Insp Repts 50-369/85-06 & 50-370/85-06 on 850120-0320. Noncompliance Noted:Inadequate Separation Criteria, Inadequate Diesel Generator Surveillance Interval & Failure to Follow Procedures & to Take Prompt Corrective ActionML20133H019 |
Person / Time |
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Site: |
Mcguire, McGuire, 05000120 |
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Issue date: |
06/21/1985 |
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From: |
Dance H, William Orders, Pierson R, Skinner P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
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To: |
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Shared Package |
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ML20133H000 |
List: |
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References |
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50-369-85-06, 50-369-85-6, 50-370-85-06, 50-370-85-6, NUDOCS 8508090158 |
Download: ML20133H019 (16) |
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Category:INSPECTION REPORT
MONTHYEARIR 05000369/19990061999-10-0404 October 1999 Insp Repts 50-369/99-06 & 50-370/99-06 on 990801-0911. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000369/19990051999-08-26026 August 1999 Insp Repts 50-369/99-05 & 50-370/99-05 on 990620-0731.Two Violations Noted Being Treated as Ncv.Major Areas Inspected: Operations,Maint,Engineering & Plant Support IR 05000369/19990041999-07-13013 July 1999 Insp Repts 50-369/99-04 & 50-370/99-04 on 990509-0619.Four Violations of NRC Requirements Occurred & Being Treated as Ncvs.Major Areas Inspected:Aspects of Licensee Operations, Maint,Engineering & Plant Support IR 05000369/19990101999-06-16016 June 1999 Insp Repts 50-369/99-10 & 50-370/99-10 on 990322-26.No Violations Noted.Major Areas Inspected:Aspect of Licensee Health Physics Activities During Unit 2 Refueling Outage IR 05000369/19990031999-06-0202 June 1999 Insp Repts 50-369/99-03 & 50-370/99-03 on 990328-0508. Non-cited Violations Noted.Major Areas Inspected:Operations, Maintenance,Engineering & Plant Support IR 05000369/19990021999-04-23023 April 1999 Insp Repts 50-369/99-02 & 50-370/99-02 on 990214-0327.No Violations Noted.Major Areas Inspected:Licensee Operations, Maint,Engineering & Plant Support IR 05000369/19990011999-03-10010 March 1999 Insp Repts 50-369/99-01 & 50-370/99-01 on 990103-0213.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000369/19980101998-12-18018 December 1998 Insp Repts 50-369/98-10 & 50-370/98-10 on 981004-1121.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000369/19980091998-10-30030 October 1998 Insp Repts 50-369/98-09 & 50-370/98-09 on 980823-1003.No Violations Noted.Major Areas Inspected:Aspects of Licensee Operations,Maint,Engineering & Plant Support IR 05000369/19980081998-09-21021 September 1998 Insp Repts 50-369/98-08 & 50-370/98-08 on 980712-0822.No Violations Noted.Major Areas Inspected:Aspects of Licensee Operations,Maint,Engineering & Plant Support IR 05000369/19980111998-08-27027 August 1998 Insp Repts 50-369/98-11 & 50-370/98-11 on 980601-26 & 0805-07.No Violations Noted.Major Areas Inspected:Maint & Engineering Programs.Rept Reviewed Maintenance,Surveillance & Matl Condition of Mcquire,Unit 1 Ice Condenser System IR 05000369/19980071998-08-0707 August 1998 Insp Rept 50-369/98-07 & 50-370/98-07 on 980531-0711. Violations Noted.Major Areas Inspected:Licensee Operations, Maint,Engineering & Plant Support IR 05000369/19980061998-06-25025 June 1998 Insp Repts 50-369/98-06 & 50-370/98-06 on 980419-0530.No Violations Noted.Major Areas Inspected:Aspects of Licensee Operations,Maint,Engineering & Plant Support IR 05000369/19980041998-06-0404 June 1998 Insp Repts 50-369/98-04 & 50-370/98-04 on 980413-24. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000369/19980031998-05-18018 May 1998 Insp Repts 50-369/98-03 & 50-370/98-03 on 980308-0418.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support ML20216H6171998-04-0606 April 1998 Insp Repts 50-369/98-02 & 50-370/98-02 on 980125-0307. Violations Noted.Major Areas Inspected:Operations, Maintenance,Engineering & Plant Support IR 05000369/19970201998-02-23023 February 1998 Insp Repts 50-369/97-20 & 50-370/97-20 on 971214-980124. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support,Including Review of Radiological Protection Practices & Plant Physical Security IR 05000369/19980011998-02-17017 February 1998 Partially Withheld Insp Repts 50-369/98-01 & 50-370/98-01 on 980114-15 (Ref 10CFR2.790).No Violations Noted.Major Areas Inspected:Plant Support,Including Malevolent Use of Vehicles at Plant & Vehicle Barrier Sys ML20198P3771998-01-12012 January 1998 Insp Repts 50-369/97-18 & 50-370/97-18 on 971102-1213. Violations Noted.Major Areas Inspected:Integrated Insp Included Aspects of Licensee Operation,Maint,Engineering & Plant Support ML20199B1641998-01-0505 January 1998 Insp Repts 50-369/97-19 & 50-370/97-19 on 971205-06. Violations Noted.Major Areas Inspected:Licensee Response to 971202 Event Involving Seal Damage Event at Four Air Lock Doors of Unit 2 Containment Bldg IR 05000369/19970171997-12-0101 December 1997 Insp Repts 50-369/97-17 & 50-370/97-17 on 970921-1101.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000369/19970151997-10-20020 October 1997 Insp Repts 50-369/97-15 & 50-370/97-15 on 970810-0920. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000369/19970121997-09-22022 September 1997 Insp Repts 50-369/97-12 & 50-370/97-12 on 970804-08.No Violations Noted.Major Areas Inspected:Observation & Evaluation of Biennial Emergency Preparedness Exercise ML20211E7981997-09-16016 September 1997 Insp Repts 50-369/97-16 & 50-370/97-16 on 970712-0827. Violations Being Considered for Escalated Eas.Major Areas Inspected:Review of Aspects of Problem Involving Inoperable Unit 2 Ice Condenser Lower Inlet Doors IR 05000369/19970101997-09-0808 September 1997 Insp Repts 50-369/97-10 & 50-370/97-10 on 970629-0809.No Violations Noted.Major Areas Inspected:Operations, Engineering,Maint & Plant Support IR 05000369/19970131997-08-22022 August 1997 Insp Repts 50-369/97-13 & 50-370/97-13 on 970721-24.No Violations Noted.Major Areas Inspected:Licensees Program for Compensatory Measures for Degraded Security Equipment ML20149L5751997-07-28028 July 1997 Insp Repts 50-369/97-09 & 50-370/97-09 on 970518-0628. Violations Noted.Major Areas Inspected:Aspects of Licensee Operations,Engineering,Maint & Plant Support ML20149G6881997-06-16016 June 1997 Insp Repts 50-369/97-08 & 50-370/97-08 on 970406-0517. Violations Noted.Major Areas Inspected:Licensee Operations, Engineering,Maint & Plant Support IR 05000369/19970071997-06-0202 June 1997 Insp Rept 50-369/97-07 on 970406-0503.Violations Noted.Major Areas Inspected:Sg Replacement Project Activities in Areas of Maint & Engineering IR 05000369/19970041997-05-0505 May 1997 Insp Repts 50-369/97-04 & 50-370/97-04 on 970223-0405. Violations Noted.Major Areas Inspected:Operations, Maintenance,Engineering & Plant Support IR 05000369/19970051997-04-28028 April 1997 Insp Rept 50-369/97-05 on 970309-0405.No Violations Noted. Major Areas Inspected:Maint,Engineering & Plant Support IR 05000369/19970031997-04-0101 April 1997 Insp Rept 50-369/97-03 on 970125-0308.No Violations Noted. Major Areas Inspected:Sg Replacement Project Preoutage Activities in Areas of Maint,Engineering & Plant Support ML20137V1531997-03-24024 March 1997 Insp Repts 50-369/97-01 & 50-370/97-01 on 970112-0222. Violations Noted.Major Areas Inspected:Operations, Maintenance,Engineering & Plant Support IR 05000369/19970021997-03-0505 March 1997 Insp Repts 50-369/97-02 & 50-370/97-02 on 970203-06.No Violations Noted.Major Area Inspected:Licensee Plant Support ML20134L1461997-02-10010 February 1997 Insp Repts 50-369/96-11 & 50-370/96-11 on 961201-970111. No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000369/19960101996-12-30030 December 1996 Insp Repts 50-369/96-10 & 50-370/96-10 on 961020-1130.No Violations Noted.Major Areas Inspected:Operations, Engineering,Maint & Plant Support IR 05000369/19960091996-11-27027 November 1996 Insp Repts 50-369/96-09 & 50-370/96-09 on 961104-08.No Violations Noted.Major Areas Inspected:Safeguards Insp Included Aspects of Licensee Plant Support IR 05000369/19960081996-11-15015 November 1996 Insp Repts 50-369/96-08 & 50-370/96-08 on 960908-1019. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support ML20128H6951996-10-0202 October 1996 Insp Repts 50-369/96-07 & 50-370/96-07 on 960728-0907. Violations Noted.Major Areas Inspected:Licensee Operations, Engineering Maint & Plant Support IR 05000369/19940291994-12-28028 December 1994 Insp Repts 50-369/94-29 & 50-370/94-29 on 941205-09.No Violations Noted.Major Areas Inspected:Util Physical Security Program for Np Reactors Including Protection of Safeguards Info,Access Controls & Alarm Stations IR 05000369/19930291994-01-11011 January 1994 Insp Repts 50-369/93-29 & 50-370/93-29 on 931121-1218.No Violations Noted.Major Areas Inspected:Plant Operations, Surveillance Testing,Maintenance Observations & Cold Weather Preparation IR 05000369/19930301994-01-0707 January 1994 Insp Repts 50-369/93-30 & 50-370/93-30 on 931213-17.No Violations Noted.Major Areas Inspected:Design Changes & Plant Mods,Engineering & Technical Support Activities & follow-up on Previously Identified Insp Findings IR 05000269/19930321994-01-0606 January 1994 Insp Repts 50-269/93-32,50-270/93-32,50-287/93-32, 50-369/93-31,50-370/93-31,50-413/93-35 & 50-414,respectively on 931213-17.Violations Noted.Major Areas Inpected:Licensee Safeguards Info Program to folow-up on Licensee Repts IR 05000369/19930281993-12-29029 December 1993 Partially Withheld Insp Repts 50-369/93-28 & 50-370/93-28 on 931129-1202 (Ref 10CFR73.21).Violation Not Subj to Enforcement Action.Major Areas Inspected:Physical Security Program IR 05000369/19930241993-12-16016 December 1993 Insp Repts 50-369/93-24 & 50-370/93-24 on 931017-1120. Violations Noted.Major Areas Inspected:Plant Operations, Engineered Safety Features Sys Walkdown,Surveillance Testing & Maintenance IR 05000369/19930261993-12-15015 December 1993 Insp Repts 50-369/93-26 & 50-370/93-26 on 931115-19.No Violations Noted.Major Areas Inspected:Engineering & Technical Support of Plant Modifications,Design Changes & Plant Operations IR 05000369/19930251993-12-0202 December 1993 Partially Withheld Insp Repts 50-369/93-25 & 50-370/93-25 on 931101-04 (Ref 10CFR73.21).Noncited Violations Noted.Major Areas Inspected:Licensee Physical Security Program for Power Reactors IR 05000369/19930211993-11-10010 November 1993 Insp Repts 50-369/93-21 & 50-370/93-21 on 931018-21.No Violations Noted.Major Areas Inspected:Simulator Control Room,Tsc,Osc & EOF IR 05000369/19930221993-11-0909 November 1993 Insp Repts 50-369/93-22 & 50-370/93-22 on Stated Date. Violations Noted.Major Areas Inspected:Plant Operations, Surveillance Testing,Maintenance Observations,Ler & Followup on Previous Insp Findings IR 05000369/19930181993-10-19019 October 1993 Insp Repts 50-369/93-18 & 50-370/93-18 on 930822-0925. Violations Noted.Major Areas Inspected:Plant Operations, Surveillance Testing,Maint Observations,Plant Mods & Emergency Preparedness Training Exercise 1999-08-26
