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Category:INSPECTION REPORT
MONTHYEARIR 05000341/19990171999-10-21021 October 1999 Insp Rept 50-341/99-17 on 990927-1005.No Violations Noted. Major Areas Inspected:Incident Involving Loaded Firearm in Protected Area Identified on 990922 & Being Considered as Noncited Violation IR 05000341/19990111999-10-0707 October 1999 Insp Rept 50-341/99-11 on 990724-0908.Two NCVs Noted.Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000341/19990101999-08-10010 August 1999 Insp Rept 50-341/99-10 on 990619-0723.Violations Noted.Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000341/19990061999-08-0606 August 1999 Insp Rept 50-341/99-06 on 990712-0716.No Violations Noted. Major Areas Inspected:Review of Various Aspects of Licensee Chemistry & Radiation Protection Programs,Specifically in Listed Areas IR 05000341/19990091999-07-12012 July 1999 Insp Rept 50-341/99-09 on 990516-0618.No Violations Noted. Major Areas Inspected:Operations,Engineering,Maint & Plant Operations IR 05000016/19990011999-06-30030 June 1999 Insp Rept 50-016/99-01 on 990614-17.No Violations Noted. Major Areas Inspected:Mgt & Control,Decommissioning Support Activities,Industry Safety & Radiological Safety IR 05000341/19990071999-06-0101 June 1999 Insp Rept 50-341/99-07 on 990402-0515.Violations Noted.Major Areas Inspected:Aspects of Licensee Operations,Engineering, Maint & Plant Support IR 05000341/19990041999-05-26026 May 1999 Insp Rept 50-341/99-04 on 990503-07.No Violations Noted. Major Areas Inspected:Radiological Emergency Response Preparedness Program,Aspect of Plant Support IR 05000341/19990081999-04-29029 April 1999 Partially Withheld (Ref 10CFR73.21) Insp Rept 50-341/99-08 on 990405-09.No Violations Noted.Major Areas Inspected: Physical Protection Program,Aspect of Plant Support IR 05000341/19990031999-04-23023 April 1999 Insp Rept 50-341/99-03 on 990218-0401.Two Violations Noted & Being Treated as non-cited Violations.Major Areas Inspected: Operations,Engineering,Maint & Plant Support ML20205P1751999-04-14014 April 1999 Insp Rept 50-341/99-06 on 990315-19.No Violations Noted. Major Areas Inspected:Licensee Plant Support Performance Re Gaseous & Liquid Effluents,Liquid Waste Processing,Esf Filtration & CR Heating Ventilation & Air Conditioning IR 05000341/19990051999-03-19019 March 1999 Insp Rept 50-341/99-05 on 990308-11.No Violations Noted. Major Areas Inspected:Reviewed Fire Protection Program,An Aspect of Plant Support IR 05000341/19990021999-03-0808 March 1999 Insp Rept 50-341/99-02 on 990111-29.Violations Noted.Major Areas Inspected:Review of Engineering & Technical Support & Corrective Actions IR 05000341/19980151999-02-22022 February 1999 Errata to Insp Rept 50-341/98-15.Rept Incorrectly Documented That Loose Internal Sleeving on Turbine Control Valve Caused Power Oscillations Greater than 10% During Plant Operation IR 05000341/19980191999-01-21021 January 1999 Insp Rept 50-341/98-19 on 981110-990104.No Violations Noted. Major Areas Inspected:Operations,Engineering,Maintenance & Plant Support ML20198D5671998-12-0707 December 1998 Insp Rept 50-341/98-15 on 980922-1109.Noncited Violations Were Identified.Major Areas Inspected:Aspects of Licensee Operations,Maint,Engineering & Plant Support IR 05000341/19980171998-11-16016 November 1998 Insp Rept 50-341/98-17 on 980909-1021.No Violations Noted. Major Areas Inspected:Review of Implementation of Inservice Insp Program for Plant Refueling Outage 6 IR 05000341/19980181998-10-30030 October 1998 Insp Rept 50-341/98-18 on 981006-08.No Violations Noted. Major Areas Inspected:Licensee Implementation of 10CFR50.65, Requirements for Monitoring Effectiveness of Maintenance at Nuclear Power Plants IR 05000341/19980131998-10-20020 October 1998 Insp Rept 50-341/98-13 on 980730-0921.No Violations Noted. Major Areas Inspected:Aspects Oflicensee Operations, Engineering,Maint & Plant Support IR 05000341/19980161998-10-0606 October 1998 Insp Rept 50-341/98-16 on 981014-18.No Violations Noted. Major Areas Inspected:Alara Planning & Controls for Sixth Refueling Outage,Internal Exposure Monitoring,Radiological Surveys & Posting & Radiation Worker Performance IR 05000016/19980071998-09-30030 September 1998 Insp Rept 50-016/98-07 on 980909-11.No Violations Noted. Major Areas Inspected:Licensee Mgt & Control,Decommissioning Support Activities,Industrial Safety & Radiological Safety IR 05000341/19980121998-09-0101 September 1998 Insp Rept 50-341/98-12 on 980619-0803.Violations Noted. Major Areas Inspected:Aspects of Licensee Operations, Engineering,Maint & Plant Support IR 05000341/19980081998-07-14014 July 1998 Insp Rept 50-341/98-08 on 980504-0618.Violations Noted.Major Areas Inspected:Aspects of Licensee Operations,Engineering, Maint & Plant Support IR 05000341/19980101998-06-29029 June 1998 Insp Rept 50-341/98-10 on 980608-12.No Violations Noted. Major Areas Inspected:Plant Support & Evaluation of Licensee Performance During Station Biennial Exercise of Emergency Plan IR 05000341/19980111998-06-25025 June 1998 Insp Rept 50-341/98-11 on 980608-12.No Violations Noted. Major Areas Inspected:Radiological Controls for Spent Fuel Pool Clean Out Project IR 05000341/19980091998-06-0404 June 1998 Insp Rept 50-341/98-09 on 980511-15.No Violations Noted. Major Areas Inspected:Aspects of Licensee Performance Re Physical Security for Facility IR 05000341/19980061998-06-0303 June 1998 Insp Rept 50-341/98-06 on 980317-0427.No Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000341/19980031998-05-11011 May 1998 Insp Rept 50-341/98-03 on 971221-980316.Violations Noted. Major Areas Inspected:Aspects of Licensee Operations, Engineering,Maint & Plant Support ML20247D4511998-05-0606 May 1998 Insp Rept 50-341/98-07 on 980406-09.Violations Noted.Major Areas Inspected:Plant Support IR 05000016/19980061998-04-21021 April 1998 Insp Rept 50-016/98-06 on 980324-26.No Violations Noted. Major Areas Inspected:Licensee Mgt & Control,Decommissioning Support Activities & Radiological Safety ML20216E7901998-04-10010 April 1998 Insp Rept 50-341/98-05 on 980320-0406.Violations Noted: Failure to Demonstrate Reactor Protection Sys Trip Function Units & Isolation Actuation Trip Units within Response Time Limit of at Least Once Per 18 Months IR 05000341/19980041998-03-31031 March 1998 Insp Rept 50-341/98-04 on 971113-980226.Violations Noted. Major Areas Inspected:Operations,Engineering & Plant Support ML20217K2821998-03-31031 March 1998 Insp Rept 50-341/98-04 on 971113-980226.Violations Noted. Major Areas Inspected:Operations,Engineering & Plant Support IR 05000341/19970161998-02-0505 February 1998 Insp Rept 50-341/97-16 on 981108-0105.Noncited Violation Identified.Major Areas Inspected:License Operations,Maint, Engineering & Plant Support IR 05000341/19970171998-01-21021 January 1998 Insp Rept 50-341/97-17 on 971201-05.No Violations Noted. Major Areas Inspected:Conduct of Operations,Operator Training & Qualification & Miscellaneous Operations Issues ML20202H8581998-01-0303 January 1998 Insp Rept 50-341/97-14 on 970923-1107.Violations Noted. Major Areas Inspected:Operations,Engineering,Maintenance & Plant Support IR 05000341/19970141998-01-0202 January 1998 Insp Rept 50-341/97-14 on 970923-1107.Violations Noted.Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000341/19970151997-11-0404 November 1997 Insp Rept 50-341/97-15 on 971008-10.No Violations Noted. Major Areas Inspected:Plant Support Performance Re mid-cycle Outage Chemistry,Alara Planning & Implementation & Radiation Worker Practices ML20198N3291997-10-29029 October 1997 Insp Rept 50-341/97-11 on 970804-1010.Violations Noted. Major Areas Inspected:Review & Assess Engineering & Technical Support at Plant IR 05000341/19970131997-10-27027 October 1997 Insp Rept 50-341/97-13 on 970811-0922.Violations Noted.Major Areas Inspected:Operations,Engineering,Maint & Plant Support IR 05000341/19970121997-09-25025 September 1997 Insp Rept 50-341/97-12 on 970804-06.No Violations Noted. Major Areas Inspected:Exam Procedures & Representative Records,Observations of Activities & Interviews W/Staff & Conduct of Security & Safeguards Activities IR 05000341/19970101997-09-25025 September 1997 Insp Rept 50-341/97-10 on 970630-0812.No Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000341/19970071997-08-26026 August 1997 Insp Rept 50-341/97-07 on 970508-0630.Violations Noted. Major Areas Inspected:Operations,Maintenance,Engineering & Plant Support ML20149K8691997-07-0101 July 1997 Insp Rept 50-341/97-03 on 970320-0509.Violations Noted.Major Areas Inspected:Operations,Engineering,Maint & Plant Plant Support IR 05000341/19970091997-06-26026 June 1997 RP Insp Rept 50-341/97-09 on 970602-06.No Violations Noted. Major Areas Inspected:Plant Support Performance Re Chemistry,Effluents & Environ Monitoring ML20148N1471997-06-19019 June 1997 Insp Rept 50-341/97-05 on 970512-30.Violations Noted. Major Areas Inspected:Maint & Engineering IR 05000341/19970081997-06-13013 June 1997 Insp Rept 50-341/97-08 on 970519-23.No Violations Noted. Major Areas Inspected:Review of Physical Security Program Performance IR 05000341/19970041997-06-13013 June 1997 Insp Rept 50-341/97-04 on 970310-14 & 0512-16.No Violations Noted.Major Areas Inspected:Review of Representative Post Job ALARA Reviews,Radiation Exposure Data & self-assessments from 1996 Refueling Outage ML20140D3521997-06-0202 June 1997 Insp Rept 50-341/97-02 on 970201-0319.Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000341/19970061997-05-21021 May 1997 Insp Rept 50-341/97-06 on 970428-0502.No Violations Noted. Major Areas Inspected:Insp Included Review of Radiological Emergency Response Preparedness Program 1999-08-06
[Table view] Category:NRC-GENERATED
MONTHYEARIR 05000341/19990171999-10-21021 October 1999 Insp Rept 50-341/99-17 on 990927-1005.No Violations Noted. Major Areas Inspected:Incident Involving Loaded Firearm in Protected Area Identified on 990922 & Being Considered as Noncited Violation IR 05000341/19990111999-10-0707 October 1999 Insp Rept 50-341/99-11 on 990724-0908.Two NCVs Noted.Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000341/19990101999-08-10010 August 1999 Insp Rept 50-341/99-10 on 990619-0723.Violations Noted.Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000341/19990061999-08-0606 August 1999 Insp Rept 50-341/99-06 on 990712-0716.No Violations Noted. Major Areas Inspected:Review of Various Aspects of Licensee Chemistry & Radiation Protection Programs,Specifically in Listed Areas IR 05000341/19990091999-07-12012 July 1999 Insp Rept 50-341/99-09 on 990516-0618.No Violations Noted. Major Areas Inspected:Operations,Engineering,Maint & Plant Operations IR 05000016/19990011999-06-30030 June 1999 Insp Rept 50-016/99-01 on 990614-17.No Violations Noted. Major Areas Inspected:Mgt & Control,Decommissioning Support Activities,Industry Safety & Radiological Safety IR 05000341/19990071999-06-0101 June 1999 Insp Rept 50-341/99-07 on 990402-0515.Violations Noted.Major Areas Inspected:Aspects of Licensee Operations,Engineering, Maint & Plant Support IR 05000341/19990041999-05-26026 May 1999 Insp Rept 50-341/99-04 on 990503-07.No Violations Noted. Major Areas Inspected:Radiological Emergency Response Preparedness Program,Aspect of Plant Support IR 05000341/19990081999-04-29029 April 1999 Partially Withheld (Ref 10CFR73.21) Insp Rept 50-341/99-08 on 990405-09.No Violations Noted.Major Areas Inspected: Physical Protection Program,Aspect of Plant Support IR 05000341/19990031999-04-23023 April 1999 Insp Rept 50-341/99-03 on 990218-0401.Two Violations Noted & Being Treated as non-cited Violations.Major Areas Inspected: Operations,Engineering,Maint & Plant Support ML20205P1751999-04-14014 April 1999 Insp Rept 50-341/99-06 on 990315-19.No Violations Noted. Major Areas Inspected:Licensee Plant Support Performance Re Gaseous & Liquid Effluents,Liquid Waste Processing,Esf Filtration & CR Heating Ventilation & Air Conditioning IR 05000341/19990051999-03-19019 March 1999 Insp Rept 50-341/99-05 on 990308-11.No Violations Noted. Major Areas Inspected:Reviewed Fire Protection Program,An Aspect of Plant Support IR 05000341/19990021999-03-0808 March 1999 Insp Rept 50-341/99-02 on 990111-29.Violations Noted.Major Areas Inspected:Review of Engineering & Technical Support & Corrective Actions IR 05000341/19980151999-02-22022 February 1999 Errata to Insp Rept 50-341/98-15.Rept Incorrectly Documented That Loose Internal Sleeving on Turbine Control Valve Caused Power Oscillations Greater than 10% During Plant Operation IR 05000341/19980191999-01-21021 January 1999 Insp Rept 50-341/98-19 on 981110-990104.No Violations Noted. Major Areas