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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: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:UTILITY
MONTHYEARIR 05000338/19900231990-10-0909 October 1990 Insp Repts 50-338/90-23 & 50-339/90-23 on 900819-0915. Violation Noted But Not Cited.Major Areas Inspected: Operations,Maint,Surveillances,Operational Event Followup, LER Followup & Evaluation of Licensee self-assessment IR 05000338/19900191990-09-14014 September 1990 Insp Repts 50-338/90-19 & 50-339/90-19 on 900820-24. Violations Noted But Not Cited.Major Areas Inspected: Licensee Radiation Protection Program Consisting of Review in Areas of External & Internal Exposure Control IR 05000338/19900181990-09-11011 September 1990 Insp Repts 50-338/90-18 & 50-339/90-18 on 900718-0818. Violations Noted.Major Areas Inspected:Operations,Maint, Surveillances,Operational Event Followup,Mods,Self Assessment Capabilities & LER Followup IR 05000338/19900201990-09-0606 September 1990 Insp Repts 50-338/90-20 & 50-339/90-20 on 900906.No Violations or Deviations Noted.Major Areas Inspected: Annual Emergency Preparedness Exercise IR 05000338/19900171990-07-27027 July 1990 Partially Withheld Insp Repts 50-338/90-17 & 50-339/90-17 on 900709-13 (Ref 10CFR2.790).No Violations or Deviations.Major Areas Inspected:Physical Security Program for Power Reactors & Security Plan & Implementing Procedures IR 05000338/19900131990-06-27027 June 1990 Insp Repts 50-338/90-13 & 50-339/90-13 on 900514-18 & 29. Noncited Violations Noted.Major Areas Inspected:Radiation Monitoring Sys,Water Chemistry & QC IR 05000338/19900141990-06-22022 June 1990 Insp Repts 50-338/90-14 & 50-339/90-14 on 900604-08.No Violations or Deviations Noted.Major Areas Inspected:Fire Protection & Followup on Unresolved Item Identified During App R Triennial Insp on 880718-22 IR 05000338/19890261989-09-21021 September 1989 Insp Repts 50-338/89-26 & 50-339/89-26 on 890715-0822. Violation Noted.Major Areas Inspected:Plant Status,Maint, Surveillance,Esf Walkdown,Operational Safety Verification, Operating Reactor Events & LER Followup IR 05000338/19890221989-08-24024 August 1989 Insp Repts 50-338/89-22 & 50-339/89-22 on 890601-0714.No Violations or Deviations Noted.Major Areas Inspected:Plant Status,Maint,Surveillance,Esf Walkdown,Operational Safety Verification,Generic Ltr 88-17 & Plant Startup IR 05000338/19890271989-08-22022 August 1989 Insp Repts 50-338/89-27 & 50-339/89-27 on 890731-0804.No Violations or Deviations Noted.Major Areas Inspected: Followup on Licensee Action Re Previous Insp Findings. Weaknesses Noted Re Labeling of Instruments & App R Sys IR 05000338/19892001989-08-0808 August 1989 Safety Sys Outage Mod & Maint Team Insp Repts 50-338/89-200 & 50-339/89-201 on 890508-12 & 22-26.No Violations Noted. Major Areas Inspected:Implementation of Matl & Work Control Sys to Ensure Mod Conformed to Installation Requirements IR 05000338/19890241989-08-0707 August 1989 Insp Repts 50-338/89-24 & 50-339/89-24 on 890710-14.No Violations Noted.Major Areas Inspected:Functional Areas of Emergency Preparedness Program,Including Training,Audit Repts,Distribution of Changes to EPIPs & Staff Augmentation IR 05000338/19890211989-07-27027 July 1989 Insp Repts 50-338/89-21 & 50-339/89-21 on 890613-14.No Violations or Deviations Noted.Major Areas Inspected: Physical Security Program for Power Reactors,Specifically pre-employment Screening & Clearances ML20247D5441989-07-0707 July 1989 Insp Repts 50-338/89-12 & 50-339/89-12 on 890412-14 & 20-26. Violation Noted.Major Areas Inspected:Witnessing Containment Integrated Leak Rate Test,Reviewing Test Procedures & Evaluating Test Results IR 05000338/19890121989-07-0707 July 1989 Corrected Pages 1 & 2 to Insp Repts 50-338/89-12 & 50-339/89-12 on 890412-14 & 20-26.Violation Noted.Major Areas Inspected:Containment Integrated Leak Rate Test,Test Procedures,Evaluation of Test Results & Previous Items IR 05000338/19890191989-06-30030 June 1989 Insp Repts 50-338/89-19 & 50-339/89-19 on 890605-08.Major Areas Inspected:Solid Wastes,Transportation of Radioactive Matls & Radwaste & Followup on previously-identified Insp Findings IR 05000338/19890201989-06-28028 June 1989 Insp Repts 50-338/89-20 & 50-339/89-20 on 890605-09 & 12-13. No Violations or Deviations Noted.Major Areas Inspected: Results of 10-yr Ultrasonic Exam of Unit 1 Reactor Pressure Vessel & Observation of Inservice Activities ML20246J9231989-06-27027 June 1989 Insp Repts 50-338/89-14 & 50-339/89-14 on 890418-0531. Violation Noted.Major Areas Inspected:Plant Status, Maint,Surveillance,Esf Walkdown,Operational Safety Verification,Operating Reactor Events & LER follow-up IR 05000338/19890091989-06-0909 June 1989 Insp Repts 50-338/89-09 & 50-339/89-09 on 890522-24.No Violations or Deviations Noted.Major Areas Inspected:Primary & Secondary Chemistry,Radwaste Processing,Radioactive Effluents & Environ Monitoring IR 05000339/19892001989-06-0707 June 1989 Insp Rept 50-339/89-200 on 890213-17 & 0227-0303.Potential Enforcement Items Noted.Major Areas Inspected:Evaluation of Planned Design Changes & Mods Against Regulatory Requirements & Licensee Commitments ML20245D5481989-06-0707 June 1989 Insp Repts 50-338/89-11 & 50-339/89-11 on 890403-07. Violations,Deviations & Unresolved Items Noted.Major Areas Inspected:Licensee Conformance to Reg Guide 1.97, Instrumentation for Light Water Cooled Nuclear Power.. IR 05000338/19890171989-06-0606 June 1989 Partially Withheld Insp Repts 50-338/89-17 & 50-339/89-17 on 890501-05 (Ref 10CFR2.790(d) & 10CFR73.21).No Violations or Deviations Noted.Major Areas Inspected:Core Insp Program. Noncited Violation Re Improper Badging Noted ML20244E5611989-06-0606 June 1989 Insp Repts 50-338/89-18 & 50-339/89-18 on 890515-19. Violations Noted.Major Areas Inspected:Areas of Inservice Insp - Observation of Work & Work Activities IR 05000338/19890131989-06-0202 June 1989 Insp Repts 50-338/89-13 & 50-339/89-13 on 890418-20. Violations Noted.No Deviations Identified.Major Areas Inspected:Areas of Welding safety-related Components & Review of Reactor Vessel 10-yr Ultrasonic Exam Program ML20245D3511989-06-0202 