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Category:INSPECTION REPORT
MONTHYEARIR 05000255/20240122024-11-12012 November 2024 Restart Inspection Report 05000255/2024012 IR 05000255/20244022024-09-0606 September 2024 Public: Palisades Nuclear Plant - Decommissioning Security Inspection Report 05000255/2024402 IR 05000255/20240022024-08-0909 August 2024 NRC Inspection Report No. 05000255/2024002 IR 05000255/20240112024-07-15015 July 2024 Nuclear Plant - Restart Inspection Report 05000255/2024011 IR 05000255/20240012024-05-10010 May 2024 NRC Inspection Report No. 05000255/2024001 IR 05000255/20244012024-04-0909 April 2024 – Decommissioning Security Inspection Report 05000255/2024401 IR 05000255/20240102024-03-20020 March 2024 Plant Reference Simulator Inspection Report 05000255/2024010 IR 05000255/20230042024-02-20020 February 2024 NRC Inspection Report 05000255/2023004(DRSS) Holtec Decommissioning International, LLC, Palisades Nuclear Plant IR 05000255/20230032023-10-0404 October 2023 NRC Inspection Report No. 05000255/2023003(DRSS)-Holtec Decommissioning International, LLC, Palisades Nuclear Plant IR 05000255/20230022023-07-19019 July 2023 NRC Inspection Report 05000255/2023002 DRSS-Holtec Decommissioning International, LLC, Palisades Nuclear Plant IR 05000255/20220032022-12-28028 December 2022 NRC Inspection Report No. 05000255/2022003(DRSS); 07200007/2022001 (Drss) – Holtec Decommissioning International, LLC, Palisades Nuclear Plant IR 05000255/20224012022-11-0909 November 2022 Decommissioning Palisades Nuclear Plant - Decommissioning Security Inspection Report 05000255/2022401 IR 05000255/20220022022-08-0303 August 2022 Integrated Inspection Report 05000255/2022002 IR 05000255/20220012022-05-13013 May 2022 Integrated Inspection Report 05000255/2022001 IR 05000255/20220102022-04-0101 April 2022 Triennial Inspection of Evaluation of Changes, Tests and Experiments Baseline Inspection Report 05000255/2022010 IR 05000255/20210062022-03-0202 March 2022 Annual Assessment Letter for Palisades Nuclear Plant, Unit 1, (Report 05000255/2021006) IR 05000255/20210102022-02-24024 February 2022 Triennial Fire Protection Inspection Report 05000255/2021010 IR 05000255/20210042022-02-0808 February 2022 Integrated Inspection Report 05000255/2021004 and Exercise of Enforcement Discretion IR 05000255/20214042021-11-15015 November 2021 NRC Independent Spent Fuel Storage Installation Security Inspection Report 05000255/2021404 and 07200007/2021401 IR 05000255/20210032021-11-0303 November 2021 Integrated Inspection Report 05000255/2021003 IR 05000255/20214032021-10-21021 October 2021 Material Control and Accounting Program Inspection Report 05000255/2021403 IR 05000255/20214022021-10-0606 October 2021 Security Baseline Inspection Report 05000255/2021402 IR 05000255/20210052021-09-0101 September 2021 Updated Inspection Plan for Palisades Nuclear Plant (Report 05000255/2021005) IR 05000255/20210022021-08-10010 August 2021 Integrated Inspection Report 05000255/2021002 ML21197A0322021-07-21021 July 2021 Review of the Fall 2020 Steam Generator Tube Inspection Report IR 05000255/20210012021-05-12012 May 2021 Integrated Inspection Report 05000255/2021001 IR 05000255/20214012021-04-14014 April 2021 Security Baseline Inspection Report 05000255/2021401 IR 05000255/20200062021-03-0404 March 2021 Annual Assessment Letter for Palisades Nuclear Plant (Report 05000255/2020006) IR 05000255/20200042021-02-11011 February 2021 Integrated Inspection Report 05000255/2020004 IR 05000255/20204012021-01-0606 January 2021 Security Baseline Inspection Report 05000255/2020401 IR 05000255/20204202020-12-10010 December 2020 Security Inspection Report 05000255/2020420 ML20342A1812020-12-10010 December 2020 Security Inspection Report Cover Letter 05000255/2020420 IR 05000255/20204022020-11-30030 November 2020 Cyber Security Inspection Report 05000255/2020402 IR 05000255/20205012020-11-20020 November 2020 Emergency Preparedness Inspection Report 05000255/2020501 IR 05000255/20200032020-11-13013 November 2020 Integrated Inspection Report 05000255/2020003 IR 05000255/20200052020-09-0101 September 2020 Updated Inspection Plan for Palisades Nuclear Plant (Report 05000255/2020005) IR 05000255/20200102020-08-24024 August 2020 Biennial Problem Identification and Resolution Inspection Report 05000255/2020010 IR 05000255/20203012020-08-13013 August 2020 NRC Initial License Examination Report 05000255/2020301 IR 05000255/20200022020-08-11011 August 2020 Integrated Inspection Report 05000255/2020002 and Exercise of Enforcement Discretion IR 05000255/20010082020-05-12012 May 2020 Final ASP Analysis - Palisades (IR 050002552001008) IR 05000255/20200012020-05-12012 May 2020 Integrated Inspection Report 05000255/2020001 IR 05000255/20200112020-04-21021 April 2020 Design Basis Assurance Inspection (Teams) Inspection Report 05000255/2020011 IR 05000254/20204012020-03-23023 March 2020 Security Baseline Inspection Report 05000254/2020401 and 05000265/2020401 IR 05000255/20190062020-03-0303 March 2020 Annual Assessment Letter Palisades Nuclear Plant (Report 05000255/2019006) IR 05000255/20190042020-01-28028 January 2020 Integrated Inspection Report 05000255/2019004 and 07200007/2019001 ML19357A2752019-12-23023 December 2019 Request for Information for an NRC Triennial Baseline Design Bases Assurance Inspection (Team); Inspection Report 05000255/2020011 IR 05000255/20194112019-11-25025 November 2019 Security Baseline Inspection Report 05000255/2019411 and Independent Spent Fuel Storage Security Inspection Report 07200007/2019401 (Cover Letter Only) (DRS-M.Ziolkowski) IR 05000255/20190032019-11-14014 November 2019 Integrated Inspection Report 05000255/2019003 ML19294A2872019-10-21021 October 2019 Design Basis Assurance Inspection (Programs) Inspection Report 05000255/2019010 IR 05000255/20190052019-08-28028 August 2019 Updated Inspection Plan for Palisades Nuclear Plant, Unit 1 (Report 05000255/2019005) 2024-09-06