Inspected:Operations,Engineering,Maintenance & Plant Support ML20198D5671998-12-0707 December 1998 Insp Rept 50-341/98-15 on 980922-1109.Noncited Violations Were Identified.Major Areas Inspected:Aspects of Licensee Operations,Maint,Engineering & Plant Support IR 05000341/19980171998-11-16016 November 1998 Insp Rept 50-341/98-17 on 980909-1021.No Violations Noted. Major Areas Inspected:Review of Implementation of Inservice Insp Program for Plant Refueling Outage 6 IR 05000341/19980181998-10-30030 October 1998 Insp Rept 50-341/98-18 on 981006-08.No Violations Noted. Major Areas Inspected:Licensee Implementation of 10CFR50.65, Requirements for Monitoring Effectiveness of Maintenance at Nuclear Power Plants IR 05000341/19980131998-10-20020 October 1998 Insp Rept 50-341/98-13 on 980730-0921.No Violations Noted. Major Areas Inspected:Aspects Oflicensee Operations, Engineering,Maint & Plant Support IR 05000341/19980161998-10-0606 October 1998 Insp Rept 50-341/98-16 on 981014-18.No Violations Noted. Major Areas Inspected:Alara Planning & Controls for Sixth Refueling Outage,Internal Exposure Monitoring,Radiological Surveys & Posting & Radiation Worker Performance IR 05000016/19980071998-09-30030 September 1998 Insp Rept 50-016/98-07 on 980909-11.No Violations Noted. Major Areas Inspected:Licensee Mgt & Control,Decommissioning Support Activities,Industrial Safety & Radiological Safety IR 05000341/19980121998-09-0101 September 1998 Insp Rept 50-341/98-12 on 980619-0803.Violations Noted. Major Areas Inspected:Aspects of Licensee Operations, Engineering,Maint & Plant Support IR 05000341/19980081998-07-14014 July 1998 Insp Rept 50-341/98-08 on 980504-0618.Violations Noted.Major Areas Inspected:Aspects of Licensee Operations,Engineering, Maint & Plant Support IR 05000341/19980101998-06-29029 June 1998 Insp Rept 50-341/98-10 on 980608-12.No Violations Noted. Major Areas Inspected:Plant Support & Evaluation of Licensee Performance During Station Biennial Exercise of Emergency Plan IR 05000341/19980111998-06-25025 June 1998 Insp Rept 50-341/98-11 on 980608-12.No Violations Noted. Major Areas Inspected:Radiological Controls for Spent Fuel Pool Clean Out Project IR 05000341/19980091998-06-0404 June 1998 Insp Rept 50-341/98-09 on 980511-15.No Violations Noted. Major Areas Inspected:Aspects of Licensee Performance Re Physical Security for Facility IR 05000341/19980061998-06-0303 June 1998 Insp Rept 50-341/98-06 on 980317-0427.No Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000341/19980031998-05-11011 May 1998 Insp Rept 50-341/98-03 on 971221-980316.Violations Noted. Major Areas Inspected:Aspects of Licensee Operations, Engineering,Maint & Plant Support ML20247D4511998-05-0606 May 1998 Insp Rept 50-341/98-07 on 980406-09.Violations Noted.Major Areas Inspected:Plant Support IR 05000016/19980061998-04-21021 April 1998 Insp Rept 50-016/98-06 on 980324-26.No Violations Noted. Major Areas Inspected:Licensee Mgt & Control,Decommissioning Support Activities & Radiological Safety ML20216E7901998-04-10010 April 1998 Insp Rept 50-341/98-05 on 980320-0406.Violations Noted: Failure to Demonstrate Reactor Protection Sys Trip Function Units & Isolation Actuation Trip Units within Response Time Limit of at Least Once Per 18 Months IR 05000341/19980041998-03-31031 March 1998 Insp Rept 50-341/98-04 on 971113-980226.Violations Noted. Major Areas Inspected:Operations,Engineering & Plant Support ML20217K2821998-03-31031 March 1998 Insp Rept 50-341/98-04 on 971113-980226.Violations Noted. Major Areas Inspected:Operations,Engineering & Plant Support IR 05000341/19970161998-02-0505 February 1998 Insp Rept 50-341/97-16 on 981108-0105.Noncited Violation Identified.Major Areas Inspected:License Operations,Maint, Engineering & Plant Support IR 05000341/19970171998-01-21021 January 1998 Insp Rept 50-341/97-17 on 971201-05.No Violations Noted. Major Areas Inspected:Conduct of Operations,Operator Training & Qualification & Miscellaneous Operations Issues ML20202H8581998-01-0303 January 1998 Insp Rept 50-341/97-14 on 970923-1107.Violations Noted. Major Areas Inspected:Operations,Engineering,Maintenance & Plant Support IR 05000341/19970141998-01-0202 January 1998 Insp Rept 50-341/97-14 on 970923-1107.Violations Noted.Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000341/19970151997-11-0404 November 1997 Insp Rept 50-341/97-15 on 971008-10.No Violations Noted. Major Areas Inspected:Plant Support Performance Re mid-cycle Outage Chemistry,Alara Planning & Implementation & Radiation Worker Practices ML20198N3291997-10-29029 October 1997 Insp Rept 50-341/97-11 on 970804-1010.Violations Noted. Major Areas Inspected:Review & Assess Engineering & Technical Support at Plant IR 05000341/19970131997-10-27027 October 1997 Insp Rept 50-341/97-13 on 970811-0922.Violations Noted.Major Areas Inspected:Operations,Engineering,Maint & Plant Support IR 05000341/19970121997-09-25025 September 1997 Insp Rept 50-341/97-12 on 970804-06.No Violations Noted. Major Areas Inspected:Exam Procedures & Representative Records,Observations of Activities & Interviews W/Staff & Conduct of Security & Safeguards Activities IR 05000341/19970101997-09-25025 September 1997 Insp Rept 50-341/97-10 on 970630-0812.No Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000341/19970071997-08-26026 August 1997 Insp Rept 50-341/97-07 on 970508-0630.Violations Noted. Major Areas Inspected:Operations,Maintenance,Engineering & Plant Support ML20149K8691997-07-0101 July 1997 Insp Rept 50-341/97-03 on 970320-0509.Violations Noted.Major Areas Inspected:Operations,Engineering,Maint & Plant Plant Support IR 05000341/19970091997-06-26026 June 1997 RP Insp Rept 50-341/97-09 on 970602-06.No Violations Noted. Major Areas Inspected:Plant Support Performance Re Chemistry,Effluents & Environ Monitoring ML20148N1471997-06-19019 June 1997 Insp Rept 50-341/97-05 on 970512-30.Violations Noted. Major Areas Inspected:Maint & Engineering IR 05000341/19970081997-06-13013 June 1997 Insp Rept 50-341/97-08 on 970519-23.No Violations Noted. Major Areas Inspected:Review of Physical Security Program Performance IR 05000341/19970041997-06-13013 June 1997 Insp Rept 50-341/97-04 on 970310-14 & 0512-16.No Violations Noted.Major Areas Inspected:Review of Representative Post Job ALARA Reviews,Radiation Exposure Data & self-assessments from 1996 Refueling Outage ML20140D3521997-06-0202 June 1997 Insp Rept 50-341/97-02 on 970201-0319.Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000341/19970061997-05-21021 May 1997 Insp Rept 50-341/97-06 on 970428-0502.No Violations Noted. Major Areas Inspected:Insp Included Review of Radiological Emergency Response Preparedness Program 1999-08-06
