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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: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:UTILITY
MONTHYEARIR 05000341/19900151990-10-26026 October 1990 Insp Rept 50-341/90-15 on 901009-12.No Violations or Addl Open Items Noted.Major Areas Inspected:Pumps & Valves IR 05000344/19900201990-10-12012 October 1990 Revised Section 1, Persons Contacted, to Insp Rept 50-344/90-20 IR 05000341/19900121990-09-13013 September 1990 Partially Withheld Physical Security Insp Rept 50-341/90-12 on 900827-31 (Ref 10CFR73.21).No Violations Noted.Major Areas Inspected:Alarm Stations & Communications,Power Supply & Security Training & Qualification IR 05000341/19900111990-09-0707 September 1990 Insp Rept 50-341/90-11 on 900625-0824,No Violations Noted. Major Areas Inspected:Action on Previous Insp Findings, Operational Safety,Maint,Surveillance,Followup of Events, LER Followup,Medical Drill Observation & Regional Requests IR 05000341/19900091990-07-25025 July 1990 Insp Rept 50-341/90-09 on 900514-0706.Violations Noted,But Not Cited.Major Areas Inspected:Action on Previous Insp Findings,Operational Safety,Maint,Surveillance,Followup of Events,Ler Followup,Bulletin & Info Notice Followup IR 05000341/19900071990-06-27027 June 1990 Insp Rept 50-341/90-07 on 900331-0525.Violations Noted.Major Areas Inspected:Action on Previous Insp Findings,Operational Safety,Maint,Surveillance,Followup of Events,Ler & Review of Maint on East Mainstream Bypass Valve & Reactor Scram IR 05000341/19892001989-09-28028 September 1989 SSOMI Rept 50-341/89-200 on 890717-21 & 0731-0804.Weaknesses Identified.Major Areas Inspected:Detailed Design & Engineering Work Products Required to Support Mods Planned for First Refueling Outage IR 05000341/19890211989-09-27027 September 1989 Insp Rept 50-341/89-21 on 890717-0905.No Violations Noted. Major Areas Inspected:Operational Safety,Maint, Surveillances,Followup of Events,Ler Followup,Assembly/ Accountability,& Management Meetings IR 05000341/19890231989-09-25025 September 1989 Insp Rept 50-341/89-23 on 890818-22 & 0901-06.No Violations Noted.Major Areas Inspected:Radwaste Transportation & Chemistry Programs,Including Organization & Mgt Controls, Gaseous & Solid Radwaste,Shipping & QC Programs IR 05000341/19890201989-08-23023 August 1989 Insp Rept 50-341/89-20 on 890626-30 & 0720.Deviation Noted. Major Areas inspected:post-fire Safe Shutdown Capability Configuration Mgt Program & Fire Protection Program IR 05000341/19890181989-08-14014 August 1989 Insp Rept 50-341/89-18 on 890606-0724.No Violations Noted. Major Areas Inspected:Followup of Events,Operational Safety, Maint,Surveillance,Ler Followup,Allegation Followup,Det Review,Preparations for Refueling & Mgt Meetings IR 05000341/19890161989-07-19019 July 1989 Insp Rept 50-341/89-16 on 890531-0602 & 26-31.No Violations Noted.Major Areas inspected:self-initiated SSFI of HPCI Sys. Present Design Control Measures Showed Significant Improvement IR 05000341/19890121989-07-12012 July 1989 Insp Rept 50-341/89-12 on 890225-0623.No Violations Noted. Major Areas Inspected:Allegations Pertaining to Security Operations at Facility IR 05000341/19890111989-07-0707 July 1989 Insp Rept 50-341/89-11 on 890411-0605.Violations Noted. Major Areas Inspected:Action on Previous Insp Findings, Operational Safety,Maint,Surveillance,Followup of Events, LER Followup & NUREG-0737 Action Items IR 05000016/19890011989-06-27027 June 1989 Insp Repts 50-016/89-01 & 50-341/89-14 on 890522-26.No Violations or Deviations Noted.Major Areas Inspected: Radiation Protection Program at Unit 2 During Operation, Including Training & Qualifications IR 05000341/19890191989-06-23023 June 1989 Insp Rept 50-341/89-19 on 890613-15.No Violations,Deviations or Deficiencies Noted.Exercise Weakness Noted.Major Areas Inspected:Annual Emergency Preparedness Exercise IR 05000341/19890131989-06-0909 June 1989 Insp Rept 50-341/89-13 on 890508-12.No Violations or Deviations Noted.Major Areas Inspected:Licensee Actions to Correct Deficiencies Identified by NRC Diagnostic Evaluation Team Re Training & Qualification Effectiveness IR 05000341/19890151989-05-31031 May 1989 Insp Rept 50-341/89-15 on 890515-19.Violation Noted.Major Areas Inspected:Allegation Re Operation of Facility ML20247A6941989-05-15015 May 1989 Safety Insp Rept 50-341/89-06 on 890203-0412.Violations Noted Re Failure to Properly Design Railcar Door Seals for Flood Protection & Containment Integrity.Major Areas Inspected:Reactor Bldg Railcar Door Designs IR 05000341/19890101989-05-10010 May 1989 Partially Withheld Insp Rept 50-341/89-10 on 890417-21 & 24- 27 (Ref 10CFR73.21 & 2.790).Violations Noted.Major Areas Inspected:Mgt Support,Alarm Stations & Communications, Testing & Maint & Training & Qualification IR 05000341/19890071989-04-28028 April 1989 Page 7 to Special Safety Insp Rept 50-341/89-07 ML20245H7491989-04-17017 April 1989 Insp Rept 50-341/89-07 on 890118-0323.Violations Noted. Major Areas Inspected:Followup of 890118 Event Where HPCI Div II Steam Line Flow Differential Pressure Transmitter Was Found Calibr to Value Greater than Tech Spec Limit IR 05000341/19880331989-04-0404 April 1989 Insp Rept 50-341/88-33 on 881212-890323.Violations Noted. Major Areas Inspected:Licensee Actions on Previous Insp Findings & Review of Allegations Re Plant Operation IR 05000341/19890091989-03-27027 March 1989 Insp Rept 50-341/89-09 on 890306-10.No Violations Noted. Major Areas Inspected:Plant Chemistry & Radiation Protection Organization,Mgt Controls,Qa,Confirmatory Measurements for in-plant Radiochemical Analysis,Audits & Environ Monitoring IR 05000341/19890021989-03-0303 March 1989 Insp Rept 50-341/89-02 on 890101-0217.Violations Noted.Major Areas Inspected:Action on Previous Insp Findings,Operational Safety,Maint,Surveillance,Followup of Events,Ler Followup & Regional Request IR 05000341/19890051989-02-16016 February 1989 Enforcement Conference Rept 50-341/89-05 on 890208.Major Areas discussed:10CFR50,App B Violations Re Failure to Implement Corrective Action for Info Notice 87-12 & Failure to Lubricate Train B Breaker Per Applicable Procedures IR 