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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 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 1999-07-02
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G4 4, UNIT E D ST AT ES
% 4o NUCLEAR REGULATORY COMMisslON REGloN 11
$ aE 101 MARIEll A Sint ET. o 'f AT L ANT A. 0EOHOl A 30323 94 ,o rcn - a ou Report Nos.: 50-338/93-02 and 50-339/93-02 Licensee: Virginia Electric and_ Power Company 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: January 4-8, 1993 Inspectors: . 7./ P/ O g -
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. 'iftener ~ Date Signed Approved by: Au H. Branch,gCMeT F b7 ./dt li/2'_f'_
Test Programs Sectio (n/ // 7Date Gigned Engineering Branch Division of Reactor Safety SUMMARY Scope: 1 This routine, announced inspection was conducted in the areas of design '
changes and modifications, engineering support activities, and licensee event report-followu Results:
Violations-or deviations were not identified in the areas. inspecte The licensee has implemented a process for prioritizing and scheduling plant modifications that address nuclear safet The quality and . technical content of the design change packages reviewed -
were considered goo The licensee has established and is implementing a Design Basis Documentation (DBD) program. The design change process has mechanisms for providing feedback to the DBD program when a plant design change has been implemente PDR ADOCK 03000338 G PDR
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The licensee has effective controls to ensure that applicable design ,
documents are updated in a timely manner to reflect the as built plan ;
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The engineering staff provided adequate and timely support to the plan *
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The engineering training program was considered to be above average. The-number of managers and supervisors in engineeri.ng who have operations '
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REPORT DETAILS Persons Contacted Licensee Employees D. Benson, Manager, Nuclear Engineering
- Bischof, Assistant Superintendent, Station Engineering D. Heacock, Superintendent, Station Engineering
- P. Kemp, Acting Assistant Station Manager, Nuclear Safety and Licensing
- J. Leberstien, Staff Engineer, Licensing
- G. Modzelewski, Supervisor, Civil Engineering, Station Engineering
- R. Riley, Supervisor, Project Engineering, Nuclear Engineering D. Roberts, Supervisor, Station Nuclear Safety
- J. Smith, Manager, Quality Assurance
'J. Stall, Acting Assistant Station Manager, Operations and Maintenance Other licensee employees contacted during this inspection included engineers, operators, security force members, and administrative personne NRC Resident inspectors
- Lesser, Senior Resident inspector
- Taylor, Resident inspector S. Lee, Resident inspector
- Attended exit meeting Acronyms and initialisms used throughout this report are listed in the last paragrap . Design Changes and Plant Hodifications (37700) Plant Modifications to Improve Reactor Safety The inspectors reviewed the initiatives taken by the licensee to identify and implement plant modifications to improve reactor safety. Documentation reviewed during this effort included:
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Procedure VPAP-0304, Requests for Engineering Assistance / Engineering Transmittals, Rev. 0
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North Anna Modification Request Guidelines
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North Anna Power Station 1993 Capital Budget Scope Statement, July 16, 1992
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North Anna Power Station Minor / Major Modifications Projects Installed, Units 1 and 2, January 4, 1993
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North Anna Power Station Minor / Major Modifications Projects issued, Units 1 and 2, January 4, 1993
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1993 Unit 1 Outage Modification List
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1993 Unit 2 Outage Modification List The inspectors determined that the Assistant Superintendent Design Engineering (Station Engineering) was responsible for the initial screening and prioritizing of design changes to the plant. The MMRT approves the design change priority, the assignment to a NES
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neganization and the assignment to an implementing organizatio The MMRT consists of the Assistant Station Manager 0&M, Superintendent Operations, Superintendent Radiological Protection, Superintendent Station Engineering, Superintendent Nuclear Site Services, Superintendent Outage and Planning, and the Superintendent Maintenanc Based on _ discussions with licensee engineering personnel, and review of the above documentation the inspectors concluded that the licensee has a satisfactory prioritization process for identifying and implementing plant design changes to improve reactor safet Planning, Development and Implementation of Plant Modifications The inspectors reviewed the DCPs listed below to: 1) determine the adequacy of the 10 CFR 50.59 evaluations performed; 2) verify that the DCPs were reviewed and approved in accordance with TS and applicable administrative controls; 3) verify the subject modifications were installed (for those that could be physically inspected) in accordance with the DCP package; 4) verify that-applicable plant operating and design documents (drawings, plant procedures, FSAR, TS, -etc.) were revised to -reflect -subject modifications; 5) verify that the modifications-were reviewed and-incorporated into the operations training _ program as applicable; and 6) verify that post modification test requirements were specified and that adequate testing was performed. The following DCPs were reviewed:
