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Category:INSPECTION REPORT
MONTHYEARIR 05000338/19990031999-07-0202 July 1999 Insp Repts 50-338/99-03 & 50-339/99-03 on 990425-0605.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000338/19990011999-04-12012 April 1999 Insp Repts 50-338/99-01 & 50-339/99-01 on 990131-0313. Violations Noted.Major Areas Inspected:Operations, Engineering,Maintenance & Plant Support.In Addition,Results of Insp by Region Based Fire Protection Specialist Encl IR 05000338/19980111999-03-0101 March 1999 Insp Repts 50-338/98-11 & 50-339/98-11 on 981220-990130.No Violations Noted.Major Areas Inspected:Operations, Maintenance,Engineering & Plant Support IR 05000338/19980101999-01-14014 January 1999 Insp Repts 50-338/98-10 & 50-339/98-10 on 981108-1219.No Violations Noted.Major Areas Inspected:Operations, Engineering,Maintenance & Plant Support ML20196H4131998-11-0505 November 1998 Insp Repts 50-338/98-05 & 50-339/98-05 on 980713-31 & 0921- 25.Violation Noted.Major Areas Inspected:Review of Licensee Calculations,Analysis,Performance Test Procedures & Other Engineering Documents Used to Support Design & Performance IR 05000338/19980071998-08-18018 August 1998 Insp Repts 50-338/98-07 & 50-339/98-07 on 980720-23.No Violations Noted.Major Areas Inspected:Observation & Evaluation of Biennial EP Exercise for North Anna Nuclear Station ML20216H6711998-04-0303 April 1998 Insp Repts 50-338/98-01,50-338/98-01 & 72-0016/98-01 on 980125-0307.No Violations Noted.Major Areas Inspected: Operations,Engineering,Maintenance & Plant Support IR 05000338/19970111998-01-12012 January 1998 Insp Repts 50-338/97-11,50-339/97-11 & 72-0016/97-04 on 971102-1213.No Violations Noted.Major Areas Inspected: Operations,Engineering,Maintenance & Plant Support IR 05000338/19970101997-10-0707 October 1997 Partially Withheld Insp Repts 50-338/97-10 & 50-339/97-10 on 970922-23 (Ref 10CFR73.21).No Violations Noted.Major Areas Inspected:Plant Support by Regional Safeguards Specalist IR 05000338/19970041997-07-21021 July 1997 Insp Repts 50-338/97-04 & 50-339/97-04 on 970518-0621.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000338/19970051997-07-15015 July 1997 Insp Repts 50-338/97-05 & 50-339/97-05 on 970616-20.No Violations Noted.Major Areas Inspected:Plant Support ML20140F2651997-06-0606 June 1997 Insp Repts 50-338/97-03 & 50-339/97-03 on 970406-0517. Non-cited Violation Noted.Major Areas Inspected:Operations, Engineering,Maintenance & Plant Support IR 05000338/19970021997-05-0505 May 1997 Insp Repts 50-338/97-02 & 50-339/97-02 on 970223-0405.Major Areas Inspected:Operations,Maint,Engineering & Plant Support ML20137F7661997-03-21021 March 1997 Insp Repts 50-338/97-01 & 50-339/97-01 on 970112-0222. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000338/19960131997-02-0707 February 1997 Insp Repts 50-338/96-13 & 50-339/96-13 on 961208-970111.No Violations Noted.Major Areas Inspected:Operations, Maintenance,Engineering & Plant Support ML20133J1991997-01-0606 January 1997 Insp Repts 50-338/96-12 & 50-339/96-12 on 961102-1207. Violations Noted.Major Areas Inspected:Operations,Maint & Engineering IR 05000338/19960101996-12-0202 December 1996 Insp Repts 50-338/96-10 & 50-339/96-10 on 960922-1102. Violations Noted.Major Areas Inspected:Licensee Operations, Engineering,Maint & Plant Support IR 05000338/19960111996-11-15015 November 1996 Insp Repts 50-338/96-11 & 50-339/96-11 on 961014-18.No Violations Noted.Major Areas Inspected:Plant Support ML20134G9071996-10-21021 October 1996 Insp Repts 50-338/96-09 & 50-339/96-09 on 960811-0921. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support ML20128K0591996-09-30030 September 1996 Insp Repts 50-338/96-08 & 50-339/96-08 on 960812-16.No Violations Noted.Major Areas Inspected:Cr Simulator,Tsc,Osc, EOF, & Joint Info Ctr IR 05000338/19960071996-09-0909 September 1996 Insp Repts 50-338/96-07 & 50-339/96-07 on 960810.Violations Noted.Major Areas Inspected:Licensee Operations,Engineers, Maint & Plant Support IR 05000338/19940291994-12-29029 December 1994 Partially Withheld Insp Repts 50-338/94-29 & 50-339/94-29 on 941128-1202 (Ref 10CFR73.21).No Violations or Deviations Noted.Major Areas Inspected:Physical Security Program for Power Reactors IR 05000338/19930291994-01-12012 January 1994 Insp Repts 50-338/93-29 & 50-339/93-29 on Stated Date.No Violations Noted.Major Areas Inspected:Plant Status,Ler Followup,Safety Verification,Maintenance Observation, Surveillance Observation & Cold Weather Preparations ML20059B2881993-12-14014 December 1993 Insp Repts 50-338/93-27 & 50-339/93-27 on 931017-1120. Violations Noted.Major Areas Inspected:Plant Status, Operational Safety Verification,Maintenance Observation & Surveillance Observation IR 05000338/19930241993-11-15015 November 1993 Insp Repts 50-338/93-24 & 50-339/93-24 on 930919-1016.No Violations Noted.Major Areas Inspected:Plant Status, Operational Safety Verification,Maintenance Observation, Surveillance Observation & LER Followup IR 05000338/19930281993-10-29029 October 1993 Insp Repts 50-338/93-28 & 50-339/93-28 on 931014-20. Violations Noted.Major Areas Inspected:Circumstances Surrounding Unit 2 High Head Safety Injection Subsystem Not Meeting TS Min Flow Requirement on 931014 IR 05000338/19930261993-10-27027 October 1993 Insp Repts 50-338/93-26 & 50-339/93-26 on 930927-1001.No Violations or Deviations Noted.Major Areas Inspected: Licensee Radiation Protection Program,Involving Review of HP Activities Primarily Associated W/Unit 2 Refueling Outage IR 05000338/19930211993-10-20020 October 1993 Insp Repts 50-338/93-21 & 50-339/93-21 on 930920-24.No Violations Noted.Major Areas Inspected:Organization of Chemistry Dept & Units Responsible for Handling & Shipping of Radioactive Matl & Plant Water Chemistry IR 05000338/19930231993-10-15015 October 1993 Insp Repts 50-338/93-23 & 50-339/93-23 on 930822-0918.No Violations Noted.Major Areas Inspected:Plant Status, Operational Verification,Maint Observation,Training & Action on Previous Insp Items IR 05000338/19930251993-10-13013 October 1993 Insp Repts 50-338/93-25 & 50-339/93-25 on 930914-17.No Violations Noted.Major Areas Inspected:Eddy Current Exam of Steam Generator Tubes IR 05000338/19930201993-09-17017 September 1993 Insp Repts 50-338/93-20 & 50-339/93-20 on 930718-0821.No Violations Noted.Major Areas Inspected:Plant Status, Operational Safety Verification,Maint Observation, Surveillance Observation & Action on Previous Insp Items ML20056E8651993-08-0404 August 1993 Insp Repts 50-338/93-19 & 50-339/93-19 on 930620-0717. Violations Noted.Major Areas Inspected:Operational Safety Verification,Maint Observation,Plant Status & Surveillance Observation ML20056D1671993-07-13013 July 1993 Insp Repts 50-338/93-18 & 50-339/93-18 on 930509-0619. Violations Noted.Major Areas Inspected:Examinations of Procedures & Representative Records,Interviews W/Personnel & Observaton of Activities in Progress IR 05000338/19930091993-03-24024 March 1993 Insp Repts 50-338/93-09 & 50-339/93-09 on 930208-12 & 22-55. No Violations Noted.Major Areas Inspected:Fitup,Preheat & Fabrication of Field Welds,Weld Repairs,Nde & Review of Fabrication Records IR 05000338/19930081993-03-15015 March 1993 Insp Repts 50-338/93-08 & 50-339/93-08 on 