[Table view] Category:NRC-GENERATED
MONTHYEARIR 05000369/19990061999-10-0404 October 1999 Insp Repts 50-369/99-06 & 50-370/99-06 on 990801-0911. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000369/19990051999-08-26026 August 1999 Insp Repts 50-369/99-05 & 50-370/99-05 on 990620-0731.Two Violations Noted Being Treated as Ncv.Major Areas Inspected: Operations,Maint,Engineering & Plant Support IR 05000369/19990041999-07-13013 July 1999 Insp Repts 50-369/99-04 & 50-370/99-04 on 990509-0619.Four Violations of NRC Requirements Occurred & Being Treated as Ncvs.Major Areas Inspected:Aspects of Licensee Operations, Maint,Engineering & Plant Support IR 05000369/19990101999-06-16016 June 1999 Insp Repts 50-369/99-10 & 50-370/99-10 on 990322-26.No Violations Noted.Major Areas Inspected:Aspect of Licensee Health Physics Activities During Unit 2 Refueling Outage IR 05000369/19990031999-06-0202 June 1999 Insp Repts 50-369/99-03 & 50-370/99-03 on 990328-0508. Non-cited Violations Noted.Major Areas Inspected:Operations, Maintenance,Engineering & Plant Support IR 05000369/19990021999-04-23023 April 1999 Insp Repts 50-369/99-02 & 50-370/99-02 on 990214-0327.No Violations Noted.Major Areas Inspected:Licensee Operations, Maint,Engineering & Plant Support IR 05000369/19990011999-03-10010 March 1999 Insp Repts 50-369/99-01 & 50-370/99-01 on 990103-0213.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000369/19980101998-12-18018 December 1998 Insp Repts 50-369/98-10 & 50-370/98-10 on 981004-1121.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000369/19980091998-10-30030 October 1998 Insp Repts 50-369/98-09 & 50-370/98-09 on 980823-1003.No Violations Noted.Major Areas Inspected:Aspects of Licensee Operations,Maint,Engineering & Plant Support IR 05000369/19980081998-09-21021 September 1998 Insp Repts 50-369/98-08 & 50-370/98-08 on 980712-0822.No Violations Noted.Major Areas Inspected:Aspects of Licensee Operations,Maint,Engineering & Plant Support IR 05000369/19980111998-08-27027 August 1998 Insp Repts 50-369/98-11 & 50-370/98-11 on 980601-26 & 0805-07.No Violations Noted.Major Areas Inspected:Maint & Engineering Programs.Rept Reviewed Maintenance,Surveillance & Matl Condition of Mcquire,Unit 1 Ice Condenser System IR 05000369/19980071998-08-0707 August 1998 Insp Rept 50-369/98-07 & 50-370/98-07 on 980531-0711. Violations Noted.Major Areas Inspected:Licensee Operations, Maint,Engineering & Plant Support IR 05000369/19980061998-06-25025 June 1998 Insp Repts 50-369/98-06 & 50-370/98-06 on 980419-0530.No Violations Noted.Major Areas Inspected:Aspects of Licensee Operations,Maint,Engineering & Plant Support IR 05000369/19980041998-06-0404 June 1998 Insp Repts 50-369/98-04 & 50-370/98-04 on 980413-24. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000369/19980031998-05-18018 May 1998 Insp Repts 50-369/98-03 & 50-370/98-03 on 980308-0418.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support ML20216H6171998-04-0606 April 1998 Insp Repts 50-369/98-02 & 50-370/98-02 on 980125-0307. Violations Noted.Major Areas Inspected:Operations, Maintenance,Engineering & Plant Support IR 05000369/19970201998-02-23023 February 1998 Insp Repts 50-369/97-20 & 50-370/97-20 on 971214-980124. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support,Including Review of Radiological Protection Practices & Plant Physical Security IR 05000369/19980011998-02-17017 February 1998 Partially Withheld Insp Repts 50-369/98-01 & 50-370/98-01 on 980114-15 (Ref 10CFR2.790).No Violations Noted.Major Areas Inspected:Plant Support,Including Malevolent Use of Vehicles at Plant & Vehicle Barrier Sys ML20198P3771998-01-12012 January 1998 Insp Repts 50-369/97-18 & 50-370/97-18 on 971102-1213. Violations Noted.Major Areas Inspected:Integrated Insp Included Aspects of Licensee Operation,Maint,Engineering & Plant Support ML20199B1641998-01-0505 January 1998 Insp Repts 50-369/97-19 & 50-370/97-19 on 971205-06. Violations Noted.Major Areas Inspected:Licensee Response to 971202 Event Involving Seal Damage Event at Four Air Lock Doors of Unit 2 Containment Bldg IR 05000369/19970171997-12-0101 December 1997 Insp Repts 50-369/97-17 & 50-370/97-17 on 970921-1101.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000369/19970151997-10-20020 October 1997 Insp Repts 50-369/97-15 & 50-370/97-15 on 970810-0920. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000369/19970121997-09-22022 September 1997 Insp Repts 50-369/97-12 & 50-370/97-12 on 970804-08.No Violations Noted.Major Areas Inspected:Observation & Evaluation of Biennial Emergency Preparedness Exercise ML20211E7981997-09-16016 September 1997 Insp Repts 50-369/97-16 & 50-370/97-16 on 970712-0827. Violations Being Considered for Escalated Eas.Major Areas Inspected:Review of Aspects of Problem Involving Inoperable Unit 2 Ice Condenser Lower Inlet Doors IR 05000369/19970101997-09-0808 September 1997 Insp Repts 50-369/97-10 & 50-370/97-10 on 970629-0809.No Violations Noted.Major Areas Inspected:Operations, Engineering,Maint & Plant Support IR 05000369/19970131997-08-22022 August 1997 Insp Repts 50-369/97-13 & 50-370/97-13 on 970721-24.No Violations Noted.Major Areas Inspected:Licensees Program for Compensatory Measures for Degraded Security Equipment ML20149L5751997-07-28028 July 1997 Insp Repts 50-369/97-09 & 50-370/97-09 on 970518-0628. Violations Noted.Major Areas Inspected:Aspects of Licensee Operations,Engineering,Maint & Plant Support ML20149G6881997-06-16016 June 1997 Insp Repts 50-369/97-08 & 50-370/97-08 on 970406-0517. Violations Noted.Major Areas Inspected:Licensee Operations, Engineering,Maint & Plant Support IR 05000369/19970071997-06-0202 June 1997 Insp Rept 50-369/97-07 on 970406-0503.Violations Noted.Major Areas Inspected:Sg Replacement Project Activities in Areas of Maint & Engineering IR 05000369/19970041997-05-0505 May 1997 Insp Repts 50-369/97-04 & 50-370/97-04 on 970223-0405. Violations Noted.Major Areas Inspected:Operations, Maintenance,Engineering & Plant Support IR 05000369/19970051997-04-28028 April 1997 Insp Rept 50-369/97-05 on 970309-0405.No Violations Noted. Major Areas Inspected:Maint,Engineering & Plant Support IR 05000369/19970031997-04-0101 April 1997 Insp Rept 50-369/97-03 on 970125-0308.No Violations Noted. Major Areas Inspected:Sg Replacement Project Preoutage Activities in Areas of Maint,Engineering & Plant Support ML20137V1531997-03-24024 March 1997 Insp Repts 50-369/97-01 & 50-370/97-01 on 970112-0222. Violations Noted.Major Areas Inspected:Operations, Maintenance,Engineering & Plant Support IR 05000369/19970021997-03-0505 March 1997 Insp Repts 50-369/97-02 & 50-370/97-02 on 970203-06.No Violations Noted.Major Area Inspected:Licensee Plant Support ML20134L1461997-02-10010 February 1997 Insp Repts 50-369/96-11 & 50-370/96-11 on 961201-970111. No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000369/19960101996-12-30030 December 1996 Insp Repts 50-369/96-10 & 50-370/96-10 on 961020-1130.No Violations Noted.Major Areas Inspected:Operations, Engineering,Maint & Plant Support IR 05000369/19960091996-11-27027 November 1996 Insp Repts 50-369/96-09 & 50-370/96-09 on 961104-08.No Violations Noted.Major Areas Inspected:Safeguards Insp Included Aspects of Licensee Plant Support IR 05000369/19960081996-11-15015 November 1996 Insp Repts 50-369/96-08 & 50-370/96-08 on 960908-1019. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support ML20128H6951996-10-0202 October 1996 Insp Repts 50-369/96-07 & 50-370/96-07 on 960728-0907. Violations Noted.Major Areas Inspected:Licensee Operations, Engineering Maint & Plant Support IR 05000369/19940291994-12-28028 December 1994 Insp Repts 50-369/94-29 & 50-370/94-29 on 941205-09.No Violations Noted.Major Areas Inspected:Util Physical Security Program for Np Reactors Including Protection of Safeguards Info,Access Controls & Alarm Stations IR 05000369/19930291994-01-11011 January 1994 Insp Repts 50-369/93-29 & 50-370/93-29 on 931121-1218.No Violations Noted.Major Areas Inspected:Plant Operations, Surveillance Testing,Maintenance Observations & Cold Weather Preparation IR 05000369/19930301994-01-0707 January 1994 Insp Repts 50-369/93-30 & 50-370/93-30 on 931213-17.No Violations Noted.Major Areas Inspected:Design Changes & Plant Mods,Engineering & Technical Support Activities & follow-up on Previously Identified Insp Findings IR 05000269/19930321994-01-0606 January 1994 Insp Repts 50-269/93-32,50-270/93-32,50-287/93-32, 50-369/93-31,50-370/93-31,50-413/93-35 & 50-414,respectively on 931213-17.Violations Noted.Major Areas Inpected:Licensee Safeguards Info Program to folow-up on Licensee Repts IR 05000369/19930281993-12-29029 December 1993 Partially Withheld Insp Repts 50-369/93-28 & 50-370/93-28 on 931129-1202 (Ref 10CFR73.21).Violation Not Subj to Enforcement Action.Major Areas Inspected:Physical Security Program IR 05000369/19930241993-12-16016 December 1993 Insp Repts 50-369/93-24 & 50-370/93-24 on 931017-1120. Violations Noted.Major Areas Inspected:Plant Operations, Engineered Safety Features Sys Walkdown,Surveillance Testing & Maintenance IR 05000369/19930261993-12-15015 December 1993 Insp Repts 50-369/93-26 & 50-370/93-26 on 931115-19.No Violations Noted.Major Areas Inspected:Engineering & Technical Support of Plant Modifications,Design Changes & Plant Operations IR 05000369/19930251993-12-0202 December 1993 Partially Withheld Insp Repts 50-369/93-25 & 50-370/93-25 on 931101-04 (Ref 10CFR73.21).Noncited Violations Noted.Major Areas Inspected:Licensee Physical Security Program for Power Reactors IR 05000369/19930211993-11-10010 November 1993 Insp Repts 50-369/93-21 & 50-370/93-21 on 931018-21.No Violations Noted.Major Areas Inspected:Simulator Control Room,Tsc,Osc & EOF IR 05000369/19930221993-11-0909 November 1993 Insp Repts 50-369/93-22 & 50-370/93-22 on Stated Date. Violations Noted.Major Areas Inspected:Plant Operations, Surveillance Testing,Maintenance Observations,Ler & Followup on Previous Insp Findings IR 05000369/19930181993-10-19019 October 1993 Insp Repts 50-369/93-18 & 50-370/93-18 on 930822-0925. Violations Noted.Major Areas Inspected:Plant Operations, Surveillance Testing,Maint Observations,Plant Mods & Emergency Preparedness Training Exercise 1999-08-26
[Table view] Category:INSPECTION REPORT
