Insp Rept 50-353/88-25 on 8880912-1016.Violations Noted. Major Areas Inspected:Work Activities,Procedures,Records Re Spent Fuel Pool Racks,Preoperational Test Procedure Review, Startup Test Activities,Engineering & Deficiency ReptsML20206C892 |
Person / Time |
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Site: |
Limerick ![Constellation icon.png](/w/images/b/be/Constellation_icon.png) |
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Issue date: |
10/28/1988 |
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From: |
Linville J, Williams J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
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To: |
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Shared Package |
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ML20206C877 |
List: |
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References |
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TASK-1.C.1, TASK-1.C.5, TASK-2.D.3, TASK-2.E.4.2, TASK-2.K.1, TASK-2.K.3.13, TASK-2.K.3.18, TASK-2.K.3.24, TASK-TM 50-353-88-25, IEB-76-04, IEB-76-4, IEB-88-005, IEB-88-5, IEC-80-25, NUDOCS 8811160450 |
Download: ML20206C892 (22) |
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Category:INSPECTION REPORT
MONTHYEARIR 05000352/19990051999-09-16016 September 1999 Insp Repts 50-352/99-05 & 50-353/99-05 on 990713-0816.One Violation Noted & Being Treated as Ncv.Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000352/19990041999-08-10010 August 1999 Insp Repts 50-352/99-04 & 50-353/99-04 on 990525-0712.One Violation Noted & Being Treated as Ncv.Major Areas Inspected:Aspects of Licensee Operations,Engineering & Maint IR 05000352/19990031999-06-24024 June 1999 Insp Repts 50-352/99-03 & 50-353/99-03 on 990413-0524.No Violations Noted.Major Areas Inspected:Operations, Maintenance,Engineering & Plant Support.Also Inspected, Radiological Protection,Security & Inservice Insp IR 05000352/19990021999-05-0707 May 1999 Insp Repts 50-352/99-02 & 50-353/99-02 on 990302-0412. Violations Noted & Being Treated as non-cited Violations. Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000352/19990011999-03-26026 March 1999 Insp Repts 50-352/99-01 & 50-353/99-01 on 990112-0301. Violations Noted.Major Areas Inspected:Operations, Engineering,Maint & Plant Support ML20199C6641999-01-0606 January 1999 Insp Repts 50-352/98-09 & 50-353/98-09 on 981018-1130. Violations Noted.Major Areas Inspected:Operations, Engineering,Maintenance & Plant Support ML20196C3371998-11-23023 November 1998 Insp Repts 50-352/98-08 & 50-353/98-08 on 980901-1017.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support.Security & Safeguards Activities Were Conducted in Manner That Protected Public Health IR 05000352/19980071998-09-25025 September 1998 Insp Repts 50-352/98-07 & 50-353/98-07 on 980707-0831.No Violations Noted.Major Areas Inspected:Operations, Engineering,Maint & Plant Support IR 05000352/19980051998-08-0707 August 1998 Insp Repts 50-352/98-05 & 50-353/98-05 on 980601-24. Violations Noted.Major Areas Inspected:Backlogged Engineering Activities IR 05000352/19980041998-08-0505 August 1998 Insp Repts 50-352/98-04 & 50-353/98-04 on 980519-0706. Violations Noted.Major Areas Inspected:Aspects of PECO Energy Operations,Engineering & Maint IR 05000352/19980031998-06-18018 June 1998 Insp Repts 50-352/98-03 & 50-353/98-03 on 980317-0518. Violations Noted.Major Areas Inspected:Aspects of PECO Energy Operations,Engineering,Maint & Plant Support ML20247J2451998-05-11011 May 1998 Insp Repts 50-352/98-02 & 50-353/98-02 on 980120-0316. Violations Noted.Major Areas Inspected:Operations, Engineering,Maintenance & Plant Support IR 05000353/19970091998-03-11011 March 1998 Insp Rept 50-353/97-09 on 971010-980116.Violations Noted. Major Areas Inspected:Operations,Maintenance,Engineering & Plant Support ML20203G9211998-02-23023 February 1998 Insp Repts 50-352/97-10 & 50-353/97-10 on 971118-980119. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000352/19970081997-12-0808 December 1997 Insp Repts 50-352/97-08 & 50-353/97-08 on 970916-1117.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support ML20198N1771997-10-27027 October 1997 Insp Repts 50-352/97-07 & 50-353/97-07 on 970722-0915. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000352/19970061997-08-13013 August 1997 Insp Repts 50-352/97-06 & 50-353/97-06 on 970528-0721. Violations Noted.Major Areas Inspected:Peco Energy Operations,Engineering,Maintenance & Plant Support IR 05000352/19970051997-07-31031 July 1997 Insp Repts 50-352/97-05 & 50-353/97-05 on 970623-26.No Violations Noted.Major Areas Inspected:Licensee Performance During Biennial full-participation EP Exercise IR 05000352/19970031997-07-11011 July 1997 Insp Repts 50-352/97-03 & 50-353/97-03 on 970330-0527. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000352/19970011997-05-0707 May 1997 Insp Repts 50-352/97-01 & 50-353/97-01 on 970204-0329. Violations Noted.Major Areas Inspected:Operations, Engineering,Plant Support & Maintenance ML20136C0951997-03-0606 March 1997 Insp Repts 50-352/96-10 & 50-353/96-10 on 961217-970203. Violations Noted.Major Areas Inspected:Operations, Engineering,Maint & Plant Support ML20133H7391997-01-0909 January 1997 Insp Repts 50-352/96-09 & 50-353/96-09 on 961022-1216. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support ML20132G4901996-12-20020 December 1996 Insp Repts 50-277/96-11,50-278/96-11,50-352/96-08 & 50-353/96-08 on 961003-1127.No Violations Noted.Major Areas Inspected:Documentations Containing Safeguards Info IR 05000352/19960071996-11-15015 November 1996 Insp Repts 50-352/96-07 & 50-353/96-07 on 960827-1021. Violations Noted.Major Areas Inspected:Conduct of Operations,Operational Status of Facilities & Equipment & Operations Procedures & Documentation IR 05000352/19950191996-02-0909 February 1996 Insp Repts 50-352/95-19 & 50-353/95-19 on 951120-1201. No Violations Noted.Major Areas Inspected:Program Implementation,Status & Scope,Operating Sizing & Settings IR 05000352/19940231994-11-10010 November 1994 Insp Repts 50-352/94-23 & 50-353/94-23 on 940927-1031. Violations Noted.Major Areas Inspected:Plant Operations, Maint,Surveillance,Engineering,Plant Support & Safety Assessment & Quality Verification IR 05000352/19930311993-12-30030 December 1993 Insp Repts 50-352/93-31 & 50-353/93-31 on 931201.No Violations Noted.Major Areas Inspected:Protected Area Physical Barriers & Detection Aids IR 05000352/19930291993-12-22022 December 1993 Insp Repts 50-352/93-29 & 50-353/93-29 on 931102-1213.No Violations Noted.Major Areas Inspected:Plant Operations, Maint,Engineering,Plant Support & Review of Licensee Event & Routine Repts IR 05000352/19930271993-11-29029 November 1993 Insp Repts 50-352/93-27 & 50-353/93-27 on 931101-05.No Violations Noted.Major Areas Inspected:Licensed Operator Requalification Training Program IR 05000352/19930261993-11-19019 November 1993 Insp Repts 50-352/93-26 & 50-353/93-26 on 931004-08.No Violations Noted.Major Areas Inspected:Review of Licensee Corrective Actions of Nine Previously Identified Edsfi Findings Including Escalated Enforcement Item IR 05000352/19930191993-11-10010 November 1993 Insp Repts 50-352/93-19 & 50-353/93-19 on 930928-30.No Weaknesses Noted.Major Areas Inspected:Annual full- Participation Emergency Preparedness Exercise IR 05000352/19930251993-11-0808 November 1993 Insp Repts 50-352/93-25 & 50-353/93-25 on 930926-1101. Enforcement Discretion Exercised Re Missed Firewatch.Major Areas Inspected:Plant Operations,Maint,Surveillance,Plant Support & LER Re Missed Firewatch IR 05000352/19930241993-11-0101 November 1993 Insp Repts 50-352/93-24 & 50-353/93-24 on 930908-14.No Violations Noted.Major Areas Inspected:Reviewed Causes Leading to Loss of One Offsite Electrical Power Source & Subsequent Reactor Scram at Plant IR 05000352/19930231993-10-25025 October 1993 Insp Repts 50-352/93-23 & 50-353/93-23 on 930907-14. No Violations Noted.Major Areas Inspected:Radiological Controls Program Enhancements,Qa Oversight Activities & Contamination Control Program IR 05000352/19930221993-10-13013 October 1993 Insp Repts 50-352/93-22 & 50-353/93-22 on 930817-0925. Violations Noted.Major Areas Inspected:Plant Operations, Maint,Surveillance & Engineering & Technical Support IR 05000352/19930201993-09-0909 September 1993 Insp Repts 50-352/93-20 & 50-353/93-20 on 930816-20.No Violations Noted.Major Areas Inspected:Technical Support of Plant Operations,Configuration Mgt,Pep,Esw & Residual Improvement Programs IR 05000352/19930111993-08-27027 August 1993 Insp Repts 50-352/93-11 & 50-353/93-11 on 930524-27.No Violations Noted.Major Areas Inspected:Changes to Emergency Plan & Implementing Procedures;Emergency Facilities, Equipment,Instrumentation & Supplies IR 05000352/19930101993-08-13013 August 1993 Erratum to Insp Repts 50-352/93-10 & 50-353/93-10 IR 05000352/19930171993-08-0202 August 1993 Insp Repts 50-352/93-17 & 50-353/93-17 on 930706-09.Two Unresolved Items Identified.Major Areas Inspected:Storage, Radioactive Waste Handling,Processing & Transportation Programs IR 05000352/19930011993-02-0404 February 1993 Insp Repts 50-352/93-01 & 50-353/93-01 on 930111-15.No Violations Noted.Major Areas Inspected:Radiological & non-radiological Chemistry Programs,Including Confirmatory Measurements IR 05000352/19920291993-01-27027 January 1993 Insp Repts 50-352/92-29 & 50-353/92-29 on 921115-930102. Noncited Violations Noted.Major Areas inspected:921204 Reactor Trip & Maint Efforts to Return Unit to Svc IR 05000352/19920301992-12-30030 December 1992 Insp Repts 50-352/92-30 & 50-353/92-30 on 921130-1204.No Violations Noted.Major Areas Inspected:Design Mods, Experience & Professional Proficiency of Engineering Staff Engaged in Design Mods IR 05000277/19920331992-12-11011 December 1992 Corrected Insp Repts 50-277/92-33,50-278/92-33,50-352/92-28 50-353/92-28 on 921123-25.Previously Missing Line from Page 8 of Original Rept Appears at Top of Page 9 ML20127F2831992-12-11011 December 1992 Insp Repts 50-277/92-33,50-278/92-33,50-352/92-28 & 50-353/92-28 on 921123-25.No Violations Noted.Major Areas Inspected:Annual partial-participation Exercise Conducted on 921124 IR 05000352/19920271992-12-0707 December 1992 Insp Repts 50-352/92-27 & 50-353/92-27 on 921004-1114. Violations Noted.Major Areas Inspected:Plant Operations, Surveillance & Maintenance,Engineering & Technical Support & Safety Assessment & Quality Verification IR 05000352/19920811992-12-0404 December 1992 Edsfi Repts 50-352/92-81 & 50-353/92-81 on Stated Date. Violations Noted.Major Areas Inspected:Review of Functionality of Electrical Distribution Sys IR 05000352/19920141992-05-0606 May 1992 Insp Repts 50-352/92-14 & 50-353/92-14 on 920420-24. Violations Noted.Major Areas Inspected:Review of Status of Radioactive Material,Staffing & Qualifications of Contractor Technicians,Alara & Tours of Radiological Controls Area IR 05000352/19900211990-11-15015 November 1990 Insp Repts 50-352/90-21 & 50-353/90-20 on 900827-31.No Violations Noted.Major Areas Inspected:Emeergency Preparedness Program IR 05000352/19900241990-10-26026 October 1990 Radiological Safety Insp Rept 50-352/90-24 & 50-353/90-23 on 901001-05.No Violations Noted.Major Areas Inspected: Radiological Safety Insp of Licensee Radiological Controls Program IR 05000352/19900221990-10-18018 October 1990 Insp Repts 50-352/90-22 & 50-353/90-21 on 900912-19.No Violations Noted.Major Areas Inspected:Engineering Organization,Staffing,Communications,Mgt Support,Design Changes & Mod Process 1999-09-16
[Table view] Category:NRC-GENERATED