June 1989 Insp Repts 50-338/89-15 & 50-339/89-15 on 890501-05. Violation Noted.Major Areas Inspected:Radiation Protection Program,Including Review of Areas of External & Internal Exposure Control & Program to Maintain Doses ALARA ML20244B8151989-05-17017 May 1989 Insp Repts 50-338/89-08 & 50-339/89-08 on 890321-0417 & 0425-0503.Violations Noted.Major Areas Inspected:Plant Status,Maint,Surveillance,Operational Safety Verification, Operating Reactor Events & LER Followup IR 05000338/19890041989-04-26026 April 1989 Insp Repts 50-338/89-04 & 50-339/89-04 on 890306-10.No Violations or Deviations Noted.Major Areas Inspected:Seismic Analyses for as-built safety-related Piping Sys Per IE Bulletin 79-14 IR 05000338/19890101989-04-17017 April 1989 Insp Repts 50-338/89-10 & 50-339/89-10 on 890403-07.No Violations or Deviations Noted.Major Areas Inspected:Safety Sys Outage Mod Insp Followup ML20245C0071989-04-13013 April 1989 Insp Repts 50-338/89-05 & 50-339/89-05 on 890320-24. Violations Noted.Major Areas Inspected:Radiation Protection Program in Areas of Organization & Mgt Controls,Training & Qualifications & Internal Exposure Control IR 05000338/19890051989-04-13013 April 1989 Insp Repts 50-338/89-05 & 50-339/89-05 on 890320-24. Violations Noted.Major Areas Inspected:Radiation Protection Program in Areas of Organization & Mgt Controls,Training & Qualifications & Internal Exposure Control IR 05000338/19890031989-04-12012 April 1989 Insp Repts 50-338/89-03 & 50-339/89-03 on 890203-0320. Violations Noted.Major Areas Inspected:Plant Status,Maint, Surveillance,Esf Walkdown,Operational Safety Verification, Operating Reactor Events & LER Followup IR 05000338/19890071989-04-11011 April 1989 Insp Repts 50-338/89-07 & 50-339/89-07 on 890313-17.No Violations or Deviations Noted.Major Areas Inspected: Inservice Insp Work Observation,Inserice Insp Data Review & Licensee Recovery Efforts from 890225 Hot Leg Plug Failure ML20247F0791989-03-23023 March 1989 Insp Repts 50-338/89-02 & 50-339/89-02 on 890221-23.No Violations Noted.Major Areas Inspected:Licensee Response to Emergency Response Facility Appraisal Open Items & Emergency Preparedness Program Enhancement Items IR 05000338/19880361989-03-21021 March 1989 Insp Repts 50-338/88-36 & 50-339/88-36 on 881231-890202. Violations Noted Re Failure to Take Prompt Corrective Action Re Inadequate Instrument Air Quality.Major Areas Inspected: Plant Status,Maint,Surveillance & LERs IR 05000338/19890061989-03-20020 March 1989 Insp Repts 50-338/89-06 & 50-339/89-06 on 890306-10.No Violations or Deviations Noted.Major Areas Inspected: Inservice Insp,Including Eddy Current Exam of Steam Generator Tubing & Reviews of NDE Procedures IR 05000338/19880261989-02-16016 February 1989 Suppl to Insp Repts 50-338/88-26 & 50-339/88-26.Results of Analysis & Evaluation of Health Physics Counting Room Indicate Considerable Improvement Between Licensee & NRC Data for Radionuclides IR 05000280/19880401988-10-26026 October 1988 Insp Repts 50-280/88-40,50-281/88-40,50-338/88-28 & 50-339/88-28 on 880926-30.No Violations or Deviations Noted. Major Areas Inspected:Control Room Habitability & Insp Followup Items IR 05000338/19880271988-10-24024 October 1988 Insp Repts 50-338/88-27 & 50-339/88-27 on 880820-0916.No Violations Noted.Major Areas Inspected:Plant Status,Maint, Surveillance & Operational Safety Verification,Including Reviews of Backshift Operations IR 05000338/19880291988-10-19019 October 1988 Insp Repts 50-338/88-29 & 50-339/88-29 on 880912-16.No Violations or Deviations Noted.Major Areas Inspected: IE Bulletin 79-14 IR 05000338/19880301988-10-0707 October 1988 Insp Repts 50-338/88-30 & 50-339/88-30 on 880912-16.No Violations or Deviations Noted.Major Areas Inspected: Requested Actions on NRC Bulletins,Temporary Instruction 2500/26 & Licensee Action on Previous Insp Followup Items ML20155C2181988-09-26026 September 1988 Insp Repts 50-338/88-24 & 50-339/88-24 on 880815-19. Violations Noted.Major Areas Inspected:Emergency Preparedness,Including Emergency Plan & Implementing Procedures & Emergency Facilities Equipment ML20154R3651988-09-20020 September 1988 Insp Repts 50-338/88-26 & 50-339/88-26 on 880815-19.No Violations or Deviations Noted.Major Areas Inspected: Confirmatory Measurements & Counting Room QA for in-plant Radiochemical Analyses ML20155A1911988-09-15015 September 1988 Insp Repts 50-338/88-22 & 50-339/88-22 on 880716-0819. Violations Noted.Major Areas Inspected:Plant Status,Maint, Sueveillance,Esf Walkdown,Operational Safety Verification, Operating Reactor Events & LER Followup IR 05000338/19880131988-09-13013 September 1988 Insp Repts 50-338/88-13 & 50-339/88-13 on 880718-22. Violation Noted.Major Areas Inspected:Triennial post-fire Safe Shutdown Capability Reverification & Assessment, Including App R Compliance & post-fire Shutdown Capability IR 05000338/19880251988-09-0707 September 1988 Insp Repts 50-338/88-25 & 50-339/88-25 on 880808-12.No Violations,Deviations or Program Weaknesses Noted.Major Areas Inspected:Plant Chemistry,Chemical Corrosion & Pipe Wall Thinning IR 05000338/19880141988-08-18018 August 1988 Insp Repts 50-338/88-14 & 50-339/88-14 on 880627-30.No Violations or Deviations Noted.Major Areas Inspected: Emergency Response Facility & Equipment,Interviews W/Util Personnel & Equipment for Emergency Response Organization IR 05000338/19880211988-08-12012 August 1988 Insp Repts 50-338/88-21 & 50-339/88-21 on 880611-0715.No Violations or Deviations Noted.Major Areas Inspected: Plant Status,Ler,Review of Inspector Followup Items,Monthly Maint Observation & Operator Safety Verification ML20151W7621988-08-0909 August 1988 Insp Repts 50-338/88-18 & 50-339/88-18 on 880606-10. Violations Noted.Major Areas Inspected:External Exposure Control & Assessment,Control of Radioactive Matls, Contamination,Surveys & Monitoring & Solid Waste IR 05000338/19880171988-07-0808 July 1988 Insp Repts 50-338/88-17 & 50-339/88-17 on 880606-10.No Violations or Deviations Noted.Major Areas Inspected:Review & Evaluation of Inservice Insp Data from Unit 2,1987 Refueling Outage & Maint Records Review of Coolant Pump IR 05000338/19880121988-07-0606 July 1988 Insp Repts 50-338/88-12 & 50-339/88-12 on 880420-22.No Violations or Deviations Noted.Major Areas Inspected:Snubber Surveillance Program & Followup on Licensee Action on Previous Insp Findings 1990-09-06
