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Category:INSPECTION REPORT
MONTHYEARIR 05000344/19990061999-09-0909 September 1999 Insp Rept 50-344/99-06 on 990630-0701,21 & 0404-08.No Violations Noted.Major Areas Inspected:Organization,Mgt & Cost Controls & Decommissioning Performance & Status Review, Insp of Transportation Activities & Maint & Surveillance IR 05000344/19990041999-05-0707 May 1999 Insp Repts 50-344/99-04 & 72-0017/99-02 on 0322-25 & 29- 0408.Non-cited Violations Noted.Major Areas Inspected: Licensee Readiness to Load Sf Into Independent ISFSI IR 05000344/19990051999-05-0707 May 1999 Insp Repts 50-344/99-05 & 72-0017/99-04 on 990419-22.No Violations Noted.Major Areas Inspected:Decommissioning Performance & Status Review IR 05000344/19990031999-04-20020 April 1999 Insp Repts 50-344/99-03 & 72-0017/99-03 on 990301-04,15-18 & 22-25.No Violations Noted.Major Areas Inspected:Site Tours & Review of Licensee Preparedness for ISFSI Operations IR 05000344/19990021999-04-13013 April 1999 Insp Rept 50-344/99-02 on 990329-0401.No Violations Noted. Major Areas Inspected:Licensee Physical Security Program, Including Access Authorization,Alarm Station & Communications & Access Control of Personnel & Packages IR 05000344/19980041999-01-21021 January 1999 Insp Repts 50-344/98-04 & 72-0017/98-01 on 981106-07 & 1202-10.Violations Noted.Major Areas Inspected: Decommissioning & Dismantlement Activities at Plant Site IR 05000344/19982021998-10-30030 October 1998 Insp Rept 50-344/98-202 on 980831-0903.No Violations Noted. Major Areas Inspected:Safety Review Program Re Modular Sf Cooling Sys & Maint Program IR 05000344/19980031998-08-25025 August 1998 Insp Rept 50-344/98-03 on 980727-30.No Violations Noted. Major Areas Inspected:Sfp Safety,Ore,Decommissioning Performance & Status Review,Organization Mgt & Cost Controls & Solid Radioactive Waste & Transport IR 05000344/19980021998-07-0101 July 1998 Insp Rept 50-344/98-02 on 980601-04.No Violations Noted. Major Areas Inspected:Activities Including Spent Fuel Pool Safety,Occupational Radiation Exposure & Decommissioning Performance & Status Review IR 05000344/19980011998-05-22022 May 1998 Insp Rept 50-344/98-01 on 980504-07.No Violations Noted. Major Areas Inspected:Specific Areas of Licensee Physical Security Program IR 05000344/19982011998-04-29029 April 1998 Insp Rept 50-344/98-201 on 980223-26.No Violations Noted. Major Areas Inspected:Safety Review Program & Insp follow- Up ML20199D7511998-01-23023 January 1998 Cover Page for Insp Rept 50-344/97-05 on 971201-03, Inadvertently Omitted in Original Submittal ML20199F0361998-01-23023 January 1998 Insp Rept 50-344/97-05 on 971201-03.Violations Noted.Major Areas Inspected:Status of Dismantlement Activities,Changes to Util Emergency Exercise Plan Implementing Procedures & Decommissioning IR 05000344/19970041997-11-21021 November 1997 Insp Repts 50-344/97-04 & 72-0017/97-04 on 970929-1002.No Violations Noted.Major Areas Inspected:Fuel Debris Processing,Dry Cask Storage & Control of Radioactive Matl. Insp Repts Reissued Due to Omission of Pages 4 & 5 ML20198N3461997-10-31031 October 1997 Insp Repts 50-344/97-04 & 72-0017/97-04 on 970929-1010.No Violations Noted.Major Areas Inspected:Fuel Debris Processing Preparation for Pouring Concrete for Portion of ISFSI Pad & Control & Release of Contaminated Matl IR 05000344/19970031997-09-0909 September 1997 Insp Repts 50-344/97-03 & 72-0017/97-03 on 970721-24. Violations Noted.Major Areas Inspected:Control of Radioactive Material,Spent Fuel Pool Debris Project,Dry Cask Storage,Spent Fuel Pool & Health Physics Activities IR 05000344/19970021997-05-0606 May 1997 Insp Repts 50-344/97-02 & 72-0017/97-02 on 970414-17.No Violations Noted.Major Areas Inspected:Health Physics, Training Program,Spent Fuel Pool,Independent Spent Fuel Storage Installation & Fuel Building Crane Tests IR 05000344/19970011997-02-25025 February 1997 Insp Repts 50-344/97-01 & 72-0017/97-01 on 970204-06. Violations Noted.Major Areas Inspected:Review of Radiation Protection Program,Compliance W/Ts,Operations Involving Licensee Insp of Spent Fuel & Quality Assurance Program IR 05000344/19960081997-02-13013 February 1997 Insp Repts 50-344/96-08 & 72-0017/96-02 on 961104-07.No Violations Noted.Major Areas Inspected:Decommissioning Activities Related to Ongoing Efforts to Decontaminate Facility & Place Spent Fuel in Storage at ISFSI IR 05000344/19960051997-02-13013 February 1997 Correction to Insp Repts 50-344/96-05 & 72-0017/96-02. Requests That Encl Pages Be Added as Last Two Pages of Listed Insp Rept IR 05000344/19930151993-12-14014 December 1993 Insp Rept 50-344/93-15 on 931115-18.No Violations Noted. Major Areas Inspected:Operational Status of EP Program & of Annual EP Exercise IR 05000344/19930141993-12-0606 December 1993 Insp Rept 50-344/93-14 on 930930-1112.Violations Noted.Major Areas Inspected:Resident Insp of Operational Safety Verification,Maintenance,Surveillance & follow-up of Previously Identified Items IR 05000344/19930121993-10-22022 October 1993 Insp Rept 50-344/93-12 on 930817-0929.No Violations or Deviations Noted.Major Areas Inspected:Operational Safety Verification,Maint,Surveillance & Followup of Previously Identified Items IR 05000344/19930131993-09-24024 September 1993 Insp Rept 50-344/93-13 on 930913-17.No Violations Noted. Major Areas Inspected:Listed Portions of Licensee Physical Security Program IR 05000344/19930111993-09-0303 September 1993 Insp Rept 50-344/93-11 on 930706-0816.No Violations or Deviations Noted.Major Areas Inspected:Operational Safety Verification,Maint,Surveillance & Followup of Previously Identified Items IR 05000344/19930101993-08-12012 August 1993 Insp Rept 50-344/93-10 on 930706-08.No Violations Noted. Major Areas Inspected:Chemistry & Radiation Protection Program Organization & Staffing & Solid Radwaste Storage IR 05000344/19930081993-06-25025 June 1993 Insp Rept 50-344/93-08 on 930422-0531.No Violations Noted. Major Areas Inspected:Operational Safety Verification,Maint, Emergency Preparedness & Followup of Previously Identified Items IR 05000344/19920321993-01-0808 January 1993 Insp Rept 50-344/92-32 on 921027-1207.Violations Noted.Major Areas Inspected:Maintenance,Surveillance,Event Followup & Followup of Previously Identified Items IR 05000344/19920341992-12-31031 December 1992 Meeting Rept 50-344/92-34 on 921201.Areas Discussed:Sg Tube Leak & Licensees Subsequent Insp of SGs IR 05000344/19920331992-12-29029 December 1992 Insp Rept 50-344/92-33 on 921207-11.No Violations or Deviations Noted.Major Areas Inspected:Licensee Erosion/ Corrosion Program Activities,Including Followup of Previously Identified Items IR 05000344/19920281992-12-21021 December 1992 Insp Rept 50-344/92-28 on 921109-1215.No Violations or Deviations Noted.Major Areas Inspected:Rev 7 to Emergency Plan Implementing Procedure EP-001, Emergency Classification IR 05000344/19920301992-11-25025 November 1992 Insp Rept 50-344/92-30 on 920915-1026.Violations Noted. Major Areas Inspected:Operational Safety Verification, Maintenance,Surveillance & Followup of Previously Identified IR 05000344/19920311992-11-10010 November 1992 Insp Rept 50-344/92-31 on 920928-1002.No Violations Noted. Major Areas Inspected:Environ Monitoring,Cr Ventilation & Control of Radwaste Activities IR 05000344/19910161991-06-0404 June 1991 Insp Rept 50-344/91-16 on 910506-16.No Violations or Deviations Noted.Major Areas Inspected:Proposed Rev 6 to Emergency Procedure (EP)-001, Emergency Classification IR 05000344/19900291990-11-0505 November 1990 Insp Rept 50-344/90-29 on 900902-1006.Violations Noted.Major Areas Inspected:Operational Safety Verification & Maint IR 05000344/19900201990-10-12012 October 1990 Revised Section 1, Persons Contacted, to Insp Rept 50-344/90-20 IR 05000344/19900251990-09-18018 September 1990 Insp Rept 50-344/90-25 on 900820-24.No Violations Noted. Major Areas Inspected:Inspector Followup Items,Lers & Gaseous Radwaste Sys IR 05000344/19900261990-09-0505 September 1990 Partially Withheld Enforcement Conference Rept 50-344/90-26 on 900830 (Ref 10CFR2.790).Major Areas Discussed: Description of Violation Associated w/900719-0817 Security Insp,Nrc Concerns & Corrective Action Planned & Implemented ML20056B2531990-08-20020 August 1990 Partially Withheld Security Insp Rept 50-344/90-23 on 900719-0817 (Ref 10CFR2.790).Violation Noted.Major Areas Inspected:Access Control of Personnel & Packages & Entry of Unauthorized Firearm Into Plant Protected Area ML20059C1991990-08-16016 August 1990 Insp Rept 50-344/90-21 on 900609-0721.Violation Noted Re Inattentive Fire Watch.Major Areas Inspected:Operational Safety Verification,Maint,Surveillance,Event Followup,Sys Engineering & Open Item Followup IR 05000344/19900221990-07-20020 July 1990 Mgt Meeting Insp Rept 50-344/90-22 on 900615.Major Areas Discussed:Results of NRC SALP for 890101 Through 900331 ML20059A4051990-07-20020 July 1990 Insp Rept 50-344/90-17 on 900604-07.No Violations or Deviations Noted.Major Areas Inspected:Licensee Actions in Response to Issues Identified in Insp Rept 50-344/89-12 IR 05000344/19900191990-07-11011 July 1990 Insp Rept 50-344/90-19 on 900611-15.Violations Noted.Major Areas Inspected:Followup of Items of Noncompliance, Occupational Exposure During Outages & Keeping Occupational Exposure ALARA IR 05000344/19900161990-07-0606 July 1990 Insp Rept 50-344/90-16 on 900506-0609.No Violations or Deviations Noted.Major Areas Inspected:Safety Verification, Refueling Activities,Maint,Surveillance & Followup of Previously Identified Items IR 05000344/19900011990-02-12012 February 1990 Mgt Meeting Rept 50-344/90-01 on 900112.Major Areas Discussed:Licensee Improvement Plans for Plant IR 05000344/19890221989-08-31031 August 1989 Enforcement Conference Rept 50-344/89-22 on 890831.No Violation Noted.Major Areas Inspected:Nrc Concerns Developed as Result of Special Insp Rept 50-344/89-19 IR 05000344/19890091989-08-22022 August 1989 Insp Rept 50-344/89-09 on 890522-0609 & 0719-21.Violations Noted.Major Areas Inspected:Effectiveness of Licensee Programs in Identifying & Correcting Design Related Plant Vulnerabilities IR 05000344/19890191989-08-11011 August 1989 Insp Rept 50-344/89-19 on 890712-0808.Violations Noted.Major Areas Inspected:Licensee Actions Following Identification of Debris in Containment Recirculation Sump Prior to & Subsequent to Establishing Containment Integrity ML20245L1471989-08-0303 August 1989 Insp Rept 50-344/89-12 on 890522-0601.Violations Noted.Major Areas Inspected:Review of Licensee NDE Procedures,Nde Records,Radiographs & QA Documentation & NRC NDE Personnel Reperformed Sample NDE on Safety Related Sys & Components ML20245K2741989-08-0303 August 1989 Insp Rept 50-344/89-18 on 890712-14.Violations Noted.Major Areas Inspected:Uresolved Item Re Licensee High Pressure Hydrogen & Nitrogen Storage Facility at Plant & Review of Licensee Implementation of NRC Info Notice 87-020 1999-09-09
[Table view] Category:NRC-GENERATED
