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Category:INSPECTION REPORT
MONTHYEARIR 05000312/19990031999-08-31031 August 1999 Insp Rept 50-312/99-03 on 990802-06.No Violations Noted. Major Areas Inspected:Decommissioning & Dismantlement Activities,Including Organization,Mgt & Cost Controls IR 05000312/19990021999-03-19019 March 1999 Insp Rept 50-312/99-02 on 990309-11.No Violations Noted. Major Areas Inspected:Licensee Physical Security Program, Including Access Authorization,Alarm Station & Communication & Testing & Maint IR 05000312/19980031998-08-0707 August 1998 Insp Rept 50-312/98-03 on 980706-09.No Violations Noted. Major Areas Inspected:Review of Licensee Programs Related to SFP Safety,Status of Decommissioning,Safety Review & self-assessments & Radiological Safety Programs IR 05000312/19980021998-06-0303 June 1998 Insp Rept 50-312/98-02 on 980519-21.Violations Noted. Major Areas Inspected:Announced Insp of Licensee Physical Security Program ML20202C4981998-02-0505 February 1998 Insp Rept 50-312/98-01 on 980105-08.Violations Noted.Major Areas Inspected:Organization,Mgt & Cost Controls,Maint & Surveillance,Cold Weather Preparation,Decommissioning Performance & Status Review & Health Physics IR 05000312/19970041997-10-21021 October 1997 Insp Rept 50-312/97-04 on 970922-25.Violations Noted. Major Areas Inspected:Organization,Mgt,Cost Control,Safety Reviews,Design Changes,Mods,Decommissioning Performance & Status Review IR 05000312/19970031997-06-17017 June 1997 Insp Rept 50-312/97-03 on 970603-05.No Violations Noted. Major Areas Inspected:Records & Repts,Testing & Maint, Protected Area Barrier & Detection Aids,Assessment Aids, Alarm Station & Communication & Security System IR 05000312/19970021997-04-25025 April 1997 Insp Rept 50-312/97-02 on 970331-0403.No Violations Noted. Major Areas Inspected:Incremental Decommissioning Activities in Turbine Bldg,Radiation Protection,Sfp Activities & Quality Assurance IR 05000312/19970011997-03-21021 March 1997 Insp Repts 50-312/97-01 & 72-0011/97-01 on 970224-27.No Violations Noted.Major Areas Inspected:Licensee Planned Work Associated W/Dismantlement of Turbine Bldg & Radiological Controls Being Implemented During Work Activities IR 05000312/19960031996-09-27027 September 1996 Insp Repts 50-312/96-03 & 72-0011/96-01 on 960909-12.No Violations Noted.Major Areas Inspected:Sfp & Radiological Ts,Radiological Exposure Controls & Implementation of New 10CFR49 Shipping Regulations IR 05000312/19930061993-09-0202 September 1993 Insp Rept 50-312/93-06 on 930819.No Violations or Deviations Noted.Major Areas Inspected:Licensee Employee Concerns Program IR 05000312/19930041993-08-11011 August 1993 Mgt Meeting Rept 50-312/93-04 on 930727.Major Areas Discussed:Status of Activities,Including Maint of Plant Equipment,Fire Protection Equipment & Plant Personnel Morale IR 05000312/19920071992-12-10010 December 1992 Insp Rept 50-312/92-07 on 921110-11.No Deviations or Violations Noted.Major Areas inspected:1992 Annual Emergency Preparedness Exercise & Associated Critiques & Inspector Identified Items IR 05000312/19900141990-11-14014 November 1990 Insp Rept 50-312/90-14 on 901003-04,09-11 & 1102.Violations Noted.Areas inspected:follow-up of Licensee Event Repts, Liquid Effluent,Solid Waste & Allegations IR 05000312/19900111990-07-31031 July 1990 Insp Rept 50-312/90-11 on 900527-0706.No Violations or Deviations Noted.Major Areas Inspected:Operational Safety Verification,Health Physics & Security Observations,Esf Sys Walkdown,Maint,Surveillance & Testing & QA IR 05000312/19890121989-09-21021 September 1989 Insp Rept 50-312/89-12 on 890801-04,21-25 & 30.No Violations Noted.Major Areas Inspected:Occupational Exposure,Including Alara,Radwaste Sys,Liquid & Liquid Wastes & Radwaste Mgt & Transportation IR 05000312/19890161989-09-21021 September 1989 Enforcement Conference Rept 50-312/89-16 on 890915. Violations Noted.Major Areas Discussed:Violations Noted in Insp Rept 50-312/89-16 & Indications That Findings Represent Decrease in Mgt Commitment to Emergency Preparedness IR 05000312/19890141989-09-11011 September 1989 Insp Rept 50-312/89-14 on 890828-0901.Violations Noted Re Failure to Conduct Required Semiannual Health Physics Drill & Initial Training.Major Areas Inspected:Operational Status of Emergency Preparedness Program IR 05000312/19890101989-08-10010 August 1989 Insp Rept 50-312/89-10 on 890603-0721.No Violations Noted. Major Areas Inspected:Areas of Operational Safety Verification,Health Physics & Security Observations,Maint, Surveillance & Testing & QA & Followup Items IR 05000312/19890081989-07-11011 July 1989 Insp Rept 50-312/89-08 on 890422-0602.No Violations or Deviations Noted.Two non-cited Violations Discussed.Major Areas Inspected:Operational Safety Verification,Health Physics & Security Observations & ESF Sys Walkdown IR 05000312/19890111989-07-0606 July 1989 Insp Rept 50-312/89-11 on 890629-30.No Violations Noted. Major Areas Inspected:Licensee Radiochemical Analyses to Verify Accuracy of Measurements of Radionuclides in Release Tank Water & Sediment from Effluent Discharge Point IR 05000312/19890071989-04-28028 April 1989 Insp Rept 50-312/89-07 on 890417-21.No Violations Noted. Major Areas Inspected:Previously Identified Items & Status of Emergency Preparedness Program IR 05000312/19890041989-03-31031 March 1989 Insp Rept 50-312/89-04 on 890114-0303.Violations Noted.Major Areas Inspected:Operational Safety Verification,Health Physics & Security Observations,Esf Sys Walkdown,Maint,Qa Surveillance & Testing & Followup Items ML20244B1161989-03-24024 March 1989 Insp Rept 50-312/89-01 on 890123-0217.Violations Noted.Major Areas Inspected:Maint Program & Implementation of Related Activities IR 05000312/19880411989-02-13013 February 1989 Insp Rept 50-312/88-41 on 881214-890103.No Violations Noted. Major Areas Inspected:Onsite Followup of Event of 881212 & Associated Mgt Meetings on 881219 & 890103.Weaknesses Observed Re Decision to Operate Plant in Degraded State IR 05000312/19880421989-02-13013 February 1989 Insp Rept 50-312/88-42 on 881227-30 & 890125-27.No Violations Noted.Major Areas Inspected:Followup Items,Part 21 Repts,Lers & Licensee Program to Maintain Quality of Diesel Generator Fuel Oil IR 05000312/19880401989-02-0606 February 1989 Insp Rept 50-312/88-40 on 881208-890113.No Violations or Deviations Noted.Major Areas Inspected:Operational Safety Verification,Health Physics & Security Observations,Esf Sys Walkdown,Maint,Qa & Surveillance & Testing IR 05000312/19880351988-11-21021 November 1988 Mgt Meeting Rept 50-312/88-35 on 881114.Major Areas Discussed:Licensee Operational Performance Since Restart in Mar 1988 & Progress Re Restart Commitments in Areas of Engineering,Procurement,Maint & Effluent Sys Areas IR 05000312/19880321988-10-25025 October 1988 Insp Rept 50-312/88-32 on 880919-1007.Violations Noted. Major Areas Inspected:Design Changes & Mods,Qa Audits,Pwr Moderator Dilution Requirements & Followup Items IR 05000312/19880301988-10-13013 October 1988 Insp Rept 50-312/88-30 on 880912-16.No Violations or Deviations Noted.Major Areas Inspected:Licensee Actions on Previous Insp Findings,Radioactive Liquid & Gaseous Waste & Review of Licensee Repts IR 05000312/19880271988-09-30030 September 1988 Insp Rept 50-312/88-27 on 880912-16.No Violations Noted. Major Areas Inspected:Licensee Conformance W/Rev 3 to Reg Guide 1.97.Rept Addresses & Closes Sims Issue Number 67.3.3 IR 05000312/19880231988-09-27027 September 1988 Insp Rept 50-312/88-23 on 880709-0906.Violations Noted. Major Areas Inspected:Operational Safety Verification, Health Physics & Security Observations,Esfs Sys Walkdown, Maint,Surveillance & Testing & Followup Items IR 05000312/19880261988-09-0909 September 1988 Enhanced Operational Insp Rept 50-312/88-26 on 880801-09.No Violations Noted.Major Areas Inspected:Plant Operation & Operational Support Activities ML20154H8171988-09-0101 September 1988 Insp Rept 50-312/88-25 on 880719-21.No Violations Noted. Major Areas Inspected:Exam of Emergency Facilities, Equipment & Emergency Preparedness Training ML20153E5081988-08-16016 August 1988 Insp Rept 50-312/88-24 on 880719-22.Violation Noted. Major Areas Inspected:Licensee Actions on Previous Insp Findings & Lers,External Exposure Control & Internal Exposure Control IR 05000312/19880161988-07-27027 July 1988 Insp Rept 50-312/88-16 on 880601-0708.No Violations or Deviations Noted.Major Areas Inspected:Operational Safety Verification,Health Physics & Security Observations,Esf Sys Walkdown,Maint & Surveillance & Testing IR 05000312/19880211988-07-27027 July 1988 Insp Rept 50-312/88-21 on 880711-15.No Violations or Deviations Noted.Major Areas Inspected:Licensee Action on Fastener Testing,Primary Coolant Sys Pressure Isolation Valves & Natural Circulation Cooldown ML20151W0871988-07-25025 July 1988 Insp Rept 50-312/88-02 on 880104-0309.Weaknesses Noted. Major Areas Inspected:Past & Present Procurement,Matls Control & Warehouse Activities Before Restart IR 05000312/19880191988-07-13013 July 1988 Enhanced Operational Insp Rept 50-312/88-19 on 880613-17. No Violations Noted.Major Areas Inspected:Plant Operation & Operational Support Activities IR 05000312/19880221988-07-13013 July 1988 Enforcement Conference Rept 50-312/88-22 on 880707.Major Areas Discussed:Implementation of Licensee Corrective Action to Improve Radiation Protection Program Following 880204 Incident When Individual Received Excess Radiation Exposure ML20150D9231988-06-24024 June 1988 Insp Rept 50-312/88-17 on 880606-10.Violations Noted.Major Areas Inspected:Licensee Action on Previous Insp Findings, Control of Radioactive Matls & Contamination,Alara, Facilities & Equipment & Review of Licensee Repts IR 05000312/19880151988-06-23023 June 1988 Insp Rept 50-312/88-15 on 880503-31.No Violations or Deviations Noted.Major Areas Inspected:Operational Safety Verification,Esf Sys Walkdown,Maint,Surveillance & Testing, Review of Control Rod Worth & Followup Items IR 05000312/19880201988-06-23023 June 1988 Insp Rept 50-312/88-20 on 880617.Violations Noted.Major Areas Inspected:Status of Unresolved Item 50-312/88-07-01 Re Skin Exposure of Worker Reported by Licensee on 880204 IR 05000312/19880121988-05-23023 May 1988 Insp Rept 50-312/88-12 on 880330-0502.Violations Noted.Major Areas Inspected:Operational Safety Verification,Maint, Surveillance & Followup Items IR 05000312/19880141988-05-19019 May 1988 Insp Rept 50-312/88-14 on 880425-28.No Violations or Deviations Noted.Major Areas Inspected:Licensee Plans for Coping W/Strikes & Nonlicensed Staff Training.Specific Weaknesses in Licensee Program Observed IR 05000312/19880131988-05-10010 May 1988 Insp Rept 50-312/88-13 on 880404-08 & 19.Violations Noted. Major Areas Inspected:Action on Previous Insp Findings,Solid Wastes,Transportation & Facility Tours IR 05000312/19880051988-05-10010 May 1988 Insp Rept 50-312/88-05 on 880204-0329.Violations Noted.Major Areas Inspected:Operational Safety Verification,Maint, Surveillance,Security & Health Physics Routine Modules & Followup Items IR 05000312/19880081988-04-21021 April 1988 Insp Rept 50-312/88-08 on 880307-22.Violations Noted.Major Areas Inspected:Licensee Capabilities for Mgt & Implementation of Effective Liquid & Gaseous Effluents Program After Restart IR 05000312/19880111988-04-20020 April 1988 Insp Rept 50-312/88-11 on 880317.No Violations Noted.Major Areas Inspected:Unusual Event on 880315 IR 05000312/19870401988-04-19019 April 1988 Insp Rept 50-312/87-40 on 871207-18 & 880208-17.Deficiencies Noted.Major Areas Inspected:Review of Licensee Readiness to Operate Facility,Including Functional Areas of Operations, Maint,Surveillance Testing & Design Change Control 1999-08-31
[Table view] Category:NRC-GENERATED
