|
---|
Category:INSPECTION REPORT
MONTHYEARIR 05000397/19990011999-03-19019 March 1999 Insp Rept 50-397/99-01 on 990201-04 & 0303-05.No Violations Noted.Major Areas Inspected:Physical Security Program IR 05000397/19970071997-11-18018 November 1997 Partially Withheld Insp Rept 50-397/97-07 on 971020-26. (Ref 10CFR73.21).Violations Noted.Major Areas Inspected: Plant Support Re Vehicle Barrier Sys Which Was Consistent W/Summary Description & Accurately in Security Plan IR 05000397/19970061997-06-0909 June 1997 Insp Rept 50-397/97-06 on 970519-23.No Violations Noted. Major Areas Inspected:Insp Consisted of Review of Licensee Planned & Implemented Activities Associated W/Isi Program IR 05000397/19970021997-03-0606 March 1997 Insp Rept 50-397/97-02 on 970127-31 & 0212-14.No Violations Noted.Major Areas Inspected:Engineering & Plant Support Security IR 05000397/19960231996-12-16016 December 1996 Insp Rept 50-397/96-23 on 961118-22.No Violations Noted. Major Areas Inspected:Engineering & Plant Support IR 05000397/19930281993-08-26026 August 1993 Insp Rept 50-397/93-28 on 930809-13.No Violations Noted. Major Areas Inspected:Emergency Preparedness Program, Emergency Detection & Classification,Notification & Communication IR 05000397/19920341992-12-30030 December 1992 Insp Rept 50-397/92-34 on 921207-11.No Violations Noted. Major Areas Inspected:Emergency Preparedness Program IR 05000397/19880221988-06-29029 June 1988 Insp Rept 50-397/88-22 on 880606-09.Violation Noted.Major Areas inspected:880512 Radioactive Resins Spill in Radwaste Bldg Which Resulted in Declaration of Unusual Event & Facility Tour IR 05000397/19870271987-12-0303 December 1987 Insp Rept 50-397/87-27 on 871001-1105.Violations Noted.Major Areas Inspected:Control Room Operations,Esf Status, Surveillance & Maint Programs,Lers,Special Insp Topics & Licensee Action on Previous Insp Findings IR 05000397/19870031987-03-18018 March 1987 Insp Rept 50-397/87-03 on 870223-27.No Violations Noted. Major Areas Inspected:Calibr of Instrumentation,Ie Bulletin Followup,Licensee Action on Previous Insp Findings,Licensee Action on Items of Noncompliance & Part 21 Followup IR 05000397/19870011987-03-0303 March 1987 Insp Rept 50-397/87-01 on 870104-0214.No Violations or Deviations Identified.Major Areas Inspected:Control Room Operations,Esf Status,Surveillance Programs,Maint Topics, Lers,Special Insp Topics & Listed Insp Procedures IR 05000397/19860371987-01-16016 January 1987 Insp Rept 50-397/86-37 on 861116-870103.No Violations or Deviations Identified.Major Areas Inspected:Esf Status.Lers, Surveillance Program,Maint Program,Special Insp Topics & Licensee Action on Previous Insp Findings IR 05000397/19860381987-01-0707 January 1987 Insp Rept 50-397/86-38 on 861124-26 & 1215-19.No Violations Noted.Major Areas Inspected:Gaseous Waste Sys,Liquids & Liquid Wastes,Facilities & Equipment,Followup on IE Info Notices & Enforcement Items IR 05000397/19860261986-11-19019 November 1986 Insp Rept 50-397/86-26 on 860915-20.No Violations Noted. Major Areas Inspected:Emergency Preparedness Exercise & Associated Critique & Followup on Open Items Identified During Previous Insps IR 05000397/19860311986-09-17017 September 1986 Enforcement Conference Rept 50-397/86-31.Topics Discussed: Violations Identified in Insp Rept 50-397/86-12 Re Equipment Qualification Program,Violations in Insp Rept 50-397/86-11 & Repeat Violations in Control of Combustible Matls IR 05000397/19860111986-07-25025 July 1986 Insp Rept 50-397/86-11 on 860616-27.Violations Noted.Major Areas Inspected:Mgt Controls & Licensee Activities,Including Operator Recovery Actions,Qa Program,Measuring & Test Equipment & Tech Spec Surveillances & Tests IR 05000397/19860161986-05-16016 May 1986 Enforcement Conference Rept 50-397/86-16 on 860415.Major Areas Discussed:Apparent Violation Re Fire Protection Program Discussed in Insp Rept 50-397/86-05.App R Fire Protection Audit Findings Encl IR 05000397/19860081986-04-22022 April 1986 Insp Rept 50-397/86-08.No Violation or Deviation Noted.Major Areas Inspected:Changes to Emergency Preparedness Program, Public Info,Shift Staffing & Augmentation & Notifications & Communications ML20153H0281986-02-14014 February 1986 Insp Rept 50-397/86-02 on 860113-17 & 21 & 0203.No Violation or Deviation Noted.Major Area Inspected:Radiological Controls.Allegation Re Failure to Make Every Effort to Maintain Radiation Exposures ALARA Substantiated IR 05000397/19850261985-10-25025 October 1985 Insp Rept 50-397/85-26 on 850909-13.No Significant Deficiencies or Violations Noted.Major Areas Inspected: Emergency Preparedness Exercise & Associated Critique,Follow Up on Previous Findings & IE Info Notices & Previous Drills IR 05000397/19850341985-09-30030 September 1985 Safety Insp Rept 50-397/85-34 on 850909-13.No Violations or Deviations Noted.Major Areas Inspected:Followup of Generic Ltr 83-28, Required Actions Based on Generic ... & Ti 2515/64,Rev 1, Near-Term Insp Followup to Generic.. IR 05000397/19850131985-07-23023 July 1985 Insp Rept 50-397/85-13 on 850624-25.No Significant Deficiencies or Violations Identified.Major Areas Inspected: Emergency Preparedness,Including Knowledge & Performance (Training),Licensee Audits & Changes to Program IR 05000397/19850101985-07-0505 July 1985 Insp Rept 50-397/85-10 on 850325-29.No Violations or Deficiencies Noted.Major Areas Inspected:Emergency Response Facilities & Implementation of NUREG-0737,Suppl 1 Requirements.Items for Improvement Noted IR 05000397/19820141982-08-0202 August 1982 IE Insp Rept 50-397/82-14 on 820607-0709.Noncompliance Noted:Pipe Bending Procedures Not Properly Qualified & Approved & Prompt Measures Not Initiated to Document Condition or Identify Nonconforming Matl IR 05000397/19820161982-07-30030 July 1982 IE Insp Rept 50-397/82-16 on 820719-22.No Noncompliance Noted.Major Areas Inspected:Previously Identified Enforcement & Followup Items & Licensee Identified 10CFR50.55e Reported Items IR 05000397/19820121982-07-0101 July 1982 IE Insp Rept 50-397/82-12 on 820501-31.No Noncompliance Noted.Major Areas Inspected:Contractor Activities & Investigation of Allegations Re Processing of Nonconformance Repts & Insp of Fire Protection Sys IR 05000397/19820111982-06-25025 June 1982 IE Insp Rept 50-397/82-11 on 820517-20,0607 & 0609-11.No Noncompliance Noted.Major Areas Inspected:Activities Associated w/as-built Drawing Program & Followup Items IR 05000397/19820091982-05-26026 May 1982 IE Insp Rept 50-397/82-09 During Apr 1982.No Noncompliance Noted.Major Areas Inspected:Licensee & Contractor Activities to re-evaluate & Improve Detailed Work Methods IR 05000397/19780091978-09-14014 September 1978 Insp Rept 50-397/78-09 on 780822-25.No Noncompliance Noted. Major Areas Inspected:Review of Quality Records,Installation Procedures & Implementation of Fire Protection Program 1999-03-19
[Table view] Category:NRC-GENERATED