[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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Report Hos.: -50-338/87-21 and 50-339/87-21 Licensee: Virginia Electric & Power Company-Richmond, VA 23261 Docket Nos.: 50-338 and 50-339 Facility Name: ' North Anna 1 and 2 l Inspection Conducted: June 21,1987 - July 10,1987 Team Members: J. L. Caldwell L.' P. King L. E. Nicholsen A. R. Long C. L. Vanderneit Approved by: d'h.4 ([ Mef F. S.~Cantrell, Secti
// b Date Signed Division of Reactor P ects SUMMARY Scope: This ~ isDa special inspection covering the loss of reactor coolant l system inventory event which occurred during June 17, 1987 to June 21, 1987,
.and involved -the following areas: Introduction and General Description of the Event, NRC Response to the Event, Sequence of Events, Potential ~ Safety Issues Associated with the Event, Contributing Factors or Factors which Complicated .
the Event, Reactor Vessel Level Instrumentation System Training, Enforcement and Conclusion Results: Two violations were identified: Violation of Technical Specification 6.8.1.a with four examples and a failure to perform a 10 CFR 50.59 safety evaluation. (See Paragraph 9)
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REPORf DETAILS Licensee Employees Contacted
- W. Harrell, Station Manager
- C. Driscoll, Quality Control (QC) Manager
- M. L. Bowling, Assistant Station Manager
- R. O. Enfinger, Superintendent, Operations M. R. Kansler, Superintendent, Maintenance J. A. Stall, Superintendent, Technical Services J. R. Hayes, Operations Coordinator D. A. Heacock, Engineering Supervisor J. P. Smith, Superintendent, Engineering D. B. Roth, Nuclear Specialist J. H. Leberstein, Engineer
- G. G. Harkness, Licensing Coordinator Other licensee employees contacted include technicians, operators, mechanics, security force members, and office personne * Attended exit interview Exit Interview (30703)
The inspection scope and findings were summarized on July 10, 1987, with those persons indicated in paragraph 1 above. The licensee acknowledged the inspectors findings. The licensee did not identify as proprietary any of the material provided to or reviewed by the inspectors during this inspectio (0 pen) Violation 338/87-21-01: Violation of TS 6.8.1.a with four examples for inadequate procedures and lack of procedures. (paragraph 9)
(0 pen) Violation 338/87-21-02: Faliure to conduct a 10 CFR 50.59 safety evaluation prior to conducting a test or experiment on the reactor coolant syste . Introduction and General Description of the Event On June 21, 1987, the licensee informed the resident inspector of a situation discovered on Unit 1, involving the inadvertent formation of voids in the reactor vessel head and Steam Generator (SG) tube are The licensee had already taken action to return the unit to a stable condition !
I by filling the Reactor Coolant System (RCS) and venting the reactor vessel
, head to the top of the pressurizer. The pressurizer was also vented to
! the Pressurizer Relief Tank (PRT) via the Power Operated Relief Valve I (PORV). The licensee reported that it took approximately 17,000 gallons to refill the RCS and the reactor vessel was verified full by a 100%
reading on the Reactor Vessel Level Indication System (RVLIS). The other
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conditions of the unit on June 21, 1987, were RCS temperature of 110 degrees F, RCS pressure of approximately 20 psig and a pressurizer level of approximately 36L The inspector responded to the station to review the event with the licensee and verify the unit had been placed in a safe and stable conditio Background information and a description of the event are provided in the following discussion: ;
On June 17, 1987, the licensee had commenced a heat up on Unit I to change modes from Mode 5 to Mode 4. The unit was being restarted from a 60 day refueling outage. The plant conditions were RCS temperature of 195 degrees F, RCS pressure of 320 psig, pressurizer temperature of 425 degrees F with a steam bubble and both "A" and "C" Reactor Coolant Pumps (RCP) operating. Approximately 25 minutes after the "A" RCP was started, it tripped automatically due to an electrical ground on the motor. The licensee determined that it would be necessary to cool down and depressurize the RCS to allow the "A" RCP motor repair The initial pla'n was to drain the RCS to a level approximately 40 inches above the loop nozzle centerline to allow removal of the "A" RCP motor and prevent leakage out of the RCS via the RCP shaf Later the evening of June 17, following a review of the RCP design, the licensee determined that it would not be necessary to fully drain the RCS j and the decision was made to maintain a level in the pressurizer of '
approximately 20%., This decision was based on the RCP design which provided a backseat for the shaft to rest, once uncoupled from the motor.
The inspectors later were told that Westinghouse had informed the licensee that the RCP backseat would allow a maximum of one gpm out of the RCS as long as RCS pressure at the pump was less than 15 psig. This information was contained in the maintenance procedure MMP-C-RC-28 but does not appear to have been communicated to the station operator RCS pressure was maintained between 15 to 20 psig during the even ,
The licensee also decided that for added protection, seal injection would be maintained to the "A" RCP at a pressure higher than RCS pressure to ensure any leakage would be into the RCS not out of the system. However at that time the licensee's understanding was that seal injection water entered the RCP above the backseat. Following the event the inspector discovered that based on a RCP technical manual drawing it appeared that the seal injection water entered the RCP below the backseat. The licensne discussed this situation with Westinghouse and confirmed that seal injection water was actually entering the "A" RCP below the backseat.