05000341/19880341988-12-0505 December 1988 Enforcement Conference Rept 50-341/88-34 on 881118.Major Areas Discussed:Apparent Violations to 10CFR50,App B Identified & Info Pertinent to Cause,Extent,Treatment & Corrective Action to Prevent Recurrence of Problems IR 05000341/19880291988-12-0505 December 1988 Insp Rept 50-341/88-29 on 881018-20,1031-1103 & 09.No Violations or Deviations Identified.Major Areas Inspected: Licensee Compliance W/Atws rule,10CFR50.62 ML20206L5651988-11-23023 November 1988 Insp Rept 50-341/88-08 on 880308-0920.Violations Noted.Major Areas Inspected:Circumstances Re Licensee Actions in Response to Matl Control Allegations Reported to NRC in Jan & Feb 1988 IR 05000341/19880251988-11-0808 November 1988 Insp Rept 50-341/88-25 on 880906-1006.Apparent Violations Noted.Major Areas Inspected:Failure of Recirculation Pump B Discharge Valve to Close on 880820 & 28 & Issuance of Confirmatory Action Ltr CAL-RIII-88-24 IR 05000341/19880281988-11-0808 November 1988 Partially Withheld Safeguards Insp Rept 50-341/88-28 on 881003-14 (Ref 10CFR73.21).Violation Noted.Major Areas Inspected:Mgt Support,Security Program,Plans,Audits, Protected & Vital Area Barriers,Packages & Vehicles ML20204K1171988-10-12012 October 1988 Insp Rept 50-341/88-21 on 880716-0831.Violations Noted. Major Areas Inspected:Action on Previous Insp Findings, Operational Safety,Maint,Surveillance,Followup of Events, LER Followup,Personnel Qualifications & Regional Requests IR 05000341/19880201988-08-26026 August 1988 Insp Rept 50-341/88-20 on 880705-14.No Violations Noted. Major Areas Inspected:Licensee Emergency Operating Procedures,Operator Training & Plant Sys to Accomplish Listed Objectives for NRC Temporary Instruction 2515/92 IR 05000341/19880191988-08-15015 August 1988 Insp Rept 50-341/88-19 on 880531-0715.No Violations Noted. Major Areas Inspected:Followup of Events,Operational Safety, Maint,Surveillance,Ler Followup,Startup Test Observation, Generic Ltr Review,Rept Review & Mgt Meetings IR 05000341/19880121988-07-19019 July 1988 Insp Rept 50-341/88-12 on 880401-0527.Violations Noted.Major Areas Inspected:Action on Previous Insp Findings,Operational Safety,Maint,Surveillance,Ler Followup,Mgt Meetings,Tmi Action Item Followup & Operation Safety Team Insp Followup IR 05000341/19880181988-06-24024 June 1988 Safety Insp Rept 50-341/88-18 on 880516-20 & 0606-10. Violations Noted.Major Areas Inspected:Msiv Open/Close Manual Relay Logic,Surveillance Program Review,App R - High Impedence Fault & Deviation Rept Review IR 05000341/19880161988-06-0606 June 1988 Insp Rept 50-341/88-16 on 880517-20.No Violations or Deviations Noted.Major Areas Inspected:Annual Util Emergency Preparedness Exercise Involving Observations by Three NRC Representatives of Functions & Locations During Exercise IR 05000341/19880061988-05-26026 May 1988 Insp Rept 50-341/88-06 on 880206-0331.Violations Noted. Major Areas Inspected:Operational Safety Verification,Maint, Surveillance,Ler Followup,Safety evaluation,NUREG-0737 Actions,Followup of Events & Startup Test Preparation IR 05000341/19880151988-05-24024 May 1988 Insp Rept 50-341/88-15 on 880427-29.No Violations or Deviations Noted.Major Areas Inspected:Maint Activities Conducted at End of Planned Local Leak Rate Test Outage IR 05000341/19880141988-05-12012 May 1988 Insp Rept 50-341/88-14 on 880117-0428.Violation Noted.Major Areas Inspected:Circumstances & Licensee Actions Surrounding Failure of Noninterruptible Control Air Compressor on 880114 IR 05000341/19880071988-05-11011 May 1988 Revised Page 7 to Insp Rept 50-341/88-07,correcting Errors & to Assure Clearer Understanding of NRC Concerns ML20154E6481988-05-0505 May 1988 Insp Rept 50-341/87-48 on 871018-880331.Violations Noted. Major Areas Inspected:Events Surrounding Failure of Licensed Operators to Comply W/Tech Spec Action Requirements Associated W/Reactor Protection Sys Instrument Channel ML20151X8461988-04-21021 April 1988 Insp Rept 50-341/88-07 on 880307-25.Violation & Deviation Noted.Major Areas Inspected:Maint Activities & Licensee Action on Previous Inspector Identified Problems IR 05000341/19880131988-04-20020 April 1988 Enforcement Conference Rept 50-341/88-13 on 880413.Major Areas Discussed:Review & Discussion of Enforcement Options Re Four Potential Violations of Licensee Security Plan IR 05000341/19880111988-04-15015 April 1988 Insp Rept 50-341/88-11 on 880328-30.No Violations or Deviations Noted.Major Areas Inspected:Activities Re Main Steam Isolation Valve Spring Failures & IE Bulletin 85-003 Concerning motor-operated Valve Switch Settings IR 05000341/19880101988-04-12012 April 1988 Partially Withheld Insp Rept 50-341/88-10 on 880310-24 (Ref 10CFR73.21).Violation Noted.Major Areas Inspected: Security Program Audits,Records & Repts,Testing & Maint, Locks,Keys & Combinations & Vital Area Barriers IR 05000341/19880021988-03-30030 March 1988 Partially Withheld Allegation Review & Physical Security Insp Rept 50-341/88-02 (Ref 10CFR73.21(c)(2)).No Violations Noted.Major Areas Inspected:Security Plan & Implementing Procedures,Mgt Effectiveness & Records & Repts IR 05000341/19880051988-02-23023 February 1988 Insp Rept 50-341/88-05 on 880202-05.No Violations Noted. Major Areas Inspected:Onsite Followup of Events at Operating Reactors,Onsite Followup of Written Repts & non-license Training IR 05000341/19870411988-01-12012 January 1988 Insp Rept 50-341/87-41 on 870824-1228.No Violations Noted. Major Areas Inspected:Inadequate Controls for Drug Test Urine Samples,Excessive Alcohol Use & Drug Use at Offsite Locations & Personnel Under Influence of Drugs or Alcohol IR 05000341/19870501988-01-0606 January 1988 Insp Rept 50-341/87-50 on 871207-11.Violation Noted.Major Areas Inspected:Radiation Protection Activities,Including Organization & Mgt Control,Training & Qualification,Exposure Control,Control of Radioactive Matls & Contamination 1990-09-07
[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
[Table view] |
See also: IR 05000341/1985040
Text
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U.S. NL' CLEAR REGULATORY C0m11SSION
REGION III l
l
Report No. 50-341/85040(DRP)
Docket No. 50-341 License No. NPF-43
.