MONTHYEARIR 05000369/19990061999-10-0404 October 1999 Insp Repts 50-369/99-06 & 50-370/99-06 on 990801-0911. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000369/19990051999-08-26026 August 1999 Insp Repts 50-369/99-05 & 50-370/99-05 on 990620-0731.Two Violations Noted Being Treated as Ncv.Major Areas Inspected: Operations,Maint,Engineering & Plant Support IR 05000369/19990041999-07-13013 July 1999 Insp Repts 50-369/99-04 & 50-370/99-04 on 990509-0619.Four Violations of NRC Requirements Occurred & Being Treated as Ncvs.Major Areas Inspected:Aspects of Licensee Operations, Maint,Engineering & Plant Support IR 05000369/19990101999-06-16016 June 1999 Insp Repts 50-369/99-10 & 50-370/99-10 on 990322-26.No Violations Noted.Major Areas Inspected:Aspect of Licensee Health Physics Activities During Unit 2 Refueling Outage IR 05000369/19990031999-06-0202 June 1999 Insp Repts 50-369/99-03 & 50-370/99-03 on 990328-0508. Non-cited Violations Noted.Major Areas Inspected:Operations, Maintenance,Engineering & Plant Support IR 05000369/19990021999-04-23023 April 1999 Insp Repts 50-369/99-02 & 50-370/99-02 on 990214-0327.No Violations Noted.Major Areas Inspected:Licensee Operations, Maint,Engineering & Plant Support IR 05000369/19990011999-03-10010 March 1999 Insp Repts 50-369/99-01 & 50-370/99-01 on 990103-0213.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000369/19980101998-12-18018 December 1998 Insp Repts 50-369/98-10 & 50-370/98-10 on 981004-1121.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000369/19980091998-10-30030 October 1998 Insp Repts 50-369/98-09 & 50-370/98-09 on 980823-1003.No Violations Noted.Major Areas Inspected:Aspects of Licensee Operations,Maint,Engineering & Plant Support IR 05000369/19980081998-09-21021 September 1998 Insp Repts 50-369/98-08 & 50-370/98-08 on 980712-0822.No Violations Noted.Major Areas Inspected:Aspects of Licensee Operations,Maint,Engineering & Plant Support IR 05000369/19980111998-08-27027 August 1998 Insp Repts 50-369/98-11 & 50-370/98-11 on 980601-26 & 0805-07.No Violations Noted.Major Areas Inspected:Maint & Engineering Programs.Rept Reviewed Maintenance,Surveillance & Matl Condition of Mcquire,Unit 1 Ice Condenser System IR 05000369/19980071998-08-0707 August 1998 Insp Rept 50-369/98-07 & 50-370/98-07 on 980531-0711. Violations Noted.Major Areas Inspected:Licensee Operations, Maint,Engineering & Plant Support IR 05000369/19980061998-06-25025 June 1998 Insp Repts 50-369/98-06 & 50-370/98-06 on 980419-0530.No Violations Noted.Major Areas Inspected:Aspects of Licensee Operations,Maint,Engineering & Plant Support IR 05000369/19980041998-06-0404 June 1998 Insp Repts 50-369/98-04 & 50-370/98-04 on 980413-24. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000369/19980031998-05-18018 May 1998 Insp Repts 50-369/98-03 & 50-370/98-03 on 980308-0418.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support ML20216H6171998-04-0606 April 1998 Insp Repts 50-369/98-02 & 50-370/98-02 on 980125-0307. Violations Noted.Major Areas Inspected:Operations, Maintenance,Engineering & Plant Support IR 05000369/19970201998-02-23023 February 1998 Insp Repts 50-369/97-20 & 50-370/97-20 on 971214-980124. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support,Including Review of Radiological Protection Practices & Plant Physical Security IR 05000369/19980011998-02-17017 February 1998 Partially Withheld Insp Repts 50-369/98-01 & 50-370/98-01 on 980114-15 (Ref 10CFR2.790).No Violations Noted.Major Areas Inspected:Plant Support,Including Malevolent Use of Vehicles at Plant & Vehicle Barrier Sys ML20198P3771998-01-12012 January 1998 Insp Repts 50-369/97-18 & 50-370/97-18 on 971102-1213. Violations Noted.Major Areas Inspected:Integrated Insp Included Aspects of Licensee Operation,Maint,Engineering & Plant Support ML20199B1641998-01-0505 January 1998 Insp Repts 50-369/97-19 & 50-370/97-19 on 971205-06. Violations Noted.Major Areas Inspected:Licensee Response to 971202 Event Involving Seal Damage Event at Four Air Lock Doors of Unit 2 Containment Bldg IR 05000369/19970171997-12-0101 December 1997 Insp Repts 50-369/97-17 & 50-370/97-17 on 970921-1101.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000369/19970151997-10-20020 October 1997 Insp Repts 50-369/97-15 & 50-370/97-15 on 970810-0920. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000369/19970121997-09-22022 September 1997 Insp Repts 50-369/97-12 & 50-370/97-12 on 970804-08.No Violations Noted.Major Areas Inspected:Observation & Evaluation of Biennial Emergency Preparedness Exercise ML20211E7981997-09-16016 September 1997 Insp Repts 50-369/97-16 & 50-370/97-16 on 970712-0827. Violations Being Considered for Escalated Eas.Major Areas Inspected:Review of Aspects of Problem Involving Inoperable Unit 2 Ice Condenser Lower Inlet Doors IR 05000369/19970101997-09-0808 September 1997 Insp Repts 50-369/97-10 & 50-370/97-10 on 970629-0809.No Violations Noted.Major Areas Inspected:Operations, Engineering,Maint & Plant Support IR 05000369/19970131997-08-22022 August 1997 Insp Repts 50-369/97-13 & 50-370/97-13 on 970721-24.No Violations Noted.Major Areas Inspected:Licensees Program for Compensatory Measures for Degraded Security Equipment ML20149L5751997-07-28028 July 1997 Insp Repts 50-369/97-09 & 50-370/97-09 on 970518-0628. Violations Noted.Major Areas Inspected:Aspects of Licensee Operations,Engineering,Maint & Plant Support ML20149G6881997-06-16016 June 1997 Insp Repts 50-369/97-08 & 50-370/97-08 on 970406-0517. Violations Noted.Major Areas Inspected:Licensee Operations, Engineering,Maint & Plant Support IR 05000369/19970071997-06-0202 June 1997 Insp Rept 50-369/97-07 on 970406-0503.Violations Noted.Major Areas Inspected:Sg Replacement Project Activities in Areas of Maint & Engineering IR 05000369/19970041997-05-0505 May 1997 Insp Repts 50-369/97-04 & 50-370/97-04 on 970223-0405. Violations Noted.Major Areas Inspected:Operations, Maintenance,Engineering & Plant Support IR 05000369/19970051997-04-28028 April 1997 Insp Rept 50-369/97-05 on 970309-0405.No Violations Noted. Major Areas Inspected:Maint,Engineering & Plant Support IR 05000369/19970031997-04-0101 April 1997 Insp Rept 50-369/97-03 on 970125-0308.No Violations Noted. Major Areas Inspected:Sg Replacement Project Preoutage Activities in Areas of Maint,Engineering & Plant Support ML20137V1531997-03-24024 March 1997 Insp Repts 50-369/97-01 & 50-370/97-01 on 970112-0222. Violations Noted.Major Areas Inspected:Operations, Maintenance,Engineering & Plant Support IR 05000369/19970021997-03-0505 March 1997 Insp Repts 50-369/97-02 & 50-370/97-02 on 970203-06.No Violations Noted.Major Area Inspected:Licensee Plant Support ML20134L1461997-02-10010 February 1997 Insp Repts 50-369/96-11 & 50-370/96-11 on 961201-970111. No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000369/19960101996-12-30030 December 1996 Insp Repts 50-369/96-10 & 50-370/96-10 on 961020-1130.No Violations Noted.Major Areas Inspected:Operations, Engineering,Maint & Plant Support IR 05000369/19960091996-11-27027 November 1996 Insp Repts 50-369/96-09 & 50-370/96-09 on 961104-08.No Violations Noted.Major Areas Inspected:Safeguards Insp Included Aspects of Licensee Plant Support IR 05000369/19960081996-11-15015 November 1996 Insp Repts 50-369/96-08 & 50-370/96-08 on 960908-1019. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support ML20128H6951996-10-0202 October 1996 Insp Repts 50-369/96-07 & 50-370/96-07 on 960728-0907. Violations Noted.Major Areas Inspected:Licensee Operations, Engineering Maint & Plant Support IR 05000369/19940291994-12-28028 December 1994 Insp Repts 50-369/94-29 & 50-370/94-29 on 941205-09.No Violations Noted.Major Areas Inspected:Util Physical Security Program for Np Reactors Including Protection of Safeguards Info,Access Controls & Alarm Stations IR 05000369/19930291994-01-11011 January 1994 Insp Repts 50-369/93-29 & 50-370/93-29 on 931121-1218.No Violations Noted.Major Areas Inspected:Plant Operations, Surveillance Testing,Maintenance Observations & Cold Weather Preparation IR 05000369/19930301994-01-0707 January 1994 Insp Repts 50-369/93-30 & 50-370/93-30 on 931213-17.No Violations Noted.Major Areas Inspected:Design Changes & Plant Mods,Engineering & Technical Support Activities & follow-up on Previously Identified Insp Findings IR 05000269/19930321994-01-0606 January 1994 Insp Repts 50-269/93-32,50-270/93-32,50-287/93-32, 50-369/93-31,50-370/93-31,50-413/93-35 & 50-414,respectively on 931213-17.Violations Noted.Major Areas Inpected:Licensee Safeguards Info Program to folow-up on Licensee Repts IR 05000369/19930281993-12-29029 December 1993 Partially Withheld Insp Repts 50-369/93-28 & 50-370/93-28 on 931129-1202 (Ref 10CFR73.21).Violation Not Subj to Enforcement Action.Major Areas Inspected:Physical Security Program IR 05000369/19930241993-12-16016 December 1993 Insp Repts 50-369/93-24 & 50-370/93-24 on 931017-1120. Violations Noted.Major Areas Inspected:Plant Operations, Engineered Safety Features Sys Walkdown,Surveillance Testing & Maintenance IR 05000369/19930261993-12-15015 December 1993 Insp Repts 50-369/93-26 & 50-370/93-26 on 931115-19.No Violations Noted.Major Areas Inspected:Engineering & Technical Support of Plant Modifications,Design Changes & Plant Operations IR 05000369/19930251993-12-0202 December 1993 Partially Withheld Insp Repts 50-369/93-25 & 50-370/93-25 on 931101-04 (Ref 10CFR73.21).Noncited Violations Noted.Major Areas Inspected:Licensee Physical Security Program for Power Reactors IR 05000369/19930211993-11-10010 November 1993 Insp Repts 50-369/93-21 & 50-370/93-21 on 931018-21.No Violations Noted.Major Areas Inspected:Simulator Control Room,Tsc,Osc & EOF IR 05000369/19930221993-11-0909 November 1993 Insp Repts 50-369/93-22 & 50-370/93-22 on Stated Date. Violations Noted.Major Areas Inspected:Plant Operations, Surveillance Testing,Maintenance Observations,Ler & Followup on Previous Insp Findings IR 05000369/19930181993-10-19019 October 1993 Insp Repts 50-369/93-18 & 50-370/93-18 on 930822-0925. Violations Noted.Major Areas Inspected:Plant Operations, Surveillance Testing,Maint Observations,Plant Mods & Emergency Preparedness Training Exercise 1999-08-26
[Table view] Category:UTILITY