MONTHYEARIR 05000397/19990011999-03-19019 March 1999 Insp Rept 50-397/99-01 on 990201-04 & 0303-05.No Violations Noted.Major Areas Inspected:Physical Security Program IR 05000397/19970071997-11-18018 November 1997 Partially Withheld Insp Rept 50-397/97-07 on 971020-26. (Ref 10CFR73.21).Violations Noted.Major Areas Inspected: Plant Support Re Vehicle Barrier Sys Which Was Consistent W/Summary Description & Accurately in Security Plan IR 05000397/19970061997-06-0909 June 1997 Insp Rept 50-397/97-06 on 970519-23.No Violations Noted. Major Areas Inspected:Insp Consisted of Review of Licensee Planned & Implemented Activities Associated W/Isi Program IR 05000397/19970021997-03-0606 March 1997 Insp Rept 50-397/97-02 on 970127-31 & 0212-14.No Violations Noted.Major Areas Inspected:Engineering & Plant Support Security IR 05000397/19960231996-12-16016 December 1996 Insp Rept 50-397/96-23 on 961118-22.No Violations Noted. Major Areas Inspected:Engineering & Plant Support IR 05000397/19930281993-08-26026 August 1993 Insp Rept 50-397/93-28 on 930809-13.No Violations Noted. Major Areas Inspected:Emergency Preparedness Program, Emergency Detection & Classification,Notification & Communication IR 05000397/19920341992-12-30030 December 1992 Insp Rept 50-397/92-34 on 921207-11.No Violations Noted. Major Areas Inspected:Emergency Preparedness Program IR 05000397/19880221988-06-29029 June 1988 Insp Rept 50-397/88-22 on 880606-09.Violation Noted.Major Areas inspected:880512 Radioactive Resins Spill in Radwaste Bldg Which Resulted in Declaration of Unusual Event & Facility Tour IR 05000397/19870271987-12-0303 December 1987 Insp Rept 50-397/87-27 on 871001-1105.Violations Noted.Major Areas Inspected:Control Room Operations,Esf Status, Surveillance & Maint Programs,Lers,Special Insp Topics & Licensee Action on Previous Insp Findings IR 05000397/19870031987-03-18018 March 1987 Insp Rept 50-397/87-03 on 870223-27.No Violations Noted. Major Areas Inspected:Calibr of Instrumentation,Ie Bulletin Followup,Licensee Action on Previous Insp Findings,Licensee Action on Items of Noncompliance & Part 21 Followup IR 05000397/19870011987-03-0303 March 1987 Insp Rept 50-397/87-01 on 870104-0214.No Violations or Deviations Identified.Major Areas Inspected:Control Room Operations,Esf Status,Surveillance Programs,Maint Topics, Lers,Special Insp Topics & Listed Insp Procedures IR 05000397/19860371987-01-16016 January 1987 Insp Rept 50-397/86-37 on 861116-870103.No Violations or Deviations Identified.Major Areas Inspected:Esf Status.Lers, Surveillance Program,Maint Program,Special Insp Topics & Licensee Action on Previous Insp Findings IR 05000397/19860381987-01-0707 January 1987 Insp Rept 50-397/86-38 on 861124-26 & 1215-19.No Violations Noted.Major Areas Inspected:Gaseous Waste Sys,Liquids & Liquid Wastes,Facilities & Equipment,Followup on IE Info Notices & Enforcement Items IR 05000397/19860261986-11-19019 November 1986 Insp Rept 50-397/86-26 on 860915-20.No Violations Noted. Major Areas Inspected:Emergency Preparedness Exercise & Associated Critique & Followup on Open Items Identified During Previous Insps IR 05000397/19860311986-09-17017 September 1986 Enforcement Conference Rept 50-397/86-31.Topics Discussed: Violations Identified in Insp Rept 50-397/86-12 Re Equipment Qualification Program,Violations in Insp Rept 50-397/86-11 & Repeat Violations in Control of Combustible Matls IR 05000397/19860111986-07-25025 July 1986 Insp Rept 50-397/86-11 on 860616-27.Violations Noted.Major Areas Inspected:Mgt Controls & Licensee Activities,Including Operator Recovery Actions,Qa Program,Measuring & Test Equipment & Tech Spec Surveillances & Tests IR 05000397/19860161986-05-16016 May 1986 Enforcement Conference Rept 50-397/86-16 on 860415.Major Areas Discussed:Apparent Violation Re Fire Protection Program Discussed in Insp Rept 50-397/86-05.App R Fire Protection Audit Findings Encl IR 05000397/19860081986-04-22022 April 1986 Insp Rept 50-397/86-08.No Violation or Deviation Noted.Major Areas Inspected:Changes to Emergency Preparedness Program, Public Info,Shift Staffing & Augmentation & Notifications & Communications ML20153H0281986-02-14014 February 1986 Insp Rept 50-397/86-02 on 860113-17 & 21 & 0203.No Violation or Deviation Noted.Major Area Inspected:Radiological Controls.Allegation Re Failure to Make Every Effort to Maintain Radiation Exposures ALARA Substantiated IR 05000397/19850261985-10-25025 October 1985 Insp Rept 50-397/85-26 on 850909-13.No Significant Deficiencies or Violations Noted.Major Areas Inspected: Emergency Preparedness Exercise & Associated Critique,Follow Up on Previous Findings & IE Info Notices & Previous Drills IR 05000397/19850341985-09-30030 September 1985 Safety Insp Rept 50-397/85-34 on 850909-13.No Violations or Deviations Noted.Major Areas Inspected:Followup of Generic Ltr 83-28, Required Actions Based on Generic ... & Ti 2515/64,Rev 1, Near-Term Insp Followup to Generic.. IR 05000397/19850131985-07-23023 July 1985 Insp Rept 50-397/85-13 on 850624-25.No Significant Deficiencies or Violations Identified.Major Areas Inspected: Emergency Preparedness,Including Knowledge & Performance (Training),Licensee Audits & Changes to Program IR 05000397/19850101985-07-0505 July 1985 Insp Rept 50-397/85-10 on 850325-29.No Violations or Deficiencies Noted.Major Areas Inspected:Emergency Response Facilities & Implementation of NUREG-0737,Suppl 1 Requirements.Items for Improvement Noted IR 05000397/19820141982-08-0202 August 1982 IE Insp Rept 50-397/82-14 on 820607-0709.Noncompliance Noted:Pipe Bending Procedures Not Properly Qualified & Approved & Prompt Measures Not Initiated to Document Condition or Identify Nonconforming Matl IR 05000397/19820161982-07-30030 July 1982 IE Insp Rept 50-397/82-16 on 820719-22.No Noncompliance Noted.Major Areas Inspected:Previously Identified Enforcement & Followup Items & Licensee Identified 10CFR50.55e Reported Items IR 05000397/19820121982-07-0101 July 1982 IE Insp Rept 50-397/82-12 on 820501-31.No Noncompliance Noted.Major Areas Inspected:Contractor Activities & Investigation of Allegations Re Processing of Nonconformance Repts & Insp of Fire Protection Sys IR 05000397/19820111982-06-25025 June 1982 IE Insp Rept 50-397/82-11 on 820517-20,0607 & 0609-11.No Noncompliance Noted.Major Areas Inspected:Activities Associated w/as-built Drawing Program & Followup Items IR 05000397/19820091982-05-26026 May 1982 IE Insp Rept 50-397/82-09 During Apr 1982.No Noncompliance Noted.Major Areas Inspected:Licensee & Contractor Activities to re-evaluate & Improve Detailed Work Methods IR 05000397/19780091978-09-14014 September 1978 Insp Rept 50-397/78-09 on 780822-25.No Noncompliance Noted. Major Areas Inspected:Review of Quality Records,Installation Procedures & Implementation of Fire Protection Program 1999-03-19
[Table view] Category:INSPECTION REPORT
MONTHYEARIR 05000397/19990011999-03-19019 March 1999 Insp Rept 50-397/99-01 on 990201-04 & 0303-05.No Violations Noted.Major Areas Inspected:Physical Security Program IR 05000397/19970071997-11-18018 November 1997 Partially Withheld Insp Rept 50-397/97-07 on 971020-26. (Ref 10CFR73.21).Violations Noted.Major Areas Inspected: Plant Support Re Vehicle Barrier Sys Which Was Consistent W/Summary Description & Accurately in Security Plan IR 05000397/19970061997-06-0909 June 1997 Insp Rept 50-397/97-06 on 970519-23.No Violations Noted. Major Areas Inspected:Insp Consisted of Review of Licensee Planned & Implemented Activities Associated W/Isi Program IR 05000397/19970021997-03-0606 March 1997 Insp Rept 50-397/97-02 on 970127-31 & 0212-14.No Violations Noted.Major Areas Inspected:Engineering & Plant Support Security IR 05000397/19960231996-12-16016 December 1996 Insp Rept 50-397/96-23 on 961118-22.No Violations Noted. Major Areas Inspected:Engineering & Plant Support IR 05000397/19930281993-08-26026 August 1993 Insp Rept 50-397/93-28 on 930809-13.No Violations Noted. Major Areas Inspected:Emergency Preparedness Program, Emergency Detection & Classification,Notification & Communication IR 05000397/19920341992-12-30030 December 1992 Insp Rept 50-397/92-34 on 921207-11.No Violations Noted. Major Areas Inspected:Emergency Preparedness Program IR 05000397/19880221988-06-29029 June 1988 Insp Rept 50-397/88-22 on 880606-09.Violation Noted.Major Areas inspected:880512 Radioactive Resins Spill in Radwaste Bldg Which Resulted in Declaration of Unusual Event & Facility Tour IR 05000397/19870271987-12-0303 December 1987 Insp Rept 50-397/87-27 on 871001-1105.Violations Noted.Major Areas Inspected:Control Room Operations,Esf Status, Surveillance & Maint Programs,Lers,Special Insp Topics & Licensee Action on Previous Insp Findings IR 05000397/19870031987-03-18018 March 1987 Insp Rept 50-397/87-03 on 870223-27.No Violations Noted. Major Areas Inspected:Calibr of Instrumentation,Ie Bulletin Followup,Licensee Action on Previous Insp Findings,Licensee Action on Items of Noncompliance & Part 21 Followup IR 05000397/19870011987-03-0303 March 1987 Insp Rept 50-397/87-01 on 870104-0214.No Violations or Deviations Identified.Major Areas Inspected:Control Room Operations,Esf Status,Surveillance Programs,Maint Topics, Lers,Special Insp Topics & Listed Insp Procedures IR 05000397/19860371987-01-16016 January 1987 Insp Rept 50-397/86-37 on 861116-870103.No Violations or Deviations Identified.Major Areas Inspected:Esf Status.Lers, Surveillance Program,Maint Program,Special Insp Topics & Licensee Action on Previous Insp Findings IR 05000397/19860381987-01-0707 January 1987 Insp Rept 50-397/86-38 on 861124-26 & 1215-19.No Violations Noted.Major Areas Inspected:Gaseous Waste Sys,Liquids & Liquid Wastes,Facilities & Equipment,Followup on IE Info Notices & Enforcement Items IR 05000397/19860261986-11-19019 November 1986 Insp Rept 50-397/86-26 on 860915-20.No Violations Noted. Major Areas Inspected:Emergency Preparedness Exercise & Associated Critique & Followup on Open Items Identified During Previous Insps IR 05000397/19860311986-09-17017 September 1986 Enforcement Conference Rept 50-397/86-31.Topics Discussed: Violations Identified in Insp Rept 50-397/86-12 Re Equipment Qualification Program,Violations in Insp Rept 50-397/86-11 & Repeat Violations in Control of Combustible Matls IR 05000397/19860111986-07-25025 July 1986 Insp Rept 50-397/86-11 on 860616-27.Violations Noted.Major Areas Inspected:Mgt Controls & Licensee Activities,Including Operator Recovery Actions,Qa Program,Measuring & Test Equipment & Tech Spec Surveillances & Tests IR 05000397/19860161986-05-16016 May 1986 Enforcement Conference Rept 50-397/86-16 on 860415.Major Areas Discussed:Apparent Violation Re Fire Protection Program Discussed in Insp Rept 50-397/86-05.App R Fire Protection Audit Findings Encl IR 05000397/19860081986-04-22022 April 1986 Insp Rept 50-397/86-08.No Violation or Deviation Noted.Major Areas Inspected:Changes to Emergency Preparedness Program, Public Info,Shift Staffing & Augmentation & Notifications & Communications ML20153H0281986-02-14014 February 1986 Insp Rept 50-397/86-02 on 860113-17 & 21 & 0203.No Violation or Deviation Noted.Major Area Inspected:Radiological Controls.Allegation Re Failure to Make Every Effort to Maintain Radiation Exposures ALARA Substantiated IR 05000397/19850261985-10-25025 October 1985 Insp Rept 50-397/85-26 on 850909-13.No Significant Deficiencies or Violations Noted.Major Areas Inspected: Emergency Preparedness Exercise & Associated Critique,Follow Up on Previous Findings & IE Info Notices & Previous Drills IR 05000397/19850341985-09-30030 September 1985 Safety Insp Rept 50-397/85-34 on 850909-13.No Violations or Deviations Noted.Major Areas Inspected:Followup of Generic Ltr 83-28, Required Actions Based on Generic ... & Ti 2515/64,Rev 1, Near-Term Insp Followup to Generic.. IR 05000397/19850131985-07-23023 July 1985 Insp Rept 50-397/85-13 on 850624-25.No Significant Deficiencies or Violations Identified.Major Areas Inspected: Emergency Preparedness,Including Knowledge & Performance (Training),Licensee Audits & Changes to Program IR 05000397/19850101985-07-0505 July 1985 Insp Rept 50-397/85-10 on 850325-29.No Violations or Deficiencies Noted.Major Areas Inspected:Emergency Response Facilities & Implementation of NUREG-0737,Suppl 1 Requirements.Items for Improvement Noted IR 05000397/19820141982-08-0202 August 1982 IE Insp Rept 50-397/82-14 on 820607-0709.Noncompliance Noted:Pipe Bending Procedures Not Properly Qualified & Approved & Prompt Measures Not Initiated to Document Condition or Identify Nonconforming Matl IR 05000397/19820161982-07-30030 July 1982 IE Insp Rept 50-397/82-16 on 820719-22.No Noncompliance Noted.Major Areas Inspected:Previously Identified Enforcement & Followup Items & Licensee Identified 10CFR50.55e Reported Items IR 05000397/19820121982-07-0101 July 1982 IE Insp Rept 50-397/82-12 on 820501-31.No Noncompliance Noted.Major Areas Inspected:Contractor Activities & Investigation of Allegations Re Processing of Nonconformance Repts & Insp of Fire Protection Sys IR 05000397/19820111982-06-25025 June 1982 IE Insp Rept 50-397/82-11 on 820517-20,0607 & 0609-11.No Noncompliance Noted.Major Areas Inspected:Activities Associated w/as-built Drawing Program & Followup Items IR 05000397/19820091982-05-26026 May 1982 IE Insp Rept 50-397/82-09 During Apr 1982.No Noncompliance Noted.Major Areas Inspected:Licensee & Contractor Activities to re-evaluate & Improve Detailed Work Methods IR 05000397/19780091978-09-14014 September 1978 Insp Rept 50-397/78-09 on 780822-25.No Noncompliance Noted. Major Areas Inspected:Review of Quality Records,Installation Procedures & Implementation of Fire Protection Program 1999-03-19
[Table view] Category:UTILITY
MONTHYEARIR 05000397/19880221988-06-29029 June 1988 Insp Rept 50-397/88-22 on 880606-09.Violation Noted.Major Areas inspected:880512 Radioactive Resins Spill in Radwaste Bldg Which Resulted in Declaration of Unusual Event & Facility Tour IR 05000397/19870271987-12-0303 December 1987 Insp Rept 50-397/87-27 on 871001-1105.Violations Noted.Major Areas Inspected:Control Room Operations,Esf Status, Surveillance & Maint Programs,Lers,Special Insp Topics & Licensee Action on Previous Insp Findings IR 05000397/19870031987-03-18018 March 1987 Insp Rept 50-397/87-03 on 870223-27.No Violations Noted. Major Areas Inspected:Calibr of Instrumentation,Ie Bulletin Followup,Licensee Action on Previous Insp Findings,Licensee Action on Items of Noncompliance & Part 21 Followup IR 05000397/19870011987-03-0303 March 1987 Insp Rept 50-397/87-01 on 870104-0214.No Violations or Deviations Identified.Major Areas Inspected:Control Room Operations,Esf Status,Surveillance Programs,Maint Topics, Lers,Special Insp Topics & Listed Insp Procedures IR 05000397/19860371987-01-16016 January 1987 Insp Rept 50-397/86-37 on 861116-870103.No Violations or Deviations Identified.Major Areas Inspected:Esf Status.Lers, Surveillance Program,Maint Program,Special Insp Topics & Licensee Action on Previous Insp Findings IR 05000397/19860381987-01-0707 January 1987 Insp Rept 50-397/86-38 on 861124-26 & 1215-19.No Violations Noted.Major Areas Inspected:Gaseous Waste Sys,Liquids & Liquid Wastes,Facilities & Equipment,Followup on IE Info Notices & Enforcement Items IR 05000397/19860261986-11-19019 November 1986 Insp Rept 50-397/86-26 on 860915-20.No Violations Noted. Major Areas Inspected:Emergency Preparedness Exercise & Associated Critique & Followup on Open Items Identified During Previous Insps IR 05000397/19860311986-09-17017 September 1986 Enforcement Conference Rept 50-397/86-31.Topics Discussed: Violations Identified in Insp Rept 50-397/86-12 Re Equipment Qualification Program,Violations in Insp Rept 50-397/86-11 & Repeat Violations in Control of Combustible Matls IR 05000397/19860161986-05-16016 May 1986 Enforcement Conference Rept 50-397/86-16 on 860415.Major Areas Discussed:Apparent Violation Re Fire Protection Program Discussed in Insp Rept 50-397/86-05.App R Fire Protection Audit Findings Encl IR 05000397/19860081986-04-22022 April 1986 Insp Rept 50-397/86-08.No Violation or