930117-0220. Violation Noted.Major Areas Inspected:Plant Status,License Event Rept & Surveillance Observation IR 05000338/19930011993-03-12012 March 1993 Insp Repts 50-338/93-01 & 50-339/93-01 on 930115-0211.Two Noncited Violations Identified.Major Areas Inspected:Program Organization & Mgt Controls,Hp Technician Training & Operational & Administrative Controls IR 05000338/19930061993-02-11011 February 1993 Partially Withheld Insp Repts 50-338/93-06 & 50-339/93-06 on 930125-29.No Violations Noted.Major Areas Inspected: Physical Security Program,Including Protected Vital Area Barriers.Portions Withheld (Ref 10CFR2.790) IR 05000338/19930051993-02-0505 February 1993 Insp Repts 50-338/93-05 & 50-339/93-05 on 930111-15.No Violations or Deviations Noted.Major Areas Inspected:Control of Heavy Loads in Containment & Crane Insps to Be Performed During SG Replacement Project IR 05000338/19930021993-02-0303 February 1993 Insp Repts 50-338/93-02 & 50-339/93-02 on 930104-08.No Violations Noted.Major Areas Inspected:Design Changes & Mod,Engineering Support Activities & Licensee Event Rept Followup IR 05000338/19920291993-01-13013 January 1993 Insp Repts 50-338/92-29 & 50-339/92-29 on 921122-1219.No Violations Noted.Major Areas Inspected:Operations,Maint, Minor Mods,Surveillances & Action on Previous Insp Findings IR 05000338/19920261992-12-31031 December 1992 Insp Repts 50-338/92-26 & 50-339/92-26 on 921130-1204.No Violations Noted.Major Areas Inspected:Organization & Staffing,Radiation Protection Training,Procedures & Work Controls ML20126E3431992-12-23023 December 1992 Insp Repts 50-338/92-30 & 50-339/92-30 on 921130-1204. Violations Noted.Major Areas Inspected:Mgt Support & Security Program Plans,Protected & Vital Area Barriers, Detection & Power Supply.Rept Partially Withheld IR 05000338/19920311992-12-17017 December 1992 Insp Repts 50-338/92-31 & 50-339/92-31 on 921207-10.No Violations or Deviations Noted.Major Areas Inspected: Emergency Operating Procedure & Abnormal Operating Procedure Followup IR 05000338/19920271992-12-16016 December 1992 Insp Repts 50-338/92-27 & 50-339/92-27 on 921116-20.No Violations or Deviations Noted.Major Areas Inspected:Primary Water Plant Chemistry,Confirmatory Measurements of non-radiological Samples & Radiological REMP IR 05000338/19920281992-12-15015 December 1992 Insp Repts 50-338/92-28 & 50-339/92-28 on 921116-20.No Violations or Deviations Noted.Major Areas Inspected:To Observe Certain Activities in Preparation for SG Replacement Project in Unit 1 & to Review Approved Welding Procedures IR 05000338/19920231992-12-11011 December 1992 Insp Repts 50-338/92-23 & 50-339/92-23 on 921018-1121.No Violations or Deviations Noted.Major Areas Inspected:Minor Mods,Operations,Maintenance,Surveillance,Esf Walkdown,Ler Followup & Actions on Previous Insp Findings IR 05000338/19920251992-11-25025 November 1992 Insp Repts 50-338/92-25 & 50-339/92-25 on 921102-06.No Violations Noted.Weaknesses Noted Re Heavy Loads Program. Major Areas inspected:post-refueling Startup Tests,Routine Surveillance of Core Performance & Control of Heavy Loads IR 05000280/19910221991-08-23023 August 1991 Insp Repts 50-280/91-22,50-281/91-22,50-338/91-18 & 50-339/91-18 on 910731 & 0801-02.No Violations Noted.Major Areas Inspected:Evaluation of Licensee Pipe Wall Thinning Insp & Replacement Program IR 05000338/19910041991-03-0606 March 1991 Insp Repts 50-338/91-04 & 50-339/91-04 on 910128-0201.Major Areas Inspected:Observation of Inservice Insp Work Activities & Reactive Issues Re Relief Request for Noncode Repair on Unit 2 IR 05000338/19900251990-11-19019 November 1990 Insp Repts 50-338/90-25 & 50-339/90-25 on 900916-1020. Noncited Violation Noted.Major Areas Inspected:Operations, Maint,Surveillance,Mods,Operational Event Followup,Midloop Operations,Ler Followup & Action on Previous Insp Items 1999-07-02
[Table view] Category:NRC-GENERATED
MONTHYEARIR 05000338/19990031999-07-0202 July 1999 Insp Repts 50-338/99-03 & 50-339/99-03 on 990425-0605.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000338/19990011999-04-12012 April 1999 Insp Repts 50-338/99-01 & 50-339/99-01 on 990131-0313. Violations Noted.Major Areas Inspected:Operations, Engineering,Maintenance & Plant Support.In Addition,Results of Insp by Region Based Fire Protection Specialist Encl IR 05000338/19980111999-03-0101 March 1999 Insp Repts 50-338/98-11 & 50-339/98-11 on 981220-990130.No Violations Noted.Major Areas Inspected:Operations, Maintenance,Engineering & Plant Support IR 05000338/19980101999-01-14014 January 1999 Insp Repts 50-338/98-10 & 50-339/98-10 on 981108-1219.No Violations Noted.Major Areas Inspected:Operations, Engineering,Maintenance & Plant Support ML20196H4131998-11-0505 November 1998 Insp Repts 50-338/98-05 & 50-339/98-05 on 980713-31 & 0921- 25.Violation Noted.Major Areas Inspected:Review of Licensee Calculations,Analysis,Performance Test Procedures & Other Engineering Documents Used to Support Design & Performance IR 05000338/19980071998-08-18018 August 1998 Insp Repts 50-338/98-07 & 50-339/98-07 on 980720-23.No Violations Noted.Major Areas Inspected:Observation & Evaluation of Biennial EP Exercise for North Anna Nuclear Station ML20216H6711998-04-0303 April 1998 Insp Repts 50-338/98-01,50-338/98-01 & 72-0016/98-01 on 980125-0307.No Violations Noted.Major Areas Inspected: Operations,Engineering,Maintenance & Plant Support IR 05000338/19970111998-01-12012 January 1998 Insp Repts 50-338/97-11,50-339/97-11 & 72-0016/97-04 on 971102-1213.No Violations Noted.Major Areas Inspected: Operations,Engineering,Maintenance & Plant Support IR 05000338/19970101997-10-0707 October 1997 Partially Withheld Insp Repts 50-338/97-10 & 50-339/97-10 on 970922-23 (Ref 10CFR73.21).No Violations Noted.Major Areas Inspected:Plant Support by Regional Safeguards Specalist IR 05000338/19970041997-07-21021 July 1997 Insp Repts 50-338/97-04 & 50-339/97-04 on 970518-0621.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000338/19970051997-07-15015 July 1997 Insp Repts 50-338/97-05 & 50-339/97-05 on 970616-20.No Violations Noted.Major Areas Inspected:Plant Support ML20140F2651997-06-0606 June 1997 Insp Repts 50-338/97-03 & 50-339/97-03 on 970406-0517. Non-cited Violation Noted.Major Areas Inspected:Operations, Engineering,Maintenance & Plant Support IR 05000338/19970021997-05-0505 May 1997 Insp Repts 50-338/97-02 & 50-339/97-02 on 970223-0405.Major Areas Inspected:Operations,Maint,Engineering & Plant Support ML20137F7661997-03-21021 March 1997 Insp Repts 50-338/97-01 & 50-339/97-01 on 970112-0222. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000338/19960131997-02-0707 February 1997 Insp Repts 50-338/96-13 & 50-339/96-13 on 961208-970111.No Violations Noted.Major Areas Inspected:Operations, Maintenance,Engineering & Plant Support ML20133J1991997-01-0606 January 1997 Insp Repts 50-338/96-12 & 50-339/96-12 on 961102-1207. Violations Noted.Major Areas Inspected:Operations,Maint & Engineering IR 05000338/19960101996-12-0202 December 1996 Insp Repts 50-338/96-10 & 50-339/96-10 on 960922-1102. Violations Noted.Major Areas Inspected:Licensee Operations, Engineering,Maint & Plant Support IR 05000338/19960111996-11-15015 November 1996 Insp Repts 50-338/96-11 & 50-339/96-11 on 961014-18.No Violations Noted.Major Areas Inspected:Plant Support ML20134G9071996-10-21021 October 1996 Insp Repts 50-338/96-09 & 50-339/96-09 on 960811-0921. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support ML20128K0591996-09-30030 September 1996 Insp Repts 50-338/96-08 & 50-339/96-08 on 960812-16.No Violations Noted.Major Areas Inspected:Cr Simulator,Tsc,Osc, EOF, & Joint Info Ctr IR 05000338/19960071996-09-0909 September 1996 Insp Repts 50-338/96-07 & 50-339/96-07 on 960810.Violations Noted.Major Areas Inspected:Licensee Operations,Engineers, Maint & Plant Support IR 05000338/19940291994-12-29029 December 1994 Partially Withheld Insp Repts 50-338/94-29 & 50-339/94-29 on 941128-1202 (Ref 10CFR73.21).No Violations or Deviations Noted.Major Areas Inspected:Physical Security Program for Power Reactors IR 05000338/19930291994-01-12012 January 1994 Insp Repts 50-338/93-29 & 50-339/93-29 on Stated Date.No Violations Noted.Major Areas Inspected:Plant Status,Ler Followup,Safety Verification,Maintenance Observation, Surveillance Observation & Cold Weather Preparations ML20059B2881993-12-14014 December 1993 Insp Repts 50-338/93-27 & 50-339/93-27 on 931017-1120. Violations Noted.Major Areas Inspected:Plant Status, Operational Safety Verification,Maintenance Observation & Surveillance Observation IR 05000338/19930241993-11-15015 November 1993 Insp Repts 50-338/93-24 & 50-339/93-24 on 930919-1016.No Violations Noted.Major Areas Inspected:Plant Status, Operational Safety Verification,Maintenance Observation, Surveillance Observation & LER Followup IR 05000338/19930281993-10-29029 October 1993 Insp Repts 50-338/93-28 & 50-339/93-28 on 931014-20. Violations Noted.Major Areas Inspected:Circumstances Surrounding Unit 2 High Head Safety Injection Subsystem Not Meeting TS Min Flow Requirement on 931014 IR 05000338/19930261993-10-27027 October 1993 Insp Repts 50-338/93-26 & 50-339/93-26 on 930927-1001.No Violations or Deviations Noted.Major Areas Inspected: Licensee Radiation Protection Program,Involving Review of HP Activities Primarily Associated W/Unit 2 Refueling Outage IR 05000338/19930211993-10-20020 October 1993 Insp Repts 50-338/93-21 & 50-339/93-21 on 930920-24.No Violations Noted.Major Areas Inspected:Organization of Chemistry Dept & Units Responsible for Handling & Shipping of Radioactive Matl & Plant Water Chemistry IR 05000338/19930231993-10-15015 October 1993 Insp Repts 50-338/93-23 & 50-339/93-23 on 930822-0918.No Violations Noted.Major Areas Inspected:Plant Status, Operational Verification,Maint Observation,Training & Action on Previous Insp Items IR 05000338/19930251993-10-13013 October 1993 Insp Repts 50-338/93-25 & 50-339/93-25 on 930914-17.No Violations Noted.Major Areas Inspected:Eddy Current Exam of Steam Generator Tubes IR 05000338/19930201993-09-17017 September 1993 Insp Repts 50-338/93-20 & 50-339/93-20 on 930718-0821.No Violations Noted.Major Areas Inspected:Plant Status, Operational Safety Verification,Maint Observation, Surveillance Observation & Action on Previous Insp Items ML20056E8651993-08-0404 August 1993 Insp Repts 50-338/93-19 & 50-339/93-19 on 930620-0717. Violations Noted.Major Areas Inspected:Operational Safety Verification,Maint Observation,Plant Status & Surveillance Observation ML20056D1671993-07-13013 July 1993 Insp Repts 50-338/93-18 & 50-339/93-18 on 930509-0619. Violations Noted.Major Areas Inspected:Examinations of Procedures & Representative Records,Interviews W/Personnel & Observaton of Activities in Progress IR 05000338/19930091993-03-24024 March 1993 Insp Repts 50-338/93-09 & 50-339/93-09 on 930208-12 & 22-55. No Violations Noted.Major Areas Inspected:Fitup,Preheat & Fabrication of Field Welds,Weld Repairs,Nde & Review of Fabrication Records IR 05000338/19930081993-03-15015 March 1993 Insp Repts 50-338/93-08 & 50-339/93-08 on 930117-0220. Violation Noted.Major Areas Inspected:Plant Status,License Event Rept & Surveillance Observation IR 05000338/19930011993-03-12012 March 1993 Insp Repts 50-338/93-01 & 50-339/93-01 on 930115-0211.Two Noncited Violations Identified.Major Areas Inspected:Program Organization & Mgt Controls,Hp Technician Training & Operational & Administrative Controls IR 05000338/19930061993-02-11011 February 1993 Partially Withheld Insp Repts 50-338/93-06 & 50-339/93-06 on 930125-29.No Violations Noted.Major Areas Inspected: Physical Security Program,Including Protected Vital Area Barriers.Portions Withheld (Ref 10CFR2.790) IR 05000338/19930051993-02-0505 February 1993 Insp Repts 50-338/93-05 & 50-339/93-05 on 930111-15.No Violations or Deviations Noted.Major Areas Inspected:Control of Heavy Loads in Containment & Crane Insps to Be Performed During SG Replacement Project IR 05000338/19930021993-02-0303 February 1993 Insp Repts 50-338/93-02 & 50-339/93-02 on 930104-08.No Violations Noted.Major Areas Inspected:Design Changes & Mod,Engineering Support Activities & Licensee Event Rept Followup IR 05000338/19920291993-01-13013 January 1993 Insp Repts 50-338/92-29 & 50-339/92-29 on 921122-1219.No Violations Noted.Major Areas Inspected:Operations,Maint, Minor Mods,Surveillances & Action on Previous Insp Findings IR 05000338/19920261992-12-31031 December 1992 Insp Repts 50-338/92-26 & 50-339/92-26 on 921130-1204.No Violations Noted.Major Areas Inspected:Organization & Staffing,Radiation Protection Training,Procedures & Work Controls ML20126E3431992-12-23023 December 1992 Insp Repts 50-338/92-30 & 50-339/92-30 on 921130-1204. Violations Noted.Major Areas Inspected:Mgt Support & Security Program Plans,Protected & Vital Area Barriers, Detection & Power Supply.Rept Partially Withheld IR 05000338/19920311992-12-17017 December 1992 Insp Repts 50-338/92-31 & 50-339/92-31 on 921207-10.No Violations or Deviations Noted.Major Areas Inspected: Emergency Operating Procedure & Abnormal Operating Procedure Followup IR 05000338/19920271992-12-16016 December 1992 Insp Repts 50-338/92-27 & 50-339/92-27 on 921116-20.No Violations or Deviations Noted.Major Areas Inspected:Primary Water Plant Chemistry,Confirmatory Measurements of non-radiological Samples & Radiological REMP IR 05000338/19920281992-12-15015 December 1992 Insp Repts 50-338/92-28 & 50-339/92-28 on 921116-20.No Violations or Deviations Noted.Major Areas Inspected:To Observe Certain Activities in Preparation for SG Replacement Project in Unit 1 & to Review Approved Welding Procedures IR 05000338/19920231992-12-11011 December 1992 Insp Repts 50-338/92-23 & 50-339/92-23 on 921018-1121.No Violations or Deviations Noted.Major Areas Inspected:Minor Mods,Operations,Maintenance,Surveillance,Esf Walkdown,Ler Followup & Actions on Previous Insp Findings IR 05000338/19920251992-11-25025 November 1992 Insp Repts 50-338/92-25 & 50-339/92-25 on 921102-06.No Violations Noted.Weaknesses Noted Re Heavy Loads Program. Major Areas inspected:post-refueling Startup Tests,Routine Surveillance of Core Performance & Control of Heavy Loads IR 05000280/19910221991-08-23023 August 1991 Insp Repts 50-280/91-22,50-281/91-22,50-338/91-18 & 50-339/91-18 on 910731 & 0801-02.No Violations Noted.Major Areas Inspected:Evaluation of Licensee Pipe Wall Thinning Insp & Replacement Program IR 05000338/19910041991-03-0606 March 1991 Insp Repts 50-338/91-04 & 50-339/91-04 on 910128-0201.Major Areas Inspected:Observation of Inservice Insp Work Activities & Reactive Issues Re Relief Request for Noncode Repair on Unit 2 IR 05000338/19900251990-11-19019 November 1990 Insp Repts 50-338/90-25 & 50-339/90-25 on 900916-1020. Noncited Violation Noted.Major Areas Inspected:Operations, Maint,Surveillance,Mods,Operational Event Followup,Midloop Operations,Ler Followup & Action on Previous Insp Items 1999-07-02
