Protection of Safeguards Info IR 05000267/19880161988-08-26026 August 1988 Insp Rept 50-267/88-16 on 880701-31.No Violations or Deviations Noted.Major Areas Inspected:Operational Safety Verification,Ler Review,Monthly Maint Observation,Monthly Surveillance & Monthly Security Observation ML20151X4411988-08-11011 August 1988 Insp Rept 50-267/88-13 on 880601-30.Violation Noted.Major Areas Inspected:Licensee Action on NRC Bulletins,Operational Safety Verification,Followup of Allegations,Equipment Qualification Temp Profile & Radiological Protection ML20150C2571988-06-21021 June 1988 Insp Rept 50-267/88-12 on 880501-31.Deviation Noted.Major Areas Inspected:Operational Safety Verification,Ler Review, Monthly Maint Observation,Monthly Surveillance Observation, Radiological Protection & Monthly Security Observation IR 05000267/19880101988-06-0808 June 1988 Insp Rept 50-267/88-10 on 880401-30.Violations Noted.Major Areas Inspected:Followup of Licensee Action on Previously Identified Findings,Followup of Allegation 88-A-01, Operational Safety Verification & Fire Protection IR 05000267/19880111988-05-25025 May 1988 Insp Rept 50-267/88-11 on 880425-29.Violations Noted.Major Areas Inspected:Emergency Response Program,Including Training,Emergency Facilities,Equipment,Instrumentation & Supplies IR 05000267/19880091988-05-13013 May 1988 Insp Rept 50-267/88-09 on 880411-15.No Violations or Deviations Noted.Major Areas Inspected:Licensee Chemistry/ Radiochemistry Program & Water Chemistry & Radiochemistry Confirmatory Measurements IR 05000267/19880071988-05-12012 May 1988 Insp Rept 50-267/88-07 on 880301-31.Violations Noted.Major Areas Inspected:Followup of Licensee Action on Previously Identified Findings,Operational Safety Verification,Review of 10CFR50.59 Safety Evaluations & Radiological Protection IR 05000267/19880081988-04-19019 April 1988 Insp Rept 50-267/88-08 on 880321-25.Violations Noted.Major Areas Inspected:Qa Program,Implementation of 10CFR21,LER Followup & Actions on Previous Insp Findings ML20151R7491988-04-0808 April 1988 Partially Withheld Insp Rept 50-267/88-05 on 880229-0304 (Ref 10CFR73.21).Major Areas Inspected:Insp of Previously Identified Items,Security Plan & Procedures,Security Organization,Locks,Keys & Combinations & Protected Areas IR 05000267/19880041988-03-30030 March 1988 Insp Rept 50-267/88-04 on 880222-26.No Violations or Deviations Noted.Major Areas Inspected:Fire Protection/ Prevention Program & Implementation IR 05000267/19880061988-03-25025 March 1988 Insp Rept 50-267/88-06 on 880229-0304.No Violations Noted. Major Areas Inspected:Licensee Actions Re IE Bulletin 85-003 ML20150F0081988-03-25025 March 1988 Insp Rept 50-267/88-03 on 880201-29.Violations Noted.Major Areas Inspected:Licensee Action on Previously Identified Findings,Operational Safety Verification,Followup of Unusual Events,Esf Walkdown & Physical Security Observation IR 05000267/19880021988-02-22022 February 1988 Insp Rept 50-267/88-02 on 880125-29.No Violations Noted. Major Areas Inspected:Changes to Emergency Plan,Shift Staffing & Augmentation,Knowledge & Performance of Duties & Operational Status of Emergency Preparedness Program IR 05000267/19880011988-02-16016 February 1988 Insp Rept 50-267/88-01 on 880101-31.No Violations or Deviations Noted.Major Areas Inspected:Operational Safety Verification,Followup of NRC Bulletin,Licensee Action on Lers,Core Safety Limit & Monthly Surveillance IR 05000267/19870341988-02-0202 February 1988 Insp Rept 50-267/87-34 on 871122-1231.Violations Noted. Major Areas Inspected:Operational Safety Verification, Followup of Allegation 4-86-A-119,followup of NRC Compliance Bulletin 87-002 & Monthly Security Observation ML20148T5801988-01-25025 January 1988 Insp Rept 50-267/87-32 on 871116-1204.No Violations or Deviations Noted.Major Areas Inspected:Fire Recovery Activities in Response to 871002 Fire 1990-08-03
[Table view] Category:TEXT-INSPECTION & AUDIT & I&E CIRCULARS
MONTHYEARIR 05000267/19970011997-04-0707 April 1997 Insp Rept 50-267/97-01 on 970310-11.No Violations Noted. Major Areas Inspected:Reviews of Status of Radiation Protection,Environ Monitoring & Radwaste Mgt Programs IR 05000267/19960051996-12-23023 December 1996 Insp Rept 50-267/96-05 on 961203-05.No Violations Noted. Major Areas Inspected:Access Licensees Implementation of Radiation Protection Program & Decommissioning Plan & Included Reviews of Status of Radiation Protection IR 05000267/19940031996-04-0202 April 1996 Revised NOV from Insp Rept 50-267/94-03.Violation Noted: Contractor to Licensee Submitted Inaccurate Radiation Surveys ML20136B3051996-04-0202 April 1996 Revised NOV from Insp Rept 50-267/94-03.Violation Noted: Numerous Required Records of Radiation Surveys Were Created Which Were Not Complete & Accurate ML20137H1731995-08-17017 August 1995 Investigation Rept 4-95-015.Noncompliance Noted.Major Areas Investigated:Alleged Deliberate Failure of Contract Employee to Perform Daily Response Checks on Portable Contamination Monitor ML20137K0551995-05-26026 May 1995 Investigation Rept 4-94-010 on 950526.No Noncompliance Noted.Major Areas Investigated:Allegations Re Falsification of Radiation Survey Records ML20058P5931993-10-12012 October 1993 EN-93-101:on 931012,notice of Proposed Imposition of Civil Penalty in Amount of $80,000 Issued to Licensee.Action Discussed in SECY-93-263 & Approved by Commission on 931007 ML20062H8191990-11-29029 November 1990 Notice of Violation from Insp on 901022-26.Violation Noted: Test of Protected Area Intrusion Detection Zones Defeated by Testing Personnel Jumping Over Zone IR 05000267/19900171990-11-29029 November 1990 Insp Rept 50-267/90-17 on 901001-1109.No Violations or Deviations Noted.Major Areas Inspected:Operational Safety, Monthly Surveillance & Maint Observation IR 05000267/19900181990-11-20020 November 1990 Partially Withheld Insp Rept 50-267/90-18 on 901022-26. Violation Noted.Major Areas Inspected:Physical Security Program,Including Protected & Vital Area Barriers,Detection & Assessment Aidscommunications,Testing,Packages & Maint IR 05000267/19900191990-11-16016 November 1990 Insp Rept 50-267/90-19 on 901015-19.No Violations or Deviations Noted.Areas Inspected:Stated Radiological