Licensee: Detroit Edison Company ;
2000 Second Avenue !
Detroit, MI 48226 i
facility Name: Femi 2
Inspection At: Femi Site, Newport, MI
Inspection Conducted: July 1 through October 15, 1985 i
'
Management Meetings At: Glen Ellyn, Illinois on July 23
i and September 10, 1985
Inspectors: P. M. Byron
] M. E. Parker
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D. C. Jones i
! I
i dG LO
Approved By: )G. C. Wright, Chief
Projects Section 2C;
/lf/'/ff[
Date !
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Inspection Summary
I
Inspection on July 1 through October 15, 1985, and Management Meetings on i
July 23 and September 10, 1985 (Report No. 50-341/85040(DRP)) !
Areas Inspected: Special, unannounced inspection by resident inspectors of
activities surrounding the out-of-sequence rod pull, the control room HVAC,
the RCIC/ core spray room cooler, the cooling tower bypass valve, the hydrogen :
recombiner and the breach of primary containment integrity. The inspection ,
involved a total of 246 inspector-hours onsite by three inspectors including '
77 hours8.912037e-4 days <br />0.0214 hours <br />1.273148e-4 weeks <br />2.92985e-5 months <br /> onsite during off-shifts. The Management Meetings involved a total of
153 hours0.00177 days <br />0.0425 hours <br />2.529762e-4 weeks <br />5.82165e-5 months <br /> by 26 NRC personnel.
Results: Twenty-sixviblations(includingexamples)wereidentified(seven- ,
Limiting Condition for Operations and nineteen - Procedural). j
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i DETAILS
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1. Attendees
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a. Persons Attending Management Meeting on July 23, 1985
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Deco
C. M. Heidel President
W. H. Jens. Vice-President, Nuclear Operations
R. S. Lenart, Assistant Manager, Nuclear Production
A. Wegele, Compliance Engineer
D. A. Aniol. Nuclear Shift Supervisor
G. R. Overbeck, Superintendent, Operations
P. A. Marquardt, General Attorney
L. C. Lessor, Advisor, Management Analysis Co.
Public
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B. Campball, Reporter, Detroit Free Press
NRC HQ's
E. Jordon, Director, Division of EP
B. J. Youngblood, NRR Licensing Chief, Branch No. 1
M. D. Lynch, NRR Licensing Project Manager
NRC RI!!
J. G. Keppler, Regional Administrator
C. J. Paperiello, Director, Division of Reactor Safety
E. Greenman, Deputy Director, Division of Reactor Projects
l N. J. Chrissotimos, Chief, Branch 2. DRP
L. A. Reyes, Chief, Operations Branch, DRS
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l G. C. Wright, Chief. Section 2C, DRP
P. M. Byron, SRI Fermi 2
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T. E. Lang, Operator Licensing
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B. Stapleton, Enforcement Specialist
W. H. Schultz, Enforcement Coordinator
S. Stasek, Project Inspector, Femi
R. B. Landsman, Project Manager, Section 2C, DRP
5. G. DuPont, Reactor Inspector
R. D. Lanksbury, Reactor Inspector
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b. Persons Attending Management Meeting on September 10, 1985
DECO
C. M. Heidel, President
W. H. Jens, Vice-President, Nuclear Operations
R. S. Lenart Assistant Manager, Nuclear Production
T. Randazzo Director, Regulatory Affairs
E. P. Griffing Assistant Manager, Regulatory Compliance
L. C. Lessor, Advisor, Management Analysis Co.
Wolverine Power Supply
C. Borr, Member, Services Coordinator
J. Gore, Consultant
Public
T. Lam, Reporter, Ann Arbor News
S. Benkelman, Reporter, The Detroit News
B. Campball, Reporter, Detroit Free Press
M. Johnston, Member, Safe Energy Coalition of Michigan
J. Puntennery, Director, Safe Energy Coalition of Michigan
F. Kuron, Monroe County Commissioner
J. Eckert. Director, Office of Civil Preparedness
NRC HQ's
H. D. Lynch, NRR Licensing Project Manager
L. P. Crocker, NRR Licensing Section Chief, Quality Branch
NRC RIII
J. G. Keppler, Regional Administrator
A. B. Davis, Deputy Regional Administrator
C. E. Norelius Director, Division of Reactor Projects
E. Greenman, Deputy Director, Division of Reactor Projects
G. C. Wright, Chief, Section 2C, DRP
P. H. Byron, SRI, Fermi 2
B. W. Stapleton, Enforcement Specialist
J. Strasma. Public Affairs Officer
R. Lickus, Chief. State of Government Affairs
J. A. Hind. Director, Division of Radiation Safety and Safeguards
W. D. Shafer Branch Chief Emergency Preparedness and Radiological
Protection
R. B. Landsman, Project Manager, Section 2C, DRP
C. H. Weil, Compliance Specialist
T. E. Long Operator Licensing
L. Dimmock, Operator Licensing
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2. Out-of-Sequence Rod Pull
While withdrawing control rods to achieve criticality on July 1, 1985,
the Nuclear Supervising Operator (NS0) pulled eleven control rods in '
Group 3 to position 48 rather than position 04 as required by the control
rod pull sheets.
l
The afternoon shift NSO had started pulling control rods around 10:21 p.m.
! EDT on July 1, 1985, and completed pulling centrol rods through step 37
l at 11:15 p.m. EDT. The night shift NSO started to pull rods at step 38
one minute and eleven seconds later. The night shift NSO had observed
l the off going NSO for a period of time before taking the controls. The
l nightshift NSO utilized a Shift Technical Advisor in Training (STAIT) to
l monitor the Source Range Monitor (SRM) instrumentation to facilitate the
l rod pull rather than perform that function himself. The NSO completed
pulling rods in Group 2 and then commenced pulling rods in Group 3
(step 46). Starting with step 46 and for the next 10 steps the NSO
pulled each control rod to the full out position (48) rather than
position 04 as required by the procedure. The NSO verified by his
initials, on the rod pull sheet, that each of the eleven control rods
was at position 04 when in fact they were at position 48.
While pulling the eleventh control rod in Group 3 (control rod 18-51),
the Short Period Alarm annunciated five times and the pen for the
Channel A SRM recorder failed to ink for about three minutes. When
l the pen started inking again the NSO and STAIT observed that recorder
was reading approximately 5x103 counts per second and increasing. The
- Shif t Reactor Engineer (SRE) had predicted that criticality should occur
'
between steps 150 and 160, when the NSO observed the increasing count
l rata he was only on step 56. The NSO instructed the STAIT to inform the
Nuclear Shif t Supervisor (NSS) of the situation and immediately started
to insert rod 18-51. It took 14 minutes and 41 seconds to insert all
eleven control rods to position 04. Thirty-five (35) seconds later
the NSO continued the startup by pulling rods from step 57 of
the procedure.
