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Category:INSPECTION REPORT
MONTHYEARIR 05000424/20243012025-01-24024 January 2025 NRC Operator License Examination Report 05000424/2024301 and 05000425/2024301 IR 05000424/20244022024-12-13013 December 2024 Security Baseline Inspection Report 05000424/2024402 05000425/2024402 052000252/024404, and 052000262/024405 ML24313A0632024-11-14014 November 2024 Integrated Inspection Report and Assessment Follow-Up Letter 05200025/2024003 and 05200026/2024003 IR 05000424/20240032024-10-30030 October 2024 – Integrated Inspection Report 05000424/2024003 and 05000425/2024003 IR 05000424/20240052024-08-26026 August 2024 Updated Inspection Plan for Vogtle Electric Generating Plant, Units 1 and 2 - Report 05000424/2024005 and 05000425/2024005 IR 05000424/20244012024-08-15015 August 2024 4 - Security Baseline Inspection Report 05000424-2024401, 05000425-2024401, 05200025-2024402, and 05200026-2024403 - Cover Letter ML24212A1442024-08-0101 August 2024 Integrated Inspection Report 05200025/2024002 and 05200026/2024002 IR 05000424/20240022024-07-29029 July 2024 Integrated Inspection Report 05000424/2024002 and 05000425/2024002 IR 05000424/20244042024-07-26026 July 2024 Material Control and Accounting Program Inspection Report 05000424/2024404 and 05000425/2024404 (Cover Letter) ML24194A0342024-07-12012 July 2024 Review of the Refueling Outage 1R24 Steam Generator Tube Inspection Report ML24191A3792024-07-10010 July 2024 – Initial Test Program and Operational Programs Inspection Report 05200026/2024011 ML24130A2412024-05-13013 May 2024 Integrated Inspection Report 05200025/2024001 and 05200026/2024001 ML24127A2372024-05-0909 May 2024 Initial Test Program and Operational Programs Inspection Report 05200026/2024010 IR 05000424/20244032024-05-0101 May 2024 Cyber Security Inspection Report 05000424/2024403 and 05000425/2024403 Public IR 05000424/20240012024-04-23023 April 2024 –Integrated Inspection Report 05000424/2024001 and 05000425/2024001 IR 05000424/20230062024-02-28028 February 2024 Annual Assessment Letter for Vogtle Electric Generating Plant Units 1 and 2 - NRC Inspection Report 05000424-2023006 and 05000425-2023006 IR 05000424/20240102024-02-14014 February 2024 – Fire Protection Team Inspection Report 0500424/2024010 and 05000425/2024010 IR 05000202/20300042024-02-13013 February 2024 Integrated Inspection Report 052000250/2023004 and 05200026/2023004 IR 05000424/20230042024-02-0505 February 2024 Integrated Inspection Report 05000424-2023004 and 05000425-2023004 ML24032A0252024-02-0505 February 2024 NRC Initial Test Program and Operational Programs Integrated Inspection Report 05200026-2023009 ML24031A6102024-01-31031 January 2024 Cyber Security Inspection Report 05200026/2024401 - Public ML23312A3502023-11-14014 November 2023 – Integrated Inspection Report 05200026/2023003 ML23318A4582023-11-14014 November 2023 Integrated Inspection Report 05200025/2023003 IR 05000424/20234022023-11-0606 November 2023 – Security Baseline Inspection Report 05000424/2023402 and 05000425/2023402 IR 05000424/20230032023-10-27027 October 2023 Integrated Inspection Report 05000424/2023003 and 05000425/2023003 ML23254A2032023-09-13013 September 2023 – Initial Test Program and Operational Programs Inspection Report 05200025/2023013 IR 05000424/20230912023-09-0505 September 2023 Plan Units 1 and 2 - NRC Investigation Report 2-2022-006 and Notice of Violation - NRC Inspection Report 05000424/2023091 and 05000425/2023091 ML23234A3002023-09-0101 September 2023 NRC Integrated Inspection Report 05200026/2023003 IR 05000424/20230052023-08-29029 August 2023 Updated Inspection Plan for Vogtle Electric Generating Plant, Units 1 & 2 - Report 05000424/2023005 and 05000425/2023005 ML23223A0022023-08-14014 August 2023 Integrated Inspection Report 