[Table view] Category:TEXT-INSPECTION & AUDIT & I&E CIRCULARS
MONTHYEARIR 05000341/19990171999-10-21021 October 1999 Insp Rept 50-341/99-17 on 990927-1005.No Violations Noted. Major Areas Inspected:Incident Involving Loaded Firearm in Protected Area Identified on 990922 & Being Considered as Noncited Violation IR 05000341/19990111999-10-0707 October 1999 Insp Rept 50-341/99-11 on 990724-0908.Two NCVs Noted.Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000341/19990101999-08-10010 August 1999 Insp Rept 50-341/99-10 on 990619-0723.Violations Noted.Major Areas Inspected:Operations,Maint,Engineering & Plant Support ML20210Q4191999-08-10010 August 1999 Notice of Violation from Insp on 990619-0723.Violation Noted:Within 2 Hours of Removing Div 1 Diesel Generator 11 from Svc Licensee Failed to Verify That Components Depending on Div 2 Diesel Were Operable IR 05000341/19990061999-08-0606 August 1999 Insp Rept 50-341/99-06 on 990712-0716.No Violations Noted. Major Areas Inspected:Review of Various Aspects of Licensee Chemistry & Radiation Protection Programs,Specifically in Listed Areas ML20210J2201999-07-23023 July 1999 Notice of Violation from Insp on 990524.Violation Noted: on 980920 Kf Enoch Engaged in Deliberate Misconduct That Caused Licensee to Be in Violation of Condition of License IR 05000341/19990091999-07-12012 July 1999 Insp Rept 50-341/99-09 on 990516-0618.No Violations Noted. Major Areas Inspected:Operations,Engineering,Maint & Plant Operations IR 05000016/19990011999-06-30030 June 1999 Insp Rept 50-016/99-01 on 990614-17.No Violations Noted. Major Areas Inspected:Mgt & Control,Decommissioning Support Activities,Industry Safety & Radiological Safety IR 05000341/19990071999-06-0101 June 1999 Insp Rept 50-341/99-07 on 990402-0515.Violations Noted.Major Areas Inspected:Aspects of Licensee Operations,Engineering, Maint & Plant Support IR 05000341/19990041999-05-26026 May 1999 Insp Rept 50-341/99-04 on 990503-07.No Violations Noted. Major Areas Inspected:Radiological Emergency Response Preparedness Program,Aspect of Plant Support IR 05000341/19990081999-04-29029 April 1999 Partially Withheld (Ref 10CFR73.21) Insp Rept 50-341/99-08 on 990405-09.No Violations Noted.Major Areas Inspected: Physical Protection Program,Aspect of Plant Support IR 05000341/19990031999-04-23023 April 1999 Insp Rept 50-341/99-03 on 990218-0401.Two Violations Noted & Being Treated as non-cited Violations.Major Areas Inspected: Operations,Engineering,Maint & Plant Support ML20205P1751999-04-14014 April 1999 Insp Rept 50-341/99-06 on 990315-19.No Violations Noted. Major Areas Inspected:Licensee Plant Support Performance Re Gaseous & Liquid Effluents,Liquid Waste Processing,Esf Filtration & CR Heating Ventilation & Air Conditioning IR 05000341/19990051999-03-19019 March 1999 Insp Rept 50-341/99-05 on 990308-11.No Violations Noted. Major Areas Inspected:Reviewed Fire Protection Program,An Aspect of Plant Support IR 05000341/19990021999-03-0808 March 1999 Insp Rept 50-341/99-02 on 990111-29.Violations Noted.Major Areas Inspected:Review of Engineering & Technical Support & Corrective Actions ML20207J1531999-03-0808 March 1999 Notice of Violation from Insp on 990111-29.Violation Noted: as of Jan 1999,calculation DC-0367, Design Calculations for RHR Sys, Rev 6,incorrectly Concluded That Stated Item Would Occur IR 05000341/19980151999-02-22022 February 1999 Errata to Insp Rept 50-341/98-15.Rept Incorrectly Documented That Loose Internal Sleeving on Turbine Control Valve Caused Power Oscillations Greater than 10% During Plant Operation IR 05000341/19980191999-01-21021 January 1999 Insp Rept 50-341/98-19 on 981110-990104.No Violations Noted. Major Areas Inspected:Operations,Engineering,Maintenance & Plant Support ML20198D5671998-12-0707 December 1998 Insp Rept 50-341/98-15 on 980922-1109.Noncited Violations Were Identified.Major Areas Inspected:Aspects of Licensee Operations,Maint,Engineering & Plant Support IR 05000341/19980171998-11-16016 November 1998 Insp Rept 50-341/98-17 on 980909-1021.No Violations Noted. Major Areas Inspected:Review of Implementation of Inservice Insp Program for Plant Refueling Outage 6 PNO-III-98-055, on 981113,licensee Shut Unit Down to Repair Steam Leak from Reactor Feedwater Check Valve.Valve Is SR & Would Provide Containment Isolation Function Under Accident Conditions1998-11-13013 November 1998 PNO-III-98-055:on 981113,licensee Shut Unit Down to Repair Steam Leak from Reactor Feedwater Check Valve.Valve Is SR & Would Provide Containment Isolation Function Under Accident Conditions IR 05000341/19980181998-10-30030 October 1998 Insp Rept 50-341/98-18 on 981006-08.No Violations Noted. Major Areas Inspected:Licensee Implementation of 10CFR50.65, Requirements for Monitoring Effectiveness of Maintenance at Nuclear Power Plants PNO-III-98-048, on 981008,Detroit Edison Declared Alert Based on Operator Rept of Smoke & Fire Alarm Coming from EDG 12 Control Panel in Switchgear Room.Operator Tripped EDG 12, Opened Output Breaker & Left Switchgear Room1998-10-21021 October 1998 PNO-III-98-048:on 981008,Detroit Edison Declared Alert Based on Operator Rept of Smoke & Fire Alarm Coming from EDG 12 Control Panel in Switchgear Room.Operator Tripped EDG 12, Opened Output Breaker & Left Switchgear Room IR 05000341/19980131998-10-20020 October 1998 Insp Rept 50-341/98-13 on 980730-0921.No Violations Noted. Major Areas Inspected:Aspects Oflicensee Operations, Engineering,Maint & Plant Support IR 05000341/19980161998-10-0606 October 1998 Insp Rept 50-341/98-16 on 981014-18.No Violations Noted. Major Areas Inspected:Alara Planning & Controls for Sixth Refueling Outage,Internal Exposure Monitoring,Radiological Surveys & Posting & Radiation Worker Performance IR 05000016/19980071998-09-30030 September 1998 Insp Rept 50-016/98-07 on 980909-11.No Violations Noted. Major Areas Inspected:Licensee Mgt & Control,Decommissioning Support Activities,Industrial Safety & Radiological Safety ML20154D1361998-09-30030 September 1998 Notice of Violation