Controls IR 05000267/19900201990-11-14014 November 1990 Insp Rept 50-267/90-20 on 901029-1102.Noncitable Violation Noted.Major Areas Inspected:Insp of Fire Protection/ Prevention Program ML20058E4951990-10-30030 October 1990 Notice of Violation from Insp on 900928.Violation Noted: Licensee Did Not Perform Radiation & Airborne Surveys Before Allowing Special Svcs Licensed Operator to Enter Hot Svc Facility to Remove Five Unshielded Radioactive Samples IR 05000267/19900141990-10-11011 October 1990 Insp Rept 50-267/90-14 on 900801-0930.No Violations or Deviations Noted IR 05000267/19900111990-08-15015 August 1990 Insp Rept 50-267/90-11 on 900601-0728.No Violations Noted. Major Areas Inspected:Onsite Followup of Ler,Operational Safety Verification,Monthly Maint Observation & Monthly Surveillance Observation IR 05000267/19900131990-08-0303 August 1990 Insp Rept 50-267/90-13 on 900709-13.No Violations or Deviations Noted.Major Areas Inspected:Emergency Preparedness Program Including Emergency Detection & Classification,Knowledge & Performance of Duties IR 05000267/19900101990-07-25025 July 1990 Insp Rept 50-267/90-10 on 900611-15.No Violations or Deviations Noted.Major Areas Inspected:Radioactive Matl Transportation Program,Liquid & Gaseous Radwaste Mgt Programs,Including Radiological Effluent Releases IR 05000267/19890191989-10-0202 October 1989 Insp Rept 50-267/89-19 on 890821-26 & 29-30.No Violations or Deviations Noted.Major Areas Inspected:Region 19 CRD Assembly Recovery Activities,Followup on Region 19 CRD Clevis Bolt Failures & Steam Generator Ring Header Problems ML20248B3051989-09-26026 September 1989 Notice of Violation from Insp on 890716-0831.Violation Noted:Four Reactor Engineers Worked on safety-related Test of Reactor Core Beyond Tech Specs Limit W/O Documented Authorization IR 05000267/19890161989-09-26026 September 1989 Insp Rept 50-267/89-16 on 890716-0831.Violation Noted.Major Areas Inspected:Onsite Followup of Ler,Followup on Violations,Followup of Open Item,Review of Part 21 Repts & Review of Licensee Action of Events PNO-IV-89-055, on 890829,Board of Directors Directed Termination of Nuclear Operations at Facility for 100-day Cooldown Period in Preparation for 30-month Reactor Defueling.Nrc Currently Reviewing Defueling Safety Analysis1989-08-29029 August 1989 PNO-IV-89-055:on 890829,Board of Directors Directed Termination of Nuclear Operations at Facility for 100-day Cooldown Period in Preparation for 30-month Reactor Defueling.Nrc Currently Reviewing Defueling Safety Analysis PNO-IV-89-052C, updates 890818,21 & 23 Unplanned Reactor Shutdowns Due to Inoperable Control Rod.Control Rod Assembly Will Be Removed Using Bldg Crane.Aluminum Shutter Will Be Remotely Placed on Bottom of Canister1989-08-25025 August 1989 PNO-IV-89-052C:updates 890818,21 & 23 Unplanned Reactor Shutdowns Due to Inoperable Control Rod.Control Rod Assembly Will Be Removed Using Bldg Crane.Aluminum Shutter Will Be Remotely Placed on Bottom of Canister PNO-IV-89-052B, on 890823,unplanned Reactor Shutdown Due to Inoperable Control Rod.Licensee Plans to Remove Control Rod Pair W/Bldg Crane in Unshielded Configuration to Shielded, Contained Evolution1989-08-23023 August 1989 PNO-IV-89-052B:on 890823,unplanned Reactor Shutdown Due to Inoperable Control Rod.Licensee Plans to Remove Control Rod Pair W/Bldg Crane in Unshielded Configuration to Shielded, Contained Evolution PNO-IV-89-052A, on 890818,after Attempting to Withdraw & Insert Control Rod Pair from Region 19,control Rod Motor Stopped Drawing Current & Indicated Open Conductor or Thermal Overload.Pair Will Be Withdrawn Using Bldg Crane1989-08-21021 August 1989 PNO-IV-89-052A:on 890818,after Attempting to Withdraw & Insert Control Rod Pair from Region 19,control Rod Motor Stopped Drawing Current & Indicated Open Conductor or Thermal Overload.Pair Will Be Withdrawn Using Bldg Crane ML20246E6011989-08-21021 August 1989 Notice of Violation from Insp on 890710-14.Violation Noted:From 890101-0712,only Three of Seven Shipments of Nonexempt Radioactive Matls Had Current License on File PNO-IV-89-052, on 890817,unplanned Reactor Shutdown Due to Inoperable Control Rod Drive Occurred.Attempts to Clear Cause of Slack Cable Light Failed.Loop 2 Shutdown Due to Upset in Bearing Water Sys Occurred During Plant Shutdown1989-08-18018 August 1989 PNO-IV-89-052:on 890817,unplanned Reactor Shutdown Due to Inoperable Control Rod Drive Occurred.Attempts to Clear Cause of Slack Cable Light Failed.Loop 2 Shutdown Due to Upset in Bearing Water Sys Occurred During Plant Shutdown IR 05000267/19890131989-08-16016 August 1989 Insp Rept 50-267/89-13 on 890626-30.Violation Noted.No Deviations Noted.Major Areas Inspected:Radwaste Sys IR 05000267/19890141989-08-15015 August 1989 Insp Rept 50-267/89-14 on 890710-14.Violation Noted.Major Areas Inspected:Radiation Protection Program ML20245J5721989-08-10010 August 1989 Notice of Violation from Insp on 890717-21.Violation Noted: Procedures Covering Timely Testing of Reactor Protection Sys Startup Channel & Periodic Test & Calibr of Diesel Engine Overspeed Trip for diesel-driven Fire Pump Not Established ML20245J5791989-08-10010 August 1989 Insp Rept 50-267/89-17 on 890717-21.Violations Noted.Major Areas Inspected:Licensee Programs for Instrument Calibr & Functional Testing of Diesel Fuel Oil Quality & Storage & Actions on Previously Identified Insp Findings ML20246A7061989-08-0909 August 1989 Exam Rept 50-267/OL 89-02 During Wk of 890710.Exam Results: Three of Four Limited Senior Reactor Operator Applicants Passed Exam.Answer Key Encl ML20245H3971989-08-0808 August 1989 Insp Rept 50-267/89-12 on 890601-0715.Violation Noted.Major Areas Inspected:Onsite Followup of Lers,Operational Safety Verification & Monthly Surveillance & Maint Observations ML20245H3941989-08-0808 August 1989 Notice of Violation from Insp on 890628.Violation Noted:On 890625,util Failed to Verify Positioning of HS-6335 to Tank 1 B,Resulting in Unanalyzed Gaseous Waste Release ML20248E0101989-08-0303 August 1989 Notice of Violation from Insp on 880522-26.Violations Noted: Inadequate Testing of cross-connect Valves Per Tech Spec SR 5.3.4 & Failure to Test High Flow Alarms Per Tech Spec