[Table view] Category:TEXT-INSPECTION & AUDIT & I&E CIRCULARS
MONTHYEARIR 05000338/19990031999-07-0202 July 1999 Insp Repts 50-338/99-03 & 50-339/99-03 on 990425-0605.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000338/19990011999-04-12012 April 1999 Insp Repts 50-338/99-01 & 50-339/99-01 on 990131-0313. Violations Noted.Major Areas Inspected:Operations, Engineering,Maintenance & Plant Support.In Addition,Results of Insp by Region Based Fire Protection Specialist Encl IR 05000338/19980111999-03-0101 March 1999 Insp Repts 50-338/98-11 & 50-339/98-11 on 981220-990130.No Violations Noted.Major Areas Inspected:Operations, Maintenance,Engineering & Plant Support IR 05000338/19980101999-01-14014 January 1999 Insp Repts 50-338/98-10 & 50-339/98-10 on 981108-1219.No Violations Noted.Major Areas Inspected:Operations, Engineering,Maintenance & Plant Support ML20196H4081998-11-0505 November 1998 Notice of Violation from Insp on 980713-31 & 0921-25. Violation Noted:As of 980712,AFW Pipe Supports Were Not Constructed IAW Details Shown on Design Drawings as Listed ML20196H4131998-11-0505 November 1998 Insp Repts 50-338/98-05 & 50-339/98-05 on 980713-31 & 0921- 25.Violation Noted.Major Areas Inspected:Review of Licensee Calculations,Analysis,Performance Test Procedures & Other Engineering Documents Used to Support Design & Performance ML20155B0671998-10-0202 October 1998 NRC Operator Licensing Exam Repts 50-338/98-301 & 50-339/98-301 (Including Completed & Graded Tests) for Tests Administered on 980817-21 & 31-0903 IR 05000338/19980071998-08-18018 August 1998 Insp Repts 50-338/98-07 & 50-339/98-07 on 980720-23.No Violations Noted.Major Areas Inspected:Observation & Evaluation of Biennial EP Exercise for North Anna Nuclear Station ML20216H6711998-04-0303 April 1998 Insp Repts 50-338/98-01,50-338/98-01 & 72-0016/98-01 on 980125-0307.No Violations Noted.Major Areas Inspected: Operations,Engineering,Maintenance & Plant Support IR 05000338/19970111998-01-12012 January 1998 Insp Repts 50-338/97-11,50-339/97-11 & 72-0016/97-04 on 971102-1213.No Violations Noted.Major Areas Inspected: Operations,Engineering,Maintenance & Plant Support IR 05000338/19970101997-10-0707 October 1997 Partially Withheld Insp Repts 50-338/97-10 & 50-339/97-10 on 970922-23 (Ref 10CFR73.21).No Violations Noted.Major Areas Inspected:Plant Support by Regional Safeguards Specalist IR 05000338/19970041997-07-21021 July 1997 Insp Repts 50-338/97-04 & 50-339/97-04 on 970518-0621.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000338/19970051997-07-15015 July 1997 Insp Repts 50-338/97-05 & 50-339/97-05 on 970616-20.No Violations Noted.Major Areas Inspected:Plant Support ML20140F2651997-06-0606 June 1997 Insp Repts 50-338/97-03 & 50-339/97-03 on 970406-0517. Non-cited Violation Noted.Major Areas Inspected:Operations, Engineering,Maintenance & Plant Support ML20148B6541997-05-0505 May 1997 Notice of Violation from Insp on 970223-0405.Violation Noted:Operators Failed to Verify That Unit 1 & 2 RCPs 1 Seal Leakoffs & Unit 2 Nr 46 Nuclear Power Range Chart Recorders Were Operational IR 05000338/19970021997-05-0505 May 1997 Insp Repts 50-338/97-02 & 50-339/97-02 on 970223-0405.Major Areas Inspected:Operations,Maint,Engineering & Plant Support ML20137F7411997-03-21021 March 1997 Notice of Violation from Insp on 970112-0222.Violation Noted:As of 970213,radiation Monitors Installed in Fuel Handling & Storage Locations,Did Not Provide Full Coverage for Area Used for New Fuel Receipt ML20137F7661997-03-21021 March 1997 Insp Repts 50-338/97-01 & 50-339/97-01 on 970112-0222. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000338/19970991997-02-21021 February 1997 SALP Repts 50-338/97-99 & 50-339/97-99 for 941225-970111 IR 05000338/19960131997-02-0707 February 1997 Insp Repts 50-338/96-13 & 50-339/96-13 on 961208-970111.No Violations Noted.Major Areas Inspected:Operations, Maintenance,Engineering & Plant Support ML20133J1991997-01-0606 January 1997 Insp Repts 50-338/96-12 & 50-339/96-12 on 961102-1207. Violations Noted.Major Areas Inspected:Operations,Maint & Engineering ML20133G8881997-01-0606 January 1997 Notice of Violation from Insp on 961103-1207.Violation Noted:Licensee Failed to Ensure That Safeguards Area Walls Met Design Basis for Containing Pump Seal Leakage Described in Updated Final Safety Analysis Rept Section 15.4.1.8 ML20133C9491996-12-27027 December 1996 EN-96-098:order Prohibiting Involvement in NRC Licensed Activities Will Be Issued on or About 970102 to Unlicensed Individual Formerly Employed as Contract Millwright.State of VA Will Be Notified ML20149M5831996-12-0202 December 1996 Notice of Violation from Insp on 960922-1102.Violation Noted:Rce Had Not Been Completed for Several Pump 1-CH-P-1A Seal Failures Which Occurred Between 960211 & 0718 IR 05000338/19960101996-12-0202 December 1996 Insp Repts 50-338/96-10 & 50-339/96-10 on 960922-1102. Violations Noted.Major Areas Inspected:Licensee Operations, Engineering,Maint & Plant Support IR 05000338/19960111996-11-15015 November 1996 Insp Repts 50-338/96-11 & 50-339/96-11 on 961014-18.No Violations Noted.Major Areas Inspected:Plant Support PNO-II-96-081, on 961112,Unit 2 Experienced Turbine Generator Trip from 100% Power.Investigation Into Cause of Turbine Generator Trip Revealed Ground Fault on Main Generator Stator Phase a Windings.Addl Followup Will Be Performed1996-11-13013 November 1996 PNO-II-96-081:on 961112,Unit 2 Experienced Turbine Generator Trip from 100% Power.Investigation Into Cause of Turbine Generator Trip Revealed Ground Fault on Main Generator Stator Phase a Windings.Addl Followup Will Be Performed ML20134G7971996-10-21021 October 1996 Notice of Violation from Insp on 960811-0921.Violation Noted:Procedure for Irradiated Fuel Damage While Refueling, 0-AP-30 Inadequate ML20134G9071996-10-21021 October 1996 Insp Repts 50-338/96-09 & 50-339/96-09 on 960811-0921. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support ML20128K0591996-09-30030 September 1996 Insp Repts 50-338/96-08 & 50-339/96-08 on 960812-16.No Violations Noted.Major Areas Inspected:Cr Simulator,Tsc,Osc, EOF, & Joint Info Ctr ML20134C6401996-09-0909 September 1996 Notice of Violation from Insp on 960810.Violation Noted: on 940802,inadequate Maint Procedure Was Used to Control Maint Activities Affecting Quality IR 05000338/19960071996-09-0909 September 1996 Insp Repts 50-338/96-07 & 50-339/96-07 on 960810.Violations Noted.Major Areas Inspected:Licensee Operations,Engineers, Maint & Plant Support IR 05000338/19940291994-12-29029 December 1994 Partially Withheld Insp Repts 50-338/94-29 & 50-339/94-29 on 941128-1202 (Ref 10CFR73.21).No Violations or Deviations Noted.Major Areas Inspected:Physical Security Program for Power Reactors IR 05000338/19930291994-01-12012 January 1994 Insp Repts 50-338/93-29 & 50-339/93-29 on Stated Date.No Violations Noted.Major Areas Inspected:Plant Status,Ler Followup,Safety Verification,Maintenance Observation, Surveillance Observation & Cold Weather Preparations ML20059L0511994-01-0404 January 1994 EN-94-001:on 940107,notice of Violation & Proposed Imposition of Civil Penalty in Amount of $15,000 Will Be Issued.Action Based on Two Previous Similar Severity Level IV Violations Issued on 901207 & 920515 ML20059B2521993-12-14014 December 1993 Corrected NOV from Insp on 931017-1120,including Response Instruction ML20059B2881993-12-14014 December 1993 Insp Repts 50-338/93-27 & 50-339/93-27 on 931017-1120. Violations Noted.Major Areas Inspected:Plant Status, Operational Safety Verification,Maintenance Observation & Surveillance Observation ML20059B2751993-12-14014 December 1993 Notice of Violation from Insp on 931017-1120.Violation Noted:On 931029,periodic Test Procedure 2-PT-82H Was Not Implemented Correctly & While Performing Step 6.4.5,operator Incorrectly Placed Control Switch Breaker in pull-to-lock IR 05000338/19930241993-11-15015 November 1993 Insp Repts 50-338/93-24 & 50-339/93-24 on 930919-1016.No Violations Noted.Major Areas Inspected:Plant Status, Operational Safety Verification,Maintenance Observation, Surveillance Observation & LER Followup IR 05000338/19933011993-11-12012 November 1993 Exam Rept 50-338/93-301 on 931008-15.Exam Results:Eight ROs & Six SROs Passed Written & Operating Exams.Exam for Both Units IR 05000338/19930281993-10-29029 October 1993 Insp Repts 50-338/93-28 & 50-339/93-28 on 931014-20. Violations Noted.Major Areas Inspected:Circumstances Surrounding Unit 2 High Head Safety Injection Subsystem Not Meeting TS Min Flow Requirement on 931014 IR 05000338/19930261993-10-27027 October 1993 Insp Repts 50-338/93-26 & 50-339/93-26 on 930927-1001.No Violations or Deviations Noted.Major Areas Inspected: Licensee Radiation Protection Program,Involving Review of HP Activities Primarily Associated W/Unit 2 Refueling Outage IR 05000338/19933001993-10-20020 October 1993 Exam Repts 50-338/93-300 & 50-339/93-300 on 930825-0910 & 930921-24.Exam Results:Six SROs & Five ROs Received Written & Operating Exams.All Operators Passed Exams IR 05000338/19930211993-10-20020 October 1993 Insp Repts 50-338/93-21 & 50-339/93-21 on 930920-24.No Violations Noted.Major Areas Inspected:Organization of Chemistry Dept & Units Responsible for Handling & Shipping of Radioactive Matl & Plant Water Chemistry IR 05000338/19930231993-10-15015 October 1993 Insp Repts 50-338/93-23 & 50-339/93-23 on 930822-0918.No Violations Noted.Major Areas Inspected:Plant Status, Operational Verification,Maint Observation,Training & Action on Previous Insp Items IR 05000338/19930251993-10-13013 October 1993 Insp Repts 50-338/93-25 & 50-339/93-25 on 930914-17.No Violations Noted.Major Areas Inspected:Eddy Current Exam of Steam Generator Tubes IR 05000338/19930201993-09-17017 September 1993 Insp Repts 50-338/93-20 & 50-339/93-20 on 930718-0821.No Violations Noted.Major Areas Inspected:Plant Status, Operational Safety Verification,Maint Observation, Surveillance Observation & Action on Previous Insp Items ML20056E8521993-08-0505 August 1993 Notice of Violation from Insp on 930620-0717.Violation Noted:Operating Procedure 1-OP-6.5.A Not Implemented Properly,In That While Performing Step 5.3.4.e,operator Failed to Fully Open EDG Exhaust Muffler Bypass Valve ML20056E8651993-08-0404 August 1993 Insp Repts 50-338/93-19 & 50-339/93-19 on 930620-0717. Violations Noted.Major Areas Inspected:Operational Safety Verification,Maint Observation,Plant Status & Surveillance Observation ML20056D1581993-07-13013 July 1993 Notice of Violation from Insp on 930509-0619.Violation Noted:Hydrogen Analyzer Determined to Be Inoperable from 930209 to 0509 W/O Implementing Requirements of Action Statement 1999-07-02
[Table view] |
See also: IR 05000338/1993027
Text
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UNITED STATES
- go are%
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NUCLEAR REGULATORY COMMISSION
REGloN 11
- g 101 MARIETTA STREET, N.W., SUITE 2300
7, ;j ATLANTA, GEORGIA 3032M199
\, +..../
Report Nos.: 50-338/93-27 and 50-339/93-27
Licensee: Virginia Electric & Power Company
5000 Dominion Boulevard
Glen Allen, VA 23060
Docket Nos.: 50-338 and 50-339
License Nos.: NPF-4 and NPF-7
Facility Name: North Anna 1 and 2
Inspection Conducted: October 17 - November 20, 1993
Inspectors: #itt ) sS%% Gu /2 - / y- P 3
R. D. McWhorter, Senior Resident Inspector Date Signed
J- tv 2L n /L / L-fy- 73
D. R. Taylor, Resident Inspector Date Signed
Approved by: / /
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D. . .c K lLf/ '// h
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G. A. 'Belisle, Sebthn Chief Date Signed
Division of Reactor Projectc
SUMMARY
Scope:
This routine resident inspection was conducted on site in the areas of plant
status, operational safety verification, maintenance observation, surveillance
cbservation, engineered safety feature system walkdown, licensee event report
followup, and action on previous inspection items. Inspections of licensee
backshift activities were conducted on October 17, 23 and 26, and November 5,
8 and 18, 1993.
Results:
Doerations functional area
A violation was identified for a failure to correctly implement a periodic
test procedure which led to disabling Emergency Diesel Generator 2H for
approximately six hours (paragraph 3.c).
Removing and storing the loose fuel material identified during the Unit 2
refueling outage was well planned and controlled (paragraph 3.d).
9401040071 931214
PDR ADDCK 05000338
G PDR
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Enaineerina functional area
An-Inspector follow-up Item was identified concerning the determination of a
proper venting interval to ensure that the Low Head Safety Injection system
initiates without excessive pressure surges (paragraph 8.a).
On November 8, as a result of continued evaluations into the cause of High
Head Safety Injection flow balance test problems, all charging pumps were
determined to be inoperable (paragraph 5.a). Enforcement discretion was
granted to allow the licensee 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for corrective action.
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REPORT DETAILS
1. Persons Contacted
Licensee Employees
L. Edmonds, Superintendent, Nuclear Training r
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R. Enfinger, Assistant Station Manager, Operations and Maintenance '
G. Gordon, Acting Superintendent, Maintenance
J. Hayes, Superintendent of Operations
D. Heacock, Superintendent, Station Engineering '
- P. Kemp, Supervisor, Licensing ,
- W. Matthews, Acting Assistant Station Manager, Operations and ;
'
Maintenance
J. O'Hanlon, Vice President, Nuclear Operations
D. Roberts, Supervisor, Station Nuclear Safety
R. Saunders, Assistant Vice President, Nuclear Operations
D. Schappell, Superintendent, Site Services
R. Shears, Superintendent, Outage and Planning
- J. Smith, Manager, Quality Assurance
A. Stafford, Superintendent, Radiological Protection
J. Stall, Assistant Station Manager, Nuclear Safety and Licensing
t
Other licensee employees contacted included engineers, technicians,
operators, mechanics, security force members, and office personnel.