During the control rod pulls the NSS and the Nuclear Assistant Shift
Supervisor (NASS) were in the NSS's office. The SRE was behind the panels
and could not observe the rod pulls. The NSO in charge of the control
room was at his desk facing the pan 11s and the Shift Technical Advisor
(STA) and the Shift Operations Advisor (50A) were by the NSO's desk,
Neither the NSO in charge, the SOA, nor the STA were observing the rod
pull nor were they aware of the incident. The STAIT Informed the SRC
of the event who wrote in his log that the reactor may have been
critical.
The NSS reviewed the event with the NSO (at the controls) and the STAIT
and determined that the reactor had not gone critical. lhe NSS then
directed that rod pulling recommence. The NSS apparently did not seek
the advice or counsel of the SRE, the SOA, or the S1A, The SRE also ,
lined out in his log book the reference of the unit being critical.
Neither the NSS nor the NSO logs contained an entry regarding the
4
.
.
out-of-sequence rod pull. The NSS, however, did write a Deviation /
Event Report (DER) (No. NP-85-0334) describing the event and stated that
the reactor had not gone critical.
DER No. NP-85-0334 was reviewed by the licensee's Corrective Action
Review Board (CARB) on July 2,1985, who concurred with the NSS's
determination that the incident was not reportable under either 10 CFR
50.72 or 50.73. It appeared that there was disagreement within the
licensee's organization as to whether or not the reactor had been critical.
The licensee directed that additional engineering review be made. The
licensee informed the Resident Inspector (RI) of the event on July 3,
1985, and stated that the unit had not gone critical but that there was a
question among the staff and that Reactor Engineering was performing a
technical review. The licensee stated that they would get back to the
RI when the determination had been made. The RI informed RIII of his
meeting.
A SRE made the determination on July 4,195 that the reactor had been
critical on July 1, 1985, with a 114 second period and informed his
management of the determination. Several licensee meetingr. were held on
July 5 and 6, 1985 to discuss this event and to initiate an investigation
into its cause.
The next discussion with the NRC resident staff, af ter July 3,1985,
was on July 15, 1985, when the Senior Resident Inspector (SRI)
was asked by licensee management if he was aware of the July 1, 1985
incident and that the reactor had been critical. The SRI was aware of
,
the out-of-sequence rod pull but was not aware that the reactor had
been critical. The SRI informed RIII of the meeting, and the new
information on criticality.
Region !!! Issued a Confirmatory Action Letter (CAL-RI!!-85-10) to the
licensee on July 16, 1985. The CAL detailed the corrective action
the licensee was to take relating to the out-of-sequence rod pull. The
CAL is detailed in Inspection Report 50-341/85043(DRP). The licensee
- made a presentation in Region III on July 23, 1985, regarding their
corrective action program and finu ngs related to the event which is
described in Paragraph 9 of this report. The licensee's presentation
is included as an attachment to their response to the CAL, Deco letter
RC-LG 85-0017 (Jens to Keppler) dated September 5, 1985.
During the inspection and review of the event, nine examples of apparent
violations of Technical Specification requirements were identified and are
as follows:
Technical Specification 6.8.1.a requires that written procedures shall
be estab11shed, implemented, and maintained covering the applicable
procedure recommendations of Appendix A of Regulatory Guide 1.33,
Revision 2, 1978. Appendix A of Regulatory Guide 1.33 lists the
following activities under Administrative procedures:
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- Hot Standby to Minimum Load (Nuclear Startup)
- Authorities and Responsibilities for Safe Operation...
- Equipment Control
- Shift and Relief Turnovers
- Log Entries
Contrary to the above, the licensee failed to adhere to the provisions of
Technical Specification 6.8.1.a covering the startup of the reactor on
July 1, 1985, as indicated below:
a. P0M Procedure 51.000.08, " Control Rod Sequence and Movement
Control," paragraph 3.1.1, requires that rod withdrawals in the
region from 100% Rod Density to 20% Reactor Power must be
performed according to the rod pull sheet. The rod pull sheets
in effect on July 1,1985, required the rods for Group 3 to be
pulled in notch control (00-04, 04-08, etc.). The licensee
pulle<* :leven control rods in Group 3 to the full out position
(48) rather than to the 04 position as required (341/85040-01a).
b. POM Procedure 51.000.08 Paragraph 3.1.4 states, in part, "Following
each rod move the Nuclear Supervising Operator (NS0) shall verify
the control rod was lef t in the proper position indicated and shall
document this verification by initialing the ' Final Position
-
Verified' block of Attachment 1." The NSO verified eleven rods to
be at position 04, by initialinj the pull sheet, when in actuality
they were at position 48(341/85040-01b).
c. POM Procedures 12.000.57, " Nuclear Production Organization" and
21.000.01, "Shif t Operation and Control Room" delineate the
responsibilittee of the NSS to include supervision of all
activities and observation and/or direction of major plant
evolutions to ensure compliance with Technical Specificatiens,
procedures, and regulations. The NSS did not appropriately
discharge his duties on July 1 and 2,1985, in that Me neither
,
,
supervised, observed, nor directed the activities essociated ,
with the control rod pulls (a major plant evaluation) nor was
he in the proximity of the appropriate control panel and
associated nuclear instrumentation (341/85040-01c).
d. POM Procedur 21.000.01, Enclosure 1 Item 12, requires the Nuclear
Assistant Shif t Supervisor (NASS) to provide direct supervision of
shift personnel. The NASS did not provide direct supervision of the
NSP manipulating the controls on July 1 and 2,1985 nor was he in
the proximity of the appropriate control panel and associated
'
nuclear instrumentation (341/85040 01d).
e. P0H Procedure 21.000.01, Enclosure 2, Item 5 requires the NSO
to be responsible for the plant's main control room operation.
The control room NSO was unaware of the out-of-sequence rod
pull and thus was not successfully discharging his duties
(341/85040-01e).
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f. POM Procedure 21.000.01, Enclosure 6, Item 2, requires the Shift
Operations Advisor (SOA) observe actuation of annunciators to ensure
that they are being promptly and properly addressed with actions
taken. Five short period alarms were received in less than four
minutes while pulling rod 18-51 on July 1, 1985. The NSO at the
controls was allowed to continue pulling rods and the SOA did not
discharge his responsibilities by failing to become involved in the
resolution of the short period alarms (341/85040-01f).
g. P0M Procedure 21.000.02, " Operating Logs and Records," Section
4.2.5.8, requires the NSS to record the occurrence of significant
events in the NSS log. The NSS log for July 1 and 2,1985,
contained no entries for the out-of-sequence rod pulls, a
significant event, which occurred between 11:40 and 11:59 p.m.
on July 1,1985(341/85040-01g).
h. POM Procedure 21.000.01, " Shift Operation and Control Room," Section
6.3.8 states, " Reactor Engineering Administrative Procedure No.