MONTHYEARIR 05000352/19990051999-09-16016 September 1999 Insp Repts 50-352/99-05 & 50-353/99-05 on 990713-0816.One Violation Noted & Being Treated as Ncv.Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000352/19990041999-08-10010 August 1999 Insp Repts 50-352/99-04 & 50-353/99-04 on 990525-0712.One Violation Noted & Being Treated as Ncv.Major Areas Inspected:Aspects of Licensee Operations,Engineering & Maint IR 05000352/19990031999-06-24024 June 1999 Insp Repts 50-352/99-03 & 50-353/99-03 on 990413-0524.No Violations Noted.Major Areas Inspected:Operations, Maintenance,Engineering & Plant Support.Also Inspected, Radiological Protection,Security & Inservice Insp IR 05000352/19990021999-05-0707 May 1999 Insp Repts 50-352/99-02 & 50-353/99-02 on 990302-0412. Violations Noted & Being Treated as non-cited Violations. Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000352/19990011999-03-26026 March 1999 Insp Repts 50-352/99-01 & 50-353/99-01 on 990112-0301. Violations Noted.Major Areas Inspected:Operations, Engineering,Maint & Plant Support ML20199C6641999-01-0606 January 1999 Insp Repts 50-352/98-09 & 50-353/98-09 on 981018-1130. Violations Noted.Major Areas Inspected:Operations, Engineering,Maintenance & Plant Support ML20196C3371998-11-23023 November 1998 Insp Repts 50-352/98-08 & 50-353/98-08 on 980901-1017.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support.Security & Safeguards Activities Were Conducted in Manner That Protected Public Health IR 05000352/19980071998-09-25025 September 1998 Insp Repts 50-352/98-07 & 50-353/98-07 on 980707-0831.No Violations Noted.Major Areas Inspected:Operations, Engineering,Maint & Plant Support IR 05000352/19980051998-08-0707 August 1998 Insp Repts 50-352/98-05 & 50-353/98-05 on 980601-24. Violations Noted.Major Areas Inspected:Backlogged Engineering Activities IR 05000352/19980041998-08-0505 August 1998 Insp Repts 50-352/98-04 & 50-353/98-04 on 980519-0706. Violations Noted.Major Areas Inspected:Aspects of PECO Energy Operations,Engineering & Maint IR 05000352/19980031998-06-18018 June 1998 Insp Repts 50-352/98-03 & 50-353/98-03 on 980317-0518. Violations Noted.Major Areas Inspected:Aspects of PECO Energy Operations,Engineering,Maint & Plant Support ML20247J2451998-05-11011 May 1998 Insp Repts 50-352/98-02 & 50-353/98-02 on 980120-0316. Violations Noted.Major Areas Inspected:Operations, Engineering,Maintenance & Plant Support IR 05000353/19970091998-03-11011 March 1998 Insp Rept 50-353/97-09 on 971010-980116.Violations Noted. Major Areas Inspected:Operations,Maintenance,Engineering & Plant Support ML20203G9211998-02-23023 February 1998 Insp Repts 50-352/97-10 & 50-353/97-10 on 971118-980119. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000352/19970081997-12-0808 December 1997 Insp Repts 50-352/97-08 & 50-353/97-08 on 970916-1117.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support ML20198N1771997-10-27027 October 1997 Insp Repts 50-352/97-07 & 50-353/97-07 on 970722-0915. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000352/19970061997-08-13013 August 1997 Insp Repts 50-352/97-06 & 50-353/97-06 on 970528-0721. Violations Noted.Major Areas Inspected:Peco Energy Operations,Engineering,Maintenance & Plant Support IR 05000352/19970051997-07-31031 July 1997 Insp Repts 50-352/97-05 & 50-353/97-05 on 970623-26.No Violations Noted.Major Areas Inspected:Licensee Performance During Biennial full-participation EP Exercise IR 05000352/19970031997-07-11011 July 1997 Insp Repts 50-352/97-03 & 50-353/97-03 on 970330-0527. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000352/19970011997-05-0707 May 1997 Insp Repts 50-352/97-01 & 50-353/97-01 on 970204-0329. Violations Noted.Major Areas Inspected:Operations, Engineering,Plant Support & Maintenance ML20136C0951997-03-0606 March 1997 Insp Repts 50-352/96-10 & 50-353/96-10 on 961217-970203. Violations Noted.Major Areas Inspected:Operations, Engineering,Maint & Plant Support ML20133H7391997-01-0909 January 1997 Insp Repts 50-352/96-09 & 50-353/96-09 on 961022-1216. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support ML20132G4901996-12-20020 December 1996 Insp Repts 50-277/96-11,50-278/96-11,50-352/96-08 & 50-353/96-08 on 961003-1127.No Violations Noted.Major Areas Inspected:Documentations Containing Safeguards Info IR 05000352/19960071996-11-15015 November 1996 Insp Repts 50-352/96-07 & 50-353/96-07 on 960827-1021. Violations Noted.Major Areas Inspected:Conduct of Operations,Operational Status of Facilities & Equipment & Operations Procedures & Documentation IR 05000352/19950191996-02-0909 February 1996 Insp Repts 50-352/95-19 & 50-353/95-19 on 951120-1201. No Violations Noted.Major Areas Inspected:Program Implementation,Status & Scope,Operating Sizing & Settings IR 05000352/19940231994-11-10010 November 1994 Insp Repts 50-352/94-23 & 50-353/94-23 on 940927-1031. Violations Noted.Major Areas Inspected:Plant Operations, Maint,Surveillance,Engineering,Plant Support & Safety Assessment & Quality Verification IR 05000352/19930311993-12-30030 December 1993 Insp Repts 50-352/93-31 & 50-353/93-31 on 931201.No Violations Noted.Major Areas Inspected:Protected Area Physical Barriers & Detection Aids IR 05000352/19930291993-12-22022 December 1993 Insp Repts 50-352/93-29 & 50-353/93-29 on 931102-1213.No Violations Noted.Major Areas Inspected:Plant Operations, Maint,Engineering,Plant Support & Review of Licensee Event & Routine Repts IR 05000352/19930271993-11-29029 November 1993 Insp Repts 50-352/93-27 & 50-353/93-27 on 931101-05.No Violations Noted.Major Areas Inspected:Licensed Operator Requalification Training Program IR 05000352/19930261993-11-19019 November 1993 Insp Repts 50-352/93-26 & 50-353/93-26 on 931004-08.No Violations Noted.Major Areas Inspected:Review of Licensee Corrective Actions of Nine Previously Identified Edsfi Findings Including Escalated Enforcement Item IR 05000352/19930191993-11-10010 November 1993 Insp Repts 50-352/93-19 & 50-353/93-19 on 930928-30.No Weaknesses Noted.Major Areas Inspected:Annual full- Participation Emergency Preparedness Exercise IR 05000352/19930251993-11-0808 November 1993 Insp Repts 50-352/93-25 & 50-353/93-25 on 930926-1101. Enforcement Discretion Exercised Re Missed Firewatch.Major Areas Inspected:Plant Operations,Maint,Surveillance,Plant Support & LER Re Missed Firewatch IR 05000352/19930241993-11-0101 November 1993 Insp Repts 50-352/93-24 & 50-353/93-24 on 930908-14.No Violations Noted.Major Areas Inspected:Reviewed Causes Leading to Loss of One Offsite Electrical Power Source & Subsequent Reactor Scram at Plant IR 05000352/19930231993-10-25025 October 1993 Insp Repts 50-352/93-23 & 50-353/93-23 on 930907-14. No Violations Noted.Major Areas Inspected:Radiological Controls Program Enhancements,Qa Oversight Activities & Contamination Control Program IR 05000352/19930221993-10-13013 October 1993 Insp Repts 50-352/93-22 & 50-353/93-22 on 930817-0925. Violations Noted.Major Areas Inspected:Plant Operations, Maint,Surveillance & Engineering & Technical Support IR 05000352/19930201993-09-0909 September 1993 Insp Repts 50-352/93-20 & 50-353/93-20 on 930816-20.No Violations Noted.Major Areas Inspected:Technical Support of Plant Operations,Configuration Mgt,Pep,Esw & Residual Improvement Programs IR 05000352/19930111993-08-27027 August 1993 Insp Repts 50-352/93-11 & 50-353/93-11 on 930524-27.No Violations Noted.Major Areas Inspected:Changes to Emergency Plan & Implementing Procedures;Emergency Facilities, Equipment,Instrumentation & Supplies IR 05000352/19930101993-08-13013 August 1993 Erratum to Insp Repts 50-352/93-10 & 50-353/93-10 IR 05000352/19930171993-08-0202 August 1993 Insp Repts 50-352/93-17 & 50-353/93-17 on 930706-09.Two Unresolved Items Identified.Major Areas Inspected:Storage, Radioactive Waste Handling,Processing & Transportation Programs IR 05000352/19930011993-02-0404 February 1993 Insp Repts 50-352/93-01 & 50-353/93-01 on 930111-15.No Violations Noted.Major Areas Inspected:Radiological & non-radiological Chemistry Programs,Including Confirmatory Measurements IR 05000352/19920291993-01-27027 January 1993 Insp Repts 50-352/92-29 & 50-353/92-29 on 921115-930102. Noncited Violations Noted.Major Areas inspected:921204 Reactor Trip & Maint Efforts to Return Unit to Svc IR 05000352/19920301992-12-30030 December 1992 Insp Repts 50-352/92-30 & 50-353/92-30 on 921130-1204.No Violations Noted.Major Areas Inspected:Design Mods, Experience & Professional Proficiency of Engineering Staff Engaged in Design Mods IR 05000277/19920331992-12-11011 December 1992 Corrected Insp Repts 50-277/92-33,50-278/92-33,50-352/92-28 50-353/92-28 on 921123-25.Previously Missing Line from Page 8 of Original Rept Appears at Top of Page 9 ML20127F2831992-12-11011 December 1992 Insp Repts 50-277/92-33,50-278/92-33,50-352/92-28 & 50-353/92-28 on 921123-25.No Violations Noted.Major Areas Inspected:Annual partial-participation Exercise Conducted on 921124 IR 05000352/19920271992-12-0707 December 1992 Insp Repts 50-352/92-27 & 50-353/92-27 on 921004-1114. Violations Noted.Major Areas Inspected:Plant Operations, Surveillance & Maintenance,Engineering & Technical Support & Safety Assessment & Quality Verification IR 05000352/19920811992-12-0404 December 1992 Edsfi Repts 50-352/92-81 & 50-353/92-81 on Stated Date. Violations Noted.Major Areas Inspected:Review of Functionality of Electrical Distribution Sys IR 05000352/19920141992-05-0606 May 1992 Insp Repts 50-352/92-14 & 50-353/92-14 on 920420-24. Violations Noted.Major Areas Inspected:Review of Status of Radioactive Material,Staffing & Qualifications of Contractor Technicians,Alara & Tours of Radiological Controls Area IR 05000352/19900211990-11-15015 November 1990 Insp Repts 50-352/90-21 & 50-353/90-20 on 900827-31.No Violations Noted.Major Areas Inspected:Emeergency Preparedness Program IR 05000352/19900241990-10-26026 October 1990 Radiological Safety Insp Rept 50-352/90-24 & 50-353/90-23 on 901001-05.No Violations Noted.Major Areas Inspected: Radiological Safety Insp of Licensee Radiological Controls Program IR 05000352/19900221990-10-18018 October 1990 Insp Repts 50-352/90-22 & 50-353/90-21 on 900912-19.No Violations Noted.Major Areas Inspected:Engineering Organization,Staffing,Communications,Mgt Support,Design Changes & Mod Process 1999-09-16
[Table view] Category:INSPECTION REPORT
MONTHYEARIR 05000352/19990051999-09-16016 September 1999 Insp Repts 50-352/99-05 & 50-353/99-05 on 990713-0816.One Violation Noted & Being Treated as Ncv.Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000352/19990041999-08-10010 August 1999 Insp Repts 50-352/99-04 & 50-353/99-04 on 990525-0712.One Violation Noted & Being Treated as Ncv.Major Areas Inspected:Aspects of Licensee Operations,Engineering & Maint IR 05000352/19990031999-06-24024 June 1999 Insp Repts 50-352/99-03 & 50-353/99-03 on 990413-0524.No Violations Noted.Major Areas Inspected:Operations, Maintenance,Engineering & Plant Support.Also Inspected, Radiological Protection,Security & Inservice Insp IR 05000352/19990021999-05-0707 May 1999 Insp Repts 50-352/99-02 & 50-353/99-02 on 990302-0412. Violations Noted & Being Treated as non-cited Violations. Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000352/19990011999-03-26026 March 1999 Insp Repts 50-352/99-01 & 50-353/99-01 on 990112-0301. Violations Noted.Major Areas Inspected:Operations, Engineering,Maint & Plant Support ML20199C6641999-01-0606 January 1999 Insp Repts 50-352/98-09 & 50-353/98-09 on 981018-1130. Violations Noted.Major Areas Inspected:Operations, Engineering,Maintenance & Plant Support ML20196C3371998-11-23023 November 1998 Insp Repts 50-352/98-08 & 50-353/98-08 on 980901-1017.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support.Security & Safeguards Activities Were Conducted in Manner That Protected Public Health IR 05000352/19980071998-09-25025 September 1998 Insp Repts 50-352/98-07 & 50-353/98-07 on 980707-0831.No Violations Noted.Major Areas Inspected:Operations, Engineering,Maint & Plant Support IR 05000352/19980051998-08-0707 August 1998 Insp Repts 50-352/98-05 & 50-353/98-05 on 980601-24. Violations Noted.Major Areas Inspected:Backlogged Engineering Activities IR 05000352/19980041998-08-0505 August 1998 Insp Repts 50-352/98-04 & 50-353/98-04 on 980519-0706. Violations Noted.Major Areas Inspected:Aspects of PECO Energy Operations,Engineering & Maint IR 05000352/19980031998-06-18018 June 1998 Insp Repts 50-352/98-03 & 50-353/98-03 on 980317-0518. Violations Noted.Major Areas Inspected:Aspects of PECO Energy Operations,Engineering,Maint & Plant Support ML20247J2451998-05-11011 May 1998 Insp Repts 50-352/98-02 & 50-353/98-02 on 980120-0316. Violations Noted.Major Areas Inspected:Operations, Engineering,Maintenance & Plant Support IR 05000353/19970091998-03-11011 March 1998 Insp Rept 50-353/97-09 on 971010-980116.Violations Noted. Major Areas Inspected:Operations,Maintenance,Engineering & Plant Support ML20203G9211998-02-23023 February 1998 Insp Repts 50-352/97-10 & 50-353/97-10 on 971118-980119. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000352/19970081997-12-0808 December 1997 Insp Repts 50-352/97-08 & 50-353/97-08 on 970916-1117.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support ML20198N1771997-10-27027 October 1997 Insp Repts 50-352/97-07 & 50-353/97-07 on 970722-0915. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000352/19970061997-08-13013 August 1997 Insp Repts 50-352/97-06 & 50-353/97-06 on 970528-0721. Violations Noted.Major Areas Inspected:Peco Energy Operations,Engineering,Maintenance & Plant Support IR 05000352/19970051997-07-31031 July 1997 Insp Repts 50-352/97-05 & 50-353/97-05 on 970623-26.No Violations Noted.Major Areas Inspected:Licensee Performance During Biennial full-participation EP Exercise IR 05000352/19970031997-07-11011 July 1997 Insp Repts 50-352/97-03 & 50-353/97-03 on 970330-0527. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000352/19970011997-05-0707 May 1997 Insp Repts 50-352/97-01 & 50-353/97-01 on 970204-0329. Violations Noted.Major Areas Inspected:Operations, Engineering,Plant Support & Maintenance ML20136C0951997-03-0606 March 1997 Insp Repts 50-352/96-10 & 50-353/96-10 on 961217-970203. Violations Noted.Major Areas Inspected:Operations, Engineering,Maint & Plant Support ML20133H7391997-01-0909 January 1997 Insp Repts 50-352/96-09 & 50-353/96-09 on 961022-1216. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support ML20132G4901996-12-20020 December 1996 Insp Repts 50-277/96-11,50-278/96-11,50-352/96-08 & 50-353/96-08 on 961003-1127.No Violations Noted.Major Areas Inspected:Documentations Containing Safeguards Info IR 05000352/19960071996-11-15015 November 1996 Insp Repts 50-352/96-07 & 50-353/96-07 on 960827-1021. Violations Noted.Major Areas Inspected:Conduct of Operations,Operational Status of Facilities & Equipment & Operations Procedures & Documentation IR 05000352/19950191996-02-0909 February 1996 Insp Repts 50-352/95-19 & 50-353/95-19 on 951120-1201. No Violations Noted.Major Areas Inspected:Program Implementation,Status & Scope,Operating Sizing & Settings IR 05000352/19940231994-11-10010 November 1994 Insp Repts 50-352/94-23 & 50-353/94-23 on 940927-1031. Violations Noted.Major Areas Inspected:Plant Operations, Maint,Surveillance,Engineering,Plant Support & Safety Assessment & Quality Verification IR 05000352/19930311993-12-30030 December 1993 Insp Repts 50-352/93-31 & 50-353/93-31 on 931201.No Violations Noted.Major Areas Inspected:Protected Area Physical Barriers & Detection Aids IR 05000352/19930291993-12-22022 December 1993 Insp Repts 50-352/93-29 & 50-353/93-29 on 931102-1213.No Violations Noted.Major Areas Inspected:Plant Operations, Maint,Engineering,Plant Support & Review of Licensee Event & Routine Repts IR 05000352/19930271993-11-29029 November 1993 Insp Repts 50-352/93-27 & 50-353/93-27 on 931101-05.No Violations Noted.Major Areas Inspected:Licensed Operator Requalification Training Program IR 05000352/19930261993-11-19019 November 1993 Insp Repts 50-352/93-26 & 50-353/93-26 on 931004-08.No Violations Noted.Major Areas Inspected:Review of Licensee Corrective Actions of Nine Previously Identified Edsfi Findings Including Escalated Enforcement Item IR 05000352/19930191993-11-10010 November 1993 Insp Repts 50-352/93-19 & 50-353/93-19 on 930928-30.No Weaknesses Noted.Major Areas Inspected:Annual full- Participation Emergency Preparedness Exercise IR 05000352/19930251993-11-0808 November 1993 Insp Repts 50-352/93-25 & 50-353/93-25 on 930926-1101. Enforcement Discretion Exercised Re Missed Firewatch.Major Areas Inspected:Plant Operations,Maint,Surveillance,Plant Support & LER Re Missed Firewatch IR 05000352/19930241993-11-0101 November 1993 Insp Repts 50-352/93-24 & 50-353/93-24 on 930908-14.No Violations Noted.Major Areas Inspected:Reviewed Causes Leading to Loss of One Offsite Electrical Power Source & Subsequent Reactor Scram at Plant IR 05000352/19930231993-10-25025 October 1993 Insp Repts 50-352/93-23 & 50-353/93-23 on 930907-14. No Violations Noted.Major Areas Inspected:Radiological Controls Program Enhancements,Qa Oversight Activities & Contamination Control Program IR 05000352/19930221993-10-13013 October 1993 Insp Repts 50-352/93-22 & 50-353/93-22 on 930817-0925. Violations Noted.Major Areas Inspected:Plant Operations, Maint,Surveillance & Engineering & Technical Support IR 05000352/19930201993-09-0909 September 1993 Insp Repts 50-352/93-20 & 50-353/93-20 on 930816-20.No Violations Noted.Major Areas Inspected:Technical Support of Plant Operations,Configuration Mgt,Pep,Esw & Residual Improvement Programs IR 05000352/19930111993-08-27027 August 1993 Insp Repts 50-352/93-11 & 50-353/93-11 on 930524-27.No Violations Noted.Major Areas Inspected:Changes to Emergency Plan & Implementing Procedures;Emergency Facilities, Equipment,Instrumentation & Supplies IR 05000352/19930101993-08-13013 August 1993 Erratum to Insp Repts 50-352/93-10 & 50-353/93-10 IR 05000352/19930171993-08-0202 August 1993 Insp Repts 50-352/93-17 & 50-353/93-17 on 930706-09.Two Unresolved Items Identified.Major Areas Inspected:Storage, Radioactive Waste Handling,Processing & Transportation Programs IR 05000352/19930011993-02-0404 February 1993 Insp Repts 50-352/93-01 & 50-353/93-01 on 930111-15.No Violations Noted.Major Areas Inspected:Radiological & non-radiological Chemistry Programs,Including Confirmatory Measurements IR 05000352/19920291993-01-27027 January 1993 Insp Repts 50-352/92-29 & 50-353/92-29 on 921115-930102. Noncited Violations Noted.Major Areas inspected:921204 Reactor Trip & Maint Efforts to Return Unit to Svc IR 05000352/19920301992-12-30030 December 1992 Insp Repts 50-352/92-30 & 50-353/92-30 on 921130-1204.No Violations Noted.Major Areas Inspected:Design Mods, Experience & Professional Proficiency of Engineering Staff Engaged in Design Mods IR 05000277/19920331992-12-11011 December 1992 Corrected Insp Repts 50-277/92-33,50-278/92-33,50-352/92-28 50-353/92-28 on 921123-25.Previously Missing Line from Page 8 of Original Rept Appears at Top of Page 9 ML20127F2831992-12-11011 December 1992 Insp Repts 50-277/92-33,50-278/92-33,50-352/92-28 & 50-353/92-28 on 921123-25.No Violations Noted.Major Areas Inspected:Annual partial-participation Exercise Conducted on 921124 IR 05000352/19920271992-12-0707 December 1992 Insp Repts 50-352/92-27 & 50-353/92-27 on 921004-1114. Violations Noted.Major Areas Inspected:Plant Operations, Surveillance & Maintenance,Engineering & Technical Support & Safety Assessment & Quality Verification IR 05000352/19920811992-12-0404 December 1992 Edsfi Repts 50-352/92-81 & 50-353/92-81 on Stated Date. Violations Noted.Major Areas Inspected:Review of Functionality of Electrical Distribution Sys IR 05000352/19920141992-05-0606 May 1992 Insp Repts 50-352/92-14 & 50-353/92-14 on 920420-24. Violations Noted.Major Areas Inspected:Review of Status of Radioactive Material,Staffing & Qualifications of Contractor Technicians,Alara & Tours of Radiological Controls Area IR 05000352/19900211990-11-15015 November 1990 Insp Repts 50-352/90-21 & 50-353/90-20 on 900827-31.No Violations Noted.Major Areas Inspected:Emeergency Preparedness Program IR 05000352/19900241990-10-26026 October 1990 Radiological Safety Insp Rept 50-352/90-24 & 50-353/90-23 on 901001-05.No Violations Noted.Major Areas Inspected: Radiological Safety Insp of Licensee Radiological Controls Program IR 05000352/19900221990-10-18018 October 1990 Insp Repts 50-352/90-22 & 50-353/90-21 on 900912-19.No Violations Noted.Major Areas Inspected:Engineering Organization,Staffing,Communications,Mgt Support,Design Changes & Mod Process 1999-09-16
[Table view] Category:UTILITY
MONTHYEARIR 05000352/19900211990-11-15015 November 1990 Insp Repts 50-352/90-21 & 50-353/90-20 on 900827-31.No Violations Noted.Major Areas Inspected:Emeergency Preparedness Program IR 05000352/19900221990-10-18018 October 1990 Insp Repts 50-352/90-22 & 50-353/90-21 on 900912-19.No Violations Noted.Major Areas Inspected:Engineering Organization,Staffing,Communications,Mgt Support,Design Changes & Mod Process IR 05000352/19900201990-10-12012 October 1990 Insp Repts 50-352/90-20 & 50-353/90-19 on 900813-0916.No Violations Noted.Major Areas Inspected:Plant Operations, Radiation Protection,Surveillance & Maint,Emergency Preparedness & Security IR 05000352/19900191990-08-0303 August 1990 Insp Repts 50-352/90-19 & 50-353/90-18 on 900709-13.No Violations Noted.Major Areas Inspected:Radiological Control Program,Including Organization & Staffing,Training & Qualification of Personnel & Applied Health Physics IR 05000352/19900171990-08-0303 August 1990 Insp Repts 50-352/90-17 & 50-353/90-16 on 900522-0701. Violations Noted.Major Areas Inspected:Plant Operations, Radiation Protection,Surveillance & Maint,Emergency Preparedness,Security,Engineering & Technical Support ML20055F5621990-06-25025 June 1990 Insp Repts 50-352/90-80 & 50-353/90-80 on 900521-25.Plant Transient Response Implementing Plan (Trip) Procedures Technically Acceptable.Major Areas Inspected:Comparison of Trip Procedures W/Specific Technical Guidelines IR 05000352/19900031990-02-11011 February 1990 Insp Repts 50-352/90-03 & 50-353/90-03 on 900116-19.No Violations Noted.Major Areas Inspected:Design & Surveillance Program for Compliance W/Atws as Described in 10CFR50.62 & NUREG-0991,SSER 9 IR 05000353/19890811989-09-27027 September 1989 Insp Rept 50-353/89-81 on 890731-0804.Violation Noted.Major Areas Inspected:Readiness of Licensee to Safely Conduct Power Operations at Facility Considering near-term Full Power Licensing IR 05000352/19890151989-09-22022 September 1989 Insp Repts 50-352/89-15 & 50-353/89-24 on 890626-0730.No Violations Noted.Major Areas Inspected:Maint & Surveillance Testing,Review of LERs & Periodic Repts & Operational Events.Viewgraphs from 890724 Meeting Encl IR 05000352/19890171989-09-0707 September 1989 Insp Repts 50-352/89-17 & 50-353/89-25 on 890724-27.No Violations Noted.Major Areas Inspected:Effectiveness of Training Conducted to Correct Inability of Operators to Properly Classify Events in Escalating Emergency IR 05000352/19890161989-09-0505 September 1989 Insp Rept 50-352/89-16 on 890807-11.No Violations Noted. Major Areas Inspected:Corporate Engineering Group & Support Provided to Facility & Mods Performed During Plant Second Refueling Outage IR 05000353/19892011989-08-0808 August 1989 Corrective Action Insp Rept 50-353/89-201 on 890424-28. Plant Design Meets Licensing Commitments.Major Areas Inspected:Mechanical Sys,Verification of Nonstandard Computer Codes & Incorrect Nameplate for RHR Pump Motor IR 05000352/19890121989-07-28028 July 1989 Insp Repts 50-352/89-12 & 50-353/89-19 on 890529-0625. Violations Noted.Major Areas Inspected:Maint & Surveillance Testing,Review of Lers,Periodic Repts & Operational Events & Sys Walkdowns IR 05000352/19890141989-07-20020 July 1989 Enforcement Conference Rept 50-352/89-14 on 890717.Major Items Discussed:Findings of NRC Insp Rept 50-352/89-14 Re Shipment of Seavan to Vendor Site in Oakridge,Tn IR 05000353/19890201989-07-13013 July 1989 Preoperational Safety Insp Rept 50-353/89-20 on 890530-0621. Programs Adequate to Support Testing & Startup.Major Areas Inspected:Control of Radioactive Matl & Contamination, Surveys & Monitoring,Facilities & Equipment & ALARA ML20246K5771989-07-0707 July 1989 Reactive Insp Rept 50-352/89-14 on 890629.Violation Noted. Major Areas Inspected:Circumstances Surrounding Shipment of Seavan to Quadrex Recycle Ctr IR 05000353/19890211989-07-0505 July 1989 Insp Rept 50-353/89-21 on 890530-0602.No Violations or Deviations Noted.Major Areas Inspected:Licensee Activities Re NRC Bulletin 79-14 Concerning Pipe Supports & Preservice Insp of Piping & Components IR 05000352/19890111989-06-19019 June 1989 Insp Repts 50-352/89-11 & 50-353/89-17 on 890522-26 & 0607. Violations Noted.Major Areas Inspected:Changes to Emergency Preparedness Program,Emergency Facilities,Equipment, Instrumentation & Supplies IR 05000353/19890231989-06-15015 June 1989 Insp Rept 