MONTHYEARIR 05000344/19990061999-09-0909 September 1999 Insp Rept 50-344/99-06 on 990630-0701,21 & 0404-08.No Violations Noted.Major Areas Inspected:Organization,Mgt & Cost Controls & Decommissioning Performance & Status Review, Insp of Transportation Activities & Maint & Surveillance IR 05000344/19990041999-05-0707 May 1999 Insp Repts 50-344/99-04 & 72-0017/99-02 on 0322-25 & 29- 0408.Non-cited Violations Noted.Major Areas Inspected: Licensee Readiness to Load Sf Into Independent ISFSI IR 05000344/19990051999-05-0707 May 1999 Insp Repts 50-344/99-05 & 72-0017/99-04 on 990419-22.No Violations Noted.Major Areas Inspected:Decommissioning Performance & Status Review IR 05000344/19990031999-04-20020 April 1999 Insp Repts 50-344/99-03 & 72-0017/99-03 on 990301-04,15-18 & 22-25.No Violations Noted.Major Areas Inspected:Site Tours & Review of Licensee Preparedness for ISFSI Operations IR 05000344/19990021999-04-13013 April 1999 Insp Rept 50-344/99-02 on 990329-0401.No Violations Noted. Major Areas Inspected:Licensee Physical Security Program, Including Access Authorization,Alarm Station & Communications & Access Control of Personnel & Packages IR 05000344/19980041999-01-21021 January 1999 Insp Repts 50-344/98-04 & 72-0017/98-01 on 981106-07 & 1202-10.Violations Noted.Major Areas Inspected: Decommissioning & Dismantlement Activities at Plant Site IR 05000344/19982021998-10-30030 October 1998 Insp Rept 50-344/98-202 on 980831-0903.No Violations Noted. Major Areas Inspected:Safety Review Program Re Modular Sf Cooling Sys & Maint Program IR 05000344/19980031998-08-25025 August 1998 Insp Rept 50-344/98-03 on 980727-30.No Violations Noted. Major Areas Inspected:Sfp Safety,Ore,Decommissioning Performance & Status Review,Organization Mgt & Cost Controls & Solid Radioactive Waste & Transport IR 05000344/19980021998-07-0101 July 1998 Insp Rept 50-344/98-02 on 980601-04.No Violations Noted. Major Areas Inspected:Activities Including Spent Fuel Pool Safety,Occupational Radiation Exposure & Decommissioning Performance & Status Review IR 05000344/19980011998-05-22022 May 1998 Insp Rept 50-344/98-01 on 980504-07.No Violations Noted. Major Areas Inspected:Specific Areas of Licensee Physical Security Program IR 05000344/19982011998-04-29029 April 1998 Insp Rept 50-344/98-201 on 980223-26.No Violations Noted. Major Areas Inspected:Safety Review Program & Insp follow- Up ML20199D7511998-01-23023 January 1998 Cover Page for Insp Rept 50-344/97-05 on 971201-03, Inadvertently Omitted in Original Submittal ML20199F0361998-01-23023 January 1998 Insp Rept 50-344/97-05 on 971201-03.Violations Noted.Major Areas Inspected:Status of Dismantlement Activities,Changes to Util Emergency Exercise Plan Implementing Procedures & Decommissioning IR 05000344/19970041997-11-21021 November 1997 Insp Repts 50-344/97-04 & 72-0017/97-04 on 970929-1002.No Violations Noted.Major Areas Inspected:Fuel Debris Processing,Dry Cask Storage & Control of Radioactive Matl. Insp Repts Reissued Due to Omission of Pages 4 & 5 ML20198N3461997-10-31031 October 1997 Insp Repts 50-344/97-04 & 72-0017/97-04 on 970929-1010.No Violations Noted.Major Areas Inspected:Fuel Debris Processing Preparation for Pouring Concrete for Portion of ISFSI Pad & Control & Release of Contaminated Matl IR 05000344/19970031997-09-0909 September 1997 Insp Repts 50-344/97-03 & 72-0017/97-03 on 970721-24. Violations Noted.Major Areas Inspected:Control of Radioactive Material,Spent Fuel Pool Debris Project,Dry Cask Storage,Spent Fuel Pool & Health Physics Activities IR 05000344/19970021997-05-0606 May 1997 Insp Repts 50-344/97-02 & 72-0017/97-02 on 970414-17.No Violations Noted.Major Areas Inspected:Health Physics, Training Program,Spent Fuel Pool,Independent Spent Fuel Storage Installation & Fuel Building Crane Tests IR 05000344/19970011997-02-25025 February 1997 Insp Repts 50-344/97-01 & 72-0017/97-01 on 970204-06. Violations Noted.Major Areas Inspected:Review of Radiation Protection Program,Compliance W/Ts,Operations Involving Licensee Insp of Spent Fuel & Quality Assurance Program IR 05000344/19960081997-02-13013 February 1997 Insp Repts 50-344/96-08 & 72-0017/96-02 on 961104-07.No Violations Noted.Major Areas Inspected:Decommissioning Activities Related to Ongoing Efforts to Decontaminate Facility & Place Spent Fuel in Storage at ISFSI IR 05000344/19960051997-02-13013 February 1997 Correction to Insp Repts 50-344/96-05 & 72-0017/96-02. Requests That Encl Pages Be Added as Last Two Pages of Listed Insp Rept IR 05000344/19930151993-12-14014 December 1993 Insp Rept 50-344/93-15 on 931115-18.No Violations Noted. Major Areas Inspected:Operational Status of EP Program & of Annual EP Exercise IR 05000344/19930141993-12-0606 December 1993 Insp Rept 50-344/93-14 on 930930-1112.Violations Noted.Major Areas Inspected:Resident Insp of Operational Safety Verification,Maintenance,Surveillance & follow-up of Previously Identified Items IR 05000344/19930121993-10-22022 October 1993 Insp Rept 50-344/93-12 on 930817-0929.No Violations or Deviations Noted.Major Areas Inspected:Operational Safety Verification,Maint,Surveillance & Followup of Previously Identified Items IR 05000344/19930131993-09-24024 September 1993 Insp Rept 50-344/93-13 on 930913-17.No Violations Noted. Major Areas Inspected:Listed Portions of Licensee Physical Security Program IR 05000344/19930111993-09-0303 September 1993 Insp Rept 50-344/93-11 on 930706-0816.No Violations or Deviations Noted.Major Areas Inspected:Operational Safety Verification,Maint,Surveillance & Followup of Previously Identified Items IR 05000344/19930101993-08-12012 August 1993 Insp Rept 50-344/93-10 on 930706-08.No Violations Noted. Major Areas Inspected:Chemistry & Radiation Protection Program Organization & Staffing & Solid Radwaste Storage IR 05000344/19930081993-06-25025 June 1993 Insp Rept 50-344/93-08 on 930422-0531.No Violations Noted. Major Areas Inspected:Operational Safety Verification,Maint, Emergency Preparedness & Followup of Previously Identified Items IR 05000344/19920321993-01-0808 January 1993 Insp Rept 50-344/92-32 on 921027-1207.Violations Noted.Major Areas Inspected:Maintenance,Surveillance,Event Followup & Followup of Previously Identified Items IR 05000344/19920341992-12-31031 December 1992 Meeting Rept 50-344/92-34 on 921201.Areas Discussed:Sg Tube Leak & Licensees Subsequent Insp of SGs IR 05000344/19920331992-12-29029 December 1992 Insp Rept 50-344/92-33 on 921207-11.No Violations or Deviations Noted.Major Areas Inspected:Licensee Erosion/ Corrosion Program Activities,Including Followup of Previously Identified Items IR 05000344/19920281992-12-21021 December 1992 Insp Rept 50-344/92-28 on 921109-1215.No Violations or Deviations Noted.Major Areas Inspected:Rev 7 to Emergency Plan Implementing Procedure EP-001, Emergency Classification IR 05000344/19920301992-11-25025 November 1992 Insp Rept 50-344/92-30 on 920915-1026.Violations Noted. Major Areas Inspected:Operational Safety Verification, Maintenance,Surveillance & Followup of Previously Identified IR 05000344/19920311992-11-10010 November 1992 Insp Rept 50-344/92-31 on 920928-1002.No Violations Noted. Major Areas Inspected:Environ Monitoring,Cr Ventilation & Control of Radwaste Activities IR 05000344/19910161991-06-0404 June 1991 Insp Rept 50-344/91-16 on 910506-16.No Violations or Deviations Noted.Major Areas Inspected:Proposed Rev 6 to Emergency Procedure (EP)-001, Emergency Classification IR 05000344/19900291990-11-0505 November 1990 Insp Rept 50-344/90-29 on 900902-1006.Violations Noted.Major Areas Inspected:Operational Safety Verification & Maint IR 05000344/19900201990-10-12012 October 1990 Revised Section 1, Persons Contacted, to Insp Rept 50-344/90-20 IR 05000344/19900251990-09-18018 September 1990 Insp Rept 50-344/90-25 on 900820-24.No Violations Noted. Major Areas Inspected:Inspector Followup Items,Lers & Gaseous Radwaste Sys IR 05000344/19900261990-09-0505 September 1990 Partially Withheld Enforcement Conference Rept 50-344/90-26 on 900830 (Ref 10CFR2.790).Major Areas Discussed: Description of Violation Associated w/900719-0817 Security Insp,Nrc Concerns & Corrective Action Planned & Implemented ML20056B2531990-08-20020 August 1990 Partially Withheld Security Insp Rept 50-344/90-23 on 900719-0817 (Ref 10CFR2.790).Violation Noted.Major Areas Inspected:Access Control of Personnel & Packages & Entry of Unauthorized Firearm Into Plant Protected Area ML20059C1991990-08-16016 August 1990 Insp Rept 50-344/90-21 on 900609-0721.Violation Noted Re Inattentive Fire Watch.Major Areas Inspected:Operational Safety Verification,Maint,Surveillance,Event Followup,Sys Engineering & Open Item Followup IR 05000344/19900221990-07-20020 July 1990 Mgt Meeting Insp Rept 50-344/90-22 on 900615.Major Areas Discussed:Results of NRC SALP for 890101 Through 900331 ML20059A4051990-07-20020 July 1990 Insp Rept 50-344/90-17 on 900604-07.No Violations or Deviations Noted.Major Areas Inspected:Licensee Actions in Response to Issues Identified in Insp Rept 50-344/89-12 IR 05000344/19900191990-07-11011 July 1990 Insp Rept 50-344/90-19 on 900611-15.Violations Noted.Major Areas Inspected:Followup of Items of Noncompliance, Occupational Exposure During Outages & Keeping Occupational Exposure ALARA IR 05000344/19900161990-07-0606 July 1990 Insp Rept 50-344/90-16 on 900506-0609.No Violations or Deviations Noted.Major Areas Inspected:Safety Verification, Refueling Activities,Maint,Surveillance & Followup of Previously Identified Items IR 05000344/19900011990-02-12012 February 1990 Mgt Meeting Rept 50-344/90-01 on 900112.Major Areas Discussed:Licensee Improvement Plans for Plant IR 05000344/19890221989-08-31031 August 1989 Enforcement Conference Rept 50-344/89-22 on 890831.No Violation Noted.Major Areas Inspected:Nrc Concerns Developed as Result of Special Insp Rept 50-344/89-19 IR 05000344/19890091989-08-22022 August 1989 Insp Rept 50-344/89-09 on 890522-0609 & 0719-21.Violations Noted.Major Areas Inspected:Effectiveness of Licensee Programs in Identifying & Correcting Design Related Plant Vulnerabilities IR 05000344/19890191989-08-11011 August 1989 Insp Rept 50-344/89-19 on 890712-0808.Violations Noted.Major Areas Inspected:Licensee Actions Following Identification of Debris in Containment Recirculation Sump Prior to & Subsequent to Establishing Containment Integrity ML20245L1471989-08-0303 August 1989 Insp Rept 50-344/89-12 on 890522-0601.Violations Noted.Major Areas Inspected:Review of Licensee NDE Procedures,Nde Records,Radiographs & QA Documentation & NRC NDE Personnel Reperformed Sample NDE on Safety Related Sys & Components ML20245K2741989-08-0303 August 1989 Insp Rept 50-344/89-18 on 890712-14.Violations Noted.Major Areas Inspected:Uresolved Item Re Licensee High Pressure Hydrogen & Nitrogen Storage Facility at Plant & Review of Licensee Implementation of NRC Info Notice 87-020 1999-09-09
[Table view] Category:INSPECTION REPORT