MONTHYEARIR 05000369/19900201990-11-0707 November 1990 Insp Repts 50-369/90-20 & 50-370/90-20 on 901001-05 & 1101. No Violations or Deviations Noted.Major Areas Inspected: Design Changes & Mod & Engineering Support Activities IR 05000369/19900191990-10-0404 October 1990 Insp Repts 50-369/90-19 & 50-370/90-19 on 900924-28.No Violations or Deviations Noted.Major Areas Inspected: Inservice Insp,Including Review of NDE Procedures, Observations of in-progress NDE Exams & Insp Plan IR 05000369/19900171990-09-11011 September 1990 Insp Repts 50-369/90-17 & 50-370/90-17 on 900726-0828. Violations Noted But Not Cited.Major Areas Inspected:Plant Operations Safety Verification,Surveillance Testing,Maint Activities & Facility Mods IR 05000369/19900151990-09-10010 September 1990 Insp Repts 50-369/90-15 & 50-370/90-15 on 900813-17. Violations Noted But Not Cited.Major Areas Inspected:Annual Emergency Exercise ML20056A5861990-07-24024 July 1990 Insp Repts 50-369/90-11 & 50-370/90-11 on 900522-0625. Violations Noted.Major Areas Inspected:Plant Operations Safety Verification,Surveillance Testing,Maint Activities, Facility Mods & Follow Up of Events Repts ML20055H4841990-07-13013 July 1990 Insp Repts 50-369/90-14 & 50-370/90-14 on 900626-0705. Violations Noted.Major Areas inspected:licensee-identified Issues Re Unit 1 Diesel Generator Inoperability for Approx 26 H on 900625-26 IR 05000369/19890301989-09-20020 September 1989 Insp Repts 50-369/89-30 & 50-370/89-30 on 890821-24.Noncited Violation Noted.Major Areas Inspected:Physical Security Program for Power Reactors.Details Withheld (Ref 10CFR2.790 & 73.21) IR 05000369/19890151989-09-0707 September 1989 Insp Repts 50-369/89-15 & 50-370/89-15 on 890605-09,19-23 & 0728.No Violations or Deviations Noted.Major Areas Inspected:Maint Program & Program Implementation IR 05000369/19890291989-08-31031 August 1989 Insp Repts 50-369/89-29 & 50-370/89-29 on 890821-25.No Violations or Deviations Noted.Major Areas Inspected: Portions of Inservice Insp Program,Unit 2 Insp Plan for Outage,Review of NDE Procedures & Exam Verifications IR 05000369/19890261989-08-30030 August 1989 Insp Repts 50-369/89-26 & 50-370/89-26 on 890807-11.No Violations or Deviations Noted.Major Areas Inspected:Plant Chemistry,Previously Identified Items & Status of Steam Generator Blowdown Recycle Sys IR 05000369/19890221989-08-17017 August 1989 Insp Repts 50-369/89-22 & 50-370/89-22 on 890724-28.No Violations or Deviations Noted.Major Areas Inspected: Inservice Insp,Including Eddy Current Exam of Unit 2 Steam Generator Tubing & Previous Open Item IR 05000369/19890201989-08-16016 August 1989 Insp Repts 50-369/89-20 & 50-370/89-20 on 890717-21.No Violations Noted.Major Areas Inspected:Containment Local Leak Rate Testing & Verification of Containment Integrity IR 05000369/19890211989-08-16016 August 1989 Insp Repts 50-369/89-21 & 50-370/89-21 on 890707-18. Violations Noted.Major Areas Inspected:Operation of Unit 1 Following Improperly Performed Heat Balance & Concomitant Nonconservative Calibr of Power Range Nuclear Instruments IR 05000369/19890181989-08-0909 August 1989 Insp Repts 50-369/89-18 & 50-370/89-18 on 890629-0728.No Violations or Deviations Noted.Major Areas Inspected: Operations Safety Verification,Surveillance Testing,Maint Activities,Followup of LER & Followup on Previous Findings IR 05000369/19890161989-08-0808 August 1989 Insp Repts 50-369/89-16 & 50-370/89-16 on 890622-28.One Violation & One Deviation Noted.Major Areas Inspected: Operations Safety Verification,Surveillance Testing,Maint Activities & Followup on LER & Previous Insp Findings IR 05000369/19890231989-08-0303 August 1989 Partially Withheld Insp Repts 50-369/89-23 & 50-370/89-23 on 890727 (Ref 10CFR2.790 & 73.21).Violations Noted.Major Areas Inspected:Security Event Logs IR 05000369/19890191989-07-19019 July 1989 Insp Repts 50-369/89-19 & 50-370/89-19 on 890710-14.No Violations or Deviations Noted.Major Areas Inspected: Inservice Insp Program & Unit 2 Insp Plan for Outage,Nde procedures,in-progress NDE Exams & NDE Equipment Calibr ML20236E6471989-07-13013 July 1989 Insp Repts 50-369/89-14 & 50-370/89-14 on 890422-0601. Violation Noted.Major Areas Inspected:Operation Safety Verification,Surveillance Testing,Maint activities,10CFR21 Reviews,Followup on Previous Insp Findings & LERs IR 05000369/19890171989-07-10010 July 1989 Insp Repts 50-369/89-17 & 50-370/89-17 on 890605-09.No Violations or Deviations Noted.Major Areas Inspected: Responses to Previous Insp Findings,Including Followup on NRC Bulletins 88-001 & 88-003 & on 10CFR21 Rept on Breakers ML20244E5881989-06-0505 June 1989 Insp Repts 50-369/89-11 & 50-370/89-11 on 890330-0421. Violations Noted.Major Areas Inspected:Operations Safety Verification,Surveillance Testing,Maint Activities & Followup on Previous Insp Findings IR 05000369/19890131989-06-0101 June 1989 Partially Withheld Insp Repts 50-369/89-13 & 50-370/89-13 on 890501-05 (Ref 10CFR2.790 & 73.21).Two Noncited Violations Noted Re Failure to Conduct Psychological Exam.Major Areas Inspected:Mgt Support,Record & Repts & Lighting ML20247M5801989-05-15015 May 1989 Insp Repts 50-369/89-10 & 50-370/89-10 on 890404-07.No Violations or Deviations Noted.Major Areas Inspected: Emergency Preparedness Requirements & Practices Implemented During Licensee Response to Steam Generator B Tube Rupture IR 05000369/19890021989-04-25025 April 1989 Operational Safety Team Insp Repts 50-369/89-02 & 50-370/89-02 on 890213-17 & 0227-0322.Violations Noted.Major Areas Inspected:Operations,Maint Support of Operations,Mgt Controls & Emergency Operating Procedures ML20245G9781989-04-20020 April 1989 Insp Repts 50-369/89-05 & 50-370/89-05 on 890228-0329. Violations Noted.Major Areas Inspected:Operations Safety Verification,Surveillance Testing,Maint Activities & Followup on Previous Insp Findings IR 05000369/19890071989-04-17017 April 1989 Insp Repts 50-369/89-07 & 50-370/89-07 on 890320-24.No Violations or Deviations Noted.Major Areas Inspected: Inservice Insp,Including Review of Procedures,Observation of Work Activities & Evaluation of Eddy Current Testing IR 05000369/19890061989-04-10010 April 1989 Insp Repts 50-369/89-06 & 50-370/89-06 on 890308-11.Major Areas Inspected:Events Re 890307 Steam Generator B Tube Failure.Procedures Found to Have Weaknesses Which Could Result in Release of Radioactivity to Environ IR 05000369/19890081989-04-0606 April 1989 Insp Repts 50-369/89-08 & 50-370/89-08 on 890327-31.No Violations Noted.Major Areas Inspected:Steam Generator Tubing Eddy Current Exam & Activities Associated W/Unit 1 Steam Generator B Ruptured Tube IR 05000369/19890031989-03-30030 March 1989 Insp Repts 50-369/89-03 & 50-370/89-03 on 890306-10.No Violations or Deviations Noted.Major Areas Inspected: Triennial post-fire Safe Shutdown Capability Reverification & Assessment (Module 64150) IR 05000369/19890091989-03-30030 March 1989 Partially Withheld Insp Repts 50-369/89-09 & 50-370/89-09 on 890220-24 (Ref 10CFR73.21).Violations Noted.Major Areas Inspected:Mgt Support,Security Program Plans,Security Program Audit,Records & Repts & Compensatory Measures IR 05000369/19890011989-03-29029 March 1989 Insp Repts 50-369/89-01 & 50-370/89-01 on 890120-0227. Violations Noted.Major Areas Inspected:Operations Safety Verification,Surveillance Testing,Maint Activities & Review of Plant Procedures ML20244A8831989-03-29029 March 1989 Insp Repts 50-369/89-01 & 50-370/89-01 on 890120-0227. Violations Noted.Major Areas Inspected:Operations Safety Verification,Surveillance Testing,Maint Activities & Review of Plant Procedures ML20235P5621989-02-0707 February 1989 Insp Repts 50-369/88-33 & 50-370/88-33 on 881122-890119. Violations Noted.Major Areas Inspected:Operations Safety Verification,Surveillance Testing,Maint activities,10CFR21 Insp,Startup from Refueling & Followup on Previous Insp IR 05000369/19880301988-11-0404 November 1988 Insp Repts 50-369/88-30 & 50-370/88-30 on 880924-1020. Violation Noted.Major Areas Inspected:Operations Safety Verification,Surveillance Testing,Maint Activities & Followup on Previous Insp Findings IR 05000369/19880271988-10-28028 October 1988 Insp Repts 50-369/88-27 & 50-370/88-27 on 880913-16.No Violations or Deviations Noted.Weakness Noted.Major Areas Inspected:Annual Radiological Emergency Response Exercise IR 05000369/19880281988-10-14014 October 1988 Partially Withheld Insp Repts 50-369/88-28 & 50-370/88-28 on 880912-16 (Ref 10CFR2.790 & 73.21).No Violations Noted.Major Areas Inspected:Maint Barriers,Assessment Aids,Access Controls,Alarm Stations & Training & Contingencies IR 05000369/19880261988-10-12012 October 1988 Insp Repts 50-369/88-26 & 50-370/88-26 on 880820-0923. Violation Noted:Inadequate Fire Barrier Penetrations.Major Areas Inspected:Operations Safety Verification,Surveillance Testing,Maint Activities & Followup on Previous Findings IR 05000369/19880241988-10-0606 October 1988 Insp Repts 50-369/88-24 & 50-370/88-24 on 880801-0916. Violations & Unresolved Item Noted.Major Areas Inspected: Past & Current Operability of Hydrogen Skimmer Sys IR 05000369/19880291988-09-23023 September 1988 Insp Repts 50-369/88-29 & 50-370/88-29 on 880829-0909. Violations Noted.Major Areas Inspected:Inoperability of Safety Sys Due to Inadequate post-mod Testing ML20205S0711988-09-13013 September 1988 Insp Repts 50-369/88-25 & 50-370/88-25 on 880816-18.No Violations or Deviations Identified.Major Areas Inspected: Resolution of Findings from NRC Diagnostic Evaluation Team Rept & Status of Licensee Written Response to Rept ML20154F9911988-09-0606 September 1988 Insp Repts 50-369/88-23 & 50-370/88-23 on 880723-0819.One Violation Noted.Major Areas Inspected:Operations Safety Verification,Surveillance Testing,Maint Activities & Followup on Previous Insp Findings ML20151Z8821988-08-19019 August 1988 Insp Repts 50-369/88-20 & 50-370/88-20 on 880625-0722. Violations Noted.Major Areas Inspected:Operations Safety Verification,Surveillance Testing,Maint Activities & Followup on Previous Insp Findings IR 05000369/19880221988-08-11011 August 1988 Partially Withheld Insp Repts 50-369/88-22 & 50-370/88-22 on 880718-22 (Ref 10CFR2.790 & 73.21).No Violations Noted. Major Areas Inspected:Procedures & Operations of SNM IR 05000369/19880161988-07-26026 July 1988 Insp Repts 50-369/88-16 & 50-370/88-16 on 880620-24.No Violations or Deviations Noted.Major Areas Inspected: Occupational Exposure During Extended Outages IR 05000369/19880191988-07-21021 July 1988 Insp Repts 50-369/88-19 & 50-370/88-19 on 880627-0701.No Violations or Deviations Noted.Major Areas Inspected:Nde Activities Re Resistance Temp Detector Sys Mods & Inservice Insp & Preservice Insp Being Accomplished During Outage IR 05000369/19880171988-07-15015 July 1988 Insp Repts 50-369/88-17 & 50-370/88-17 on 880620-24.No Violations or Deviations Noted.Major Areas Inspected:Liquid & Gaseous Effluents IR 05000369/19880181988-07-12012 July 1988 Partially Withheld Insp Repts 50-369/88-18 & 50-370/88-18 on 880620-24 (Ref 10CFR2.790 & 73.21).One Licensee Identified Violation Noted.Major Areas Inspected:Mgt Effectiveness - Security Program & Records & Repts ML20151E6081988-07-0808 July 1988 Insp Repts 50-369/88-14 & 50-370/88-14 on 880521-0624. Violations Noted:Continued Weakness in Procedural Compliance.Major Areas Inspected:Safety Verification, Surveillance Testing & Refueling Outage Activities IR 05000369/19880151988-06-30030 June 1988 Insp Repts 50-369/88-15 & 50-370/88-15 on 880613-17.No Violations or Deviations Noted.Major Areas Inspected:Nde Procedures Review,Observation & Review of in-process NDE Exam & Review of Inservice Insp Exam Data ML20195C8611988-06-0707 June 1988 Insp Repts 50-369/88-13 & 50-370/88-13 on 880502-06.One Violation & Two Unresolved Items Noted.Major Areas Inspected:Nrc Diagnostic Evaluation Team Rept Findings & Action on Previous Insp Findings ML20155J3411988-05-31031 May 1988 Insp Repts 50-369/88-12 & 50-370/88-12 on 880423-0520. Violations Noted.Major Areas Inspected:Operations Safety Verification,Surveillance Testing,Maint Activities & Followup on Previous Insp Findings 1990-09-11
[Table view] Category:TEXT-INSPECTION & AUDIT & I&E CIRCULARS