from Insp on 980304-0702.Violation Noted:On 980213,individual Failed to Contact Radiation Protection Dept for Appropriate Radiological Briefing IR 05000341/19980121998-09-0101 September 1998 Insp Rept 50-341/98-12 on 980619-0803.Violations Noted. Major Areas Inspected:Aspects of Licensee Operations, Engineering,Maint & Plant Support ML20236R1251998-07-15015 July 1998 Notice of Violation from Insp Completed on 970922.Violation Noted:Licensee Made Revs to Procedures as Described in Safety Analysis Rept W/O Receiving Prior Commission Approval ML20236Q9241998-07-14014 July 1998 Notice of Violation from Insp on 980504-0618.Violation Noted:Operators Were Making Changes to Facility by Defeating Various Control Room Annunciators W/O Performing Written Safety Analysis Rept IR 05000341/19980081998-07-14014 July 1998 Insp Rept 50-341/98-08 on 980504-0618.Violations Noted.Major Areas Inspected:Aspects of Licensee Operations,Engineering, Maint & Plant Support IR 05000341/19980101998-06-29029 June 1998 Insp Rept 50-341/98-10 on 980608-12.No Violations Noted. Major Areas Inspected:Plant Support & Evaluation of Licensee Performance During Station Biennial Exercise of Emergency Plan IR 05000341/19983011998-06-29029 June 1998 NRC Operator Licensing Exam Rept 50-341/98-301OL(including Completed & Graded Tests) for Tests Administered on 980406- 0520.Six Applicants Were Administered Exam,Two Failed Written Exam,Two Failed Operating Exam & One Failed Both IR 05000341/19980111998-06-25025 June 1998 Insp Rept 50-341/98-11 on 980608-12.No Violations Noted. Major Areas Inspected:Radiological Controls for Spent Fuel Pool Clean Out Project IR 05000341/19980091998-06-0404 June 1998 Insp Rept 50-341/98-09 on 980511-15.No Violations Noted. Major Areas Inspected:Aspects of Licensee Performance Re Physical Security for Facility IR 05000341/19980061998-06-0303 June 1998 Insp Rept 50-341/98-06 on 980317-0427.No Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000341/19980031998-05-11011 May 1998 Insp Rept 50-341/98-03 on 971221-980316.Violations Noted. Major Areas Inspected:Aspects of Licensee Operations, Engineering,Maint & Plant Support ML20247D4511998-05-0606 May 1998 Insp Rept 50-341/98-07 on 980406-09.Violations Noted.Major Areas Inspected:Plant Support ML20247D4371998-05-0606 May 1998 Notice of Violation from Insp on 980406-09.Violation Noted: on 980120,two Mechanical Maint Staff Entered North Reactor Water Cleanup Room,Locked High Radiation Area,W/O Stay Time Tracking & Deviation Not Authorized by Radiation Protection IR 05000016/19980061998-04-21021 April 1998 Insp Rept 50-016/98-06 on 980324-26.No Violations Noted. Major Areas Inspected:Licensee Mgt & Control,Decommissioning Support Activities & Radiological Safety ML20216E7901998-04-10010 April 1998 Insp Rept 50-341/98-05 on 980320-0406.Violations Noted: Failure to Demonstrate Reactor Protection Sys Trip Function Units & Isolation Actuation Trip Units within Response Time Limit of at Least Once Per 18 Months IR 05000341/19980041998-03-31031 March 1998 Insp Rept 50-341/98-04 on 971113-980226.Violations Noted. Major Areas Inspected:Operations,Engineering & Plant Support ML20217K2531998-03-31031 March 1998 Notice of Violation from Insp on 971113-980226.Violation Noted:Inspector Identified That on 971115,licensee Removed Multiple Fuel Rods from Irradiated Fuel Bundle YJ7119,up to Four at One Time,During Failed Fuel Insp Activities ML20217K2681998-03-31031 March 1998 Notice of Deviation from Insp on 971113-980226.Deviation Noted:Licensee Stored Irradiated Fuel in West Fuel Preparation Machine in Sf Pool Oversight on 971114-15 & 971115-17,resulting in Only 20.5 Feet Water Above Top of Sf ML20217K2821998-03-31031 March 1998 Insp Rept 50-341/98-04 on 971113-980226.Violations Noted. Major Areas Inspected:Operations,Engineering & Plant Support ML20216B5451998-03-0404 March 1998 Notice of Violation from Insp on 970804-1010.Violation Noted:Analysis Did Not Consider All Scenarios in Providing Bases for Determination That USQ Did Not Exist IR 05000341/19970161998-02-0505 February 1998 Insp Rept 50-341/97-16 on 981108-0105.Noncited Violation Identified.Major Areas Inspected:License Operations,Maint, Engineering & Plant Support PNO-III-98-015, on 980201,reactor Scrammed from 96% Power Following Trip of Main Turbine.Main Turbine Trip Resulted from Main Generator Load Rejection Protective Signal. Investigation Continuing1998-02-0404 February 1998 PNO-III-98-015:on 980201,reactor Scrammed from 96% Power Following Trip of Main Turbine.Main Turbine Trip Resulted from Main Generator Load Rejection Protective Signal. Investigation Continuing IR 05000341/19970171998-01-21021 January 1998 Insp Rept 50-341/97-17 on 971201-05.No Violations Noted. Major Areas Inspected:Conduct of Operations,Operator Training & Qualification & Miscellaneous Operations Issues ML20202H8581998-01-0303 January 1998 Insp Rept 50-341/97-14 on 970923-1107.Violations Noted. Major Areas Inspected:Operations,Engineering,Maintenance & Plant Support 1999-08-06
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Inspection Report - Fermi - 1998019 |
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U.S. NUCLEAR REGULATORY COMMISSION REGIONlli Docket No: 50-341 License No: NPF-43 l Report No: 50-341/98019(DRP) :
l Licensee: Detroit Edison Company Facility: Enrico Fermi, Unit 2 Location: 6400 N. Dixie Hw Newport, MI 48166 l
Dates: November 10,1998 - January 4,1999 i
Inspectors: S. Campbell, Acting Senior Resident inspector
- J. Larizza, Resident inspector l
l Approved by: Anton Vegel, Chief Reactor Projects Branch 6
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EXECUTIVE SUMMARY Enrico Fermi, Unit 2 Fermi Inspection Report 50-341/98019(DRP)
This inspection included aspects of licensee operations, engineering, maintenance, and plant support. The report covers an 8-week period of resident inspectio Operations
- The shutdown to perform repairs on a leaking pressure seal for a feedwater check valve and subsequent startup of the unit was performed in a controlled and deliberate manner (Section 01.1).
e The actions taken by operations personnel in recovering general service water intake level due to ice formation at the station intake from the lake, were performed in a timely, effective manner in accordance with established procedures (Section 01.2).