05200025/2023002 IR 05000424/20230112023-08-11011 August 2023 Biennial Problem Identification and Resolution Inspection Report 05000424/2023011 and 05000425/2023011 ML23215A0822023-08-0404 August 2023 (Vego), Unit 3 – Initial Test Program and Operational Programs Integrated 05200025/2023011 Inspection Report IR 05000424/20234012023-07-31031 July 2023 Security Baseline Inspection Report 05000424/2023401 and 05000425/2023401 (Cover Letter) ML23212B0612023-07-31031 July 2023 Security Baseline Inspection Report 05200025/2023401 ML23216A0962023-07-26026 July 2023 Document Request for Vogtle 1 & 2 RP Inspection, Report No. 05000424/2023003 and 05000425/2023003 IR 05000424/20230022023-07-24024 July 2023 Integrated Inspection Report 05000424/2023002 and 05000425/2023002 ML23198A3802023-07-19019 July 2023 NRC Integrated Inspection Report 05200026/2023002 ML23199A0892023-07-18018 July 2023 Initial Test Program and Operational Programs Integrated Inspection Report 05200026/2023007 IR 05000424/20233012023-06-30030 June 2023 – NRC Operator License Examination Report 05000424/2023301 and 05000425/2023301 ML23128A2932023-05-11011 May 2023 NRC Integrated Inspection Report 05200026/2023001 ML23129A0222023-05-10010 May 2023 Integrated Report 05200025/2023001 ML23128A3492023-05-0909 May 2023 – Initial Test Program and Operational Programs Integrated Inspection Report 05200026/2023006 ML23121A3202023-05-0404 May 2023 NRC Initial Test Program and Operational Programs Integrated Inspection Report 05200025/2023010 IR 05000424/20040252023-04-28028 April 2023 Public Meeting Summary - Vogtle Electric Generating Plant, Units 1, 2, 3, & 4 Docket No. 5000424, 5000425, 5200025, 5200026, Meeting Number 20230375 IR 05000424/20230012023-04-26026 April 2023 Integrated Inspection Report 05000424/2023001 and 05000425/2023001 IR 05000424/20230902023-03-30030 March 2023 NRC Inspection Report 05000424/2023090 and 05000425/2023090, and Investigation Report 2-2022-006; and Apparent Violation ML23083B3702023-03-24024 March 2023 Security Baseline Inspection Report 05200026/2023401 IR 05000424/20220062023-03-0101 March 2023 Annual Assessment Letter for Vogtle Electric Generating Plant Units 1 and 2, NRC Inspection Reports 05000424/2022006 and 05000425/2022006 ML23044A3902023-02-14014 February 2023 Integrated Inspection Report05200025 2022007 ML23040A0422023-02-0909 February 2023 NRC Initial Test Program and Operational Programs Integrated Inspection Report 05200025/2022008 2025-01-24
[Table view] Category:NRC-GENERATED
MONTHYEARIR 05000424/19990061999-10-0101 October 1999 Insp Repts 50-424/99-06 & 50-425/99-06 on 990725-0904. Violations Noted.Major Areas Inspected:Licensee Operations, Engineering,Maint & Plant Support IR 05000424/19990051999-08-16016 August 1999 Insp Repts 50-424/99-05 & 50-425/99-05 on 990620-0724.No Violations Noted.Major Areas Inspected:Opertions, Engineering,Maintenance & Plant Support.Results of Announced Insp by Security Inspector Also Encl IR 05000424/19990041999-07-15015 July 1999 Insp Repts 50-424/99-04 & 50-425/99-04 on 990502-0619. Non-cited Violations Noted.Major Areas Inspected:Operations, Engineering,Maintenance & Plant Support IR 05000424/19990031999-05-19019 May 1999 Insp Repts 50-424/99-03 & 50-425/99-03 on 990321-0501. Non-cited Violations Noted.Major Areas Inspected:Operations, Engineering,Maintenance & Plant Support IR 05000424/19990021999-04-15015 April 1999 Insp Repts 50-424/99-02 & 50-425/99-02 on 990214-0320. Violations Noted.Major Areas Inspected:Operations, Engineering,Maint & Plant Support IR 05000424/19990011999-03-0808 March 1999 Partially Withheld Insp Repts 50-424/99-01 & 50-425/99-01 on 990125-27 (Ref 10CFR73.21).Violations Noted.Major Areas Inspected:Area of Plant Support by Regional Safeguards Inspector & Select Personnel from NRR IR 