DCP 92-104,. Rebuilding of Selected SW MOVs This DCP involved the inspection and rebuilding of the Unit 1 16 inch SW butterfly valves 1-SW M0V-103A,B,C,D-and 1-SW MOV-104A,B,C,0 in order to reduce the high seating torque experienced during seating of the valves._ These
- valves provide isolation of the RSHX and are safety relate Modifications to the valves included installing a stainless-steel sleeve in the stub shaft and valve shaft bore; increasing the diameter (from 7/16-inch to 5/8-inch) of _the groove pins holding the disc to the valve shaft; and replacing the thrust collar with one shrunk fit to= the valve shaft. The new thrust collar design was also installed on -
the 24-inch SW butterfly valves 1 SW MOV-101A,B,C,0; J-SW-MOV-102A,8; l-SW-MOV-105A,B,C,D; and 1-SW MOV-106A,B.-
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The 24 inch valves are located in the SW supply and return lines to the RSHXs. The inspectors reviewed the safety evaluation for adecuacy. Areas addressed in the safety evaluation includec , but were not limited to, seismic, material compatibility, effects of weight changes, and post modification test requirement During review of the DCP and associated field changes, the inspectors noted that the diagnostic testing performed on the valves was being used for information Jurposes onl The data were not used for acceptance of tie work performed under the DCP nor for setting of the torcue switch and the torque switch bypass. The basis arovidec in the change was.-
that the test _ equipment accuracy 1ad not been-independently validated. The diagnostic equipment was used to aid the MOV Engineer in evaluating the effect that the repairs made to the valve internals had on the motor operators. The valves were stroke tested and the motor operator current checked to verify operabilit Evaluation of the diagnostic test data-by the MOV Engineer indicated that there were no conditions internal to the valves which would be detrimental to the motor operator. During discussions with the inspectors, licensee personnel indicated that a letter modifying GL 89-10 commitments on DP testing of quarter turn valves would be sent to the NRC. The licensee's Gl. 89 10 program will be reviewed during subsequent inspection The inspectors determined from the information-reviewed that this DCP was implemented in accordance with licensee procedures and control * DCP 91-205, Auxiliary feedwater Total Flow Indication Removal This DCP involved removing the' AFW total flow indicator from the Unit 2 control room. in addition, the logic card which summed the three individual AFW flow loo)s and associated cabling were removed from the process casinets in the emergency switchgear room. The-flow indicators were installed under DCP 87-31. During a review of the E0Ps to identify revisions which might be required as a result of DCP 87-31, the licensee determined that use of the total-flow indicator did not provide accurate information for all credible situations. -This modification was never installed-on Unit 1. The inspectors reviewed the safety evaluation t verify that items considered included human factors, instrument accuracy _ calculation,- and Appendix The inspectors concluded that the safety evaluation bounded the scope-of the work covered by the DCP and the DCP.was implemented-in accordance with licensee procedures. The inspectors did note, however, that the original design =
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review for DCP 87-31 could have prevented the unnecessary plant modification that was later removed. The inspectors noted that the licensee's design change process has been enhanced since the original review of DCP 87-31 which provides for a more thorough upfront review of CCP *
DCP 92-252, Missile Protection for EDG Fuel Transfer Piping This DCP involved installing a structural steel plate missile barrier in each of the Unit I and Unit 2 EDG rooms in order to protect short runs of exposed 1-1/2 inch and >
l inch diameter EDG fuel oil transfer lines from tornado generated missile hazards. The two lines supply fuel oil to each EDG, one primary supply and one standby supply. The fuel supply lines are located near the intake louvers in i each EDG roo The intake louvers for each EDG room were not designed to protect the short run of fuel oil transfer piping from a missile hazard. The inspectors reviewed the safety evaluation to verify that items considered included seismic, Appendix R, and TS surveillance requirement The inspectors concluded that the safety evaluation ;
addressed the scope of work and the DCP was implemented in accordance with licensee procedure * DCP 84-71, Pressurizer Safety and Relief Valve Discharge Pipe Support Modifications In response to NUREG 0737, item 11.0,1, Virginia Electric-and Power Company (VEPC0) analyzed the transient fluid loads ,
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which would result when the pressurizer safety valves (PSVs)
and/or Power Operated Relief Valves (PORVs) lift and system-pressure accelerates the loop seal cold water through the valvo and discharge piping. .The analysis indicated that significantly high fluid transient .. loads would result Lin-unacceptable stress levels and pipe support loads, it was determined that the installation of reflective metal thermal insulation on the loop seals (loop seal- ovens) to maintain a--
water temperature greater than 400'F and modification of the PSV discharge piping supports would adequately accommodate the fluid transient loading. The loop seal: ovens have been'
installed on both. Units and the PSV discharge pipe support; modifications has been completed on Unit 2. -DCP 84-71 was '
issued to modify the PSV discharge pipe support system in Unit 1. -The proposed modification' included addition of~.