[Table view] Category:NRC-GENERATED
MONTHYEARIR 05000255/19990101999-10-13013 October 1999 Insp Rept 50-255/99-10 on 990812-0921.One Violation Noted & Being Treated as Ncv.Major Areas Inspected:Aspects of Licensee Operations,Maint,Engineering & Plant Support IR 05000255/19990141999-09-23023 September 1999 Insp Rept 50-255/99-14 on 990831-0901.No Violations Noted. Major Areas Inspected:Review of Chemical & Radiological Services Dept on-line Planning & Scheduling Program IR 05000255/19990091999-09-0303 September 1999 Insp Rept 50-255/99-09 on 990522-0811.No Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000255/19990081999-07-13013 July 1999 Insp Rept 50-255/99-08 on 990522-0630.No Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000255/19990041999-06-0404 June 1999 Insp Rept 50-255/99-04 on 990410-0521.No Violations Noted. Major Areas Inspected:Operations,Maint Engineering & Plant Support IR 05000255/19990061999-06-0303 June 1999 Insp Rept 50-255/99-06 on 990506-12.Three Violations Noted & Being Treated as non-cited Violations.Major Areas Inspected: Effectiveness of Radiation Protection Program IR 05000255/19990051999-05-19019 May 1999 Insp Rept 50-255/99-05 on 990503-06.Violations Noted.Major Areas Inspected:Activities Associated with GL 96-05, Periodic Verification of Design-Basis Capability of Safety- Related Movs IR 05000255/19990031999-04-23023 April 1999 Insp Rept 50-255/99-03 on 990226-0409.No Violations Noted. Major Areas Inspected:Operations,Maintenance,Engineering & Plant Support IR 05000255/19990011999-03-0505 March 1999 Insp Rept 50-255/99-01 on 990112-0225.No Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support ML18066A4101999-02-0505 February 1999 Insp Rept 50-255/98-22 on 981126-990112.Violations Noted. Major Areas Inspected:Licensee Operations,Engineering & Plant Support IR 05000255/19990021999-02-0505 February 1999 Partially Withheld Insp Rept 50-255/99-02 on 990119-22. Violations Noted.Major Areas Inspected:Status of Security Facilities & Equipment,Testing & Maintenance,Protected Area Detection & Assessment Aids IR 05000255/19980211998-12-29029 December 1998 Insp Rept 50-255/98-21 on 981130-1204.No Violations Noted. Major Areas Inspected:Licensee Performance During Plant Biennial Exercise of Emergency Plan IR 05000255/19980191998-12-14014 December 1998 Insp Rept 50-255/98-19 on 981008-1125.No Violations Noted. Major Areas Inspected:Licensee Operations,Engineering & Plant Support IR 05000255/19980201998-11-24024 November 1998 Insp Rept 50-255/98-20 on 981026-30.No Violations Noted. Major Areas Inspected:Review Evaluation of Shipping Cask Used in Transportation Incident Wherein Class 7 Radioactive Matl Shipment,Exceeded NRC & DOT Limits for Radiation IR 05000255/19980071998-11-12012 November 1998 Insp Rept 50-255/98-07 on 980413-1023.One Apparent Violation Be Considered for Escalated Enforcement Action.Major Areas Inspected:Review of Events,Circumstances & Licensee Investigation of TS Surveillance Refueling Test IR 05000255/19980171998-11-0505 November 1998 Insp Rept 50-255/98-17 on 980821-1007.No Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000255/19980181998-10-0101 October 1998 Insp Rept 50-255/98-18 on 980824-0902.One Violation Being Considered for Escalated Enforcement Action.Major Areas Inspected:Review Transportation Incident in Which Class 7 Radioactive Package,Shipped on Open Transport Vehicle ML18068A4741998-09-18018 September 1998 Insp Rept 50-255/98-15 on 980702-0821.No Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support Re Fire Brigade Response to Minor Electrical Fire Wearing Appropriate Safety Gear in Timely Manner IR 05000255/19980121998-09-0202 September 1998 Insp Rept 50-255/98-12 on 980706-24.No Violations Noted. Major Areas Inspected:Engineering IR 05000255/19980161998-08-28028 August 1998 Insp Rept 50-255/98-16 on 980810-14.No Violations Noted. Major Areas Inspected:Review of Emergency Preparedness Program,As Aspect of Plant Support IR 05000255/19980131998-08-0707 August 1998 Insp Rept 50-255/98-13 on 980720-22 & 27-29.No Violations Noted.Major Areas Inspected:Reviewed Fire Protection Program,Aspect of Plant Support ML18066A2601998-07-30030 July 1998 Insp Rept 50-255/98-10 on 980507-0701.Violation Noted,Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000255/19980141998-07-29029 July 1998 Insp Rept 50-255/98-14 on 980707-10.No Violations Noted. Major Areas Inspected:Review of Planning & Radiological Controls for Resin Sluice,Calibration of Personal Contamination Monitors & Mgt & Operation of Area IR 05000255/19980111998-07-0202 July 1998 Insp Rept 50-255/98-11 on 980518-0604.No Violations Noted. Major Areas Inspected:Licensee C/As & Engineering Involvement in C/A Process ML18066A1951998-06-15015 June 1998 Insp Rept 50-255/98-09 on 980504-0601.Violations Noted.Major Areas Inspected:Control of Plant Radiological Conditions, Development of RWP & Planning to Ensure That Radiation Exposure During Recent Refueling Outage Was ALARA IR 05000255/19980061998-06-12012 June 1998 Insp Rept 50-255/98-06 on 980504-08 & 11-14.No Violations Noted.Major Areas Inspected:Maint & Engineering ML18066A1911998-06-11011 June 1998 Insp Rept 50-255/98-05 on 980314-0506.Violations Noted.Major Areas Inspected:Licensee Operations,Maint,Engineering & Plant Support IR 05000255/19980081998-05-28028 May 1998 Partially Withheld Insp Rept 50-255/98-08 on 980504-08 (Ref 10CFR73.71).No Violations Noted.Major Areas Inspected: Effectiveness of Access Control Functions & Testing & Maint Activities Related to Security Equipment ML18066A2131998-05-18018 May 1998 Insp Rept 50-255/98-03 on 980325-0410.Violations Noted.Major Areas Inspected:Engineering ML18065B2491998-05-18018 May 1998 Insp Rept 50-255/98-04 on 980325-0401.Violations Noted.Major Areas Inspected:Review of Training Procedures,Written & Operating Exam Matl & Observation & Evaluation of Operator Performance & Licensee Evaluators During Exam ML18065B2161998-04-16016 April 1998 Insp Rept 50-255/98-02 on 980128-0313.Violation Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support ML18065B1681998-02-26026 February 1998 Insp Rept 50-255/97-18 on 971206-980127.Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000255/19970161998-02-0202 February 1998 Insp Rept 50-255/97-16 on 971212-19 & 980114-16.Violation Noted.Major Areas Inspected:Control Room Habitability Sys, Respiratory Protection Program,Plant Water Quality,Chemistry Program,Fuel Monitoring,Post Accident Sample Monitoring Sys ML18065B1481998-01-21021 January 1998 Insp Rept 50-255/97-13 on 971018-1205.Violations Noted.Major Areas Inspected:Aspects of Licensee Operations,Maint, Engineering & Plant Support IR 05000255/19970171998-01-12012 January 1998 Insp Rept 50-255/97-17 on 971210-11.No Violations Noted. Major Areas Inspected:Maint & Matl Condition of Facilities & Equipment,Miscellaneous Maint Issues & Mgt Meetings IR 05000255/19972011997-12-30030 December 1997 Insp Rept 50-255/97-201 on 970916-1114.Deficiencies Identified in Control & Performance of Calculations.Purpose of Insp Was to Evaluate Capability of Selected Sys to Perform Safety Functions Required by Design Bases ML18065B1281997-12-19019 December 1997 Insp Rept 50-255/97-11 on 970828-1017.Violations Noted.Major Areas Inspected:Operations,Maint,Engineering & Plant Support ML18065B1241997-12-13013 December 1997 Insp Rept 50-255/97-15 on 971105-07.Violations Noted.Major Areas Inspected:High Radiation Area Posting Incident, Radiation Protection Training,Corrective Action Program & Communication of Radiation Protection Expectations of Staff IR 05000255/19970141997-12-12012 December 1997 Insp Rept 50-255/97-14 on 971028-1119.Apparent Violations Being Considered for Escalated Enforcement Action.Major Areas Inspected:Operations & Maint IR 05000255/19970121997-10-25025 October 1997 Insp Rept 50-255/97-12 on 970922-26.No Violations Noted. Major Areas Inspected:Implementation of Radiological Effluents & Radiological Environ Monitoring Programs IR 05000255/19970091997-10-14014 October 1997 Insp Rept 50-255/97-09 on 970708-0827.No Violations Noted. Major Areas Inspected:Operations,Maint & Engineering ML18067A6891997-09-0505 September 1997 Insp Rept 50-255/97-08 on 970524-0707.Violations Noted.Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000255/19970101997-09-0101 September 1997 Insp Rept 50-255/97-10 on 970804-08.No Violations Noted. Major Areas Inspected:Review of Implementation of Solid Radioactive Waste Mgt & Shipping Program IR 05000255/19970061997-07-0909 July 1997 Insp Rept 50-255/97-06 on 970412-0523.No Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support ML18067A5951997-06-17017 June 1997 Insp Rept 50-255/97-05 on 970301-0411.Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000255/19970021997-04-22022 April 1997 Insp Rept 50-255/97-02 on 970111-0303.No Violations Noted. Major Areas Inspected:Operations,Maintenance,Engineering & Plant Support IR 05000255/19960171997-02-20020 February 1997 Insp Rept 50-255/96-17 on 961124-970110.Violations Noted. Major Areas Inspected:Licensee Operations,Maint,Engineering & Plant Support IR 05000255/19960141997-01-22022 January 1997 Insp Rept 50-255/96-14 on 961019-1123.No Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000255/19960181997-01-17017 January 1997 Insp Rept 50-255/96-18 on 961118-970106.No Violations Noted. Major Areas Inspected:Engineering IR 05000255/19960161997-01-0303 January 1997 Insp Rept 50-255/96-16 on 961119-21 & 1216.No Violations Noted.Major Areas Inspected:Maintenance Procedures, Documentation & Engineering Support of Facilities 1999-09-03
[Table view] Category:TEXT-INSPECTION & AUDIT & I&E CIRCULARS
MONTHYEARPNO-II-99-043, on 991013,Palisades Nuclear Plant Located Near South Haven,Mi Notified NRC That Package Received from Licensee Exceeded External Radiation Limits of 200 Mrem Per H Authorized by Regulations.Shipper & Carrier Notified1999-10-14014 October 1999 PNO-II-99-043:on 991013,Palisades Nuclear Plant Located Near South Haven,Mi Notified NRC That Package Received from Licensee Exceeded External Radiation Limits of 200 Mrem Per H Authorized by Regulations.Shipper & Carrier Notified IR 05000255/19990101999-10-13013 October 1999 Insp Rept 50-255/99-10 on 990812-0921.One Violation Noted & Being Treated as Ncv.Major Areas Inspected:Aspects of Licensee Operations,Maint,Engineering & Plant Support IR 05000255/19993011999-10-0404 October 1999 NRC Operator Licensing Exam Rept 50-255/99-301OL (Including Completed & Graded Tests) for Tests Administered on 990607- 14 IR 05000255/19990141999-09-23023 September 1999 Insp Rept 50-255/99-14 on 990831-0901.No Violations Noted. Major Areas Inspected:Review of Chemical & Radiological Services Dept on-line Planning & Scheduling Program IR 05000255/19990091999-09-0303 September 1999 Insp Rept 50-255/99-09 on 990522-0811.No Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000255/19990081999-07-13013 July 1999 Insp Rept 50-255/99-08 on 990522-0630.No Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support PNO-III-99-032, on 990617,fire Discovered in Trailer Complex Containing Offices for Licensee Dry Cask Storage Project Staff.Fire Caused Extensive Damage to Main Portion of complex,triple-wide Trailer.Fire Extinguished1999-06-18018 June 1999 PNO-III-99-032:on 990617,fire Discovered in Trailer Complex Containing Offices for Licensee Dry Cask Storage Project Staff.Fire