Therefore with a seal injection pressure of approximately 30 psig, the
"A" RCP seal injection was potentially unseating the shaft and creating the leakage out of the RC ,
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Along with the decision to maintain a level in the pressurizer, the licensee decided not to install the spool pieces and hoses necessary to fill and vent the RCS following maintenance. This decision was based in i part on the elimination of the radiation dose which would be received j during installation of the venting equipment and to minimize the time necessary to restart the unit following the "A" RCP maintenanc The fact. that water level would be maintained in the pressurizer and the RCS ;
was not going to be opened convinced the licensee that venting following 1 maintenance would not be required. However, the unit was depressurized and based on events associated with pressurizer drain, the requirement to vent the vessel head following maintenance was determined to be necessar )
Therefore, following the event, the head was vented per 1-0P-5.5 prior to resterting the uni .The instructions, provided to the operators to place the unit in a condition which would allow the RCP motor maintenance, were to follow 1-0P-3.4 step 4.15, cooldown and depressurize the RCS for the performance of maintenance where a pressurizer bubble would not be maintained and the RCS would not be opened. This procedure did not describe in detail how I the operators would depressurize the pressurizer or the final conditions of the pressurize On the evening of June 17, the operators raised and lowered water level in the pressurizer to cool and depressurize it. Later the following morning the pressurizer was filled solid and cooled using auxiliary spray. Several hours following the fill procedure, the operators initiated action to lower the pressurizer level to 20%. This level reduction was performed with the PORV closed because the operators felt based on vapor space temperature that a steam bubble still remained in the pressurizer. Therefore the pressurizer was drained and allowed to cool aown with the PORV closed and the pressurizer unvente This appears contrary to the intent of 1-0P-3.4, however, as will be discussed in section 9 of this report, it appears that the procedure was inadequat A review of the pressurizer vapor space temperature trend was not possible because that temperature is not logged or trended by the compute However, the data for pressurizer liquid space temperature was available and indicated that the temperature of the liquid in the pressurizer would not support a steam bubble. The temperature of the pressurizer liquid just prior to the drain was approximately 185 degrees F (See Figure 4).
This demonstrates that the pressurizer bubble most likely began to collapse following the initiation of the drain of the pressurizer. Also the motive force for the drain was provided by the Residual Heat Removal
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(RHR) pum Therefore, it was not necessary to have a positive pressure i in the pressurizer to reduce the level to 20%. A low pressure or vacuum could have begun to be established in the pressurizer anytime following or during the drain down. Additionally, during the pressurizer draining ,
! evolution the operators were not required to monitor RVLIS or perform a I mass inventory balance to determine if the volume of letdown was equal to or greater than the change in pressurizer leve .
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Following the pressurizer drain, RCS inventory was maintained by monitoring and maintaining pressurizer level constant. This was performed by adjusting letdown flow which was through the RHR pump back to the Chemical Volume and Control System (CVCS) to match makeup which was via the Volume Control Tank (VCT) through the RCP seal injection line Make up was obtained by maintaining a nitrogen pressure of :pp oximately 30 psig on the VCT. Prior to June 17, when the nitroge , nk1ket was established, a hydrogen blanket had been maintained on the v' . The RCS system was not degassed prior to establishing the nitrogen blanke Since the RCS was not going to be opened the licensee was not required to minimize hydrogen in the plan RCS samples indicated a hydrogen concentration of 6.4cc/k The inspector also reviewed the shift logs for the letdown flowrate and makeup flowrat The operators consistently logged a greater letdown flowrate than makeup flo cate (approximately 20 gpm vs.18-19gpm). This along with the knowledge that the RCS had at least a 2 gpm leak out of the system could have alerted the operators to the loss of RCS inventor However the meter for letdown flowrate was 0 to 150 gpm with the smallest (i.e. the first) mark on the meter being 20 gpm. Therefore the operators could have been mislead into thinking the discrepancy was in the meter accurac Just prior to the pressurizer level manipulation, the "C" RCP was secured and the operators used RHR to cooldown the RCS. Following the securing of the "C" RCP, RCS temperature dropped rapidly. Along with a review of the RHR temperature data, the rapid drop of RCS temperature demonstrated that the core had very little decay hea The operators continued to maintain system status with the RCS temperature relatively constant at 110 degrees F, RCS pressure relatively constant at approximately 20 psig and pressurizer level relatively constant at 20%
during the period between June 18 and June 20. The only major indicators that were changing were RVLIS which was gradually dropping and pressurizer liquid temperature which was also dropping. Either of these instruments could have alerted the operator to a problem. RVLIS would have told the ,
operator directly that vessel level was dropping and pressurizer liquid temperature would have warned an operator who understood the initial conditions of the pressurizer (i.e. hot with a possible steam bubble and the PORVs closed) that a low pressure or vacuum condition was being established in the pressurizer. An additional indication available to the operator would be an inventory balance. None of these indicators were monitored by the operators to back up pressurizer level which was being used by the operator as the sole indicator of RCS inventory. Also based on the apparent stability of the RCS parameters there was no reason for the operator to suspect the indicators they were monitoring.
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+ 5 During the night of June 20, Westinghouse personnel requested operations to reduce the leakage out of the "A" RCP seals. The first attempt to reduce the leakage involved lowering the pressurizer level to approxi-mately 5% to reduce the head of water on the "A" RCP shaft back- sea This was performed without a procedure by increasing letdown which used the RHR pump to provide flow into the CVCS. Apparently unknown to the operators at this time was the condition of the pressurizer which was at a lower pressure than the rest of the RCS, therefore, the effect of the operation of the RHR pump was to actually decrease RCS inventory greater than twice the volume reduced in the pressurize The RVLIS trace (see figure 1) shows a rapid vessel level decrease near the end of the event which is explained by this lowering of the pressurizer leve This RCS level reduction was also verified by the licensee using a mass i inventory balance between the volume of water diverted compared to the volume reduction in the pressurizer from 20% to 5%. The volume diverted ;
was greater than twice the volume change in the pressurize ;.