supports, deletion of supports and modification of existing supports.
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Review of the pipe support modification package.(DCP 84-71)
l-showed that the project:was worked over three outages and-l l
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was closed out in 1992 without completion of the support modifications. The DCP was to be implemented.in the 1985 refueling outage. However, the license determined that the project was so extensive that completion in a single outage would significantly extend the outage time. Consequently the controlling procedure was revised twice, once in field Change (FC) FC-4 in 1985 and again by FC 47 in 198 The project was divided into three phases as follows:
Phase ! - Modification upgrade of load capacity of an existing support. For instance replacement of a 11 inch hydraulic snubber with a 31 inch hydraulic snubber. In this phase, support functions were not changed and supports were not added, deleted or relocated. The original stress analysis remained vali Phase 11 - In this phase all additional supports required for the piping upgrade were to be installed except they would not be connected to the pipin Therefore, the original pipe stress analysis remained '
vali Phase Ill - All physical connections for added supports to the piping will be made and disconnection between piping and existing supports to be removed will be performed. These changes to support function -
and location of supports are validated by the revised pipe stress mode Phase I and Phase 11 were implemente Phase 111 was not; implemente Consequently, .the as left pipe support- system conforms to the original stress analysis.- The close out wa's considered prudent since 1) the DCP_had become difficult to work under significantly different design control procedures, 2) the package had become complex (75 revisions).
and difficult for craftsmen to follow and, 3) management was considering a different resolution.to item II.D.1 which may not require the support modification '
The DCP 84-71 close out was' documented in the package and-included a system walkdown, verification of-document. updates; and revision of system description-to reflect the a installed system configuration. Post modification-testing:
was not require The licensee's Engineering Review and Safety Analysis was >
adequate and included evaluation of areas such as fire hazards, seismic analysis, environmental qualification, t ALARA, NRC concerns, impact'of other design changes,.
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documents-and impact on design basis document The licensee provided a letter to the f4RC dated flovember 12, 1992, which indicated that the modification to meet fiUREG 0737, item II.D.1 on Unit.I will consist of draining off the loop seal water to provide a steam environment.at the PSVs. This modification has been deferred until the f1RC has completed the review of the-Westinghouse Owners Group final report on PSV set)oint drift since f4RC positions on draining the loop seal mig 1t affect the planned modificatio * DCP 92 182, RVLIS Tubing Configuration Change, Unit 2 *
This DCP was issued due to leakage at the Reactor Vessel Level Indication System-(RVLIS) tee connection at.the seal table. When reviewing the condition the licensee found that subsequent to installation of the RVLIS seal table fittings on Unit 2 and prior to the Unit 1 installation, the Westinghouse drawing 1598E06 which controlled the installation was revised. The change at the too connection at the seal table reduced the number of fittings and :
potential leakage path The design was previously approved per DCP 81 01'. .
(installation of the system) and Westinghouse drawing ,
1598 E 06, Revision 2. The inspectors determined that- '
10 CFR 50.59 safety evaluations-adequately addressed the DC Maintenance of the Design Basis Document Through The DCP Process-The licensee. initiated a system design basis documentation (S000)
program in flovember 198 Scheduled com)1etion-date is December 199 The SDBDs will be performed for a)out 80. systems. Thirty of these-are safety related systems. The rest are balance of plant and sy_ stems important to safet The inspectors determined that the licensee has established a- .