50-353/89-23 on 890605-07.No Violation Noted.Major Areas Inspected:Licensee Liquid & Gaseous Radioactive Effluent Control Programs & Solid Radwaste Program Including Installations,Testings & Calibr IR 05000353/19890181989-05-17017 May 1989 Insp Rept 50-353/89-18 on 890429-0506.No Violations Noted. Major Areas Inspected:Structural Integrity Test Procedures & Implementation & Qa/Qc Involvement W/Integrity Test Procedures IR 05000353/19892001989-05-12012 May 1989 Independent Const Assessment Insp Rept 50-353/89-200 on 890330-31.No Violations Noted.Major Areas Inspected:Final S&W Independent Const Assessment Rept & Licensee Action Re Deficiencies & Issues Identified During Overview IR 05000352/19890091989-05-11011 May 1989 Insp Repts 50-352/89-09 & 50-353/89-15 on 880329-0423. Violations Noted.Major Areas Inspected:Operations, Radiological Controls,Surveillance Testing,Maint,Emergency Preparedness,Security & Engineer/Technical Support IR 05000353/19890131989-04-19019 April 1989 Insp Rept 50-353/89-13 on 890227-0316.No Violations Noted. Major Areas Inspected:Preoperational Test Program Implementation,Preoperational Test Procedures,Preoperational Test Results & Qa/Qc Involvement in Test Program IR 05000352/19890081989-04-14014 April 1989 Partially Withheld Physical Security Insp Repts 50-352/89-08 & 50-353/89-14 on 890307-09 & 20-23 (Ref 10CFR73.21).Violations Noted.Major Areas Inspected:Action on Previously Identified Items & Security Program Plans IR 05000353/19890111989-04-0707 April 1989 Insp Rept 50-353/89-11 on 890213-0326.No Violations Noted. Major Areas Inspected:Work Activities,Security Implementation,Environ Qualification of Equipment & Proposed Tech Specs IR 05000352/19890031989-04-0707 April 1989 Insp Rept 50-352/89-03 on 890227-0326.No Violations Noted. Major Areas Inspected:Routine Daytime & Backshift Operations,Including Plant Tours,Observations of Maint & Surveillance Testing & Review of Lers & Periodic Repts ML20244D4891989-04-0303 April 1989 Insp Rept 50-352/89-07 on 890306-10.No Violations Noted. Major Areas Inspected:Inservice Insp Activities to Ascertain Activities Conducted Per Applicable ASME Code & Regulatory Requirements & Licensee Response to Generic Ltr 88-01 IR 05000353/19890071989-04-0303 April 1989 Insp Rept 50-353/89-07 on 890126-0203.No Violations, Deviations or Unresolved Items Noted.Major Areas Inspected: Licensee Programs That Identify & Control Specific Differences in Design & Const of Both Units IR 05000352/19880241989-03-31031 March 1989 Insp Rept 50-352/88-24 on 881107-1218.No Apparent Vulnerabilities in Balance of Plant Found Which Have,To Date,Contributed to Reactor Challenges,I.E.,Recurrent Scrams.Major Areas inspected:balance-of-plant Sys IR 05000353/19882031989-03-23023 March 1989 Insp Rept 50-353/88-203 on 890103-06.No Violations Noted. Major Areas Inspected:S&W Evaluation of Closed Action Items, Observation Repts to Reflect Action Item Unresolved Issues & Status of Compliance W/Previous Insp IR 05000353/19890121989-03-22022 March 1989 Insp Rept 50-353/89-12 on 890224-0303.No Violations Noted. Major Areas Inspected:Licensee Action on Previous Insp Findings,Procedure Reviews,Qa/Qc Interfaces & Tours of Facility IR 05000352/19890801989-03-21021 March 1989 Maint Team Insp Repts 50-352/89-80 & 50-353/89-80 on 890130-0210.Weaknesses Noted.Major Areas Inspected:Maint Program & Program Implementation,Including Equipment Walkdowns & Observation of Maint Work IR 05000352/19890041989-03-17017 March 1989 Insp Rept 50-352/89-04 on 890124-0226.No Violations Noted. Major Areas Inspected:Plant Tours,Observations of Maint & Surveilance Testing & Review of Lers,Periodic Repts, Operational Events & Sys Walkdowns IR 05000353/19890101989-03-10010 March 1989 Insp Rept 50-353/89-10 on 890206-16.No Violations Noted. Major Areas Inspected:Preoperational Test Program Implementation,Preoperational Test Procedures,Preoperational Test Results & Qa/Qc Involvement in Test Program IR 05000352/19890061989-03-0707 March 1989 Insp Repts 50-352/89-06 & 50-353/89-06 on 890123-27. Violation Noted.Major Areas Inspected:Safe Shutdown Capability of Plant in Event of Fire IR 05000352/19890051989-03-0202 March 1989 Safety Insp Repts 50-352/89-05 & 50-353/89-08 on 890130- 0203.No Violations Noted.Major Areas Inspected:Licensee Radiological Controls Program,Including Unit 1 Outage Activities & Changes to Health Physics Organization IR 05000353/19890091989-03-0101 March 1989 Insp Rept 50-353/89-09 on 890131-0207.No Violations Noted. Major Areas Inspected:Overall Power Ascension Program Including Training for Test Engineers.Two Unresolved Items Identified Including Limiting Control Rod Withdrawal IR 05000352/19890011989-02-22022 February 1989 Insp Rept 50-352/89-01 on 890117-20.No Violations Noted. Major Areas Inspected:Implementation of post-accident Monitoring Instrumentation in Accordance W/Reg Guide 1.97, Rev 2 IR 05000353/19890031989-02-14014 February 1989 Insp Rept 50-353/89-03 on 890109-19.No Violations Noted. Major Areas Inspected:Overall Power Ascension Program, Including Procedure Review,Qa/Qc Interfaces & Tour of Facility IR 05000353/19880251988-10-28028 October 1988 Insp Rept 50-353/88-25 on 8880912-1016.Violations Noted. Major Areas Inspected:Work Activities,Procedures,Records Re Spent Fuel Pool Racks,Preoperational Test Procedure Review, Startup Test Activities,Engineering & Deficiency Repts IR 05000353/19880221988-10-18018 October 1988 Insp Rept 50-353/88-22 on 880912-23.No Violations Noted. Major Areas Inspected:Preoperational Test Program,Including Review of Implementation Requirements,Preoperational Test Procedures & Integrated Sys Flush Test IR 05000353/19880241988-10-11011 October 1988 Insp Rept 50-353/88-24 on 880912-15.No Violations Noted. Major Areas Inspected:Installation of safety-related Instrumentation Components & Status of Previously Identified Open Items IR 05000353/19880261988-10-0606 October 1988 Insp Rept 50-353/88-26 on 880927-30.No Violations or Deviations Noted.Major Areas Inspected:Corporate Emergency Support Program,Staffing,Training,Mgt Support & Communications ML20207K8681988-10-0404 October 1988 Daytime & Backshift/Holiday Insps of 880815-0924.No Violations Noted.Major Areas Inspected:Plant Tours,Sys Walkdowns,Observations of Maint & Surveillance & Review of LERs & Periodic Repts.Supporting Info Encl IR 05000353/19880211988-09-28028 September 1988 Insp Rept 50-353/88-21 on 880808-0911.No Violations Noted. Major Areas Inspected:Work Activities,Procedures,Records Relative to Preoperational & Technical Tests,Independent Design & Const Assessment & Welding IR 05000352/19880181988-09-23023 September 1988 Insp Rept 50-352/88-18 on 880816-19.No Violations Noted. Major Areas Inspected:Fire Protection/Prevention Program, Including Program Administration & Organization,Equipment Maint,Insp & Test,Qa Audits & Facility Tours IR 05000353/19882001988-09-23023 September 1988 Insp Rept 50-353/88-200 on 880808-12.Insp Scope & Objective: Independent Design & Const Assessment Review Plans Prepared in Sufficient Technical Depth to Permit Adequate Evaluation of Design & Const of Facility IR 05000353/19880201988-09-14014 September 1988 Insp Rept 50-353/88-20 on 880808-12.No Violations Noted. Major Areas Inspected:Preoperational Test Program Implementation Requirements & Preoperational Test Procedures Activities in Qa/Qc Interface W/Preoperational Test Program IR 05000353/19880171988-09-0808 September 1988 Insp Rept 50-353/88-17 on 880725-29.No Violations Noted. Major Areas Inspected:Preoperational Test Program,Including Review of Implementation Requirements,Procedures & Test Witnessing of Emergency Diesel Generator a IR 05000353/19880191988-09-0202 September 1988 Insp Rept 50-353/88-19 on 880808-12.No Violations Noted. Major Areas Inspected:Preservice Insp Activities to Ascertain Whether Licensee Activities Conducted in Compliance W/Applicable ASME Code 1990-08-03
[Table view] Category:TEXT-INSPECTION & AUDIT & I&E CIRCULARS
MONTHYEARPNO-I-99-045, on 990923,operators at Limerick Generating Station Declared Unusual Event Due to Presence of Toxic Gases within Site Boundary.No Toxic Gases Were Detected within Main Cr.No Personnel Were Injured or Made Ill1999-09-24024 September 1999 PNO-I-99-045:on 990923,operators at Limerick Generating Station Declared Unusual Event Due to Presence of Toxic Gases within Site Boundary.No Toxic Gases Were Detected within Main Cr.No Personnel Were Injured or Made Ill IR 05000352/19990051999-09-16016 September 1999 Insp Repts 50-352/99-05 & 50-353/99-05 on 990713-0816.One Violation Noted & Being Treated as Ncv.Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000352/19993031999-09-0808 September 1999 Exam Repts 50-352/99-303OL & 50-353/99-303OL on 990812.Exam Results: One Reactor Operator Applicant Was Administered Retake Section B of Test & Passed IR 05000352/19990041999-08-10010 August 1999 Insp Repts 50-352/99-04 & 50-353/99-04 on 990525-0712.One Violation Noted & Being Treated as Ncv.Major Areas Inspected:Aspects of Licensee Operations,Engineering & Maint IR 05000352/19993021999-08-0404 August 1999 NRC Operator Licensing Exam Repts 50-352/99-302 & 50-353/99-302 Adminsitered on 990702-14 (Administration) & 990715-22 (Grading).Six of Six Limited SROs Passed All Portions of Exams IR 05000352/19990031999-06-24024 June 1999 Insp Repts 50-352/99-03 & 50-353/99-03 on 990413-0524.No Violations Noted.Major Areas Inspected:Operations, Maintenance,Engineering & Plant Support.Also Inspected, Radiological Protection,Security & Inservice Insp IR 05000352/19990021999-05-0707 May 1999 Insp Repts 50-352/99-02 & 50-353/99-02 on 990302-0412. Violations Noted & Being Treated as non-cited Violations. Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000352/19993011999-04-30030 April 1999 NRC Operator Licensing Exam Repts 50-352/99-301 & 50-353/99-301 Administered on 990312-19 (Administration & 990322-26 (Grading).Exam Results:Five RO & Four SRO Applicants Were Administered Exam.One RO & One SRO Failed PNO-I-99-019, on 990420,Limerick Unit 1 Automatically Shutdown from 100% Power on Low Rwl Due to Loss of Mfw. Normal Feedwater Sys Has Been Restored,Which Allowed for Securing of RCIC & HPCI Systems.Licensee Issued Pr1999-04-21021 April 1999 PNO-I-99-019:on 990420,Limerick Unit 1 Automatically Shutdown from 100% Power on Low Rwl Due to Loss of Mfw. Normal Feedwater Sys Has Been Restored,Which Allowed for Securing of RCIC & HPCI Systems.Licensee Issued Pr IR 05000352/19990011999-03-26026 March 1999 Insp Repts 50-352/99-01 & 50-353/99-01 on 990112-0301. Violations Noted.Major Areas Inspected:Operations, Engineering,Maint & Plant Support ML20199C6571999-01-0606 January 1999 Notice of Violation from Insp on 981018-1130.Violation Noted:On 981105,procedure M-053-006,required by App a of Reg Guide 1.33,not Implemented as Required by Procedure A-C-079 ML20199C6641999-01-0606 January 1999 Insp Repts 50-352/98-09 & 50-353/98-09 on 981018-1130. Violations Noted.Major Areas Inspected:Operations, Engineering,Maintenance & Plant Support ML20196C3371998-11-23023 November 1998 Insp Repts 50-352/98-08 & 50-353/98-08 on 980901-1017.