MONTHYEARIR 05000312/19990031999-08-31031 August 1999 Insp Rept 50-312/99-03 on 990802-06.No Violations Noted. Major Areas Inspected:Decommissioning & Dismantlement Activities,Including Organization,Mgt & Cost Controls IR 05000312/19990021999-03-19019 March 1999 Insp Rept 50-312/99-02 on 990309-11.No Violations Noted. Major Areas Inspected:Licensee Physical Security Program, Including Access Authorization,Alarm Station & Communication & Testing & Maint IR 05000312/19980031998-08-0707 August 1998 Insp Rept 50-312/98-03 on 980706-09.No Violations Noted. Major Areas Inspected:Review of Licensee Programs Related to SFP Safety,Status of Decommissioning,Safety Review & self-assessments & Radiological Safety Programs IR 05000312/19980021998-06-0303 June 1998 Insp Rept 50-312/98-02 on 980519-21.Violations Noted. Major Areas Inspected:Announced Insp of Licensee Physical Security Program ML20202C4981998-02-0505 February 1998 Insp Rept 50-312/98-01 on 980105-08.Violations Noted.Major Areas Inspected:Organization,Mgt & Cost Controls,Maint & Surveillance,Cold Weather Preparation,Decommissioning Performance & Status Review & Health Physics IR 05000312/19970041997-10-21021 October 1997 Insp Rept 50-312/97-04 on 970922-25.Violations Noted. Major Areas Inspected:Organization,Mgt,Cost Control,Safety Reviews,Design Changes,Mods,Decommissioning Performance & Status Review IR 05000312/19970031997-06-17017 June 1997 Insp Rept 50-312/97-03 on 970603-05.No Violations Noted. Major Areas Inspected:Records & Repts,Testing & Maint, Protected Area Barrier & Detection Aids,Assessment Aids, Alarm Station & Communication & Security System IR 05000312/19970021997-04-25025 April 1997 Insp Rept 50-312/97-02 on 970331-0403.No Violations Noted. Major Areas Inspected:Incremental Decommissioning Activities in Turbine Bldg,Radiation Protection,Sfp Activities & Quality Assurance IR 05000312/19970011997-03-21021 March 1997 Insp Repts 50-312/97-01 & 72-0011/97-01 on 970224-27.No Violations Noted.Major Areas Inspected:Licensee Planned Work Associated W/Dismantlement of Turbine Bldg & Radiological Controls Being Implemented During Work Activities IR 05000312/19960031996-09-27027 September 1996 Insp Repts 50-312/96-03 & 72-0011/96-01 on 960909-12.No Violations Noted.Major Areas Inspected:Sfp & Radiological Ts,Radiological Exposure Controls & Implementation of New 10CFR49 Shipping Regulations IR 05000312/19930061993-09-0202 September 1993 Insp Rept 50-312/93-06 on 930819.No Violations or Deviations Noted.Major Areas Inspected:Licensee Employee Concerns Program IR 05000312/19930041993-08-11011 August 1993 Mgt Meeting Rept 50-312/93-04 on 930727.Major Areas Discussed:Status of Activities,Including Maint of Plant Equipment,Fire Protection Equipment & Plant Personnel Morale IR 05000312/19920071992-12-10010 December 1992 Insp Rept 50-312/92-07 on 921110-11.No Deviations or Violations Noted.Major Areas inspected:1992 Annual Emergency Preparedness Exercise & Associated Critiques & Inspector Identified Items IR 05000312/19900141990-11-14014 November 1990 Insp Rept 50-312/90-14 on 901003-04,09-11 & 1102.Violations Noted.Areas inspected:follow-up of Licensee Event Repts, Liquid Effluent,Solid Waste & Allegations IR 05000312/19900111990-07-31031 July 1990 Insp Rept 50-312/90-11 on 900527-0706.No Violations or Deviations Noted.Major Areas Inspected:Operational Safety Verification,Health Physics & Security Observations,Esf Sys Walkdown,Maint,Surveillance & Testing & QA IR 05000312/19890121989-09-21021 September 1989 Insp Rept 50-312/89-12 on 890801-04,21-25 & 30.No Violations Noted.Major Areas Inspected:Occupational Exposure,Including Alara,Radwaste Sys,Liquid & Liquid Wastes & Radwaste Mgt & Transportation IR 05000312/19890161989-09-21021 September 1989 Enforcement Conference Rept 50-312/89-16 on 890915. Violations Noted.Major Areas Discussed:Violations Noted in Insp Rept 50-312/89-16 & Indications That Findings Represent Decrease in Mgt Commitment to Emergency Preparedness IR 05000312/19890141989-09-11011 September 1989 Insp Rept 50-312/89-14 on 890828-0901.Violations Noted Re Failure to Conduct Required Semiannual Health Physics Drill & Initial Training.Major Areas Inspected:Operational Status of Emergency Preparedness Program IR 05000312/19890101989-08-10010 August 1989 Insp Rept 50-312/89-10 on 890603-0721.No Violations Noted. Major Areas Inspected:Areas of Operational Safety Verification,Health Physics & Security Observations,Maint, Surveillance & Testing & QA & Followup Items IR 05000312/19890081989-07-11011 July 1989 Insp Rept 50-312/89-08 on 890422-0602.No Violations or Deviations Noted.Two non-cited Violations Discussed.Major Areas Inspected:Operational Safety Verification,Health Physics & Security Observations & ESF Sys Walkdown IR 05000312/19890111989-07-0606 July 1989 Insp Rept 50-312/89-11 on 890629-30.No Violations Noted. Major Areas Inspected:Licensee Radiochemical Analyses to Verify Accuracy of Measurements of Radionuclides in Release Tank Water & Sediment from Effluent Discharge Point IR 05000312/19890071989-04-28028 April 1989 Insp Rept 50-312/89-07 on 890417-21.No Violations Noted. Major Areas Inspected:Previously Identified Items & Status of Emergency Preparedness Program IR 05000312/19890041989-03-31031 March 1989 Insp Rept 50-312/89-04 on 890114-0303.Violations Noted.Major Areas Inspected:Operational Safety Verification,Health Physics & Security Observations,Esf Sys Walkdown,Maint,Qa Surveillance & Testing & Followup Items ML20244B1161989-03-24024 March 1989 Insp Rept 50-312/89-01 on 890123-0217.Violations Noted.Major Areas Inspected:Maint Program & Implementation of Related Activities IR 05000312/19880411989-02-13013 February 1989 Insp Rept 50-312/88-41 on 881214-890103.No Violations Noted. Major Areas Inspected:Onsite Followup of Event of 881212 & Associated Mgt Meetings on 881219 & 890103.Weaknesses Observed Re Decision to Operate Plant in Degraded State IR 05000312/19880421989-02-13013 February 1989 Insp Rept 50-312/88-42 on 881227-30 & 890125-27.No Violations Noted.Major Areas Inspected:Followup Items,Part 21 Repts,Lers & Licensee Program to Maintain Quality of Diesel Generator Fuel Oil IR 05000312/19880401989-02-0606 February 1989 Insp Rept 50-312/88-40 on 881208-890113.No Violations or Deviations Noted.Major Areas Inspected:Operational Safety Verification,Health Physics & Security Observations,Esf Sys Walkdown,Maint,Qa & Surveillance & Testing IR 05000312/19880351988-11-21021 November 1988 Mgt Meeting Rept 50-312/88-35 on 881114.Major Areas Discussed:Licensee Operational Performance Since Restart in Mar 1988 & Progress Re Restart Commitments in Areas of Engineering,Procurement,Maint & Effluent Sys Areas IR 05000312/19880321988-10-25025 October 1988 Insp Rept 50-312/88-32 on 880919-1007.Violations Noted. Major Areas Inspected:Design Changes & Mods,Qa Audits,Pwr Moderator Dilution Requirements & Followup Items IR 05000312/19880301988-10-13013 October 1988 Insp Rept 50-312/88-30 on 880912-16.No Violations or Deviations Noted.Major Areas Inspected:Licensee Actions on Previous Insp Findings,Radioactive Liquid & Gaseous Waste & Review of Licensee Repts IR 05000312/19880271988-09-30030 September 1988 Insp Rept 50-312/88-27 on 880912-16.No Violations Noted. Major Areas Inspected:Licensee Conformance W/Rev 3 to Reg Guide 1.97.Rept Addresses & Closes Sims Issue Number 67.3.3 IR 05000312/19880231988-09-27027 September 1988 Insp Rept 50-312/88-23 on 880709-0906.Violations Noted. Major Areas Inspected:Operational Safety Verification, Health Physics & Security Observations,Esfs Sys Walkdown, Maint,Surveillance & Testing & Followup Items IR 05000312/19880261988-09-0909 September 1988 Enhanced Operational Insp Rept 50-312/88-26 on 880801-09.No Violations Noted.Major Areas Inspected:Plant Operation & Operational Support Activities ML20154H8171988-09-0101 September 1988 Insp Rept 50-312/88-25 on 880719-21.No Violations Noted. Major Areas Inspected:Exam of Emergency Facilities, Equipment & Emergency Preparedness Training ML20153E5081988-08-16016 August 1988 Insp Rept 50-312/88-24 on 880719-22.Violation Noted. Major Areas Inspected:Licensee Actions on Previous Insp Findings & Lers,External Exposure Control & Internal Exposure Control IR 05000312/19880161988-07-27027 July 1988 Insp Rept 50-312/88-16 on 880601-0708.No Violations or Deviations Noted.Major Areas Inspected:Operational Safety Verification,Health Physics & Security Observations,Esf Sys Walkdown,Maint & Surveillance & Testing IR 05000312/19880211988-07-27027 July 1988 Insp Rept 50-312/88-21 on 880711-15.No Violations or Deviations Noted.Major Areas Inspected:Licensee Action on Fastener Testing,Primary Coolant Sys Pressure Isolation Valves & Natural Circulation Cooldown ML20151W0871988-07-25025 July 1988 Insp Rept 50-312/88-02 on 880104-0309.Weaknesses Noted. Major Areas Inspected:Past & Present Procurement,Matls Control & Warehouse Activities Before Restart IR 05000312/19880191988-07-13013 July 1988 Enhanced Operational Insp Rept 50-312/88-19 on 880613-17. No Violations Noted.Major Areas Inspected:Plant Operation & Operational Support Activities IR 05000312/19880221988-07-13013 July 1988 Enforcement Conference Rept 50-312/88-22 on 880707.Major Areas Discussed:Implementation of Licensee Corrective Action to Improve Radiation Protection Program Following 880204 Incident When Individual Received Excess Radiation Exposure ML20150D9231988-06-24024 June 1988 Insp Rept 50-312/88-17 on 880606-10.Violations Noted.Major Areas Inspected:Licensee Action on Previous Insp Findings, Control of Radioactive Matls & Contamination,Alara, Facilities & Equipment & Review of Licensee Repts IR 05000312/19880151988-06-23023 June 1988 Insp Rept 50-312/88-15 on 880503-31.No Violations or Deviations Noted.Major Areas Inspected:Operational Safety Verification,Esf Sys Walkdown,Maint,Surveillance & Testing, Review of Control Rod Worth & Followup Items IR 05000312/19880201988-06-23023 June 1988 Insp Rept 50-312/88-20 on 880617.Violations Noted.Major Areas Inspected:Status of Unresolved Item 50-312/88-07-01 Re Skin Exposure of Worker Reported by Licensee on 880204 IR 05000312/19880121988-05-23023 May 1988 Insp Rept 50-312/88-12 on 880330-0502.Violations Noted.Major Areas Inspected:Operational Safety Verification,Maint, Surveillance & Followup Items IR 05000312/19880141988-05-19019 May 1988 Insp Rept 50-312/88-14 on 880425-28.No Violations or Deviations Noted.Major Areas Inspected:Licensee Plans for Coping W/Strikes & Nonlicensed Staff Training.Specific Weaknesses in Licensee Program Observed IR 05000312/19880131988-05-10010 May 1988 Insp Rept 50-312/88-13 on 880404-08 & 19.Violations Noted. Major Areas Inspected:Action on Previous Insp Findings,Solid Wastes,Transportation & Facility Tours IR 05000312/19880051988-05-10010 May 1988 Insp Rept 50-312/88-05 on 880204-0329.Violations Noted.Major Areas Inspected:Operational Safety Verification,Maint, Surveillance,Security & Health Physics Routine Modules & Followup Items IR 05000312/19880081988-04-21021 April 1988 Insp Rept 50-312/88-08 on 880307-22.Violations Noted.Major Areas Inspected:Licensee Capabilities for Mgt & Implementation of Effective Liquid & Gaseous Effluents Program After Restart IR 05000312/19880111988-04-20020 April 1988 Insp Rept 50-312/88-11 on 880317.No Violations Noted.Major Areas Inspected:Unusual Event on 880315 IR 05000312/19870401988-04-19019 April 1988 Insp Rept 50-312/87-40 on 871207-18 & 880208-17.Deficiencies Noted.Major Areas Inspected:Review of Licensee Readiness to Operate Facility,Including Functional Areas of Operations, Maint,Surveillance Testing & Design Change Control 1999-08-31
[Table view] Category:INSPECTION REPORT
MONTHYEARIR 05000312/19990031999-08-31031 August 1999 Insp Rept 50-312/99-03 on 990802-06.No Violations Noted. Major Areas Inspected:Decommissioning & Dismantlement Activities,Including Organization,Mgt & Cost Controls IR 05000312/19990021999-03-19019 March 1999 Insp Rept 50-312/99-02 on 990309-11.No Violations Noted. Major Areas Inspected:Licensee Physical Security Program, Including Access Authorization,Alarm Station & Communication & Testing & Maint IR 05000312/19980031998-08-0707 August 1998 Insp Rept 50-312/98-03 on 980706-09.No Violations Noted. Major Areas Inspected:Review of Licensee Programs Related to SFP Safety,Status of Decommissioning,Safety Review & self-assessments & Radiological Safety Programs IR 05000312/19980021998-06-0303 June 1998 Insp Rept 50-312/98-02 on 980519-21.Violations Noted. Major Areas Inspected:Announced Insp of Licensee Physical Security Program ML20202C4981998-02-0505 February 1998 Insp Rept 50-312/98-01 on 980105-08.Violations Noted.Major Areas Inspected:Organization,Mgt & Cost Controls,Maint & Surveillance,Cold Weather Preparation,Decommissioning Performance & Status Review & Health Physics IR 05000312/19970041997-10-21021 October 1997 Insp Rept 50-312/97-04 on 970922-25.Violations Noted. Major Areas Inspected:Organization,Mgt,Cost Control,Safety Reviews,Design Changes,Mods,Decommissioning Performance & Status Review IR 05000312/19970031997-06-17017 June 1997 Insp Rept 50-312/97-03 on 970603-05.No Violations Noted. Major Areas Inspected:Records & Repts,Testing & Maint, Protected Area Barrier & Detection Aids,Assessment Aids, Alarm Station & Communication & Security System IR 05000312/19970021997-04-25025 April 1997 Insp Rept 50-312/97-02 on 970331-0403.No Violations Noted. Major Areas Inspected:Incremental Decommissioning Activities in Turbine Bldg,Radiation Protection,Sfp Activities & Quality Assurance IR 05000312/19970011997-03-21021 March 1997 Insp Repts 50-312/97-01 & 72-0011/97-01 on 970224-27.No Violations Noted.Major Areas Inspected:Licensee Planned Work Associated W/Dismantlement of Turbine Bldg & Radiological Controls Being Implemented During Work Activities IR 05000312/19960031996-09-27027 September 1996 Insp Repts 50-312/96-03 & 72-0011/96-01 on 960909-12.No Violations Noted.Major Areas Inspected:Sfp & Radiological Ts,Radiological Exposure Controls & Implementation of New 10CFR49 Shipping Regulations IR 05000312/19930061993-09-0202 September 1993 Insp Rept 50-312/93-06 on 930819.No Violations or Deviations Noted.Major Areas Inspected:Licensee Employee Concerns Program IR 05000312/19930041993-08-11011 August 1993 Mgt Meeting Rept 50-312/93-04 on 930727.Major Areas Discussed:Status of Activities,Including Maint of Plant Equipment,Fire Protection Equipment & Plant Personnel Morale IR 05000312/19920071992-12-10010 December 1992 Insp Rept 50-312/92-07 on 921110-11.No Deviations or Violations Noted.Major Areas inspected:1992 Annual Emergency Preparedness Exercise & Associated Critiques & Inspector Identified Items IR 05000312/19900141990-11-14014 November 1990 Insp Rept 50-312/90-14 on 901003-04,09-11 & 1102.Violations Noted.Areas inspected:follow-up of Licensee Event Repts, Liquid Effluent,Solid Waste & Allegations IR 05000312/19900111990-07-31031 July 1990 Insp Rept 50-312/90-11 on 900527-0706.No Violations or Deviations Noted.Major Areas Inspected:Operational Safety Verification,Health Physics & Security Observations,Esf Sys Walkdown,Maint,Surveillance & Testing & QA IR 05000312/19890121989-09-21021 September 1989 Insp Rept 50-312/89-12 on 890801-04,21-25 & 30.No Violations Noted.Major Areas Inspected:Occupational Exposure,Including Alara,Radwaste Sys,Liquid & Liquid Wastes & Radwaste Mgt & Transportation IR 05000312/19890161989-09-21021 September 1989 Enforcement Conference Rept 50-312/89-16 on 890915. Violations Noted.Major Areas Discussed:Violations Noted in Insp Rept 50-312/89-16 & Indications That Findings Represent Decrease in Mgt Commitment to Emergency Preparedness IR 05000312/19890141989-09-11011 September 1989 Insp Rept 50-312/89-14 on 890828-0901.Violations Noted Re Failure to Conduct Required Semiannual Health Physics Drill & Initial Training.Major Areas Inspected:Operational Status of Emergency Preparedness Program IR 05000312/19890101989-08-10010 August 1989 Insp Rept 50-312/89-10 on 890603-0721.No Violations Noted. Major Areas Inspected:Areas of Operational Safety Verification,Health Physics & Security Observations,Maint, Surveillance & Testing & QA & Followup Items IR 05000312/19890081989-07-11011 July 1989 Insp Rept 50-312/89-08 on 890422-0602.No Violations or Deviations Noted.Two non-cited Violations Discussed.Major Areas Inspected:Operational Safety Verification,Health Physics & Security Observations & ESF Sys Walkdown IR 05000312/19890111989-07-0606 July 1989 Insp Rept 50-312/89-11 on 890629-30.No Violations Noted. Major Areas Inspected:Licensee Radiochemical Analyses to Verify Accuracy of Measurements of Radionuclides in Release Tank Water & Sediment from Effluent Discharge Point IR 05000312/19890071989-04-28028 April 1989 Insp Rept 50-312/89-07 on 890417-21.No Violations Noted. Major Areas Inspected:Previously Identified Items & Status of Emergency Preparedness Program IR 05000312/19890041989-03-31031 March 1989 Insp Rept 50-312/89-04 on 890114-0303.Violations Noted.Major Areas Inspected:Operational Safety Verification,Health Physics & Security Observations,Esf Sys Walkdown,Maint,Qa Surveillance & Testing & Followup Items ML20244B1161989-03-24024 March 1989 Insp Rept 50-312/89-01 on 890123-0217.Violations Noted.Major Areas Inspected:Maint Program & Implementation of Related Activities IR 05000312/19880411989-02-13013 February 1989 Insp Rept 50-312/88-41 on 881214-890103.No Violations Noted. Major Areas Inspected:Onsite Followup of Event of 881212 & Associated Mgt Meetings on 881219 & 890103.Weaknesses Observed Re Decision to Operate Plant in Degraded State IR 05000312/19880421989-02-13013 February 1989 Insp Rept 50-312/88-42 on 881227-30 & 890125-27.No Violations Noted.Major Areas Inspected:Followup Items,Part 21 Repts,Lers & Licensee Program to Maintain Quality of Diesel Generator Fuel Oil IR 05000312/19880401989-02-0606 February 1989 Insp Rept 50-312/88-40 on 881208-890113.No Violations or Deviations Noted.Major Areas Inspected:Operational Safety Verification,Health Physics & Security Observations,Esf Sys Walkdown,Maint,Qa & Surveillance & Testing IR 05000312/19880351988-11-21021 November 1988 Mgt Meeting Rept 50-312/88-35 on 881114.Major Areas Discussed:Licensee Operational Performance Since Restart in Mar 1988 & Progress Re Restart Commitments in Areas of Engineering,Procurement,Maint & Effluent Sys Areas IR 05000312/19880321988-10-25025 October 1988 Insp Rept 50-312/88-32 on 880919-1007.Violations Noted. Major Areas Inspected:Design Changes & Mods,Qa Audits,Pwr Moderator Dilution Requirements & Followup Items IR 05000312/19880301988-10-13013 October 1988 Insp Rept 50-312/88-30 on 880912-16.No Violations or Deviations Noted.Major Areas Inspected:Licensee Actions on Previous Insp Findings,Radioactive Liquid & Gaseous Waste & Review of Licensee Repts IR 05000312/19880271988-09-30030 September 1988 Insp Rept 50-312/88-27 on 880912-16.No Violations Noted. Major Areas Inspected:Licensee Conformance W/Rev 3 to Reg Guide 1.97.Rept Addresses & Closes Sims Issue Number 67.3.3 IR 05000312/19880231988-09-27027 September 1988 Insp Rept 50-312/88-23 on 880709-0906.Violations Noted. Major Areas Inspected:Operational Safety Verification, Health Physics & Security Observations,Esfs Sys Walkdown, Maint,Surveillance & Testing & Followup Items IR 05000312/19880261988-09-0909 September 1988 Enhanced Operational Insp Rept 50-312/88-26 on 880801-09.No Violations Noted.Major Areas Inspected:Plant Operation & Operational Support Activities ML20154H8171988-09-0101 September 1988 Insp Rept 50-312/88-25 on 880719-21.No Violations Noted. Major Areas Inspected:Exam of Emergency Facilities, Equipment & Emergency Preparedness Training ML20153E5081988-08-16016 August 1988 Insp Rept 50-312/88-24 on 880719-22.Violation Noted. Major Areas Inspected:Licensee Actions on Previous Insp Findings & Lers,External Exposure Control & Internal Exposure Control IR 05000312/19880161988-07-27027 July 1988 Insp Rept 50-312/88-16 on 880601-0708.No Violations or Deviations Noted.Major Areas Inspected:Operational Safety Verification,Health Physics & Security Observations,Esf Sys Walkdown,Maint & Surveillance & Testing IR 05000312/19880211988-07-27027 July 1988 Insp Rept 50-312/88-21 on 880711-15.No Violations or Deviations Noted.Major Areas Inspected:Licensee Action on Fastener Testing,Primary Coolant Sys Pressure Isolation Valves & Natural Circulation Cooldown ML20151W0871988-07-25025 July 1988 Insp Rept 50-312/88-02 on 880104-0309.Weaknesses Noted. Major Areas Inspected:Past & Present Procurement,Matls Control & Warehouse Activities Before Restart IR 05000312/19880191988-07-13013 July 1988 Enhanced Operational Insp Rept 50-312/88-19 on 880613-17. No Violations Noted.Major Areas Inspected:Plant Operation & Operational Support Activities IR 05000312/19880221988-07-13013 July 1988 Enforcement Conference Rept 50-312/88-22 on 880707.Major Areas Discussed:Implementation of Licensee Corrective Action to Improve Radiation Protection Program Following 880204 Incident When Individual Received Excess Radiation Exposure ML20150D9231988-06-24024 June 1988 Insp Rept 50-312/88-17 on 880606-10.Violations Noted.Major Areas Inspected:Licensee Action on Previous Insp Findings, Control of Radioactive Matls & Contamination,Alara, Facilities & Equipment & Review of Licensee Repts IR 05000312/19880151988-06-23023 June 1988 Insp Rept 50-312/88-15 on 880503-31.No Violations or Deviations Noted.Major Areas Inspected:Operational Safety Verification,Esf Sys Walkdown,Maint,Surveillance & Testing, Review of Control Rod Worth & Followup Items IR 05000312/19880201988-06-23023 June 1988 Insp Rept 50-312/88-20 on 880617.Violations Noted.Major Areas Inspected:Status of Unresolved Item 50-312/88-07-01 Re Skin Exposure of Worker Reported by Licensee on 880204 IR 05000312/19880121988-05-23023 May 1988 Insp Rept 50-312/88-12 on 880330-0502.Violations Noted.Major Areas Inspected:Operational Safety Verification,Maint, Surveillance & Followup Items IR 05000312/19880141988-05-19019 May 1988 Insp Rept 50-312/88-14 on 880425-28.No Violations or Deviations Noted.Major Areas Inspected:Licensee Plans for Coping W/Strikes & Nonlicensed Staff Training.Specific Weaknesses in Licensee Program Observed IR 05000312/19880131988-05-10010 May 1988 Insp Rept 50-312/88-13 on 880404-08 & 19.Violations Noted. Major Areas Inspected:Action on Previous Insp Findings,Solid Wastes,Transportation & Facility Tours IR 05000312/19880051988-05-10010 May 1988 Insp Rept 50-312/88-05 on 880204-0329.Violations Noted.Major Areas Inspected:Operational Safety Verification,Maint, Surveillance,Security & Health Physics Routine Modules & Followup Items IR 05000312/19880081988-04-21021 April 1988 Insp Rept 50-312/88-08 on 880307-22.Violations Noted.Major Areas Inspected:Licensee Capabilities for Mgt & Implementation of Effective Liquid & Gaseous Effluents Program After Restart IR 05000312/19880111988-04-20020 April 1988 Insp Rept 50-312/88-11 on 880317.No Violations Noted.Major Areas Inspected:Unusual Event on 880315 IR 05000312/19870401988-04-19019 April 1988 Insp Rept 50-312/87-40 on 871207-18 & 880208-17.Deficiencies Noted.Major Areas Inspected:Review of Licensee Readiness to Operate Facility,Including Functional Areas of Operations, Maint,Surveillance Testing & Design Change Control 1999-08-31
[Table view] Category:UTILITY
MONTHYEARIR 05000312/19900111990-07-31031 July 1990 Insp Rept 50-312/90-11 on 900527-0706.No Violations or Deviations Noted.Major Areas Inspected:Operational Safety Verification,Health Physics & Security Observations,Esf Sys Walkdown,Maint,Surveillance & Testing & QA IR 05000312/19890121989-09-21021 September 1989 Insp Rept 50-312/89-12 on 890801-04,21-25 & 30.No Violations Noted.Major Areas Inspected:Occupational Exposure,Including Alara,Radwaste Sys,Liquid & Liquid Wastes & Radwaste Mgt & Transportation IR 05000312/19890161989-09-21021 September 1989 Enforcement Conference Rept 50-312/89-16 on 890915. Violations Noted.Major Areas Discussed:Violations Noted in Insp Rept 50-312/89-16 & Indications That Findings Represent Decrease in Mgt Commitment to Emergency Preparedness IR 05000312/19890141989-09-11011 September 1989 Insp Rept 50-312/89-14 on 890828-0901.Violations Noted Re Failure to Conduct Required Semiannual Health Physics Drill & Initial Training.Major Areas Inspected:Operational Status of Emergency Preparedness Program IR 05000312/19890101989-08-10010 August 1989 Insp Rept 50-312/89-10 on 890603-0721.No Violations Noted. Major Areas Inspected:Areas of Operational Safety Verification,Health Physics & Security Observations,Maint, Surveillance & Testing & QA & Followup Items IR 05000312/19890081989-07-11011 July 1989 Insp Rept 50-312/89-08 on 890422-0602.No Violations or Deviations Noted.Two non-cited Violations Discussed.Major Areas Inspected:Operational Safety Verification,Health Physics & Security Observations & ESF Sys Walkdown IR 05000312/19890111989-07-0606 July 1989 Insp Rept 50-312/89-11 on 890629-30.No Violations Noted. Major Areas Inspected:Licensee Radiochemical Analyses to Verify Accuracy of Measurements of Radionuclides in Release Tank Water & Sediment from Effluent Discharge Point IR 05000312/19890071989-04-28028 April 1989 Insp Rept 50-312/89-07 on 890417-21.No Violations Noted. Major Areas Inspected:Previously Identified Items & Status of Emergency Preparedness Program IR 05000312/19890041989-03-31031 March 1989 Insp Rept 50-312/89-04 on 890114-0303.Violations Noted.Major Areas Inspected:Operational Safety Verification,Health Physics & Security Observations,Esf Sys Walkdown,Maint,Qa Surveillance & Testing & Followup Items ML20244B1161989-03-24024 March 1989 Insp Rept 50-312/89-01 on 890123-0217.Violations Noted.Major Areas Inspected:Maint Program & Implementation of Related Activities IR 05000312/19880421989-02-13013 February 1989 Insp Rept 50-312/88-42 on 881227-30 & 890125-27.No Violations Noted.Major Areas Inspected:Followup Items,Part 21 Repts,Lers & Licensee Program to Maintain Quality of Diesel Generator Fuel Oil IR 05000312/19880411989-02-13013 February 1989 Insp Rept 50-312/88-41 on 881214-890103.No Violations Noted. Major Areas Inspected:Onsite Followup of Event of 881212 & Associated Mgt Meetings on 881219 & 890103.Weaknesses Observed Re Decision to Operate Plant in Degraded State IR 05000312/19880401989-02-0606 February 1989 Insp Rept 50-312/88-40 on 881208-890113.No Violations or Deviations Noted.Major Areas Inspected:Operational Safety Verification,Health Physics & Security Observations,Esf Sys Walkdown,Maint,Qa & Surveillance & Testing IR 05000312/19880351988-11-21021 November 1988 Mgt Meeting Rept 50-312/88-35 on 881114.Major Areas Discussed:Licensee Operational Performance Since Restart in Mar 1988 & Progress Re Restart Commitments in Areas of Engineering,Procurement,Maint & Effluent Sys Areas IR 05000312/19880321988-10-25025 October 1988 Insp Rept 50-312/88-32 on 880919-1007.Violations Noted. Major Areas Inspected:Design Changes & Mods,Qa Audits,Pwr Moderator Dilution Requirements & Followup Items IR 05000312/19880301988-10-13013 October 1988 Insp Rept 50-312/88-30 on 880912-16.No Violations or Deviations Noted.Major Areas Inspected:Licensee Actions on Previous Insp Findings,Radioactive Liquid & Gaseous Waste & Review of Licensee Repts IR 05000312/19880271988-09-30030 September 1988 Insp Rept 50-312/88-27 on 880912-16.No Violations Noted. Major Areas Inspected:Licensee Conformance W/Rev 3 to Reg Guide 1.97.Rept Addresses & Closes Sims Issue Number 67.3.3 IR 05000312/19880231988-09-27027 September 1988 Insp Rept 50-312/88-23 on 880709-0906.Violations Noted. Major Areas Inspected:Operational Safety Verification, Health Physics & Security Observations,Esfs Sys Walkdown, Maint,Surveillance & Testing & Followup Items IR 05000312/19880261988-09-0909 September 1988 Enhanced Operational Insp Rept 50-312/88-26 on 880801-09.No Violations Noted.Major Areas Inspected:Plant Operation & Operational Support Activities ML20154H8171988-09-0101 September 1988 Insp Rept 50-312/88-25 on 880719-21.No Violations Noted. Major Areas Inspected:Exam of Emergency Facilities, Equipment & Emergency Preparedness Training ML20153E5081988-08-16016 August 1988 Insp Rept 50-312/88-24 on 880719-22.Violation Noted. Major Areas Inspected:Licensee Actions on Previous Insp Findings & Lers,External Exposure Control & Internal Exposure Control IR 05000312/19880161988-07-27027 July 1988 Insp Rept 50-312/88-16 on 880601-0708.No Violations or Deviations Noted.Major Areas Inspected:Operational Safety Verification,Health Physics & Security Observations,Esf Sys Walkdown,Maint & Surveillance & Testing IR 05000312/19880211988-07-27027 July 1988 Insp Rept 50-312/88-21 on 880711-15.No Violations or Deviations Noted.Major Areas Inspected:Licensee Action on Fastener Testing,Primary Coolant Sys Pressure Isolation Valves & Natural Circulation Cooldown ML20151W0871988-07-25025 July 1988 Insp Rept 50-312/88-02 on 880104-0309.Weaknesses Noted. Major Areas Inspected:Past & Present Procurement,Matls Control & Warehouse Activities Before Restart IR 05000312/19880191988-07-13013 July 1988 Enhanced Operational Insp Rept 50-312/88-19 on 880613-17. No Violations Noted.Major Areas Inspected:Plant Operation & Operational Support Activities IR 05000312/19880221988-07-13013 July 1988 Enforcement Conference Rept 50-312/88-22 on 880707.Major Areas Discussed:Implementation of Licensee Corrective Action to Improve Radiation Protection Program Following 880204 Incident When Individual Received Excess Radiation Exposure ML20150D9231988-06-24024 June 1988 Insp Rept 50-312/88-17 on 880606-10.Violations Noted.Major Areas Inspected:Licensee Action on Previous Insp Findings, Control of Radioactive Matls & Contamination,Alara, Facilities & Equipment & Review of Licensee Repts IR 05000312/19880201988-06-23023 June 1988 Insp Rept 50-312/88-20 on 880617.Violations Noted.Major Areas Inspected:Status of Unresolved Item 50-312/88-07-01 Re Skin Exposure of Worker Reported by Licensee on 880204 IR 05000312/19880151988-06-23023 June 1988 Insp Rept 50-312/88-15 on 880503-31.No Violations or Deviations Noted.Major Areas Inspected:Operational Safety Verification,Esf Sys Walkdown,Maint,Surveillance & Testing, Review of Control Rod Worth & Followup Items IR 05000312/19880121988-05-23023 May 1988 Insp Rept 50-312/88-12 on 880330-0502.Violations Noted.Major Areas Inspected:Operational Safety Verification,Maint, Surveillance & Followup Items IR 05000312/19880141988-05-19019 May 1988 Insp Rept 50-312/88-14 on 880425-28.No Violations or Deviations Noted.Major Areas Inspected:Licensee Plans for Coping W/Strikes & Nonlicensed Staff Training.Specific Weaknesses in Licensee Program Observed IR 05000312/19880131988-05-10010 May 1988 Insp Rept 50-312/88-13 on 880404-08 & 19.Violations Noted. Major Areas Inspected:Action on Previous Insp Findings,Solid Wastes,Transportation & Facility Tours IR 05000312/19880051988-05-10010 May 1988 Insp Rept 50-312/88-05 on 880204-0329.Violations Noted.Major Areas Inspected:Operational Safety Verification,Maint, Surveillance,Security & Health Physics Routine Modules & Followup Items IR 05000312/19880081988-04-21021 April 1988 Insp Rept 50-312/88-08 on 880307-22.Violations Noted.Major Areas Inspected:Licensee Capabilities for Mgt & Implementation of Effective Liquid & Gaseous Effluents Program After Restart IR 05000312/19880111988-04-20020 April 1988 Insp Rept 50-312/88-11 on 880317.No Violations Noted.Major Areas Inspected:Unusual Event on 880315 IR 05000312/19870401988-04-19019 April 1988 Insp Rept 50-312/87-40 on 871207-18 & 880208-17.Deficiencies Noted.Major Areas Inspected:Review of Licensee Readiness to Operate Facility,Including Functional Areas of Operations, Maint,Surveillance Testing & Design Change Control ML20151C3641988-03-24024 March 1988 Insp Rept 50-312/87-44 on 871205-880203.Violation Noted. Major Areas Inspected:Operational Safety Verification,Maint, Surveillance & Followup Items IR 05000312/19880091988-03-15015 March 1988 Insp Rept 50-312/88-09 on 880307-08.No Violations Noted. Major Areas Inspected:Emergency Preparedness Program & Followup on Open Items.Insp Procedure 92701 Covered IR 05000312/19870491988-03-0808 March 1988 Insp Rept 50-312/87-49 on 871228-30 & 880127-28.No Violations or Deviations Noted.Major Areas Inspected:Fire Protection Program Implementation & Identified Open Items ML20148B7061988-03-0303 March 1988 Insp Rept 50-312/88-07 on 880205 & 08.Findings of Rept Will Be Identified as Unresolved Pending Completion of Investigation.Major Areas Inspected:Response to Licensee 880204 Rept of Potential Exposure to Extremity of Worker ML20148B4321988-03-0202 March 1988 Insp Rept 50-312/88-06 on 880124-0219.Violation Noted.Major Areas Inspected:Licensee Action on Previously Identified Inspector Items,Lers,Followup on Items of Noncompliance & Followup on Eastrp Corrective Action IR 05000312/19880011988-02-0505 February 1988 Insp Rept 50-312/88-01 on 880104-08,20 & 0202.No Violations or Deviations Noted.Major Areas inspected:post-accident Sampling Sys & Tour of Facility.Insp Procedures 25565,30703, 92701 & 92702 Addressed IR 05000312/19870371988-02-0303 February 1988 Insp Rept 50-312/87-37 on 871024-1204.Violations Noted.Major Areas Inspected:Operational Safety Verification,Maint, Surveillance & Followup Items IR 05000312/19870461988-01-26026 January 1988 Insp Rept 50-312/87-46 on 871214-18.No Violations Noted. Major Areas Inspected:Emergency Preparedness Program, Followup on Open Items & Insp Procedures 82206 & 92701 IR 05000312/19870421988-01-0808 January 1988 Insp Rept 50-312/87-42 on 871130-1204.No Violations or Deviations Noted.Major Areas inspected:post-accident Sampling Sys & Independent Insp Effort.Insp Procedures 30730,92701 & 92702 Addressed IR 05000312/19870451988-01-0505 January 1988 Insp Rept 50-312/87-45 on 871207-11.No Violations or Deviations Noted.Major Areas Inspected:Action on Previously Identified Items,Lers & NRC Bulletin Followup ML20195J7241988-01-0404 January 1988 Augmented Sys Review & Test Program Insp Rept 50-312/87-29 on 870928-1009.Open & Unresolved Items Noted.Major Areas Inspected:Open & Unresolved Items from Augmented Sys Review & Test Program Insp Rept 50-312/86-41 IR 05000312/19870391987-12-24024 December 1987 Insp Rept 50-312/87-39 on 871116-19.No Violations or Deviations Noted.Major Areas Inspected:Followup on Previously Identified Open Items & Fire Protection Program IR 05000312/19870271987-12-21021 December 1987 Insp Rept 50-312/87-27 on 871102-06.No Violations Noted. Major Areas Inspected:Emergency Preparedness Exercise, Associated Critique & Followup Items IR 05000312/19870331987-12-16016 December 1987 Insp Rept 50-312/87-33 on 871019-23.No Deficiencies or Violations Noted.Major Areas Inspected:Emergency Preparedness Program Including Meteorology & Followup of Open Items 1990-07-31
[Table view] Category:TEXT-INSPECTION & AUDIT & I&E CIRCULARS
MONTHYEARIR 05000312/19990031999-08-31031 August 1999 Insp Rept 50-312/99-03 on 990802-06.No Violations Noted. Major Areas Inspected:Decommissioning & Dismantlement Activities,Including Organization,Mgt & Cost Controls IR 05000312/19990021999-03-19019 March 1999 Insp Rept 50-312/99-02 on 990309-11.No Violations Noted. Major Areas Inspected:Licensee Physical Security Program, Including Access Authorization,Alarm Station & Communication & Testing & Maint IR 05000312/19980031998-08-0707 August 1998 Insp Rept 50-312/98-03 on 980706-09.No Violations Noted. Major Areas Inspected:Review of Licensee Programs Related to SFP Safety,Status of Decommissioning,Safety Review & self-assessments & Radiological Safety Programs ML20248K6301998-06-0303 June 1998 Notice of Violation from Insp on 980519-21.Violation Noted:Inspector Determined That Licensee Failed to Review & Consider All Info Obtained During Background Investigation IR 05000312/19980021998-06-0303 June 1998 Insp Rept 50-312/98-02 on 980519-21.Violations Noted. Major Areas Inspected:Announced Insp of Licensee Physical Security Program ML20202C4771998-02-0505 February 1998 Notice of Violation from Insp on 980105-08.Violation Noted: on 971222,shipment of Scrap Metal,In Form of Auxiliary Boiler,Was Released from Rancho Seco Site W/O Having Been Surveyed ML20202C4981998-02-0505 February 1998 Insp Rept 50-312/98-01 on 980105-08.Violations Noted.Major Areas Inspected:Organization,Mgt & Cost Controls,Maint & Surveillance,Cold Weather Preparation,Decommissioning Performance & Status Review & Health Physics ML20198K5451997-10-21021 October 1997 Notice of Violation from Insp on 970922-25.Violation Noted:On 970806,thermocouple for Spent Fuel Pool Temp Indicator Was Found to Be out-of-tolerance During Annual Calibration IR 05000312/19970041997-10-21021 October 1997 Insp Rept 50-312/97-04 on 970922-25.Violations Noted. Major Areas Inspected:Organization,Mgt,Cost Control,Safety Reviews,Design Changes,Mods,Decommissioning Performance & Status Review IR 05000312/19970031997-06-17017 June 1997 Insp Rept 50-312/97-03 on 970603-05.No Violations Noted. Major Areas Inspected:Records & Repts,Testing & Maint, Protected Area Barrier & Detection Aids,Assessment Aids, Alarm Station & Communication & Security System IR 05000312/19970021997-04-25025 April 1997 Insp Rept 50-312/97-02 on 970331-0403.No Violations Noted. Major Areas Inspected:Incremental Decommissioning Activities in Turbine Bldg,Radiation Protection,Sfp Activities & Quality Assurance IR 05000312/19970011997-03-21021 March 1997 Insp Repts 50-312/97-01 & 72-0011/97-01 on 970224-27.No Violations Noted.Major Areas Inspected:Licensee Planned Work Associated W/Dismantlement of Turbine Bldg & Radiological Controls Being Implemented During Work Activities IR 05000312/19960031996-09-27027 September 1996 Insp Repts 50-312/96-03 & 72-0011/96-01 on 960909-12.No Violations Noted.Major Areas Inspected:Sfp & Radiological Ts,Radiological Exposure Controls & Implementation of New 10CFR49 Shipping Regulations IR 05000312/19930061993-09-0202 September 1993 Insp Rept 50-312/93-06 on 930819.No Violations or Deviations Noted.Major Areas Inspected:Licensee Employee Concerns Program IR 05000312/19930041993-08-11011 August 1993 Mgt Meeting Rept 50-312/93-04 on 930727.Major Areas Discussed:Status of Activities,Including Maint of Plant Equipment,Fire Protection Equipment & Plant Personnel Morale IR 05000312/19920071992-12-10010 December 1992 Insp Rept 50-312/92-07 on 921110-11.No Deviations or Violations Noted.Major Areas inspected:1992 Annual Emergency Preparedness Exercise & Associated Critiques & Inspector Identified Items IR 05000312/19900141990-11-14014 November 1990 Insp Rept 50-312/90-14 on 901003-04,09-11 & 1102.Violations Noted.Areas inspected:follow-up of Licensee Event Repts, Liquid Effluent,Solid Waste & Allegations IR 05000312/19900111990-07-31031 July 1990 Insp Rept 50-312/90-11 on 900527-0706.No Violations or Deviations Noted.Major Areas Inspected:Operational Safety Verification,Health Physics & Security Observations,Esf Sys Walkdown,Maint,Surveillance & Testing & QA IR 05000312/19890161989-09-21021 September 1989 Enforcement Conference Rept 50-312/89-16 on 890915. Violations Noted.Major Areas Discussed:Violations Noted in Insp Rept 50-312/89-16 & Indications That Findings Represent Decrease in Mgt Commitment to Emergency Preparedness IR 05000312/19890121989-09-21021 September 1989 Insp Rept 50-312/89-12 on 890801-04,21-25 & 30.No Violations Noted.Major Areas Inspected:Occupational Exposure,Including Alara,Radwaste Sys,Liquid & Liquid Wastes & Radwaste Mgt & Transportation PNO-V-89-056, on 890911,SMUD Board Rejected Golden State Energy Proposal to Purchase Plant1989-09-12012 September 1989 PNO-V-89-056:on 