computerized data base to identify any activities which may impact-a SDBD. For instance, a- )lant modification-which will impact the-system design basis!will ao identified and maintained in this data-base. Changes to the design. basis are accumulated-in this-data-hase and can be reviewed through the Data Management.information-System (DMIS) as=needed. The design basis documents are periodically reviewed and update :In addition _to the system DBDs the licensee is preparing.an Accident Analysis DB t I
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d. Configuration Control The inspectors reviewed selected controls developed and implemented by the licensee to ensure that applicable design documents and procedures affected by completed DCPs were updated in a timely manner to reflect the as-built plant. Documents reviewed included procedures VPAP-0301, Design Change Process and ADM-6.10, Annotation and Revision of Station Drawing These documents describe the controls for updating applicable priority and non-priority plant documents as a result of a DCP; and for annotating, revising, and distributing station drawing Priority documents include drawings, procedures, and other controlled plan documents which are needed to support operation of the Priority documents are required to be revised before returning the affected system or component to operable statu Controlled drawings at North Anna comprise three categories which are priority drawings, test loop diagrams, and non priority drawing Priority drawings are those required in the control room, 150, and operation / maintenance coordinator's office, for DCPs and EWRs, priority drawings are required to be revised prior to test completion, technical review, or operational readiness review as applicable, to be revised within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of the technical review.in Priority all cases priority dra DURs are required to be revised within 15 days of a notification to update following the completion of an engineering review and verification. DURs are a means of informing engineering of drafting and typographical errors or to reflect plant as-built condition Test loop diagrams are required to be updated within 30 days after receipt of a notification to update. Non-priority drawings are required of a notification to be updated within 90 days after receipt to updat The inspectors reviewed selected documents that were affected by the DCPs discussed above and verified that the documents were updated in accordance with the licensee's administrative controls, in addition, the inspectors also reviewed performance indicators which showed that, as of November engineering were issued on time. 30, 1992, drawings issued by The inspectors concluded that the licensee had adequate controls '
for ensuring that applicable documents were updated in a timely manner to reflect the as-built plan .
~ PRA Application in Design Control Discussions with licensee management revealed that the licensee recently completed an IPE for North Anna. The final report was submitted to the NRC by letter dated Decemb9r 14, 1992. The licensee's letter indicated that several hardware modifications designed to further enhance the flood protection system have been
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implemented. Completed modifications included DCP 92-015, Individual Plant Examination (IPE) Internal Flooding Civil 14difications and DCd 92-161 Charging Pump Cubicle floor Drain Backflow Preventer. Licensee personnel indicated that the completed PRA is available for use by NES personnel in the design ,
control arocess. The inspectors concluded that the completed PRA i for Norta Anna is another tool that is now available to the design organizatio Use of the PRA should enhance the design control proces . Organization, Staffing, and Training The inspectors reviewed the licensee's organization and staffing to determine whether the licensee's engineering organization was adequately staffed to provide effective engineering support to the plan The Nuclear Engineering organization is comprised of seven departments which report-via managers to the Vice President Nuclear-Engineering Services. This includes the special group established for the steam generator replacement project. Station Engineering is part of NES and reports through the Manager Nuclear Engineering to the Vice President NE Day to day real time support was primarily provided by Station Engineerin The staffing levols within NES have not changed significantly over the-last year. The staffing levels were sufficient to_ support plant activitie The inspectors reviewed variocs performance indicators for selected engineering activities which showed that Engineering provided timely support to the plant during 1992. Drawings which required updating were completed arior to their due dates. Engineering established a goal for tie number of backlogged (greater than 90 days old) minor modifications not to exceed 50. . The backlog was reviewed on a monthly basis. The actual backlog never reached 40 during any month-in 199 CTS items and DRs assigned to Engineering were answered before their due date The inspectors concluded from reviewing the completed DCPs and the
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various performance indicators that NES:provided adequate and timely -
support to the plant, in addition to reviewing the licensee's organization and staffing,_'the inspectors also reviewed the training provided to the Engineering staffs. Training was provided in accordance with the requirements-
'pecified in the Nuclear Technical Staff and' Technical: Staff Managers'
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Training Program, Revision 9. The program specifies initial' and