Deviation Noted.Major Areas Inspected:Changes to Emergency Preparedness Program, Public Info,Shift Staffing & Augmentation & Notifications & Communications ML20153H0281986-02-14014 February 1986 Insp Rept 50-397/86-02 on 860113-17 & 21 & 0203.No Violation or Deviation Noted.Major Area Inspected:Radiological Controls.Allegation Re Failure to Make Every Effort to Maintain Radiation Exposures ALARA Substantiated IR 05000397/19850261985-10-25025 October 1985 Insp Rept 50-397/85-26 on 850909-13.No Significant Deficiencies or Violations Noted.Major Areas Inspected: Emergency Preparedness Exercise & Associated Critique,Follow Up on Previous Findings & IE Info Notices & Previous Drills IR 05000397/19850341985-09-30030 September 1985 Safety Insp Rept 50-397/85-34 on 850909-13.No Violations or Deviations Noted.Major Areas Inspected:Followup of Generic Ltr 83-28, Required Actions Based on Generic ... & Ti 2515/64,Rev 1, Near-Term Insp Followup to Generic.. IR 05000397/19850131985-07-23023 July 1985 Insp Rept 50-397/85-13 on 850624-25.No Significant Deficiencies or Violations Identified.Major Areas Inspected: Emergency Preparedness,Including Knowledge & Performance (Training),Licensee Audits & Changes to Program IR 05000397/19850101985-07-0505 July 1985 Insp Rept 50-397/85-10 on 850325-29.No Violations or Deficiencies Noted.Major Areas Inspected:Emergency Response Facilities & Implementation of NUREG-0737,Suppl 1 Requirements.Items for Improvement Noted IR 05000397/19820141982-08-0202 August 1982 IE Insp Rept 50-397/82-14 on 820607-0709.Noncompliance Noted:Pipe Bending Procedures Not Properly Qualified & Approved & Prompt Measures Not Initiated to Document Condition or Identify Nonconforming Matl IR 05000397/19820161982-07-30030 July 1982 IE Insp Rept 50-397/82-16 on 820719-22.No Noncompliance Noted.Major Areas Inspected:Previously Identified Enforcement & Followup Items & Licensee Identified 10CFR50.55e Reported Items IR 05000397/19820121982-07-0101 July 1982 IE Insp Rept 50-397/82-12 on 820501-31.No Noncompliance Noted.Major Areas Inspected:Contractor Activities & Investigation of Allegations Re Processing of Nonconformance Repts & Insp of Fire Protection Sys IR 05000397/19820111982-06-25025 June 1982 IE Insp Rept 50-397/82-11 on 820517-20,0607 & 0609-11.No Noncompliance Noted.Major Areas Inspected:Activities Associated w/as-built Drawing Program & Followup Items IR 05000397/19820091982-05-26026 May 1982 IE Insp Rept 50-397/82-09 During Apr 1982.No Noncompliance Noted.Major Areas Inspected:Licensee & Contractor Activities to re-evaluate & Improve Detailed Work Methods IR 05000397/19780091978-09-14014 September 1978 Insp Rept 50-397/78-09 on 780822-25.No Noncompliance Noted. Major Areas Inspected:Review of Quality Records,Installation Procedures & Implementation of Fire Protection Program 1988-06-29
[Table view] Category:TEXT-INSPECTION & AUDIT & I&E CIRCULARS
MONTHYEARIR 05000397/19990011999-03-19019 March 1999 Insp Rept 50-397/99-01 on 990201-04 & 0303-05.No Violations Noted.Major Areas Inspected:Physical Security Program ML20154H7501998-10-13013 October 1998 Revised Notice of Violation from Insp on 971118.Violation Noted:In April 1996,licensee Made Changes to Procedures as Described in Safety Analysis Rept Without Seeking Prior Commission Approval & Changes Had Effect of Changing TS PNO-IV-98-025, on 980615,WNP-2 Initiated Plant Shutdown as Result of Traversing Incore Probe That Could Not Be Moved. Licensee Observed Some Drive Cable Damage & Cable Wrapped Around Some Components Under Reactor Vessel1998-06-16016 June 1998 PNO-IV-98-025:on 980615,WNP-2 Initiated Plant Shutdown as Result of Traversing Incore Probe That Could Not Be Moved. Licensee Observed Some Drive Cable Damage & Cable Wrapped Around Some Components Under Reactor Vessel ML20199E3161997-11-18018 November 1997 Notice of Violation from Insp on 971020-26.Violation Noted: on 971021,inspector Identified Gap in Vehicle Barrier Sys That Provided Path for Design Basis Vehicle to Gain Access to Unauthorized Proximity to Vital Area IR 05000397/19970071997-11-18018 November 1997 Partially Withheld Insp Rept 50-397/97-07 on 971020-26. (Ref 10CFR73.21).Violations Noted.Major Areas Inspected: Plant Support Re Vehicle Barrier Sys Which Was Consistent W/Summary Description & Accurately in Security Plan IR 05000397/19970061997-06-0909 June 1997 Insp Rept 50-397/97-06 on 970519-23.No Violations Noted. Major Areas Inspected:Insp Consisted of Review of Licensee Planned & Implemented Activities Associated W/Isi Program IR 05000397/19970021997-03-0606 March 1997 Insp Rept 50-397/97-02 on 970127-31 & 0212-14.No Violations Noted.Major Areas Inspected:Engineering & Plant Support Security IR 05000397/19960231996-12-16016 December 1996 Insp Rept 50-397/96-23 on 961118-22.No Violations Noted. Major Areas Inspected:Engineering & Plant Support ML20134Q0381996-11-21021 November 1996 EN-96-084:on 961126,notice of Proposed Imposition of Civil Penalty in Amount of $100,000 Issued to Licensee.Action Based on Several Instances Where Surveillances Not Performed & Mode Changes Made W/O Assurances That Equipment Operable PNO-IV-95-007, on 950218,plant Reactor Scrammed from 80% Power Due to Turbine Trip.News Media Was Notified of Event1995-02-21021 February 1995 PNO-IV-95-007:on 950218,plant Reactor Scrammed from 80% Power Due to Turbine Trip.News Media Was Notified of Event PNO-V-93-021, on 931201,chemical Spill in Radwaste Building. Caused by Addition of Oxidizing Agent,Hydrogen Peroxide. Employees Working on Floor Were Moved to Different Part of Plant1993-12-0202 December 1993 PNO-V-93-021:on 931201,chemical Spill in Radwaste Building. Caused by Addition of Oxidizing Agent,Hydrogen Peroxide. Employees Working on Floor Were Moved to Different Part of Plant ML20059D2141993-10-15015 October 1993 Notice of Violation from Insp on 930402-0517.Violation Noted:Licensee Determined That Records Required to Be Maintained by NRC Not Complete & Accurate in All Matl Respects IR 05000397/19930281993-08-26026 August 1993 Insp Rept 50-397/93-28 on 930809-13.No Violations Noted. Major Areas Inspected:Emergency Preparedness Program, Emergency Detection & Classification,Notification & Communication PNO-V-93-004, on 930121,automatic Reactor Scram Received Due to Low Level in Reactor Pressure Vessel.Licensee Estimates That Plant Will Be Shut Down for Repairs & Maint for 3 to 5 Days.Inspector Onsite During Event.Press Release Issued1993-01-21021 January 1993 PNO-V-93-004:on 930121,automatic Reactor Scram Received Due to Low Level in Reactor Pressure Vessel.Licensee Estimates That Plant Will Be Shut Down for Repairs & Maint for 3 to 5 Days.Inspector Onsite During Event.Press Release Issued IR 05000397/19920341992-12-30030 December 1992 Insp Rept 50-397/92-34 on 921207-11.No Violations Noted. Major Areas Inspected:Emergency Preparedness Program PNO-V-92-024, on 920711,while Retesting Main Steam SRV at Approx 14% Reactor Power,Srv 3B Opened When Operated from Control Room But Would Not Close.Reactor Operators Reduced Reactor Pressure in Effort to Reseat Valve1992-07-13013 July 1992 PNO-V-92-024:on 920711,while Retesting Main Steam SRV at Approx 14% Reactor Power,Srv 3B Opened When Operated from Control Room But Would Not Close.Reactor Operators Reduced Reactor Pressure in Effort to Reseat Valve PNO-V-91-031, on 911119,licensee Declared Unusual Event Following Low Reactor Pressure Vessel Level Condition W/Eccs Injecting.Reactor Tripped on Turbine Trip.All ECCS Sys Responded as Designed1991-11-19019 November 1991 PNO-V-91-031:on 911119,licensee Declared Unusual Event Following Low Reactor Pressure Vessel Level Condition W/Eccs