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support.Security & Safeguards Activities Were Conducted in Manner That Protected Public Health IR 05000352/19980071998-09-25025 September 1998 Insp Repts 50-352/98-07 & 50-353/98-07 on 980707-0831.No Violations Noted.Major Areas Inspected:Operations, Engineering,Maint & Plant Support IR 05000352/19980051998-08-0707 August 1998 Insp Repts 50-352/98-05 & 50-353/98-05 on 980601-24. Violations Noted.Major Areas Inspected:Backlogged Engineering Activities ML20237A3091998-08-0707 August 1998 Notice of Violation from Insp on 980606-24.Violation Noted: Defective Equipment in Supply Circuit Breaker of Load Ctr 124B Not Identified & Corrected & on 980322 Breaker Tripped Unexpectedly & de-energized All Loads Supplied by Center ML20236X8161998-08-0505 August 1998 Notice of Violation from Insp on 980519-0706.Violation Noted:As of 980304,licensee Had Not Submitted LER for Condition Prohibited by Plant TS within 30 Days After Discovery of Event IR 05000352/19980041998-08-0505 August 1998 Insp Repts 50-352/98-04 & 50-353/98-04 on 980519-0706. Violations Noted.Major Areas Inspected:Aspects of PECO Energy Operations,Engineering & Maint ML20236M7331998-07-0707 July 1998 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $55,000.Violation Noted:During 970901-980121, Condition Adverse to Quality Existed Involving Inoperability of 1B RHR Min Flow Valve & No C/As Taken ML20237E4241998-07-0101 July 1998 EN-98-049:on 980707,notice of Proposed Imposition of Civil Penalty in Amount of $55,000 Issued to Licensee.Action Based on Two Violations Re Failure to Take Appropriate Corrective Action to Address Conditions Adverse to Quality at Facility IR 05000352/19980031998-06-18018 June 1998 Insp Repts 50-352/98-03 & 50-353/98-03 on 980317-0518. Violations Noted.Major Areas Inspected:Aspects of PECO Energy Operations,Engineering,Maint & Plant Support ML20249C1901998-06-18018 June 1998 Notice of Violation from Insp on 980317-0518.Violation Noted:Measures Established to Correct Nonconformances Re Log Entries,Identified in Violation 97-10-01,did Not Preclude Repetition of Similar Problem PNO-I-98-019, on 980603,operators Found One of Three Standby Liquid Injection Pumps Running & Injecting Into Reactor Vessel.No Alarms Identified on Redundant Reactivity Control Sys Which Provides Automatic SLC Initiation Feature1998-06-0404 June 1998 PNO-I-98-019:on 980603,operators Found One of Three Standby Liquid Injection Pumps Running & Injecting Into Reactor Vessel.No Alarms Identified on Redundant Reactivity Control Sys Which Provides Automatic SLC Initiation Feature ML20247J2401998-05-11011 May 1998 Notice of Violation from Insp on 980120-0316.Violations Noted:On 980213,significant Condition Adverse to Quality Identified & Previous C/A on Control of Locked Valves Did Not Preclude Repetition ML20247J2451998-05-11011 May 1998 Insp Repts 50-352/98-02 & 50-353/98-02 on 980120-0316. Violations Noted.Major Areas Inspected:Operations, Engineering,Maintenance & Plant Support PNO-I-98-013, on 980417,alert Declared After Detection by Smell of Unidentified Odor,Initially Believed to Be Acetylene or Propane Gas,Resulting in Evacuation of Area. Fire Brigade Activated1998-04-17017 April 1998 PNO-I-98-013:on 980417,alert Declared After Detection by Smell of Unidentified Odor,Initially Believed to Be Acetylene or Propane Gas,Resulting in Evacuation of Area. Fire Brigade Activated IR 05000353/19970091998-03-11011 March 1998 Insp Rept 50-353/97-09 on 971010-980116.Violations Noted. Major Areas Inspected:Operations,Maintenance,Engineering & Plant Support ML20203G9111998-02-23023 February 1998 Notice of Violation from Insp on 971118-980119.Violation Noted:On 971206,required Narrative Log Entries in Unified Log for Safety Sys Inoperability Were Not Made ML20203G9211998-02-23023 February 1998 Insp Repts 50-352/97-10 & 50-353/97-10 on 971118-980119. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support ML20202F9901998-02-0505 February 1998 Exam Repts 50-352/98-01 & 50-353/98-01 on 980120-23.No Violations Noted.Exam Results:Two Ro,Two Srou & Four SRO Candidates Were Administered Initial Licensing Exams. Everyone Passed All Portions of Exam IR 05000352/19970081997-12-0808 December 1997 Insp Repts 50-352/97-08 & 50-353/97-08 on 970916-1117.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support ML20198N1771997-10-27027 October 1997 Insp Repts 50-352/97-07 & 50-353/97-07 on 970722-0915. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support ML20198N1701997-10-27027 October 1997 Notice of Violation from Insp on 970722-0915.Violation Noted:Inspector Identified Valve Locking Devices Not Applied Through Valve Handwheel or Other Operating Mechanism to Restrict Operation of Valves Listed on Valve List Exhibits ML20198Q9181997-09-29029 September 1997 Notice of Violation from Insp on 970528-0721.Violation Noted:As of 960726,licensee Did Not Implement & Maintain in Effect Certain Provisions of Approved FP Program as Described in UFSAR for Facility IR 05000352/19970061997-08-13013 August 1997 Insp Repts 50-352/97-06 & 50-353/97-06 on 970528-0721. Violations Noted.Major Areas Inspected:Peco Energy Operations,Engineering,Maintenance & Plant Support ML20210N9861997-08-13013 August 1997 Notice of Violation from Insp on 970528-0721.Violation Noted:Peco Energy Did Not Submit LER within 30 Days After Discovery of an Event Which Occurred on 930316 for Condition Prohibited by Plants TS ML20210K9141997-07-31031 July 1997 EN-97-066:order Prohibiting Involvement in NRC-licensed Activities Issued on or About 970805 to Unlicensed Individual Who Formerly Worked as Primary Chemistry Manager at Limerick Generating Station,Units 1 & 2 ML20210K8841997-07-31031 July 1997 EN-97-065:on 970805,notice of Proposed Imposition of Civil Penalty in Amount of $80,000 Issued to Licensee.Action Includes Two Violations Involving Instances of Record Falsification at Limerick Generating Station IR 05000352/19970051997-07-31031 July 1997 Insp Repts 50-352/97-05 & 50-353/97-05 on 970623-26.No Violations Noted.Major Areas Inspected:Licensee Performance During Biennial full-participation EP Exercise ML20210K9771997-07-31031 July 1997 EN-97-067:order Prohibiting Involvement in NRC-licensed Activities Issued on or About 970805 to Sf Nevin Unlicensed Individual at Limerick Generating Station,Units 1 & 2.Action Based on Investigation Conducted by OI IR 05000352/19970031997-07-11011 July 1997 Insp Repts 50-352/97-03 & 50-353/97-03 on 970330-0527. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support ML20149E1391997-07-11011 July 1997 Notice of Violation from Insp on 970330-0527.Violation Noted:Master Keys Were Not Properly Controlled & Were in Possession of Unauthorized Personnel & Temporary Change to GP12 Altered Intent of Original Procedure IR 05000352/19970991997-05-0909 May 1997 SALP Repts 50-352/97-99 & 50-353/97-99 for 950402-970329 IR 05000352/19970041997-05-0808 May 1997 Exam Repts 50-352/97-04OL & 50-353/97-04OL on 970501. Exam Results:Initial Retake Exam Administered to One RO Applicant on 970501.Applicant Passed Exam ML20148C1511997-05-0707 May 1997 Notice of Violation from Insp on 970204-0329.Violation Noted:In Jan 1997,mod Made to Unit 2 Fuel Preparation Machines That Made Info in SAR Incomplete in That Test Fixture Was Added Which Caused Fuel to Be Raised IR 05000352/19970011997-05-0707 May 1997 Insp Repts 50-352/97-01 & 50-353/97-01 on 970204-0329. Violations Noted.Major Areas Inspected:Operations, Engineering,Plant Support & Maintenance ML20136C0891997-03-0606 March 1997 Notice of Violation from Insp on 961217-970203.Violation Noted:Diesel Generator Fuel Oil Storage Tank Level Was Below TS Value & Required Actions for Inoperable Diesel Generator Was Not Performed ML20136C0951997-03-0606 March 1997 Insp Repts 50-352/96-10 & 50-353/96-10 on 961217-970203. Violations Noted.Major Areas Inspected:Operations, Engineering,Maint & Plant Support IR 05000352/19970021997-02-12012 February 1997 NRC Operator Licensing Exam Repts 50-352/97-02OL & 50-353/97-02OL on 970120-24.Exam Results:Good Performance Including Teamwork & Communications Was Demonstrated by Applicants.Six of Seven Applicants Passed Exam ML20134F9051997-02-0303 February 1997 Notice of Violation from Insp on 960305 & 0506 & Between 1003 & 1127.Violation Noted:Electronic Copy of Limerick Physical Security Plan,Located on PECO Nuclear Local Area Network & Document Not Under Control 1999-09-08
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U. S. NUCLEAR REGULATORY. COMMISSION i REGION I L 2 t
Report No. 88-25 I Docket No. 50-353 i i
License No. CPPR-107 Category A/B Licensee: Philadelphia Electric Company !
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2301 Market Street !
Philadelphia, PA 19101
Facility Name: Limerick Generating Station, Unit 2 Inspection Conducted: September 12, 1988 to October 16, 1988 ,
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Inspectors: R. A. Gramm, Senior Resident Inspector, Unit 2 !
R. L. Fuhrmeister, Resident 7.ispector, Unit 2 !
r E. H. Gray, Senici Reactor .ngineer, ORS ;
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Reviewed by: u M F2/
. Wm fims, Project Engineer
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, 9/ctor Projects Sectioi 2A l Approved by: 4 /4 [
j s' C. Linvil e. Chief AT - ate !
tor Projects Section A'
Inspection Summary: Report for Inspection Conducted September 12, 1988 to !
, October )f, 1988 (Report No. 50-353/88-25)
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Areas Inspected: '
Routine inspection by the resident inspector of work activities, procedures, and records relative to spent fuel pool racks, I preoperational test procedure review, startup test activities, engineering, f; independent design and construction assessment, reactor vessel internals, and deffetency reports. The inspectors reviewed licensee action on previously l identified items and performed plant inspection tours. The inspection i involved 231 hours0.00267 days <br />0.0642 hours <br />3.819444e-4 weeks <br />8.78955e-5 months <br /> by the inspector l
Results: One violation was identified involving the fatture of GE engineering l
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to incorporate a wiring design change into the Unit 2 RRCS for the function of j i a feedwater runback as described in section The change had been originally t issued for Unit I while construction activity had ceased on Unit 2. While the t
- engineering review at Unit 2 construction restart identified the necessity to !
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implement the wiring design change for Unit 2, it was never incorporated into i
! the appropriate design document or plant hardwar I
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$DR ADOCK 05000353 N
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TABLE OF CONTENTS Page 1.0 Summary . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 2.0 Plant Inspection Tours. . . . . . . . . . . . . . . . . . . . . . 2 3.0 Licensee Action on Previously Identified Items. . . . . . . . . . 4 4.0 Licensee Action on Bulletins and Circulars. . . . . . . . . . . . 5 5.0 Three Mile Island Action Plan Items . . . . . . . . . . . . . . . 6 6.0 Spent Fuel Pool Racks . , . . . . . . . . . . . . . . . . . . . . 10 7.0 Preoperational Test Procedure Revie .............. 11 8.0 Startup Test Activities . . . . . . . . . . . . . . . . . . . . . 12 9.0 Engineering . ......................... 14 10.0 Independent Design and Construction Assessmen ......... 15 11.0 Reactor Vessel Internals. . . . . . . . . . . . . . . . . . . . . 16 12.0 Deficiency Reports. . ..................... 16 13.0 Assurance of Quality. . . . . . . . ............... 18 14.0 Meetings with Licensee. . . . . . . . . . . . . . . . . . . . . . 18 Appendix 1 - Acronyms and Abbreviations
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. DETAILS 1.0 Sunmary A concern identified by the NRR design review effort involving potential misoperation of the RHR pump motors was reviewed and found to not be an operability concern (section 2). Eighteen NRC open items were reviewed and 11 were closed. As a result of inconsistencies between FSAR commitments and corrective actions presented for the open items several remain open (sections 3, 4 and 5). The spent fuel pool rack insta'lations were found properly controlled (section 6). Review of the RRCS design documents identified a wiring error in the feedwater pump runback circuitry. A GE design change had been implemented for Unit 1 but hvi not been incorporated into the Unit 2 design, this concern was identifud as a violation of the design control provisions of 10 CFR 50 Appendix 8 (section 7). Startup fiC d test activities were observed for the CS, RHR, D-G, recirculation pump anu integrated recirculation system flush. The testing was performed in accordance with the appropriate administrative and technical requirements (section 8). Further Bechtel SALP improvement plan actions were reviewed (section 9). The conduct of the IDCA was monitored (section 10). The installation of a feedwater sparger and CRDMs was observed (section 11). The identification of deficient conditions by PECo and Bechtel QA was reviewed (section 12).