. continuing training requirements for both site and corporate engineering personnel. The training program specifies fundamental training required for all engineers and additional training for the various disciplines, included in the fundamental training is three weeks of systems l training.-
In addition to'the training specified in the program, the inspector noted that engineerfrg personnel receive 10 CFR 50.59 Safety Evaluation
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training. The inspectors verified that selected engineers involved in the DCPs discussed in paragraph 2.b. of this report had received 10 CFR 50.59 training within the last year. The inspectors also noted that several of the supervisors and managers in Engineering (site and
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corporate) have received operations training. Several of the supervisors and managers have either worked in the plant as a SR0 or have SRO certification The inspectors concluded that the licensee's training program for the engineering staff was adequate. The inspectors considered the operations training and experience in NES to be a strengt ;
' Review of Licensee Event Reports (LERs)
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The inspectors reviewed LERs 91 002 (Unit 1),92-002 (Unit 1),90-005 (Unit 2) and 92-003 (Unit 2). The reports identify certain pressurizer safety valves (PSVs) and main steam safety valves (MSSVs) where the measured lift pressure did not meet the setpoint pressure Technical Specification (TS) limit within +/- one percent. The as found lift pressure was determined by Wyle Laboratory using-steam as a test mediu The licensee concluded that there was no significant safety implications from the high lift pressure setaoint drift since the as found lift t pressure settings were bounded )y the safety analysis for overpressure transients. Specifically, the expected pressure was less-than design basis pressure. Also, there was no significant safety impact for the safety valves where the setpoint drift was on the low side of the setpoint tolerance since the shift did not activate the valves and '
result in a challenge to safety systems. The licensee concluded that the safety valves would have performed their safety functions if require Immediate corrective action was to have the valves refurbished and the setpoints adjusted to meet the TS setpoint limit within +/- one percent *
toleranc The concerns relating to PSV setpoint shif t were identified to licensees in NRC Information Notice (IN) 89 90, Pressurizer Safety Valve Lift .-
Setpoint Shift, and Supplements 1 and 2 to IN 89-90. These notices
. identified a potential problem with pressurizer safety valve lift setpoint shifting related to setting a setpoint with steam-flow and operating the valves with a loop seal filled with wate In letters to the NRC dated December 21, 1990, October 31,-1991,.an November 12, 1992,- the licensee proposed, as.long term resolution to th setpoint drift problem, to drain the loop seals and operate the PSVs in a steam environment as is used'for setting the lift pressure. However, modification of the loop seals has been deferred pending the results of the NRC review of the Westinghouse Owners Group report (WCAP 12910) on pressurizer safety valve setpoint shif . . . . . .
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in addition to the above corrective actions, the licensee is considering submittal of a request f or a license amendment to expand the setpoint tolerance. In this regard the licensee is currently reviewing an
analysis and draft license amendment request to change the setpoint tolerance for the MSSVs from 4/- one percent to +/- three percen Since the setpoint 3roblem and corrective action is essentially the same for the four LERs tle inspector considered it appropriate to close LERs91-002 (Unit 1) and 90 005-(Unit 2). The licensee's long term
. corrective action will be tracked by LERs92-002 (Unit 1) and 92 003 (Unit 2) which remain open. Tl.e LER status is left as follows:
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(Closed) LER 50-338/91-002, Pressurizer and Main Steam Safety Valve Setpoints Out of Tolerance Due to Setpoint Drift (Closed) LER 50-339/90005, Pressurizer Safety Valve Setpoints Out of Tolerance Due to Setpoint Drift ,
(0 pen) LER 50-338/92-002, Pressurizer Safety Valve Setpoint Out of Tolerance Due to Setpoint Drift (0 pen) LER 50-339/92-003, Pressurizer and Main Steam Safety Valve-Setpoints Out of Tolerance Due to Setpoint Drift Exit Interview The inspection-scope and results were summarized on January 8, 1993, with those persons indicated in paragraph 1. The inspectors described the areas inspected and discussed in detail the inspection-results, Proprietary information.is not contained in this report. Dissenting _
comments were not received from the license 't
, Acronyms and initialisms AFW Auxiliary.Feedwater CTS Commitment Tracking System DB Design Basis Documentation DCP Design Change Package DR Deviation Report DUR Drawing Update' Request EDG- . Emergency Diesel Generator LOP- Emergency 0perating Procedure
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EWR . Engineering Work Request-FSAR' Final = Safety Analysis Report GL Generic letter IPE Individual Plant Examination MMRT Modification Management Review Team MOV Motor Operated Valve
- NES Nuclear Engineering Services V
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- 11 0&M Operations and Maintenance PRA Probabilistic Risk Assessment RSHX Recirculation Spray Heat Exchanger SR0 Senior Reactor Operator SW Service Water TS - Technical Specifications TSC Technical Support Center
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