05000424/19980101999-03-0303 March 1999 Insp Repts 50-424/98-10 & 50-425/98-10 on 981227-990213.No Violations Noted.Major Areas Inspected:Licensee Operations, Engineering,Maint & Plant Support.Rept Covers 7-wk Period of Insp & Insps in Area of Health Physica & EP IR 05000424/19980091999-01-20020 January 1999 Insp Repts 50-424/98-09 & 50-425/98-09 on 981115-1226.No Violations Noted.Major Areas Inspected:Licensee Operations, Engineering,Maint & Plant Support IR 05000424/19980081998-12-11011 December 1998 Insp Repts 50-424/98-08 & 50-425/98-08 on 980927-1114.No Violations Noted.Major Areas Inspected:Licensee Operations, Engineering,Maint & Plant Support IR 05000424/19980121998-11-0909 November 1998 Partially Withheld Insp Repts 50-424/98-12 & 50-425/98-12 on 981005-09 (Ref 10CFR73.21)Major Areas Inspected:Physical Security Program for Power Reactors IR 05000424/19980071998-10-15015 October 1998 Insp Repts 50-424/98-07 & 50-425/98-07 on 980816-0926. Violations Noted.Major Areas Inspected:Aspects of Licensee Operations,Engineering,Maint & Plant Support.Insp Also Addressed 980904 Reactor Trip IR 05000424/19980061998-09-10010 September 1998 Insp Repts 50-424/98-06 & 50-425/98-06 on 980628-0815.No Violations Noted.Major Areas Inspected:Aspects of Licensee Operations,Engineering,Maint & Plant Support IR 05000424/19980111998-07-31031 July 1998 Insp Repts 50-424/98-11 & 50-425/98-11 on 980622-26.No Violations Noted.Major Areas Inspected:Announced Insp Was Observation & Evaluation of Biennial Emergency Preparedness Exercise for Plant ML20236H4081998-06-15015 June 1998 Insp Repts 50-424/98-04 & 50-425/98-04 on 980419-0516. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000424/19970121998-02-23023 February 1998 Insp Repts 50-424/97-12 & 50-425/97-12 on 971214-980124.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000424/19970111998-01-12012 January 1998 Insp Repts 50-424/97-11 & 50-425/97-11 on 971102-1213. Violations Noted.Major Areas Inspected:Operations & Maint IR 05000424/19970071997-08-28028 August 1997 Insp Repts 50-424/97-07 & 50-425/97-07 on 970706-0802. Violations Noted.Major Areas Inspected:Licensee Operations, Engineering,Maint & Plant Support IR 05000424/19970081997-08-14014 August 1997 Insp Repts 50-424/97-08 & 50-425/97-08 on 970623-27. Deviations Noted.Major Areas Inspected:Qa in Operations, Maint,Engineering & Health Physics ML20198F8631997-08-0404 August 1997 Insp Repts 50-424/97-06 & 50-425/97-06 on 970601-0705. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support ML20141F7031997-06-24024 June 1997 Insp Repts 50-424/97-05 & 50-425/97-05 on 970427-0531. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support Re Scenario for off-hour Emergency Response Drill ML20140B4071997-05-21021 May 1997 Insp Repts 50-424/97-04 & 50-425/97-04 on 970316-0426. Violations Noted.Major Areas Inspected:Operations, Maintenance,Engineering & Plant Support & Emergency Preparedness Area ML20137X3811997-04-14014 April 1997 Integrated Insp Repts 50-424/97-01 & 50-425/97-01 on 970202- 0315.Violations Noted.Major Areas Inspected:Operations, Maint,Engineering & Plant Support ML20137T7111997-04-0404 April 1997 Insp Repts 50-424/97-03 & 50-425/97-03 on 970303-07. Violations Noted.Major Areas Inspected:Fitness for Duty & Physical Security Program for Power Reactors ML20137U6741997-03-27027 March 1997 Insp Repts 50-424/97-02 & 50-425/97-02 on 970210-0307.No Violations Noted.Major Areas Inspected:Plant Support,Solid Radwaste,Radioactive Liquid & Gaseous Waste & Radioactive Matl Transportation Programs ML20135C8511997-02-24024 February 1997 Insp Repts 50-424/96-14 & 50-425/96-14 on 961222-970201. Violations Noted.Major Areas Inspected:Aspects of Licensee Operations,Engineering,Maintenance & Plant Support ML20134H1601997-01-17017 January 1997 Insp Repts 50-424/96-12 & 50-425/96-12 on 961110-1221. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000424/19960131997-01-0606 January 1997 Insp Repts 50-424/96-13 & 50-425/96-13 on 961118-22. Weakness Noted.Major Areas Inspected:Observation & Evaluation of Biennial Emergency Preparedness Exercise IR 05000424/19960111996-12-0505 December 1996 Insp Repts 50-424/96-11 & 50-425/96-11 on 960929-1109. Violations Noted.Major Areas Inspected:Operations, Engineering,Maintenance & Plant Support ML20134F0141996-10-28028 October 1996 Insp Repts 50-424/96-10 & 50-425/96-10 on 960818-0928. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000424/19960091996-09-16016 September 1996 Insp Repts 50-424/96-09 & 50-425/96-09 on 960707-0817. Violations Noted.Major Areas Inspected:Engineering,Maint & Plant Support IR 05000424/19930271994-01-11011 January 1994 Insp Repts 50-424/93-27 & 50-425/93-27 on 931121-1218.One Noncited Violation Identified.Major Areas Inspected:Plant Operations,Surveillance,Maint,Engineered Safety Sys Walkdown & Evaluation of Licensee self-assessment IR 05000424/19930181993-12-22022 December 1993 Insp Repts 50-424/93-18 & 50-425/93-18 on 931129-1203. Violations Noted.Major Areas Inspected:Licensed Operator Requalification Training ML20059B5951993-12-13013 December 1993 Insp Repts 50-424/93-26 & 50-425/93-26 on 931024-1120. Violations Noted.Major Areas Inspected:Plant Operations, Surveillance,Maintenance,Fire Protection & Followup of Open Items IR 05000424/19930231993-11-17017 November 1993 Insp Repts 50-424/93-23 & 50-425/93-23 on 930919-1023. Violations Noted.Major Areas Inspected:Plant Operations, Surveillance,Complex Surveillance,Maintenance,Mid Loop Reduced Inventory Activities & Modifications IR 05000424/19930241993-10-27027 October 1993 Insp Repts 50-424/93-24 & 50-425/93-24 on 931004-08.No Violations Noted.Major Areas Inspected:Unit 2 Isi,Review of Radiographic Film & EC ET Exam of SG Tubes IR 05000424/19930221993-10-15015 October 1993 Insp Repts 50-424/93-22 & 50-425/93-22 on 930920-24.No Violations Noted.Major Areas Inspected:Occupational Radiation Safety,Training & Qualification,Exposure Control & Maintaining Exposures ALARA IR 05000424/19930211993-10-0707 October 1993 Insp Repts 50-424/93-21 & 50-425/93-21 on 930822-0918.No Violations Noted.Major Areas Inspected:Plant Operations, Surveillance,Maint,Esf Sys Walkdown,Installation & Testing of Mods & Followup of Open Items IR 05000424/19930201993-09-30030 September 1993 Insp Repts 50-424/93-20 & 50-425/93-20 on 930830-0903. Violations Noted.Major Areas Inspected:Radiation Protection Program Activities Associated W/Llrw Processing,Temporary Storage,Transportation & Offsite Dose Assessment IR 05000424/19930171993-09-0707 September 1993 Insp Repts 50-424/93-17 & 50-425/93-17 on 930801-21.Noncited Violation Noted.Major Areas Inspected:Plant Operations, Surveillance,Maintenance,Evaluation of Licensee self-assessment & Employee Concerns Program ML20056G8491993-08-23023 August 1993 Insp Repts 50-424/93-16 & 50-425/93-16 on Stated Date. Violations Noted.Major Areas Inspected:Plant Operations, Surveillance,Maint & Fire Protection IR 05000424/19930191993-08-21021 August 1993 Insp Repts 50-424/93-19 & 50-425/93-19 on 930802-06.No Violations or Deviations Noted.Major Areas Inspected: Observation & Evaluation of Annual Emergency Preparedness Exercise IR 05000424/19930111993-07-21021 July 1993 Insp Repts 50-424/93-11 & 50-425/93-11 on 930510-0611. Violations Noted.Major Areas Inspected:Capacity of Eds to Perform Intended Functions & Adequacy of Engineering & Technical Support Provided to Maintain Eds Operability IR 05000424/19930141993-07-14014 July 1993 Insp Repts 50-424/93-14 & 50-425/93-14 on 930530-0626. Violations Noted.Major Areas Inspected:Plant Operations, Surveillance,Maint & Followup of Open