51.000.10, ' Reactor Engineering Conduct of Operations,' details the
duties and responsibilities of on-shif t Reactor Engineering personnel."
Procedure 51.000.10 Section 1.0, states, "The purpose of this
procedure is to outline operational interfaces between Reactor
Engineering and Plant Operations and to clarify the overall responsi-
bilities of on-shif t Reactor Engineering personnel." Procedure 51.000.10
does not detail the duties and responsibilities of the on-shift
Reactor Engineer (341/85040-01h).
1. POM Procedure 21.000.01, Section 6.8 addresses shift relief and
Section 6.8.4 specifically addresses the control room nuclear
supervisingoperator(NS0). The procedure defines the required
turnover for the NSO in charge of the control room but does not
define any turnuver requirements for the NSO assigned to duties in
the control room but not in charge of the control room (341/85040-011).
3. Control Room HVAC
On July 11, 1985 PN-21 No. 286934 was issued to inspect the Division !!
Control Room HVAC condensate tray. For personnel protection the Division !!
Control Room HVAC supply fan control switch was placed in the off position
at 8:35 a.m. on July 18, 1985 and the feeder break was opened and red
tagged at 8:50 a.m. The Nuclear Supervising Operator (NS0) entered the
action in his log but did not list the Technical Specification appitcability.
The NSO also entered the action in the Control Room Information System
(CRIS) equipment status file and placed the applicable CRIS dot next to
the switch on the sanel. The NSO also advised the protection leader that
protection had to )e removed by 3:00 ).m. on July 25, 1985, however, the
NSO failed to notify the NSS of the c1ange in equipment status. Neither
the NSS log nor the out-of-specification log contain any entries on the
inoperable Division !! HVAC. The work was completed and the request to
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removeprotectionwasmadeat1:20g.m.onJuly 18, 1985. However, the
package was misfiled in the " active file rather thar, the " protection to
be cleared" file.
The out-of-specification condition went unnoticed for 27 shift turnovers
by the oncoming NSS, NASS, and NS0's even though the switch was marked,
a log entry had been made, and it was entered in the CRIS equipment
status file. It was not until July 27, 1985 that a nightshift NSS
questioned the status of the Division II Control Room HVAC fan and
had the fan returned to service at 5:38 a.m. on July 27, 1985.
During the inspection and review of the event, two apparent violations
of Technical Specification requirements were identified as follows:
l a. Technical Specification 3.7.2.C.1 requires that with the control
center emergency filtration system supply fan inoperable, with the
plant in cold shutdown, the fan be made operable in seven days or
initiate and maintain operation of the system in the recirculation
mode of operation.
Centrary to the above, the licensee failed to place the control
room emergency filtration system in the recirculation mode of
l
operation on July 25, 1985; seven days after the system was
l rendered inoperable on July 18, 1985. This condition existed
l for aroroximately forty-five (45) hours (341/85040-02).
b. Technicsl Specification 6.8.1.a requires that written prac#dures
shall be established, implemented, and maintained covering the
l applicable procedure reconinendations of Appendix A of Regulatory
Guide 1.33 Revision 2, 1978. Appendix A of Regulatory Guide 1.33
'
lists the following activities under Administrative Procedures:
- Authorities and Responsibilities for Safe Operation...
- Equipnent Control
! - Shif t and helief Turnovers
- Log Entries...
Contrary to the above, the licensee failed to adhere to the
provisions of Technical Specification 6.8.1.a as follows:
(1) POM Procedure 21.000.01 "Shif t Operations and Control Room,"
delineates the shift turnover responsibilities of the Nuclear
Shif t Supervisor (NSS) the Nuclear Assistant Shift Supervisor
(NAJS) and the Nuclear Station Operator (NS0). Included in the
responsibilities is a review of past log entries, and a review
of each Combination Operating Panel for off-normal conditions
or the addition of CRIS " dots." The NSS NASS, and NSO all
l failed to adequately perform the required activities as
indicatedbelow(341/85040-03a):
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(a) The Control Center Division II HVAC supply fan switch was
placed in the off position on July 18, 1985, and not
observed to be out of position until July 27, 1985. The
out-of-specification switch position went unobserved for
27 shift turnovers.
(b) The NSO entered the switch position in the equipment
status file and placed a CRIS " dot" by the switch on
July 18, 1985. The CRIS " dot" went unobserved for
27 shift turnovers.
(c) The NS0 had logged placing the Division II Control
Center HVAC supply fan in the off position at 8:35 a.m.
on July 18, 1985. Subsequent reviews of the log either
failed to note the entry or failed to recognize its
significance. (6 NSS turnovers, 15 NASS turnovers,
and 27 NSO turnovers)
(2) P0H Procedure 21.000.01, Section 6.19.1.1 states, in part.
" Evaluate the consequences of removing the system or component
from service considering such items as Technical Specifications
L.initing Condition for Operations which require an action
! statement to be carried out...." The licensee failed to
I evaluate the consequences of removing cornponents from service
in that no acknowledgernent of any Technical Specification
applicability was made in either the NSO log of the Control
Room Information System (CRIS) when the Division !! Control
Center HVAC was removed from service (341/85040-03b).
l 4. RCIC/ Core Spray Room Cooler
The NSS observed whilt. reviewing the combination o)erating panels during
his turnover on July 24, 1985, at 6:30 p.m. that tie control switch for
the Division ! Reactor Core Injection Cooling (RCIC)/ Core Spray Room
Cooler was in the off-reset position, this made both RCIC and Division !
I
core spray inoperable. The NSS who discovered the out-of-position switch
stated that it was in the proper position at 3:30 p.m. on July 23, 1985.
The Itcensee also determined that the Motor Control Center (MCC-728-3A
Position 20) feeding the room cooler was found in the off position.
Subsequent investigation by the licensee did not reveal any reason for
the coolers status nor could any PN-215 be identified which would have
authorized de-energizing the MCC feeder breaker. The room cooler was
returned to service and the licensee documented the incident in
DER NP-85-0390.
Theunitwasinthestartupmodeofoperation(OperationalCondition2)
at the time the room cooler was taken out of service, but was in a
planned shutdown due to the loss of the South Reactor Feed Pump when
the cooler was found out of service. (Reactorpressurehadbeenreduced
to less than 150 psig at 7:30 a.m. on July 24,1985.) RCIC is not
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l required to be operational below 150 psig; however, the High Pressure ;
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CoreInjection(HPCI)hadbeeninoperablesinceJuly 11, 1985 thus for
! approximately sixteen (16) hours the HPCI, RCIC and Division I core
spray systems were all inoperable.