MONTHYEARIR 05000344/19990061999-09-0909 September 1999 Insp Rept 50-344/99-06 on 990630-0701,21 & 0404-08.No Violations Noted.Major Areas Inspected:Organization,Mgt & Cost Controls & Decommissioning Performance & Status Review, Insp of Transportation Activities & Maint & Surveillance IR 05000344/19990041999-05-0707 May 1999 Insp Repts 50-344/99-04 & 72-0017/99-02 on 0322-25 & 29- 0408.Non-cited Violations Noted.Major Areas Inspected: Licensee Readiness to Load Sf Into Independent ISFSI IR 05000344/19990051999-05-0707 May 1999 Insp Repts 50-344/99-05 & 72-0017/99-04 on 990419-22.No Violations Noted.Major Areas Inspected:Decommissioning Performance & Status Review IR 05000344/19990031999-04-20020 April 1999 Insp Repts 50-344/99-03 & 72-0017/99-03 on 990301-04,15-18 & 22-25.No Violations Noted.Major Areas Inspected:Site Tours & Review of Licensee Preparedness for ISFSI Operations IR 05000344/19990021999-04-13013 April 1999 Insp Rept 50-344/99-02 on 990329-0401.No Violations Noted. Major Areas Inspected:Licensee Physical Security Program, Including Access Authorization,Alarm Station & Communications & Access Control of Personnel & Packages IR 05000344/19980041999-01-21021 January 1999 Insp Repts 50-344/98-04 & 72-0017/98-01 on 981106-07 & 1202-10.Violations Noted.Major Areas Inspected: Decommissioning & Dismantlement Activities at Plant Site IR 05000344/19982021998-10-30030 October 1998 Insp Rept 50-344/98-202 on 980831-0903.No Violations Noted. Major Areas Inspected:Safety Review Program Re Modular Sf Cooling Sys & Maint Program IR 05000344/19980031998-08-25025 August 1998 Insp Rept 50-344/98-03 on 980727-30.No Violations Noted. Major Areas Inspected:Sfp Safety,Ore,Decommissioning Performance & Status Review,Organization Mgt & Cost Controls & Solid Radioactive Waste & Transport IR 05000344/19980021998-07-0101 July 1998 Insp Rept 50-344/98-02 on 980601-04.No Violations Noted. Major Areas Inspected:Activities Including Spent Fuel Pool Safety,Occupational Radiation Exposure & Decommissioning Performance & Status Review IR 05000344/19980011998-05-22022 May 1998 Insp Rept 50-344/98-01 on 980504-07.No Violations Noted. Major Areas Inspected:Specific Areas of Licensee Physical Security Program IR 05000344/19982011998-04-29029 April 1998 Insp Rept 50-344/98-201 on 980223-26.No Violations Noted. Major Areas Inspected:Safety Review Program & Insp follow- Up ML20199D7511998-01-23023 January 1998 Cover Page for Insp Rept 50-344/97-05 on 971201-03, Inadvertently Omitted in Original Submittal ML20199F0361998-01-23023 January 1998 Insp Rept 50-344/97-05 on 971201-03.Violations Noted.Major Areas Inspected:Status of Dismantlement Activities,Changes to Util Emergency Exercise Plan Implementing Procedures & Decommissioning IR 05000344/19970041997-11-21021 November 1997 Insp Repts 50-344/97-04 & 72-0017/97-04 on 970929-1002.No Violations Noted.Major Areas Inspected:Fuel Debris Processing,Dry Cask Storage & Control of Radioactive Matl. Insp Repts Reissued Due to Omission of Pages 4 & 5 ML20198N3461997-10-31031 October 1997 Insp Repts 50-344/97-04 & 72-0017/97-04 on 970929-1010.No Violations Noted.Major Areas Inspected:Fuel Debris Processing Preparation for Pouring Concrete for Portion of ISFSI Pad & Control & Release of Contaminated Matl IR 05000344/19970031997-09-0909 September 1997 Insp Repts 50-344/97-03 & 72-0017/97-03 on 970721-24. Violations Noted.Major Areas Inspected:Control of Radioactive Material,Spent Fuel Pool Debris Project,Dry Cask Storage,Spent Fuel Pool & Health Physics Activities IR 05000344/19970021997-05-0606 May 1997 Insp Repts 50-344/97-02 & 72-0017/97-02 on 970414-17.No Violations Noted.Major Areas Inspected:Health Physics, Training Program,Spent Fuel Pool,Independent Spent Fuel Storage Installation & Fuel Building Crane Tests IR 05000344/19970011997-02-25025 February 1997 Insp Repts 50-344/97-01 & 72-0017/97-01 on 970204-06. Violations Noted.Major Areas Inspected:Review of Radiation Protection Program,Compliance W/Ts,Operations Involving Licensee Insp of Spent Fuel & Quality Assurance Program IR 05000344/19960081997-02-13013 February 1997 Insp Repts 50-344/96-08 & 72-0017/96-02 on 961104-07.No Violations Noted.Major Areas Inspected:Decommissioning Activities Related to Ongoing Efforts to Decontaminate Facility & Place Spent Fuel in Storage at ISFSI IR 05000344/19960051997-02-13013 February 1997 Correction to Insp Repts 50-344/96-05 & 72-0017/96-02. Requests That Encl Pages Be Added as Last Two Pages of Listed Insp Rept IR 05000344/19930151993-12-14014 December 1993 Insp Rept 50-344/93-15 on 931115-18.No Violations Noted. Major Areas Inspected:Operational Status of EP Program & of Annual EP Exercise IR 05000344/19930141993-12-0606 December 1993 Insp Rept 50-344/93-14 on 930930-1112.Violations Noted.Major Areas Inspected:Resident Insp of Operational Safety Verification,Maintenance,Surveillance & follow-up of Previously Identified Items IR 05000344/19930121993-10-22022 October 1993 Insp Rept 50-344/93-12 on 930817-0929.No Violations or Deviations Noted.Major Areas Inspected:Operational Safety Verification,Maint,Surveillance & Followup of Previously Identified Items IR 05000344/19930131993-09-24024 September 1993 Insp Rept 50-344/93-13 on 930913-17.No Violations Noted. Major Areas Inspected:Listed Portions of Licensee Physical Security Program IR 05000344/19930111993-09-0303 September 1993 Insp Rept 50-344/93-11 on 930706-0816.No Violations or Deviations Noted.Major Areas Inspected:Operational Safety Verification,Maint,Surveillance & Followup of Previously Identified Items IR 05000344/19930101993-08-12012 August 1993 Insp Rept 50-344/93-10 on 930706-08.No Violations Noted. Major Areas Inspected:Chemistry & Radiation Protection Program Organization & Staffing & Solid Radwaste Storage IR 05000344/19930081993-06-25025 June 1993 Insp Rept 50-344/93-08 on 930422-0531.No Violations Noted. Major Areas Inspected:Operational Safety Verification,Maint, Emergency Preparedness & Followup of Previously Identified Items IR 05000344/19920321993-01-0808 January 1993 Insp Rept 50-344/92-32 on 921027-1207.Violations Noted.Major Areas Inspected:Maintenance,Surveillance,Event Followup & Followup of Previously Identified Items IR 05000344/19920341992-12-31031 December 1992 Meeting Rept 50-344/92-34 on 921201.Areas Discussed:Sg Tube Leak & Licensees Subsequent Insp of SGs IR 05000344/19920331992-12-29029 December 1992 Insp Rept 50-344/92-33 on 921207-11.No Violations or Deviations Noted.Major Areas Inspected:Licensee Erosion/ Corrosion Program Activities,Including Followup of Previously Identified Items IR 05000344/19920281992-12-21021 December 1992 Insp Rept 50-344/92-28 on 921109-1215.No Violations or Deviations Noted.Major Areas Inspected:Rev 7 to Emergency Plan Implementing Procedure EP-001, Emergency Classification IR 05000344/19920301992-11-25025 November 1992 Insp Rept 50-344/92-30 on 920915-1026.Violations Noted. Major Areas Inspected:Operational Safety Verification, Maintenance,Surveillance & Followup of Previously Identified IR 05000344/19920311992-11-10010 November 1992 Insp Rept 50-344/92-31 on 920928-1002.No Violations Noted. Major Areas Inspected:Environ Monitoring,Cr Ventilation & Control of Radwaste Activities IR 05000344/19910161991-06-0404 June 1991 Insp Rept 50-344/91-16 on 910506-16.No Violations or Deviations Noted.Major Areas Inspected:Proposed Rev 6 to Emergency Procedure (EP)-001, Emergency Classification IR 05000344/19900291990-11-0505 November 1990 Insp Rept 50-344/90-29 on 900902-1006.Violations Noted.Major Areas Inspected:Operational Safety Verification & Maint IR 05000344/19900201990-10-12012 October 1990 Revised Section 1, Persons Contacted, to Insp Rept 50-344/90-20 IR 05000344/19900251990-09-18018 September 1990 Insp Rept 50-344/90-25 on 900820-24.No Violations Noted. Major Areas Inspected:Inspector Followup Items,Lers & Gaseous Radwaste Sys IR 05000344/19900261990-09-0505 September 1990 Partially Withheld Enforcement Conference Rept 50-344/90-26 on 900830 (Ref 10CFR2.790).Major Areas Discussed: Description of Violation Associated w/900719-0817 Security Insp,Nrc Concerns & Corrective Action Planned & Implemented ML20056B2531990-08-20020 August 1990 Partially Withheld Security Insp Rept 50-344/90-23 on 900719-0817 (Ref 10CFR2.790).Violation Noted.Major Areas Inspected:Access Control of Personnel & Packages & Entry of Unauthorized Firearm Into Plant Protected Area ML20059C1991990-08-16016 August 1990 Insp Rept 50-344/90-21 on 900609-0721.Violation Noted Re Inattentive Fire Watch.Major Areas Inspected:Operational Safety Verification,Maint,Surveillance,Event Followup,Sys Engineering & Open Item Followup IR 05000344/19900221990-07-20020 July 1990 Mgt Meeting Insp Rept 50-344/90-22 on 900615.Major Areas Discussed:Results of NRC SALP for 890101 Through 900331 ML20059A4051990-07-20020 July 1990 Insp Rept 50-344/90-17 on 900604-07.No Violations or Deviations Noted.Major Areas Inspected:Licensee Actions in Response to Issues Identified in Insp Rept 50-344/89-12 IR 05000344/19900191990-07-11011 July 1990 Insp Rept 50-344/90-19 on 900611-15.Violations Noted.Major Areas Inspected:Followup of Items of Noncompliance, Occupational Exposure During Outages & Keeping Occupational Exposure ALARA IR 05000344/19900161990-07-0606 July 1990 Insp Rept 50-344/90-16 on 900506-0609.No Violations or Deviations Noted.Major Areas Inspected:Safety Verification, Refueling Activities,Maint,Surveillance & Followup of Previously Identified Items IR 05000344/19900011990-02-12012 February 1990 Mgt Meeting Rept 50-344/90-01 on 900112.Major Areas Discussed:Licensee Improvement Plans for Plant IR 05000344/19890221989-08-31031 August 1989 Enforcement Conference Rept 50-344/89-22 on 890831.No Violation Noted.Major Areas Inspected:Nrc Concerns Developed as Result of Special Insp Rept 50-344/89-19 IR 05000344/19890091989-08-22022 August 1989 Insp Rept 50-344/89-09 on 890522-0609 & 0719-21.Violations Noted.Major Areas Inspected:Effectiveness of Licensee Programs in Identifying & Correcting Design Related Plant Vulnerabilities IR 05000344/19890191989-08-11011 August 1989 Insp Rept 50-344/89-19 on 890712-0808.Violations Noted.Major Areas Inspected:Licensee Actions Following Identification of Debris in Containment Recirculation Sump Prior to & Subsequent to Establishing Containment Integrity ML20245L1471989-08-0303 August 1989 Insp Rept 50-344/89-12 on 890522-0601.Violations Noted.Major Areas Inspected:Review of Licensee NDE Procedures,Nde Records,Radiographs & QA Documentation & NRC NDE Personnel Reperformed Sample NDE on Safety Related Sys & Components ML20245K2741989-08-0303 August 1989 Insp Rept 50-344/89-18 on 890712-14.Violations Noted.Major Areas Inspected:Uresolved Item Re Licensee High Pressure Hydrogen & Nitrogen Storage Facility at Plant & Review of Licensee Implementation of NRC Info Notice 87-020 1999-09-09
[Table view] Category:UTILITY
MONTHYEARIR 05000344/19900291990-11-0505 November 1990 Insp Rept 50-344/90-29 on 900902-1006.Violations Noted.Major Areas Inspected:Operational Safety Verification & Maint IR 05000344/19900201990-10-12012 October 1990 Revised Section 1, Persons Contacted, to Insp Rept 50-344/90-20 IR 05000344/19900251990-09-18018 September 1990 Insp Rept 50-344/90-25 on 900820-24.No Violations Noted. Major Areas Inspected:Inspector Followup Items,Lers & Gaseous Radwaste Sys IR 05000344/19900261990-09-0505 September 1990 Partially Withheld Enforcement Conference Rept 50-344/90-26 on 900830 (Ref 10CFR2.790).Major Areas Discussed: Description of Violation Associated w/900719-0817 Security Insp,Nrc Concerns & Corrective Action Planned & Implemented ML20056B2531990-08-20020 August 1990 Partially Withheld Security Insp Rept 50-344/90-23 on 900719-0817 (Ref 10CFR2.790).Violation Noted.Major Areas Inspected:Access Control of Personnel & Packages & Entry of Unauthorized Firearm Into Plant Protected Area ML20059C1991990-08-16016 August 1990 Insp Rept 50-344/90-21 on 900609-0721.Violation Noted Re Inattentive Fire Watch.Major Areas Inspected:Operational Safety Verification,Maint,Surveillance,Event Followup,Sys Engineering & Open Item Followup IR 05000344/19900221990-07-20020 July 1990 Mgt Meeting Insp Rept 50-344/90-22 on 900615.Major Areas Discussed:Results of NRC SALP for 890101 Through 900331 ML20059A4051990-07-20020 July 1990 Insp Rept 50-344/90-17 on 900604-07.No Violations or Deviations Noted.Major Areas Inspected:Licensee Actions in Response to Issues Identified in Insp Rept 50-344/89-12 IR 05000344/19900191990-07-11011 July 1990 Insp Rept 50-344/90-19 on 900611-15.Violations Noted.Major Areas Inspected:Followup of Items of Noncompliance, Occupational Exposure During Outages & Keeping Occupational Exposure ALARA IR 05000344/19900161990-07-0606 July 1990 Insp Rept 50-344/90-16 on 900506-0609.No Violations or Deviations Noted.Major Areas Inspected:Safety Verification, Refueling Activities,Maint,Surveillance & Followup of Previously Identified Items IR 05000344/19900011990-02-12012 February 1990 Mgt Meeting Rept 50-344/90-01 on 900112.Major Areas Discussed:Licensee Improvement Plans for Plant IR 05000344/19890221989-08-31031 August 1989 Enforcement Conference Rept 50-344/89-22 on 890831.No Violation Noted.Major Areas Inspected:Nrc Concerns Developed as Result of Special Insp Rept 50-344/89-19 IR 05000344/19890091989-08-22022 August 1989 Insp Rept 50-344/89-09 on 890522-0609 & 0719-21.Violations Noted.Major Areas Inspected:Effectiveness of Licensee Programs