890911,SMUD Board Rejected Golden State Energy Proposal to Purchase Plant IR 05000312/19890141989-09-11011 September 1989 Insp Rept 50-312/89-14 on 890828-0901.Violations Noted Re Failure to Conduct Required Semiannual Health Physics Drill & Initial Training.Major Areas Inspected:Operational Status of Emergency Preparedness Program PNO-V-89-053, on 890901,Golden State Energy Proposal to Purchase Rancho Seco Submitted to Util,Including MOU for Purchase of Plant,Power Sale Agreement & Interim Operation & Maint of Facility & Rate Structure.Vote Expected on 8909071989-09-0505 September 1989 PNO-V-89-053:on 890901,Golden State Energy Proposal to Purchase Rancho Seco Submitted to Util,Including MOU for Purchase of Plant,Power Sale Agreement & Interim Operation & Maint of Facility & Rate Structure.Vote Expected on 890907 PNO-V-89-050, on 890823,util Announced That Board of Directors Would Meet on 890825 Re Proposed Golden State Energy Purchase of Plant.Key Issues Listed,Including MOU Addressing Power Sale Agreement1989-08-23023 August 1989 PNO-V-89-050:on 890823,util Announced That Board of Directors Would Meet on 890825 Re Proposed Golden State Energy Purchase of Plant.Key Issues Listed,Including MOU Addressing Power Sale Agreement IR 05000312/19890101989-08-10010 August 1989 Insp Rept 50-312/89-10 on 890603-0721.No Violations Noted. Major Areas Inspected:Areas of Operational Safety Verification,Health Physics & Security Observations,Maint, Surveillance & Testing & QA & Followup Items PNO-V-89-044, on 890720,util Board Voted by 4-1 Vote to Enter Exclusive Negotiations W/Quadrex Corp for Possible Sale of Plant.Key Milestone Dates Listed.Board Maintained That Several Key Issues Must Be Addressed Before Voting on Sale1989-07-21021 July 1989 PNO-V-89-044:on 890720,util Board Voted by 4-1 Vote to Enter Exclusive Negotiations W/Quadrex Corp for Possible Sale of Plant.Key Milestone Dates Listed.Board Maintained That Several Key Issues Must Be Addressed Before Voting on Sale IR 05000312/19890081989-07-11011 July 1989 Insp Rept 50-312/89-08 on 890422-0602.No Violations or Deviations Noted.Two non-cited Violations Discussed.Major Areas Inspected:Operational Safety Verification,Health Physics & Security Observations & ESF Sys Walkdown IR 05000312/19890111989-07-0606 July 1989 Insp Rept 50-312/89-11 on 890629-30.No Violations Noted. Major Areas Inspected:Licensee Radiochemical Analyses to Verify Accuracy of Measurements of Radionuclides in Release Tank Water & Sediment from Effluent Discharge Point PNO-V-89-039, on 890620,util Announced That Licensee Open to Offers to Purchase Facility Until 890630.Of All Bidders,Only Quadrex Corp Proposes to Operate Facility as Nuclear Plant. Evaluation of Bids Expected to Be Completed by End of Jul1989-07-0303 July 1989 PNO-V-89-039:on 890620,util Announced That Licensee Open to Offers to Purchase Facility Until 890630.Of All Bidders,Only Quadrex Corp Proposes to Operate Facility as Nuclear Plant. Evaluation of Bids Expected to Be Completed by End of Jul PNO-V-89-036, on 890620,SMUD Voted 3-2 to Allow 10 Days for Qualified Private Bidders to Submit Proposals to Take Over Facility.Conditions Imposed on Bidders Listed.Existing Quadrex Proposal Withdrawn1989-06-21021 June 1989 PNO-V-89-036:on 890620,SMUD Voted 3-2 to Allow 10 Days for Qualified Private Bidders to Submit Proposals to Take Over Facility.Conditions Imposed on Bidders Listed.Existing Quadrex Proposal Withdrawn PNO-V-89-035, on 890619,licensee Announced That D Keuter Had Been Appointed New Site Manager & Jr Shetler as Deputy Site Manager.Licensee Recognizes That Organizational Changes Subj to NRC Approval1989-06-20020 June 1989 PNO-V-89-035:on 890619,licensee Announced That D Keuter Had Been Appointed New Site Manager & Jr Shetler as Deputy Site Manager.Licensee Recognizes That Organizational Changes Subj to NRC Approval PNO-V-89-034, on 890615,offer to Assume Financial & Technical Responsibility for Plant Announced.Plant Presently in Cold Shutdown W/Activities Continuing Towards off-loading Reactor Core in Oct 19891989-06-16016 June 1989 PNO-V-89-034:on 890615,offer to Assume Financial & Technical Responsibility for Plant Announced.Plant Presently in Cold Shutdown W/Activities Continuing Towards off-loading Reactor Core in Oct 1989 PNO-V-89-033C, on 890609,plant Reached Cold Shutdown in Preparation for Reinstalling Refueling Bridge Into Reactor Bldg.Bridge Removed for Refurbishment/Mod.Reduction in Force of Nonessential Contractor Personnel in Progress1989-06-12012 June 1989 PNO-V-89-033C:on 890609,plant Reached Cold Shutdown in Preparation for Reinstalling Refueling Bridge Into Reactor Bldg.Bridge Removed for Refurbishment/Mod.Reduction in Force of Nonessential Contractor Personnel in Progress PNO-V-89-033B, on 890608,licensee Continuing Cooldown of Plant.Ceo Nuclear,J Firlit,Announced Resignation.Work Force Reductions Initiated Which Will Initially Involve Approx 420 Nonessential Contractor Clerical & Crafts Personnel1989-06-0808 June 1989 PNO-V-89-033B:on 890608,licensee Continuing Cooldown of Plant.Ceo Nuclear,J Firlit,Announced Resignation.Work Force Reductions Initiated Which Will Initially Involve Approx 420 Nonessential Contractor Clerical & Crafts Personnel PNO-V-89-033A, on 890607,util Shut Down Plant & Entered Hot Shutdown Due to Voter Defeat of Measure K.Util Continuing to Implement Contingency Plan to Remove Plant from Svc. Reductions in Site Work Force Under Consideration1989-06-0707 June 1989 PNO-V-89-033A:on 890607,util Shut Down Plant & Entered Hot Shutdown Due to Voter Defeat of Measure K.Util Continuing to Implement Contingency Plan to Remove Plant from Svc. Reductions in Site Work Force Under Consideration PNO-V-89-033, on 890606,voters Defeated Measure K,Encouraging Util to Cease Operating Facility.Util Board Previously Announced That Plant Would Be Shutdown If Measure K Defeated.Safe Shutdown Plan Implemented1989-06-0707 June 1989 PNO-V-89-033:on 890606,voters Defeated Measure K,Encouraging Util to Cease Operating Facility.Util Board Previously Announced That Plant Would Be Shutdown If Measure K Defeated.Safe Shutdown Plan Implemented PNO-V-89-030, on 890518,airborne Process Monitors for Reactor Bldg Stack,Auxiliary Bldg Stack & Auxiliary Bldg Grade Level Vent Inoperable.Caused by Computer Controlled Svc Air Purge Valves in Open Position.Possibly Caused by Software Errors1989-05-19019 May 1989 PNO-V-89-030:on 890518,airborne Process Monitors for Reactor Bldg Stack,Auxiliary Bldg Stack & Auxiliary Bldg Grade Level Vent Inoperable.Caused by Computer Controlled Svc Air Purge Valves in Open Position.Possibly Caused by Software Errors IR 05000312/19890071989-04-28028 April 1989 Insp Rept 50-312/89-07 on 890417-21.No Violations Noted. Major Areas Inspected:Previously Identified Items & Status of Emergency Preparedness Program IR 05000312/19890041989-03-31031 March 1989 Insp Rept 50-312/89-04 on 890114-0303.Violations Noted.Major Areas Inspected:Operational Safety Verification,Health Physics & Security Observations,Esf Sys Walkdown,Maint,Qa Surveillance & Testing & Followup Items ML20248J6521989-03-31031 March 1989 Notice of Violation from Insp on 890114-0303.Violations Noted:Engineering Change Notice Not Initiated for Rebuilt Governor for Auxiliary Feed Pump Installed on 890131 & Maint Work Request Not Reviewed Prior to Performance of Test IR 05000312/19880391989-03-28028 March 1989 SALP Rept 50-312/88-39 for July 1986 - Dec 1988 ML20244A8021989-03-28028 March 1989 SALP Rept 50-312/88-39 for July 1986 - Dec 1988 ML20244B1141989-03-27027 March 1989 Notice of Violation from Insp on 890123-0217.Violations Noted:Nonconformance Rept Not Written After Determination That Debris Caused Failure of Two Instrument Air Sys Check Valves During Performance of Test Procedure STP-774 ML20244B1161989-03-24024 March 1989 Insp Rept 50-312/89-01 on 890123-0217.Violations Noted.Major Areas Inspected:Maint Program & Implementation of Related Activities IR 05000312/19880421989-02-13013 February 1989 Insp Rept 50-312/88-42 on 881227-30 & 890125-27.No Violations Noted.Major Areas Inspected:Followup Items,Part 21 Repts,Lers & Licensee Program to Maintain Quality of Diesel Generator Fuel Oil IR 05000312/19880411989-02-13013 February 1989 Insp Rept 50-312/88-41 on 881214-890103.No Violations Noted. Major Areas Inspected:Onsite Followup of Event of 881212 & Associated Mgt Meetings on 881219 & 890103.Weaknesses Observed Re Decision to Operate Plant in Degraded State IR 05000312/19880401989-02-0606 February 1989 Insp Rept 50-312/88-40 on 881208-890113.No Violations or Deviations Noted.Major Areas Inspected:Operational Safety Verification,Health Physics & Security Observations,Esf Sys Walkdown,Maint,Qa & Surveillance & Testing ML20235T2211989-02-0606 February 1989 Exam Rept 50-312/OL-88-02 on 881206-13.Exam Results:All Seven Senior Reactor Operator Candidates Passed Written & Oral Exams ML20196B6881988-11-30030 November 1988 PNS-V-88-006:on 881126,licensee Received Telcon Alleging That Nonlicensed Equipment Operator Observed Using Illegal Drugs.Individual Submitted to Urinalysis Test & Showed Positive for Marijuana.Individual Terminated on 881130 IR 05000312/19880351988-11-21021 November 1988 Mgt Meeting Rept 50-312/88-35 on 881114.Major Areas Discussed:Licensee Operational Performance Since Restart in Mar 1988 & Progress Re Restart Commitments in Areas of Engineering,Procurement,Maint & Effluent Sys Areas 1999-08-31
[Table view] |
See also: IR 05000312/1987016
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U. S. NUCLEAR REGULATORY COMMISSION
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Report No. 50-312/87-16 .'
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Docket'No. 50-312 '
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License No. 'DPR-54-
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Licensee: Sacramento Municipal Utility' District (SMUD)
P. O. Box 15830
Sacramento, California 95813
Facility Name: Rancho Seco Nuclear Generating Station 1
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Inspection Conducted: May 4 to'May 8, 1987
Inspected by: . /A) y S-2n- t 1
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W. P ,.Projs - spector Date Signed
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Approved by:
L lier, Chief, Pr6 ject Section 2
5'N'h
Date Signed
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. Accompanying' Personnel: D.' A. Beckman, Prisuta-Beckman Associates
~ Summary:.
Inspection on May 4 to May 8, 1987 (Report No. 50-312/87-16)'
Areas Inspected: Routine announced inspection by a region base'd inspector and l
, an NRC contractor of licensee action on previously identified inspector items,
Licensee Event Reports, and personnel qualifications. Inspection Procedures
30703, 36100, 92700, 92701, and 92702 were'used during this inspection.
Results': In the areas inspected, one violation regarding inadequate inservice I
testing procedures for valve full stroke testing (paragraph 4. A.) was
identified.
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8706180000 870529
PDR ADOCK 05000312
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DETAILS , ,
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F < ll ' Personnel Contacted y
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- B. Croley, Plant Manager.-
<- W.,Kemper, Operations Manager.
D. Army, Nuclear Maintenance Manager' ,
'J. Vinquist, Licensing Manager (Acting) , ,
G. Shanker, Deputy Maintenance Manager,
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G. Clefton, Assistant Maintenance Manager. '
- *D. Brock,' Maintenance Programs Supervisorf . t
- S.'Redeker, Assistant to the Operations Manager.
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D. Wiles, I&C Supervisor
H. Humphrey, I&C Supervisor
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J. Lingenfelter, Systems Review and Test Program Assistant Director
'*J. Robertson, Nuclear Licensing Engineer
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- A. D'Angelo,. Senior NRC Resident Inspect'or
- Attended the exit meetings.
'The inspector also held discussions with other licensee and contract
personne1'during the inspection. This included plant staff engineers,
technicians, administrative and clerical assistants.
2. Licensee Action on' Previous Enforcement Matters
A. (Closed) Violation 86-18-02, Failure of PRC to Review Temporary
. Valve. Modification per TS 6.5.1.6(d), and ..
(Closed) Violation 86-18-03, Failure to1 Implement' Abnormal Tag
Procedure Requirements for Temporary Valve Modification
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Valve SFV-22006 was modified by installation .of a temporary clamping
ring and sealant to correct a body to bonnet reactor coolant. '
pressure boundary leak (see Unresolved Item 86-18-01, paragraph 4.B
for bect. ground information).