MONTHYEARIR 05000369/19990061999-10-0404 October 1999 Insp Repts 50-369/99-06 & 50-370/99-06 on 990801-0911. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000369/19990051999-08-26026 August 1999 Insp Repts 50-369/99-05 & 50-370/99-05 on 990620-0731.Two Violations Noted Being Treated as Ncv.Major Areas Inspected: Operations,Maint,Engineering & Plant Support IR 05000369/19990041999-07-13013 July 1999 Insp Repts 50-369/99-04 & 50-370/99-04 on 990509-0619.Four Violations of NRC Requirements Occurred & Being Treated as Ncvs.Major Areas Inspected:Aspects of Licensee Operations, Maint,Engineering & Plant Support IR 05000369/19990101999-06-16016 June 1999 Insp Repts 50-369/99-10 & 50-370/99-10 on 990322-26.No Violations Noted.Major Areas Inspected:Aspect of Licensee Health Physics Activities During Unit 2 Refueling Outage IR 05000369/19990031999-06-0202 June 1999 Insp Repts 50-369/99-03 & 50-370/99-03 on 990328-0508. Non-cited Violations Noted.Major Areas Inspected:Operations, Maintenance,Engineering & Plant Support IR 05000369/19990021999-04-23023 April 1999 Insp Repts 50-369/99-02 & 50-370/99-02 on 990214-0327.No Violations Noted.Major Areas Inspected:Licensee Operations, Maint,Engineering & Plant Support IR 05000369/19993011999-03-18018 March 1999 NRC Operator Licensing Exam Repts 50-369/99-301 & 50-370/99-301 (Including Completed & Graded Tests) for Tests Administered on 990125-0205.Five SRO & Six RO Candidates Received Written Exams & Operating Tests IR 05000369/19990011999-03-10010 March 1999 Insp Repts 50-369/99-01 & 50-370/99-01 on 990103-0213.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000369/19980101998-12-18018 December 1998 Insp Repts 50-369/98-10 & 50-370/98-10 on 981004-1121.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000369/19980091998-10-30030 October 1998 Insp Repts 50-369/98-09 & 50-370/98-09 on 980823-1003.No Violations Noted.Major Areas Inspected:Aspects of Licensee Operations,Maint,Engineering & Plant Support ML20154C4131998-09-21021 September 1998 Notice of Violation from Insp on 980712-0822.Violation Noted:On or Before 971217,operations Personnel Failed to Designate Appropriate Vent Valves for Venting to Properly Return Sys to Svc as Required by Omp 7-1 IR 05000369/19980081998-09-21021 September 1998 Insp Repts 50-369/98-08 & 50-370/98-08 on 980712-0822.No Violations Noted.Major Areas Inspected:Aspects of Licensee Operations,Maint,Engineering & Plant Support IR 05000369/19980111998-08-27027 August 1998 Insp Repts 50-369/98-11 & 50-370/98-11 on 980601-26 & 0805-07.No Violations Noted.Major Areas Inspected:Maint & Engineering Programs.Rept Reviewed Maintenance,Surveillance & Matl Condition of Mcquire,Unit 1 Ice Condenser System ML20237B1561998-08-0707 August 1998 Notice of Violation from Insp on 980531-0711.Violation Noted:Licensee Failed to Establish Procedural Guidance for Abnormal Vent Path Used for Degassing Unit 1 Volume Control Tank to Environ IR 05000369/19980071998-08-0707 August 1998 Insp Rept 50-369/98-07 & 50-370/98-07 on 980531-0711. Violations Noted.Major Areas Inspected:Licensee Operations, Maint,Engineering & Plant Support IR 05000369/19980061998-06-25025 June 1998 Insp Repts 50-369/98-06 & 50-370/98-06 on 980419-0530.No Violations Noted.Major Areas Inspected:Aspects of Licensee Operations,Maint,Engineering & Plant Support PNO-II-98-030, on 980603,loss of Offsite Power Occurred,Due to Loss of 1B Bus.Caused by Faulted 230 Kv Switchyard Current Transformer.Resident Inspectors Onsite & Responded to Event & Will Continue to Evaluate Activities W/Event1998-06-0404 June 1998 PNO-II-98-030:on 980603,loss of Offsite Power Occurred,Due to Loss of 1B Bus.Caused by Faulted 230 Kv Switchyard Current Transformer.Resident Inspectors Onsite & Responded to Event & Will Continue to Evaluate Activities W/Event ML20249A2451998-06-0404 June 1998 Notice of Violation from Insp on 980413-24.Violation Noted: Procedure Investigation Processes 2-M96-1440 & 0-M97-1933 Were Not Initiated within 24 H After Realization That Procedure Investigation Process Should Have Been Written IR 05000369/19980041998-06-0404 June 1998 Insp Repts 50-369/98-04 & 50-370/98-04 on 980413-24. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000369/19980031998-05-18018 May 1998 Insp Repts 50-369/98-03 & 50-370/98-03 on 980308-0418.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support ML20216H6171998-04-0606 April 1998 Insp Repts 50-369/98-02 & 50-370/98-02 on 980125-0307. Violations Noted.Major Areas Inspected:Operations, Maintenance,Engineering & Plant Support ML20216H6051998-04-0606 April 1998 Notice of Violation from Insp on 980125-0307.Violation Noted:Licensee Failed to Adequately Establish or Adhere to Procedural Guidance for Repair of Two safety-related Containment Isolation Valves as Evidenced IR 05000369/19970201998-02-23023 February 1998 Insp Repts 50-369/97-20 & 50-370/97-20 on 971214-980124. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support,Including Review of Radiological Protection Practices & Plant Physical Security ML20203F5921998-02-23023 February 1998 Notice of Violation from Insp on 980105-08.Violations Noted: Licensee Failed to Follow Procedures for Security Badge & Access Control IR 05000369/19980011998-02-17017 February 1998 Partially Withheld Insp Repts 50-369/98-01 & 50-370/98-01 on 980114-15 (Ref 10CFR2.790).No Violations Noted.Major Areas Inspected:Plant Support,Including Malevolent Use of Vehicles at Plant & Vehicle Barrier Sys ML20198P3771998-01-12012 January 1998 Insp Repts 50-369/97-18 & 50-370/97-18 on 971102-1213. Violations Noted.Major Areas Inspected:Integrated Insp Included Aspects of Licensee Operation,Maint,Engineering & Plant Support IR 07100102/20120131998-01-12012 January 1998 Notice of Violation from Insp on 971102-1213.Violation Noted:Inadequate Measures Were Provided for Verification or Checking Adequacy of Design Documents ML20199B1641998-01-0505 January 1998 Insp Repts 50-369/97-19 & 50-370/97-19 on 971205-06. Violations Noted.Major Areas Inspected:Licensee Response to 971202 Event Involving Seal Damage Event at Four Air Lock Doors of Unit 2 Containment Bldg ML20199B1571998-01-0505 January 1998 Notice of Violation from Insp on 971205-06.Violation Noted: an Event Occurred on 971202 in Which Person or Persons Made Credible Threat to Commit or Cause Significant Physical Damage to Power Reactor & Not Reported within One Hour ML20203M4471998-01-0505 January 1998 Errata to Notice of Violation for Insp Repts 50-369/97-19 & 50-370/97-19.Statement in Nov,Page 2, Under Authority of Section 182 of Act.42USC 2232,this Response Shall Be Submitted Under Oath or Affirmation, Was Incorrect IR 05000369/19970171997-12-0101 December 1997 Insp Repts 50-369/97-17 & 50-370/97-17 on 970921-1101.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000369/19970151997-10-20020 October 1997 Insp Repts 50-369/97-15 & 50-370/97-15 on 970810-0920. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support ML20198N4701997-10-20020 October 1997 Notice of Violation from Insp on 970810-0920.Violation Noted:On 960420,ET Guidelines,Apps C & E Were Not Implemented as Evidenced By;Resolution Analyst Revised & Overruled Reexam Request for SG 2A Tube R7C60 ML20212A0361997-10-0808 October 1997 Notice of Violation from Insp on 970712-0827.Violation Noted:As of 970717,10 of 48 Ice Condenser Inlet Doors on Unit 2 Required Initial Opening Torque in Ixcess of 675 inch-pound Operability Limit ML20211K9431997-09-26026 September 1997 Notice of Violation from Insp on 970721-26.Violation Noted: Licensee Failed to Follow Procedures for Security Badges & Access Control of Facility IR 05000369/19970121997-09-22022 September 1997 Insp Repts 50-369/97-12 & 50-370/97-12 on 970804-08.No Violations Noted.Major Areas Inspected:Observation & Evaluation of Biennial Emergency Preparedness Exercise ML20211E7981997-09-16016 September 1997 Insp Repts 50-369/97-16 & 50-370/97-16 on 970712-0827. Violations Being Considered for Escalated Eas.Major Areas Inspected:Review of Aspects of Problem Involving Inoperable Unit 2 Ice Condenser Lower Inlet Doors IR 05000369/19970101997-09-0808 September 1997 Insp Repts 50-369/97-10 & 50-370/97-10 on 970629-0809.No Violations Noted.Major Areas Inspected:Operations, Engineering,Maint & Plant Support IR 05000369/19973001997-08-29029 August 1997 NRC Operator Licensing Exam Repts 50-369/97-300 & 50-370/97-300 (Including Completed & Graded Tests) for Test Administered on 970728-31.Exam Results:Five SRO & One RO Passed Exam & One SRO Failed Exam IR 05000369/19970131997-08-22022 August 1997 Insp Repts 50-369/97-13 & 50-370/97-13 on 970721-24.No Violations Noted.Major Areas Inspected:Licensees Program for Compensatory Measures for Degraded Security Equipment ML20217R1161997-08-18018 August 1997 EN-97-076:on 970818,order Prohibiting Involvement in NRC- Licensed Activities for a Period of One Year Will Be Issued. Action Based on Investigation Conducted by Oi,Which Determined Falsification of QA Document PNO-II-97-051, on 970906,McGuire Units 1 & 2 Automatically Tripped.Porvs Utilized Until Steam Dumps Could Be Made Available.Steam Relieved Through Main Steam PORVs Until Power to Bus Kxa Restored & MSIVs Reopened1997-08-0909 August 1997 PNO-II-97-051:on 970906,McGuire Units 1 & 2 Automatically Tripped.Porvs Utilized Until Steam Dumps Could Be Made Available.Steam Relieved Through Main Steam PORVs Until Power to Bus Kxa Restored & MSIVs Reopened ML20149L5751997-07-28028 July 1997 Insp Repts 50-369/97-09 & 50-370/97-09 on 970518-0628. Violations Noted.Major Areas Inspected:Aspects of Licensee Operations,Engineering,Maint & Plant Support ML20149L5701997-07-28028 July 1997 Notice of Violation from Insp on 970518-0628.Violation Noted:Procedure IP/0/A/3250/12B Inadequate to Provide Sufficient Guidance to Properly Test Emergency Diesel Generator Sequencer Logic Circuitry ML20149G6881997-06-16016 June 1997 Insp Repts 50-369/97-08 & 50-370/97-08 on 970406-0517. Violations Noted.Major Areas Inspected:Licensee Operations, Engineering,Maint & Plant Support ML20149G6771997-06-16016 June 1997 Notice of Violation from Insp on 970406-0517.Violation Noted:Procedure PT/1/A/4600/014D Was Inadequate in Providing Sufficient Guidance to Bypass Properly RPS Functions of an Inoperable N-41 Channel to Permit Testing of Channel N-42 IR 05000369/19970071997-06-0202 June 1997 Insp Rept 50-369/97-07 on 970406-0503.Violations Noted.Major Areas Inspected:Sg Replacement Project Activities in Areas of Maint & Engineering ML20148B9621997-05-0505 May 1997 Notice of Violation from Insp on 970223-0405.Violation Noted:Prior to 961130,activities Affecting Quality,Not Accomplished in Accordance W/Instructions,Procedures or Drawings IR 05000369/19970041997-05-0505 May 1997 Insp Repts 50-369/97-04 & 50-370/97-04 on 970223-0405. Violations Noted.Major Areas Inspected:Operations, Maintenance,Engineering & Plant Support IR 05000369/19970051997-04-28028 April 1997 Insp Rept 50-369/97-05 on 970309-0405.No Violations Noted. Major Areas Inspected:Maint,Engineering & Plant Support 1999-08-26
[Table view] |
See also: IR 05000369/1985006
Text
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. UNITED STATES
- D Cfog% NUCLEAR REGULATORY COMMISSION
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[' n REGloN 11
g .j 101 MARIETTA STREET, N.W.