Injecting.Reactor Tripped on Turbine Trip.All ECCS Sys Responded as Designed ML20203C2231991-06-14014 June 1991 PNO-V-91-04B on 910614,Region V Issued Rev 3 to CAL Concerning Actions to Be Taken by WPPSS Subsequent to Unsuccessful Simulator Requalification Retake Exam Performed 910605-06 PNO-V-90-049, on 901207,w/plant Operating at Full Power, Explosion Occurred in Area of B Phase Insulator of Plant Main Transformer,Which Caused Turbine & Reactor Trip.Unusual Event Was Declared Due to Explosion1990-12-0707 December 1990 PNO-V-90-049:on 901207,w/plant Operating at Full Power, Explosion Occurred in Area of B Phase Insulator of Plant Main Transformer,Which Caused Turbine & Reactor Trip.Unusual Event Was Declared Due to Explosion PNO-V-90-041, on 901024,licensee Declared Unusual Event After Determining That Vital & non-vital Instrument Power Supplies Interconnected Through Certain Sys Instrumentation1990-10-25025 October 1990 PNO-V-90-041:on 901024,licensee Declared Unusual Event After Determining That Vital & non-vital Instrument Power Supplies Interconnected Through Certain Sys Instrumentation PNO-IV-90-028, on 900603,while Attempting to Energize Station Normal Auxiliary Power Transformers,Short Circuit Failure in Bus Works for 25 Kv Sys.Fire Brigade Responded But No Fire Was Reported.Event Under Investigation1990-06-0404 June 1990 PNO-IV-90-028:on 900603,while Attempting to Energize Station Normal Auxiliary Power Transformers,Short Circuit Failure in Bus Works for 25 Kv Sys.Fire Brigade Responded But No Fire Was Reported.Event Under Investigation PNO-V-88-054, on 880824,licensee Declared Unusual Event as Result of Increase in Unidentified Leakage to Level Above TS Limit of 5 Gpm.Reactor Was Later Shutdown & Unidentified Leakage Rate Had Correspondingly Decreased to Approx 8 Gpm1988-08-24024 August 1988 PNO-V-88-054:on 880824,licensee Declared Unusual Event as Result of Increase in Unidentified Leakage to Level Above TS Limit of 5 Gpm.Reactor Was Later Shutdown & Unidentified Leakage Rate Had Correspondingly Decreased to Approx 8 Gpm IR 05000397/19880221988-06-29029 June 1988 Insp Rept 50-397/88-22 on 880606-09.Violation Noted.Major Areas inspected:880512 Radioactive Resins Spill in Radwaste Bldg Which Resulted in Declaration of Unusual Event & Facility Tour ML20150F9771988-06-29029 June 1988 Notice of Violation from Insp on 880606-09.Violation Noted: on 880512,individual Entered Radwaste Bldg W/O Being Accompanied or Provided W/Radiation Monitoring Device & on 880608,door to Radwaste Bldg Not Locked PNO-V-88-013, on 880213,plant Experienced Condenser Tube Failure & Shut Down Manually Scramming Plant from 35% Power. on 880214,reactor Bldg Air Supply Fan Started W/O Trip Circuit Being Energized.Cause Under Investigation1988-02-16016 February 1988 PNO-V-88-013:on 880213,plant Experienced Condenser Tube Failure & Shut Down Manually Scramming Plant from 35% Power. on 880214,reactor Bldg Air Supply Fan Started W/O Trip Circuit Being Energized.Cause Under Investigation IR 07100001/20110051987-12-0404 December 1987 Notice of Violation from Insp on 871001-1105.Violation Noted:Maint Electrician Worked More than 24 H in 48 H Period & Plant Operations Committee Meeting Held W/Chairman & Three Rather than Four Members as Required IR 05000397/19870271987-12-0303 December 1987 Insp Rept 50-397/87-27 on 871001-1105.Violations Noted.Major Areas Inspected:Control Room Operations,Esf Status, Surveillance & Maint Programs,Lers,Special Insp Topics & Licensee Action on Previous Insp Findings PNO-V-87-079, on 871126,digital Voltmeter Connected to Wrong Terminal Resulting in Inadvertent Opening of Safety Relief Valve 2D.Caused by Technician Error.Position of Safety Relief Valve Identified & Shut1987-11-27027 November 1987 PNO-V-87-079:on 871126,digital Voltmeter Connected to Wrong Terminal Resulting in Inadvertent Opening of Safety Relief Valve 2D.Caused by Technician Error.Position of Safety Relief Valve Identified & Shut ML20236T8241987-10-30030 October 1987 Exam Rept 50-397/OL-87-03 on 870922-30.Exam Results:Four Out of Six Reactor Operator Candidates & Eight Out of Eleven Senior Reactor Operator Candidates Passed Exams.Sample Test & Other Supporting Info Encl ML20236G3791987-10-26026 October 1987 PNS-V-87-008:on 871024,licensed Plant Operator Reportedly Arrested by Kennewick City Police Dept & Charged W/Discharge of Firearm within City Limits & Reckless Endangerment. Licensee Suspended Employee Unescorted Access to Plant PNO-V-87-024A, on 870322,reactor Manually Tripped Due to Loss of Feedwater.Caused by Mechanical Failure of 1/4-amp Fuse in Feedwater Control Sys.Rcic Sys Operated Properly.Plant Restarted on 8703241987-03-25025 March 1987 PNO-V-87-024A:on 870322,reactor Manually Tripped Due to Loss of Feedwater.Caused by Mechanical Failure of 1/4-amp Fuse in Feedwater Control Sys.Rcic Sys Operated Properly.Plant Restarted on 870324 PNO-V-87-024, on 870322,both Main Feedwater Pumps Lost Suction Pressure & Tripped.Plant Operator Manually Tripped Reactor Upon Losing All Feedwater Flow.Reactor Vessel Level Restored & Heat Manually Removed.Investigation Pending1987-03-23023 March 1987 PNO-V-87-024:on 870322,both Main Feedwater Pumps Lost Suction Pressure & Tripped.Plant Operator Manually Tripped Reactor Upon Losing All Feedwater Flow.Reactor Vessel Level Restored & Heat Manually Removed.Investigation Pending ML20205G6601987-03-20020 March 1987 Exam Rept 50-397/OL-87-02.Requalification Program Evaluated as Satisfactory,Per Rev 0 to NUREG-1021 & WT Russell 860522 Memo Re Listed Requirements PNO-V-87-022, on 870319,licensee Found Pressure Switch on Discharge Side of RHR Sys Pump B Isolated.Licensee Unisolated Switch & Restored Sys to Full Operability.Region V Followup Continuing1987-03-20020 March 1987 PNO-V-87-022:on 870319,licensee Found Pressure Switch on Discharge Side of RHR Sys Pump B Isolated.Licensee Unisolated Switch & Restored Sys to Full Operability.Region V Followup Continuing IR 05000397/19870031987-03-18018 March 1987 Insp Rept 50-397/87-03 on 870223-27.No Violations Noted. Major Areas Inspected:Calibr of Instrumentation,Ie Bulletin Followup,Licensee Action on Previous Insp Findings,Licensee Action on Items of Noncompliance & Part 21 Followup IR 05000397/19870011987-03-0303 March 1987 Insp Rept 50-397/87-01 on 870104-0214.No Violations or Deviations Identified.Major Areas Inspected:Control Room Operations,Esf Status,Surveillance Programs,Maint Topics, Lers,Special Insp Topics & Listed Insp Procedures PNO-V-87-015, on 870220,shutdown Commenced Due to Decreasing Lubrication Oil Pressure to Turbine Bearings.Caused by Flange or Pipe Leak Inside Lube Oil Reservoir.Shutdown Will Continue for Approx 4 to 6 Days1987-02-20020 February 1987 PNO-V-87-015:on 870220,shutdown Commenced Due to Decreasing Lubrication Oil Pressure to Turbine Bearings.Caused by Flange or Pipe Leak Inside Lube Oil Reservoir.Shutdown Will Continue for Approx 4 to 6 Days IR 05000397/19860371987-01-16016 January 1987 Insp Rept 50-397/86-37 on 861116-870103.No Violations or Deviations Identified.Major Areas Inspected:Esf Status.Lers, Surveillance Program,Maint Program,Special Insp Topics & Licensee Action on Previous Insp Findings IR 05000397/19860381987-01-0707 January 1987 Insp Rept 50-397/86-38 on 861124-26 & 1215-19.No Violations Noted.Major Areas Inspected:Gaseous Waste Sys,Liquids & Liquid Wastes,Facilities & Equipment,Followup on IE Info Notices & Enforcement Items PNO-V-86-084, on 861120,plant Shut Down Due to Inoperability of Acoustic Monitor for Safety Relief Valve 5c.Caused by Lack of Environ Qualification Documentation for Connector. Investigation Underway.Plant Will