SR 5.4.5 ML20248E0261989-08-0101 August 1989 Team Insp Rept 50-267/89-08 on 890522-26.Violations Noted. Major Areas Inspected:Maint Activities Re Reactor Water Cooling Sys (Sys 46) ML20247L6141989-07-14014 July 1989 Notice of Violation from Insp on 890623-27.Violation Noted: Failure to Provide Adequate Administrative Control of Plant Changes That Affect safety-related Plant Procedures IR 05000267/19890151989-07-11011 July 1989 Insp Rept 50-267/89-15 on 890623-27.Violation Noted.Major Areas Inspected:Circumstances & Events Associated W/ Operation of Facility Above Authorized Max Power Level of 82% of Full Power PNO-IV-89-044, on 890628,pressure in Waste Gas Receiver a Decreased from 250 Psig & Pressure in Receiver a Decreased from 60 to 50 Psig.Caused by Erroneous Valve Lineup.Plant Stack Monitors Did Not Alarm1989-06-28028 June 1989 PNO-IV-89-044:on 890628,pressure in Waste Gas Receiver a Decreased from 250 Psig & Pressure in Receiver a Decreased from 60 to 50 Psig.Caused by Erroneous Valve Lineup.Plant Stack Monitors Did Not Alarm PNO-IV-89-040, from 890622-23,power Exceeded 82% & Secondary Heat Balance Indication in Control Room Read Approx 79.2%.On 890623,discovered Incorrect Input Into Secondary Heat Balance Calculation.Power Reduced to 65% Pending Evaluation1989-06-23023 June 1989 PNO-IV-89-040:from 890622-23,power Exceeded 82% & Secondary Heat Balance Indication in Control Room Read Approx 79.2%.On 890623,discovered Incorrect Input Into Secondary Heat Balance Calculation.Power Reduced to 65% Pending Evaluation ML20245G4781989-06-22022 June 1989 Exam Rept 50-267/OL-9-01 on 890523-25.Exam Results:Two Senior Reactor Operator & Three Reactor Operator Candidates Passed All Portions of Exams & Issued Appropriate Licenses. One Reactor Operator Failed Written Exam IR 05000267/19890101989-06-15015 June 1989 Insp Rept 50-267/89-10 on 890501-31.No Violations Noted. Major Areas inspected:follow-up of Ler,Licensee Action on Previously Identified Insp Findings,Operational Safety Verification & Monthly Surveillance Observation ML20244C1271989-06-0808 June 1989 Notice of Violation from Insp on 890324-0430.Violations Noted:Two Examples of Failing to Comply W/Tech Spec Requirements & Inadequate Control of Replacement Parts for safety-related Equipment ML20244C1301989-06-0101 June 1989 Insp Rept 50-267/89-07 on 890319-0430.Violations Noted.Major Areas Inspected:Previously Identified Insp Findings, Operational Safety Verification,Monthly Surveillance Observation & Monthly Maint Observation PNO-IV-89-036, on 890529,two Teenagers Shot by off-duty Security Guard Following Confrontation Re Assault.Guard Arrested & Being Held for Murder.Licensee Plans to Issue Press Release.State of Co Will Be Informed.Record Copy1989-05-30030 May 1989 PNO-IV-89-036:on 890529,two Teenagers Shot by off-duty Security Guard Following Confrontation Re Assault.Guard Arrested & Being Held for Murder.Licensee Plans to Issue Press Release.State of Co Will Be Informed.Record Copy PNO-IV-89-031, on 890427,CRD 3 Failed to Insert on Scram During Performance of Weekly Partial Insertion Scram Tests. Troubleshooting Confirmed That CRD Brake Deenergized & That Rod Out Limit Cleared.Licensee Plans to Replace CRDs 3 & 71989-04-28028 April 1989 PNO-IV-89-031:on 890427,CRD 3 Failed to Insert on Scram During Performance of Weekly Partial Insertion Scram Tests. Troubleshooting Confirmed That CRD Brake Deenergized & That Rod Out Limit Cleared.Licensee Plans to Replace CRDs 3 & 7 IR 05000267/19890061989-04-24024 April 1989 Partially Withheld Insp Rept 50-267/89-06 on 890313-17 (Ref 10CFR73.21).Violation Noted.Major Areas Inspected:Physical Security Program,Including Mgt Support & Security Program Plan & Protected & Vital Area Barriers ML20245C8311989-04-14014 April 1989 Notice of Violation from Insp on 890217.Violation Noted: Stairway of Reactor Bldg Utilized by Potentially Contaminated Individuals Prior to Performing Whole Body Frisk & by Individuals Exiting Area After Frisking ML20245C8341989-04-13013 April 1989 Insp Rept 50-267/89-03 on 890201-0318.Violations Noted. Major Areas Inspected:Lers,Reserve Shutdown Matl Removal, Operational Safety Verification,Radiological Controls, Monthly Surveillance Observation & Maint Observation IR 05000267/19890051989-04-12012 April 1989 Insp Rept 50-267/89-05 on 890306-10 & 13-17.No Violations Noted.Major Areas Inspected:Previously Identified Insp Items,Surveillance Procedures & Records,Allegation Followup & Preparations for Refueling IR 05000267/19870351989-04-0707 April 1989 Final SALP Rept 50-267/87-35 for May 1987 - Aug 1988. Category 1 Assigned in Areas of Maint,Fire Protection & Radiological Controls 1997-04-07
[Table view] |
See also: IR 05000267/1989003
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' APPENDIX B
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LU.S. NUCLEhR REGULATORY COMMISSION
H REGION IV?
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NRC Inspection Report: 50-267/89-03- Operating License: DPR-34
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7 Docket: 50-267
'Licenseei Public Service Company of Colorado (PSC)
P.O. Box 840 v,.. ,
Denver, Colorado . 80210-0840:
.. Facility Name: Fort St. Vrain Nuclear Generating Station (FSV)
Inspection At: FSV, Platteville, Colorado
,. .. Inspection Conducted: LFebruary .1 through March 18, 1989
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, Inspectors: lR. E. Farrell, Senior Resident' Inspector (SRI)
P. W. Michaud,' Resident Inspector (RI)
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LApproved: *
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T. F. Westerman,. Chief, Project Section 8 Datfe
Division of Reactor Projects
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Inspection Summary
Inspection Conducted February 19through March 18, 1989 (Report 50-267/89-03)
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Areas Inspected: Routine,: unannounced inspection of onsite. followup of
licensee event reports-(LERs),_ reserve' shutdown material removal, operational-
safety verification, radiological controls,. monthly surveillance observation,
-monthly maintenance observation, and a coastdown and defueling' meeting.