Caused Extensive Damage to Main Portion of complex,triple-wide Trailer.Fire Extinguished PNO-III-99-031, on 990609,minor Hydrogen Burns Occurred During Welding of Structural Lid on Spent Fuel Storage Cask Following Loading Earlier in Wk.Nrc Resident Inspector Will Follow Licensee Response to Incident & Observe1999-06-10010 June 1999 PNO-III-99-031:on 990609,minor Hydrogen Burns Occurred During Welding of Structural Lid on Spent Fuel Storage Cask Following Loading Earlier in Wk.Nrc Resident Inspector Will Follow Licensee Response to Incident & Observe IR 05000255/19990041999-06-0404 June 1999 Insp Rept 50-255/99-04 on 990410-0521.No Violations Noted. Major Areas Inspected:Operations,Maint Engineering & Plant Support IR 05000255/19990061999-06-0303 June 1999 Insp Rept 50-255/99-06 on 990506-12.Three Violations Noted & Being Treated as non-cited Violations.Major Areas Inspected: Effectiveness of Radiation Protection Program IR 05000255/19990051999-05-19019 May 1999 Insp Rept 50-255/99-05 on 990503-06.Violations Noted.Major Areas Inspected:Activities Associated with GL 96-05, Periodic Verification of Design-Basis Capability of Safety- Related Movs IR 05000255/19990031999-04-23023 April 1999 Insp Rept 50-255/99-03 on 990226-0409.No Violations Noted. Major Areas Inspected:Operations,Maintenance,Engineering & Plant Support IR 05000255/19990011999-03-0505 March 1999 Insp Rept 50-255/99-01 on 990112-0225.No Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support ML18066A4091999-02-10010 February 1999 Notice of Violation from Insp on 981126-990112.Violation Noted:As of 981218,util Had Not Submitted Evaluation of Exam Results Completed on 980523 on Acceptability of Continued Svc with 2 Degraded Pressure Retaining Code Class 1 Studs ML18066A4101999-02-0505 February 1999 Insp Rept 50-255/98-22 on 981126-990112.Violations Noted. Major Areas Inspected:Licensee Operations,Engineering & Plant Support IR 05000255/19990021999-02-0505 February 1999 Partially Withheld Insp Rept 50-255/99-02 on 990119-22. Violations Noted.Major Areas Inspected:Status of Security Facilities & Equipment,Testing & Maintenance,Protected Area Detection & Assessment Aids IR 05000255/19980211998-12-29029 December 1998 Insp Rept 50-255/98-21 on 981130-1204.No Violations Noted. Major Areas Inspected:Licensee Performance During Plant Biennial Exercise of Emergency Plan IR 05000255/19980191998-12-14014 December 1998 Insp Rept 50-255/98-19 on 981008-1125.No Violations Noted. Major Areas Inspected:Licensee Operations,Engineering & Plant Support IR 05000255/19980201998-11-24024 November 1998 Insp Rept 50-255/98-20 on 981026-30.No Violations Noted. Major Areas Inspected:Review Evaluation of Shipping Cask Used in Transportation Incident Wherein Class 7 Radioactive Matl Shipment,Exceeded NRC & DOT Limits for Radiation IR 05000255/19980071998-11-12012 November 1998 Insp Rept 50-255/98-07 on 980413-1023.One Apparent Violation Be Considered for Escalated Enforcement Action.Major Areas Inspected:Review of Events,Circumstances & Licensee Investigation of TS Surveillance Refueling Test IR 05000255/19980171998-11-0505 November 1998 Insp Rept 50-255/98-17 on 980821-1007.No Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000255/19980181998-10-0101 October 1998 Insp Rept 50-255/98-18 on 980824-0902.One Violation Being Considered for Escalated Enforcement Action.Major Areas Inspected:Review Transportation Incident in Which Class 7 Radioactive Package,Shipped on Open Transport Vehicle ML18068A4741998-09-18018 September 1998 Insp Rept 50-255/98-15 on 980702-0821.No Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support Re Fire Brigade Response to Minor Electrical Fire Wearing Appropriate Safety Gear in Timely Manner IR 05000255/19980121998-09-0202 September 1998 Insp Rept 50-255/98-12 on 980706-24.No Violations Noted. Major Areas Inspected:Engineering ML18068A4281998-09-0202 September 1998 Notice of Violation from Insp on 980706-24.Violation Noted: Testing Program Not Developed Until 971201,after 44 of 72 Molded Case Circuit Breakers Failed to Trip During Testing IR 05000255/19980161998-08-28028 August 1998 Insp Rept 50-255/98-16 on 980810-14.No Violations Noted. Major Areas Inspected:Review of Emergency Preparedness Program,As Aspect of Plant Support IR 05000255/19980131998-08-0707 August 1998 Insp Rept 50-255/98-13 on 980720-22 & 27-29.No Violations Noted.Major Areas Inspected:Reviewed Fire Protection Program,Aspect of Plant Support ML18066A2581998-07-30030 July 1998 Notice of Violation from Insp on 980507-0701.Violation Noted:Shift Supervisor Failed to Maintain Proper Procedure Configuration in That Safety Injection Tank Pressure Control Valves Manual Isolation Valves ES-3038 & ES3042 Not Closed ML18066A2601998-07-30030 July 1998 Insp Rept 50-255/98-10 on 980507-0701.Violation Noted,Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000255/19980141998-07-29029 July 1998 Insp Rept 50-255/98-14 on 980707-10.No Violations Noted. Major Areas Inspected:Review of Planning & Radiological Controls for Resin Sluice,Calibration of Personal Contamination Monitors & Mgt & Operation of Area IR 05000255/19980111998-07-0202 July 1998 Insp Rept 50-255/98-11 on 980518-0604.No Violations Noted. Major Areas Inspected:Licensee C/As & Engineering Involvement in C/A Process ML18066A1951998-06-15015 June 1998 Insp Rept 50-255/98-09 on 980504-0601.Violations Noted.Major Areas Inspected:Control of Plant Radiological Conditions, Development of RWP & Planning to Ensure That Radiation Exposure During Recent Refueling Outage Was ALARA ML18066A1941998-06-15015 June 1998 Notice of Violation from Insp on 980504-0601.Violation Noted:On 980429,Radiation Controlled Door to 607 Mainsteam Room in Containment,W/Radiation Levels Ranging Up to 5,000 Mrem/H Was Not Locked & Guarded IR 05000255/19980061998-06-12012 June 1998 Insp Rept 50-255/98-06 on 980504-08 & 11-14.No Violations Noted.Major Areas Inspected:Maint & Engineering ML18066A1901998-06-11011 June 1998 Notice of Violation from Insp on 980314-0506.Violation Noted:On 980426,inspectors Identified That Palisades Administrative Procedure 5.09 Failed to Prescribe Foreign Matl Exclusion Controls for Electrical Safety Equipment ML18066A1911998-06-11011 June 1998 Insp Rept 50-255/98-05 on 980314-0506.Violations Noted.Major Areas Inspected:Licensee Operations,Maint,Engineering & Plant Support IR 05000255/19980081998-05-28028 May 1998 Partially Withheld Insp Rept 50-255/98-08 on 980504-08 (Ref 10CFR73.71).No Violations Noted.Major Areas Inspected: Effectiveness of Access Control Functions & Testing & Maint Activities Related to Security Equipment ML18066A2121998-05-18018 May 1998 Notice of Deviation from Insp on 980325-0410.Deviation noted:FC-854 Moved Backup Power Source from MCC 3 to MCC 2, Redundant Power Source,Which Resulted in Bus Y-01 Being Able to Automatically Transfer Between Two safety-related Busses ML18066A2111998-05-18018 May 1998 Notice of Violation from Insp on 980325-0410.Violation Noted:As of 971114,listed Analyses Were Not Revised When Analytical Inputs Were Changed or Found to Be in Error ML18065B2491998-05-18018 May 1998 Insp Rept 50-255/98-04 on 980325-0401.Violations Noted.Major Areas Inspected:Review of Training Procedures,Written & Operating Exam Matl & Observation & Evaluation of Operator Performance & Licensee Evaluators During Exam ML18065B2481998-05-18018 May 1998 Notice of Violation from Insp on 980325-0401.Violation Noted:On 980121 & 980128,licensee Annual Licensed Operator Category B Written Exam Constructed w/look-up Questions & 10 of 23 Questions Considered Simple Knowledge Level Questions ML18066A2131998-05-18018 May 1998 Insp Rept 50-255/98-03 on 980325-0410.Violations Noted.Major Areas Inspected:Engineering ML18065B2161998-04-16016 April 1998 Insp Rept 50-255/98-02 on 980128-0313.Violation Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support ML18065B2151998-04-16016 April 1998 Notice of Violation from Insp on 980128-0313.Violation Noted:On 980113,activity Affecting Quality Was Not Accomplished in Accordance W/Procedure 4.02 & Associated Checklist Cl 3.4 in That Watertight Door 59 Found W/O Dogs ML20217K5821998-04-0202 April 1998 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $55,000.Violation Noted:On 971017,shift Supervisor Failed to Ensure That Equipment Could Be Removed from Svc,By Failing to Ensure That TS Requirements Were Met ML18066A1561998-03-30030 March 1998 EN-98-019:on 980402,notice of Proposed Imposition of Civil Penalty in Amount of $55,000 Issued to Licensee.Action Based on Six Violations,That Represent Severity Level III Problem ML18065B1681998-02-26026 February 1998 Insp Rept 50-255/97-18 on 971206-980127.Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support ML18067A8191998-02-0606 February 1998 Notice of Violation from Insp on 971212-19 & 980114-16. Violation Noted:Licensee Failed to Post High Radiation Area W/Conspicuous Signs Bearing Radiation Symbol & Words Caution High Radiation Area on 980107 ML18067A8241998-02-0505 February 1998 Errata to NOV from Insp on 971213.NRC Agree That NOV Should Refer Only to Failure to Perform Contamination Survey on 970910,based on Further Review of Radiological Survey Sheets & Conversation W/Staff IR 05000255/19970161998-02-0202 February 1998 Insp Rept 50-255/97-16 on 971212-19 & 980114-16.Violation Noted.Major Areas Inspected:Control Room Habitability Sys, Respiratory Protection Program,Plant Water Quality,Chemistry Program,Fuel Monitoring,Post Accident Sample Monitoring Sys 1999-09-03
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U.S. NUCLEAR REGULATORY COMMISSION REGION I I I Docket No.:
License No.:
Report No.:
Licensee:
Facility:
Location:
Dates:
Inspectors:
Approved by:
9612260129 961018 PDR ADOCK 05000255 G
PDR 50-255 DPR-20 50-255/96008{DRP)
Consumers Power Company 212 West Michigan Avenue Jackson, MI 49201 Palisades Nuclear Generating Plant 27780 Blue Star Memorial Highway Covert, MI 49043-9530 July 27 through September 6, 1996 M. Parker, Senior Resident Inspector P. Prescott, Resident Inspector W. J. Kropp, Chief, Projects Branch 3 Division of Reactor Projects
EXECUTIVE SUMMARY Palisades Nuclear Generating Plant NRC Inspection Report 50-255/96008 This inspection included aspects of licensee operations, maintenance, engineering and plant support. The report covers a 6-week period of resident *
inspectio Operations
There were two instances of inadequate senior reactor operator {SRO)
coverage in the control room; however, these incidents had minor safety
- significance. This is considered a violation of TS 6.2.2b for failing to have a SRO in the control room at all times {Section 01.2).
Maintenance
Maintenance personnel missed a procedure step during post maintenance testing of the new wattmeters for the Emergency Diesel Generator {EOG)
1-The licensee reviewed the event, and the same testing for EOG 1-2 was completed without any problem During the maintenance outage to install the wattmeter, however, a technician operated the ventilation system without proper authorization {Section Ml.2).
Engineering
The Emergency Diesel Generator system engineer took inappropriate troubleshooting actions by manually stopping the fuel rack from oscillating during surveillance testing of EOG 1-1. The licensee took appropriate corrective actions {Section El.l).
- The inspectors expressed concern to licensee management that initial baseline testing of the containment air coolers had not been performed
{Section El.2).
Plant Support
Radiological worker practices appeared adequate~ {Section Rl.1).