t ATL ANTA, GEORGI A 30323
%, .....f
Report Nos.: 50-369/85-06 and 50-370/85-06
Licensee: Duke Power Company
422 South Church Street
Charlotte, NC 28242
Docket Nos.: 50-369 and 50-370 License Nos.: NPF-9 and NPF-17
Facility Name: McGuire 1 and 2
Inspection Conducted: J ary 20 - March 20, 1985
"
Inspectors: a h /g' // f0
W. rder Upte'S'gne
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[ // ate 71gned
P. M ne k ar tr and -- ,1985)
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ate igned
Approved by: I t Gt. O M'L{A y 2-( hy
H.'Uancg,SectionChief Date S1'gned
Division of Reactor Projects
SUMMARY
Scope: This routine, unannounced inspection entailed 470 inspector-hours on site
in the areas of operations, safety verification, surveillance testing,
maintenance activities and refueling activities.
Results: Of the four areas inspected, four items of noncompliance were found in
three areas (Violation of 10 CFR 50, Appendix B, Criterion III for inadequate
separation criteria; Violation of Technical Specification (TS) 6.8.1 for failure
to follow procedures; Violation of TS 4.8.1.1.2a for inadequate diesel generator
surveillance interval and Violation of 10 CFR, Appendix B, Criterion XVI for
failure to take prompt corrective action).
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8508090150 050628
PDR ADOCK 05000369
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REPORT DETAILS
1. Licensee Employees Contacted
T. McConnell, Station Manager
- D. Rains, Superintendent of Maintenance
- G. Cage. Superintendent of Operations
- L. Weaver, Superintendent of Station Services
N. McCraw, Licensing Engineer
- J. Foster, Station Health Physicist
- M. Birch, System /Radwaste Engineer General Office
- R. Michaels, Station Chemist
- B. Hasty, McGuire Nuclear Station - QA
- P. Roberson, Associate Engineer - Performance
Other licensee employees contacted included teci.nicians, operators,
mechanics, security force members, and office personnei.
2. Exit Interview
The inspection scope and findings were summarized on March 29, 1985, with
those persons indicated in paragraph I above. The licensee acknowledged
understanding of the violations and issues discussed and offered no
substantive related discussion. The licensee did not identify as pro-
prietary any of the materials provided to or reviewed by the inspectors
during this inspection.
3. Licensee Action on Previous Enforcement Matters
This subject was not addressed in the inspection.
4. Unresolved Items *
Unresolved items are matters about which more information is required to
determine whether they are acceptable or may involve noncompliance or
deviations. New unresolved items identified during this inspection are
discussed in paragraph 17.
5. Plant Operations
The inspection staff reviewed plant operations during the report period,
January 20 - March 20, 1985, to verify conformance with applicable
- An Unresolved Ite'n is a matter about which more information is required to ,
determine whether it is acceptable or may involve a violation or deviation.
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regulatory requirements. Control room logs, shift supervisors logs, shift
turnover records and equipment removal and restoration records were
routinely perused. Interviews were conducted with plant operations,
maintenance, chemistry, health physics, and performance personnel.
Activities within the control rooms were monitored during shifts and at
shift changes. Actions and/or activities observed were conducted as
prescribed in applicable station administrative directives. The complement
of licensed personnel on each shift met or exceeded the minimum required by
TSs.
Plant tours were taken during the reporting period on a systematic basis.
The areas toured include but are not limited to the following:
Turbine Buildings
Auxiliary Buildings
Unit 1 and 2, Electrical Equipment Rooms
Units 1 and 2, Cable Spreading Rooms
Station yard Zone within the protected area
Unit 2 Reactor Building
During the plant tours, ongoing activities, housekeeping, security,
equipment status and radiation control practices were observed.
Unit 1 Operations
McGuire Unit 1 began the reporting period in Mode 1 operating at 100 percent
reactor power and operated at or about that power level until January 28.
On that morning, the IB main feedwater pump trinped when a suction pressure
instrumentation line failed. A turbine runbaci failed to initiate upon the
loss of feed pump due to a failed diode in tF runback circuitry. The unit
subsequently tripped on steam generator 1B 1 lo level.
The unit was subsequently recovered and ent red Mode 1 at 11:09 p.m., on the
evening of January 30. The unit was paralleled to the grid and power held
to 30 percent to allow secondary chemistry to be brought into specification.
The unit's power was subsequently increased to 100 percent and maintained at ~l
that level until February 5, when the unit apparently tripped on negative
high flux rate. This trip is discussed in detail in paragraph 7.
During the trip recovery, two engineered safeguards features actuations
occurred. These events are discussed in paragraph 12. It was also
determined that a wiring modification on the solid state protection system
for Unit 1 had been incorrectly installed thus rendering the reactor trip
breakers inoperable for Unit 1. This event is discussed in paragraph 11.
Following correction of the modification the unit was restarted reaching
criticality at 6:18 a.m., on February 7 Reactor power was subsequently
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increased to and maintained at or about 100 percent until February 21, when
power was reduced to 90-95 percent to maintain generator hydrogen temperature
within limits (one cooler was valved out due to a leak). Power was maintained
between 90-95 percent until March 8, when power was reduced to optimize
outage scheduling. The unit was subsequently operated between 55-62 percent
throughout the duration of the report period.
Unit 2 Operations
McGuire Unit 2 began the reporting period in Mode 1 operating at 100%
reactor power. The unit was maintained at or about that power until
8:54 a.m., on January 25, when unit shutdown was begun to facilitate a
refueling outage. The unit was shutdown and cooled down entering Mode 5 at
10:05 p.m., on January 26. The unit was maintained in Mode 5 until
February 7 when the unit entered Mode 6.
Detensioning of the Reactor Vessel Head was complete at 3:00 a.m. on
February 8. Core alterations comenced at 3:40 p.m., on February 16.
Fuel removal was completed at 2:45 p.m., on March 3. The unit remained
defueled until March 20 when fuel reload was initiated.
6. Reactor Trip of January 28
On January 28, when Unit I was operating at 100 percent reactor power, an instru-
ment air line failure to the B main feedwater (CF) pump suction pressure
transmitter caused the loss of B CF pump on apparent low suction pressure.
A turbine runback signal from loss of this feedpump failed to initiate a
turbine runback due to a bad diode on a card in the turbine electro-
hydraulic control. Operators attempted a manual turbine load reduction but
were unsuccessful and a reactor trip occurred on 10-10 B steam ger.erator
level. After the trip some problems were encountered with B and C steam
generator Pressure Operated Relief Valves (PORV). These valves failed to
close for 4 minutes and 25 seconds respectively. A faulty pressure trans-
mitter on B steam generator pressure caused the delay in closing the B steam
generator PORV. The resultant inventory loss and void collapse caused B
steam generator level to drop below its narrow range scale for approximately
6 minutes. The resulting cooldown caused pressurizer level to fall below
the letdown isolation setpoint. A second charging pump was started,
pressurizer level was recovered and letdown reestablished.
Following the trip the check valve in the Turbine Driven Auxiliary Feed Pump
(TDAFP) line to the "C" steam generator failed to seat when the TDAFP was
being realigned to the A and B steam generators. The valve was subsequently
isolated, however a large portion of motor driven auxiliary feedpump flow '
to the "C" steam generator was backfeeding into the TDAFP suction line
i through the check valve prior to isolation. Further discussion related
to backleakage of auxiliary feedwater check values is contained in para-
graph 15.
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7. Reactor Trip of February 5,1985
On February 5, 1985, a Unit i reactor trip occurred on what appeared to be a
High Negative Flux Rate. Unit I was at 94 percent reactor power in steady state
operation. Power had been reduced to this level to facilitate the resetting
of the High Negative Flux Rate trip setpoints per Westinghouse recomen-
dation as discussed in paragraph 9. At the time of the trip, three of the
four Power Range Nuclear Instruments had been reset; preparations were
underway to reset the fourth. No instrumentation and electrical work was in
progress at the time of the trip. Two design engineering personnel were
performing a visual inspection of the nucler station modification installed
in the Unit 1 Reactor Trip Breaker Cabinets discussed in paragraph 11.
There is no conclusive evidence tc indicate that changing the High Flux Rate
trip setpoints contributed to the reactor trip. A reenactment of the
visual inspection which design engineering was conducting did not result
in opening of the reactor trip breakers. Efforts to determine the exact
sequence of events was hampered by the fact that the events recorder points
for the reactor trip breakers were out of service as had been noted on the
reactor trip which occurred on January 28. A work request to correct this
problem had been issued but the repairs had not been affected.
It cannot be determined conclusively whether one or both of the reactor trip
breakers opened causing the rods to fall and thus causing a High Negative
Flux Rate trip indication or whether an actual High Negative Flux Rate
signal opened the reactor trip breakers.
Since the cause of the reactor trip could not be determined, an independent
review was performed per Station Directive 3.1.10. Licensee personnel
evaluated the occurrence and could not determine the cause of the trip. The
Station Manager made the decision to restart the unit with instructions to
monitor the High Flux Rate trips with recorders.
8. Diesel Generator (D/G) 2A Valid Failure
Diesel Generator (D/G) 2A experienced a valid failure on January 31, 1985.
The failure occurred as a result of a low lube oil pressure trip while
Operations personnel were performing a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> run test in preparation for
an engineered safety features (ESF) test. After the trip, inspections were
made to determine the cause for low lube oil pressure. When no cause was
found, D/G 2A was restarted for additional troubleshooting. Due to abnormal
vibration in the engine, the run was terminated and the D/G was declared
inoperable.
An inspection of the main bearinas following the shutdown of the D/G showed
severe damage had occurred to five of ten main bearings. The bearing
deterioration appears to be the result of a mechanical failure. Preliminary
investigations indicate that damage was not due to oil starvatica of the
bearings. A final determination of the cause of the bearing failure can not
be made until the licensee completes all inspections and measurements during
the course of repairs.
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Details concerning the D/G 2A failure is covered in Report No. 50-369/85-13
and 50-370/85-12.
9. Westinghouse Determination of Incorrect Rod Drop Time Specifications
On February 1,1985, Westinghouse notified the licensee that McGuire's TS
3.1.3.4 allows a rod drop time of 3.3 seconds. This does not coincide with
Reactor Trip System Instrumentation Trip Setpoints stipulated in Table 2.2-1
Item 4. This specification if corrected would require Power Range, Neutron
Flux, High Negative Rate, Trip Setpoint of less than or equal to 5 percent
of Rated Thermal Power with a time constant greater than or equal to 2
seconds. It was identified during a review of this issue that the applicable
TS 2.2.1, Table 2.2-1, Item 4 is incorrect in that it specifies a trip
setpoint of greater than 5 percent rated thermal power when it should state
less than 5 percent rated thermal power. From Westinghouse's calculations a
trip setpoint of less than or equal to 5%/2 seconds would require a rod drop
time of'less than or equal to 1.7 seconds.