Results: The licensee completed.the reserve shutdown material removal during
this inspection period. Several equipment malfunctions resulted in various
delays _during this effort, but support by all licensee organizations
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. contributed to the' completion of_this effort in as timely a manner as possible.
Numerous abnormal or first-time operations and configurations existed during
'this. inspection period. An appropriate-level of training, pre-job briefing,-
and monitoring contributed to-the. licensee's success in recovering from the
- inadvertent actuation of the reserve' shutdown system and the high moisture
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levels in the primary coolant.
One' violation was identified by the NRC resident inspectors (paragraph 6),
which involved incorrectly posted radiological boundaries. The licensee's
health' physics organization performed in an effective manner in support of
-numerous evolutions which included radiological. concerns, with the exception of
this: violation.
8904270410 89J414
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PDR ADOCK 05000267
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. .s The licensee's preventive maintenance program.was reviewed and found to contain
some improvements, but is still not existing at a level which is desirable.
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DETAILS
1. Persons Contacted
D.' Alps, Supervisor, Security
- M. Block, System Engineering Manager
- L. Brey,' Manager, Nuclear Licensing and Resources
- M. Coppello, Central Planning and Scheduling Manager
R. Craun, Nuclear Site Engineering Manager
, *D. Evans, Operations Manager
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- M. Ferris, QA Operations Manager
- C. Fuller, Manager, Nuclear Production
- B. Gares, Executive Secretary to Vice President, Nuclear Operations
- J. Gramling, Supervisor, Nuclear Licensing Operations
M. Holmes, Nuclear Licensing Manager
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- R. Hooper,' Nuclear Technical Training Supervisor i
- J. Johns, Supervisor, Nuclear Licensing Engineering 'j
M. Niehoff, Nuclear Design Manager '
F. Novachek, Nuclear Support Manager
- H. O'Hagan,' Outage Manager q
- J. Reesy, Nuclear Support Engineering Manager i
- D. Rodgers, Nuclear Computer Services Manager
- R. Sargent, Assistant to Vice President, Nuclear Operations
- L.. Scott, QA Services Manager
- V. Snyder, Maintenance Dept. Manager
- P. Tomlinson, Manager, Quality Assurance
- D. Warembourg, Manager, Nuclear Engineering
R. Williams, Jr. , Senior Vice President, Nuclear Operations l
The N9C inspectors also contacted other licensee and contractor personnel
during the inspection.
- Denotes those attending the exit interview conducted March 21, 1989.
2. Plant Status
The reactor remained shut down throughout this inspection period. The
licensee's efforts were directed towards recovery from the unplanned ;
actuation of the reserve shutdown material and the removal of moisture
from the reactor coolant system.
The reserve shutdown material removal effort was hampered with equipment
malfunctions, but was completed satisfactorily on March 2, 1989.
Moisture removal from the reactor coolant system was being accomplished by
an. evacuation of the prestressed concrete reactor vessel (PCRV) at the end
of the report period.
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3. Onsite Followup of Licen*ee Event Reports (LERs) (92700)
The NRC inspectors reviewed selected LERs to determine whether corrective
actions as stated in the LERs are appropriate to correct the cause of the
event and to verify these corrective actions have been implemented.
LER 87-15 reported a Loop 1 shutdown (ESF actuation) when the interlock
- - sequence switch (ISS)lwas moved from " Low Power" to " Power." The loop
shutdown was caused by an improper wiring configuration which provided a
trip signal to both "A"' and "B" Helium Circulator's logic circuitry when
the ISS was placed in the " Power" position. The improper wiring was a
result of incorrect electrical drawings which showed certain cables to be
determinate and some used as spares that actually were not. These
incorrect drawings were used to ground spare ccaductors to reduce
electrical noise during corrective actions in response to LER 86-28-1.
The licensee's investigation of the discrepancy between electrical
drawings and the as-found configuration concluded the cables in question
should have been, but apparently were not, determinate during original
plant construction. Corrective actions included determinating the two
conductors, which corrected the discrepancy with the electrical drawings
and also removed the false trip signal from the'"A" and "B" Helium
Circulator's logic circuitry. A special test (T-360) was also performed
prior to startup to ensure the plant protective system (PPS) had no
abnormal trip signals. These actions are acceptable to close this LER.
LER 87-22 reported a. loop shutdown (ESF actuation) with the reactor shut
down. This occurred during a surveillance test due to the failure of an
- electronic logic chip. The failed chip placed one logic channel in a trip
l condition. When a technician tripped another channel as part of the
surveillance test, the 2-of-3 logic was satisfied and caused a loop
shutdown. The failed logic chip was replaced and the surveillance test
was subsequently completed satisfactorily. The component failure resulted
in a conservative (trip) condition as designed, and thus did not present
an unanalyzed configuration. The licensee's corrective actions are
considered suffkient to close this LER.
LER 87-28 described a loss of offsite electrical power event during
performance of a postmaintenance test with the reactor shut down. The
postmaintenance test was to be performed on the reserve auxiliary
transformer (RAT) firewater deluge control relay. Part of the test
procedure included lifting leads so the RAT would not actually trip. The
procedure incorrectly epecified the leads to be lifted, and when the RAT
deluge system was actuated per the test procedure, the RAT breakers
tripped. The root cause of'this event was identified as personnel error
by the licensee, in that the test preparer specified incorrect leads to
disable the RAT trip function as intended. Additionally, administrative !
procedures did not require an independent review of postmaintenance test '
procedures. The licensee corrected the deficient test procedure and
reperformed it satisfactorily. The engineer involved was counseled on the
accuracy required of test procedures and the need to ensure erroneous
results of this sort are precluded. The licensee's Administrative
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Procedure SMAP-23, " Post Maintenance Testing,"; Issue 6, includes !
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Step 3.3.4, which requires an independent review for accuracy. These
actions provide a sufficient basis to close this LER.
LER 88-04 reported a manual reactor scram from 74 percent power due.to an
upset on the offsite electrical power grid. This grid disturbance caused ,
L several western power plants;ta shut down. The reactor operator manuallyJ
scrammed the reactor just "; the turbine automatically tripped due to load
swings. The plant subse b .1tly experienced an unplanned radioactive gas
release from the core support floor vent system, and a Notification of
Unusual Event was declared. The velease occurred when a safety valve in
the core support floor vent system lifted due to flow restrictions in the'
downstream' piping. The total activity released was approximately 15
percent of technical specification (TS) limits and resulted in a total
dose of 3.67 E-5 rem at 'the exclu: ion area boundary. The licensee
performed a special test (T-383), on the core support floor vent system
after cleaning strainers and replacing downstream filte,s. The results of
this test indicated the relief valve setpoint (5 psig) sas too low, and
that it should be changed to 10 psig. This setpoint '.nange was reviewed
by the NRC inspectors and verified to be acceptable, both for protecting
the-system from overpressurization and to provide a margin against
unplanned releases. -The new setpoint has been verified to be successful
in preventing unplanned releases from this path during subsequent reactor
shutdowns. Additionally, wiring deficiencies found in the turbine control
circuitry following this event have been corrected. This LER is closed.