2.0 Plant Inspection Tours (70453, 52053, 51c53, 70311, 37055, 49063)
The inspector observed in progress work activities, completed work, and plant status in several areas during inspection tours. Work was examined
, for defects and compliance with regulatory and licensee requirements.
l Particular note was taken of the presence of quality control inspectors l and quality control evidence such as inspection records, material i
identification, nonconforming material identification, housekeeping and
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equipment preservation. The inspector interviewed craf t supervision, l craft and quality control personnel in the work areas. Observations are l noted below:
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The inspector witnessed calibration checks of the load switches for the auxiliary hoist on the refueling bridge. The work was perfurmed to Startup Work Order (SWO)-281A-009, in order to resolve Test Exception (TE) 2 to Preoperational Test (POT) 2P81.1 "Feel Handling System," The TE was written when the load switch setting (400250 pounds) would not allow the 340 pound test weight to be lifted. A calibration check nowed the load switch to be tripped at a value greater than the test ,teight. The inspector independently verified the trip point calcinatio The load test was subsequently reperformed after the load suitches were reset to allow lifting the test weights. The switches were then rechecked and verified to be within the specified to' rance from the nominal set poin These mechanical switches s peared to be sensitive to the manner in which the hoist was opera.ad. "Jogging" the drive motor results in the switch mechanism changing state, which causes trips at a lighter load. The switch mechanism response does not allow reset as the
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load was not reduced 200 pounds below the trip set point. There are curreatly plans to replace the mechantcal switches with solid state electronic load switches which should result in a permanent solution to the difficulty, ;
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The inspector observed the setting of the electrical and mechanical stops on the scoop tube positioner for the A Recirculation M-G Se The work was performed to SWO 264A-30, and used the settings obtained during the Unit 1 preoperational test. This produced settings close to those desired, in order to avoid exceeding equipment limitations during the initial pump run The inspector attended a Test Review Board (TRB) meeting to review i preoperational test procedure 2P-59.1, Revision F, "Containment Isolation and Nuclear Steam Supply Shutoff System." Licensee personnel represe.n.ed the TRP, General Electric, PECo engineering and field -
engineering. The procedure Md been previously reviewed on two occasions by the TRB. The incorporation of the previously identified changes was verified by the review pane The inspector had no concern The inspector was informed that an NRC design review had identified a potential problem with respect to the RHR pump motors. A postulated loss of off W e power would result in a reduced bus voltage which could cause an overcurrent trip of the motor circuit breaker. The inspector met with PECo electrical engineering ,
representatives and discussed Bechtel calculations 6900 E.05B and 6380 E.08. The RHR motors were procurred to be able to accelerate i to rated speed while the supplied voltage was 75% of normal. PECo determined that the minimum bus voltage during a lost of offsite power and simultaneous forced shutdown situation would be 79% of 4160 volts. The resulting voltage at the motor, inclusive of line !
losses, would be approximately 81% of the rated motor voltage (4,000 i
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volts). The existing time-current characteristic curves in the calculation bound this condition and this would not cause an overcurrent tri PECo has issued SDR 251-1 to track this issu The Unit 1 and Unit 2 inspectors reviewed the calculations and found no outstanding operability concern The inspector identified a loose bolt on the standby diesel generator A skid mounted lube oil discharge pipe stress cone fittin No laak of lube oil was found. The system engineer promptly had the bolt properly tightene The inspector observed bolt torque operations on RHR piping HBB-218-7 flange M- The hydraulic torque machine was used to perform a fourth pass torque to 750 +/- 75 ft-lb The QC inspector was intersiewed, the work package was reviewed, and calibration control of the torque machine was verifie The inspector had no further question . _ _ _ _ - _ _ _ . - _ __ . - _________- _
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3.0 Licensee Action on previously Identified items (292700, 292701, 292702} (Closed) Construction Deficiency Report (81-00-06): Limitorque motor operator defects. The inspector reviewed the following documents:
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PEco Significant Deficiency 38
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Bechtel Quality Action Request 477
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Bechtel Procedure FM-4, Limitorque Rework Program The inspector verified that all Unit 2 safety relatea valve motor operators were processed through the limitorque rework program. The rework program accomplished the following aspects: replacement of terminal blocks with direct splicing to motor leads, replacement of defective rotors, replacement of fiber shims in torque switches, replacement of damaged gaskets, removal of heaters, replacement of main gear box housing grease and installation of prepar drain plug Based upon the extensive rework program this item is closed, pen) Unresolved Item (87-02-02). Control of GE Service Advice Letters. The inspector was informed that PECo will track SALs in a similar manner to other GE issued industry notifications such as SIL The inspector requested the licensee to provide a description of the 35 SALs that were found applicaole to Unit 2 and to address the physical inspection of the HFA relays for potential mispositioned stop tab This item remains ope (0 pen) Violation (87-11-09): Undersized raceway support weld The inspector reviewed the following documents:
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PECo Finding report IN-573
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NCRs 12547, QA-L-017, QA-L-014, QA-L-026
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Apparent Discrepancy Notific' tion L-025, 0-022 The licensee re-reviewed weld inspection reports and engineering documents to identify field installation that utilized skewed fillet welds for Unit 1 support Bechtel reviewed the Unit 2 supports and found additional weldment had been specified which negated the need for the skewed fillet weld Pending review of the Bechtel calculations for the Unit 2 supports this item remains open, [ Closed) Construction Deficiency Report (88-00-09): Internal conduit seals. The inspector reviewed the folicwing documents relating to this issue:
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Evaluation of Reportability - 50R #236-2 dated August 16, 1938
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Engineering evaluation of three-hour internal conduit fire seals dated August 12, 198S
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Engineering evaluation of three-hour internal conduit fire seals dated August 22, 1988
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FPER, Section _ _ - _ _ _ _
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The qualification test data and engineering calculations demonstrate that; the as-installed seals are adequate to meet the requirements stated in the FPER. This item is close .0 Licensee Action on Bulletins and Circulars (392703}
The inspector reviewed licensee records related to the Bulletins and Circulars identified below to verify that: the Bulletin or Circular was
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received and reviewed for applicability; a written response was provided if requireo; and the corrective action taken was adequate. The following i Bulletins and Circulars were reviewed: i (Closed) Bulletin (76-04): Cracks in cold worked piping at BWR The inspector reviewed the following pertinent documentation:
i Bechtel Letter BLP-45102 dated September 14, 1988
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PEco Memorandum PMOM-2283 dated September 19, 1983 The inspector determined that the problem described in the bulletin i should not occur at Limerick 2 since the licensee confirmed that no austen1 tic stainless steel pipe or fitting located in the reactor coolant pressure boundary had been subjected to cold bendin This item is close ' (Closed) Circular (80-25): Operating problems with target-rock f safety-relief valves at BWR The inspector reviewed the following ;
documents related to the bulletin: !
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GP-1, Preparations for Normal Plant Startup, Rev. 4
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PECo Letter PLG-1594, dated October 27, 1986
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GE Letter PE-3492, dated December 3, 1986
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PECo Letter PLG-1601, dated December 16, 1986
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PEco Letter PLG-1606, dated February 20, 1987
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Bechtel letter BLP-39913, dated March 13, 1987
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PECo Letter PLG-1665, dated February 1,1988
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PECo M(morandum PMOM-2265, dated September 12, 1988
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ST-4-041-210-2, Main Steam Relief Valve Test The inspector determined that the main steam safety relief valves I which will be used at Limerick 2 use an actuator of an improved design which is not assembled with adhesives and can withstand pneumatic pressures higher than those which calculations show might i occur in the nitrogen system. In addition, at least one-half of the i valves are tested every 18 months and general plant procedure GP-1 !
requires a special surveillance test for any valve which failed to !
function as designed during the reactor shutdown evolution. This l ttem is close i i (0 pen) Bulletin (8S-05}: Nonconforming material provided by Piping !
Supplies, Inc. The inspector reviewed Bechtel memorandum FME-7854 I that described Unit 2 site investigations to dat Safety related i
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piping system records have been reviewed for evidence whether the nonconforming material described by the bulletin had been use Each stainless flange was tested with a portable alloy analyzer and the carbon steel flanges were hardness tested. A total of 312 carbon flanges and 13 stainless *langes were tested. The hardness results were converted to equivalent tensile strengt The inspector reviewed the matrix results for material heat code versus tensile strength. The site results are under Bechtel engineering review. This item remaint ope .0 Three Mile Island Action Plan Items (5254018) (0 pen) I.C.1: Short term accident procedu.'e The inspector reviewed the following:
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NUREG 0737
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FSAR section 1.13 and question 440.18
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SER section 13.5.2.3 and SSER section 13.5. Administrative procedure A-94 The NRC staff has previously reviewed the administrative guidelines for generation of E0Ps and found them acceptabl The inspector was informed that PECo engineering is currently reviewing the Unit 2 plant specific setpoint calculations to revise the TRIP procedures. This item remains open pending generation of the revised TRIP procedures which will conform with revision 3 of the Boiling Water Reactor Owners Group (BWROG) guidelines.
i (0 pen) I.C.5: Feedback of operating plant experienc The i inspector reviewed the following:
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FSAR sections 1.13 and question 630.32
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SER section 1 SSER 1 section 13
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PECo Interim Nuclear Group Administrative Procedure for Operating Experience Assessment Program (OEAP)
The corporate and site program and organization responsibilities for review and dissemination of operating experience information had been previously reviewed and accepted by the NRC staff. The new OEAP has superseded elements of the previously described program, This item remains open pending revision of the FSAR to reflect the OEAP and development of implementing procedures for corporate and site organizations, (0 pen) 11.0.3: Safety relief valve position indicatio The inspector reviewed:
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Limerick FSAR sections 1.13, 7.5.1.4.2.2.1, 7.6.1.5 and 7.6 _ _ _ _ __ ._ . _ _ _ _ _ - _ - _ _ _ - _ _ _ _ _ _ _ _ _
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- Limerick SER 7.5. The inspector examined the installed valve position. indication devices in the control room and confirmed that indications are provided for valve open, closed and valve was open position The FSAR indicated the acoustic monitoring system was installed in accordance with the QA progra The inspector was informed that the Unit 2 acoustic monitors are located in the warehous A design change will be issued to clarify the ambiguous Quality Assurance 01agram (QAD) description of the quality program coverage for the sensors. The work packages and quality reports had not yet been generated for the sensors. The inspector was informed that an Apparent Olscrepancy Notification (ADN) has been issued to alert the Unit 1 staff of the potential lack of quality overview for the Unit 1 sensors. The inspector noted that while the FSAR stated that all system components except the power supply are seismically qualified, the SER erroneously states that the power supply is seismically qualified. This item remains ope d. (Open) II.E.4.2
- Containment isolation dependability. The inspector reviewed the following pertinent documentation:
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NUREG 0737, Clarification of THI Action Plan Requirements, enclosure 3, section II.E. FSAR section 1.13
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Limerick SER section 6.2.4.3 l
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Supplement 6 to the timerick SED, section 6.2.4 l
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NRC letter, Butler to Bauer,. dated May 20, 1986 l
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PECo letter, Kemper to Butler, dated June 20, 1986
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NRC letter, Butler to Bauer, dated August 22, 1986
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PECo SDR #385. dated January 3, 1984 l
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PECo letter PLB-21894, dited May 5, 1988
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PECo letter PLB-22913, dated September 9, 1988 The NUREG 0737 clarification states that the isolation function
! must be performed automatically with no credit for operator l action. Containment isolation valves at Limerick have been l identified as being susceptible to the MCC circuit breakers I tripping when the valve motor receives a closure signal while l
running in the open directio This situation will require i operator action to reset the circuit breaker. This item remains open pending resolution of the issues surrounding the circuit breaker trip on motor reversal phenomeno Construction Deficiency Report 83-00-06 documents the licensee identified problem with the circuit breaker trip phenomen e. (Closed) II.K.1.5: Assurance of proper engineered safety features functioning. The inspector reviewed the following pertinent documents:
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FSAR section 1.13
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Limerick SER section 15. Supplement 3 to Limerick SER, Section 15. A-8, Procedure for Control of Locked Valves and Device Revision 4
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A-26, Procedure for corrective maintenance, Rev.13
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A-41, Procedure for control of plant equipment, Rev. 6
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PEco Letter, Bradley to Schwencer, dated May 11, 1983 The inspector determined that the staf f approved the methodology of including controls on equipment in administrative procedures in the SER. A confirmatory item was noted to verify that the contents of the procedures covered the issues. This confirma-tory issue was closed in SER Supplement 3. The inspector verified that the procedural controls have been maintained in the current revisions. This item is closed.