Report Details Summary of Plant Status The unit operated at full power during the inspection perio Conduct of Operations 01.l General Comments C71707l I. Operations Using Inspection Procedure 71707, the inspectors conducted frequent reviews of ongoing plant operation In general, the conduct of opera-tions was professional and safety-conscious; however, on two separate occasions, no senior reactor operator was present in the control room for a short period of time. A violation was issued for failure to meet TS 6.2.2.2 Control Room Manning Inspection Scope C71707l On August 9, the Operations Manager notified the inspectors that no senior reactor operators (SROs) were present in the control room for a short period of tim The inspectors followed up on the licensee's evaluation and corrective action Observations and Findings On August 9, at 4:30 am, the control room supervisor (CRS} left the control room to confer with the other two on-shift SROs, the shift supervisor (SS) and the shift engineer (SE), who were in the shift supervisor's office. The SROs recognized that no SRO was present in the control room, and the CRS immediately returned to the control roo The duration of the absence was believed to be less than 10 seconds, and the CRS was within eyesight of the control room through the viewing gallery windo The inspectors noted that the CRS was not ~ permanent shift holder but was on-shift to maintain proficiency. Also, the CRS had incorrectly assumed that the control room boundaries had been moved to accommodate changes in the physical seating of the SROs as a result of ongoing construction modifications in the control roo The licensee had previously evaluated the impact of construction on the seating arrangements.and work stations of the SROs and had determined that no changes to the defined control room boundaries were necessar On August 13, the Operations Manager informed the inspectors that a second incident of improper shift manning had occurre On August 13, at 3:15 p.m., the SE left the control roo The SE had been asked to maintain control room SRO oversight manning responsibilities while the
CRS left the cQntrol room for a short period of tim The SE left the control room a short time later to process a work order; the absence lasted for less than one minut When questioned by the CRS in the control room, the SE immediately recognized this oversigh The SE stated that he had been briefed on the August 9 incident and that he was aware of the control room boundarie He also indicated that the night orders had addressed this issue and that control room manning had been covered during a prior shift turnover. After recognizing this incident, the shift noted that the oncoming CRS was in the control room during the time of the incident; however, the oncoming CRS was not fully aware of existing plant conditions nor had he received a proper turnover to assume control of the shif Technical Specifications 6.2.2b. and 10 CFR 50.54 (m)(2)(iii) state that at least one licensed senior reactor operator shall be in the control room at all times during conditions other than cold shutdown or refueling. Administrative Procedure 4.00, "Operations Organization Responsibilities and Conduct", Rev. 17, dated June 25, 1996, states in paragraph 5.2.1.a that the shift supervisor shall ensure the operating shift is properly manned and shall be maintained in accordance with 10 CFR 50.54, Palisades Technical Specifications, and the Site Emergency Pla The Operations Control Panel Monitoring Standard, dated February 14, 1996, includes diagram defining both the "At-The-Controls" area of the control room and the control room boundaries and shows the expected shift manning position c. Conclusions Confusion due to ongoing construction activities, compounded in one instance by having a non-permanent shift holder assume the shift, resulted in no SROs being present in the control room when require Due to the short duration of the absences, these incidents were of minor safety significance and were considered two examples of a violation of TS 6.2.2b.(50-255/96008-0l(DRP)).
Miscellaneous Operations Issues (92700 and 92702)
08.l (Closed) Violation CVIOl 50-255/93030-01:
Cooldown Rate Exceede Inadequate procedural guidance and personnel error resulted in failure to maintain the cooldown rates less than 40°F/hr with the primary coolant system (PCS) temperature between 170° and 250° and less than 20°F/hr with the PCS temperature less 170° The licensee's evaluation showed that the proper temperature indication to use in the cooldown calculations was the vessel return temperatur The applicable procedures were revised to include monitoring.vessel return temperature, and the operating crews were given classroom and simulator training.*
Additionally, the calculation for IO CFR 50, Appendix G indicates that the vessel brittle fracture limit had not been exceeded during the September 17, 1993, cooldow This item is close.2 CClosedl VIO 50-255/93030-02:
Procedures Not Implemented as Require Administrative Procedure 4.00, "Operation, Organization Responsibilities, and Conduct," requires the shift supervisor and operating shift to remain cognizant of the cooldow The shift involved*
with the excessive cooldown rate was removed from licensed duties for training which focused on specific tasks associated with reactor system cooldowns, job planning, teamwork and communication skills. The shift*
was then evaluated on the simulator and received an adequate performance rating prior to resuming licensed duties. Also, the remaining shifts received similar training. This item is close.3 CClosedl VIO 50-255/93030-03:
Procedures Not Appropriate to Circumstance System Operating Procedure (SOP) 1, "Primary Coolant System," did not provide sufficient guidance to properly control the plant cooldown and transition from forced circulation to shutdown cooling flo The prime concern was the temperature change of the water flow over the reactor vessel beltline wel The procedure was revised to provide specific guidance on controlling the cooldown rate throughout the transient period corresponding to stopping all primary coolant pump A licensee evaluation concluded that the transition to shutdown cooling (SOC) could be performed within the TS limits by testing the revised procedure on the simulator. The operating crews then received simulator training with the revised procedures. This item is closed~
08.4 Related Open Items In addition to the items discussed in paragraphs 08.1 through 0 above, the following related open items are closed:
o Licensee Event Report 50-255/93010 (closed)
~
Unresolved Item 50-255/93021-0l(DRP) (closed)
Apparent Violation 50-255/93028-0l(DRP) (closed)
Apparent Violation 50-255/93028-02(DRP) (closed)
Apparent Violation 50-255/93028-0Ja(DRP) (closed)
Apparent Violation 50-255-93028-03b(DRP) (closed)
Apparent Violation 50-255/93028-04a(DRP) (closed)
Apparent Violation 50-255/93028-04b(DRP) (closed)
II. Maintenance Ml Conduct of Maintenance Ml.I General Comments Inspection Scope (62703 and 61726)
- The inspectors observed all or portions of the following work activities:
24612917:
PPAC FWS067 P-8A Inspect coupling and change pump oil Removal, inspection and reinstallation of service
24611504:
24610199:
24513491:
water pump P-78 upper motor bearings Replacement of EOG Tachometer
.