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During the inspection and review of the event, two apparent violations l
l of Technical Specification requirements were identified as follows:
!
!
a. Technical Specification 3.5.1.C.1 requires that during the startup l
l modeofoperation,theHighPressureCoreInjection(HPCI) system
may be inoperable provided that the Core Spray (CS) system, the
Low Pressure Coolant Injection (LPCI) system, the Automatic
Depressurization System (ADS), and the Reactor Core Isolation
Cooling (RCIC)systemareoperable.
Contrary to the above, the licensee failed to ensure that the ;
RCIC and Division ! core spray systems were operable when they i
allowed the RCIC/CS room cooler to be removed from service at j
3:30 p.m. on July 23, 1985 with the HPCI system already inoperable ;
as of 3:00 a.m. on July 11, 1985. This condition existed for
approximately sixteen hours, with the reactor in the Startup
condition (341/85040-04).
b. Technical Specification 6.8.1.a requires that written procedures
shall be established, implemented, and maintained covering the
applicable procedure recomendations of Appendix A of Regulatory
Guide 1.33 Revision 2, 1978. Appendix A of Regulatory Guide 1.33
lists the following activities under Administrative Procedures:
- Authorities and Responsibilities for Safe Operation...
l - Equipment Control
l - Shift and Reitef Turnovers
( - Log Entries...
Contrary to the above the licensee failed to ad (n to the
!
provisions of Technical Specification 6.8.1.a as voilows: i
(1) POM Procedure 12.000.15"PN-21jWorkOrder) Processing,"
Section 7.2.1 states, in part, All work activities at
Fermi 2...sha11 be controlled by a PN-21 and Attachmeet 'A' ,
, to the PN-21." The licensee failed to write a PN-21 to !
de-energize the feeder breaker (NCC-728-3A Position 20) for
the RCIC/ Core Spray room cooler fan on July 23 and 24,1965
(341/8504005a).
(2) POM Procedure 21.000.01, " Shift Operations and Control Room " ,
l delineates the shif t turnover responsibilities of the Nuclear !
l
Shif t Supervisor (NSS) the Nuclear Assistant Shif t Supervisor !
(NASS) and the Nuclear Station Operator (NS0). Included in the !
responsibilities is a review of past log entries, and a review '
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of each Combination Operating Panel for off-normal conditions
or the addition of CRIS " dots." The NSS, NASS, and NSO all
failed to adequately perform the required activities as the
RCIC/ Core Spray room cooler fan switch was in the "off-reset"
l position for approximately 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on July 23 and 24,1985. The
normal position for the switch is in the " Auto" position. The
'
out of position switch went unobserved for two shift turnovers
(341/85040-05b).
(3) P0M Procedure 21.000.01, Section 6.19.1.1 states, in part.
l " Evaluate the consequences of removing the system or component
from service considering such items as Technical Specifications
'
Limiting Condition for Operations which require an action
statement to be carried out...." The licensee failed to
evaluate the consequences of removing components from service
! as he did not take into account the existing inoperability of
l the HPCI system prior to removing the RCIC/ Core Spray room
l cooler from service nor was the action entered into the NSO
log or the CRIS equipment status file (341/85040-05c).
5. Cooling Tower Bypass Valve
On July 26, 1985, while performing surveillance testing on Division I,
l Emergency Diesel Generator (EDG) #11, a Diesel Generator Service Water
l
(DGSW) Low Flow Alarm was received. The alarm indicated a lack of
cooling water for the EDG. The operator verified the low flow and
l
innediately shutdown the EOG. The licensee, upon further investigatibn.
determined that the mechanical draft cooling tower bypass valve
E1150-F603A was closed and de-energized. This valve is required by a
condition of the license to be open and de-energized, or one of the
cooling tower shutoff valves E1150 F604A/F605A is to be open and
de-energized to prevent spurious closure due to hot shorts in the event
of a fire in the plant. The nomal position for this motor operated
va'te is de-energized and open per POM Procedure 23.208, Revision 8.
Thi . is an apparent violation of License Condition 2.C.(9)(d) (341/85010-06).
Invtstigation into the rcason why the bypass valve was out of proper
position, identified that the valve was last manipulated on July 23,
1985, while running the Reactor Heat Removal Service Water (RHR$W)
system. The valve had exhibited a tendency to trip either the thermal
overloads or the torque switches during stroking and an operator had been
required to partially stroke the valve to the desired position as well as
reset the thermal overloads to allow continued stroking from the control
room. It appears that clear instructions were not given to the Reactor
Building Rounds Operator as he was not aware of the necessity of leaving
the Ell 50 F603A valve in the open de energized condition.
The E1.50 F603A valve is located in the discharge flow path to the
coolin$ water reservoir and its closure affects multiple systems. With
the valve closed, flow of Erwrgency Equipment Service Water (EESW),
11
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RHR$W, and DGSW is blocked. Besides affecting the Division I EDG's,
with the bypass valve closed all Division I emergency core cooling
systems were inoperable including the core spray and residual heat
removal systems.
At the time the bypass valve was discovered in the closed position, the
reactor was in cold shutdown, Condition 4, with the reactor temperature
at approximately 130*F and atmospheric pressure. In cold shutdown the
plant is required to have one operable division of ECCS, and one operable
divisionofEDG's(twodiesels). This condition was satisfied, however,
the bypass valve E1150-F603A had been closed since about 1:19 p.m. on
July 23, 1985. On July 23, 1985, theunitwasinCondition2(Startup)
which requires both divisions of ECCS and both divisions of the onsite
electrical power source (EDG's) to be operable. As a result of the
bypass valve being closed, only one division was operable. The failure
to take remedial action with one division of the EDG's inoperable is
an apparent violation of T.S. 3.8.1.1.b (341/85040-07).
On July 23, 1985, the licensee connenced a reactor shutdown at about
1:15 p.m. as a result cf the failure of the South Reactor Feed Pums.
It was fortuitous that the licensee coemenced a recctor shutdown a>out
the same time the cooling tower bypass valve was de-energized in 'le
closed position, as the licensee was by chance co.. plying with the
Limiting Condition for Operation (LCO) action statements in reducing
power and proceeding to cold shutdown. Without this action, the plant
would have been in further violation of technical specifications.
6. Hydrogen Recombiner
On June 20, 1985, the licensee completed maintenance on the Division !!
hydrogen recombiner per Work Order PN-21269327 to replace a leaking
blower seal. The work order stated that post maintenance testing was
required, and identified Plant Operations Manual (POM) Procedures
43.409.01, " Post LOCA Thermal Recombiner System Test," and 24.409.01
" Post LOCA Thermal Recombiner Functional Test." These procedures were
required to demonstrate leak tight integrity and operability,
respectively. The work order was stoned off as completed by the Nuclear !