LER 88 2 06 reported a manual scram actuation from 71 percent power when all
circulating water flow was lost. The loss of circulating water was due to.
an expansion joint failure on the "1A" Circulating Water Pump which
flooded the circulating water pump pit. The expansion joint failed due to
its age of approximately 15 years. The service life of these joints is
approximately 10 years. The root cause of this event was the lack of a
preventive maintenance program for rubber expansion joints. As a result
of 'this event, all eight expansion joints in the circulating water pump
pit were replaced. In addition, the licensee inspected and evaluated the
condition of all expansion joints in the plant. A number of expansion
joints have been replaced as a result of these inspections, including
those on tne condenser water boxes, diesel generator heat exchangers, and
condensate pumps. The licensee has developed and implemented a preventive
maintenance program for the inspection and periodic replacement of
expansion joints throughout the plant. These actions are sufficient to
close this LER.
4. Reserve Shutdown (RSD) Material Removal (6071(
The seven-region group of the RSD system was inadvertently inserted into
the reactor on January 19, 1989. The NRC inspectors closely monitored the
licensee's preparation and implementation of activities to remove the RSD
material'from the core.
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!Thehotservicefacility(HSF)wouldnormallyhavebeenutilizedtosetup
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,' the reserve shutdown vacuum tool. However, the HSF was configured for
control rod drive' refurbishment. Since it was' desirable to leave the HSF '
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.in.this configuration ,and with the fact that it would have taken 2 weeks
v .to' reconfigure the HSF, the licensee' decided to utilize the new fuel .
, loading' port (NFLP) to set up the RSD vacuum tool. A new Procedure,.
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! !MPF-1074, Issue 1, "In-Core Removal of RSD Material /NFLP," was written to
perform this evolution. . The'NRC inspectors reviewed this procedure and
found that it contained. adequate precautions and instructions.to ensure
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the, reactor was maintaird 'n refueling conditions and to specify
responsibilities of personnel involved in its use. Cetailed steps were-
- ' provided:to' move,sset.up, and tu t equipment. The licensee provided
, in-depth training on this procedure, as well as other procedures, and the
overall-scheme of the RSD removal operations. The NRC inspectors attended
two of these training'sessiont and found them to be well organized and
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informative.
The' vacuum tool consists of a 400 Hz motor attached to a vacuum impeller,
a hopper to collect the RSD material, and a suction probe to be inserted
into the RSD channel; all of which are housed inside the auxiliary
transfer cask'-(ATC). The ATC provides shielding for personnel and a
radiological boundary to handle control rod ~ drive and orifice assemblies
and the~ reserve shutdown vacuum tool. An external motor generator
provides' the 400 Hz power to the vacuum motor, and is connected via wiring
inside the ATC. . Because of the configuration, the. Vacuum motor has
minimal heat removal characteristics, and as such is limited to a 4 minute
duty' cycle which must be followed by a minimum 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> cooldown period.
The general sequence of activities to remove the RSD material for each of
the'seven affected regions was:
a. Perform a shutdown margin verification in accordance with Procedure
SR 4.1.6.c/d-x, '" Shutdown Margin Evaluation. for In-Core Maintenance."
b.- Retract the control rods and insert a rewind tool to hold them after
power is removed.
c. Install a reacter isolation valve (RIV).
d. Remove the control rod drive and orifice assembly (CRD0A) using the
ATC.
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e. Transf er and store the CRD0A in an equipment storage well.
f. Assemble the vacuum. tool, test, and place inside the ATC.
g. Move the ATC to the RIV, open the RIV and vacuum the RSD material ;
' from the region. This operation consists of lowering the vacuun
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probe until it contacts the_ RSD material (as indicated by a loss of
weight"from the ATC grapple), then energizing the vacuum motor and
slowly. lowering the probe into the RSD channel. When the end of the
probe-is approximately 6' inches from the bottom of the RSD channel, a
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mechanical stop prevents' further travel, and the probe is withdrawn
into the ATC.
h. . . Move the ATC to the NFLP, and extend and disconnect the probe and
vacuum tool.
i. Empty the vacuum tool hopper and weigh the RSD material to verify all
the material was removed.
j.- Install a refurbished CRDOA.into the region using the ATC.
The NRC~ inspectors attended shift briefings and observed good
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informational exchanges and overall coordination. Key personnel were
interviewed to ensure their understanding of their responsibilities, and
knowledge of procedures, administrative requirements, and actions to be
taken under unexpected or abnormal conditions. Management involvement was
observed throughout thisieffort. Overall, the RSD removal effort went
well, despite problems which occurred at various stages.
Following ex-core testing, the first attempt to vacuum RSD material on
February 5, 1989, was unsuccessful. Procedure MPF-1074 specified the
starting. current for the vacuum motor should decrease to less than 40 amps
within approximately 40 seconds. When it did not do so after 45 seconds,
the motor was deenergized. Investigation of the problem found wiring
damaged on the pigtail between the ATC grapple head and the vacuum motor.
In addition, external wiring on the ATC was.found to be damaged. This
wiring was repaired on February 9. ,As part of the troubleshooting to
determine the cause of the wiring damage, the 400 Hz motor generator was
tested separately and found to be defective. A new 400 Hz generator was
obtained, installed, and tested satisfactorily on February 13.
On February 14, the vacuuming effort was partially successful, but the l
probe stopped approximately 2 feet before it should have.' An
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investigation discovered the vacuum tool hopper / canister had a restriction
which prevented movement of the probe for the last 2 feet. This
restriction was relieved and the RSD material from Regions 5 and 22 l
was removed on February 15. Regions 3 and 34 were successfully vacuumed j
on February 17.
On February 19, while vacuuming RSD material from Region 28, the 400 Hz
-vacuum motor failed. The motor was disassembled and sent out for repair
on February 22. Alternate means of removing RSD material had been under 1
consideration from the outset. An auger was developed which was fairly
successful in shop tests, but which tended to grind the RSD balls together,
creating dust and other concerns. An external blower scheme was also
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developed which was similar to the existing vacuum tool, but utilizing an
external blower rather than a motor lowered into the reactor. This
external blower appeared to be a viable option and was reviewed by the NRC
. inspectors.
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l Controlled Work Procedure (CWP)89-050, "In-Core Removal of Reserve
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Shutdown Material with Roots Blower" was developed by the licensee. The I
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NRClinspectorsreviewedCWP89-050andtheassociated'designinformation
and safety evaluation. Concerns with this proposed method were discussed
with the licensee and resolved. However, the 400 Hz vacuum motor was
rebuilt and returned to the site before this alternate meth3d was
implemented. The existing vacuum tool was ceassembied and all.RSD
material was removed from the core on March 2.
A visual examination was made on the RSD material removed from each of the
seven regions. A sample from one high and one low boron
concentration material was sent offsite to be chemically analyzed for
leachable boron content, in accordance with TS 4.1.9 D.4. A visual
inspection of one RSD hopper was also performed.