Technical Specification 6.5.1.6(d) requires that the Plant Review l
Committee (PRC) review all proposed changes or modification to plant
systems or equipment that affect nuclear safety.. Violation 85-18-02
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cited the failure of the PRC to review the above andification.
Rancho Seco Administrative Procedure AP-26, Abnormal Tag Procedure, i
requires an Abnoratal Tag be issued any time a system is modified and
placed .in service without an approved Drawing Change Notice. !
Violation 86-18-03 was issued for failure to process an Abnormal Tag .
for the modification. I
The licensee provided a combined response (JEW 86-896,~ November 20,
'1986). for the two . violations, addressing five commitments / actions as
discussed below: 1
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N The licensee committed to having the PRC review all temporary
changes to.any Class.1 systems.or components in the plant, ;
regardless'of the Part.50.59 determination. '
This! commitment is: implemented by revision 13 to AP-26,
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Abnormal. Tag Procedure, which now requires that all' Abnormal
' Tags be provided to and reviewed by the PRC.within one working
day. . Inspector's review of the Abnormal. Tag log confirmed.
- implementation. !
The Nonconformance' Report (NCR) Procedure (QAP-17) and Abnormal ,
Tag: Procedure.(AP-26) were revised in accordance with the
- 1icensee's response to include' provisions to invoke the
Abnormal = Tag process.and 10 CFR 50.59 reviews. Revision 4 of
.QAP-17 included addition of a '" Note" requiring implementation
of AP-26 if temporary repairs or interim accept-as-is"
dispositions'are specified for an NCR. AP-26, revision 13,
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incorporated a new'10 CFR 50.59 evaluation questionnaire and
, provisions for.PRC review as previously noted above.
,The licensee's response noted that.both' procedure revisions
vpuld be made byL January 5,1987. . However, revision 4'of-
QAP-17.was not approved and issued for' distribution until
Jhnuary 11, 1987; revision 13 of AP-26'was not effective until
March'30, 1987. This failure to meet commitment dates to NRC
is essentially. identical to Deviation 87-11-01 issued on
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April.-20,.1987; the licensee's. response to Deviation 87-11-01
was p6nding at the. time of this inspection. The licensee was
' advised that-their response to Deviation 87-11-01 would be
evaluated.in light of the-apparent-recurring nature of the
problems described therein and above.
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The licensee's response to this item further committed to
conduct a' review of the. technical adequacy of previous
temporary changes to Class 1 systems implemented by NCRs by i
February 2, 1987. Where establishment of adequacy was not
apparent,.an_ assessment would be performed. 1
SMUD memorandum QLC 87-006, dated January 26, 1987, documented
the results of the QA/QC review of all open Class 1, 2, and 3
NCRs through December 31, 1986. A total of 747 NCRs were ,
reviewed; three NCRs were identified as having implemented i
temporary changes without performance-of 10 CFR 50.59 reviews.
The three NCRs were provided to the PRC for review and the PRC
review of the NCR's for compliance with 10CFR 50.59 were ,
documented in PRC Meeting Minutes No.1637, January 30, 1987.
The inspector reviewed the NCRs and the PRC review conclusions
and found the PRC review to be acceptable.
The licensee review also included a statistical sample of 260 l
out of 4,000 NCRs issued during the period July 1980 through
December 1986. The' review found that none of the samples
involved NCRs implementing temporary changes to the facility
that were not subject to 10 CFR 50.59 and Technical Specification
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PRC reviews, concluding that the problems ideritified by NRC
Inspection 50-312/86-18 were a recently developed trend.
The licensee also committed'to a programmatic review of the i
District's procedures for the control of modifications pursuant
to 10 CFR 50.59 by December 8, 1986.' Memorandum QLC 86-121 -l i
issued Audit Report No. 0-846, " Response to Inspection 86-18,"
on October 30, 1986, for the audit completed on September 25,
~1986.
The audit recommended: revision of existing procedures to. '
clarify and consolidate programmatic requirements; provision of j
additional staff training; incorporation of INP0 Good Practice
TS-415 provisions;' application of 10 CFR 50.59 provisions to
changes to Nuclear Engineering Procedures; and, others. ]
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A new procedure, RSAP-0901, " Safety Review of Proposed Changes,
Tests, and Experiments," Draft, had been issued to_ replace the
combined requirements of QCI-5 and QCI-18; to incorporate the
Audit 0-846 findings and recommendations, and meet new licensee
procedure upgrade program requirements. The procedure had been ,
PRC and MSRC approved but not yet implemented pending personnel
training.
Although this inspection confirmed that the licensee's corrective
and preventive actions for Violations 86-18-02 and -03 had been
implemented, NRC Inspection 50-312/87-06 identified two similar
violations (87-06-01 and -02) wherein temporary repairs had been
made to a leaking pipe in the Nuclear Service Raw Water (NSRW)
system without issuance of a Nonconformance Report, Work Request ,
and/or Abnormal Tag for a temporary patch. Violations 86-18-02 and 4
-03 will be closed for record purposes. Apparent continuing
weaknesses in the licensee's programs for timely completion of '
commitments to NRC and in programs for control .of temporary
modifications will be reviewed upon NRC receipt of the SMUD
responses to NRC Inspections 87-06 and 87-11.
3. Licensee Action on Region V Open Items Regarding Inspection Report
50-312/86-07 and the December 26, 1985 Event
A. RV - MA-4 (0 pen)
SMUD - 16c(4)
EDO - 4a
Verify Operability of Manual Vaives and Remote Operated Valves.
Perform Inspections to Assure Irategrity of Packing and Verify Proper
Assembly of Manual Operators Including Setting of " Neutral" Position
and Mounting Devices
Inspection Report 50-312/86-07 and 87-11 documented NRC inspection
of the licensee's inspection, repair and testing of manual and
remote operated valves. Inspector's concerns regarding the manual
valve inspection and preventative maintenance program were
identified in inspection report 50-312/87-11 as follows:
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(1) The licensee did not appear to have a reviewed and approved
document that lists all manual valves which are critical for
plant operations. The list of 142 valves appears to have been
developed by an informal piece-meal process, rather than by a
formal, pre-planned review process. The NRC considered that
the importance of this activity should have been subjected to
a review and approval by appropriate levels of management.-
(2) The inspections of the valves appear to have been performed by
maintenance personnel. Many valves appear to have been
accepted as-is or accepted with minor lubrication corrective
action. No verification and documentation of individual valve
acceptability appears to have been performed. A majority of
the valves appear to have been accepted with no QC inspection.
(3) AP 650 revision 5, PM Program, categorized manual valves in QA
Class 1 systems that are required for controlld safe-shutdown
of the plant as Category 1 and Category 2A valves. Corrective
maintenance on Category 1 valves had been performed but the
licensee's program did not include a requirement or plan to
perform corrective maintenance on all Category 2A valves
before restart.
During this inspection, the inspector discussed the above noted
concerns with the Maintenance Manager and performed a sampling
inspection of the manual valves. The discussions and inspection
resulted in the following:
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(1) The Maintenance Manager provided the inspector with a copy of a ]
memorandum from the Nuclear Operations Manager to the l
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Maintenance Manager, dated May 4, 1987, that formalizes the
review and listing of 142 manual valves that are considered
critical for plant operations. The inspector had no further 2
concerns regarding this item. !
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(2) The Maintenance Manager stated that inspections and corrective
maintenance had been completed on the 142 manual valves that
were critical for plant operations. Current procedures allow
for the QA Department to require QC verification of maintenance
activities regarding the manual valves but QC inspection was
not performed on the 142 manual valves that had been determined
to be critical for plant operations and none was planned at the
time of the initial discussion. On that basis, the inspector
selected 7 of the 142 valves for a sampling visual inspection i
to determine the adequacy of the maintenance department l
baseline inspections and corrective maintenance. The sample I
was selected based on the Senior Reactor Operator's I
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determination of valves on the list (142 critical manual
valves) that could be cycled by an auxiliary operator without
disrupting plant conditions or operations in progress and the
inspector's determination of relative importance of the valves.
The inspector also requested a QC inspector to perform the
inspections with the NRC inspector to determine the adequacy of ,
normal QC inspections of manual valves. The following are the l
valves inspected and the discrepancies observed:
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NSW-001 - (Nuclear Service Cooling Water Surge Tank Discharge
Isolation Valve).
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- Operation of valve handwheel causes a valve position-
indication reversed from the valve position direction
i marking _in the handwheel. As a result,'the auxiliary
operator, the QC inspector and the Maintenance
Engineer could not determine the-actual valve
position. 'In addition, during potential emergency
conditions, the valve condition could be diagnosed as
a stuck valve and forceful operation of the valve, if.
performed, could result in valve damage.
NSW-003 - (Nuclear Service Cooling Water Pump A Suction. ;
Isolation Valve).
- Valve position indicator had no visible "open" or '
" closed" markings.
- Body and bonnet fasteners did not have full thread
engagement (i.e. not flush with the nut). No !
apparent technical evaluation for acceptability was
provided by the licensee during the' inspection.
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BWS-036 "B" Boric Acid Pump Discharge Isolation.
- Body-to-Bonnet Leak.
- Packing Leak.
BSW-030 "B" Boric Acid Pump Suction Isolation.
- Packing Leak.
NRW-009 "A" Nuclear Service Cooling Water Hx Vent.
- No discrepancies observed. -!
FWS-046 - Auxiliary Fd Pump P319 Suction Isolation.
- No discrepancies observed.-
FWS-052 - Auxiliary Fd Pump P319 Flow Orifice Isolation. _
- No discrepancies observed.
As a result of the above inspection, QC issued NCR-6688 for the i
NSW-003 discrepancies and NCR-6687 for the NWS-001 i
discrepancies. As immediate corrective action, the Maintenance
Manager and QC Supervisor initiated a 100% reinspection of the :
142 critical valves for the conditions noted above. t
(3) During the initial discussions, the Maintenance Manager stated
that the intent of AP 650 was not to categorize valves required
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for controlled safe shutdown of the plant in both Category 1
and Category 2A. The Maintenance Manager stated that a
revision to AP 650 would change the Category 2A definition and
would consequently only have valves required for controlled
safe shutdown of the plant in Category 1.
Pending licensee completion of satisfactory inspection of manual
valves and revision of AP 650 to reflect the current licensee
intent, RV-MA-4 was left open.
No violations or deviations were identified.
4. Licensee Action on Previously Identified Inspector Items
A. (Closed) Unresolved Item 85-23-03, Adequacy of IST Program
Procedures
.This item involves six separate procedure discrepancies and
weaknesses (Items 3.a - f in inspection report 50-312/85-23)inthe
licensee's Surveillance Procedures for implementation of the ASME,
Section XI, Inservice Test Program.
Item 3.d of the above report identified the absence of pump suction
pressure and bearing temperature acceptance criteria in SP 213.01.
This item was previously reviewed and is being separately tracked as
Unresolved Item 50-312/84-41-31 and is considered closed for the
purposes of this report.
Item 3.e was the subject of Violation 50-312/85-23-02 (Failure to
implement calibration controls for instruments used in Surveillance
Procedures) and of Deviation 50-312/87-11-01 (Failure to implement
corrective action for Violation 85-23-02). The licensee's actions
regarding Item 3.e will be reviewed in conjunction with their
responses to the Violation and Deviation and are considered closed
with respect to this Unresolved Item.
Item 3.f identified inadequacies in relief valve testing and was
cited as an example of Violation 85-23-04. Therefore, the
licensee's actions pursuant to this item will be reviewed in light
of their response to the violation and are considered closed with
respect to this Unresolved Item.
Item 3.a involves Decay Heat System return header isolation valves
DHS-015 and -016. SP 203.06 previously required the performer to
" record proper flow path and design flow provided through the
valves..." while the data sheet (Enclosure 6.2) required only a sign
I off for those valves to verify that the valves were locked open. i
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Revision 11 to SP 203.06 has been issued which requires DHS in
operation at 3,000 gpm flow (per Operating Procedure AP-8),
verification of the valve (s) in the open position, and recording of
the flow rate through the valves. The valve configuration is such
that full system flow rate (per AP-8) should be seen through the
valves. The inspector noted that no specific acceptance criteria is
provided but, based on the system configuration for test and the
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combined requirements of tl'e two procedures, the test method is now
acceptable. This portion of Unresolved Item 85-23-03 is considered
closed.
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Item 3.b - Main Turbine Throttle Stop (Trip) Valves TV-1 through
TV-4 are fast acting valves controlled by the electro-hydraulic
control system to trip the turbine and act as main steam isolation '
valves. The facility is not equipped with in line main steam
isolation valves upstream of the turbine steam chest.
SP 213.03C, " Turbine Throttle Stop Valve Fail Safe Test," provides
for full stroke testing of the valves in accordance with the IST-
program requirements and SP 214.02, Valve Test Information. Prior
revisions of SP 214.02 provided valve closure time requirements of ;
3.3 to 5.6 seconds which were in conflict with the NRC Safety J
Evaluation Report, Relief Request PV-14, dated September 25, 1984,
which stipulated measurement of valve closure times with a maximum
closure time " typical of a new or recently reconditioned valve
(typically one second) plus two seconds...." SP 213.03C,
revision 1, included stroke time requirements of -3 seconds
consistent with the SER.
Item 3.b further noted that SP 213.03C did not require recording of
actual stroke time, only a verification that the valve stroked in
less than 3 seconds.
During the current inspection, SP 214.03, revision 6, was found to
include correct valve stroke time limits for TV-1 through TV-4 (1 - 4
3 seconds). This portion of Item 3.b is considered closed.
Revision 1 of SP 213.03C was still in effect, unrevised from the
previous inspection. The procedure did not require that stroke time
data be recorded but required only & verification signature that the
" valve moves from open to closed in three seconds or less."
TS 4.2.2, Inservice Inspection, requires inservice testing of ASME !
Code Classes 1, 2, and 3 components to be performed as closely as
design permits in accordance with Section XI of the ASME Boiler and l
Pressure Vessel Code and applicable addenda as required by 10 CFR 1
50.55.a(g) except where specific written relief has been granted by
the Commission.