in Identifying & Correcting Design Related Plant Vulnerabilities IR 05000344/19890191989-08-11011 August 1989 Insp Rept 50-344/89-19 on 890712-0808.Violations Noted.Major Areas Inspected:Licensee Actions Following Identification of Debris in Containment Recirculation Sump Prior to & Subsequent to Establishing Containment Integrity ML20245K2741989-08-0303 August 1989 Insp Rept 50-344/89-18 on 890712-14.Violations Noted.Major Areas Inspected:Uresolved Item Re Licensee High Pressure Hydrogen & Nitrogen Storage Facility at Plant & Review of Licensee Implementation of NRC Info Notice 87-020 IR 05000344/19890161989-06-28028 June 1989 Insp Rept 50-344/89-16 on 890514-0617.Unresolved Item Noted Re Appropriate Level of Review Necessary for Lower Tier Procedures.Major Areas Inspected:Operational Safety Verification,Maint,Surveillance & Refueling Activities ML20245E6811989-06-0505 June 1989 Insp Rept 50-344/89-10 on 890326-0513.Violations Noted. Major Areas Inspected:Operational Safety Verification,Maint, Surveillance,Event Followup & Open Item Followup ML20245D5851989-06-0202 June 1989 Insp Rept 50-344/89-14 on 890508-12.Violations Noted. Major Areas Inspected:Occupational Exposure During Extended Outage & in-office Review of Licensee Records IR 05000344/19890111989-05-30030 May 1989 Mgt Meeting Rept 50-344/89-11 on 890413.SALP Results for Dec 1987 - Dec 1988 Reviewed & Recent Plant Transient & Activities in Fire Protection & Outage Mgt Discussed IR 05000344/19890151989-05-26026 May 1989 Enforcement Conference Rept 50-344/89-15 on 890510.Major Areas Discussed:Concerns Identified in Security Team Insp Rept 50-344/89-02,Chemistry Team Insp Rept 50-344/89-07 & Special Insp Rept 50-344/89-13 IR 05000344/19890071989-05-23023 May 1989 Insp Rept 50-344/89-07 on 890417-21.No Violations Noted. Major Areas Inspected:Plant Chemistry Related Areas, Including Organization & Mgt,Qa Training & Qualifications, Water Chemistry Control & Analysis & Facilities IR 05000344/19890131989-05-19019 May 1989 Insp Rept 50-344/89-13 on 890409-29.Violations Noted.Major Areas Inspected:Licensee Activities Re Failure of Permissive & Interlock Features for RHR Sys Shutdown Cooling Suction Isolation Valve ML20246D8961989-04-19019 April 1989 Insp Rept 50-344/89-05 on 890212-0325.Violations Noted.Major Areas Inspected:Safety Verification,Maint,Surveillance,Event Followup,Design Engineering & Open Item Followup IR 05000344/19890061989-04-18018 April 1989 Insp Rept 50-344/89-06 on 890320-24.No Violations Noted. Major Areas Inspected:Licensee Action on Previous Insp Findings,Review of Lers,Followup on IE Info Notices,Mgt & Organization,Training & Qualification & Facility Tours IR 05000344/19890041989-03-23023 March 1989 Insp Rept 50-344/89-04 on 890228-0303.Violations Noted. Major Areas Inspected:Follow Up on Two Open Items & One Unresolved Item Identified During Previous Emergency Preparedness Insps & Emergency Preparedness Program ML20247G2151989-03-13013 March 1989 Insp Rept 50-344/89-01 on 890101-0211.Violations Noted.Major Areas Insepcted:Operational Safety Verification,Maint, Surveillance,Event Followup & Followup on Previously Identified Items IR 05000344/19890031989-02-10010 February 1989 Enforcement Conference/Mgt Meeting Rept 50-344/89-03 on 890126.Major Areas Discussed:Nrc Concerns Developed as Result of Insp of Commercial Grade Procurement,Per Insp Rept 50-344/88-46 & Licensee Efforts in Areas of QA Program IR 05000344/19880401988-11-0303 November 1988 Insp Rept 50-344/88-40 on 880807-1001.Violations Noted.Major Areas Inspected:Operational Safety Verification,Maint, Surveillance,Event Followup,Sys Engineering & Open Item Followup IR 05000344/19880441988-10-25025 October 1988 Mgt Meeting Insp Rept 50-344/88-44 on 881004.Major Areas Discussed:Concerns Developed as Result of Sept 1988 Reactor Trip & Subsequent Forced Outage Activities ML20154P6391988-09-16016 September 1988 Insp Rept 50-344/88-36 on 880808-12.Deviation Noted.Major Areas Inspected:Licensee Conformance to Reg Guide 1.97,Rev 3 ML20154N8951988-08-31031 August 1988 Insp Rept 50-344/88-39 on 880808-12.One Unresolved Item on Purchase & Use of Commercial Grade Items in safety-related Sys Identified.Major Areas Inspected:Commercial Grade Procurement & Pipe Support Design Verification IR 05000344/19880291988-08-31031 August 1988 Insp Rept 50-344/88-29 on 880619-0730.No Violations Noted. Major Areas Inspected:Operational Safety Verification, Maint,Surveillance,Event Follow Up & Open Item Follow Up IR 05000344/19880311988-08-23023 August 1988 Insp Rept 50-344/88-31 on 880718-22.No Violations or Deviations Noted.Major Areas Inspected:Unresolved, Enforcement & Followup Items ML20151T4361988-07-29029 July 1988 Insp Rept 50-344/88-27 on 880627-0701.Violations Noted.Major Areas Inspected:Licensee Action on Previous Insp Findings, Chemistry Controls,Control of Radioactive Matls & Contamination,External Exposure Control & Internal Exposure IR 05000344/19880261988-07-28028 July 1988 Insp Rept 50-344/88-26 on 880606-10 & 14-17.Violations Noted.Major Areas Inspected:Commercial Grade Procurement & Inservice Insp Activities IR 05000344/19880281988-07-25025 July 1988 Insp Rept 50-344/88-28 on 880711-15.No Violations or Deviations Noted.Major Areas Inspected:Followup on Previous Insp Findings,Review of Emergency Facilities,Equipment, Instrumentation & Supplies & Exam of Training Program IR 05000344/19880321988-07-25025 July 1988 Insp Rept 50-344/88-32 on 880711-15.No Violations Noted. Major Areas Inspected:Followup of Open Items & Written Repts of Nonroutine Events ML20151K5411988-07-12012 July 1988 Insp Rept 50-344/88-24 on 880508-0618.Violations Noted. Major Areas Inspected:Operational Safety Verification,Maint, Surveillance,Event Follow Up & Open Item Follow Up IR 05000344/19880231988-06-30030 June 1988 Insp Rept 50-344/88-23 on 880510-26.No Violations or Deviations Noted.Major Areas Inspected:Specs for Emergency Operating Procedures IR 05000344/19880251988-06-16016 June 1988 Insp Rept 50-344/88-25 on 880516-31.No Violations Noted. Major Areas Inspected:Licensee Activities in Resolving Reactor Plant Pipe Whip Restraint Design Vs as-built Gap Discrepancies & Inservice Insp Ultrasonic Test Activities IR 05000344/19880201988-06-10010 June 1988 Insp Rept 50-344/88-20 on 880516-20.Violations Noted.Major Areas Inspected:Licensee Action on Previous Insp Findings & Occupational Exposure During Extended Outages IR 05000344/19880151988-05-25025 May 1988 Insp Rept 50-344/88-15 on 880425-29.No Violations Noted. Major Areas Inspected:Evaluation of Design Bases of Diesel Generators,Review of Tests & Experiments Program & Review of QA Program of Measuring & Test Equipment IR 05000344/19880171988-05-23023 May 1988 Insp Rept 50-344/88-17 on 880418-21.Violation Noted.Major Areas Inspected:Licensee Fire Protection Program Implementation & Action on Previous NRC Insp Findings IR 05000344/19880181988-05-18018 May 1988 Insp Rept 50-344/88-18 on 880425-29.No Violations or Deviations Noted.Major Areas Inspected:Inservice Insp Activities & Insp Procedures 30703,73051,37052,73753 & 73755 IR 05000344/19880211988-05-13013 May 1988 Mgt Meeting Rept 50-344/88-21 on 880422.Major Areas Reviewed:Salp Results for 861101-871130 & Discussion of Recently Developed Issues on Containment Isolation Valves IR 05000344/19880111988-04-27027 April 1988 Insp Rept 50-344/88-11 on 880329-31 & 0404-05.No Noncompliance Noted.Major Areas Inspected:Plant Water Chemistry Control & Chemical Analysis,Qa of Plant Chemistry Activities,Radiochemical Analysis & post-accident Sampling IR 05000344/19880121988-04-21021 April 1988 Mgt Meeting Rept 50-344/88-12 on 880325.Areas Discussed: Procedure & Maint Improvement,Outage Activities & Barton Pressure Transmitter Troubleshooting IR 05000344/19880101988-04-0707 April 1988 Insp Rept 50-344/88-10 on 880314-18.No Violations or Deviations Noted.Major Areas Inspected:Annual Review of Licensee Program to Handle Info Notices,Review of Procedures & Onsite Followup of Written Repts of non-routine Events ML20151C4741988-03-28028 March 1988 Insp Rept 50-344/88-04 on 880208-12 & 0229-0304.No Violation Noted.Major Areas Inspected:Licensee Action on Previous Findings,Organization & Mgt,Training & Qualifications,Solid Wastes,Transportation & Facility Tours IR 05000344/19880061988-03-0909 March 1988 Insp Rept 50-344/88-06 on 880222-26.No Violations or Deviations Noted.Major Areas Inspected:Nonlicensed Staff Training & Followup Items & Followup Items of Noncompliance 1990-09-05
[Table view] Category:TEXT-INSPECTION & AUDIT & I&E CIRCULARS
MONTHYEARIR 05000344/19990061999-09-0909 September 1999 Insp Rept 50-344/99-06 on 990630-0701,21 & 0404-08.No Violations Noted.Major Areas Inspected:Organization,Mgt & Cost Controls & Decommissioning Performance & Status Review, Insp of Transportation Activities & Maint & Surveillance IR 05000344/19990051999-05-0707 May 1999 Insp Repts 50-344/99-05 & 72-0017/99-04 on 990419-22.No Violations Noted.Major Areas Inspected:Decommissioning Performance & Status Review IR 05000344/19990041999-05-0707 May 1999 Insp Repts 50-344/99-04 & 72-0017/99-02 on 0322-25 & 29- 0408.Non-cited Violations Noted.Major Areas Inspected: Licensee Readiness to Load Sf Into Independent ISFSI IR 05000344/19990031999-04-20020 April 1999 Insp Repts 50-344/99-03 & 72-0017/99-03 on 990301-04,15-18 & 22-25.No Violations Noted.Major Areas Inspected:Site Tours & Review of Licensee Preparedness for ISFSI Operations IR 05000344/19990021999-04-13013 April 1999 Insp Rept 50-344/99-02 on 990329-0401.No Violations Noted. Major Areas Inspected:Licensee Physical Security Program, Including Access Authorization,Alarm Station & Communications & Access Control of Personnel & Packages IR 05000344/19980041999-01-21021 January 1999 Insp Repts 50-344/98-04 & 72-0017/98-01 on 981106-07 & 1202-10.Violations Noted.Major Areas Inspected: Decommissioning & Dismantlement Activities at Plant Site ML20202C2111999-01-21021 January 1999 Notice of Violation from Insp on 971207-10.Violation Noted: Licensee Did Not Perform Survey to Assure Compliance with 10CFR20.1902(d) IR 05000344/19982021998-10-30030 October 1998 Insp Rept 50-344/98-202 on 980831-0903.No Violations Noted. Major Areas Inspected:Safety Review Program Re Modular Sf Cooling Sys & Maint Program IR 05000344/19980031998-08-25025 August 1998 Insp Rept 50-344/98-03 on 980727-30.No Violations Noted. Major Areas Inspected:Sfp Safety,Ore,Decommissioning Performance & Status Review,Organization Mgt & Cost Controls & Solid Radioactive Waste & Transport IR 05000344/19980021998-07-0101 July 1998 Insp Rept 50-344/98-02 on 980601-04.No Violations Noted. Major Areas Inspected:Activities Including Spent Fuel Pool Safety,Occupational Radiation Exposure & Decommissioning Performance & Status Review IR 05000344/19980011998-05-22022 May 1998 Insp Rept 50-344/98-01 on 980504-07.No Violations Noted. Major Areas Inspected:Specific Areas of Licensee Physical Security Program IR 05000344/19982011998-04-29029 April 1998 Insp Rept 50-344/98-201 on 980223-26.No Violations Noted. Major Areas Inspected:Safety Review Program & Insp follow- Up ML20199D7511998-01-23023 January 1998 Cover Page for Insp Rept 50-344/97-05 on 971201-03, Inadvertently Omitted in Original Submittal ML20199F0361998-01-23023 January 1998 Insp Rept 50-344/97-05 on 971201-03.Violations Noted.Major Areas Inspected:Status of Dismantlement Activities,Changes to Util Emergency Exercise Plan Implementing Procedures & Decommissioning ML20199F0291998-01-15015 January 1998 Notice of Violation from Insp on 971201-03.Violation Noted: Licensee Failed to Ensure Adequate Survey of Certain Contaminated Tools IR 05000344/19970041997-11-21021 November 1997 Insp Repts 50-344/97-04 & 72-0017/97-04 on 970929-1002.No Violations Noted.Major Areas