- The inspectors identified that an operability assessment was not documented for degraded condition related to a containment isolation valve. Though the degraded condition had minor safety consequences, the failure to ensure an adequate documented operability evaluation was considered a vulnerability in ensuring that safety equipment in a degraded condition was thoroughly evaluated. The licensee's quality l assurance staff had previously identified similar problems and corrective actions were in the process of being implemented (Section O4.1).
Maintenance
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e The inspectors concluded that observed surveillance test activities were performed effectively and in accordance with established procedures (Section M1.1).
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- The inspectors concluded that poor communication between operations and maintenance personnel regarding the status of out-of-service equipment resulted in the l operations personnel being unaware that a damper actuator for the reactor building ventilation system was not installed for sixteen days (Section M1.2).
e The licensee determined that an electrician was injured while working on a motor control center due to: 1) less than adequate hazard assessment performance,2) less than adequate electrical safety culture, 3) a deficiency in the interface between the site safety program and the work control program, and 4) that the injured individual failed to adequately self-check his work. The inspectors concluded that the assessment was comprehensive and that the corrective actions to prevent recurrence were acceptable (Section M8.3).
Enaineerina e Corrective actions for safety relief valve performance deficiencies and surveillance test procedure overlap problems were reasonable and comprehensive (Sections E8.1 and E8.2).
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e The inspectors used a radiation detector and independently verified that areas were appropriately posted (Section R1.1). l e The inspectors observed that the central and secondary alarm stations were manned .
with security officers who were knowledgeable of their assigned duties. Equipment in l- these areas appeared to be functioning properly (Section S2.1).
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Ii Report Details l
Sumrnary of Plant Status Unit 2 began this inspection period at 96 percent power. On November 12,1998, operators shut down the unit to support repairs to a leaking pressure seal on a feedwater check valv The plant was subsequently restarted and power was retumed to 96 percent on November 2 .
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1. Operations 01 Conduct of Operations "
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01.1 General Comments (71707) !
Using inspection Procedure 71707, the inspectors conducted frequent reviews of ongoing plant operations. In general, conduct of operations was professional and safety-conscious, in particular, the shutdown to repair a leaking pressure seal on a feedwater check valve and subsequent startup of the unit was performed in a controlled and deliberate manner. Specific events and noteworthy observations are detailed in the sections belo .2 ' General Service Water (GSW) Inspection Scooe (71707)
Inspectors' review of control room logs of December 26,1998, indicated that the control room noted that the GSW intake level had experienced a rapid lowering of level. The lowest level noted on the recorder was 567 feet. Operations personnel dispatched the cutside rounds operator and the turbine building rounds operator to the GSW Pump House to check the position of the GSW de-ice valve. The inspectors reviewed the i
. action statements of Alarm Response Procedures 7D22 (7D23), " General Service H2O Screen A (B) H,0 Level High/ Low," and compared them to the actions taken by operations personne Observations and Findinas Operations personnel shutdown the East Circulating Water Make-Up to minimize level loss in the GSW intake, opened the GSW de-ice valve two additional turns, and the GSW intake level returned to normal. Following the restart of the East Circulating Water Make-Up, the GSW intake level started lowering again. The outside rounds operator operated the GSW trash rake which broke up the ice that had prevented water from entering into the intake. The GSW intake level rapidly recovered to normal without further problems. The inspectors reviewed the Updated Final Safety Analysis Report and confirmed that level did not approach the minimum Updated Final Safety Analysis Report level of 558 feet. The inspectors verified that the operators' actions were consistent with applicable procedure . . - .-
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The actions taken by operations personnel in recovering GSW intake level due to ice formation at the station intake from the lake were performed in a timely and effective manner in accordance with established procedures.
I O2 Operational Status of Facilities and Equipment J
O2.1' Enaineered Safety Feature System Walkdowns (71707)
The inspectors used inspection Procedure 71707 to walk down accessible portions of the following engineered safety feature systems:
e Residual Heat Removal Complex e Divisions 1 and 2 Motor Control Centers (MCC) and Battery Rooms e High Pressure Core injection System Pump Room e . Hydraulic Control Unit Areas Equipment operability, material condition, and housekeeping were acceptable in most cases. Several minor discrepancies were brought to the licensee's attention and were corrected. The inspectors identified no substantive concems as a result of these walkdown ;. 04 Operator Knowledge and Performance 04.1 Documentation of Operability Evaluations on Condition Assessment Resolution Documents (CARDS)
- Inspection' Scope (71707)
On December 21,1998, during a tour of the reactor building, the inspectors noted CARD 98-00488 tag on Reactor Recirculation Sample Line Valve B3100-F020, which is an outboard containment isolation valve. The CARD indicated the valve had a less than !
one drop per minute packing leak while stroke time testing the valve. The inspectors reviewed the CARD to determine if an operability evaluation to justify the acceptability of the packing leak was performe Observations and Findinas The inspectors reviewed documentation related to CARD 98-00488 and noted that an operability evaluation was not documented on the CARD. Since the safety function of the valve was to close and prevent leakage from the containment during an accident, the inspectors questioned control room operators why an operability evaluation for the leaking valve was not documented.' The inspectors were informed that documented operability evaluations were not normally performed for packing leaks on containment isolation valves since packing leaks were considered small compared to the total allowed leakage for containmen L
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l l The inspectors questioned the leak rate test engineer regarding the packing leak on l Valve B3100-F020, and found that the engineer was unaware that the leak existed.
l Consequently, this leakage was not evaluated for incorporation into the total allowed ,
leakage for containment. However, the test engineer stated that during certain postulated accident conditions, the leakage would be smaller since accident pressure (56.5 psig) was postulated to be much lower than operating pressure (1030 psig).
Although this evaluation was not documented in the CARD, the inspectors considered this assessment reasonable to justify operability of the valve and that the safety consequences of the leak was minimal. However, the inspectors were concerned that due to a lack of a documented evaluation of the potential consequences of a degraded condition involving a safety-related component, the full ramifications or potential consequences of the deficiency may not be adequately evaluate l in addition, to the inspectors' concems involving the documentation of operability evaluations for CARDS, the inspectors were informed by licensee staff that similar concerns have been brought up recently by quality assurance personnel as documented in CARD 98-18420, dated October 12,1998. Specifically, CARD 98-18420, documented that operability evaluations were not documented on the following:
- CARD 98-18700, " Inconsistencies in Motor Operated Valve (MOV) Base Design Documents,"
l CARD 98-18067 " Wrong Grease installed in Flex Couplings on Reactor l Recirculation Motor Generator Set B."