' (Closed) II.K.1.10: Operability status of safety related systems. The inspector reviewed the following pertinent documents:
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FSAR section 1.13
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Limerick SER, section 15. Supplement 2 to Limerick SER, section 15. PECo Letter, Bradley to Schwencer, dated May 11, 1983
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A-41, Procedure for Control of Plant Equipment, Rev. 6 In the SER, the staff accepted the methodology of including controls on safety-related equipment in an administrative procedure. A confirmatory item was noted requiring verification that the procedure addressed the issues surrounding knowledge of status of safety-related systems. In supplement 2 to the SER, the staff approved the procedural elements of A-41. The inspector verified that these controls and independent veri'ication requirements have been maintained in the current revision of A-41.
" (Closed) II.K.1.22: Auxiliary heat removal syste This item relates to the ability to cool the reactor on a loss of feedwater transient. The inspector reviewed the following documents applicable to this issue:
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FSAR section 5. FSAR section 5. FSAR section 6.3. FSAR 1.13
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Limerick SER section 15. Supplement 3 to Limerick SER section 15.9.3
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This issue was accepted as satisfactorily resolved in the initial SER and Supplement 3. Since that time, PECo has opted to disable the steam condensing mode of the RHR system in ,
response to staff concerns regarding water hammer potentia ,
As a result, Limerick has three separate and redundant means of '
cooling the fuel on a loss of feedwater: RCIC system operation (automatic or manual), HPCI system operation (automatic or manual) and a combination of automatic depressurization system and either core spray or LPCI operation. If the reactor is isolated in addition to having a loss of feedwater flow, safety-relief valves are available to control reactor coolant system pressure via automatic or remote manual operation. This item is close (Closed) II.K.1.23: Reactor vessel level. This item was related to instrumentation avetlable for indication of reactor vessel water inventory, allowing operators to recognize and assess feedwater transients and small break loss-of-coolant accidents. The details of the staff's evaluation are contained in NUREG 0626. The design was accepted for all BWRs and is documented in Section 15 of the Limerick Safety Evaluation Report (SER). This item is close . (Closed) II.K.3.13: Separation of high pressure coolant injection and reactor core isolation cooling system initiation levels. The inspector reviewed the following documents:
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NUREG 0737
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Limerick FSAR sections 7.4.1.1.3.2 and 1.13
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Limerick SER and SSER 2 section 15
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Letter from John Kemper to A. Schwencer dated 5/22/84
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RCIC elementary diagram 791E421TR
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RCIC preoperational test procedure 2P-5 The inspector confirmed that the RCIC system is initiated automatically upon receipt of a low Reactor Pressure Vessel (RPV) water level (level 2). When the RpV level reaches level 8, the steam supply valve for the RCIC turbine is close The system will automatically restart upon receipt of a second low RPV water level signal. Section 6.4.1.16.4 and 6.4.5.2 of preoperational test 2P-50.1 will verify proper operation of the RCIC system components. This item is close J. (Closed) II.K.3.18: Modification of Automatic Depressurization System (ADS) logic for increased diversity. The inspector reviewed the following documents:
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NUREG 0737
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Limerick FSAR section 1.13
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Limerick SER section 15
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General Electric FDDR HH2-3739
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General Electric design specification 22A2919AD
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Elementary diagram 791E403TR, Auto depressurization system
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The inspector confirmed that a manual inhibit switch has been designed for each ADS division. The inhibit switch actuation prohibits the ADS two minute timer from advancing or resettin A status light and alarm are also provided for the switch inhibit positio The ADS design was also changed to provide a seven plus or minus 1/2 minute timer for a bypass of the high drywell pressure contacts. This ensures that a break that does not produce a high drywell pressure will initiate the ADS actuation sequenc This item is closed, (Closed) II.K.3.24: Confirm adequacy of space cooling for high pressure coolant injection and reactor core isolation cooling system The inspector reviewed:
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NUREG 0737
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FSAR sections 1.13 and 9.4. SER section 9.4.2 l
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Bechtel drawings E-16. E-24 and E-67 The inspector confirmed, through review of the AC electrical distribution system drawings, that the associated unit coolers and associated cooling water system components are powered from l onsite emergency power sources. The space cooling system will l perform its design function after a complete loss of offsite AC power. This item is close .0 Spent Fuel pool Racks (250095]
l a. The inspector reviewed the following documents:
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Specification M-115 (PEco) 2-1
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Work package 20-5276-A l -
Quality Control Inspection Report (QCIR) 20-5276-45-1 l
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Drawings C-778, M115 (PECo)-28 and M115 (PEco)-29 l
I The spent fuci racks are free standing assemblies. The inspector l
examined the installed racks for the following attributes:
location, spatial separation, cleanliness, bottom clearance from the l fuel pool liner, bearing plate dimensions and welding, rack serial l nu'nber, and corner angle clip bolting and rivet The Bechtel work package governing the rack installation was found l to include the appropriate vendor instructions for the rack l installation. The QCIR was found to contain appropriate inspection attributes for the racks.
Both the Bechtel construction engineer and quality control inspector were interviewe The Bechtel personnel were knowledgeable of the
, installation requirements and the current installation status of the i rack assemblies.
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The inspector reviewed civil calculation 22.78-3, "Bearing Plate for !
Spent Fuel Pool Liner Plate." The maximum rack bearing load was provided by the vendor (par) which included dead weight of the rack and fuel, hydrodynamic mass, impact and seismic loads. One inch ,
thick bearing plates were provided at several locations since the legs were directly over a section of the liner plate where a leak chase channel existe The bearing stresses were checked for locations without a bearing plate and were found satisfactory for the concrete foundatio t Based upon examination of the installed racks and the review of ,
associated quality engineering and construction documentation and !
the interviews with cognizant personnel, the inspector observed no violations and found this activity well controlle .0 Preoperational Test Procedure Review (370311) j The inspector reviewed preoperational test procedure 2P 58.2, "Redundant Reactivity Control System (RRCS)." Additional documents reviewed included:
FSAR section 7.6.1.8, GE preoperational test program data sheet (22A2271AY i Rev. 3), and GE drawings M-1-C22-1050-E-143.3 through 185.2, M-1-C32-1020- '
E-006-(5) 3, M-1-C22-4010-H-001.9. Several deficiencies were noted. The !
deficiencies and actions taken to resolve them were: 1) The GE preoperational [
test specification required verifying that rod position indication was [
available for one hour after a loss of power. A field deviation disposition request (F00R) is being initiated to delete this requirement since the i power supply at Limerick is a battery bus, via an inverter. 2) FSAR diagram !
7.6.10 showed the APRM not downstele trip as a part of the input for RRCS f ready for reset. A licensing document change notice (LOCN) is being [
initiated to correct the diagram. 3) GE Elementary Drawing M-1-C32-1020- i E-006.3 shows the division 1 FV runback circuit initiating a runback of j the A and 8 feedwater pumps, while the division 2 circuit initiates a (
runback of the C feedwater pump. This is not consistent with FSAR section ;
7.6.1.8.3.3 and GE specification 22A7477 that state that feedwater flow i will be reduced to 0 percent within 15 seconds by either logic divisio j This constitutes a violation of 10 CFR 50, Appendix B, Criterion III which !
rettuires measures to be implemented to ensure that the design basis !
documented in the license application is correctly translated into the design drawings. (88-25-01)
In response to this discrepancy, the connection drawing and field installation were checked, and found to conform with the erroneous elementary drawing. The POT was checked to determine if it would identify this deficiency, and was confirmed to do 5 Unit 1 FDDRs for the redundant reactivity control system (RRCS) were reviewed, and it was determined that this deficiency was identified, corrected on Unit I and designated as applicable to Unit 2. Further review of Unit 1 FDDRs identified as being appitcable to Unit 2 nas been initiated to ensure that appropriate Unit 2 FDDRs were generated and incorporated into the Unit 2 design drawing _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - -
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8.0 Startup Testing Activities _._(70315, 70441, 70459, 70436, 70302, 71302) '
a The inspector witnessed portions of the core spray system logic testing. The inspector noted that portions of the testing were being performed out-of-sequence and that this was documented by test change notice (TCN) as required in AD-8.3P, "Preoperational Test Implementation." A problem was noted in the arca of control of ;
modifications when the out of sequence testing was done. A modifi- l cation installed in step 6.4.2.1(22) which would normally remain in f place for the duration of that portion of the logic test prevented the performance of the minimum flow valve logic testing, step l
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6.4.2.1(3), which was performed out of sequence after step 6.4.2.2(62). ;
The test engineer readily determined and corrected the cause of the !
difficulty in this instance, and no testing was invalidated since the !
first procedural step in the out of sequence step performed did not i i work as anticipated. During this sequence, a logic timing relay was .
1 determined to be outside its specified range. This was documented ,
on a TE #4, and testing continued. All other steps in this group ;
i were carried out satisfactoril The inspector noted that an extra !
1 precaution of a generic nature not listed in the procedure was being !
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followed. Some Limitorque motor operators were supplied with limited l duty-cycle motors. In order to avoid damaging these motors, all l Limitorque MOVs were being allowed to cool for one half hour af ter j two cycles of operation (full closed to full open and return) in a short time perio No other problems were note !
b The inspector observed portions of the preparations for, and conduct of, the initial run of the A recirculation pump conducted as part of ;
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the reactor recirculation system POT. It was noted that the test !
approach was careful and conservative, with a hold put on the test l
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on several occasions while determining that occurrences in the plant !
were not related to this test. No significant problems were l identified, t i
F c The inspector monitored preparations for the integrated flush t including valve line-ups, blocking open the MSIVs and vessel fil l One minor diffic'alty was noted when a boundary valve leaked by and :
. resulted in wetting the drywell floor. It appears as though the !
valve did not stroke fully closed when operated using the moto l This valve was subsequently closed and a tight shutoff obtained. A {
SWO has been generated to check the setting of the torque and limit *
i switches using MOVATS.
- Conduct of the integrated flush was well-controlle It was necessary to si*ghtly modify several flow paths to get adequate '
cleaning, n'ost notably on the main steam lines. Appropriate TCNs were generated to document these changes. Flush path samples for sevtral flew paths were witnessed by a regional specialist inspector ll and will be documented in IR 50-353/8S-2 li
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i d The inspector observed portions of the bearing run-in and vibration reduction work on the 0 0-G. It was initially thought that the high
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vibration on the engine was due to excessive backlash in the gears on the vertical drive. This backlash was checked with satisfactory results. Attempts were then made to rebalance the generator, which i resulted in a reduction of vibration. The bearing run-in was
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continued, and a further vibration reduction resulted when the generator was loaded. During the periodic inspections, the #10 lower bearing was determined to have failed. See IR 50-353/88-22 for details. It was replaced, and further runs were completed without difficulty, e The inspector witnessed portions of the RHR preoperational system testing (2P-49.1). The completion of the test prerequisites was verified through review of the test results package. The inspector attended the briefing for the shift startup engineer and operations personnel. The inspector witnessed logic testing and operation for
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the following valves:
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Valve --Description HV-51Tff5A Loop A and C f'ull flow test line i
HV-C-51-203B 2B RHR heat exchanger outlet bypass
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HV-C-51-203A 2A RHR heat exchanger outlet bypass HV-51-2F021 2B RHR containment spray inboard MOV The following aspects were confirmed during the test: valve stroke 4 times, valve operation from the control room hand switch, simulated t
system response to accident conditions and verification of valve a position control room indication. The test engineer performed the testing in accordance with the test instructions. The test engineer
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was thoroughly knowledgeable of the system characteristics and properly utilized the test change and exceptions during the course
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$ f The inspector observed portions of the standby diesel generator 023
- preoperational testing (2p-24.1). Personnel were present during the test from PECo field engineering, PEco instrumentation, operations, 1 Plymouth Labs, PECO QA and QC, The inspector accompanied test personnel during the switch position verification prior to running the test. The inspector reviewed two safety evaluations regarding isolation tag removal to support the desired testing. The inspector observed initiation of the diesel p.'elube pump cycle and simulation of a LOCA start signal and energization of engine start relay ESS i The engine response parameters including: rpm, generator voltag l ready to load relay energized, watts, vars, air start solenoid energized, engine overspeed and low speed relays energized were
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recorded on a strip chart recorde The engine reached rated speed and voltage in 8.7 seconds, i
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The test engineer performed some logic testing followed by a one hour engine run at 50*4 power. The testing was repeated utilizing relay ESSB to provide the engine start signal. The engine start was verified for a loss of offsite power to the bu The inspector reviewed strip chart recordings that indicate the engine reached 900 RPM in 7.2 second The engine was loaded to 100*4 for one hour then a load reject test was performed. The inspector verified the engine governor maintained generator voltage below 4784 volts. The inspector observed PECo quality control performing the requisite inspections of system restoration The observed test activities were performed in a controlled manner with requisite quality oversight coverage. No unacceptable conditions were identifie .0 Engineering (37055, 52051, 52053, 52055)
a The inspector reviewed Bechtel engineerir.g actions resulting from the SALP improvement program. Bechtel performed self-evaluations with the Intent to enhance the ability of engineering to detect gnd correct problem areas within the design proces The first summary report (Bechtel letter BLP-45025) regarding the areas investigated by Bechtel was reviewed by the inspector. Three key areas of FSAR accuracy, design interfaces and quality assurance inputs were discussed. Engiraering procedures have been revised to provide more effective control ovtr LOCNs that are used to revise the FSAR, licensing coordinators were assigned to thoroughly review design changes for FSAR impact, .ind FSAR code commitments were rereviewed to ensure accuracy with the as-built plan In the area of design interfaces, Bechtel evaluated seven multidiscipline design changes, 10 construction interface areas and a review of plant mirror slide along layout. The review process for Project Change Notice was expanded to include all engineering groups to prevent incomplete inter-disciplinary review Piping calculations for common syste'ns were re-reviewed to ensure that the Unit 2 configuration was properly depicted. A design interface agreement was developed between Bechtel and GE. Also as a result of quality assurance problems identified a common concern with lack of procedural adherence. Bechtel has developed upgraded training to assure employee understanding of the governing engineering procedure The inspector attended a meeting for the Design Process Improvement Program. Recent engineering issues were discuss (d and the associated investigations or corrective actions were presente The meeting appears to provide a unique forum for engineering nanagers to discuss the results of introspective reviews of the engineering effort _ _ _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
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The engineering initiatives appear to be responsive to the problem l areas identified through ooth NRC and licensee channels. No violations were identifie i b The inspector accompanied personnel from Bechtel engineering during [
a walkdown of installed components outside containment. The )
walkdown was performed to gather data to assure the environmental l qualification requirements were satisfied by the field t configuration. The following components were examined: (
i Location Item l panel 2R 208 Agastat relay KMF2078 !