Items IR 05000424/19930151993-07-12012 July 1993 Insp Repts 50-424/93-15 & 50-425/93-15 on 930614-18.No Violations or Deviations Noted.Major Areas Inspected: Occupational Radiation Safety & Included Exam of Organization & Staffing IR 05000424/19930131993-06-15015 June 1993 Insp Repts 50-424/93-13 & 50-425/93-13 on 930502-29. Violations Noted But Not Cited.Major Areas Inspected:Plant Operations,Surveillance,Maintenance,Esf & Fire Protection IR 05000424/19930121993-06-0303 June 1993 Partially Withheld Insp Repts 50-424/93-12 & 50-425/93-12 on 930510-14 (Ref 10CFR73.21).Noncited Violation Identified. Major Areas Inspected:Mgt Support,Security Program Plans & Audits IR 05000424/19930101993-05-26026 May 1993 Insp Repts 50-424/93-10 & 50-425/93-10 on 930510-14.No Violations Noted.Major Areas Inspected:Startup Testing & Power Escalation of Unit 1 & Routine Core Performance Surveillance of Unit 2 ML20036C3551993-05-25025 May 1993 Insp Repts 50-424/93-07 & 50-425/93-07 on 930328-0501. Violations Noted.Major Areas Inspected:Plant Operations, Surveillance,Maint,Plant Mods,Refueling Activities,Review of Overtime Records & Followup of Open Items ML20044G2231993-05-14014 May 1993 Insp Repts 50-424/93-09 & 50-425/93-09 on 930418-0508. Violations Noted.Major Areas Inspected:Safety Injection Which Occurred When Control Room Operators Shifted Configuration of Unit 1 a Train Solid State Protection Sys IR 05000424/19930081993-05-11011 May 1993 Insp Repts 50-424/93-08 & 50-425/93-08 on 930419-23.No Violations or Deviations Noted.Major Areas Inspected: Fire Protection/Prevention Implementation Program & Followup of Previous Events 1999-08-16
[Table view] Category:TEXT-INSPECTION & AUDIT & I&E CIRCULARS
MONTHYEARIR 05000424/19990061999-10-0101 October 1999 Insp Repts 50-424/99-06 & 50-425/99-06 on 990725-0904. Violations Noted.Major Areas Inspected:Licensee Operations, Engineering,Maint & Plant Support IR 05000424/19990051999-08-16016 August 1999 Insp Repts 50-424/99-05 & 50-425/99-05 on 990620-0724.No Violations Noted.Major Areas Inspected:Opertions, Engineering,Maintenance & Plant Support.Results of Announced Insp by Security Inspector Also Encl IR 05000424/19990041999-07-15015 July 1999 Insp Repts 50-424/99-04 & 50-425/99-04 on 990502-0619. Non-cited Violations Noted.Major Areas Inspected:Operations, Engineering,Maintenance & Plant Support IR 05000424/19990031999-05-19019 May 1999 Insp Repts 50-424/99-03 & 50-425/99-03 on 990321-0501. Non-cited Violations Noted.Major Areas Inspected:Operations, Engineering,Maintenance & Plant Support IR 05000424/19990021999-04-15015 April 1999 Insp Repts 50-424/99-02 & 50-425/99-02 on 990214-0320. Violations Noted.Major Areas Inspected:Operations, Engineering,Maint & Plant Support IR 05000424/19990011999-03-0808 March 1999 Partially Withheld Insp Repts 50-424/99-01 & 50-425/99-01 on 990125-27 (Ref 10CFR73.21).Violations Noted.Major Areas Inspected:Area of Plant Support by Regional Safeguards Inspector & Select Personnel from NRR ML20207L8511999-03-0808 March 1999 Notice of Violation from Insp on 990125-27.Violation Noted: on Numerous Occasions from Mar 1997 to Oct 1998,select Response Force Officers Were Posted in Locations That Would Not Permit Them to Interpose Themselves Between Intruder IR 05000424/19980101999-03-0303 March 1999 Insp Repts 50-424/98-10 & 50-425/98-10 on 981227-990213.No Violations Noted.Major Areas Inspected:Licensee Operations, Engineering,Maint & Plant Support.Rept Covers 7-wk Period of Insp & Insps in Area of Health Physica & EP IR 05000424/19980091999-01-20020 January 1999 Insp Repts 50-424/98-09 & 50-425/98-09 on 981115-1226.No Violations Noted.Major Areas Inspected:Licensee Operations, Engineering,Maint & Plant Support IR 05000424/19980081998-12-11011 December 1998 Insp Repts 50-424/98-08 & 50-425/98-08 