CARD 98-18420 noted that justifications of component / system operability were unclear in these examples. As of the end of this inspection period, this CARD remained open pending development of corrective action Following discussions with the inspectors, the licensee subsequently determined that since the safety function of the valve was in question, an operability determination should have been performed. The licensee identified several other examples, in addition to the examples mentioned above, where the operability block on the CARD assessment resolution sheet was inappropriately checked "not applicable." This block was usually reserved for minor, administrative, and/or non-plant issues. The inspectors reviewed Procedures MES27, " Verification of System Operability," and MQA11, " CARD,"
and determined that the threshold for using the "not applicable" block was not define The licensee was considering a revision to the procedures clarifying this fac c. Conclusions The inspectors identified that an operability assessment was not documented for a degraded condition related to a containment isolation valve. Though the degraded condition had minor safety consequences, the failure to ensure an adequate
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documented operability evaluation was considered a vulnerability in ensuring that safety l equipment in a degraded condition was thoroughly evaluated. The licensee's quality assurance staff had previously identified similar weaknesses and corrective actions, and were in the process of being implemente l l
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II. Maintenance l l
M1 Conduct of Maintenance i M1.1 General Comments i Insoection Scope (62707: 61726)
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- 42.302.03 Channel Functional Test of Division 2,4160-Volt Bus 65E, l
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Undervoltage Circuits
Operability Test i Observations and Findinas j These surveillance activities were properly conducted using current revisions to procedures. At the end of the EDG 14 test, the operators involved in the test requested
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l that previously initiated Work Request (WR) 000Z984694, related to replacing an l l obsolete EDG 14 generator end bearing temperature switch, be implemented before the j next scheduled surveillance. In addition, they requested that Air Receiver Outlet l Valve R3000F043D previously initiated WR 000Z984155, related to a bad valve stem !
bushing that caused difficulty in operating the valve, be worked before the next i scheduled surveillance. The inspectors will monitor resolution to these WRs. The '
t maintenance and operations personnel were proactive in identifying the need to
[ increase the priority of previous work request . Conclusions l The inspectors concluded that observed surveillance test activities were performed l effectively and in accordance with established procedures.
l M1.2 Poor Communication of the Status of Out-of-Service Eauipment Inspection Scope (62707.61726)
On December 2,1998, while performing surveillance test procedure 24.404.02,
" Division 1 Standby Gas Treatment System Filter and Secondary Containment Isolation Damper Operability Test," the reactor building pressure unexpectedly increase Subsequent investigation revealed that the cause of the pressure increase was attributed to the failure of center modulating inlet damper to open while restarting the Reactor Building Heating, Ventilation and Air Conditioning System (RBHVAC). The RBHVAC is a system not required by Technical Specifications (TSs). The inspectors l
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followed up on the cause of this failure and the circumstances surrounding the communication of the status of this out-of-service equipmen Observations and Findinos During the licensee's investigation of the failure of the center damper to open, they discovered that the actuator for the center exhaust fan modulating inlet damper was missing. A search for the actuator ensued and it was subsequently discovered in the Instrument and Control (l&C) shop, where it was in the process of being rebuilt in accordance with preventive maintenance (PM) procedures. Maintenance on the actuator was completed and it was successfully reinstalled on the damper and the RBHVAC system was tested satisfactoril Operations personnel performed an investigation of the issue and discovered that I &C personnel requested that PM be performed on the actuator on November 16. While planning the activity, operations personnel estimated that the work activity could be completed within one shift and, therefore, a tag-out was not required as allowed by the tag-out procedure. However, after l&C personnel removed the actuator, they realized that the work would take longer than one-shift. Operations personnel were not notified of the delay in the work activity and since no tag-out existed, a record of this work activity was not communicated to the subsequent operating shift A CARD was initiated to document the problem occurrence and to track corrective actions. Preliminary corrective actions included reemphasizing communicating the status of equipment out-of-service and enhancing equipment configuration contro Conclusions !
The inspectors concluded that poor communication between operations and ,
maintenance personnel regarding the status of out-of-service equipment resulted in the I operations personnel being unaware that a damper actuator for the reactor building !
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ventilation system was not installed for 16 day M2 Maintenance and Material Condition of Facilities and Equipment M2.1 Thermometers Discovered in Division 1 Battery Cells Insoection Scoce (62707)
l On December 23,1998, during a tour of the Division 1 battery room, the inspectors discovered a broken thermometer in Ceil 14 and an intact thermometer in Cell 7. The inspectors reviewed the impact the thermometers had on battery operabilit Observations and Findinos The licensee identified that the thermometers had been in the cells since the batteries were installed in 1984 and attempts to remove them were unsuccessful. An evaluation documented in Potential Design Change 1288, noted that the thermometers were
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' of the Division 1 battery is scheduled for the next refueling outage (RFO). !
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The inspectors concluded that the evaluation performed by the licensee was acceptable to justify operability of the battery cells with the thermometers presen M8 Miscellaneous Maintenance issues (92902) -
M8.1 (Closed) Licensee Event Report 50-341/96017-04: Failure of safety relief valves (SRVs)
to open within TS allowed tolerance. This involved the licensee's discovery that 11 of
! the 15 pilot valves inside the SRVs would not have lifted within the TS 1 percent
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allowable tolerance.
I l Technical Specification 3.4.2.1, requires that for the safety valve function, at least 11 of l the following SRVs shall be operable with the specified code safety valve function lift setting during Operational Conditions 1,2 and 3:
-e 5 safety / relief valves at 1135 psig i 1 percent e 5 safety / relief valves at 1145 psig i 1 percent e 5 safety / relief valves at 1155 psig ! 1 percent Contrary to the above,11 of the 15 pilot valves did not lift within the TS required 1 percent allowable tolerance.
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Corrective actions included the request for a License Amendment to modify the SRV setpoint tolerance criteria from 11 percent to 13 percent, a written justification for i operating with the installed SRV pilot assemblies for the duration of Operating Cycle 6, and the installation of platinum ion beam bombarded discs during RFO 6 to prevent l oxide bonding of the pilot valve disc and seat. The licensee also committed to follow ;
industry developments related to the improved operability of SRV setpoint performanc l The inspectors verified that these actions were complete l This licensee's identification and corrective actions of this violation is being treated as a non-cited violation (NCV), consistent with Section Vll.B.1 of the NRC Enforcement
! Policy (NCV 50-341/98019-01(DRP)).
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. This involved the licensee's identification that surveillance testing for certain portions of !
> the EDG output breaker and 480-Volt MCC load sequencer logic circuitry was inadequate. This was attributed to a deficient procedure, in that not all attributes of the associated logic circuits were fully verified by the procedur !
Technical Specification 6.8.1. d., requires written procedures shall be established, j implemented and maintained for surveillance and test activities of safety-related
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e Procedures 24 302.02(04)(05)(06), " Logic System Functional Test of !
Division 1(2)(1)(2) 4160-Volt Emergency Bus 64B(65E)(64C)(65F) and 11 AE(13EC)(12EB)(14ED) Undervoltage Circuits," used to test the 4160-Volt .
system logic, were inadequate in that the procedures did not instruct positive !