Inspected:Fuel Debris Processing,Dry Cask Storage & Control of Radioactive Matl. Insp Repts Reissued Due to Omission of Pages 4 & 5 ML20198N3461997-10-31031 October 1997 Insp Repts 50-344/97-04 & 72-0017/97-04 on 970929-1010.No Violations Noted.Major Areas Inspected:Fuel Debris Processing Preparation for Pouring Concrete for Portion of ISFSI Pad & Control & Release of Contaminated Matl ML20210S7131997-09-0909 September 1997 Notice of Violation from Insp on 970721-24.Violation Noted: from 960923-970515,licensee Failed to Conduct Surveys Adequate to Evaluate Quantity of Radioactive Matl Released from Radiological Controlled Area IR 05000344/19970031997-09-0909 September 1997 Insp Repts 50-344/97-03 & 72-0017/97-03 on 970721-24. Violations Noted.Major Areas Inspected:Control of Radioactive Material,Spent Fuel Pool Debris Project,Dry Cask Storage,Spent Fuel Pool & Health Physics Activities IR 05000344/19970021997-05-0606 May 1997 Insp Repts 50-344/97-02 & 72-0017/97-02 on 970414-17.No Violations Noted.Major Areas Inspected:Health Physics, Training Program,Spent Fuel Pool,Independent Spent Fuel Storage Installation & Fuel Building Crane Tests IR 05000344/19970011997-02-25025 February 1997 Insp Repts 50-344/97-01 & 72-0017/97-01 on 970204-06. Violations Noted.Major Areas Inspected:Review of Radiation Protection Program,Compliance W/Ts,Operations Involving Licensee Insp of Spent Fuel & Quality Assurance Program ML20135B7491997-02-25025 February 1997 Notice of Violation from Insp on 970204-06.Violation Noted: Licensee Had Not Audited Annual Radiological Environmental Report TS 6.9.1.5.1 Since 890519 IR 05000344/19960081997-02-13013 February 1997 Insp Repts 50-344/96-08 & 72-0017/96-02 on 961104-07.No Violations Noted.Major Areas Inspected:Decommissioning Activities Related to Ongoing Efforts to Decontaminate Facility & Place Spent Fuel in Storage at ISFSI IR 05000344/19960051997-02-13013 February 1997 Correction to Insp Repts 50-344/96-05 & 72-0017/96-02. Requests That Encl Pages Be Added as Last Two Pages of Listed Insp Rept ML20059A1421993-12-15015 December 1993 Notice of Violation from Insp on 930930-1112.Violation Noted:Detailed Construction Package 1 Associated W/Request for Design Change 78-103,installed in May 1980,did Not Correctly Translate Design Basis Into Applicable Procedures IR 05000344/19930151993-12-14014 December 1993 Insp Rept 50-344/93-15 on 931115-18.No Violations Noted. Major Areas Inspected:Operational Status of EP Program & of Annual EP Exercise IR 05000344/19930141993-12-0606 December 1993 Insp Rept 50-344/93-14 on 930930-1112.Violations Noted.Major Areas Inspected:Resident Insp of Operational Safety Verification,Maintenance,Surveillance & follow-up of Previously Identified Items IR 05000344/19930121993-10-22022 October 1993 Insp Rept 50-344/93-12 on 930817-0929.No Violations or Deviations Noted.Major Areas Inspected:Operational Safety Verification,Maint,Surveillance & Followup of Previously Identified Items IR 05000344/19930131993-09-24024 September 1993 Insp Rept 50-344/93-13 on 930913-17.No Violations Noted. Major Areas Inspected:Listed Portions of Licensee Physical Security Program IR 05000344/19930111993-09-0303 September 1993 Insp Rept 50-344/93-11 on 930706-0816.No Violations or Deviations Noted.Major Areas Inspected:Operational Safety Verification,Maint,Surveillance & Followup of Previously Identified Items IR 05000344/19930101993-08-12012 August 1993 Insp Rept 50-344/93-10 on 930706-08.No Violations Noted. Major Areas Inspected:Chemistry & Radiation Protection Program Organization & Staffing & Solid Radwaste Storage IR 05000344/19930081993-06-25025 June 1993 Insp Rept 50-344/93-08 on 930422-0531.No Violations Noted. Major Areas Inspected:Operational Safety Verification,Maint, Emergency Preparedness & Followup of Previously Identified Items PNO-V-93-002, on 930113,L Marbet Held Press Conference W/ Portland,Or Media & Alleged That NRC Had Inappropriately Authorized Feb 1992 Restart of Plant.Util Announced on 930104 That Operation of Plant Would Be Permanently Ceased1993-01-13013 January 1993 PNO-V-93-002:on 930113,L Marbet Held Press Conference W/ Portland,Or Media & Alleged That NRC Had Inappropriately Authorized Feb 1992 Restart of Plant.Util Announced on 930104 That Operation of Plant Would Be Permanently Ceased IR 05000344/19920321993-01-0808 January 1993 Insp Rept 50-344/92-32 on 921027-1207.Violations Noted.Major Areas Inspected:Maintenance,Surveillance,Event Followup & Followup of Previously Identified Items ML20127E9461993-01-0808 January 1993 Notice of Violation from Insp on 921027-1207.Violation Noted:Licensees Corrective Actions Not Effective in That,On 921112 & 15,access Doors to Plant Issue Warehouse Not Controlled by Authorized Personnel PNO-V-93-001, on 930104,Licensee Notified Region V That Util Board Decided That Plant Will Not Be Restarted & Currently Shutdown for Insp & Repair of SG Tubes.Licensee Notified Media1993-01-0404 January 1993 PNO-V-93-001:on 930104,Licensee Notified Region V That Util Board Decided That Plant Will Not Be Restarted & Currently Shutdown for Insp & Repair of SG Tubes.Licensee Notified Media IR 05000344/19920341992-12-31031 December 1992 Meeting Rept 50-344/92-34 on 921201.Areas Discussed:Sg Tube Leak & Licensees Subsequent Insp of SGs IR 05000344/19920331992-12-29029 December 1992 Insp Rept 50-344/92-33 on 921207-11.No Violations or Deviations Noted.Major Areas Inspected:Licensee Erosion/ Corrosion Program Activities,Including Followup of Previously Identified Items IR 05000344/19920281992-12-21021 December 1992 Insp Rept 50-344/92-28 on 921109-1215.No Violations or Deviations Noted.Major Areas Inspected:Rev 7 to Emergency Plan Implementing Procedure EP-001, Emergency Classification PNO-V-92-038, on 921209,B Roberts Plans to Notify News Media of Request of or Energy Facility Siting Council to Hold Hearing on Utility Steam Generator Safety1992-12-0808 December 1992 PNO-V-92-038:on 921209,B Roberts Plans to Notify News Media of Request of or Energy Facility Siting Council to Hold Hearing on Utility Steam Generator Safety PNO-V-92-037, on 921201,meeting Conducted at Plant to Address 921109 Steam Generator Tube Leak & Licensee Request for Emergency TS Change to Permit Restart1992-12-0101 December 1992 PNO-V-92-037:on 921201,meeting Conducted at Plant to Address 921109 Steam Generator Tube Leak & Licensee Request for Emergency TS Change to Permit Restart ML20126E9101992-11-25025 November 1992 Notice of Violation from Insp on 920915-1026.Violation Noted:Supervisor Informed of Receipt of a Nonconforming Component,Chlorine Detector & Did Not Initiate an Ncr ML20126E9131992-11-25025 November 1992 Notice of Deviation from Insp on 920915-1026.Deviation Noted:Containment Air Locks Not Tested Using Pressure Decay Method IR 05000344/19920301992-11-25025 November 1992 Insp Rept 50-344/92-30 on 920915-1026.Violations Noted. Major Areas Inspected:Operational Safety Verification, Maintenance,Surveillance & Followup of Previously Identified IR 05000344/19920311992-11-10010 November 1992 Insp Rept 50-344/92-31 on 920928-1002.No Violations Noted. Major Areas Inspected:Environ Monitoring,Cr Ventilation & Control of Radwaste Activities PNO-V-92-004, on 920225,Trojan Power Plant Entered Mode 2 After Extended Outage.Plant Currently Critical at Less than 1 Percent Power & Licensee Conducting Low Power Physics Testing.Tests Expected to Be Completed by 9202271992-02-25025 February 1992 PNO-V-92-004:on 920225,Trojan Power Plant Entered Mode 2 After Extended Outage.Plant Currently Critical at Less than 1 Percent Power & Licensee Conducting Low Power Physics Testing.Tests Expected to Be Completed by 920227 IR 05000344/19910161991-06-0404 June 1991 Insp Rept 50-344/91-16 on 910506-16.No Violations or Deviations Noted.Major Areas Inspected:Proposed Rev 6 to Emergency Procedure (EP)-001, Emergency Classification PNO-V-91-002, on 910303,Trojan Declared an Unsual Event & Initiated Plant Shutdown Due to Inability to Meet Requirements of TS 3.8.2.1,which Requires That Four 120 Volts AC Preferred Instrument Busses Be Operable1991-03-0505 March 1991 PNO-V-91-002:on 910303,Trojan Declared an Unsual Event & Initiated Plant Shutdown Due to Inability to Meet Requirements of TS 3.8.2.1,which Requires That Four 120 Volts AC Preferred Instrument Busses Be Operable ML20062F9301990-11-0808 November 1990 Notice of Violation from Insp on 900902-1006.Violation Noted:Temp of Train B Component Cooling Water Pump (ASME Code Class 3 Pump) Taken W/Instrument W/Scale More than Three Times Ref Value of Bearing Temp PNO-V-90-045, State of or Measure 4 Re Closure of Facility Defeated in 901106 Vote.Util Will Hold News Conference1990-11-0707 November 1990 PNO-V-90-045:State of or Measure 4 Re Closure of Facility Defeated in 901106 Vote.Util Will Hold News Conference 1999-09-09
[Table view] |
See also: IR 05000344/1989010
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T' 'O. S. NUCLEAR REGULATORY COMMISSION
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C, h LReport No.' .50-344/89-10 L , y <
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f',' Docket.No.< 50-344
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' Facility Name: Trojan
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> ; Inspection at: Rainier,E Oregon
Inspection conducted: March 26'- May 13,.1989
@ t Inspectors: R., C'.'Barr . .
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Senior Resident Inspector
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, 'G. Y. Suh
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Resident Inspector
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Aoriroved;By: .. %' ' ' '
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O M. M. Mendonca, Chief- Date Signed
hs Reactor Projects'Section 1
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' Summary:
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p ,.. Inspection on March 26 - May'13, 1989 (Report 50-344/89-10)
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-' Areas Inspected:
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4* Routine-inspection of, operational. safety verification.
. maintenance,-surveillance, event follow-up, and open. item follow-up.
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Inspection procedures 30702, 30703, 61726, 71707, 90712, 92700, and 93702 were
i Lused as' guidance'during the conduct of.the inspection,
,> 4Results:
!
iThis' inspection identified two' violations of NRC requirements. Paragraph 3
discusses a repeat. violation in that information required to be recorded in
the Control Room Log was not entered. Paragraph Sa, discusses vibration
- ' monitoring performed on the "A" Containment Spray Pump that used a vibration
, monitoring device that did not meet code accuracy requirements. A non-cited
violation for failure to follow procedure during removal of the equipment
' hatch was identified and reviewed during this inspection period.
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G ADOCK 0D000344
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S 'i!. DETAILS '
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f L 3 Psrsons Contacted
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<*D.;W. Cockfield,-Vice President, Nuclear
- C. P. Yundt,- Plant General Manager
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T. D. Walt,. General. Manager, Technical Functions
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l';e . *D. ~ L. Nordstrom, Acting Manager, Nuclear Quality AssuranceT
! !' s *R. P. Schmitt', Manager,;0perations and Maintenance
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G. A. :Zimmerman, Manager,-Nuclear Safety and Regulation Department
., A. N. Roller, Manager, Nuclear Plant Engineering.