At this point in time the reduction in RCS inventory was not due to the leakage out of the system but due to a forced pump down via the RHR pump i If the conditions had been right (i.e. a lower starting point in the !
vessel and a higher pressur'zer level) and pressurizer level reduction had
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continued long enough, RHR pump cavitation may have occurre However, based on the low decay heat of the core, the operator's instructions for loss of RHR and the abnormal procedure 1-AP-11 which uses the Low Head Safety Injection (LHSI) pumps to back up RHR, if all RHR is lost, the i total loss of decay heat removal capability for any extended period of time is highly unlikely. Also the licensee never actually came close to lowering vessel level below the top of the loop nozzles as indicated by the RVLIS trace. The inspectors reviewed the logs on RHR motor current, discharge flew, and temperatures and none of these instruments indicated that the RHR pump ever cavitate This reduction in pressurizer level evolution did not cause a reduction in the leakage rate because the leak was coming from the "A" RCP seal injection instead of the RCS. The fact that the leak was not coming from the RCS was not recognized by the licensee. Also, the condition of the ;
pressurizer was not recognized or understood. Therefore, an additional i attempt was made to reduce RCS pressure thereby reducing the leakage by ;
the ' A" RCP seals. This attempt involved the raising of pressurizer level to 50%, opening then closing the PORV and draining the pressurizer back to 20%. This would put the pressurizer into a vacuum conditio There are several problems associated with this and the previous pressurizer draining evolution. Both were performed without procedures and both had the potential of placing the RCS in a worse conditio The second attempt to reduce RCS pressure as described above, started at 0113 on June 21. This attempt was not completed because after the pressurizer level was increased to 50% and the PORV was opened, the PRT went into a vacuum and a reduction in pressurizer level occurred. The operators recognized this as an indication of void formation elsewhere in
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the RC The operators began to look at other indications of RCS i inventory and found RVLIS was indicating approximately 79% vessel leve The operators isolated letdown and continued makeup to the RCS. The licensee management was notified and a decision was made to install the -
reactor vessel head vent spool piece and attach it to the pressurize A total of over 19,000 gallons were added to the RCS to bring the RVLIS- l back to 100% indication and a pressurizer level of 50L The vessel head vent.was opened and pressurizer level dropped to 36%, RVLIS returned to 100L The licensee performed a mass balance of the additions and losses :
.from the RCS:from June 17 to June 21. This mass balance indicated a net-loss of approximately 17,000 gallons from the RCS which is equivalent to the 79% void in the vessel as indicated by RVLIS and an additional 73% of the total steam generator tube volum Following the event' the operators received instructions to monitor RVLIS, vent the vessel head at least once a shift and maintain the pressurizer ;
vented to the PRT via the PORV. This condition was maintained until the
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completion of the "A" RCP motor repair. Following the motor repair RCS pressure was increased to allow jogging the "C" RCP. The operators then vented gases from the reactor vessel head for approximately 30 second The additional makeup to the RCS following the venting was determined by the licensee to be approximately 865 gallons which is equivalent to approximately 5% of the total steam generator tube volume. Therefore the maximum steam generator tube voiding during the event, if RVLIS was an accurate indication of the vessel voids, was 78% of the total tube volum The licensee also evaluated the potential for damage to the PRT, after ,
having been placed in a vacuum. A review of the FSAR indicated that the PRT was designed to withstand a vacuum condition. The PRT was inspected and found to have a leak in a rupture disc. The rupture disc was replaced I prior to.the unit being started u Following the event, the accuracy of the pressurizer level instrument was questioned. There was a concern that with a vacuum in the pressurizer, the level instrument reference leg may have been affected. The licensee filled the reference leg and monitored pressurizer level. The level only dropped approximately one percent indicating that pressurizer level was accurate during the even . NRC Response to the Event The Senior Resident Inspector reported to the station on Sunday evening, June 21, 1987, following the notification by the licensee. The inspector discussed the event with the licensee and verified that the unit had been placed in a safe and stable conditinn. The inspector notified Region Il staff of the event first ',hing Monday morning, June 22. The regional staff requested a conference call with the licensee and following'the call decided to send the Resident Insper%r from the Surry Station and a
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regia ial' inspector from the Operational Programs Section. The regional
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staff also notified the Project Manager in NRR on Monday, Junr2 22, and he participated in the conference cal On Tuesday, June 23, the Resident Inspector from tb Surry Station and the. Region II Inspcctor arrived on site.'
?# On June 24, the Director.cf the Division of Reactor Projects, Luis Reyes, and the Section Chfof in charge of North Aiya, Floyd Cantr, ell, arrived on site to receive a briefing from the licensee c1.the event and other previously planned topics. The Project Managed Leon Engle, from NRR in ,
Washington also reported to the site on June ,TA and attendsd the j licenseeb' briefings. The following Monday, June 29, an additional
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e inspbtor from the 0,;erational Programs Section reported to the station
<- to continue the followup inspection of the eve & Sequence of Events
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l- 6/17/87 0135* RCS Sample Indicates Hydrogen = CR0 Log
.O G.acc/kg 0520 VCT gas space sample indicates Hydrogen = 85%, Nitrogen = 15% CR0 Log !
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'0730 Completed RCS Leak Rate with the following results: Identified leak rate equals 1.254 gra, unidentified equals 0.1304 SR0 Log t158 ' Commenced RCS heatup in preparation for Mode 4 using the "C" RCP. RHR l is Still operatin SR0 Log 1218 Str t 1 RC-P-1A, ("A" RCP) CR0 Log
,. 1242 RCS T'emp 195 degrees F; RCS f .' ' Pressure 320 psig; PZR Temp 420 l
<
degrees F with a steam bubble in Computer l
'the pressurizer j
l 1243 Auto Trip "A" RCP, indication of SR0/CR0 Log 4
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motor ground 1259 Electricians report "A" RCP has a SR0 Log motor ground j l
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1309 Secured RCS'heatup for "A" RCP work SRO Log 1421- Commenced breaking containment vacuum ~CR0 Log 1833- Stopped."C" RCP (Time O for Trend Plots; see figures 1, 2, and 3) CR0 Log RCS. Temp 182 degrees F; RCS Pressure Computer 320 psig 1907 Initiated filling and cooling of PZR CR0 Log 6/18/87 0000 Pressurizer level greater.than 100% Recorder (hot calibration).
0000 Pressurizer level equal to 100% (cold Interview calibration) and PORV open with SR0 0115 .VCT gas space sample indicates
. Oxygen = 0%, Nitrogen = 64.4%,
Hydrogen = 29.8% with a Nitrogen blanket on the VCT CR0 Log 0215 Reduced PZR level to approximately Interview to 20% (cold cal). Closed PORV at with 0600 approximately 80% PZR level.(cold SRO cal). Per the operators, vapor space temperature indicated a steam bubble (NRC comment - Liquid space temperature did not support this)
0420 Completed uncoupling "A" RCP- Maint. Dep Pressurizer level greater 15% (hot l cal) 19% (cold cal) Recorder 0605 Secured "B" Charging Pump, established !