At the time of the notification, McGuire Unit I was in Mode 1 operating at
100 percent and Unit 2 was in Mode 5 at the beginning of a refueling outage.
A licensee evaluation of the previous Unit 1 Rod Drop surveillance revealed
that McGuire Unit i rod drop times were 1.47 seconds. This is less than 1.7
seconds as required by the new Westinghouse determined requirements. On
February 5 and 6,1985, the Unit 1 Power Range Neutron Flux High Negative
Rate trip setpoints were adjusted to 21 percent of rated thermal power with
a time constant of greater than or equal to 2 seconds in accordance with
Westinghouse recommendations, Unit 2 setpoints will be set at a similar
value prior to the end of this refueling outage.
10. Inoperable Fire Barrier
On February 2, licensee personnel were preparing to implement a Nuclear
Station Modification when a i inch by 11 inch hole was discovered under
control board 2MC11. This hole connected the Unit 2 side of the Control
Room to the Unit 2 cable spreading room underneath the control room. It was
subsequently determined that a similar hole existed on the Unit 1 side in
the equivalent area under IMC11, but this hole was appropriately sealed by
fire barrier foam. A licensee evaluation failed to determine when or why
the hole was drilled.
TS 3.7.11 requires that all fire barrier penetrations (walls, floor /
ceilings, cable tray enclosures and other fire barriers) separating safety-
related fire areas or separating portions of redundant systems important to
safe shutdown within a fire area and all sealing devices in fire rated
assembly penetrations (fire doors, fire windows, fire dampers, cable piping,
and ventilation duct penetration seals) shall be OPERABLE at all times. The
fu e barrier between the Control Roor,and the Cable Spreading Room was found
by the licensee to have been inoperable for an indeterminate amount of time.
Upon discovery of the hole the licensee promptly took compensatory measures
and estab'iished continuous fire watches. The above event is a licensee
identified violation and will not be cited since it meets the NRC Enforcee
ment criterion in 10 CFR 2 Appendix C.
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11. Improper Installation Of Wiring During Modification Of Train "A" and "B"
Reactor Trip And Bypass Breakers
During the implementation of a Nuclear Station Design Modification (NSM) on
the Unit 2 Reactor Trip and Bypass Breakers, NSM MG-2-285 Rev. O, (commit-
ment to SSER No. 7, Section D.5.3) the technician responsible determined
that the NSM was not clear about the required cable separation for Train A
and Train B wiring components. As a result the technician did not perform
the modification but referred the problem to his supervisor. Subsequent
evaluation determined that the same design modification had been performed
on Unit 1 on March 26, 1984, NSM MG 1376 Rev. O.
A Quality Assurance inspection of the Unit 1 Reactor Trip and Bypass
Breakers determined that the Train A and Train B separation criteria was not
met, in that a Train A wire was routed in a Train B wire track. The NSM's
were not clear about required cable separation or which wiring tracks within
the trip breaker cabinets to use for the A and B trains.
10 CFR 50, Criterion III states in part that "... design control measures
shall provide for verifying or checking the adequacy of design..." and
further states that " design changes, including field changes, shall be
subject to design control measures commensurate with those applied to the
original design..." The original design incorporates 10 CFR 50, Appendix A,
Criterion 21 - Protection System reliability and testability, which states
in part that redundancy and independence designed into the protection system
shall be sufficient to assure that no single failure results in loss of the
protection function.
Contrary to the requirements of 10 CFR 50 Appendix B, Criterion III, NSM
MG-1376 Rev. 0 was incorporated into the Unit 1 Reactor Trip Breaker
cabinetry without adequate design control measures, in that no guidance was
provided to ensure that wiring separation criteria would be met. The above
constitutes a violation 369/85-06-01.
12. Unplanned Actuation of Engineered Safeguards Features (ESF)
On February 6, 1985, while Unit I was in Mode 3, an unplanned auto actuation
of Engineered Safeguards Features occurred when procedural prerequisites
were not met during the performance of PT/1/A/4601/03, Protective System
Channel III Functional Test (Unit 1), while a channel undergoing negative
rate trip adjustment was simultaneously out-of-service. A reactor trip and
turbine driven and motor driven auxiliary feedwater pumps initiation
occurred.
Procedure stcas 6.1 and 12.3 of PT/1/A/4601/03 were not met in that reactor
protective system instrumentation for Channel III A, B, C and D steam
generator lo-lo levels were in test with the bistables tripped while
Channel IV of the Nuclear Instrumentation (NI) power range was in test for
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adjustment of the negative rate trip per Procedure IP/0/A/3207/03K as
discussed in paragraph 9. When power range Channel IV was increased to
100 percent, the subsequent increase of steam generator 10-10 level trip setpoint
reached the actual steam generator level initiating the ESF actuation.
A few minutes later another inadvertent ESF actuation occurred resulting in
the automatic start of the A & B motor driven auxiliary feed pumps. An
electrician accidentally depressed a limit switch inside the reactor trip
breaker "A" (RTA) cabinet. After the cause was determined and corrected,
the plant was realigned to a normal shutdown lineup. The unit was in
Mode 3.
An evaluation of these incidents revealed the following concerns. Proce-
dural steps specifying that only one channel be tested at a time were
violated for both PT/1/A/4601/03, Protective System Channel III Functional
Test (Unit 1), steps 6.1 and 12.3 and IP/0/A/3207/03/K, Nuclear Instru-
mentation System (NIS) Power Range Drawer Calibration Procedure, Prerequi-
site 4.1. Furthermore, Control Room operators knew about this simultaneous
work and permitted it to be done.
TS 6.8.1 requires that written procedures shall be established, implemented,
and maintained covering the activities referenced in Appendix A of Regula-
tory Guide 1.33, Revision 2, February 1978 which includes the Nuclear
Instrumentation System. Contrary to this requirement, procedural steps
as noted above of PT/1/A/4601/03 and IP/0/A/3207/03K, were not correctly
implemented. This item in conjunction with the item in paragraph 14, is a
violation 369/85-06-02: Failure to Follow Procedure.
13. Diesel Generator Surveillance Inadequacies
On February 15, 1985, the licensee identified to the resident inspector that
McGuire has been in violation of TS Table 4.8-1, Diesel Generator Test
Schedule. This violation involved an interpretation of the criteria for
determining the number of failures and number of valid tests as identified
in the TS and Regulatory Guide 1.108, Rev.1. This criteria is based on
a per unit basis and the McGuire personnel had based their criteria on a per
diesel generator basis. Based on this interpretation, D/G 1A had a valid
failure on February 28, 1984, with unit start attempt 116 and a second valid
failure on July 22, 1984, with unit start attempt 133. On July 22, 1984,
the surveillance frequency for D/G 1A was increased to once every 14 days,
however, D/G 1B remained on a 31 day surveillance cycle. For Unit 2, D/G 2A
had a valid failure on July 8,1983, with unit start attempt 9, D/G2B had a
valid failure with unit start attempt 41. Since the criteria was not being
correctly interpreted at this time, it was not recognized that the surveil-
lance frequency for Unit 2 D/Gs was required to be increased to a frequency
of 14 days. Subsequently D/G 2B had another valid failure with unit start
attempt 42 on July 21, 1984, which should have increased the surveillance
to seven days for Unit 2 D/Gs. Action was taken at this time to increase
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surveillance frequency to D/G 2B to 14 days. On September 11, 1984, D/G 2A
again had a valid failure with unit start attempt 49. At this time D/G 2A
surveillance was increased to 14 days, when this was actually the 4th unit
failure and the frequency should have been increased to a 3 day interval.
On January 31,1985, D/G 2A had another failure which caused the diesel
to be declared inoperable and required disassembly and maintenance to be
performed which is still in progress at this time. On or about February 12,
1985, McGuire personnel recognized the interpretation problem and imple-
mented the 3 day requirement on 0/G 2B for Unit 2 and the 14 day requirement
on D/G1B for Unit 1. This item is identified as a violation 369/85-06-03,
370/85-06-01: Failure to Correctly Implement TS Surveillance Requirement
4.8.1.1.2.a.
14. Nuclear Service Water Valve Misalignment
During a routine tour of Unit 2, on January 23, 1985, the inspector
identified that 2RN-158 (RN pump 2B motor cooler inlet isolation) was not
" locked open" as required by 0P/2/A/6400/06, Nuclear Service Water System.
This observation was provided to the Shift Supervisor who took appropriate
corrective action. Subsequent investigation by McGuire station personnel as
described in Non-Routine Event Report No. 2-85-03 and Licensee Event Report
370/85-01 identified that this valve had apparently not been locked since
October 16, 1984. These reports concluded that this occurred as a result
of not adequately following 0P/0/A/6100/09, Removal and Restoration (R&R)
of Equipment. The R&R was issued October 15, to isolate RN pump 2B for
maintenance. On October 16, the R&R was cleared but the valve was returned
to an "open" position in lieu of " locked open" as prescribed by 0P/2/A/
6400/06. This failure to " lock open" this valve resulted in TS surveillance
4.7.4 not being accomplished for this valve since this valve is not checked
by the monthly surveillance test for this system. This item in conjunction
with the item in paragraph 12 is identified as a violation 370/85-06-02:
Failure to Follow Procedure OP/0/A/6100/09, Removal and Restoration of
Equipment For Valve 2RN-158.
15. Auxiliary Feedwater Overpressurization
The events relevant to auxiliary feedwater suction piping overpressurization
were analyzed in this, a followup inspection of an unresolved item (50-369/
85-08-07) identified in an earlier inspection report. There are two concerns
pertaining to this area. Both of these concerns are associated with a
failure to take appropriate corrective action in a timely manner. The first
concern is the lack of notification to plant operations personnel of a
potential problem with backleakage past feedwater check valves which could
potentially cause a degradation in the capability of auxiliary feedwater
pumps to fulfill this safety function. This was identified by a design
engineering memorandum in which a water hammer event occurred at a foreign
plant due to leaking check valves and piping configuration. In this memo
the engineer recommended a provision to provide indication of leakage past
the check valves and also recommend that operations perations personnel
should be cautioned about this potential problem. In addition, Westinghouse
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d
notified Duke Power Company (DPC) of the above backleakage problem in a
letter dated November 11, 1981. This letter also proposed modifications to
detect leakage and modify operating procedures to minimize this potential
problem.
A January 1984, report was issued discussing operability of industry
auxiliary feedwater pumps due to backleakage. This report provided specific
procedural guidance on how to detect backleakage and stated that actions to
- mitigate the situation should be provided. A DPC memorandum to various
superintendents dated June 22, 1984, identified among other recommendations
that operations should initiate as soon as possible a walkdown inspection
once per shift.
The second concern is a failure to adequately take prompt corrective action
for the improper installation of the turbine driven auxiliary feedwater pump
(TDAFWP) discharge stop check valve (ICA-22). On August 25, 1981, the
suction piping of the TDAFWP was overpressurized. Contributing to this
problem as reported in Reportable Occurrence Report R0-369/81-136 dated
September 8, 1981, was that the stop check valve in the pump discharge was
mounted in a horizontal pipe with the cylinder in a horizontal position so
that closure is not aided by gravity. Although this was identified as
a contributing factor, corrective action was not taken to correct this
deficiency. Following the January 1984 industry report and review by the
licensee, a DPC memo dated June 22, 1984, identified that stop check valves
were installed in a horizontal position and McGuire Projects should initiate
a Nuclear Station Modification (NSM) to correct this discrepancy. On
August 26 and again on August 30, 1984, the TDAFWP suction piping was
I
overpressurized due to back leakage past the check valves and the stop check
valve. It was not until September 5,1984, that NSMs were originated to
install a monitoring system to determine leakage past the check valves and
to correct the installation of the stop check valves, although this problem
was identified on various occasions since 1981.