Shif t Supervisor on June 20,1985, w' thout the leakage test having been
perforned per P0M Procedure 43.409.01. This is an apparent violation of
TechnicalSpecifications(T.S.)6.8.1.aand6.8.4.ainthatthelicensee
failed to follow estabitshed procedures and comply with the leakage
reduction program (341/85040 08). i
On August 26 1985, the licensee initiated a Deviation / Event Report
LNo. I'P-85-0I55) to document the failure to perform the post maintenance
leak rate testing on the Olvision !! hydrogen recombiner. After i
determining the failure to the licensee had sufficient l
wrfom testing}ner
infomation to declare the aydrogen recomb inoperable, as a result j
of exceeding the 30 day LCO limit, and the licensee did not take action
per technical specification 3.0.3. to place the unit in hot shutdown
,
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.
l
within six hours. The licensee proceeded to determine the leakage rate
and on August 28, 1985, declared the Division II hydrogen recombiner
innperable as a result of the initial leakage rate testing. Subsequently
on August 29, 1985, at 2:46 p.m. the licensee determined that the leakage
rate was in excess of the allowable containment leakage. This is an
apparent violation of T.S. 3.6.6.1, and 3.0.3 in that the licensee failed
to comply with the LCO action statements (341/85040-09).
At 6:00 p.m., on August 29, 1985, the licensee cummenced preparations
to proceed to hot shutdown. The hydrcgen recombiner was repaired, leak
tested, and declared operable on August 29, 1985, at 9:00 p.m. The plant
was returned to the startup mode with pressure at 950 psig and 3.8% power
for HPCI and SCRAM time testing at 10:40 p.m.
,
During the time period from June 21 to July 21, 1985, the plant entered
l Operational condition (Startup) on five (5) occasions including initial
criticality (June 21, 1985, June 29, 1985, July 2, 1985, July 6, 1985,
,
and July 10,1985) without both divisions of hydrogen recombiners
l operable. This is an apparent violation of T.S. 3.0.4(341/85040-10).
7. Breach of Primary Containment Integrity
l ThelicenseediscoveredaContainmentMonitoringSystemValve(T50-071A)
! which is a primary containment boundary, in the open position and uncapped
I on September 2, 1985. The valve was shut upon discovery. The Nuclear
l Shif t Supervisor (NSS) was informed of the event on September 4,1985,
l approximately 39 hours4.513889e-4 days <br />0.0108 hours <br />6.448413e-5 weeks <br />1.48395e-5 months <br /> af ter discovery. ADeviation/EventReport(DER)
l (No.NP-85-0469) was written to document the open valve.
Valve T50-071A was installed under Engineering Design Package (EDP)
No. 1970 dated March 25, 1985. The EDP included the installation of four
test connection cutoff valves in the primary containment monitoring
system. Valves T50-068A and B were installed in piping from the bottom
of the torus while valves T50-071A and B were installed in piping from
the top of the torus. PN-21(WorkOrder)No. 814949 was written to
install the "A" valves in Division I and PN-21 No. 814948 was written to
install the "8" valves in Olvision !!. Both PN-21s were signed off as
" Order Completed" on June 20, 1985. It should be noted that neither EDP
1970 nor the four PN-21s associated with it were closed out as of
September 10, 1985.
Doth PN-21s for the primary containment monitoring system required Local
Leak Rate Tests (LLRTs) plus Plant Operations Manual Procedure
24.000.05, " Monthly Continuity Light and Channel Check Test," Section 4
" Precautions and Limitations" to be completed. The NSS signed the
PN-21s as order complete on June 20, 1985. The licensee reviewed EDP
1970 and detemined that the LLRTs for the primary containment monitoring
system modifications had not been performed. DER No. NP-85-471 dated
September 5, 1985, was written to document this discrepancy. The licensee
subsequently performed the missed LLRTs and three of the four LLRTs met
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! procedural criteria. The LLRT for Penetration.X203A.(P0M Procedure
43.401.386) which contains valve T50-071A did not meet the leakage
criteria. Two of the three boundary valves were repaired and the
penetration subsequently met the test criteria,
p During the inspection and review of the event, three apparent violations
,
were identified as follows:
i a. Technical Specification 3.6.1.1 requires that PRIMARY CONTAINMENT
INTEGRITY shall be maintained in Operational Conditions 1, 2,-and 3.
e Without PRIMARY CONTAINMENT INTEGRITY restore PRIMARY CONTAINMENT.
INTEGRITY within one hour or be in at least HOT SHUTDOWN within the
[ next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
,
4 Contrary to the above, the licensee failed to maintain containment
i integrity from June 21 to September 2,1985, in that primary
containmentmonitoringsystemvalve(T50-F071-A)wasintheopen
position and the line downstream of the' valve was uncapped which
4 resulted in an open pathway from the primary containment to the.
L reactor building. Primary containment integrity was required during
l this time frame except for 6.25 days of the interval-(341/85040-11).
! b. Technical Specification 6.8.1.a requires that written procedures
shall be established, implemented, and maintained covering the-
applicable procedure recommendations of Appendix A of-Regulatory-
.
Guide 1.33 Revision 2, 1978. Appendix- A of Regulatory Guide'1.33.
l lists the following activities under Administrative Procedures:
!
(1) Equipment Control
(2) Log Entries...
i Contrary to the above, the licensee failed to adhere to the
1
provisions of Technical Specification 6.8.1.a as follows:
! P0M Procedure 12.000.15, "PN-21 (Work Order) Processing," Revision 11,
August 20, 1985, paragraph 7.3.16 states: "Upon completion of all-
- maintenance, testing, STR or EPC and after_the ' Accepted for Service-
'
By' slot has been signed, the pink copy-of PN-21 is forwarded to the
Nuclear Shift Supervisor who will review the order and sign ' Order
~
i Completed.'" Contrary to the above, the licensee failed to adhere - ' ,
i
to the requirements of POM Procedure 12.000.15. in that Work Order- ,
i PN-21 No. 814945 (covering the addition of leak rate test conriection. '
- valve T50-F071A) was signed " order completed" on June 20, 1985,
- without the post installation leak rate testing being performed as. ;
- specified.onthework-order-(341/85040-12)..
i
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i
. c. 10 CFR 50, Appendix B, Criterion VI,; states, in part,a" Measure. shall: !
- be established to control the issuance of documents, such as *
instructions, procedures,'and drawings,. including changes'thereto,
which prescribe all activities affecting quality. These measures
- shall assure that documents including changes are reviewed for '
adequacy...." '
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POM Procedure' 12.000.64, "EDP1 Implementation Procedure,": Revision 2, ..;
dated March 5, 1985, Section 6.5.1; states, in part, "The responsible !
PSE shall identify the plant documents requiring revision when the - 4
package is prepared."