- D..W. Swan, Manager, Technical Services
. *M. J. - Singh, Manager, Plant Modifications-
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- J. D. .Reid, Manager, Quality Support Services
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.J. W.' Lentsch, Manager, Personnel Protection
A. R. Ankrum, Manager, Nuclear Security.
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- R. E. 'Susee, Manager, Planning and Scheduling
-J. M. Anderson, Manager, Trojan Materials
E. B. James, Outage Manager
'.P. A.lMorton;-Branch Manager, Plant Systems Engineering
R.,L. Russell, Branch Manager,' Operations-
- T. 'O. Meek, ' Branch Manager, Radiation Protection
Di L. Bennett, Branch Manager, Maintenance
r S. A. Bauer, Branch Manager, Nuclear Regulation
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R. C..Rupe, Acting Operations Branch Manager, Quality Assurance
R. H.' Budzeck, Assistant Operations Supervisor
R. A. Reinart, Instrument;and Control Supervisor
.A..M..Puzey, Office Supervisor--
M.~D. Gatlin,. Warehouse Supervisor
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F. Levin, Supervisor, Plant Modifications,
R. Pre'witt, Quality Systems Supervisor
.D. A. Desmarais, Mechanical < Engineer, NPE
The. inspectors also interviewed and'. talked with other-licensee employees
during the course of the. inspection. .These included shift supervisors,
reactor and auxiliary operators, maintenance personnel, plant technicians-
and engineers, and quality assurance personnel. -v
- Denotes those attending the exit interview.
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' 2. Plant' Status
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, The plant operated at 100% power from March 26, 1989, until April 6,
.1989,1when the reactor was shutdown to begin the 1989 Refueling Outage.
' Major activities planned for the Outage, scheduled for sixty-five days,
were refueling, eddy current examination of incore flux thimbles'and all
tubes of all four steam generators, reactor vessel inservice inspection,
replacement of hee degraded electrical cabling, main generator
inspection and high pressure turbine inspection. Thusfar, outage
inspections have identified an indication on the
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"A" Reactor Coolant Hot
Leg Nozzle that appears to be within code allowable; a potential'10 CFR
21 issue with Amphenol (Bunker-Ramo) containment electrical penetrations
in that.some 14 gauge wires appear not to have been properly crimped and
pulled out of the penetration: connector; and; abnormal wear of the main
-generator rotor windings.
3. Operational- Safety Verification- (71707)
During this inspection period, the inspectors observed and examined
activities.to verify the operational safety of the licensee's facility.
The observations and examinations of those activities were conducted cn a
daily, weekly or biweekly basis.
Daily the1 inspectors observed control room activities to verify the
licensee's adherence to limiting conditions for operation as prescribed
in the facility Technical Specifications. Logs, instrumentation,
recorder traces',, and other operational; records were examined to obtain
information on plant conditions, trends, and compliance with regulations.
On occasions with a' shift turnover in progress, the turnover of
information on plant status was observed to determine that pertinent !
information was. relayed to'the onconiing shift personnel.
Each week the inspectors toured the accessible areas of the facility to
observe the following items:
(a); General. plant'and. equipment conditions.
(b) Maintenance requests and repairs. !
(c)' Fire hazards'end fire fighting equipment. j
(d) Ignition sources and flammable material control. '
(e) Conduct of activities in accordance with the licensee's
administrative controls and approved procedures.
(f) 7nteriors of electrical and control panels.
(g) Implementation of the licensee's physical security plan.
(h) Radiation protection controls.
(i) Plant housekeeping and cleanliness.
(j) Radioactive waste systems.
(k) Proper storage of compressed gas bottles.
Weekly, the inspectors examined the licensee's equipment clearance
control with respect to removal of equipment from service to determine
that the licensee complied with technical specification limiting
-conditions for operation. Active clearances were spot-checked to ensure
that their issuance was consistent with plant status and maintenance
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evolutions. Logs of jumpers, bypasses, caution and test tags,were
examined by the, inspectors. , ]
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In a review of plant-logs of the' scheduled shutdown refueling outage,'the,
inspectors noted that entry into Mode 2 was not' noted in the _ control room .
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- log or in the shift supervisor turnover checkoff list. Discussions ~ with
the involved operations shift crew indicated they were aware of the mode ~
change. The operators attributed the failure;to record the mode chang'e.
q primarily to the occurrence of the feedwater isolation event"(discussed i
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in section 5) which required various operatoF response _ actions. The.' i
y'a inspectors considered the apparent failure to" document thi's change in
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plant condition to be an apparent violation of procedural requirements
. outlined ir Administrative Orders A0-3-6, Revision 17, titled " Conduct of "
f Operations, Shift Records"-(50-344/89-10-01). Insp'ection/ report '
50-344/89-05 documented a failure to record a containment entry iri the
control room log. These two instances indicate the need for inc'reased
management attention. ,
Each week the inspectors. conversed with operators in the control room and
with other plant personnel. The discussions centered on pertinent topics
relating.to general plant conditions, procedures, security, training and
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-other topics- related to in progress work activities.
The inspectors examined the licensee's nonconformance reports (NCRs) to
confirm that deficiencies were being identified and tracked. Identified
nonconformances were being tracked and followed to the completion of
- corrective actions.
Routine inspections of the licensee's physical security program were
performed in the areas of access control, organization and staffing, and
detection and assessment systems. The inspectors observed the access
control' measures used at the entrance to the protected area, verified the
integrity of portions of the protected area barrier and vital area
barriers, and observed in several instances the implementation of
compensatory measures upon breach of vital area barriers. Portions of ;
the isolation zone were verified to be free of obstructions. Functioning
of central and secondary alarm stations (including the use of CCTV
monitors) was observed. On a sampling basis, the inspectors verified
that the required minimum number of armed guards and individuals
authorized to direct security activities were on site.
The inspectors conducted routine inspections of selected activities of
the licensee's radiological protection program. A sampling of radiation
work permits (RWPs) was reviewed for completeness and adequacy of
information. During the course of inspection activities and periodic
' tours of plant areas, the inspectors verified proper use of personnel
monitoring equipment, observed individuals leaving the radiation
controlled area and signing out on appropriate RWP's, and observed the
posting of radiation areas and contaminated areas. Posted radiation
levels at locations within the fuel and auxiliary buildings were verified
using both NRC and licensee portable survey meters. The involvement of
health physics supervisors and engineers and their awareness of
significant plant activities was assessed through conversations and
review of RWP sign-in records.
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dne vio'lation and no deviations were identified.
4. Maintenance (62703)
'The inspectors _ performed a documentation review of selected maintenance
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requests (MRs) associated with containment electrical penetration module
seal . replacements and selected maintenance requests for the pull testing
of 14 gauge wire on various Bunker-Ramo (Amphenol) electrical containment
. penetration modules, and observed selected wire pull tests.
During.a November 1988 forced outage'some containment electrical
- penetrations were observed to exhibit greater than expected local leak
. rates. Additionally, during excessively cold periods during the
1988-1989 Operating Cycle'several containment electrical penetrations
exhibited very high local leak rates. The licensee in response to the
high leak' rates planned to clean or replace the seals of these electrical
. penetrations during the 1989 Refueling Outage. The inspectors reviewed
MR 89-0917 and.MR 89-0918 whose scope was to inspect, clean and/or
replace seals for containment electrical penetration BZ01 and BZO3,
respectively. The inspectors noted pen and ink changes to the work
' instructions that were initialed, however not by any of the original
signators of the work request, but not dated. Industry. practice suggests
either the work group supervisor or the originator of the maintenance to
, initial and date the changes to documentation. Trojan Administrative
Order (AO), "Maintenace Requests" does not address changes in scope of
MRs. In.this case the change in scope was more conservative in that
instead of cleanF.g the seals the seals were to be replaced. Also,
requirements fce post maintenance testing changed during the course of
the maintenance.
During the replacement of the seale t3r containment electrical
penetration BZO3,,the maintenance aftsman'noted a disconnected wire.
The-craftsman contacted the cogniz.nt engineer for evaluation. The
evaluation concluded the wire had been previously recognized and
docun,ented as being disconnected; however, the . reason for the wire being
disconnected was unknown. During the course of the evaluation, the
cognizant engineer on Wednesday, April 26, 1989, without consulting
management or having a work request to permit troubleshooting of the !
problem, pulled on oth'er 14 (AWG) gauge: wire in the G module of
containment penetration BZ03 to ascertain if other-wires were loose. In
fact, other wires in this ' module did pull out. The engineer then
reported his findings'to his'immediate supervisor _for resolution. On
Sunday, Apri1 ^ 30,1989, the licensee'made a courtesy Emergency
Notification System'(ENS) report to,the NRC and informed the Resident
Inspector of the potential concern over the electrical integrity of the
- Bunker-Ramo (Ampbenol) containment' electrical penetrations. On Monday,
May 1, 1989, the inspectors met with plant managers to obtain additional
background information on this event. The inspectors expressed concern
that troubleshooting of a problem was being conducted without an approved
maintenance request, knowledge of operations shift management or plant
management. The Manager, Technical Services stated that the j
investigation conducted by the engineer was within the scope of the j
. engineer's authority, that the cables within that penetration were
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de-energized and there was no safety implication. The inspectors also
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questioned the channels of communication in that plant management was not
notified of.the problem until Saturday, April 29, 1989.
During the week of' April 30, 1989, a plan was drafted to pull test
various 14 and larger AWG wires of the containment electrical
penetrations. The scope of the wire pull tests was to pull test enough
wires to have a high confidence about the integrity of the wire
connections. The tests were documented on maintenance requests for each
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penetration. The inspectors observed selected pull tests and found the
tests were planned, had quality coverage and were documented. The pull
test for the 14 AWG and larger wire was conducted using a spring scale
device. The pull tensions used were based on the wire size. The
inspectors in discussion with an engineering supervisor concluded that
the pull tests may not be testing the integrity of the electrical
connection but Nsy only be testing the adhesion between the wire ,
insulation ano L e Soft epoxy seelant of the penetration module.
At the conclusion of the inspection period, the licensee was continuing
to pull test the 14 AWG and larger wire and was considering testing of
smaller gauge wire. Additionally, the licensee was considering, based on
the findings of the pull tests, submitting a 10 CFR 21 report (such a
report has been submitted subsequent to the end of the inspection
period). The scope of the pull testing had expanded during the course of
the testing because additional wires continued to pull free from their
connection. This is an open item based on resolution of troubleshooting
without an approved maintenance request, the need to understand the basis
for the pull test and the safety significance and corrective actions for
the problem (50-344/89-10-02).
5. Surveillance (61726)
Main Steam Line Safety Valve Testing
The inspectors observed portions of inservice testing of main steam line
safety valves PSV-2213, PSV-2233, PSV-2253, and PSV-2273. Safety valve
lif t set points were determined by in place testing with pneumatic assist
equipment. The testing was performed in accordance with applicable
sections of Maintenance Procedure MP-7-1, Revision 17, titled " Main Steam
Safety Valves Inservice Testing," and controlled by maintenance requests
MR 88-6946, MR 88-6947, MR 88-6948, and MR 88-6949. The work was
performed by a maintenance valve crew. The inspectors observed test
engineering and quality control coverage during performance of the valve
set point testing and verified that test instrumentation calibration was
current. A review of maintenance records and discussions with
engineering personnel indicated that required surveillance test frequency -
for main steam line code safety valves was being met.
Inservice Testing of Containment Spray Pumps
Unresolved item 50-344/89-05-02 dealt with review of inservice testing of
the "A" Containment Spray Pump (CSP). The inspectors questioned whether
the accuracy of the instrument used to measure vibration amplitude met
ASME Boiler and Pressure Vessel Code Section XI requirements. The
inspectors noted that calibration checks of the hand held vibration meter
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used in the-' inservice test observed by the inspectors specified a ,
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reference:value as defined in Section.XI for. vibration for this pump was
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e . one mil.- This'would in turn require an instrument accuracy of plus or
6 minus 0.15 mil per paragraphs.IWP-4110'and IWP-4120 of Section XI. For, .i
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thellatest calibration check of vibration: monitor T-5410 as documented on
an I&C Form 6 approved December 16, 1988, the as-found and as-left
accuracy differed. from the desired output by 0.28 to 0.55~ mils at the a
five calibration check points. 'In addition, the inspectors understood- :)
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J. , - probe. ap' pear to be .in this case less the requirements 'of Section XI. This .I
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is an apparent violation (50-344/89-10-03). l
0 The inspect $rs discussed the other; concerns outlined in the unresolved l i
item with test; engineering personnel ~and a NRR representative. Licensee :f
' representatives stated that the applicable data sheets will be revised to 't
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explicitly date the ' allowable value'for
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bearing. temperature. With
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. regard to the analysis of test data within 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> per paragraph
- IWP-3220. of Section XI; the inspectors understood that the licensee
., p.rogram ' consisted of compar,ing test-values against required action ranges
- within .96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> and'against alert. ranges,in a manner to require ' that -
alert testingcis performed on a. timely basis. The inspectors considered
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. that-this was not cle'arly inconsistent with Section XI requirements.