NRC Personnel (
- R. McWhorter, Senior Resident Inspector
- D. Taylor, Resident Inspector ,
Acronyms and initialisms used throughout this report are listed in the
last paragraph.
2. Plant Status
Unit 1 operated the entire inspection period at or near 100% power. :
Unit 2 began the inspection period in MODE 5 recovering from a refueling !
outage. On October 24, the unit entered MODE 4, followed by MODE 3 i
entry on October 25. A reactor startup was performed following MODE 2
entry on October 26. The unit entered MODE 1 on October 27, reaching ..
approximately 100% power on October 31. The unit continued at or near -
100% power for the remainder of the inspection period. :
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3. Operational Safety Verification (71707)
The inspectors conducted frequent control room tours to verify proper _ '!
staffing, operator attentiveness, and adherence to approved-procedures. *
The. inspectors attended daily plant status meetings to maintain
awareness of overall facility operations and reviewed operator logs to j
verify operational safety and compliance with TS. Instrumentation and t
safety system lineups were periodically reviewed from control room
indications to assess operability. Frequent plant tours were conducted :
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to observe equipment status, fire protection program implementation,.
radiological work practices, plant security, and housekeeping. DRs were
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reviewed to assure that potential safety concerns were properly reported- ;
and resolved. :
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a. Outage Commitments .
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The inspectors reviewed several licensee outage commitments to
ascertain that actions were completed. The inspectors verified- I
the outage commitment status by reviewing documentation, direct- )
inspection of selected plant areas, and discussions with cognizant
licensee personnel. Activities reviewed by inspectors included: ,
- Testing of manual SI input to reactor trip circuits
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Inspection of FW rupture restraints _
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- Ultrasonic inspection of Unit 2 ASME XI piping as a result
of a temporary non-code repair on Unit 1 .
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Inspection of Unit 2 containment personnel hatch 1
- Fire barrier penetration inspection and repairs. !
- ISI exam on 2-SI-153 bolting l
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Seismic . qualification walkdowns. ;
The inspectors noted that outage commitments were accurately- <
tracked and reported to station management on a weekly basis. .i
Based on the licensee successfully completing the above i
activities, the inspectors concluded that outage commitments made ;
to the NRC were being fulfilled. ;
b. ' Unit 2 Startup J
On October 26, 1993, the inspectors observed a reactor and turbine j
ctartup per 2-0P-1.5', Unit Startup from MODE 3 to MODE 2, revision
39; 2-0P-2.1, Unit Startup from MODE 2 to MODE 1,irevision 50; and: 1
2-0P-15.1, Operation of the Main Turbine, revision 24. The j
startup was performed with very few equipment problems and was - t
well controlled by the' operators. .One example of. an equipment j
problem occurred when during the-rod pull sequence, Bank C Rod- ,
H-100-failed to move. In response, the CR0 fully-inserted bank C J
as required by procedure 2-0P-1.5. Subsequent troubleshooting- l
identified the problem to be a blown. fuse. After the fuse was
replaced, the startup proceeded and no further problems were 1
observed. The inspectors noted extensive management oversight for ,
the reactor startup and placing the unit on line. ;
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c. Emergency Diesel Generator 2H Inoperability
On October 29, 1993, at 07:55 a.m., the Supervisor of Shift
Operations identified that the control switch for the EDG output
breaker, breaker number 25H2, was in the " pull-to-lock" position.
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With the switch in this position, EDG 2H was prevented from
automatically loading onto its emergency bus. The condition was
immediately corrected by placing the switch in the neutral
position. Subsequent reviews by the licensee indicated that the
switch was incorrectly put in the " pull-to-lock" position earlier
that morning by an operator while performing 2-PT-82H, 2H
Emergency Diesel Generator Slow Start Test, revision 14. The
procedure required the operator to open breaker 25H2. The
operator put the breaker switch in " pull-to-lock," which was not
called for by the procedure. This failure to properly follow
procedure 2-PT-82H by incorrectly positioning the control switch
for breaker 25H2 is identified as Violation 50-339/93-27-01:
Failure to Follow Procedure 2-PT-82H.
The inspectors reviewed the SR0 and CR0 logs to verify compliance
with TS action statement time limits and to identify if opposite
train equipment was out-of-servi _e. The.EDG was taken out of
service at 9:28 p.m., on October 28, while performing 2-PT-82H.
At 1:20 a.m., on October 29, following the apparent successful
completion of the PT, the EDG was declared operable. At 7:55
a.m., the error was discovered and the switch was placed in
neutral. The total time the EDG was inoperable was approximately
6.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />. The inspectors determined that no opposite train
equipment was out of service during this period of EDG 1
inoperability; consequently, TS action statement time limits were l
met.
The inspectors reviewed compliance with TS action statement
3.8.1.i.b. The action statement allows one EDG to be out of
service for up to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> provided that the operability of the AC
off-site power sources be demonstrated by performing surveillance
requirement 4.8.1.1.1.a within one hour and at least once per 8 )
hours thereafter. The inspectors concluded that the 72-hour time l
limit had not been exceeded,-but questioned the completion of the l
associated surveillance requirement. A review of logs indicated ,
that the licensee used 2-PT-80, AC Sources Operability l
Verification, revision 8, to meet the surveillance requirement at
9:28 p.m., and again at 8:30 a.m. Although 2-PT-80 was not
formally completed, the licensee stated that operator observations
and logs verified that equivalent actions were taken at least once
during the period between 1:00 a.m. and 2:00 a.m. The inspectors i
reviewed the licensee's findings and found that the equivalent
actions had been documented to meet the 8-hour TS surveillance .
requirement.
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The inspectors evaluated the potential impact on plant safety for
this event, since the EDG was prevented from automatically
performing its safety function. The inspectors concluded that the
safety significance of the event was minor because no opposite
train equipment was inoperable, and the amount of time the EDG was
in this condition was minimal. In addition, the E0Ps require the
operators to check EDG operations early during a transient, which
would allow for the quick detection and correction of this
condition.
It was also noted that the improper switch position should have '
been identified during walkdowns for the 7:00 a.m. shift turnover.
As a result, the licensee modified the shift turnover checklist to
add the switch to formal turnover checks. The inspectors noted
that good oversight by plant supervision was responsible for the
prompt discovery of the condition.
It was found
'
The inspectors also reviewed 2-PT-82H for adequacy.
that after unloading the EDG, step 6.4.5 required the operator to
"Open breaker 25H2." It was while performing this step that the
operator put the breaker handswitch in the " pull-to-lock"
position. The inspectors noted the switch did not have an "open"
position, but rather had: " pull-to-lock," " trip," neutral ~
(unlabeled) and "close." The licensee's corrective actions
included proceduni changes to clarify the desired breaker
position. Additionally, the inspectors noted that the procedure
did not contain incependent verification requirements for control
room switch alignments following the test. Concern was expressed
to the licensee about the lack of independent verifications in the
procedure. The licensee's investigations revealed that procedure
writers did not routinely place independent verification
requirements in procedures for switches which spring return to the
desired position. The licensee informed the inspectors that, as'a
result of the incident, they were commencing a procedure review to
identify similar steps and add verification requirements where
appropriate.
d. Removal of Fuel Pellets from Transfer Canal ;
On Nc; ember 18, 1993, the inspectors reviewed the licensee's ,
actions for the recovering fuel material from the Unit 2 transfer i
canal. The material was found while moving fuel during the fall
1993 refueling outage. The inspectors observed the pre-job brief
and reviewed the videotaped results of the recovery and
radiological surveys. The recovery was performed using temporary
procedure 0-T0P-4.26, Removal of Y-48 Debris From the Unit 2 -
Transfer Canal in the fuel Building, revision 0. The procedure, '
radiological requirements, and precautions were thoroughly
reviewed during the pre-job brief. The procedure involved using a :
heavy bristle brush attached to a pole to sweep the fuel into a
stainless steel debris container. The container was then placed
into an unusable fuel storage location. The procedure also-
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5
required practice runs in the new fuel storage area and in the
Unit I transfer canal. Overall, the inspectors considered the
recovery process well planned and concluded that the licensee's
actions had oeen successful in safely storing the loose material
in the spent fuel pool.
e. Licensee NRC Notifications ,
(1) On November 2, 1993, the licensee informed the NRC, as
required by 10 CFR 50.72, concerning notifying off-site
authorities. Specifically, the licensee notified the
Commonwealth of Virginia of chromate discharges into Lake
Anna from a CCW leak. The inspectors reviewed this
notification and verified that there was no regulatory
concern associated with the event.