Be Restarted on 8611251986-11-20020 November 1986 PNO-V-86-084:on 861120,plant Shut Down Due to Inoperability of Acoustic Monitor for Safety Relief Valve 5c.Caused by Lack of Environ Qualification Documentation for Connector. Investigation Underway.Plant Will Be Restarted on 861125 IR 05000397/19860261986-11-19019 November 1986 Insp Rept 50-397/86-26 on 860915-20.No Violations Noted. Major Areas Inspected:Emergency Preparedness Exercise & Associated Critique & Followup on Open Items Identified During Previous Insps PNO-V-86-078, on 861107 & 09 Increased Vibration from Reactor Recirculating Water Pump a Occurred.Licensee Reduced Reactor Power & Shifted Pumps Into Low Frequency Operation, Decreasing Vibration Level1986-11-12012 November 1986 PNO-V-86-078:on 861107 & 09 Increased Vibration from Reactor Recirculating Water Pump a Occurred.Licensee Reduced Reactor Power & Shifted Pumps Into Low Frequency Operation, Decreasing Vibration Level PNO-V-86-064A, on 860918,licensee Declared Alert Due to Tornado Warnings & High Winds.Train a Svc Water Sys out-of- Svc Due to Fire in Svc Water Pump House.Licensee Also Experiencing Low Fire Main Header Pressure1986-09-18018 September 1986 PNO-V-86-064A:on 860918,licensee Declared Alert Due to Tornado Warnings & High Winds.Train a Svc Water Sys out-of- Svc Due to Fire in Svc Water Pump House.Licensee Also Experiencing Low Fire Main Header Pressure PNO-V-86-064, on 860918,licensee Declared Unusual Event Due to High Winds of 85 Mph.Svc Water Pump B out-of-svc Resulting in Emergency Diesel Generator B Being out-of-svc. Rupture in Low Pressure Fire Main Also Reported1986-09-18018 September 1986 PNO-V-86-064:on 860918,licensee Declared Unusual Event Due to High Winds of 85 Mph.Svc Water Pump B out-of-svc Resulting in Emergency Diesel Generator B Being out-of-svc. Rupture in Low Pressure Fire Main Also Reported ML20206U1861986-09-18018 September 1986 Notice of Violation from Insp on 860616-27 IR 05000397/19860311986-09-17017 September 1986 Enforcement Conference Rept 50-397/86-31.Topics Discussed: Violations Identified in Insp Rept 50-397/86-12 Re Equipment Qualification Program,Violations in Insp Rept 50-397/86-11 & Repeat Violations in Control of Combustible Matls ML20206U7381986-09-17017 September 1986 Exam Rept 50-397/OL-86-02 on 860811-14.Exam Results:One Senior Reactor Operator Candidate Failed Simulator Portion & One Senior Reactor Operator Candidate Failed Oral & Simulator Portions of Exam.Eight Candidates Passed PNO-V-86-060, on 860903,reactor Feedwater Pump B Tripped Due to Failure of Overspeed Controls.Caused by Partial Control Valve Closure Re Tripping of Hydraulic Power Units. Investigation Underway1986-09-0404 September 1986 PNO-V-86-060:on 860903,reactor Feedwater Pump B Tripped Due to Failure of Overspeed Controls.Caused by Partial Control Valve Closure Re Tripping of Hydraulic Power Units. Investigation Underway IR 05000397/19860111986-07-25025 July 1986 Insp Rept 50-397/86-11 on 860616-27.Violations Noted.Major Areas Inspected:Mgt Controls & Licensee Activities,Including Operator Recovery Actions,Qa Program,Measuring & Test Equipment & Tech Spec Surveillances & Tests PNO-V-86-034, on 860620,licensee Measured 1.3 Gpm Leakage Into RHR Sys B.Caused by Leak Through LPCI Injection Valve 53B.Util Repairing Valve.Startup Will Be Delayed Until 860629 Due to BPA Load Requirements1986-06-23023 June 1986 PNO-V-86-034:on 860620,licensee Measured 1.3 Gpm Leakage Into RHR Sys B.Caused by Leak Through LPCI Injection Valve 53B.Util Repairing Valve.Startup Will Be Delayed Until 860629 Due to BPA Load Requirements 1999-03-19
[Table view] |
Text
_ - _ - - ___ --
-
s
__
- .
I i
,
U. S. NUCLEAR REGULATORY COMMISSION
REGION V
'
>
,
. Report No: 50-397/87-27'
!-
l Docket No: 50-397
. Licensee: ~ Washington Public Power Supply-System P. O. Box 968
!
.Richland, WA 99352
- Facility Name
- Washington Nuclear Project No. 2 (WNP-2)
Inspection _at: WNP-2 Site near Richland, Washington Inspection Conducted: October 1 - November 5, 1987 Inspector: uuj. 6 / # d' 7 hCTJ./sted,SeniorResidentInspectorDateSigned
.' Approved by: 4- / 87 P. hnson, Chief Date-Signed React Projects Section 3 Summary:
~ Inspection on October 1 - November 5, 1987 (50-397/87-27) ]
- Areas Inspected: Routine inspection by the resident inspector of control room ;
operations, engineered safety feature (ESF) status, surveillance program, J maintenance program, licensee event reports, special inspection topics, and licensee action on previous inspection findings. During this inspection, ,
Inspection Procedures ~ 30702, 30703, 35701, 36100, 40700, 40701, 61726, 62702,
'
71707, 71709, 71710, 71881, 90712, 90713, 92700, 92701, and 92702 were covere )
Results: Two violations were identified: exceeding . Technical Specification i overtime limitations without authorization (paragraph 3), and conducting a Plant Operations Committee meeting without the minimum Technical Specification
- quorum (paragraph 13).
)
<
1 871204 NkE&KOMMw7 Q
PDR
-
~h ,
_ _ - - _ _ _ _ _ . _ . _ _ _ _ _ _ _ _ - . - - - _ _ _ _ _ - - _ - _ _ - _ _ _ _ - _ - _ - - - - -
1h{ , -
+y ,
.
en
DETAILS Persons Contacted-L. Oxsen, Assistant Managing Director for Operations J. Burn, Director, Engineering _
R. Glasscock,-Director, Licensing and Assurance
- C. Powers', Plant Manager J. Baker, . Assistant Plant Manager
- R. Corcoran, Assistant Plant Manager (Acting)/ Operations Manager W. Shaeffer,- Assistant Operations Manager.(Acting)
- K. Cowan, Technical Manager-
'J. Harmon, Assistant Maintenance Manager
- R. Graybeal, Health Physics and Chemistry Manager D. Feldman, Plant Quality Assurance Manager J.' Peters, Administrative Manager P. Powell, Licensing Manager
.
J. Landon, Maintenance Manager The inspector also interviewed various control room operators, shift supervisors and shift managers, engineering, quality assurance, and management personnel relative to activities in progress and record * Attended the Exit Meeting on November 5,198 . Plant Status At the start of the inspection period, the plant was operating near 100%
power.. The plant operated at this power level throughout the inspection period except for brief periods of time during which power was reduced to approximately 85% while the condensate filter /demineralizers were renewed. On October 10, the acoustic flow monitor for Main Steam Safety Relief Valve MS SRV-2D was declared inoperative and Technical Specification 3.3.7.5 action' statement was entered. The Technical Specification requires that two valve position indicators be operable for each safety relief valve. The action statement required that the monitor be repaired within seven days or the plant be shut down. To effect repairs the plant must be shut down so that an entry can be made into the drywell to gain access to the monitor. The licensee applied for and and received an emergency Technical Specification change which allowed the tailpipe temperature for valve SRV-20 to be alarmed and granted L relief from the requirement that MS SRV-20 have two position indicators.
'
This relief will' continue until the next available outage when repairs can be mad l On October 19, an unusual noise was heard coming from the RPS motor generator (MG) "A". Engineers from the technical staff and members of the plant maintenance staff observed the MG, performed acoustic and temperature tests, and added grease to the MG's bearings. On October 20, another evaluation of the MG led to the decision to replace the MG with a i spare uni J
_ _ - - _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ - _ . _ _ _ _ _ __ . _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ . _ _
-
'
..