Contrary to the above, the EDP. Implementation Procedure for EDP'
- No.1970, covering.the installation of the containment sample system . '
!- leak rate test connection valve T50-f CIA, did not. identify.all -
I the plant documents requiring revision in that it did not identify. .l
POM Procedures 24.425.01, " Primary Containment Integrity i
l Verification for Valves Outside Containment," or 47.000.77, " Test *
Vent and Drain (TVD) Cap:and Plug Verification." The failure to :
,
identify these documents resulted in valve T50-F071A (an_d seven-. :
- other valves) not being incorporated into the procedures used to .
- verify containment integrity (341/85040-13). !
8. 'Sumary ];
1 ;
- . .
3
-
Twenty-six -violations (including multiple examples) of NRC requirements j
are identified in this report. The majority of these fall into the
. i
- category of failure to follow procedures._ This represents a-breakdown j
i in the licensee's ability to operate the plant in accordance with. !
prescribed procedures as required by the Technical Specifications. lj
'
The licensee's Operational Assurance (0A) organization has a program !
called. Procedure Compliance Module (PCM) which monitors, on a monthly : !
-
bases, procedural compliance by various organizations. The results'of
~
!
six monthly surveillances (January-June 1985) clearly' revealed that the
- operations section had had problems in following procedures. (Procedural i
- compliance ran from 74% to 100% and there was no trend--the results were -
erratic. The six-month average was 87% with 99% compliance as a goal. ['
'
It should be noted that the findings of-the PCM program are not absolute
-
but are excellent indicators of potential-problem areas. The'results, l
- both current and cumulative, are issued monthly. Theslicensee had 1
( sufficient knowledge of procedural compliance problems to initiate !
j, corrective actions rather than wait for a larger' data base. !
!
Seven of the violations were failures to meet Technical Specification
.
LimitingConditionforOperations(LC0's).1 Each of these were serious and !
[ collectively represented a breakdown in the licensee's administrative and i
management controls design to safely operate the plant. The safety; !
significance!of the violations was. mitigated considerably by two' items- i
. the plant had only operated for 20 days at an average power of,2 percent; .i
! and the failure of the South Reactor Feed Pump turbine which resulted in- j
<
>
the licensee shutting the reactor down. The inspectors consider the . !
second item to be fortuitous.in-that the: reactor was removed from an
'
4 ;
i
operating condition which required certain equipment to be operable or '
"ractions to'be taken when the licensee wasLunaware that the actions or..
,
J equipment were. required..
- . ] .
[ 'N !
- . .:
i s
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+
_
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1
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-15
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.ns,,,-.,,w~, - r vi, r n , ~~-~~m ~r~-~e so Iv~v h , ew"e =~ ~Ow~~'*"'- ~*A *^~*"*N""""*~-~"
'
^"A ' " " " " *
.,
.
Twenty-six violations, many of them repetitive, have been identified-
in this. report.- Operating history mitigated their safety significance;
however, they demonstrated a major breakdown in the licensee's
administrative controls to safely operate the plant.
9. Management Meetings
a. OutJof-Sequence Rod Pull
DECO management.(denoted in Paragraph 1) met with RIII management.
in' Glen Ellyn, Illinois,-on July 23, 1985', to' discuss the sequence of
events surrounding the out-of-sequence rod pull which occurred on
July 1 and 2,.1985, and their subsequent actions. This meeting was,
attended by the public.
The . licensee's presentation included a' detailed sequence.'of events
imediately preceding and following the event, the rod pull _ sheets,
and the Source Range Monitor (SRM) strip chart which. corresponded to-
the time of the incident. .The licensee also presented a layout of
the control room and the relative location in the control room of
those on shift at the time of the event. A great deal of discussion
was focused on the events and licensee' actions subsequent.to the
incident. The adequacy of the onshift review was discussed; RIII's
position was that the onshift review was insufficient. Considerable
discussion was focused around the adequacy, completeness, and
timeliness of the reporting of the incident to the NRC. The
licensee did not consider the event to he reportable under 10 CFRs
50.72 or 50.73. Region III concurred that the incident was.not
reportable under 10 CFR 50.72 or 50.73, but given;the proximity of
r the Comission's full-power briefing, Deco should have been more-
'
sensitive to the importance of keeping.the NRC informed.- The
Regional Administrator informed the licensee that he had requested
[ the Office of Investigations (OI) to. investigate the event.
The licensee also discussed their actions pertaining to whether or
~
not the unit had been critical, as a ' result of the out-of-sequence .
rod pull, and their corrective action. program. The licensee was
informed that Region III would send an inspection team to Femi.2 -
to assess control room operations and the effectiveness of. the -
corrective action program. -
The licensee's presentation is included as-an-attachment to DECO
letter No. RC-LG-85-0017~ (Jens to Keppler) dated September 5, .1985.
b. Corrective Action Program
DECO management (denoted in Paragraph 1) net with Region III-
management in Glen Ellyn,' Illinois, on September 10, 1985, to discuss
their corrective action program to preclude the repetition of the ~
events which were reported to the NRC during July and. August 1985'and
documented elsewhere in this report. -The meeting was attended by
.
representatives of the. Monroe County. Government and the public.
!
i
! 16'
.
.
The licensee proposed a corrective action program based on
observations and recommendations made by the Institute of Nuclear
Power Operations (INP0) assistance inspection team, findings of two
recent NRC team inspections, conditions of the Confimatory Action
Letter (CAL-RIII-85-10) dated July 16, 1985, findings by the
resident NRC inspectors, and recommendations made by Management
AnalysisCorporation(MAC). The program was divided into short
and long term actions. Short term actions were to be completed
prior to power escalation above five percent. Long term actions
addressed programmatic areas with the licensee indicating a phased
implementation to minimize pertubations to plant operations.
Long term actions were to be initiated prior to exceeding five
percent power but not to be completed until some later date with
the longest date of December 1, 1986.
Deco requested that the five percent power restriction be lifted but
that they would commit to not exceeding twenty percent power until
after the forthcoming outage which is scheduled to start during
October 1985. The request was denied.
Region III requested that the licensee docket the corrective action
program which had been presented and include methods of monitoring
the effectiveness of the corrective actions. The licensee
subsequently submitted their " Reactor Operations Improvement
Plan" in a letter from Jens to Keppler (DECO No. VP-85-0198)
dated October 10, 1985 (copy attached).
The licensee was also informed that another inspection team would
be sent to Femi 2 to observe operations and review the corrective
action program and its effectiveness before .the five percent
restriction could be lifted. This action was predicated upon
a satisfactory resolution of the 01 investigation.
10. Enforcement Conference
The NRC staff met with licensee representatives (denoted in Paragraph 1)
during the management meetings and at various times during the inspection
and reviewed the issues discussed in this report.
The staff also discussed the likely informational content of the
inspection report with regard to documents or processes review by the
inspectors during the inspection. The licensee did not identify any
such documents / processes as proprietary.
I
!
!
!
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