panel 2AC208 Agastat relay KS77-207C, wire fiberglass !
sheathing and AMP terminal board !
panel 20C207 Agastat relay KS76-294A panel 20C901 Vulkene SIS wire panel 2BC224 Buchanan terminal blocks The inspector reviewed specification G-47 and the checklists that were generated for the above items. The licensee identified some conduits lacking an internal :eal at the junction with the enclosures. The inspector was informed that the field would install the seals. The examination was performed in a detailed mannor and the checklists were supplemented by photographs to depict the field configurations. No violations were identifie .0 Independent Design and Construction Assessment (251053, 235060. 49063
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T90W~ DMO. $00T375M3)
The inspector continued to monitor the conduct of the Stone and Vebster Engineering Corporation (SWEC) Independent Design and Construction Assessment (IDCA) activities. The last week of the SWEC onsite construction assesseent effort was observe The SWEC inspection of instruments and instrument tubing in accordance with review plan LK-C-1908 was observed.
I The inspector additionally reviewed the radiographic film that had been identified in SWEC observation report COR-001 and action items CAI 005, 022, 023, 024, 025 and 026. The inspector found that only the radiographic film associated with field weld 6 of piping isometric OLA-212-2 contained an indication representative of a condition that is unacceptable to the criteria of ASVE Section !!!.
The SWEC inspection of metiianical components in the spray pond pump house was monitored by the inspector. The inspector noted a thick grease like substance drioping out of electrical conduit OBp543. When questioned by the inspector, PECo initiated QA finding 2N-626 and determined through chemical analysis, that the substance was flax soap which was used as a cable pull lubricant. pECo additionally issued finding 2G-765 since the
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material was not on the site hazardous / controlled material list. The material was subsequently approved for use with certain discharge and personnel protection restriction The inspector continued to overview the SWEC action items, observation reports and the Bechtel responses to the SWEC concern .0 Reactor Vessel Internals (50051, 50053, 50055)
The inspector reviewed the following documents related to the installation of the reactor pressure vessel (RPV) internals:
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GE Specification 22A4111
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GE travelers 2-280T, "Feedwater Sparger Installation" 2-206T "Control Rod Drives"
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GE drawing 197R626 The installation of the 150 degree feedwater sparger was observed by the inspector. Representatives from GE project engineering and quality control were present. The sparger was soaked for an appropriate length of time in the nitrogen bath. The sparger was inserted into the proper nozzle and thermal expansion creates an interference fit. The thermal
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I sleeve and piston rings were dunked into the nittogen bath. The temporary compressive rings were removed and tna sparger end was soaked in the nitrogen bat The sparger was inserted into the nozzle without having to utilize the available hydraulic ra The inspector additionally observed preparatory crew trainin The installation of selected CR0s was observed by the inspector. In particular CRDs 22-43, 26-43, 42-19 and 46-19 were monitored. GE quality control personnel were present and performed the requisite inspection The t-aveler and special process control shuts were properly recorde The CR0s were carefully handled, cleaned and inserted into the appropriate locations with the necessary gasket material. The CR9s were temporarily bolted in plac QC performed thorough examinations in particular to ensure the CRD flange surface was flush prior to bolt up. Both work operations wer7 properly controlled by GE and no violations were observe .0 Deficiency Reports (35060)
The inspector reviewed selected deficiency reports identified within the Bechtel and PEco quality assurance program. Bechtel generates MCARs for adverse conditions that may be reportable to the NRC. The inspector reviewed MCAR 1-42 regarding 16 flow sensors that were not sealed in accordance with the associated qualification configuration. Water entry into the flow sensor could cause a failure that would disable the drywell unit coolers. New gasketed flow sensors have been procurred for Unit 2 to eliminate the problem. Additional examinations will be performed to ensure tnat devices are installed in the qualified stat _ . _ t
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PECo SDR 244-2 was reviewed with regard to the flow sensor problem. PECo t
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determined the deficiency was not reportable based upon an analysis that i I showeo sufficient drywell mixing would occur following a LOCA to prevent !
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hydrogen and oxygen stratification without drywell cooler fan operatio !
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I, The flow sensor problem was determined to potentis11y erist on Unit 1.
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The licensee has taken compensatory measures to bypass the flow sensors ;
, so the drywell fans are enanually controlled after the concern was ;
transmitted to the plant staff on September 24, 1988. This issue was i
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determined to potentially apply to Unit 1 on August 10, 1938 and a JC0 ,
a was transmitted to PEco engineering on August 22, 193 I l
The inspector aJditionally reviewed MCAR 1-43 regarding conductive !
, Westinghouse motor starter insulation that caused a short circui Four i j wiring compartments were found on Unit 2 with the defective wiring which [
l was subsequently replaced. No di?crepancies were found on Unit I wirin l
! The inspector was informed PECo has issued SDR 250-2, and this item has -
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been reported to the NRC.
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Numerous PFCo SDRs were additionally reviewed as follows:
' SDR Description i
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2W2 Hot air bath calibration method led to incorrect calibration of f bulb and capillary type instruments. The affected instruments j were reviewed by the licensee for operability concerns and non
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were identified,
- 242-2 Radiographic film for RHR pipe weld OLA 212-2 FW-6 indicates I
an unacceptable indication. Th;s is still under revie l
{ 245-2 Damaged terminal blocks were found within level switches. This a is still under review.
, 247-2 Eight mounting bolts or welds were missing on a 4S0 V loaa
- cente The as-built condition war, analyzed by engineering and
! found acceptabl !
! 248-2 Some meter relay panels were incorrectly classified by GE as i j non-!E for the standby liquid control system. This is still l
under review.
l 249-2 *, a f t, shutdown instrumentation can be lost due to potential ;
i fires affecting tne operation of ESW valves. This item has i a been reported for both Unit I and This issue was documented t i on September 8, 19BB.
l The inspector concluded ths; adequate programs exist to ensure j significant deficiencies are identified and reviewed for potential
) reportability and ultimate correctio The issues did rot appear to be l ccmunicated in a timely m to Unit 1 operations staff in the cases j of SOR 244-2 and 249- Th a "ern is being reviewed by the Unit 1 NRC s resident inspectors..
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13.0 Assurance of Quality (40301)
During the conduct of diesel generater tetting ceteribed in soction 8 of this report, the inspector noted the PECo Senior Vice President-Nuclear per#orming a piant tour. TL_ presence of senior licensee management in the field is indicative of the level of attention and oversight provided to work activitie The failure to transfer system design change information into the Unit 2 design was reviewed in >ection 7.0. Full assurance should be maintained that design changes made during the Unit 2 su ension of construction activities have been properly incorporated into the desig Seci* ion o 0 outlines startup testing that has been performed in strict compiiance with the appropriate procedural instructions, Section 9.0 describes further Bechtel engineering initiative to perform introspective self-assessments to identify weaknesses in the engineering are The lack of timely transmittal of potentially adverse information to the operating staff was discussed in section 1 The NRB met at the Limerick site on October 6, 1988, to review safety and operations issues for both Limerick and Peach Bottom. The resident inspector attended portions of the discussion of Unit 1 Operations which might affect Unit 2, and the discussion of the Startup Program. The NRB was presented with a briefing on recently TRB and QA approved preoperational test results package.s. The NRB also requested an update on the status of work related to NUREG 1275, vol. 2 on Air System Problems. The response was that a loss of air procedure had been prepared and that training on the procedure was in progress. The NRB was also presented information on the testing scheoule and status. The members expressed concern that all the drawings associah j with the various systems be complete and up-to-date at the time o' system turnover to the plant staff for operatio The members also requested information on the Unit 2 test schedule and potential impacts on, or conflicts with the Unit 1 outage schedul The Unit 2 startup manager explained the plans for ccordination with the Unit 1 outage activitie .0 Meetings with Licensee (230703B,71301)
The NRC resident inspector discussed the issues and findings in this report with members of the licensee's staff on a weekly basis, and at an exit meeting held on October 17, 1988. Based on discussions held with licensee representatives on October 17, 1988, it was determined that this report does not contain information subject to 10 CFR 2.790 restriction ~
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The inspector attended a meeting on September 30, ISOS between PECo Fire Protection personnel and the Unit 1 NRC resident inspectors. Topics of discussion included failure of the motor driven fire pump to meet the discharge head specified in the ST, failure te deliver flow at pressure as specified in FPER and FSAR, water curtain flow per unit area, and the capabilities and equipment qualification status of the ' backup' fire pump available. A PECo licensing representative indicated that revised system operability requirements were in the process of being generated based on detailed computer analysis of the installed system. It was also stated that appropriate documentation was being drawn up to eliminate the TS requirements on fire protection system and equipmen The inspector participated in a conference call on October 6,1988 with pECo engineering personnel and Unit 1 NRC resident inspectors regarding equipment located in the battery rooms. The discussion topics included incorrect information in the FPER, ambiguous statements in the FSAR, -
incorrect information in the SER, applicability of IEEE standards, capabilities of installed ventilation and alarm systems, qualification of installed ventilation systems and potential for hydrogen pocket formation.
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, APPENDIX 1 Acronyms and Abbreviati6ns AC Alternating Current ADN Apparent Discrepancy Notification ADS Automatic Depressurization System Ap Appendix APRM Average Power Range Monitor BWR Boiling Water Reactor BWROG Boiling Water Reactor Owners Group CS Cote Spray CRD Control Rod Drive CRDM Control Rod Drive Mechanism DAI Design Action Item 0-G Diesel Generator E0P Emergency Operating Procedure ESF Engineered Safety Feature ESW Emergency Service Water FDDR Field Deviation Disposition Request FPER Fire Protection Evaluation Report FSAR Final Safety Analysis Report FW Feedwat e'-
GE General Electric HPCI High Pressure Coolant Injectiu IDCA Independent Design and Construct on Assessment IEEE Institute of Electrical and Electronics Engineers IR Inspection Report JC0 Justification for Continued Operation LDCN L. censing Document Change Notice LGS Limerick Generating Station LPCI Low Pressure Coolant Injection MCAR Management's Corrective Action Requests MCC Motor Control Center M-G Mntor Generator MOV Motor Operated Valve M0 VATS Motor Operated Valve Analysis and Test System MSIV Main Steam Isolation Valve NCR Nonconformance Reports NQA Nuclear Quality Assurance NRB Nuclear Review Board NRC Nuclear Regulatory Commission NRR Office of Nuclear Reactor Regulation PCN Project Change Notice PCR Project Engineering Change Request PECo Philadelphia Electric Conpany POT Preoperational Test QA Quality Assurance QAD Quality Assurance Diagram QC Quality Control
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QCIR Quality Control Inspection Report RCIC Reactor Core Isolation Cooling RPV Reactor Pressure Vessel RHR Residual Heat Removal RRCS Redundant Reactivity Control System SAL Service Advice Letter SALP Systematic Assessment of Licensee Performance SOR Significant Deficiency Report SER Sr.foty Evaluation Report SIL Service Information Letter SSER Supplemented Safety Evaluation Report ST Surveillance Test SWEC Stone and Webster Engineering Corporation SWO Startup Work Order TCN Test Change Notice TE Test exception TRB Test Review Board TRIP Transient Response Implementation Plan TS Technical Specifications