At the.end of the inspection period, the plant had operated at power for l 102 consecutive days.
! Previously Identified NRC Inspection Items The inspector reviewed records, interviewed personnel, and inspected !
plant conditions relative to licensee actions on previously identified inspection findings: (Closed) Enforcement Item (397/87-09-01): Underwater Light Removed Without A Survey On two different occasions an underwater light and a television camera were removed from the refueling pool without a survey being performed to detect radiation hazards. The material was surveyed after removal and bagged for contamination contro The inspector reviewed a letter issued by the plant manager to all station personnel that reinforced the need for compliance with radiological procedures and the role of all station personnel in ensuring radiological safety. The licensee also intends to install a permanent radiation monitor on the refueling bridge. This will be followed up under the normal inspection program. This item is close (Closed) Enforcement Item (397/87-09-02): Gas Bottles Were Secured to a Safety Related Support The inspector identified that 39 gas bottles were stored by attaching them to a safety related cable tray support in the railroad bay of the Reactor Building, i
The licensee removed the bottles and a sign was attached to the wall
'
which directed personnel to store the empty bottles on the floo A directive was also placed in the Radwaste Control Room's standing orders to that effect.. Plant procedure 1.3.1 " Standing Orders / Night Orders" was revised to stipulate responsibility for the surveillance and disposition of the empty bottles. These items were reviewed by the inspector and this item is close (Closed) Enforcement Item (397/87-09-031: Weekly Source Check Not Performed on Radiation Monitoring Equipment A weekly source check was not performed on a continuous air monitor on the 606 elevatio After identifying this item the air monitor was checked and found to be satisfactory and the process that performs the source checks was also reviewed. A letter to all Health Physics technicans was sent by the Health Physics / Chemistry Manager which stressed the details )
of recent NRC violations and their causes. The letter also j emphasized the need for strict compliance with plant procedure ^
i
)
__ ____ ___
_-_________-_ __ ___-- __ ._______ _ _ - _ _ - . _ - . _ - _ _ _ _ _ _
..
The inspector reviewed this letter and has inspected the radiation monitoring equipment on numerous occasions and has not found any additional lapses in the source checks. This item is considered close , (Closed) Enforcement Item (397/87-13-01): Failure to Comply With Receiving Inspection Requirements Several instances occurred wherein Conditional Release Tags were ,
filled out before the Non Conformance Report (NCR) was fully !
dispositione .
Administrative controls over the use of Conditional Release Tags have been changed by a Deviation to Plant Procedures Manual (PPM)
1.3.12 " Plant Problems" and Plant QC Manual PQC-09 to require that L
an approved completed NCR exists before a Conditional Release Tag is issued. This is insured by QC not releasing the material until receipt of an NCR signed by the Plant Technical Manager and the Plant QA Manager. The plant QC staff and plant technical staff have been informed of these changes by memo. This item is considered close, e. (Closed) Unresolved Item (397/87-09-04): Overtime Without Authorization A review of Overtime Authorizations from the first quarter of the year revealed possible problems with authorization of excess overtime. . Technical Specifications require that the Plant Manager, his assistant, or higher levels of management authorize exceeding the Technical Specification limits on work hours when the work involves safety related items. Plant procedures allowed the approval to be delegated downward to the Shift Manage Management took steps to correct the procedure and issued night orders that directed the Shift Manager to obtain approval via telecon with plant management prior to authorizing the excess overtime. -The procedure was revised in August 1987, and incorporated changes which brought the plant procedure in line with the Technical Specification Another review by the inspector of a sample of Overtime i Authorizations from the third quarter, which included the end of the l refueling outage, indicated that similar problems with the tracking
'
of overtime still existed. A health physics individual working 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> days worked 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br /> on June 22. This combined with the previous days' 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> exceeded 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in a 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> period. No authorization was obtained to exceed 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in a 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> period for this day. The next day, June 23, the individual worked another 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> day which also exceeded the 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in a 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> period, but an authorization was obtained for the second day. Although this individual was not performing safety-related work, this was not in accordance with the licensee's procedure '
?
- --
..
. - - )
, _ _ _ _ ..
_ _ _ _ _ _ . _ _ _ _ - _ _ . - . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ __ _ _____-_-______ _ ___ _ -_
% 1 The inspector also determined that an electrican worked 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> on
, June 15, and 16.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> on June 16. He had authorization to exceed
.
16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. period and 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in a 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> period for June 16 only. On June 17, he worked 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> on the Main Steam Leakage Control System motor operated valves, a safety related ]
- . system. .These work hours on June 16 and 17 totaled 28.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> in'a J 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> period exceeding the Technical Specification limit of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in a 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. period without prior authorization. This is
"
_ considered a. violation of Technical Specification 6.2.2.f. This
-
' unresolved item is considered closed and will be followed under Enforcement Item 87-27-0 . Operational' Safety Verification
' P1'a'nt Tours The following plant areas were toured by the inspector during the course of the' inspection:
o Reactor Building o Control Room o Diesel Generator Building o Radwaste Building o Service Water Buildings o- Technical Support Center o ~ Turbine Generator Building o Yard Area and Perimeter The following items were observed during the tours:
(1) and Record Records were reviewed against Operating Technical Speci Logs _Tication and administrative control procedure requirement (2) Nonitoring Instrumentation. Process instruments were observed for correlation between channels and for conformance with Technical Specification requirement (3) Shift Manning. Control room and shift manning were observed for conformance with 10 CFR 50.54.(k). Technical Specifications, and administrative procedure (4) Equipment Lineups. Valve and electrical breakers were verified to be in the position or condition required by Technical Specifications and Administrative procedures for the applicable plant mode. This verification included routine control board indication reviews and conduct of partial system lineups.
l (5) Equipment Tagging. Selected equipment, for which tagging requests had been initiated, was observed to verify that tags were-in place and the equipment was in the condition specifie _ _______ __-________________-_____ _
__- _ - _- -_ _ -
'
=.. i 5'
]
t
.(6) General Plant' Ecuipmenti Condnions. Plant equipment was observed for indications of system leakage, improper lubrication, or other. conditions that would prevent the system from fulfilling .its functional requirement (7) ' Fire Protection. : Fire fighting; equipment and' controls were ' observed for conformance with Technical Specifications and administrative procedures.
'
!
(8) Plant Chemistry.. Chemical analyses and trend results were reviewed for confomance with Technical Specifications and administrative control procedure ,
(9) Security. Abtivities were observed for conformance wit regulatory requirements, implementation of the site securit plan, and administrative procedures. These activities included vehicle and personnel access, and protected and vital area integrit (10) Plant Housekeeping. Plant conditions and material / /
equipment storage were observed to determine the general state of cleanliness and housekeeping. Housekeeping in the radiologically controlled area was evaluated with respect to controlling the spread of surface and airborne contaminatio (11)RadiationProtectionControls. Areas observed included control point operation, records of licensee's surveys and posting of radiation and high radiation areas within the radiological controlled area, compliance with Radiation '
Exposure Permits, proper wearing of personne1 ~ monitoring devices, and personnel frisking practice No violations of NRC requirements or deviations were identifie . Engineered Safety Feature System Walkdown Selected engineered safety feature systems (and systens important to safety)'were walked down by the inspector to confirm that the systems were aligned in accordance with plant procedures. During the walkdown of the systems, items such as hangers, supports, electrical power supplies, cabinets, and cables were inspected to determine that they were operable
- and in a condition to perform their required functions. The inspector .
also verified that the system valves were in the required position and !
locked as appropriate. The local and remote position indication and t controls were also confirmed to be in the required position and operabl Accessible portions of the following systems were walked down on the indicated dat System Date Diesel Generator Systems, October 7,29 Divisions 1, 2, and _ _ - _ _ _ _ - _ - _ _ _ _ _ _ . _ . _ _ . . _ _ _ _ _
.
f l'
.
h
'
I
{
Hydrogen Recombiners October 28 Low Pressure Coolant Injection (LPCI), October 19,21 Trains "A", "B", and "C" Low Pressure Core Spray October 6,19 ;
High Pressure Core Spray October 6,21
]
Reactor Core Isolation Cooling October 6 I i
Standby Service Water Systems A and B October 8 Standby Liquid Control (SLC) System October 19 125V DC Electrical Distribution, October 15 Divisions 1 and 2 ;
250V DC Electrical Distribution October 15 No violations of NRC requirements or deviations were identifie '
6. Surveillance Testing Surveillance tests required to be performed by the Technical Specifications (TS) were reviewed on a sampling basis to verify that: 1).the surveillance tests were correctly included on the facility schedule; 2) a technically adequate procedure existed for performance of the surveillance tests; 3) the surveillance tests had been performed at the frequency specified in the TS; and 4) test results satisfied acceptance criteria or were properly dispositione Portions of the following surveillance were observed by the !
inspector on the dates shown:
Procedure Description Dates Performed 7.4.1. SLC Flow Verification October 25 7.4.3.3.1.46 Automatic Depressuriza E n System October 10 ,
(ADS) Trip System B Reaccor Water l Level Low - Level 3 Channel Functional !