'VCT float via seal injection to all 3 RCPs with a 30 psig Nitrogen overpressure on the VCT CR0 Log 1 6/19/87 0337 Entered action statement on RVLIS j upper range level transmitters "A" and "B". Difference greater than 3% !
(T.S. not applicable until Mode 3) I This was discovered during the performance of 1-PT-44.-7 by an operator. The operator logged 89%
vessel level in the survie11ance !
test CR0 Log
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0455 RCS sample indicated Hydrogen concentration = 6.5cc/kg CR0 Log
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1914 Added 500 grams LIOH to primary (approximately 50 gallons water added CR0 Log 6/20/87 2200 Lowered PZR level to 5-8% in an Interview to attempt to reduce RCS pressure to with CR0 2400 reduce the leakage from the "A" RCP sea (NRC comment - This appears to be the only time in which the loss of RHR was possible.)
6/21/87 0113 Commenced makeup to RCS to raise PZR SR0/CR0 Log level to approximately 50%. The second attempt to reduce leakage by the "A" RCP seals 0130 Cycled PORV; PZR level decreased; PRT pressure decreased. This was the
- first indication recognized by the operators that the pressurizer was in a vacuum end there was a potential for RCS voidin CR0 Log 0112 VCT (RCS) makeup of 19,747.3 gallon to This filled the RCS based on RVLIS 0640 reading of 100%. CR0 Log 0230 Gassed PRT with Nitrogen and cycled PJRVs while continuing to raise PZR leve CR0 Log 0610 Vent installed between Rx head and PZ SR0/CR0 Log 0623 Rx head vented; Pressurizer level dropped approximately 10% to an indicated level of 36% (cold cal). SR0/CR0 Log 0723 VCT (RCS) makeup of 419.8 gallons CR0 Log to 0732 1354 Added 600 grams LI0H to primary CR0 Log 1425 Vented Rx head to PZR via head ven PZR level decreased approximately 1%
on cold cal level. Noted 1% increase in RVLIS full rang SR0/CR0 Log
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-l 1128 3 VCT (RCS) makeups 2340.6 gallons CR0 Log to 1425 1800 Vented Rx head; PZR level dropped approximately 1%; RVLIS went-offscale high to approximately 102%. CR0 Log 1858 Closed HCV-1303A to stop seal leakoff flow from "B" & "C" RCP from leaking out through "A" RCP sea CR0 Log 1828 3 VCT (RCS) makeups of 1275 gallons CR0 Log to 2242 Notes:
1) Prior to 6/17/87, reactor had been shutdown for 60 days for a j refueling outag I 2) Unit remained in Mode 5 during entire even ) RHR remained in service during entire even ! Potential Safety Issues Associated With the Event i The potential for the loss of RHR during the event was reviewed.' The actual vessel level decrease. by-RVLIS indication at the lowest point was still 5.3 feet above the nozzle centerline. However, if the vessel level had dropped. below the top of the nozzle, the surge line for the pressurizer would become uncovered and most likely would have equalized or burped the remaining water in the pressurizer into the RCS. The level reduction in the pressurizer would have initiated several alarms in the control room associated with pressurizer level, alerting the operator to the RCS inventory problem. The operator would have adequate time to initiate make up to prevent cavitation of the RHR pump As discussed in Section 3, the only time at which the RHR pump was in jeopardy was when the operators took action to pump down the pressurizer level on June 20. This pump down also reduced the RCS inventory and if ,
the conditions had been right and the pump down had continued RCS level 1
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-may have been reduced enough to cause cavitation of the RHR pum The inspector had previously reviewed the licensee's action taken in response to a loss of RH Based on these planned actions, the ,
availability of the LHSI pumps to back up the loss of RHR per 1-AP-11 and l the very low decay heat in the core, it appears that the operators had adequate time and equipment necessary to keep the core cooled.
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The potential for the core to beccme uncovered was reviewe The actual vessel level decrease by RVLIS at it's lowest point was'still 8.8 feet above the top of the core. If vessel level had been allowed to drop below the top of the loop nozzle, not only would the water in the pressurizer and the remaining water !n the steam generator tubes most likely burp and flood the core, but it would also provide the operator with indications of a problem with RCS inventory in plenty.of time to initiate the necessary makeu Also if no operator action had taken l place once the RHR pump cavitated and failed, letdown would become greatly {
reduced if not secured, and make up would continue to the RCS refilling ;
the vessel Therefore, there does not appear to be any potential for the
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core to become uncovered due to the actions taken place during this even Based on the plant conditions, Mode 5, RCS temperature 110 degrees F and RCS pressure of 15-20 psig, the Hcensee could have purposely drained the RCS to the levels achieved during the event. This would not have been considered an unsafe condition. However, the problem with this event, <
even though the safety significance appears to be minor, is the fact that the RCS inventory was allowed to slowly decrease over a three day period without the knowledge of the licensee or the operators. and, therefore, should be considered a significant event. The licensee is currently reviewing and performing a human performance evaluation of the event and will be modifying procedures and operator training based on the results of their review. The inspectors will monitor the-licensee's actions taken as a result of the lessons learned from the even . . Contributing Factors or Factors Which Complicated the Event
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There were a number of factors which contributed to or complicated this event. The following will be a discussion of the ones identified by the inspectors:
The initial problem associated with this event was the lack of procedural instruction and licensee understanding of the condition being placed on the unit. 1-0P-3.4 which established the condition for the maintenance war inadequate because the procedure did not describe the conditions that should be established in the pressurizer prior to allowing maintenance to j be performed. This will be addressed later in the Enforcement Section 9 of this repor The licensee also performed several evolutions on the unit without procedures such as the forced reduction in pressurizer level on June 20 and the attempt to place the pressurizer in a vacuum on June 21. These evolutions were not well thought out and did not follow any procedures which might have at least provided initial conditions and precautions to be observed prior to performance. This will also be l discussed in the Enforcement Section 9 of this repor There were no requirements to monitor any additional indicators reflecting ,
RCS inventory such as RVLIS or mass inventory balance between the make up I to and losses from the RC The operators relied entirely upon pressurizer level which because of the vacuum being created in the pressurizer was being artificially maintaine .