Verification that'all RSD material had been removed from each of the seven
regions was accomplished by weighing the removed material and comparing it
to records of the weight of material which had been installed. A
tolerance of plus or minus 1 pound of material was developed and
documented in licensee Memo PPS-89-0433, dated February 3, 1989. The 1
pound tolerance was based on consideration of:
a. The accuracy and calibration of the scale used to weigh the material
b. Uncertainty over the accuracy of the original weights from records
c. Verification that sufficient material was inserted to fill the RSD
channel above the height of the active core
d. The amount of material which could be left in the core with no
significant effects on reactivity
e. Any effects on axial or radial power distribution that any material
left in the core would have
f. Assurance that a subsequent discharge of RSD material into the same
region would not overfill the RSD channel
The NRC inspectors reviewed the licensee's calculations and evaluation of
the 1 pound tolerance and found them acceptable.
The RSD material removal from six of the seven regions met this acceptance
criteria. However, the. material removed from Region 25 weighed 5 pounds
l more than that recorded as being loaded in 1985. Nonconformance Report
(NCR)89-050 was written to' address this discrepancy. The licensee's
evaluation and disposition of this NCR concluded that an error must have
been made during the loading in 1985 since there is no possible pathway
for RSD material to migrate from one region to another. The NRC I
-inspectors reviewed the licensee's actions in response to this NCR and l
found them acceptable. l
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No violations or. deviations were identified in the review of this program
area.
t 5. Operational Safety Verification (71707)
The NRC. inspectors made daily tours of the control room during normal
working hours and at least once per week during backshift hours. Control
room staffing was verified to be at the proper level for the plant
conditions at all times. Control room operators were observed to be
- ) attentive and aware of plant status and reasons why annunciators were lit.
- The.NRC inspectors observed the operators using and adhering to approved
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procedures in the performance of their duties. A sampling of these
procedures by the NRC inspectors verified current revisions and legible
copies. During control room tours, the NRC inspectors verified that the
required number of nuclear instrumentation and plant protective system
channels.were operable. The operability of emergency AC and DC electrical
power, meteorological, and fire protection systems was also verified by
the NRC inspectors. The reactor operators and shift supervisor logs were
reviewed daily, along with the TS compliance log, clearance. log,
operations deviation report (0DR) log, temporary configuration report
(TCR) log, end operations order book. Shift turnovers were observed at
least once per week by the NRC inspectors. Information flow was
consistently good, with the shift supervisors soliciting comments or
concerns from the reactor operators, equipment operators, auxiliary
tenders,.and health physics' technicians. The licensee's station manager,
operations manager, and superintendent of operations were observed to make j
routine tours of the control room.
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The NRC inspectors made tours of all accessible areas of the plant to j
assess the overall conditions and verify the adequacy of plant equipment,
radiciogical controls, and security. During these tours, particular 1
atter. tion was paid to the licensee's fire protection program, including j
fire extinguishers, fire fighting equipment, fire barriers, control of I
flammable materials, and other fire hazards. l
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A walkdown of the purge vacuum system, reactor building ventilation
system, reactor building area radiation monitoring system, control room
ventilation system, 480 VAC essential power distribution system, and
portions of the firewater system was performed by the NRC inspectors. I
These systems were selected because of their relation to work performed j
during various portions of the reserve shutdown material retrieval and '
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moisture removal efforts. Valve and breaker positions were verified,
where possible. When affected by a clearance, the valves or breakers were
, verified to be positioned in accordance with the clearance requirements.
Power supplies for components in these systems were verified, but were
also subject to clearances in some cases. During these system walkdowns,
the NRC inspectors verified the operability of standby or backup equipment
when components or portions of systems were inoperable due to clearances.
The NRC' inspectors reviewed seseral TCRs which were used to install
equipment in support of the outage recovery efforts. Proper reviews and
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approvals were verified for each TCR. Three of then TCRs were
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independently verified by the NRC inspectors:
TCR 89-01-01 installed a manometer on the refueling f;oor to read
reactor pressure under refueling conditions (subatmospheric),
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TCR 89-01-04 supplied power to the reserve shutdown vacuum motor l
generator from a spare breaker on Reactor Motor Control Center 5. l
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TCR 89-03-02 deenergized. rod position. indications so that oxidation
j of electrical connections for rods which were removed from the core
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would be minimized.
No discrepancies were noted during these walkdowns.
The licensee estimated that approximately 250 gallons of water' entered the
reactor coolant system through a leaking core support floor cooling water
tube. This tube was known to have a leak and was inadvertently left
unisolated during the reserve shutdown removal effort. The licensee
determined it would take approximately 2 months to remove this amount of
water through the purification system. In an effort to shorten the time
to remove the water, and the associated dates for criticality and
unrestricted operation, the licensee devised a setup to evacuate the PCRV.
This evacuation to as-close-to-full-vacuum-as-achievable, was calculated
to remove the water in approximately 1 to 2 weeks rather than 2 months
using the normal purification system lineup.
The system for evacuating the PCRV was designed and approved under Change
Notice (CN) 2916. The NRC inspectors reviewed this CN and the associated
safety evaluation in detail. The PCRV was designed for a vacuum pressure
of -12 psig as documented in FSAR Appendix E, Design Criteria DC-11-1.
Evacuation of the PCRV was previously accomplished ~in 1976 and 1982.
CN-2916 included temporary.and permanent modifications to evacuate the
PCRV through a refueling penetration, a cold trap to remove moisture, and
the installed purge vacuum pumps The discharge of the purge vacuum pumps
'was directed to the reactor building ventilation system which flows
through the reactor plant exhaust filters before exhausting through the
plant stack. An additional flowpath from another refueling penetration
to the reactor building ventilation system was used to initially draw a
vacuum on the PCRV, via a commercial blower, at a faster rate than possible
with the purge vacuum pumps. In addition, a separate cold trap and vacuum
pump was used to evacuate the core support floor (CSF) in order to minimize
the differential pressure between the CSF internals and the PCRV.
The NRC inspectors examined the licensee's design and analysis of the PCRV
evacuation process, paying particular attention to radiological concerns,
structural integrity concerns, instrumentation and monitoring issues, and
the potential effects of moisture saturated coolant on core components. .;
The radiological concerns are addressed in paragraph 6 of this report. 1
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The ~ structural effects of the' evacuation on the core support floor
p , concrete,. steel, vent system, and cooling water system were analyzed and
" documented. The effects on the'PCRV steel liner, primary closure, helium
qcirculator shutdown seals, PCRV rupture discs, and region isolation valve '
seals were also documented in the design analysis.