10 CFR 50, Appendix B, Criterion XVI as implemented by Duke Power Company
(DPC) Topical Report, Quality Assurance Program Duke-1-A, Amendment 7,
Section 17.2.16 requires that conditions adverse to quality be promptly
identified and corrected and that the identification of the significant
condition, the cause of the condition 6nd the corrective action shall be
documented and reported to appropriate levels of management.
Contrary to the above, conditions adverse to quality were not promptly
identified and corrected, as detailed below. An occurrence on Unit 1 as
reported in R0-369/81-136, caused overpressurization of the suction side of
the turbine driven auxiliary feedwater pump. Identified as contributing to
this problem was the stop check valve on the outlet of the pump being
mounted in a horizontal position which prevents the closure of this valve to
be aided by gravity as designed. Furthermore, on November 11, 1981,
Westinghouse notified DPC of a potential problem concerning the design of
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10
the auxiliary feedwater pump discharge piping and valve arrangement such
that damage could occur which would compromise the safety-related function
of the auxiliary feedwater system. Westinghouse in this letter, recommended
system modifications and an operating procedures amendment to detect and
correct this problem.
No actions were taken on these items identified above until September 5,
1984, when NSM 1-1705 and NSM 2-0550 were generated to replace the existing
stop check valves with a different design valve, and NSM 1-1706 and NSM
2-0551 were generated to install a temperature monitoring system as
recommended by Westinghouse. As of March 12, 1985, NSM 1-1706 and NSM
2-0551 are in process of being installed and NSM 1-1705 and NSM 2-0550 are
scheduled for outages in 1986 due to material delivery.
This item is identified as a violation 369/85-06-04, 370/85-06-03: Failure
to Take Prompt Corrective Action to Notify Operations Personnel of Potential
Degradation of Auxiliary Feed Water System and Correct Improper Installation
of TDAFWP Discharge Stop Check Valve. This violation is applicable to both
units. This item closes unresolved item No. 50-369/85-08-07.
16. Containment Integrity
On February 19, 1985, valve 2SA-1 (the steam generator (S/G) 2C steam line to
the turbine driven auxiliary feedwater pump isolation valve) was disassembled
for maintenance. This created a possible flow path between inside contain-
ment and the interior doghouse. The valve was discovered disassembled by
the licensee on February 21, 1985, at 3:12 p.m. Between these times, core
alterations were made. TS 3.9.4 requires that containment integrity be
maintained during core alterations or movement of irradiated fuel within
containment. Core alterations are defined in TS definition 1.9 as the
movement or manipulation of any component within the reactor pressure vessel
, with the vessel head removed and fuel in the vessel. Suspension of core
l alteration shall not preclude completion of movement of a component to a
l safe conservative position. The valve being disassembled, in conjunction
with S/G 2C secondary side being open to containment atmosphere provided a
flow path directly from containment, through the S/G secondary side, through
the valve to the " dog house" (piping penetration room), directly to the
outside environment.
Two possible flow paths into S/G 2C existed inside containment. The sludge
lance cover plates were removed but the ports were taped closed with plastic
for housekeeping. These plates cover four two-inch ports and two six-inch
ports. A flow path also existed from containment atmosphere into the feed-
water line of S/G 2C, 2CF-27, a sixteen-inch check valve was disassembled
for maintenance, but plastic was taped over the valve body for housekeeping.
Operations personnel believe the containment purge ventilation system (VP)
was operating throughout the time 2SA-1 was open. This created a slight
vacuum within containment, ensuring any leakage would have been into
containment.
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The following steps are used in scheduling work during an outage:
a. The Outage Coordination group make a schedule of work to be performed
during an outage.
b. The Operations Unit Coordinator reviews the schedule.
c. Planning personnel schedule work requests using the Outage Coordination
group's schedule as a guideline,
d. Each work request is sent to the shift supervisor for clearance to
begin work.
The following occurred when scheduling the work on 2SA-1:
a. The work request description for 2SA-1 was typed in Project 2 as
"2SA-11".
b. Prior to core alterations, Operation staff personnel and Outage
Coordination personnel reviewed the outage schedule. The work on 2SA-1
was not identified as a potential containment integrity problem due to
the incorrect entry.
c. Planning personnel scheduled WR 1202930PS on February 18.
d. The Assistant Shift Supervisor signed the " clearance to begin work"
line on WR 1202930PS.
Once the work on 2SA-1 was scheduled, the Assistant Shift Supervisor was
the only control point to stop the work. It is not realistic to expect a
shift supervisor to catch every work request that could cause a containment
integrity problem during an outage because: (1) there are a large number
of containment penetrations and different ways to isolate each one (the
procedure used to verify containment integrity, PT/2/A/4700/02C, is 62 pages
long) and (2) the shift supervisor has a large number of work requests on
which to give clearance. The shift supervisors must depend on the Outage
Coordination group, the Unit Coordinator, and Planning to control scheduling
work on equ.ipment that can potentially affect containment integrity.
The Assistant Shift Supervisor stated that when he saw the work request on
2SA-1, he did not realize it could affect containment integrity. He saw
that 2SA-1 could be worked on using an existing tag out (block tag out 85-F)
so he signed the clearance line on the work request.
Corrective action to prevent future occurrence will include modifying work
request entries on outage schedules to note that the item is a " Potential
Containment Integrity Item." In future outages procedures will be modified
to reduce the likelihood of this event occurring by involving the Outage
12
Coordination Group, the Unit Coordinator and the Planners such that a
typographical error or oversight will be determined on a subsequent review
by one of these groups prior to sending the work request to operations for
clearance to begin work.
The above event is a licensee identified violation and will not be cited
since it meets the NRC enforcement criterion in 10 CFR 2, Appendix C.
17. Containment Pressure Control System (CPCS)
Subsequent to identification by the licensee, the inspector conducted a
review of TS 3.3.2, Engineered Safety Features Actuation System Instrumenta-
tion, specifically the Containment Pressure Control System (CPCS). The
function of the CPCS is to preclude depressurization of containment by
terminating containment spray and air return fans when they are no longer
required. TS Table 3.3-4 identifies the CPCS trip setpoint as &0.25 psid
for a start permissive and termination function. Table 3.3-3 identifies for
CPCS that for both the start permission and termination function there are
four total channels per train, implying a total of eight separate channels
(four for start permissive and four for termination). In actuality there
are a total of four channels per train to perform both functions. Also
Table 3.3-3 lists that two channels per train are required to trip. This
is in error. There are four pressure switches per channel: one switch
provides on an increasing pressure in containment, a permissive signal to
allow startup of the containment spray (NS) pump in that train, this switch
also provides an automatic trip signal if the spray pump is running and
containment pressure decreases to 0.25 psid; one pressure switch, on an
increasing pressure in containment provides a permissive signal to the NS
pump discharge valves, on a decreasing pressure of 0.25 psid this will
automatically shut these valves; one pressure switch provides a start
permissive signal for the Air Return and Hydrogen Skimmer Fan and will stop
the air return and Hydrogen Skimmer Fan on a decreasing pressure; and the
fourth pressure switch will provide a permissive signal for the hydrogen
skimmer fan discharge valve and the Air Return Fan damper, and will shut the
damper and valve on a decreasing pressure.
Table 3.3-3 also requires that CPCS must have a minimum of three channels
per train for operation. However, any failure of an individual pressure
switch would render that train inoperable, therefore all four pressure
switches should be required. The action statement for CPCS allows power
operation to continue with one less than the total number of channels if
(a) the channel is placed in the tripped position - there is no tripped
position for this instrument, and (b) the channel may be bypassed for up to
two hours for surveillance testing of other channels - there is no bypass
function for this channel.
The design for this system allows valves to be shut while pumps and/or fans
are running, which could cause damage to the component. The plant currently
operates under a TS interpretation which results in declaring an associated
component inoperable if any one or more of the four channels in that logic
train is inoperable.
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This item is identified as Unresolved Item (369/370-85-05): Resolution of
Containment Pressure Control System Design Questions, Pending Additional
Review By Regional and NRR Design Engineering Personnel.
18. Surveillance Testing
The surveillance tests categorized below were analyzed and/or witnessed
by the inspector to ascertain procedural and performance adequacy. The
completed test procedures examined were analyzed for embodiment of the
necessary test prerequisites, preparations, instructions, acceptance
criteria, and sufficiency of technical content. The selected tests
witnessed were examined to ascertain that current written approved
procedures were available and in use, that test equipment in use was
calibrated, that test prerequisites were met, system restoration completed
and test results were adequate. The selected procedures perused attested
conformance with applicable TS and procedural requirements, they appeared to
have received the required administrative review and they apparently were
performed within the surveillance frequency specified.
Surveillances
PT/1/A/4600/03E Quarterly Surveillance Items
PT/2/A/4600/01 RCCA Movement Test
PT/1/A/4350/02B Diesel Generator 1B Operability Test
PT/2/A/4150/16 Steam Generator Temperature Checklist
PT/2/A/4200/02C Containment Integrity Verification During Core
Alterations
PT/1/A/4204/02 ND Valve Stroke Timing
PT/1/A/4203/02 NB Valve Stroke Timing
PT/1/A/4451/02 VB Valve Stroke Timing
PT/1/A/4405/02 YM Valve Stroke Timing
PT/1/A/4208/01B NS Pump 1B PERF Test
PT/1/A/4208/01A NS Pump 1A PERF Test
PT/1/A/4403/01A RN Train A PERF Test
PT/1/A/4252/01A Motor Drive Aux Feed 1A PERF Test
PT/1/A/4209/018 NV Pump PERF Test
PT/0/A/4209/01C Standby Makeup Pump PERF Test
PT/1/A/4252/01 Aux Feed Pump #1 PERF Test
PT/0/A/4457/01A Control Room Chilled Water Pump 1 PERF Test
PT/1/A/4601/08A SSPS Train A Periodic Test
PT/1/A/4206/01A NI Pump 1A PERF Test
PT/1/A/4601/03 Proctive System Channel III
PT/0/A/4601/07A A reactor Trip Breaker Response Test
PT/0/A/4601/07B B Reactor Trip Breaker Response Test
19 Maintenance Observations
.
The maintenance activities categorized below were analyzed and/or witnessed
by the resident inspection staff to ascertain procedural and performance
adequacy. The completed procedures examined were analyzed for embodiment of
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14 ,
the necessary prerequisites, preparation, instruction, acceptance criteria
and sufficiency of technical detail. The selected activities witnessed were
examined to ascertain that where applicable, current written approved
procedures were available and in use, that prerequisites were met, equipment
restoration completed and maintenance results were adequate. The selected
work requests / maintenance packages perused attested conformance with
applicable TS and procedural requirements and appeared to have received the
required administrative review.
Work Request Equipment
65401 Battery EVCA
85953 Train B VX
93356 Train B VC
65320 Train B VC
41203 RF Pump C
123097 S/G C Narrow Range Level
119109 Loose Pails Detector
85884 Valve 1 SA 49
039480 Turbine Driven Auxiliary Feedwater
950119 A Train VC
93296 A Train VE
123349 Turbine Stop Valve TV#1
040175 Containment Pressure Channel III
03975 FWST Level
123092 Repair as Necessary "B" S/G PORV (ISU-13)
122989 Repair ICA-49 Check Valve
123014 D/G 1A Cylinder #2L Bad Temperature Indicator
Check and Repair
20. IE Circulars, Construction Deficiency Reports and Bulletin Closecut
The following IE Circulars and Construction Deficiency Reports are being
closed based on review of these items conducted at Region II:
Docket Number 50-369
CDR 82-06 78-CI-18
CDR 82-72 80-CI-03
CDR 83-15 80-CI-04
CDR 83-46 80-CI-13
80-CI-15
81-CI-13
81-CI-14
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15
Docket Number 50-370
CDR 81-06 81-CI-12
CDR 83-01 81-CI-13
CDR 83-03 81-CI-14
CDR 83-07
CDR 83-27
IE Bulletin 79-07, Seismic Stress Analysis of Safety-Related Piping, is
considered closed for the purposes of the Regional Inspection Program. This
closure does not affect the status of any NRR evaluations. Related inspec-
tion followup will be performed as required by IE Bulletin 79-14, Seismic
Analysis for As-Built Safety-Related Piping Systems.
L