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The RVLIS instrumentation would have been the most direct method of telling the operators that a problem existed with the RCS inventory. The operators did not monitor or believe the RVLIS indication for several reason The RVLIS system had just been modified during the present outage and several work request stickers still appeared on the control room display. A system malfunction alarm continued to be annunciated in
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the control room. Neither of these problems affected the operability of the RVLIS ' instrumentation but this had not been properly communicated to the operators. Additionally, RVLIS is capable of displaying several different displays of informatio The majority if not all of the time the heatup and cooldown curves were displayed instead of the RVLIS dat The strip chart associated with RVLIS had the wrong scale paper on it and the ' vessel level decrease was so gradCal it would be impossible to detect a trend in the viewing area of the trend recorder. Finally the operators ,
are not required to monitor RVLIS because Technical Specifications do not require RVLIS to_be operable in Modes 4, 5, and Since the operators had a positive pressurizer level indication and in most cases that. is the best indication of RCS inventory, the operators did not feel the need to monitor RVLIS. If RVLIS were monitored as demonstrated by the performance of 1-PT-44.7 on June 19, where an operator logged a RVLIS reading of 89% vessel level, it most likely would not have been believed over the constant pressurizer level. Another point of confusion, the performance of 1-PT-44.7 was considered unsatisfactory for the upper range because the readings indicated greater than 3% difference, one channel indicated 91% and the other indicated 86%, therefore, the operator declared the RVLIS inoperable as required. The full range instruments were both indicating 89L Logging the cooldown data per 1-0P-3.4 was terminated on June 17, even though-the 71 ant and pressurizer continued to cooldown up until June 2 If the operstor had been required to monitor the cooldown, especially of the pressurizer by logging the data every 30 minutes, the operators might have been alerted to the change in the pressurizer condition Pressurizer vapor space temperature is not required to be monitored or logged in Mode 5. This temperature reduction could have also alerted the
, operator to the loss of the bubble in pressurizer.
l There is no method of monitoring pressurizer pressure in the pressure ranges associated with this event. Therefore, the operator could not use a pressure instrument to verify a positive pressure in the pressurize A review of the R0 and SR0 logs revealed no mention of the evolutions that had taken place on the pressurizer on June 17 and 18. The logs made no mention that the pressurizer contained a steam bubble or that the PORV ,
was closed. Additionally the procedure which the operators were using to
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place the pressurizer in that condition would not have indicated the final condition of the pressurizer. Therefore, there was no documentation which indicated that operators other than the ones involved in the pressurizer drain were made aware of the actual condition of the pressurize '
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'i The operation staff did not understand the origin of the leakage by the
"A" RCP shaft. This resulted in the performance of two unnecessary evolutions ~which could have had adverse affects on the uni . Reactor Vessel Level Instrumentation System (RVLIS) Training The design change installing the original RVLIS was completed in 1982 and TMI action item II.F.2.3.8, Implement Reactor Vessel Level Instruments, i for both units, was closed out in Inspection Report 50-338/85-12 and 50-339/85-12 issued in' mid-1985. However, the original RVLIS was not installed on the training simulator until late-198 The installation of RVLIS on the simulator was also never validated to ensure it accurately reflected the operation of the RVLIS in the control room. Therefore, ifcensee training staff members involved with simulator training stated that the RVLIS on the simulator could not be relied upon for accurate dat The licensee also told the inspectors that during training on Revision 1, Emergency Procedures (EP), conducted early-1987, operators were - told that the system was providing unreliable data. Because instructors considered the data provided from RVLIS on the simulator as unreliable and the fact that it was not installed, therefore, not used in
' training until late-1986, there was the potential for conditioning the operators not to rely on RVLIS. This conditioning of the operators could have contributed to the lack of response and use of RVLIS during the RCS vacuum proble Classroom training on the newly installed RVLIS in the control room was given by Westinghouse in mid-1987 to the operations personnel. The
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inspectors reviewed the lesson material that was given to the students and determined that it appeared to adequately cover the operation and installation of the new system. The inspectors also reviewec, class -
attendance records to determine if all operation personnel had attended the training. The inspectors determined that three shift and several non-shift licensed personnel had not received the classroom trainin Due to the nature of the training and in light of current problems with the use of RVLIS at the facility, this training should be provided promptly to all operational personne The inspectors interviewed training personnel associated with improvements to the simulator and was informed that the modification of RVLIS on the simulator is currently in progress and will be completed in the near future. Completion of this modification to the simulator should include the validation of the instrumentation and then the full utilization in future simulator training sessions. This will improve the confidence of operations personnel in the use of the new RVLI . Enforcement The most significant aspects of this event involve allowing the unit to be placed into a condition that was not fully evaluated or understood by the
,
licensee and that voiding in the vessel head and steam generator tubes
! occurred over a three-day period without the knowledge of the operator This existed due to poor planning and inadequate procedures provided to
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the operators and mechanic .
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Technical Specification 6.8.1.a requires written procedures be established, implemented and maintained covering the areas associated with filling, draining, venting, startup,- shutdown and changing modes of the RCS and maintenance relating to repairs of the RCP Operating Procedure (0P) 1-0P-3.4, Unit Shutdown from Cold Shutdown (Mode 5) <200 degrees Fahrenheit to Cold Shutdown (Mode 5) <140 degrees Fahrenheif and K 0.95, was the procedure used by the operators to place the unit Tbft7<le condition which eventually resulted in the inadvertent voiding of the vessel head and steam generator tubes. This procedure was inadequate in that it did not provide detailed instructions on how to depressurize the pressurizer or the final conditions of the pressurizer. The step covering this evolution simply stated "If the RCS is to be depressurized but not opened, then perform steps 4.24 thru 4.32 of this procedure, then go to 1-0P-1.2 when maintenance is completed. N/A all remaining steps of this procedure". Step 4.27 of 1-0P-3.4 states
" Secure the pressurizer heaters". Step 4.28 of 1-0P-3.4 states
"Depressurize the reactor coolant system by raising and lowering pressurizer lev.el, by use of auxiliary spray and cycling of the pressurizer power operated relief valves (PORVS)."
Steps 4.27 and 4.28 are the only steps which provide the operators instructions on how to depressurize the pressurizer and what condition to leave it i These steps imply that the pressurizer should be depressurized without a steam bubble but do not specifically state tha Instead, on June 17, the operators using step 4.28 actually drained the pressurizer with a steam bubble still remaining (i.e. not fully s depressurized) and unvente This appears to be contrary to the intent of the procedure 1-0P-3.4, but since the procedure was not specific, it is considered inadequate. The inadequacy of 1-0P-3.4 is identified as the first example of violation (338/87-21-01).