. .The design analysis for CN-2916 also considered'the effects of moisture on--
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control' rod drive-(CRD) and RSD system operability. With the PCRV at a
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, vacuum, purge flow-to the.CRDs had to be secured. The analysis considered
lthe' effects of: saturated vapor conditions on.these components for the 7
L days during which the PCRV was evacuated.
c The:11censee reviewed plant drawings and operating procedures, then walked
down systems which could have possibly been damaged.from evacuation of the,
PCRV to establish boundaries to isolate all affected instrumentation. All
piping subject to a vacuum was double isolated, and all critical
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instrumentation had process lines removed or vented in case of failure of
.the double valve isolation. The isolation' valves were positioned and
restored on an eight part clearance, which provided a means to return
essential equipment'to_ service more easily should,an emergency have
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occurred. The NRC~ inspectors reviewed l portions of these clearances and
found no' discrepancies.
The NRC inspectors also reviewed CWP 89-38, which provided instructions
for.the installation and removal of equipment to perform the PCRV
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evacuation. Temporary tie-ins for process flows, cooling water, and -
drains ^were described for the installed. purge. vacuum pumps, the core
support floor vacuum pump, and the commercial blower. The CWP was found
to contain sufficient steps,-adequate detail, and provisions for QC
' involvement, where required;
On March 12, 1989, the licensee entered a loss of forced circulation, with
- a calculated allowable time of,193.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> before forced circulation of
primary coolant.was- required. This provided a sufficient window in which
to perform the PCRV evacuation. The NRC. inspectors witnessed the initial
phase'of the evacuation, and subsequently' monitored its status. The PCRV
, evacuation proceeded smoothly, with approximately 180. gallons of water.
removed from the PCRV at the end of this inspection period. The NRC
s .< - ' inspectors will monitor the licensee's activities in completing the
evacuation'and restoring from it.
3
The NRC inspectors. randomly verified that the number of armed security
officers required by the security plan were present. A lead security
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officer was on duty to direct security activities on each shift. The NRC
inspectors verifled that search equipment, including an x-ray machine,
. explosive detector, and metal detector,'was operational or a 100 percent
hands-on search was conducted.
The protected area barrier was surveyed by the NRC inspectors to ensure it
.was not compromised by erosion or other objects. The NRC inspectors
, t observed that vital area barriers were well maintained and not '
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compromised. The NRC inspectors also observed that persons granted access
to the site were badged and visitors were properly escorted.
6. Radiological Controls (71707)
The NRC resident inspectors observed health physics technicians performing
surveys and checking air samplers and area radiation monitors.
Contamination levels and exposure rates were posted at entrances to
radiologically controlled areas and in other appropriate areas and were
verified to be up-to-date by the NRC inspectors. Health physics
technicians were present to provide assistance when workers were required
to enter radiologically controlled areas. The NRC inspectors observed
workers following the instructions on radiation work permits concerning
protective clothing and dosimetry, and observed workers using proper
procedures for contamination control including proper removal of
protective clothing and whole body frisking upon exiting a radiologically
controlled area.
During this report period, the licensee was involved in a number of
evolutions with radiological concerns. This provided the NRC inspectnrs
with an opportunity to observe the licensee's health physics department
dealing with moderately high contamination and radiation levels, which is
not a usual occurrence at Fort St. Vrain.
Work performed in support of the reserve shutdown material removal and the
evacuation of the PCRV involved direct communication with reactor
internals, with associated high radiation levels and handling of
contaminated equipment. The NRC inspectors observed thorough involvement
and preparations by the health physics department in all phases of these
evolutions. All personnel' involved were observed to adhere to
requirements of radiation work permits (RWPs). ' The NRC inspectors
reviewed several RWPs to assess their adequacy in relation to the area
involved and the work to be performed. These included:
RWP 10571 - Reserve Shutdown Work in the New Fuel Loading Port
.RWP 10576 - Maintenance in the Auxiliary Transfer Cask
RWP 10577 - Control Rod Drive Work in the Hot Service Facility
RWP 10578 - Decontaminate / Modify Refueling Sleeve
The overall radiological controls in support of evolutions during this
report period were good, though one instance of noncompliance was found by
the NRC resident inspectors. During the reserve shutdown removal effort,
the refueling floor (Level 11) was made a radiologically controlled area
(RCA), in order to control access. The entry point was established on
Level 10 at the south stairway to Level 11. Because of relatively high
background radiation levels and the licensee's desire to monitor for ;
potential contamination at the refueling floor, friskers were located at
the top of the stairs on Level 11. Personnel leaving the refueling floor
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frisked clean on Level'11, then walked down to Level 10', where they signed
out and exited the RCA. This arrangement was acceptable'but for the fact
that the NFLP access was located in the area between the access point on
Level 10 and the frisking station on Level 11. The NFLP was utilized for
emptying the reserva shutdown vacuum tool after removal of material from
the reactor. As such, the NFLP was a high contamination / airborne activity
area and was controlled under a separate RWP. Due to the high background
radiation levels at the access.to the NTLP, a'frisker could not be ;ocated
there. Thus, personnel exiting the NFLP. removed their protective clothing
at a step-off pad located at the NFLP access, then climbed the stairs to
Level 11 to use the friskers located there. The result was that
potentially contaminated individuals were traversing the same area which i
personnel who had frisked themselves clean were'using to exit the RCA.
This was brought to the licensee's attention and was corrected by locating i
the RCA access point at the north stairway between Levels 10 and 11. The
licensee was informed that the failure to' adequately establish and control
access to radiological contrcl areas and contaminated areas is an apparent
violation of NRC regulations (267/8903-01). >
7. Monthly Surveillance Observation (61726J
The NRC resident inspectors observed portions of surveillance testing in
support of the reserve shutdown material removal effort. The selected
surveillance procedures were reviewed for conformance with TS ,
requirements, in terms of LCOs and acceptability of results. ;
Administrative approvals and clearances when required were verified by the
NRC inspectors prior to test. initiation. Test equipment was erified to
be within its calibration cycle. Testing was performed by qualified
personnel in all cases. Portions of the following surveillance procedures
were observed by the NRC inspectors:
SR-MA-11-RX, Issue 1, " Reserve Shutdown Material Sample and Hopper
Inspection"
SR-RE-48-X, Issue 6, " Refueling - CRD Penetration Leakage Test"
SR-4.1.3.C-X, Issue 2, " Control Rod Drive and Orifice Operability"
SR-4.1.6.C/D-X, Issue 2, " Shutdown Margin Evaluation for In-Core
Maintenance"
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SR-4.1.9.D.3-RX, Issue 1, " Refueling Penetrations Piping Examination"
SR-4.1.9.D.4-RX, Issue 2, " Reserve Shutdown Hopper Functional Test"
SR-5.2.15-A, Issue 16, "PCRV Penetration Interspace Pressure
Calibration"
SR-5.2.28-62-R, Issue 6, "Holddown Plate Bolting Examination"
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No violations or devii ..os-were identified in the review of this j
-program area. j
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8. Monthly Maintenance Observation (62703) 1
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The NRC inspectors observed portions of numerous safety related
maintenance activities during this inspection period. Most of these
activities were related to the RSD material removal effort. During
observation of maintenance activities, the NRC inspectors verified
the licensee was at all times in compliance with TS LCOs and that
redundant components were operable as required. Activities were
accomplished by qualified personnel. utilizing approved procedures.