Test
7.4.3.7. Accident Monitoring Instrumentation October 11 Channel Checks 7.4.6.4.1.2' Drywell Vacuum Breaker Operability October 11 7.4.7.6. Plant Fire Hose Station Operability October 11 Check 1
1
~ _ _ _ - _ - - - _ -
- _ _ . __ _ _ _ - _ _ _ - _ _ _ _ _ _ _ _ _ _
.
, 7.4.7.7. Fire Door Supervision Functional
'
October 11 Check 7.4.8. Division 1,2,&3 Breaker Alignment October 11, Weekly Check 25 7.5. LPCI Flowpath Verification October 25 No violations of NRC requirements or deviations were identifie . _P__lant Maintenance During the inspection period, the inspector observed and reviewed documentation associated with maintenance and problem investigation activities to verify compliance with regulatory requirements, compliance with administrative and maintenance procedures, required QA/QC involvement, proper use of safety tags, proper equipment alignment and use of jumpers, personnel qualifications, and proper retesting. The
' inspector verified deportability for these activities was correc The inspector witnessed portions of the following maintenance activities:
Description Dates Performed 1 Infrared scanning of Control Room October 8 Panels P609 and P611
' Calibration of Average Power Range Monitor (ARPM) October 8 Channel D per PPM 7.4.3.1.1.46 Installation of Control Room annunciator for October 16 Main Steam Safety / relief Valve (MS SRV)-20 tail pipe High Temperature Alarm Troubleshooting of Reactor Protection System (RPS) October 19 MG 'A' per AV 1480 Replacement of RPS MG 'A' per AV 1997 October 21
Installation testing of RPS MG'A' per AV 1998 October 23 l No violations of NRC requirements or deviations were identifie . Radiological Practices }
The inspector periodically observed radiological protection practices to determine whether the licensee's program was being implemented in conformance with facility policies and procedures and in compliance with j regulatory requirements. The inspector verified that health physics l supervisors and professionals conducted frequent plant tours to observe I activities in progress and were generally aware of significant plant l activities, particularly those related to radiological conditions and/or )
challenges. ALARA consideration was given each job that was performed l during maintenance activitie l 4 .
__-_____.________.--__._--______--__.___-.-.._._a
_ _ _ _ _ _ _ _
.
-
No violations of NRC requirements or deviations were identifie . Physical Security The inspector periodically observed security practices to that ascertain the licensee's implementation of the security plans was in accordance with site procedures. The inspector observed that the number of guards was adequate for the requirements of the security plan; that the search equipment at the access control points was operational; that the protected area barriers were well maintained without breaks; and that personnel allowed access to the protected area were badged and monitored and the monitoring equipment was functional. Night illumination inside the protected area was observed and obstructions were lighted adequatel Surveillance equipment was also observed during this inspectio No violations of NRC requirements or deviations were identifie ,
'" Licensee Event Report (LER) Followup The following LERs associated with operating events were reviewed by the inspector. Based on the information provided in the report it was concluded that reporting requirements had been met, root causes had been identified, and corrective actions were appropriate. The below LERs are considered close LER NUMBER DESCRIPTION .
LER 87-02 Reactor Trip Caused By a Loss of Feedwater -
LER 87-10 ESF Actuation Caused by Procedural Error No violations of NRC requirements or deviations were identifie . 10 CFR Part 21 Report Followup The following Part 21 reports associated with conditions identified by .
'
the plant and the industry were reviewed by the inspector. Based on this review, it was concluded that the root causes had been identified, and corrective actions were appropriat The below Part 21 reports are considered close Report Number DESCRIPTION 83-08-P Reactor Water Cleanup System Leak Detection 86-18-P Cracking of Limitorque Switch Rotors 86-19-P ITE/Gould Disconnect Switch Potential Failure 86-22-P Deficiencies in Wilmar Undervoltage Relays 86-23-P MSIV Thrust Bearing Sleeve Failure 86-25-P Limitorque Supplied Buchanan 724 Terminal Stripes Environmental Qualification 86-26-P SOR Inc. Pressure Switches Repeatability . _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
.
'*
11. Review of Periodic and Special Reports Periodic and special reports submitted by the licensee pursuant to Technical Specifications 6.9.1 and 6.9.2 were reviewed by the inspecto This review included the following considerations: the report contained the information required to be reported by NRC requirements; test results and/or supporting information were consistent with design predictions and performance specifications; and the validity of the reported informatio Within the scope of the above, the following reports were reviewed by the inspector, o Monthly Operating Report for September 198 No violations of NRC requirements or deviations were identifie . Corporate Nuclear Safety Review Board Meeting On October 8 and 9, a semiannual meeting of the Corporate Nuclear Safety Review Board was conducted on site. The Board had a large agenda and spent two days on the numerous facets of their review. The inspector observed discussions of the following topics during the proceedings:
Emergency Preparedness Environmental Monitoring Off Site Radiological Monitoring QA Observation on NRC Inspection Reports Radiological Control LER Review Audit Reports The members asked detailed questions of the plant staff and appeared to understand the problems experienced in the plant. A review of the meeting minutes was conducted by the inspector for details that occurred when the inspector was not in attendance. Overall, the inspector concluded, the Board performed its chartered function and fulfilled its Technical Specification requirement No violations or deviations were identifie . Plant Operations Consnittee A review of Plant Operations Consnittee (P0C) meetings conducted during the previous four months was performed by the inspector for compliance with the Technical Specifications and PPM 1.1.5 " Plant Operations Committee" The inspector noted that the Technical Specification delineates only members and alternate members of the POC. The Technical Specification lists the members of the P0C by work title and describes how to appoint an alternate member. The procedure had added " delegated" and " conditional" members to those listed in the Technical Specificatio PPM 1.1.5.3.A.1 states that "A Delegated Member is an individual with a prior written delegation, to act for a permanent member, and may attend all P0C meetings during the period of the delegation." The procedure does not specify if the delegate piember can act for the member if the member is on site. The delegation authority letter for these individuals stated that the individual was to act as that member in all capacities while the member was not on sit )
i
_______________j
- _ _ _ _ - __ ____ _ _ _ _ _ _ _ _ - _ - _ _ _ _ _ _ - _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ - _ _ _ - _ _ ___ __ __ _
__
..
, ..
- -
The minutes of 24. P0C's were reviewed. From these reviews the inspector identified that delegated members were used on three occasions:when the regular member was on site. These individuals were classified as
,
delegated (i.e., regular) members, not alternates, in the P0C minutes.
- Two of the three. meetings had enough other members in attendance to constitute a quorum, but on September 4,1987, a. condition was identified wherein a proper quorum was not established. In the morning meeting held that day, P0C 87-35.1, one regular member, an alternate member, and two
" delegated" members were in attendance in addition to the Chairman. One delegated member was acting for a regular member who was not on sit ! Contrary to the delegation letter, the other delegated member, the assistant maintenance manager, acted as and was listed in the minutes as g a delegated member even though the maintenance manager (a regular P0C
"-
member) was on site. The' assistant maintenance manager also was not
~
designated by the P0C as an alternate member. For this POC meeting, therefore, only the' P0C Chairman and three other members were officially-
, , present. This was less than the quorum (Chairman or Vice Chairman plus
, four other members) required by the Technical Specifications. This P0C reviewed and made reconmiendations regarding LER 87-13-01. This conduct of a POC meeting with less than the required quorum was a violation of Technical' Specification 6.5.1.5 (Enforcement Item 87-27-02).
Although not contrary to requirements, the inspector also identified one-case wherein the assistant operations manager acteo as the P0C vice '
chairman when the regular Chairman, Vice Chairman, and Operations Manage :were not available; i.e., the FSAR line of authority was used in this case. Discussions with senior plant management indicated to the inspector that POC meetings would normally be chaired by the Plant Mar,ager or Assistant Plant Manage . Exit Meeting The inspector met with licensee management representatives periodically during the report period to discuss inspection status and an exit meeting was' conducted with the indicated personnel on November 5, 198 The scope of the inspection and the inspector's findings, as noted in this report, were discussed and acknowledged by the licensee representative :
i i
_ _ _ . _ _ _ _ _ _ _ _ _ _ _ )