An additional confusing point involves 1-0P-1.2 which was supposed to be performed following the maintenance as stated above. This OP has an initial condition of a steam bubble in the pressurizer implying that upon exiting 1-0P-3.4 there would still be a steam bubble. The licensee has reviewed 1-0P-1.2 and changed the procedure to no longer require a steam 1 bubble to be an initial condition.
( As discussed earlier, on June 20 and 21, the licensee attempted to perform i two evolutions on unit 1 in an attempt to reduce RCS leakage out of the
"A" RCP. Since the conditions placed on the unit were not familiar to the operators, otherwise routine evolutions such as lowering pressurizer level can not be considered as routine evolutions and therefore they should require procedures. However both of these evolutions were performed without procedures and because the origin of the RCS leakage
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was. not understood by.the licensee, neither would have had any affect on leakage reduction. ' Additionally because these evolutions, reducing pressurizer level and drawing a vacuum in. the pressurizer, were not reviewed properly which would have happened if they had been
, proceduralized,. both evolutions had the potential for adversely
'
' affecting the unit without accomplishing their their intended goa .The performance of the reduction in pressurizer level on June 20 without a procedure, which resulted in additional voiding of the vessel i identified as the second example of violation (338/87-21-01). The intended performance of drawing a vacuum in the pressurizer on June 21 without a . procedure; is identified as the third example of violation
.(338/87-21-01).
Maintenance procedure MMP-C-RC-28, Reactor Coolant Pump Coupling Disassembly / Reassembly, used during the repairs to the "A" RCP in June 1987 appears to be inadeqtate for the following reasons: There'is no action' statement in the procedure directing the operators to maintain the RCS at 15 PSIG to minimize the amount of leakage from a disassembled RCP. The operators are required to not exceed 15 PSIG by step 5.4.a while lowering the shaft to minimize RCS leakage, however, no guidance is given to the operator on maintaining.15 PSIG while the' pump is disconnected. A caution preceding step 7.1 that the maximum expected leak rate from a backseated RCP is 1 GPM with the RCS at 15 PSIG, however, this.is caution and implies no action on the operators part to maintain those condition There is no guidance provided for the use of seal injection when the procedure is used without the RCS being drained. Because this condition can occur and the effect of seal injection on a 1 disassembled RCP directly effects the amount of leakage from the RCP, 1 guidance should be included in the procedure, The steps for the alignment of the RCP and motor are not included in i
'
the procedure The procedure is used to disassemble and reassemble the RCP coupling and prior to reassembling alignment of the coupling .
is needed, those alignment steps should be included in the procedur ! There is no statement concerning the minimizing of RCS leakage when ,
the pump internals are raised from their backseated position. If the procedure states that the operators shall not exceed 15 PSIG when lowering the pump internals, the same direction should be required when the pump is being raised as an increase in the expected ,
leakage rate is just as likel j
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These four exemples of the inadequacy of MMP-C-RC-28 listed above are identified as the fourth example of Violation (338/87-21-01).
10 CFR 50.59 states in part that the licensee may conduct tests or experiments not described in the Final Safety Analysis Report (FSAR)
without prior Commission approval if the licensee determines the test or experiment does not involve a change to the Technical Specification or
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an unreviewed safety questio The licensee must maintain records of these tests or experiments including a copy of the written safety evaluation which provides the basis for the determination that the test or experiment does not involve an unreviewed safety questio Contrary to the above on June 21, 1987, the licensee conducted an evolution with the intent of drawing a vacuum in the pressurizer, in an attempt to the reduce RCS leakage. This evolution is not described in the FSAR and is clearly not a routine evolution. Because the purpose of the evolution was an attempt to change a plant parameter with a nonroutine plant manipulation, it is considered a test or experiment. Based on the above and the fact the licensee did not perform a 10 CFR 50.59 safety evaluation this is identified as a violation (338/87-21-02).
2 Conclusions As shown in Figure 1, the reactor vessel level as indicated by RVLIS started to decrease following the "C" RCP being secured. Figure 2 shows that RCS temperature also dropped rapidly at the same time indicating that the initial vessel level decrease to be caused by a shrink in RCS inventory due to the reduction in temperature and reduction in pressure in the vessel head which would also allow gases to come out of solutio Several hours following the "C" RCP being secured as shown on Figure 2, the pressurizer level was reduced. During this level reduction, Figures 1 and 2 show that RVLIS continues to drop and the slope of the vessel level decrease does not change until the pressurizer level decrease is secure This indicates that the forced reduction of pressurizer level using the RHR pump was also reducing vessel level. This was probably as a result of the pressure reduction in the pressurizer as compared to the pressures in the vessel head and top of the steam generator tube After the securing of the reduction in pressurizer level on June 18, RVLIS indicates that the vessel level slowly decreased until June 20 when pressurizer level was again decreased. This slow level decrease was due to RCS make up not being equal to the letdown plus the leakage out of the RC Also, during this timeframe, the pressurizer liquid space temperature was dropping as indicated by Figure 4. This temperature reduction in an unvented pressurizer indicates a low pressure or vacuum condition was being formed in the pressurizer. This pressure decrease in the pressurizer continued to develop a Delta P between the pressurizer and the vessel head and steam generator tubes allowing the pressurizer level to remain constant as indicated by Figure 2 and the level in the vessel and steam generator tubes to decreas As the pressures equalized (i.e. reduced) in the vessel head and steam generator tube area, low pressure vapor was probably formed as well as gases were allowed to come out of solution filling the voids being create . __ - _ _ __ _ _ _______ _ _ - - - _ ___ _ _ - _ _ _ _ _
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On June 20, when the pressurizer level was again reduced using the RHR pump, RVLIS shows a greater reduction in reactor vessel level. This indicates that the forced reduction in pressurizer level also reduced the levels in the vessel head and steam generator tubes. Figure 5 shows the relative elevations of the pressurizer, vessel and steam generator RVLIS did not indicate an increase until the pressurizer level began to increase on June 21, 1987. The licensee, once recognizing the possible void formation in the RCS, continued to makeup to the RCS until RVLIS indicated 100L The root cause of this situation was the inadequate evaluation of the plant condition established for the maintenance of the "A" RC Contributing to the problem were inadequate procedures, the failure of the operators to use indications other than pressurizer level to verify RCS inventory, failure of the ifcensee to quantify and understand the source of the RCS leakage and the failure of the operators to understand and evaluate the condition of the pressurizer.
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