,
The activities observed and reviewert by the NRC inspectors included:
Operation of the reactor building crane in' accordance with Procedure
M0P-1001, Issue 5. <This crane was used' extensively in support of the
RSD removal effort. The procedure provides guidelines for
reoperation inspections in accordance wii.n ANSI B30.2 and NUREG 0612
as well as for operations involving heavy loads on the refueling
floor.
Operation of the auxiliary transfer cask'(ATC) in at cordance with
Procedure M0P-1006, Issue 1. The ATC provides shieldirg for
personnel and a radiological boundary to handle controi rod drive and
orifice assemblies and the reserve shutdown' vacuum tool. The
procedure provides precautions and instructions for handling of
various components, including expected weights of each.
Use and inspection of rigging' equipment in accordance with Procedure
M0P-1007, Issue 4.
Removal and replacement of equipment storage well covers in
accordance with Procedure MPF-1100, Issue 1.
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Removal and installation of control rod drive and orificing
assemblies (CRD0As) in accordance with Procedure MPF-1056, Issue 1.
This procedure provides instructions for moving a CRD0A with the ATC
between the PCRV, equipment storage wells, ar.d the hot service
facility.
Installation and renoval of shielding adapters in accordance with
Procedure MPF-1065. Issue 1. Shielding adapters provide personnel
shielding and a platform to mount the ATC on an equipment storage
well, hot service facility port, or the new fuel loading port.
Removal and insta)lation of reactor isolation valves (RIVs) in
accordance with Procedure MPF-1067, Issue 1, cnd operation of RIVs in
accordance with Procedure M0P-1009, Issue 1. RIVs provide personnel
shielding and a platform for mounting the ATC, fuel handling machine,
and primary seal cleaning equipment on the PCRV. These procedures
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provide prerequisites, precautions, and instructions for handling,
installation, removal, and operation of RIVs.
Removal and installation of PCRV top head holddown plates in
accordance with Procedure MPF-1091, Issue 2.
Removal and installation of' reactor penetration covers (secondary i
closures) in accordance with Procedure MPF-1094, Issue 1.
Removal and installation of helium purification train covers in
accordance with Procedure MPF-1095, Issue 1.
These activities were monitored by the NRC inspectors on a random basis
during this report period. Quality control and health physics involvement
in all phases of'these activities were observed by the NRC inspectors. No
discrepancies were noted during observations of the above activities.
During routine annual preventive maintenance on the "B" Diesel Generator,
the licensee discovered three cylinders on one engine (K-9206-X) with less
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than~ nominal, th'ough acceptable, characteristics.
On'Febfuary 27, 1989, the licensee began maintenance on this engine under
Station Service Request (SSR) 89500737. During disassembly, a metal
piec'e,.later determined to be a coolant flow director, was found in the
-engine coolant outlet plenum. An examination was made of the cylinder
. heads which had been removed for maintenance, and two coolant flow
directors were found to be missing. These coolant flow directors channel
flow to the center of a cylinder head to provide even heat removal
characteristics. Two nonconformance reports (NCRs) were written as a
result of these findings: NCRs 89-44 and 89-45. Because the type of
heads involved could not be distinguished from other installed heads, the
licensee decided to replace all 24 heads on all 4 diesel generator
engines. New heads were obtained for the "B" Diesel Generator's engines
and were installed and tested satisfactorily on March 13, 1989.
Replacement of the heads on tae "A" Diesel Generator's engines was in
process at the end of this report period and will be covered in a future
inspection report.
On March 15, 1989, the NRC inspector met with the licensee's maintenance
manager to review the licensee's preventive maintenant program. The
preventive maintenance program is described in Proce 9 e MAP-1, "FSV
Preventive Maintenance Program Description." The devc 3pment of specific
preventiva maintenance requirements is described in Procedure SMAP-27,
" Preventive and Corrective Maintenance Equipment Review." The NRC j
inspector reviewed the focus of these procedures with the licensee's :
maintenance manager. The development of maintenance procedures for larger
activities and standardized station service requests with controlled work
procedures for smaller activities was discussed in some detail.
Weaknesses in the maintenance procedures were attributed in many cases to
the inconsistencies inherent in having different individuals developing
varicus procedures. The preventive maintenance program has resulted in an
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overall: increase in the quality of maintenance procedures and consequently
the work product. Improvements in the. licensee's ability to complete J
, preventive maintenance as scheduled suggest the program is having some
success in shifting maintenance activities from a corrective focus to s
preventive program.
There are still some indications, however, that-the licensee's maintenance
program is not yet where it should be. One example of this was the
failure of Pressure Control Valve PCV-4256, which supplies a backup source
of cooling water from the firewater system to the emergency diese'
generators' engine and room coolers, as well as other components. i'is
valve had been leaking for over 2 years, causing the dow.1 stream relief
valve (V-4599) to weep whenever the firewater header was pressurized. On
March 16, 1989, PCV-4256' finally failed during performance of
SR-5.2.10.A.1-M, monthly firewater pump and instrumentation functional
test. The failure of PCV-4256 caused relief valve V-4599 to cycle
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' rapidly, which caused repeated water hammer vibrations in the turbi.e
building firewater header. .These' vibrations resulted in the failure of
the turbine lube oil reservoir room firevater deluge valve (HV-4507). The
vibrations caused the disc of HV-4507 to fail, spraying firewater into the
turbine lube oil reservoir room to a depth of approximately 6 inches
before the header was isolated. The licensee subsequently repaired Deluge
Valve HV-4507 and Pressure Control Valve PCV-4256.
No violations or deviations were identified in the review of this program
area.
9. Coastdown and Defueling Meeting (94702)
A meeting was held on March 7,1989 to discuss final coastdown operations
and defueling of Fort St. Vrain. This meeting was attended by the
licensee and their consultants, NRR, and Region IV. Coastdown issues
which were discussed included consideration of TS and FSAR limitations and
criteria, reactivity effects, and power peaking issues. The licensee
concluded operation during coastdown will be within the existing FSAR
analyses and TS limitations, and will present no unreviewed safety
questions. The licensee is scheduled to submit a coastdown safety j
analysis report to the NRC by May. 31, 1989. '
Various defueling plans and sequences were discussed, with emphasis on
reactivity control and monitoring, accident and safety analysis, and
computer modeling. The licensee has decided to defuel by regions in the l
reactor after considering the alternatives. This will include replacement !
of removed regions of fuel with boronated " dummy blocks" to maintain ]
structural integrity of the core during defueling. The defueling plan is l
scheduled to be submitted to the NRC by May 31, 1989. This plan will
include the defueling action plan, safety analysis report, and technical
specifications.
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10. ' Exit Meeting (30703)
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An exit meeting was conducted'on March 21, 1989, attended by those
. identified in paragraph 1. At this meeting, the NRC inspectors reviewed
2the scoperand findings of the inspection.
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