PM on EOG 1-2 Inspection of collector rings and end rotor bearing Repair/Recoat Containment Dome Surveillance Activities
SOP-8 Attachment Two: Testings of the Main Turbine Protective Trip Devices
M0-38: Auxiliary Feedwater System In-Service Test Procedure
SOP-22: (for EOG 1-1) Emergency Diesel Generators
TI-SC-96-011-01: Specification change test for EOG 1-1 newly installed watt-meters
TI-SC-96-011-02: Specification change test for EOG 1-2 newly installed watt-meters
MI-2A:
Thermal Margin/Low Pressure Trip Units
M0-33:
Control Room Ventilation Emergency Operation b. Observations and Findings The work performed under these activities was generally professional and thorough. All work observed was performed with the work package present and in active use, and supervisors and system engineers frequently monitored job progres When applicable, appropriate radiation control measures were in plac c. Conclusions The inspectors observed good procedure adherence practices. Specific discussions of observed maintenance are discussed in paragraph M belo M Emergency Diesel Generator CEOGl 1-2 Maintenance Outage and Testing Inspection Scope (62703 and 61726)
The inspectors observed various preventative maintenance (PM) activities for the EOG 1-2 including testing of a local wattmeter installed under a specification change (SC).
The SC also added.permanent EOG starting circuit timing test jack b. Observations and Findings On August 20, during testing of the wattmeter, a large error was noted between the control room and local panel wattmete Licensee
troubleshooting found that one of the current transformer shorting switches, TS-8/TS-17, was not closed as required by the test procedur The step had been missed by both the electrical maintenance technician and an independent verifie The wattmeter test instructions included a step which required the technician to close switch TS-2/TS-11, which was done, then close switch TS-8/TS-17, restoring the switch to its normal positio The test s~itches were not labeled, the personnel involved were performing the procedure for the first time, and only one action would normally be performed per procedure step. Additionally, the job was assigned to the electrical maintenance department the same day it was done which left little opportunity for the technicians to perform a walkdown or review the test instructions. The immediate corrective actions taken by the licensee's electrical maintenance management was to stop work and discuss the importance of self-check and independent verification with all electrical maintenance and instrumentation and control personne This failure to properly perform a step in a test instruction constitutes a violation of minor significance and is being treated as a Non-Cited Violation, consistent with Section IV of the NRC Enforcement Policy (50-255/96008-02(DRP)).
During performance of EOG preventive maintenance, an electrical maintenance technician started the supply ventilation fan to the EOG 1-2 room.without consulting operations personnel or the forema When brought to their attention by the inspectors, licensee management took appropriate corrective actions. This unauthorized manipulation of plant equipment constitutes a violation of minor significance and is being.
treated as a Non-Cited Violation, consistent with Section IV of the NRC Enforcement Policy (50-255/96008-0J(DRP)).
Conclusions The test instructions were revised and a satisfactory retest was conducte The inspectors observed the test and no further problems were identifie On August 28, the same SC was performed on the EOG 1-The inspectors witnessed the prejob brief, the test connections installation, and the post maintenance test. The prejob brief was thorough and there were no problems noted with either the test connection installation or subsequent testin The licensee took immediate corrective actions to address the inspectors's concerns regarding maintenance personnel operating plant equipment without authorizatio The corrective actions included discussions with personnel about the need to stop and ask questions if procedure steps appear unclear and the importance of self-checking.
The inspectors and the system engineer discussed the impact of the speed oscillations which occurred during performance of surveillance testing on operability of EOG 1-1. During these discussions the inspectors determined that the system engineer may have taken actions not covered by the surveillance procedur The concern about troubleshooting during an operability surveillance was discussed with operations and engineering managemen b. Observations and Findings On August 4, 1996, the licensee performed monthly surveillance M0-7A-l,
"Emergency Diesel Generators 1-1 & 1-2" for the emergency diesel generator (EOG) 1-1. After the EOG was started, but prior to loading the generator, the auxiliary operator and the system engineer noticed that the arm of the fuel rack was oscillating approximately three quarters of an inch of travel. The system engineer had seen these oscillations before and touched the fuel rack arm to stop the. motio The surveillance continued and the EOG 1-1 was declared operable. This manipulation of the fuel racks contrary to the surveillance procedure constitutes a violation of minor significance and is being treated as a Non-Cited Violation, consistent with Section IV of the NRC Enforcement Policy (50-255/96008-04(DRP)).
The system engineer stated the problem was due to the governor requiring tuning and/or possible air entrainment in the governor oi Additionally, in an accident scenario, the EOG would load to a dead bus; therefore, the oscillations would not cause a proble The inspectors were concerned that there was not a full understanding of what may occur if the oscillations had not been stopped and the EOG had been synchronized to a loaded bus instead of a dead bu The purpose of the surveillance was to demonstrate operability of the EOG, not to conduct troubleshootin Licensee management agreed that the system engineer should not have intervened in the surveillanc On August 14, the inspectors observed a surveillance performed to prove operability. The fuel rack oscillations were less pronounced than on the earlier surveillance, and the EOG successfully loaded to the bu No problems were noted while the EOG was loade c. Conclusions Licensee management agreed that it was inappropriate for a system engineer to manipulate equipment during performance of a surveillanc The licensee took appropriate corrective actions to address the inspector's concern El.2 Containment Air Coolers CCACsl Performance Testing Inspection Scope C3755ll The inspectors reviewed condition report C-PAL-96-0845, "Gross Reduction in Service Water Flow to Hypochlorite Eductor Following SW Pump Rotation." One item discussed with system engineers involved testing of the containment air cooler Equipment performance data such as air flow and motor horsepower were tested; however, heat removal capability (overall system performance) was not successfully accomplishe b. Observations and Findings On July 30, 1996, while chlorination was in progress to the service
.
water system, the control room switched from pumps P-ZA and P-ZC to P-ZB and P-ZC in service. Following the transfer, the control room received
- the "chlorination trouble" annunciator. A similar alarm occurred on May 29, 199 On May 31, maintenance personnel removed a section of piping downstream of the chlorination system educto The inner surfaces of the eductor and observable downstream piping were coated with a thick layer of calcium carbonate. Pieces of the coating, approximately three quarters of an inch in diameter, had broken off, and the inspectors were concerned about the possibility of heat exchanger foulin The chemistry technician believed that the pieces were too large to pass through the one-half inch dilution manifold perforations in the intake bay of the service water pump During discussions with plant system engineers, the inspectors became aware that the new CACs, installed during the 1995 refuel outage, did not have any baseline performance data nor had any performance testing been performed since initial installatio The inspectors reviewed the licensee's commitments to Generic Letter (GL) 89-13, "Service Water System Problems Affecting Safety-Related Equipment."