(2) On November 9, 1993, the licensee informed the NRC, as
required by.10 CFR 50.72, concerning notifying off-site
authorities. Specifically, the licensee notified the
Federal Energy Regulatory Commission of a Lake Anna Dam
emergency diesel generator failure. The inspectors reviewed ,
this notification and verified that there was no regulatory
concern associated with the event.
(3) On November 17, 1993, the licensee informed the NRC, as
required by 10 CFR 50.72, concerning notifying off-site
authorities. Specifically, the licensee notified the
Commonwealth of Virginia of the transport off-site of a
non-contaminated individual requiring medical attention.
The inspectors reviewed this notification and verified that
there was no regulatory concern associated with the event.
One violation was identified.
4. Maintenance Observation (62703)
Station maintenance activities were observed and reviewed to verify that
the activities were conducted in accordance with TS, procedures,
regulatory guides, and industry codes or standards.
a. Leak Sealant Repair ,
On November 1,1993, the inspectors observed leak sealant repair
on the pivot pin bearing cap to valve 2-FW-62, the main feedwater
to A SG inlet check valve, which also serves as a containment
isolation valve. The mechanical joint developed a 3 gpm estimated
leak during power ascen:, ion. The on-line leak repair was
performed using WO 274747 and procedure 0-MCM-1904-01, On-Line
Repair Using Contractor Leak Sealant Methods, revision 0. The
procedure was issued October 22, 1993, and replaced three )
procedures previously used for leak sealant repairs.
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The SNSOC-approved procedure provided 19 methods for leak repair
which were dependent on the specific application.
The inspectors observed the leak repair from the MSVH and reviewed
the completed work package. The inspector noted that although not
required by procedure, SNSOC requested the work package be
presented for review prior to injection of the valve. The valve
was injected using section 6.7, New Injection of a Flange With
Clamp. The inspectors judged that the maintenance was well
controlled with sufficient management oversight.
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No violations or deviations were identified. l
5. Surveillance Observation (61726)
Station surveillance testing activities were observed and reviewed to
verify that testing was performed in accordance with procedures, test
instrumentation was calibrated, LCOs were met, and any deficiencies -
identified were properly reviewed and resolved.
a. HHSI Flow Balance Test .
Near the end of the previous inspection period, the inspectors
observed licensee personnel performing 2-PT-138.1, HHSI Flow
Balance, revision 1-P2. The. purpose of the test was to verify
that ECCS flow met TS 4.5.2.h requirements. During the initial
run for the cold leg verification, branch line flows did not meet
TS requirements. This failure was the subject of NRC Inspection
Report Nos. 50-338, 339/93-28. ;
Inspectors monitored the licensee's corrective actions on this
issue in preparation for Unit 2 entry into MODE 4. The inspectors
met with system engineers on October 18 to discuss probable causes
for the repeated problems in HHSI flow balances. The valves which
control HHSI flow (2-SI-89, -97, and -103) were identified to be
Rockwell-Edwards " univalves," which were the subject of NRC
IN 84-48 (with Supplement 1). The IN detailed problems with
valves similar to this design in the areas of stem breakage and r
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disc separation. As a result of these issues, the licensee
performed radiographs of all three valves on October 20. The
radiographs revealed that the internal components of the valves
appeared to be intact.
On October 21, 1993, a conference call was held between the
licensee and the NRC to discuss the HHSI test failure. The
licensee stated that the most probable cause for test failure
continued to be valve stem movement. In addition to actions taken
in the past to prevent valve movement, the licensee installed a
thread locking compound on the valve stem to prevent movement due
to vibration or other means. The licensee also presented safety
analysis results for out-of-specification HHSI flow balances. The
resuits demonstrated that the margin to exceeding transient PCT-
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limits was adequate for flow imbalances up to 30..gpm below the TS
limit. The largest flow imbalance measured was approximately 3
gpm below the TS limit.
On November 8, 1993, continued licensee's investigations into the
cause for the HHSI test failure identified that the "Controlotron"
flow instruments used for the test may have contained excessive
errors. .The licensee performed' extensive testing concerning the-
effects of pipe configuration on the accuracy.of the instruments _ <
and concluded that the. Unit 2 piping arrangements may have led to ,
as much as ten percent error in measured flow. This inaccuracy
was analyzed, and the licensee concluded that performance could be: ,
assured within the system design basis, i
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However, due to the potential measurement errors, the licensee.
could no longer demonstrate that the TS 4.5.2.h requirements'had
been met. As a result, the licensee declared all three HHSI pumps
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inoperable, entered TS 3.0.3 at 2:45 p.m... on November 8, and
requested enforcement discretion. The enforcement discretion-
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requested a 24-hour period from TS 4.5.2.h.1 (readjust. seal water ,
flows to the reactor coolant pumps) and TS 4.5.2.h.1.c (eliminate ,
simulated reactor coolant pump seal injection flow requirement). !
A telephone conference call was held between the NRC _and the -
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licensee, and the licensee's request _was granted based on the fact ?
that the licensee's evaluations showed that the . system could carry -
out its design safety functions. The licensee exited TS 3.0.3 at ;
2:02 p.m., on November 9 which was within the_ enforcement
discretion time: limits. This enforcement discretion is considered
closed. Details of the enforcement. discretion were documented in ,
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the licensee's letter, serial 93-727, dated' November 9, 1993. '
These issues were also discussed between the NRC and-the-licensee '
as a part of the enforcement conference conducted on November 10,
1993, involving actions associated with NRC Inspection Report Nos. i
50-338,339/93-28. :
b. Reactor _ Protection System Testing
On October 22, 1993, the inspectors observed periodic test- _ l
2-PT-36.1A, Train A Reactor Protection.and ESF Logic Channel- l
Functional Test, revision 9. The test was performed in; !
preparation for' mode change-from MODE 5 to MODE 4. .The' inspectors !
observed operability verification of the reactor trip and reactor j
trip bypass breakers from the control room, and observed the logic. j
and permissive' circuitry test at the _ logic test panel in. the - .
emergency switchgear relay room. The test was adequately ;
controlled and all equipment performed as required.
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No violations or deviations were identified.
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6. Engineered Safety Feature System Walkdown (71710)
The inspectors performed a detailed CVCS system boration flow path
walkdown. The portions of the system selected were those used to meet
TSs 3.1.2.2, 3.1.2.4, 3.1.2.6 and 3.1.2.8 requirements. The inspectors
compared system alignments with drawings and procedures 1-PT-13.3 and
2-PT-13.3, Boration Flow Path Verification, revisions 15 and 7,
respectively. Additionally, general system material condition and
housekeeping were observed. The inspectors found that the system
appeared to be in good material condition. System components were found
to be in the proper lineup. Only minor housekeeping problems were
identified. The licensee corrected these minor problems. Overall,
inspectors judged radiological conditions in-the cramped area around
system valves to be good. However, it was noted that the posting for
one radioactively contaminated area boundary was vague. The posting was
promptly enhanced by the licensee. The inspectors concluded that the
system met TS requirements and was properly aligned and maintained.
No violations or deviations were identified.
7. Licensee Event Report Followup (92700) ,
The following LERs were reviewed and closed. The inspectors verified
that reporting requirements had been met, causes had been identified,
corrective actions appeared appropriate, and generic applicability had l
been considered,
a. (Closed) LER 50-338/91-19: Inadequate Procedure Causes an
Improper LHSI Relief Valve Blowdown Ring Setting Resulting in
Operability Issues
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This LER was issued as a result of a LHSI relief valve which
opened during a pump start and failed to reseat. The relief valve
failure consequences were reviewed and documented in paragraph 8.a
of this report.