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verification that the EDG output breaker re-close permissive logic circuitry. This is an example of a violatio l e Work Requests 000Z95609, 2, 3, and 4, which were used to test the EDG output logic, were inadequate in that the WRs did not direct positive verification that the 480-Volt MCC automatically connected loads are energized through the load sequencer after the EDG starts. This is a second example of a violatio Corrective actions included: a commitment to complete the remainder of the testing to )
satisfy surveillance requirements before startup from the subsequent plant outage; to {
revise the applicable surveillance test procedures for each 480-Volt emergency bus and undervoltage circuits; and, to include positive verification that the EDG output breaker re-close permissive logic circuitry was initiated via the load shed feature. In addition, existing procedures were to be revised, or new procedures were to be developed, to ensure positive verification that after the EDG starts, the 480-Volt MCC automatically connected loads were energized through the load sequencer. The inspectors verified that these actions had been complete )
l This non-repetitive, licensee identified and corrected violation, is being treated as an NCV, consistent with Section Vll.B.1 of the NRC Enforcement Policy (NCV 50-341/98019-02 (DRP)).
M8.3 Followuo on Electrician Severely iniured while Performina PM Inspection Report 50-341/98015, dated December 7,1998, documented that a Detroit Edison electrician journeyman was injured while performing a PM activity on MCC 72 The inspectors followed up on the licensee's findings regarding the circumstances surrounding this even The summary of the root cause of the incident indicated that the licensee's hazard assessment performance was less than adequate, the electrical safety culture was less than adequate, the program to program interface between the site safety program and the work control program was deficient and that the injured individual failed to adequately self-check his wor The corrective actions to prevent recurrence being implemented include e changing procedures to incorporate lessons learned, .
.e conducting electrical safety training for maintenance and operations personnel, ;
e developing in-processing training for non-licensee electricians, e reinforcing the expectations for peer checking, e reviewing the provision for properly using insulated tools,
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e reviewing maintenance work instructions to identify and eliminate common l
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e and the forming resolution subcommittees to develop proper interfaces between work control process and safety progra In addition, the licensee plans to establish an assessment review committee as part of
- the work control process to review maintenance activities that may pose serious ,
l hazards. The licensee expects to have all the above actions completed by middle '
of 1999. The inspectors concluded that the licensee's corrective actions were appropriate and reasonable to prevent recurrenc . Enaineerina E8 Miscellaneous Engineering issues (92902)
E (Closed) Violation 50-341/95005-04: Failure to follow requirements delineated in Procedure NPP-MA-01, Revision 15, " Work Control." The requirements for controlling work were not followed while implementing WR 000Z591519 to monitor reactor wide range inputs and outputs during turbine trips. Corrective action included communicating to site personnel the importance of procedure adherence via staff meetings and the plant weekly newsletter. Further, work control supervision defined these expectations to work planners. The inspectors verified these corrective actions were complete E8.2 (Closed) Follow-Up Item 50-341/95010-01: For 21 direct current MOVs, the test capability under degraded voltage conditions was in question when using the standard limitorque capability equation. Specifically, the licensee's verification methods had not been validated through testing or through a peer review process recommended by industry guidelines such as the Institute of Electrical and Electronics Engineers 129 The licensee reevaluated the direct current MOVs using standard industry methods, resulting in seven valves being identified as having an insufficient capability to trip the torque switch under degraded voltage conditions. Fermi personnel performed an operability justification on all seven valves and committed to retest the seven MOVs prior to or during the RFO 5, with action to be completed by November 30,1996. The inspectors verified that these actions were completed .
[y, Plant Support Radiological Protection and Chemistry Controls R Independent Verification of Radiation Doses rates in the Reactor and Turbine Buildinas The inspectors conducted routine tours of the reactor and the turbine buildings using a portable radiation detector to determine if radiation postings reflected the dose rates in
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. . Status of Security Facilities S2.1 Tours of the Central and Secondarv Alarm Station The inspectors toured the central and secondary alarm stations and questioned the security officers on security procedures used at the plant and security equipment used in these areas. The inspectors found that the security officers were knowledgeable of their assigned duties and that security equipment appeared to be functioning properl V. Manaaement Meetinas X1 Exit Meeting Summary The inspectors presented the inspection results to members of licensee management at l
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the conclusion of the inspection on January 4,1998. The licensee acknowledged the findings presented. The inspectors asked the licensee whether any materials examined during the inspection should be considered proprietary. No proprietary information was ;
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i PARTIAL LIST OF PERSONS CONTACTED
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P. Fessler, Assistant Vice-President, Operations ,
W. O'Connor, Assistant Vice-President, Nuclear Assessment .
T. Bergner, Director, Organization Development i K. Howard, Director, Plant Support Engineering :
J. Moyers; Director, Nuclear Quality Assurance .
N. Peterson, Director, Nuclear Licensing l
A. Kowalczuk, Manager, Nuclear Support l
J. Plona, Manager, Technical l R. Gaston, Supervisor, Compliance' l R. Russell, Supervisor, Simulator & Training Support !
S. Stasek, Supervisor, independent Safety Engineering Group ?
W. Tucker, Supervisor, Nuclear Fuels and Reactor Engineering Group P. Lynch, Nuclear Shift Supervisor, Operations :
E. Meyer, Nuclear Shift Supervisor, Operations i
- S. Booker, Superintendent, Maintenance !
R. Eberhardt, Superintendent, Outage Management E. Kokosky, Superintendent, Radiation Protection ;
K. Hlavaty, Assistant Superintendent, Operations ;
K. Harsley, Engineer, Nuclear Licensing N S. Campbell, Acting Senior Resident inspector J. Larizza, Resident inspector l
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INSPECTION PROCEDURES USED IP 61726: Surveillance Observations IP 62707: Maintenance Observation IP 71707: Plant Operations IP 92902: Followup - Maintenance ITEMS OPENED, CLOSED, AND DISCUSSED Ooened 50-341/98019-01 NCV Failure of the SRVs to open within TS allowed tolerances 50-341/98019-02 NCV Inadequate procedure to test EDG logic Closed 50-341/98019-01 NCV Failure of the SRVs to open within TS allowed tolerances 50-341/98019-02 NCV inadequate procedure to test EDG logic 50-341/96017-04 LER Failure of the SRVs to open within TS allowed tolerances 50-341/95005-04 VIO Failure to follow requirements in Procedure NPP-MA-01, Rev.15 50-341/95007-00 LER Failure to meet TS surveillance requirements for EDG logic 50-341/95010-01 IFl Test capability under degraded voltage for 21 MOVs in question Discussed None
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LIST OF ACRONYMS USED !
CARD Condition Assessment Resolution Document i EDG Emergency Diesel Generator l GSW General Service Water l&C Instrument and Control i LER Licensee Event Report
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MCC Motor Control Center j MOV Motor Operated Valves i NCV Non-Cited Violation
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PM Preventive Maintenance RBHVAC Reactor Building Heating Ventilation and Air Conditioning RFO Refueling Outage SRV- Safety Relief Valve TS Technical Specification
~WR Work Request l
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