In response to GL 89-13, an action item record (AIR), A-NL-90-036 required the licensee to test the heat transfer capability of CACs VHX-1, VHX-2 and VHX-3, demonstrating that the original CACs would perform the intended design function. This test, performed at the end of a refuel outage with negligible heat loads in containment, showed that the temperature differential between service water and containment temperature was margina In AIR A-NL-92-099, the licensee documented the-potential inaccuracy of the test data and. committed to perform testing in subsequent outages at different times of the year to determine if the test results would be consisten Post-modification testing was performed on the new CACs after the original coolers were replaced due to system leak As with the original coolers, the testing was performed at the end of a refuel
outage, and the performance data was determined to be inconclusiv Also, permanent instrumentation was installed to provide more accurate data on system parameters and allow on-line testing; however, from the I995 refuel outage to present no testing was performe In fact, test procedure T-3I8 "Containment Air Coolers Performance Test," was inactive. Licensing personnel believed that the commitments to GL 89-I3 had been met, since the original CACs had been tested. The inspectors stated that GL 89-I3 was intended to ensure SW system reliability and that the licensee's internal position to GL 89-I3 was for testing of the heat exchangers to continue on a periodic basi c. Conclusions The system engineer stated that the test procedure was under review and that CAC testing was scheduled for the end of the I996 refuel outag The system engineer's workload had not allowed ample time to prepare for testing at the start of the I996 refuel outage, when sufficient heat load in containment is expected to provide satisfactory data. Testing of the CAC heat exchangers was scheduled during plant heatup following the I996 refuel outage. Also, engineering will conduct an assessment of all GL 89-I3 heat exchangers to review the overall adequacy of heat exchanger performance trendin The evaluation of potential plugging of SW heat exchangers due to pieces of calcium carbonate breaking loose was considered an Inspection Followup Item (IFI 50-255/96008-05) pending inspector revie IV. Plant Support Rl Rad;ological Protection and Chem;stry Controls RI.I Maintenance Outages and Daily Radiological Worker Practices Inspection Scope (83750}
The inspectors observed radiological worker activities during the various maintenance outages detailed in this inspection report and monitored radiological practices during daily plant tour Observations and Findings Where applicable for maintenance outages, radiation technicians were present at the job sites. The technicians took appropriate actions and surveys in accordance with good ALARA practice c. Conclusion The inspectors concluded that radiological practices observed during the - - ****---
maintenance outages and plant daily walkdowns were adequat The inspectors had no concern IO
- V. Management Meetings Xl Exit Meeting SUD111ary The inspectors presented the inspection results to members of licensee management at the conclusion of the inspection on September 9, 1996.
PARTIAL LIST OF PERSONS CONTACTED Licensee R. A. Fenech, Vice President, Nuclear Operations T. J. Palmisano, Plant General Manager K. P. Powers, Nuclear Services General Manager G. B. Szczotka, Nuclear Performance Assessment Manager H. L. Linsinbigler, Design Engineering Manager T. C. Bordine, Licensing Manager D. W. Rogers, Operations Manager J. P. Pomeranski, Maintenance and Construction Manager D. P. Fadel, System Engineering Manager D. G. Malone, Shift Operations Supervisor D. J. Malone, Chemical & Radiation Protection Services Manager K. M. Haas, Training Manager S. Y. Wawro, Planning & Scheduling Manager M. E. Parker, Senior Resident Inspector, Palisades P. F. Prescott, Resident Inspector, Palisades
'I
INSPECTION PROCEDURES USED IP 37551:
IP 61726:
IP 62703:
IP 71707:
Onsite Engineering Surveillance Observations Maintenance Observation Plant Operations IP 83750:
Occupational Radiation Exposure IP 92700:
Onsite Followup of Written Reports of Nonroutine Events at Power Reactor Facilities IP 92702:
Followup on Corrective Actions for Violations and Deviations Opened 50-255/96008-01 VIO 50-255/96008-02 NCV 50-255/96008-03 NCV 50-255/96008-04 NCV 50-255/96008-05 IFI Closed 50-255/93030-01 VIO 50-255/93030-02 VIO 50-255/93030-03 VIO 50-255/93021-01 URI 50-255/93028-01 APP VIO 50-255/93028-02 APP VIO 50-255/93028-03a APP VI /93028-03b APP VIO 50-255/93028-04a APP VIO 50-255/93028-04b APP VIO 50-255/93010 LER 50-255/96008-02 NCV 50-255/96008-03 NCV 50-255/96008-04 NCV ITEMS OPENED AND CLOSED Failure to have a SRO in the control room at all times Failure to perform a step in a test instruction Unauthorization operation of plant equipment Failure to follow surveillanc procedure Calcium carbonate fouling of CAC heat exchanger Cooldown rate exceeded Procedures not implemented as required Procedures not appropriate to circumstances Excessive cooldown rate Failure to maintain cooldown rate less than 20 degrees an hour Failure to maintain cooldown rate less than 40 degrees an hour Failure of.the control room operators to remain cognizant of the cooldowri rate *
Failure of the shift supervisor to remain cognizant of the cooldown rate Failure to maintain an adequate cooldown data log for monitoring the cooldown rate SOP-I did not consider the transition of temperature monitoring for T-cold to SOC Exceeding the primary coolant system cooldown rate Failure to perform a step ina test instruction Unauthorization operation of plant equipment Failure to follow surveillanc procedure
- AIR ALARA APP CAC CFR CR CRS DRP EOG FSAR GL I&C IFI IP IR LCO LER NRC NRR PCS PDR PM PPAC PPEP PPM PSIG REF OUT SC soc SE SOP SRO SS SW TI TS URI VIO WO LIST OF ACRONYMS USED Action Item Record As Low As Reasonably Achievable Apparent Containment Air Cooler Code of Federal Regulations Condition Report Control Room Supervisor Division of Reactor Projects Emergency Diesel Generator Final Safety Analysis Report Generic Letter Instrumentation & Control Inspection Followup Item Inspection Procedure
Inspection Report
Limiting Condition of Operation
Licensee Event Report
Nuclear Regulatory Commission
Office of Nuclear Reactor Regulation
Primary Coolant System
Public Document Room
Preventative Maintenance
Periodic and Predetermined Activity_ Control
Palisades Performance Enhancement Program
Parts Per Million
Pounds per Square Inch Gauge
Refuel Outage
Specification Change
Shutdown Cooling
Shift Engineer
System Operating Procedure
Senior Reactor Operator
Shift Supervisor
Service Water
Test Instruction
Technical Specification
Unresolved Item
Violation
Work Order