The NRC SER dated September 25, 1984, provides for relief from
certain aspects of ASME Section XI for valves TV-1 through TV-4 but
requires slow full stroke testing quarterly (without stroke time
measurement) and fail safe (fast) full stroke testing each cold
shutdown including stroke time measurement.
ASME Section XI, Article IWV3410 requires that the stroke time of ;
power operated valves be measured to the nearest second or 10% of
the maximum allowable stroke time, whichever is less, whenever the
valve is full stroke tested. The data is required to be trend
analyzed for increases in stroke time (50% for fast acting valves)
to detect aonormal operation and invoke increased test frequencies
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or corrective action. No exemption is authorized by the NRC SER :
except for the quarterly " slow" test. {
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Procedure 213.03C, revision 1, is applicable to both the quarterly {
" slow" full stroke test and the " fast" or fail safe test at cold ,
shutdown and does not discriminate between the two test requirements j
in either test method or data acquired. As indicated above, only
verification of stroke time less than 3 seconds is recorded.
Failure to measure, record and analyze stroke time data for TV-1
through TV-4 constitutes an apparent violation of TS 4.2.2 and the '
requirements of the inservice test program above (50-312/87-16-01).
Item 3.c also involves program relief request for RCP Seal Injection j
line isolation valves SIM-019, -020, -021, and -022. These are stop '
check valves which act as reactor coolant pressure boundary valves i
and, in the reverse (check) direction, as containment isolation !
valves.
NRC SER Relief Exemption PV-3 states that the valves must be full l
stroke tested at each cold shutdown. Inspection 50-312/85-23 found i
that SP 203.03, " Quarterly Makeup and Purification System SFAS Valve l
Inspection and Surveillance Test: required only that the valves be l
" inspected"; no provisions for full stroke testing could be j
identified. j
During the current inspection, review of SP 203.03, revision 10, j
found that the applicable portion of the procedure was still as
stated above. This constitutes a further example of Violation
50-312/87-16-01 above. l
The licensee noted that, although SP 203.03 appeared unresponsive to
the above requirements, SP 205.02, Local Leak Rate Testing,
coincidentally resulted in these valves being closed and reopened
(on a nominal biennial schedule) as part of the 10 CFR 50, Appendix
J, Type C, containment isolation valve tests. Based on that fact, ,
the valves normally indicated flow conditions, and NRC authorized
relief from reverse flow testing of the containment isolation check I
valve function, the licensee considered the safety implications of
the testing oversight to be minimal. )
With respect to the two examples of noncompliance above, the
licensee advised that a revised IST Program Plan was under
preparation for the next 120-month cycle per 10 CFR 50.55a, that the
above test requirements and implementing procedure revisions were
included in that effort, and that the program was scheduled for )
submittal to NRC during June 1987. The licensee appeared to
consider that interim action to address the findings of the'1985
inspection was unwarranted. l
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The inspector further noted that, in addition to other related IST
Program findings, the Augmented System Review and Test Program
Inspection, Unresolved Item 50-312/86-41-26, found that the current ,
'IST Program had apparently expired on April 17, 1985 (as stipulated a
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in the'NRC SER above) and that the licensee.was operating without an-
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approved program. The licensee was unable to provide documentation 1
, that an extension past the above date.had been granted by NRC. !
B. . (Closed) Unresolved Item 86-18-01, Acceptability'of engineering
evaluation of natural frequency of modified valve SFV-22006 and
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effects on dynamic piping analysis -;
.During Inspection 50-312/86-18, the.above valve. developed a body-to- I
bonnet coolant leak. The licensee installed a temporary, external j
clamping ring on the above valve to support injection of a temporary 1
l- sealant (Work Request 96425, December 8-9, 1985). Based upon review
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of the licensee's actions and the Updated Safety Analysis Report
, (USAR), Section 4.3, the previous inspector was unable to determine
whether the modification reduced the valve's natural frequency below
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,. the 20 Hz. limit of USAR Section 4.3. The licensee's evaluation did
L lnot' include a' specific review of the effect of the additional weight
l. on natural frequency although it determined that other related
l. effects were negligible.
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As a result of the above finding, SMUD Nuclear Engineering performed I
further engineering eva.luation as documented in Memo DLG-86-619, . I
dated October 17, 1986, finding that the temporary modification had l
no effect on the natural frequency of the valve.
The inspector reviewed calculation Z-PLS-M4093, Letdown Cooler Inlet'
Piping Stress Summary, revision 3, Appendix A, dated June 16, 1986,
and revision 4, dated December 18, 1986. I
These calculations showed that the original frequency was about 40
Hz. and was primarily dependent upon the cantilevered mass of the
valve actuator and its moment arm. The clamping ring was installed
on the' valve body (the supported " base" of the valve / actuator
combined mass) and had no effect on the natural frequency. The ;
calculations further showed all other dynamic analysis
considerations to be well within design stress limits.
Permanent repairs were completed on the subject valve'on February
13, 1986, and the temporary clamping ring removed. Based on the
above noted licensee evaluation and permanent correction of the
condition noted, the unresolved item was closed.
No violations or deviations were identified.
C. (Closed) Unresolved Item 86-21-07, Motor Operated Valve Torque
Switch Setpoints not Incorporated in Drawings
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The previous inspection found that Drawing E1012, Motor Operated
Valve Data, did not include required torque switch settings for
valves:
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HV-20003, DHS ECCS Long Term Cooling Valve (DHR Test to-RB
Sump)
HV-23801, DHS ECCS Long Term Cooling Valve (DHR Test to RB
Sump)
HV-23802, Alternate Pressurizer; Spray Supply Valve
LV-36005, Auxiliary Boiler Isolation
LV-36505, Auxiliary Boiler Isolation
The inspector reviewed the following documents and discussed the
licensee's programs with licensee Maintenance, QC, Licensing and
contractor representatives:
QCI Tracking Item Recommendation Report 20.0136, April 27,
1987;
Memo, DLG-86-712, Nuclear Engineering to Nuclear Licensing,
November 4, 1986, forwarding Engineering Change Notices (ECNs)
for the subject valves;
ECNs R-0968C, R-0976AU, R-0976AV, R-0968AM, and R-0968AN for
the subject valves;
Coordinated Commitment ~ Tracking System Transmittal, CCTS #
T860818010C, Unresolved Item 86-21-07;
E-1012, Sheets 133, 166, and 167 incorporating Drawing Change
Notices 0 and 0A for HV-20003, -23801, -23802.
Procedure E-117C, Limitorque Valve Actuator SMB and SB Models
Electrical Refurbishment and Corrective Maintenance, revision
1.
The licensee has extensively revised Drawing E-1012. The drawing
formerly had multiple valves' data on each drawing sheet; the new
drawing format provides one sheet for each valve with considerably
more information than previously provided. l
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The current process for developing acceptable torque switch settings
involves:
Calculation of the maximum design basis differential pressure i
for each valve, then calculation of the maximum thrust and I
torque values. I
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Incorporation of data responsive to IE Bulletin 85-03, " Motor j
Operated Valve Common Mode Failures During Plant Transients Due l
to Improper Switch Settings," and IE Information Notice 86-29, i
" Effects of Changing Valve Motor Operator Switch Settings." l
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Revision of E-1012 sheets to delete old information and create
the new sheets for each valve with the newly calculated (and
other) data.
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Revision of affected elementary and wiring diagrams.
Performance of refurbishing and resetting per E-117C and the l
M0 VATS test program to confirm the switch settings. ;
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Engineered torque switch setpoint values are now provided for the
subject' valves and will be confirmed via the maintenance and testing
program discussed above. The licensee's program appears acceptable
in this regard; this item is closed.
No violations or deviations were identified.
5. Onsite Follow-up of Written Reports of Non-routine Events at Power
Reactors
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A. (Closed) LER 80-46-T1, Overspeed Trip Lever on Auxiliary Feedwater
Pump Turbine Found Tripped
On November 4, 1980, the overspeed trip lever for Auxiliary
Feedwater Pump P318 turbine was found tripped during routine
surveillance. It was thought that the lever may have tripped due to
vibration from running the pump with its motor. drive. A daily
visual check of the trip lever was instituted.
On November 21, 1980, the trip lever was again found in the trip
position even though the pump had not been operated since the
November 4 instance; no cause could be determined.
Although the motor drive of the dual drive pump remained available,
the motor drive does not receive an automatic start signal and must
be started manually should an Auxiliary Feedwater initiation signal ,
occur with the turbine drive tripped.
LER 80-46 revision 1, dated February 9, 1987, described a visual
indication device installed on the turbine trip lever and
incorporation of the overspeed trip device status into the IDADS ]
computer monitoring system.
During this inspection, the IDADS computer point display Z1622 was
demonstrated by a licensee shift supervisor. The computer point is
annunciated in the control room and the status of the trip device
(tripped /untripped, alarm in/out, circuit signal quality, etc.) is q
video displayed and the point is equipped with both audible and '
visual alarms.
The turbine trip valve, pump and shift logs were inspected and the
use of the visual indicator was discussed with a Shift Supervisor.
The licensee currently includes a visual check of the indicator on
the shift logs but the LER advised that the licensee no longer
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considers this check to be~a mandatory requirement based on the
' addition of the IDADS point.
TheLinspector noted that the IDADS. system is considered non-safety
related and plant operations may continue if the' system is
unavailable or otherwise removed from-service. Casualty Procedure
C.39, Loss of IDADS, Revision 1, effective April 8, 1986, Enclosure
3.4, Item 3, provides for hourly verification.of the overspeed trip
reset condition during.IDADS outages. iThe root cause_for the AFW
- pump trips could not be determined. .The" licensee's corrective.
action regarding monitoring of trip valve status appeared to be
appropriate for the condition reported. The LER was closed.
B. (Closed) LER 85-12-LO/L1, Loss of Reactor Building Integrity
i' While in hot shutdown conditions and during zero power physics
testing on June 16,- 1985, ' reactor building integrity was lost when l
both personnel air lock hatches were simultaneously opened.
' Containment integrity in these conditions is required by Technical
. Specification 3.6.1. The initial NRC followup of this report is
documented in'NRC Inspection Report 50-312/85-27 and identifies
NRC's W ncerns regarding. repetitive.similar occurrences (this was
the' fourth-such instance; reference LERs 83-19, 82-01, 81-13).
Reporting Timeliness
The licensee's initial written report committed to submit the.
results of a Root Cause Analysis for the incident to NRC by
Octobe r . 31^, .1986. The Root Cause Analysis, discussed below, was
completed on September 26, 1985, was approved on November 8, 1985,
and was issued via. memo GAC 85-895, on November 18, 1985. Its
results were not submitted to NRC until revision 1 to LER 85-12 was
issued on November 6, 1986.
The inspector further noted that the LER states that the event
occurred during " cold shutdown" while performing "zero power physics
testing." The plant was actually in " hot shutdown conditions" and-
during zero power physics testing.
The licensee's failure to meet a commitment to NRC is similar in
nature to: Deviation Item 87-11-01, failure to meet commitments for.
procedure revisions, issued on April 20, 1987. The licensee's
response to the Deviation item was pending at the time of this
inspection. The NRC letter and report forwarding the Deviation j
required the licensee to address general weaknesses in the '
licensee's program for tracking commitment schedules and notifying
NRC of any changes.
Accordingly, no enforcement item will be issued for the late
submittal of LER 85-12 followup'information on the basis that the
response to Item 87-11-01 above should also'be responsive to this
item. The SMUD licensing representative was advised of the above
and the need.to ensure that~the Item 87-11-01 response effectively
dealt with'all issues.
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Corrective Action Efficacy
As noted above, the subject event was the fourth in a series of
similar e_ vents. The licensee Root Cause Analysis, No. 85-14, .
identified the following root causes:. (1) inadequate maintenance, I
(2)' inadequate personnel training in door operation, and (3) prior
dismantling of the door audible alarm circuit. The report.further
identified multiple deficiencies and weakness contributing to the !
-incidents and specified a Corrective Action Plan, including: ;
(1) Implementation of training on proper operation of the door for
all vital badged personnel by December 31, 1985.
(2) -Installation of door rebound devices (snubbers) by the Cycle 9
Outage (next refueling).
(3) Reactivation of the audible door alarm circuit (no commitment
date provided).
(4) Establishment of maintenance requirements and intervals versus
door usage (no commitment date provided).
(5) Conduct'a " human factors" review of door handwheel orientation, j
use of signs and labels, etc. (no commitment date provided). !
(6) Evaluate the desirability of performing modifications
recommended by the door manufacturer (no commitment date
, provided). j
Revision 1 to LER 85-12 discussed Items 1 through 5 above stating
that they would be accomplished by the Cycle 8 refueling outage, !
currently scheduled for September 15, 1988. Item 6 was not
addressed. The licensee report further indicated that routine
testing of the door and airlock per the Technical Specification (TS) l
Surveillance Requirements will " continue to provide assurance of the
containment integrity of the reactor building personnel access
door." The LER notes that TS 3.6.1 and SP 205.02 require that the
doors be tested only within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after each opening.
-The inspector further noted that the Plant Buildings and Structures
System Investigation Report (SIR), revision 0, performed per QCI-12,
Systems Review and Test Program (SRTP) identified this matter as
Problem No. 5 (Tracking No. 20.0430). The SIR identified only items
1, 3, and 5 of the Root Cause Analysis as required resolutions. The
SIR noted that, "...until all equipment and programmatic changes are
fully implemented, specially trained personnel must perform airlock
door manipulations during those outage conditions that require i
containment integrity...." The SIR categorized the item as Priority i
3, not requiring further action prior to restart. The inspector
could identify no such actions planned or in progress.
In an attempt to reconcile the differences between the LER, the SIR
and the Root Cause Analysis Corrective Action Plan and to establish
whether any further interim actions were planned, the inspector 1
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requested additional information from the SMUD licensing
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representatives and the. Plant Buildings and Structures System
Engineer. Additional information was not available from the plant
staff and a meeting was requested with the Plant Manager to discuss
the-inspector's concerns.
During.a meeting with the Plant Manager and his staff on May 7, the
inspectors:were advised that the containment airlock vendor will be .
contracted to provide door refurbishment, assistance in establishing j
maintenance criteria, and maintenance personnel training. These l
activities are scheduled for the summer, 1987, prior to plant
restart. .