< This item was discussed with a regional specialist inspector. for possible
follow-up;in routine inspections. Based on the above, unresolved Item
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50-344/89-05-02 is considered closed.
- One' apparent violation and no deviations were identified.
6. Event Follow-u'p'(93702, 92701)
During the scheduled shutdown and in the time period shortly following
entry into Mode 5, Cold Shutduwn, the plant experienced the events which
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are summarized below.
Feedwater Isolation
L On April 6,1989, during the planned annual refueling outage shutdown, a
lc feedwater isolation event occurred shortly after the control operator
tripped the main turbine per plant shutdown procedures. ' Turbine bypass
- valve.PCV-507A failed open, apparently due to a failed pneumatic
- controller associated with the valve. This resulted in a high-high water
level in-the "C" steam generator. Per design, a feedwater isolation
occurred which in turn resulted in the trip of the operating main
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- feedwater pump. With both main feedwater pumps tripped, the auxiliary
feedwater system automatically started and resulted in the isolation of
steam generator blowdown valves. The licensee initiated an internal
event report for the occurrence and made a timely ENS report for an
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engineered safety feature actuation.
H The inspectors reviewed plant records, discussed the event response with
, involved operators, and subsequently reviewed the licensee's preliminary l
< . event evaluation with plant management during an April 10, 1989 meeting.
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During the event, an air li' en' connected to the pneumatic controllers s-
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associated.with PCV-507A-failed. Based on the-sy' stem engineer's event,
? observations and preliminary evaluation, the licensee-believed the. air
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iline failure resulted.from und was.not the cause of1the' valve l failure. 7A
maintenanc'e request was written for the pneumatic' contro11es. PCV-507A-
. was quarantin'ed for failure analysis, and metallurgical evaluation of the
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.
- failed'11ne was planned as well as inspection of similar salves for *
f"
1
!g'eneric' problems. : The licensee is planning to replace th'e' rigid: air;11ne
with flexible braided whe air 'line.
- w, '
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gjShutdown Bank "A" Fail'ure to' Manually Drive-In
'
While manually inserting control rod banks in accordance with the
,
' t
shutdown. procedure 'the operators were unable to insert Shutdown Bank "A"-
, and a-rod control. system urgent' failure alarm'was received. At the time,
all other centroitrods in control banks and shutdown banks were' fully
inserted; ,After. consultation with. maintenance personnel, operators
manually; opened.the reactor trip breakers and all withdrawn rods fully-
i~' inserted.- At the: time.of inspection, the cause of this event had not 4
been determined. .The licensee's evaluation included a r'eview of past
maintenance records and consultation with the vendor. Further
' examination.will'. be performed when the rod control system is re-energized
prior-to reactor startup. Repair and understanding of this event is a
, -licensee ready'for startup item.
Main Steam (MS) Drain Valve Failure"to Isolate on Auto-Isolation Signal
In' Mode 3 while performing surveillance testing on the "A" main steam
~ '
-line~, drain valve CV-2297 failed to close on a '!B" train steam line
isolation signal. '
The licensee preliminarily identified the cause'as a
failed solenoid valve on ~ the instrument air.line to the valve operator
and-issued a maintenance request for the' component. Main steam line
drain valves.for the other three main steam lines (CV-2294, CV-2295, and
CV-2296) closed on testing but reopened when the actuating switch was
released by theioperator. Within four hours, required by Technical
Specifications for. containment isolation valves, operations personnel
declared'the valves inoperable and secured the valves in the closed
position through~the use of clearance danger tags. Licensee review of
electrical drawings showed that the applicable "B" train circuits had-no
seal-in relay for valve closure-in contrast to those associated with an
"A". train steam line isolation signal. 'In discussions with'the '
inspectors,' plant management representatives indicated that there may be
an engineering basis for the lack of "B" train seal-in relays, and that
' ,/
the valves would remain closed on a "B" train l isolation signal as long as -
s- the signal was present. The licensee planned to evaluate whether a
design change would be. required, and, if not, to provide a documented '
basis for the lack of '!B" train seal in relays.
-
s
.a Failure of Control Room Ventilation Dampers to Close within Surveillance
fp Time Requirements t ,
g- In Mode 3, Hot Standby, while performing response' testing of various. _
'
engineered safety features, control room ventilation dampers DM 10501 A/B
j :and DM 10504 A/B failed to close within the. Technical Specifications
4
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required three seconds.in. response'to a safety injection signal. The
, -dampers ~1s'olated in approximately four seconds. These four air operated
-
dampers. isolate the normal control'. room ventilation system, CB-2, from
? the control room envelope. In response, the licensee declared.both-
I trains of the' emergency' control room ventilation system, CB-1, to be
v ; . inoperable given the effect of CB-2 isolation on th'e ability of CB-1 to
L' 1 pressurize the control room envelope. With both. trains of CB-1
inoperable, the: licensee entered technical specification 3.0.3., secured .)
s. the.four dampers in the closed position, and made timely ENS report to
p' 'the NRC.; The inspectors discussed the event with_ involved operators'and
~
F ,
.the' system engineer,-and verified that adequate controls were established" '
N .in a timely manner,for the isolation dampers. At the time'of inspection,
b >
- the licensee was reviewing previous test data on the dampers,. conducting
'
i -additional testing and reviewing testing methods and the basis for the d
- te.,t'. acceptance criteria. This item is identified as a ready for startup
item for' resolution.
p
Containment. Spray Header Structural Support Elements
s
With the plant.in Mode 4, Hot Shutdown, the.l'icensee declared both trains
of the Containment Spray. System inoperable; based'on. engineering j
evaluation of an inspection of structural elements which support J
. containment spr5y sys' tem headers _atithe 205 foot elevation of l
containment. With both' trains inoperable,fthe plant entered technical
speci fi cation m3. 0. 3.' In respons , the licensee made an ENS report to the
~#
.
~
NRC.-and placed the plant in Mode 5. The, limited' inspection found'that
certain supporting, legs of the eight containment: air coolers located ~
.inside containmentfwere not supported as expected on their respective
structural channels. #These" channels also providedJsupport to'the spray
headers of the Containment Spray System. Antengineering evaluation by
licensee and architect-engineer personnel concluded on a conservative
basis that the"unsxpected loading! configuration could affect the seismic
response capabilityfof both the co'tainment
n air coolers, which are.
required in Modes'1 through 3, and the' Containment Spray System. 1he
( evaluation also concluded that' the as-found conditions did not create
f Seismic II/I concerns for equipment located below the 205 foot elevation.
Based on discussions'with the engineers involved in the inspection and
review of applicable drasings, the' inspectors understood that the
engineering evaluation was based on a limited scope inspection, to be
augmented by additional detailed inspections, and was primarily based on
, engineering judgment pending further analysis and stress calculations.
On a preliminary basis, the licensee attributed design or construction
error as the cause of this event. The inspections were performed as part
.of the continuing followup to the licensee's pipe support verification
program which was implemented in response to pipe support issues
. identified during the 1987 Refueling Outage. Nonconformance report NCR
- 89-095.was. initiated to evaluate the inspection findings. In an exit
~ meeting with Plant Management held on April 14, 1989, the inspectors
indicated NRC interest in this event and the results of the licensee's ,
' eval uati on. The inspectors will continue to follow licensee actions and
consider this to be an open item (50-344/89-10-04).
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Minor Radiation Release during Containment Equipment Hatch Removal
,In 'the. process of opening.the containment equipment hatch, the auxiliary j
j. ' building-ventilation system process radiation monitors alarmed at their
j
alarm setpoints. Containment atmosphere pressure'was approximately 0.6
'
psig at'the time of the event. Preliminary licensee evaluation indicated
'that the refueling vendor crew failed to leave four equally spaced bolts,
as specified in the applicable maintenance procedure, in removing the z
d
equipment hatch bolts,-which resulted in the formation of an ;
approximately one to two inch gap between the top of the hatch and its <
seating surface. With containment at a relative positive' pressure, ai'r
flow occurred from. containment atmosphere into.the auxiliary and fuel
buildings. In response to the process radiation monitor alarms, the-
licensee restricted access the auxiliary building and rebolted.the hatch
with four evenly spaced bolts. The inspectors verified.in discussions
with chemistry personnel that Ter nical Specifications' release limits
were not exceeded. In discussicas with, plant management, the inspectors
understood that the licensee was evaluating the performance'of the work
at the given~ containment' atmosphere. pressure and additional work control
aspects of the event. This violation is not being cited because the
criteria specified in Section V.G. of the Enforcement Policy were
.
satisfied (NCV 89-10-05).
Failure of RHR Suction Isolation Valve Permissive / Interlock'
!
During surveillance testing in Mode 5, Cold Shutdown, motor operated
valve MO-8702, t ocated on the Residual Heat Removal System suction line
from reactor coolant system (RCS) loop 4 hot leg, failed to isolate on a
simulated RCS pressure signal of 600 psig. Valve MO-8701 located in
series on the same suction line tested satisfactorily. Preliminary
~1icensee evaluation identified an apparent polarity reversal in the
wiring between the instrument loop and bistable module PB-405 A/B, i'
apparently resulting from.1988 Refueling Outage work related to
modifications on the remote shutdown station. The polarity reversal made
ineffective interlock and permissive features for MO-8702 which isolates
, the valve on an increasing RCS pressure at 600 psig and which allows the
opening of the valve on a decreasing RCS pressure at about 425 psig.
Immediate operator action in response to this event was placen:ent of the
control switch for M0-8702 in the pull-to-lock position with the valve
open. In discussions with Plant Management, the inspectors understood
that post modification testing for remote shutdown station related work
failed to identify this problem and was considered a startup hold for the
current refueling outage. Inspection of this event was documented in
Special Inspection Report 50-344/89-13.
For events discussed in this section, the licensee had initiated internal
event reports to forther evaluate each event. Critques with involved
personnel werE also held by the licensee shortly af ter event occurrence
.to develop initial evaluation results. The inspectors met with plant
management on April 10, 1989, to discuss each event and the results of
the event evaluations available. The inspectors will continue to follow
these items in the course of routine inspections.
One violation and no deviations were identified.
/
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Follow-up of Licensee Event Reports'(90712)-
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J a.- The following LERS were closed based on in-office review, inspector
verification. of the(implementation of selected' corrective actions
. . .
...
Jand licensee: commitment to perform future. corrective actions:
&
".LER'88 19. Revision 2, (Closed),=" Surveillance Required by
Technical. Specification Not' Performed Following Containment
- Hydrogen Vent System Adsorber Replacement". This-revised LER-
- 'provided> additionalt information concerning an event in which the
- ; .wrongladsorber(bed df the Hydrogen Vent wasl replaced.resulting in.
the t'B" Train ' Containment hydrogen vent system being inoperable ~ for . !
l eleven' days. :The . licensee concluded the cause ofithe event was 'j
procedural: noncompliance and procedural inadequacy. Some corrective- ;
.-actions the lice'nsee has taken are_ revising Administrative Order l
% (AO) 3-9 " Maintenance Requests" to discontinue the practices of- 1
C ,
having' multiple work items on a single maintenance request and ' ]
attaching corrective maintenance items to a preventive maintenance 1
- work request, training maintenance personnel on properly documenting )
verbal instruction. and requiring the ' labeling of sample. The i
licensee did.not. improve the halide testing method for evaluating i
the efficiency of,the charcoal adsorber, therefore, it is likely
future testing of the. charcoal adsorber beds will have to be i
reperformed.
LER 88-31, Revision 1, (Closed), "Of fsite Power Sources Not-
Demonstrated Operable Per Technical Specification - Personnel
' Error". This revised LER provided additional information on the
'
intended corrective actions to prevent event recurrence. By June
30, 1989,- the licensee wi1* implement ~ a new procedure on shift
turnover to' prevent' future missing of surveillance.
LER 88-36, Revision 1, (Closed), " Personnel Error.Causes Partial
Containment Isolation Signal Lock-in". This revised LER provided
. additional information clarifying why the event was not initially-
recognized as reportable. As corrective action the licensee will
revise Nuclear Division Procedure (NDP)~600-3, " Event Reports" as to
what constitutes an Engineered Safety Features Actuation.
'
LER 89-02, Revision 0, (Closed), " Steam Generator
Pressure / Temperature Surveillance Not Performed - Procedure Not
Followed". This LER described a licensee identified event in which !
primary pressure was recorded once every eight hours vice every hour
as required by Technical Specifications. Surveillance procedure,
POT' 24-1, "Shif t Operating Routines," required hourly reading;
p- however, due to RCS temperature instruments being out of service an
alternate (nonrepresentative) temperature indicator was used. The
' indicator, a thermocouple mounted on the shell of the steam
generator, did not provide an accurate indication of primary
temperature. Additionally, the Operations Organization did not
properly deviate the surveillance procedure as required by
. administrative procedures nor was an engineering evaluation
performed on the appropriateness of the alternate temperature
indicator. Historically, the licensee has had a casual approach to
,
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procedure' compliance and, even though the licensee has increased:
emphasis'in this area, based on.recent events, increased _vigilence
Ha
b -is warranted. As corrective actions the' licensee has clarified the
-
surveillance procedure'and issued a Lessons' Learned Summary that
s *, ~
- , . highlights:the casual approach to. procedure. compliance 1and described
4 the desired-response. : The. inspectors verifled the surveillance
'
,
procedure had been changed'and the Lessons. Learned Summary was
- placed in Operator Required Reading.