(Closed) LER 50-339/92-10: Cold Leg Safety Injection Branch Line
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b.
Flow Below Technical Specification Requirements
This LER concerned the licensee's failure to meet TS requirements
for HHSI flow balance and was related to Violation 50-339/92-10-04
discussed in paragraph 8 b. The inspectors reviewed the LER and
verified that licensee's corrective actions had been implemented.
After recurrence of this problem, this issue was addressed by
actions related to NRC Inspection Report Nos. 50-338, 339/93-28.
8. Action on Previous Inspection Items (92701, 92702) i
The following previous inspection items were reviewed and closed:
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a. (Closed) URI 50-338/91-22-02: LHSI Relief Valve Inoperability '
Safety Consequences
This URI concerned evaluating the safety consequences.for an event ,
where the LHSI relief valve lifted and failed to reseat. The :
inspectors reviewed this issue to verify that the LHSI relief
valve failure could not. result in off-site and on-site
radiological consequences . exceeding regulatory limits. The ,
inspectors requested information regarding the dose. calculations 6
documented in LER 50-338/91-19.. Prior to providing the r
information to the inspectors, system engineers reviewed the data -
and identified that the off-site EAB and LPZ doses were incorrect
- (low) by a factor of three. A revision to the-LER was promptly
initiated. The inspectors found that the revised calculations
indicated that "best estimate" doses were well within 10 CFR 100- :'
and GDC criteria 19 limits. This action resolved the URI.
Separate from the safety consequences issue, the inspectors also
reviewed the history of problems associated with the LHSI due-to !
pressure surges during pump start operations. . Specifically,
pressure surges caused by inadequate venting have challenged the .
system and resulted in equipment failures. Most recently, NRC
Inspection Report Nos. 50-338,339/93-18, documented the progress
that had been made with suppressing these surges during testing.
This was primarily a result of additional vents which were added
to the system during the most-recent outages. Although progress ,
has been made, the inspectors questioned the adequacy of the_ . ~'
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system response to an actual SI. This was based on the fact that
prior to each test the system was vented.to remove entrained gases l
and suppress pressure surges. The . licensee indicated that as part !
of long term corrective actions, the interval between venting - ;
would be determined to assure challenges to the system were
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minimized. The licensee further indicated that recent venting .
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before testing performed on Unit 1. released only small volumes of i
gas. Until the interval between venting is established, this is ;!'
identified as IFI 50-338,339/93-27-02: Adequacy of LHSI Venting
Interval. ,
b. (Closed) VIO 50-339/92-10-04: Failure to Meet TS Flow
Requirements for ECCS i
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This violation concerned the licensee's failure to meet TS
requirements for HHSI flow. balance and was associated with
LER 50-339/92-10 addressed in paragraph 7.b. The licensee ,
responded to this violation in correspondence dated June 9, 1992.. ;
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This response was acceptable. The inspectors reviewed the l .
violation and verified that licensee's corrective actions had been-
implemented. After recurrence of this problem, this issue was "
addressed'by actions related to NRC Inspection Report Nos. 50-338,
339/93-28.
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c. (Closed) VIO 50-338,339/92-13-02: Failure to Limit Personnel
Working Hours
This violation concerned licensee management's failure to properly
monitor and control overtime which resulted in frequent problems
where personnel exceeded requirements for a maximum of 72 working
hours in a seven day period. The licensee responded to this l
violation in correspondence dated July 8,1992. This response was ,
acceptable. The inspectors routinely monitored licensee
management's efforts to monitor and control overtime during the
Unit 1 SG replacement outage in the spring of 1993 and the Unit 2 .
refueling outage in the fall of 1993. Additionally, inspectors .f
monitored QA assessments in this area. The inspectors found
management's attention to be effective in correcting the problem. -
d. (Closed) IFI 50-339/92-10-02: Loop Stop Valve Failure Due to >
Incorrect Motor Wiring
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This item was opened to follow the licensee's actions for repair
of the valve and to review personnel performance issues. Repairs
to the valve were completed under WO 00260544-03 prior to startup
from the most recent outage. With regards to personnel
performance, this item was reviewed and it was conclude <t that
fatigue could have played a role in the error as documented in NRC
Inspection Report Nos. 50-338, 339/92-10. Current personnel
performance during the most recent outage did not identify similar
problems.
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e. (Closed) VIO 50-339/92-18-02: Inadequate Corrective Maintenance
on Airlock Door to Preclude Repetition
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The violation involved repeated containment airlock door test
failures due to inadequate corrective maintenance. The licensee
responded to this violation in correspondence dated November 18, <
1992. This response was acceptable. Corrective action included
maintenance to align the airlock door during the fall 1993 Unit 2
refueling outage. The inspectors reviewed the completion of this
maintenance and subsequent testing. The inspectors found the
licensee's actions to be adequate.
f. (Closed) VIO 50-338/93-18-01: Inoperable Hydrogen Analyzer
The violation involved a hydrogen analyzer which was discovered to ;
be inoperable due to a pressure sensing line being disconnected.
The licensee responded to this violation in correspondence dated -
November 18, 1992. This response was acceptable. The cause of
the event was personnel error with procedural inadequacies as a
contributing factor. The inspectors verified that the procedures '
for calibrating the hydrogen analyzers were revised to more
clearly reflect restoration of the hydrogen analyzer and to more
clearly define verification steps. :
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To address the broader issue of an apparent negative trend in the
number of errors during performance of I&C activities, increased :
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management attention was placed on the activities. Overall,
licensee management was aggressive in trying to understand the '
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cause for the errors and initiating corrective actions. Actions
taken by the licensee have also been previously documented in NRC ,
Inspection Report Nos. 50-338, 339/93-18. I&C personnel errors
are currently trended by the licensee. The inspectors reviewed
the data which indicated zero errors for the months of June -
September 1993. The inspectors considered that actions to resolve
this issue were effective.
g. (Closed) IFI 50-339/93-24-01: Loose Fuel Material in the Transfer
Canal
This item involved the finding of several loose fuel pellets in
the Unit 2 transfer canal during the fall 1993 refueling outage.
Inspectors followed the licensee's recovery of the fuel material ,
and its return to a safe storage location in the spent fuel pool '
(paragraph 3.d).
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9. Exit (30703)
The inspection scope and findings were summarized on November 24, 1993,
with those persons indicated in paragraph 1. The inspectors described
the areas inspected, the findings in the results section of this report ,
and discussed in detail the inspection results listed below. The -
licensee did not identify as proprietary any of the material provided tn~ 1
or reviewed by the inspectors during this inspection. Dissenting
comments were not received from the licensee. l
Item Number Description and Reference
VIO 50-339/93-27-01 Failure to follow Procedure 2-PT-82H ;
(paragraph 3.c) ;
IFI 50-338, 339/93-27-02 Adequacy of LHSI Venting Interval !
(paragraph 8.a) l
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10. Acronyms and Initialisms
AC Alternating Current
ASME American Society of Mechanical Engineers !
CCW Component Cooling Water ,
CFR Code of Federal Regulations
CR0 Control Room Operator !
CVCS Chemical and Volume Control System !
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DR Deviation Report
EAB Exclusion Area Boundary t
ECCS Emergency Core Cooling System
EDG Emergency Diesel Generator r
E0P Emergency Operating Procedure [
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ESF- Engineered Safety Feature
FW Feedwater ,
GDC General Design Criteria
GPM Gallons Per Minute
HHSI High-Head Safety Injection
I&C Instrumentation and Control >
IFI Inspector Follow-up Item
IN Information Notice
ISI Inservice Inspection ;
LCO Limiting Condition for Operation i
Licensee Event Report .
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LER
LHSI Low Head Safety Injection j
LPZ Low-Population Zone
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MSVH Hain Steam Valve House
NRC Nuclear Regulatory Commission !
PCT Peak Centerline Temperature
PT Periodic Test
QA Quality Assurance
SG Steam Generator
SI Safety Injection :
SNSOC Station Nuclear Safety and Operating Committee .
SRO Senior Reactor Operator ,
TS Technical Specification
URI Unresolved Item i
VIO Violation i
WO Work Order ;
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