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The vendor apparently believes that door refurbishment and
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maintenance will essentially eliminate the mechanical problems which I
contributed to this and the prior incidents. The licensee advised
that following these actions, door operation would be evaluated and i
additional actions taken, as necessary, if the problem indicators
recurred. The Plant Manager emphasized that the Systems Review and
Test Program had established that the airlock problems had been-
categorized as Priority 3 actions and that the above interim actions i
were not to be considered as a commitment to implement any actions
prior to plant restart.
The inspectors requested that the above interim actions be
documented as formal commitments in a revised, supplemental LER.
The inspectors stipulated that the prior door failure scenarios had
the potential for simultaneous inner and outer airlock door failures
which could prevent either or both doors from being quickly
reclosed, e.g.', . failure of actuating gears, interlocks, etc. , as
previously experienced. This would result in a serious, extended
breach of containment integrity. l
The Plant Manager stated that the SRTP disagrees with the
inspector's conclusions, that such a commitment would be an-
exception to licensee policy subject to approval by the Chief
Executive Officer (CEO), Nuclear, and that he would advise the l
inspectors of the CE0's position.
The inspectors advised the Plant Manager that the licensee's
proposed long-term corrective actions will not be implemented for
one complete operating cycle and no interim or compensatory actions
are planned and the licensee's plans are considered inadequate to
prevent recurrence in a timely manner. Routine surveillance testing
stipulated by the LER is considered. inadequate to prevent recurrence
and would serve only to provide after.the fact identification of
improperly sealed doors with the alarm (and in some past cases,
interlocks) ineffective.
Subsequent to the NRC exit meeting, on May 12, 1987, the Plant
Manager informed the inspector by telephone that LER 85-12 will be
revised to provide the following corrective action prior to restart:
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The containment airlock vendor will be contracted to train
licensee personnel on vendor experience with the doors.
A " maintenance tune-up" and preventative maintenance will be
performed to provide recommended corrective action for the
doors.
Recommended corrective actions will be evaluated for required
performance prior to restart.
LER 85-12 revision 0 will be administratively closed. Revision 1 of
LER 85-12 will be administratively closed upon receipt of revision 2
of LER 85-12. Revision 2 of LER 85-12 will be evaluated for further
inspection followup.
No violations or deviations were identified.
C. Licensee Event Reports 85-16, 86-10, 87-13, 87-76 - Cable Raceway
Tracking System (CRTS) Related Items
On April 3,1987, the licensee submitted to the NRC a Wire and Cable
Program Description and Action Plan. On May 1, 1987, RV provided
the licensee written comments regarding the plan. The inspector met
with the licensee to discuss the RV comments. In addition, on May
6, 1987, the licensee met with representatives from NRR and RV to I
discuss the program. As a result of the RV comments and comments
during the May 6, 1987, meeting, the Engineering Department Manager
stated that a revision to the CRTS Program would be submitted to the
NRC.
No violations or deviations were identified.
6. 10 CFR Part 21 Reports ,
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A. (Closed) 10 CFR 21 Report 86-03, Incorrectly assembled Woodward
Governors supplied by Transamerica Delaval, Inc. (TDI) for Emergency
Diesel Generators (EDGs)
In a letter dated August 10, 1983, TDI advised that Woodward
governor internals provided on new TDI EDGs at Rancho Seco had been
j incorrectly assembled. If the governors were not~ modified, the
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possibility existed that the engines may overspeed on an automatic
start. ;
The inspector reviewed the following documents confirming that the
governors had been returned to the manufacturer, properly rebuilt
and reinstalled on the EDGs.
TDI Trip Report, Visit to Rancho Seco, September 16, 1983,
identifying the initial governor problem and recommending
rework by Woodward.
SMUD letter to TDI, September 23, 1983, confirming TDI
arrangements for reworking the governor and requesting TDI's
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approval of a SMUD governor removal / replacement procedure
(enclosed).
TDI letter to SMUD, October 28, 1983, confirming governor
rework arrangements and approving the above SMUD procedure.
SMUD Shipping Notice No. 50557/P.O. BA1123, December 15, 1983,
documenting shipment of governors to Woodward Governor Co. for
rework.
SMUD Expeditors Report, March 19, 1984, documenting shipping
plans for return of governors.
Receipt Inspection Plan No. QA1203-81, Diesel Generator Parts,
March 2, 1984, documenting receipt of Woodward governors.
TDI Certificate of Compliance for gov'ernors, March 30, 1984.
Receiving Inspection Data Report No. QA1203-81, May 21, 1984,
documenting results of receipt inspection.
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Quality Verification Document Requirements checklist, March 30, l
1984, documenting verification of test reports, seismic l
qualification documentation, certificate of conformance, etc.
The above documentation confirmed that the governors had been
repaired as required to correct.the problem identified by the
subject 10 CFR 21 Report. The inspector verified, by visual
inspection of serial numbers and the installed governor units that
the governors are installed on the engines. This item is closed.
No violations or deviations were identified.
B. (Closed) 10CFR21 Report 86-13-P, Missing Lockwelds on Anchor
Darling Check Valves.
The Anchor Darling Valve Company reported that lock welds were found
missing on 150 and 300 class check valves' hinge support, hinge
support capscrews, and hinge support / bonnet interface. The report
recommended inspection and repair techniques.
This item was previously reviewed during Region V inspection
50-312/86-38. That inspection confirmed that the licensee had
implemented an inspection and repair program for twenty-two
potentially affected valves. Six valves had been inspected at that j
time.
By the time of this inspection, the licensee had inspected fifteen
(total) valves. Six of the fifteen were found to have either
cracked tack welds or minor cracks in hinge bushings, all of which
have been repaired. The remaining nine valves inspected were
satisfactory.
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The licensee's' evaluation of the as-found conditions determined that {
none of the defects would have affected valve. operation. The cracks '
were characterized as small and in locations which would not result
in loss of valve assembly integrity. The inspector reviewed these
determinations with the responsible licensee mechanical maintenance
engineer and found the licensee's findings and conclusions
reasonable. j
Inspection of the remaining valves is being tracked by the !
licensee's Coordinated Commitment Tracking System (No..T8611061010) l
and is scheduled for completion prior to restart. Maintenance Work !
Requests have been issued for all the valves. This item is closed. ;
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No violations or deviations were identified.
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C. (0 pen) 10 CFR 21 Report 86-14-P, Failure of Automatic Sprinkler
Corp. of America (ASC0A) Model C Deluge Valves
This report involves the potential for failure of Model C fire
protection deluge valves to actuate on demand due to binding of
bronze valve latch arms. The latch arm problem applies only to six
inch valves. ASC0A notified NRC and potentially affected licensees
via the various letters below:
June 4, 1984, Letter to NRC, Additional Information re IE
Information Notice 84-16, " Failure of Automatic Sprinkler
System Valves to Operate."
November 19, 1985, Letter to NRC, Model C Deluge Valves.
December 1, 1985, Letter to licensees, Model C Deluge Valves.
December 12, 1985, Letter to licensees, Model C Deluge Valves.
April 7, 1986, 10 CFR 21 Report to NRC, Model C Deluge Valves.
April 18, 1986, Letter to NRC, Followup on April 7, 1986 10 CFR
21 Report.
- November 5, 1986, Letter to licensees, Model C. Deluge Valves .
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and Mercury Check Devices.
(* Note: In this letter, ASC0A also advised licensees of
p;tential failure of Mercury Check Devices due to plastic parts
leaking. The Mercury Check Devices are used to sense
temperature rate-of-rise to prevent spurious sprinkler syster.,
actuation on slow ambient temperature increases not resulting
from fire.)
The licensee has received and evaluated the above correspondence. '
The licensee's fire insurance underwriter has also addressed
recommendations and licensee actions for the above in an August 1986
Loss Prevention Report. The licensee has determined that thirteen
Type C valves are installed at Rancho Seco. Six of the valves are
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the 6" size subject'to the potential latch failures. The remaining 1
seven valves are 2-1/2" valves which ASC0A advises are not affected {
by the latch failures but may be. subject to the Mercury Check Device )
problems.
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The. licensee has determined by review of procurement records'that d
none'of the subject valves (by serial number) at Rancho Seco were !
initially purchased with bronze latch arms. The licensee is further
performing a review of valve maintenance history to identify past
latch failures and whether bronze _ replacement parts were ever-
installed. To date, about 75% of the maintenance records have'been
. reviewed with no latch failures nor bronze part installations found.
-The licensee plans to physically inspect the valves (see further
discussion below) to further confirm the absence of bronze latch arm
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parts. l
The various ASC0A letters recommend that the valve latch arms be ,
lubricated periodically. The licensee issued. Work Request 111958 on
March 19, 1986 to accomplish this. As.of May 1, 1987, this
lubrication'had not yet been accomplished; Work Requests for
inspection lof.6" valve latch arms and replacement of Mercury Check 1
Devices are planned but not' issued-and are to be performed l
concurrently with the lubrication.
The cognizant' licensee fire protection engineer advised that these
items are not prioritized as plant restart prerequisites and will be j
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accomplished by September 1987. This is consistent with the Fire '
Protection System Investigation Report prioritization of the item.
This 10 CFR 21 report will remain open pending further evidence of
implementation of the licensee's program lubrication, inspection,
and check device replacement.
.No violations or deviations were' identified.
D. (Closed)'10 CFR 21 Report 86-15-P, Damaged Motor Leads in Limitorque
Valve Operators
(Closed) 10 CFR 21 Report 86-18-P, Cracked Limit Switch Rotors in
Limitorque Valve Operators
(Closed) 10 CFR 21 Report 87-07-P, Warped Limit Switch Rotors in
Limitorque Valve Operators
These reports detailed defects in Limitorque motorized valve-
operators. Report 86-15 involved damaged leads found'in replacement
valve operators. Reports 86-18 and 87-07 identified defects in
limits switches during inspections of installed valves with various
service times. ?#
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The licensee has incorporated the above report items into the
ongoing motor operated valve refurbishment program. Reports 86-18 :
and 87-07 were identified by this licensee,
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Provisions to address each of the above are included in Procedure
E-117C, Limitorque Valve Actuator SMB and SB Models Electrical
Refurbishment and Corrective Maintenance Procedure, revision 1.
Instructions for inspection and replacement of damaged motor and
brake leads are included in Sections 6.2.7.8 and 6.2.9.
Instructions for inspection and replacement of cracked or warped
. limit switch rotors (and unqualified items) are included in Section
6.2.1.1.13.1.
The inspector reviewed completed work packages for the following
valves, confirming that: the applicable procedure sections were
accomplished, deficiencies were identified and corrected, proper
replacement parts were used and properly installed, and the
activities were subject to Quality Control inspection. The licensee
advised that, to date, 27 limit switch rotors have been replaced
(count based on stores withdrawal records). j
Work Request 121773, Valve HV 26046, DHS Cross Tie "A",
completed April 24, 1987
Work Request 120371, Valve HV 26007, "A" DHS Cooler Outlet to
Pump, completed April 24, 1987
Work Request 120364, Valve SFV 50009, NSW from A500A, completed
April 24, 1987
Work Request 120355, Valve HV 26105, Emergency Sump to DH Pump
261A, completed April 24, 1987.
No discrepancies were identified. The licensee has acceptably
incorporated the considerations of the above reports into their
programs. The above noted 10 CFR 21 items are closed.
No violations or deviations were identified.
E. (Closed) 10 CFR 21 Report 86-25-P, Unqualified Replacement Terminal
Strips for Limitorque Motor Actuators
The subject report (filed by Arkansas Power and Light) advised that
Buchanan 724 terminal strips had been supplied by Limitorque as in
kind, qualified replacements for Buchanan 524 strips installed in
valve motor operators. Environmental qualification could not be
established for the Model 724 strips.
The inspector reviewed SMUD Memo BK 86-089, dated December 22, 1986,
which documented the environmental qualification status of this
facility's motor operated valves. The memo noted that all terminal
blocks had been removed from 70 of 99 of the valves and the affected
leads spliced with environmentally qualified splices. Twenty-five
additional valves had not been previously modified and are being
modified per ECN R-0699 during the current outage.
The inspector also reviewed Calculation Sheet No. L-EQP-E0133, dated
September 25, 1986, which identified the modifications for the
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subsequent modifications and included replacement of the internal
wiring and terminal blocks with qualified wiring and splices. Work
packages for selected valves were reviewed as documented elsewhere
in this report, confirming that the valve refurbishment procedures,
as implemented resulted in splice installation. Additionally,
Procedure NEP 4118 includes provisions to ensure that newly l
purchased valves are site modified to meet the above configuration '
criteria prior to service. Accordingly, this 10 CFR 21 report is
not applicable to Rancho Seco. ,
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No violations or deviations were identified. l
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7. Task: Allegation ATS No. RV-87-A-024 (Closed) ]
A. Characterization !
A Rancho Seco employee was working on radiation monitoring systems
without previous experience or training. ,
B. Implied Significance to Design, Construction or Operation
Work on safety-related systems was being performed by unqualified
personnel.
C. Assessment of Safety Significance
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A review of SMUD records confirmed that the alleged individual was
an employee of Volt Technical Services performing contractor work
for the Rancho Seco Nuclear Maintenance Department in the Instrument
and Control (I&C) area. Training and Qualification records provided
by SMUD and interviews with the individual and two levels of SMUD
supervision indicate that-the individual had been trained and
qualified at another_ Region V Reactor Plant facility and was
undergoing an on-the-job training program for Rancho Seco I&C
technicians. The individual and two levels of his supervision
stated that he had not performed work on the radiation monitoring j
system. In addition, statement from the individual and his
supervisors indicate that all safety related work by contract
personnel are assigned with accompanying SMUD personnel.
D. Staff Position
Based on the records provided by the licensee and interviews with
the individual and two SMUD supervisors, the allegation was not i
confirmed, and is closed.
E. Action Required l
None. 1
8. Exit Interview I
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The inspection scope and findings were summarized on May 8, 1987, with l
those persons indicated in paragraph 1 above. The inspector described '
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'the areas inspected and discussed in detail the inspection findings. No
dissenting comments were received from the licensee. The following new
item was: identified during this inspection:
Violation 87-16-01 - Inadequate Inservice Testing Procedures for
Valve Full Stroke Testing, paragraph 4.A,
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