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..'LER 89-03, Revision'0 and Revision 1 (Clos'ed), " Spurious Chlorine
J
4' ' Monitor Signal- Causes Control Room Ventilation Isolution
f
~
' Actuation". This LER and its revision described an event in which.
both trains'of the Control Room Emergency Ventilation' System were
'
- rendered inoperable while performing surveillance testing. The
licensee concluded that inadequate work instruction permitted th.e.
H mixing of chemicals in the vicinity of both' chlorine sensing
- '
devices,!and.that this' resulted 'in the isolation of both trains of
,, the Emergency Control Room Ventilation System. .As corrective action
H ;the surveillance . procedure was changed to provide definitive
- guidance on where and how chemicals are to be mixed, a training
,
sesision on chlorine detectors and their impact on emergency. control
, room ventilation'is. planned and.a design change is being evaluated
~
,
, ,
' to enable ^ overriding of the. toxic' gas interlock on the CB-1 outside
air dampers.. The inspectors attended the critiques concerning'this
~
event, verified the surveillance' procedure had been revised and
_ , : observed the, performance of the revised procedure.
'
LER 89-04, Redision 0, (Closed), " Lack of Procedure Causes
- Containment Ventilation Isolation Signal on Iodine Background
Increase in Containment". This LER describes an event in which a
M
'
Containment. Ventilation Isolation Signal-resulted.from not having a
j< r
requirement to periodically adjust alert and' alarm setpoints of'the
iodine '(PRM-1B) radiation monitor. as background radiation levels , ,
increased. Additionally, administrative practices of' recording as '
left-as found setpoints and operators knowing the; settings'.for the3,
alert and' alarm setpoints were weak. As corrective action; the
'
.,
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~ , licensee. issued Operations Procedure OM-5-1-3 that required process '
%: 1 radiation monitors-(PRMs) setpoints periodically be compared with' '
g,4 actual background levels and adjusted when levels. change by greater ,, ,'
53= than 25L The inspectors verified Operating. Procedur'e 0M-5-1-32had
"
,
been implemented, that setpoints were being. recorded and plant *
1 operators were knowledgeable of the new requirements. Additionally,
the inspectors attended the licensee critiques of the event 'and
discusses corrective actions and concerns with licensee management.
.e
- LER 89-05,' Revision 0, (Closed), "High Energy Line Break Barrier ,
This LER described an
' '
Non-Functional - Af fects Both Safety Trains".
event in which Technical Specification 3.0.3. was entered for
approximately thirty-five minutes due to a high energy line break
and fire door (door 131)'not latching because an abnormal
ventilation line-up existed. As corrective action the licensee is
processing a design change to reverse the opening direction of the
door so that air flow will force the door shut vice open.
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~ Additionally, the licensee evaluated all facility doors for this
( anomaly and will perform appropriate design changes.
b. The following'LERs are closed based on inspector follow-up that
included discussions with licensee' representatives,' detailed event
evaluation, verification of appropriateness and implementation of:
corrective actions and licensee commitment to perform future
corrective action:
LER 87-33, Revision l'(Closed),' Main Steam Pressure Transmitters
Out-of-Calibration: Revision 0 to LER 87-33 discussed several
potential causes.for this event in.which all 12 main steam line-
E pressure' transmitters were found to have' a zero shift of 21 to 50
psig in October.1987 In response to ah NRC request for
information with regard to the licen.se'e, continuing evaluation,
' Revision.1,was^ submitted,which stated that'the observed zero shift i
was;the; result of instrument drift. The-inspectors reviewed a :
portion if the' licensee evaluation result's'and discussed the results
.
'
with. licensee engineers, maintenance itersonnel, and licensing
representatives. The inspectors understoo'd that the. evaluation
concluded that although personnel error in the calibration process
could not be definitely. eliminated as a potential cause, it was not
the likely cause given that two different technicians _were involved
in the initial calibrations of the transmitters when they were
installed during the 1987 refueling outage. Licensee and vendor
review of the instructions for checkout, testing, and initial
~
transmitter calibration did not identify deficiencies which would
have' caused the observed zero shift. In addition, licensee "
i
engineers concluded that the new transmitters had been cycled three
times prior to installation per the vendor instruction manual. The ;
licensee's determination of instrument drift as the event cause was l
based on results of its continuing monitoring program since October t
1987 of the main steam line pressure transmitters which has shown a j
continued tendency for negative instrument drift. Observed drift,
however, has been less than that observed in October 1987-and less l
than the: manufacturer's specified 1% per year drift limit. Licensee ;
review of information from the Nuclear Plant Reliability Data System ;
..
'
showed a number of reported instances of instrument drift for the
applicable transmitter. In the review of Revision 1 of the LER, the
inspectors noted that the component failure information requested on
the LER form apeared to be incorrect. .This was discussed with the l
LER writer for accuracy of future reports. Although the inspectors ;
do not necessarily agree with the determination of the event cause, i
the inspectors considered that the licensee had evaluated other
potential causes and had implemented a monitoring program, as
described in Revision 1, with the purpose of providing confidence
that the pressure transmitters would continue to fulfill their
safety functions. This item is closed. i
No violations or deviations were identified.
1
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8. Followup of Open Items (9?700) ,
'
.
. Temporary Instruction 2515/101 (Closed) Loss of Decay Heat Removal: The
inspectors conducted an inspection of licensee actions in response to'NRC
Generic Letter. 88-17..which dealt with loss of decay; heat removal during
nonpower operation. The inspection followed the guidance given' in
Temporary Instruction 2515/101 to the NRC Inspection Manual,4 titled " Loss
.of Decay Heat Removal (Generic Letter No. 88-17).10 CFR 50.54 (f)." The'
scope of the inspection was limited to licensee expeditious?
' '
actions, as,
defined its GL 88-17.
. The:11censee's response to the en iitious actions identified in Generic
Letter 88-17 was submitted in a January 16, 1989, letter. The inspectors
reviewed the response and verified implementation of. selected features
through review of plant procedures, discussions with ' operations,
licensing, and training personnel, and plant observations. In accordance
with.T1 2515/101, the inspection was performed prior to NRR! evaluation of
. the licensee's response given that the plant was in an outage that
involved a reduced inventory condition. The plant's initial entry into a
reduced inventory condition, subsequent to the issuance of TI 2515/101,
was on April 18, 1989, to allow draining of steam generator tubes and
~ installation of blank flanges on reactor coolant pump seal leakoff lines.
The inspectors reviewed training lesson plan 03-I-16-LP which covered, in
part, a discussion of GL 88-17 and licensee response actions. This
training was given to operators prior to the 1989 Refueling Outage.
Discussion with training personnel and review of detailed notes used by
the lecturer verified that the training included a discussion of the
April 1987 Diablo Canyon event and review of planned hardware,
procedural, and administrative changes implemented in response to the
concerns outlined in GL 88-17. In addition, Operation's Department
- supervisory and engineering personnel conducted pre-evolution briefings
for reduced RCS inventory operations with each shift crew prior to the
plant being p1rsed in a reduced inventory condition.
i
- Overall. control . for plant operations in a reduced inventory condition was
effected by the issuance of General Operating Instruction GOI-12,
. Revision 0, titled " Plant Operation, Reactor Coolant System Reduced
Inventory and Recovery from Refueling." This procedure also provided
transition to other, more specific, procedures such as Administrative
Order A0-3-11, Revision 23, titled " Containment Access, Integrity,
Evacuation, and Inspections" which required the completion of closed
containment restoration plans for any open containment penetrations
,
.during reduced inventory conditions. The inspectors verified that
additional procedures provided for the assurance of two available means
'
of adding inventory to the reactor coolant system in the event of failure
of both residual heat removal pumps, and provided controls for hot leg
flow paths. GOI-12 included general guidance on the avoidance of
operations that would lead to reactor coolant system perturbations. In
addition, during the entry into reduced inventory conditions on April 18,
the Operations Department provided for 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> shift coverage by
engineers' knowledgeable with GL-88-17 concerns to assist the operation
shift supervisor in the review of activities which may perturb the
reactor coolant system or connected systems during reduced inventory
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e 'conditioris. Atthe' time!o[ inspection,thelicenseewasconsidering }{
additional or different controls to avoid reactor coolant system 1
l perturbations. 1
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? Licensee procedures'provided for the' monitoring of core exit temperatures
with two core exit thermocouple ~whenever the' reactor vessel head was ,
installed. .In addition Residual Heat Removal System performance was to-
'
be' monitor'ed by control room operators for system parameters such as pump
flow, amperage, discharge pressure, suction pressure, and inlet / outlet
' temperature < i ndications.
- The licensee' reactor coolant system level indication system consisted of ~
'two. standpipes connected'to the "B" and "C" loop crossover legs of.the
,_ . reactor. coolant system. One standpipe, joined piping. associated with'
reactor coolant system flow transmitter FT-425 on the "B" loop;Lthe other
'
standpipe.' joined piping associated with FT-435 on the "C" loop. The
"" ,
- standpipes were vented through permanently installed tubing to the top of
.the pressurizer shed. The standpipe associated with the "C" loop was
vented through. tubing which joined the spray line which enters the
pressurizer steam space. 'The vent path then used piping which leads to
'the pressurizer. power. operated relief valves, through manual valve 8094,
and.then through an open flange to the pressurizer shed air space. The
. standpipe associated with the "B" loop was vented through tubing which
connected.to piping upstream of manual valve 8094. The vent path was
then through the above mentioned open flange to the pressurizer shed air
space. Almough the. vent paths shared some common piping, the inspectors
considerea .at the two level indications were not inconsistent with the
guidance of GL 88-17 for independent level instrumentation. In addition,
the inspectors noted that the licensee provided an additional vent path,
.as allowed by thei.r procedures, by opening the pressurizer power operated
. relief valves,. draining.the pressurizer relief tank below the water
spargers, and replacing one of the pressurizer relief tank rupture discs
.. .with a screen.
Prior to the plant entering reduced inventory conditions, .the inspectors.
performed'a walkdown of the accessible portions of the level indication
system'outside high radiation areas. . The.' licensee had completed
modifications to the camera system which provided visual level indication
l' to the control room.' The modifications allowed in part control room
operators to. remotely tilt, pan, and focus the camera and allowed the
camera to be moved vertically over a 20' foot range locally te reduce
= optical parallax. In the walkdown, the inspectors identified that tubing
on the vent path.for the "B" loop standpipe was disconnected at a
swagelock fitting located in the pressurizer shed air space upstream of
l- the poin't at which the tubing joined the piping associated with manual
valve.8094. LThe tubing was:thus adequately vented in the as-found
'
,
i
condition but'in'a different manner'than indicated by plant procedures.
, ;The plant was not in a reduced inventory condition. In response, the
L ' licensee initiated an; internal event report, completed level standpipe
walkdowns and no other discrepancies were identified, and connected the
l
--fitting prior to placing the plant in'a reduced inventory condition on
-April 18b l989. A critique led by plant management identified several
potential:causes for the disconnected fitting, and included a corrective
action to' require a walkdown of the system prior to use. Prior to the
,
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f; event, auxiliary operators had conducted limited shiftly inspections.of
L . the standpipes primarily for system leaks and discrepancies at steel to
gl. ass joints and glass to glass joints in the standpipes.
! In the review of licensee actions and in discussions with licensee
personnel, the inspectors understood that implemented actions differed
from those outlined in tne January 16, 1989, submittal in the following
respects. First, the licensee has not revised all plant procedures to
ensure that all operations.that may lead to perturbations of the reactor
coolant system were prohibited. This was changed to a longer term action
for consideration and compensated for by actions such as assigning 24
hour engineering coverage to support-the shift supervisor as described
above. Second, a single procedure incorporating all applicable
instructions.for draining the reactor coolant system and responding to a
loss decay heat removal was not prepared. The licensee had developed
G01-12 with the purpose of providing more definitive control over
operations during reduced inventory conditions and providing direction to
, operators for transitioning to other procedures. At the time of
inspection the licensee planned to submit a supplement to'their previous
response which would discuss these changes and discuss other additional
clarifications.
4
- No violations or deviations were identified.
,
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. 9. Unresolved Item .
U
,
An unresolved' item is a matter about which more information isl required
r. to ascertain whether it is an acceptable item, a4 deviation,'or:a
^
1/ violation. An unresolved item is discussed in paragraph 51, >
10. Exit Interview (30703)
The inspectors met with the plant management as denoted in paragraph 1 on
May 19, 1989, and with licensee management throughout the. _ ,
inspection period. The inspectors also met with plant management on
April 14, 1989. In these meetings the inspectors summarized the scope
and findings of the inspection activities.
. _ _ _ _ _ _ _ _ - _ _ _ _ _