on 980927-1114.No Violations Noted.Major Areas Inspected:Licensee Operations, Engineering,Maint & Plant Support IR 05000424/19980121998-11-0909 November 1998 Partially Withheld Insp Repts 50-424/98-12 & 50-425/98-12 on 981005-09 (Ref 10CFR73.21)Major Areas Inspected:Physical Security Program for Power Reactors ML20155A7621998-10-15015 October 1998 Notice of Violation from Insp on 980816-0926.Violation Noted:On 980824,licensee Failed to Adequately Establish Sufficient Procedural Control for Demolition of Concrete Missile Barrier IR 05000424/19980071998-10-15015 October 1998 Insp Repts 50-424/98-07 & 50-425/98-07 on 980816-0926. Violations Noted.Major Areas Inspected:Aspects of Licensee Operations,Engineering,Maint & Plant Support.Insp Also Addressed 980904 Reactor Trip ML20154C5131998-09-10010 September 1998 Notice of Violation from Insp on 980628-0815.Violation Noted:Corrective Actions Taken in Response to Violations Associated with Entry Into TS LCO for Maint & Surveillances Activities Were Inadequate to Preclude Repetition IR 05000424/19980061998-09-10010 September 1998 Insp Repts 50-424/98-06 & 50-425/98-06 on 980628-0815.No Violations Noted.Major Areas Inspected:Aspects of Licensee Operations,Engineering,Maint & Plant Support IR 05000424/19980111998-07-31031 July 1998 Insp Repts 50-424/98-11 & 50-425/98-11 on 980622-26.No Violations Noted.Major Areas Inspected:Announced Insp Was Observation & Evaluation of Biennial Emergency Preparedness Exercise for Plant ML20236T5871998-07-23023 July 1998 Notice of Violation from Insp on 980517-0627.Violation Noted:On 980419,Unit 2 Entered Mode 2 W/O Meeting LCO of TS 3.3.2,which Requires Two Trains of Turbine Trip Function to Be Operable Prior to Entering Mode 2 ML20236H3971998-06-15015 June 1998 Notice of Violations from Insp on 980419-0516.Violations Noted:On 980415,upon Identification That 1 of 3 Letdown Orifice Isolation Valves Would Not Open,Unit 2 Uss Proceeded to Allow Operation of Unit in Water Solid Conditions ML20236H4081998-06-15015 June 1998 Insp Repts 50-424/98-04 & 50-425/98-04 on 980419-0516. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support PNO-II-98-032, on 980609,electrical Fault on 2C Condensate Pump Motor Caused Loss of 1NAB 13.8KV Bus.Fault Also Caused Main Generator Trip,Turbine Trip & Reactor Trip.Reactor Coolant Pump 2 & 4 Lost Power Because of Bus Loss1998-06-10010 June 1998 PNO-II-98-032:on 980609,electrical Fault on 2C Condensate Pump Motor Caused Loss of 1NAB 13.8KV Bus.Fault Also Caused Main Generator Trip,Turbine Trip & Reactor Trip.Reactor Coolant Pump 2 & 4 Lost Power Because of Bus Loss ML20247K7531998-05-15015 May 1998 Notice of Violation from Insp on 980308-0418.Violation Noted:On 980401,Procedure PT-V-605,was Not Properly Implemented,In That,Liquid Penetrant pre-exam Cleaning for Safety Injection Sys Weld 21204-122-6 Was Inadequate ML20216J6611998-04-0202 April 1998 Notice of Violation from Insp on 980125-0307.Violation Noted:On 980219,Unit 2 Shift Supervisor Authorized Maint on Control Room Emergency Filtration Sys Train B W/O Recognizing Work Would Render Train Inoperable PNO-II-98-017, on 980320,female Contract Worker Found Unconscious at Bottom of man-lift Station in Turbine Bldg. Plant First Aid Team Responded & Ambulance Was Called. Injured Person Transported to Hosp & Pronounced Dead1998-03-20020 March 1998 PNO-II-98-017:on 980320,female Contract Worker Found Unconscious at Bottom of man-lift Station in Turbine Bldg. Plant First Aid Team Responded & Ambulance Was Called. Injured Person Transported to Hosp & Pronounced Dead IR 05000424/19970121998-02-23023 February 1998 Insp Repts 50-424/97-12 & 50-425/97-12 on 971214-980124.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support ML20198M3401998-01-12012 January 1998 Notice of Violation from Insp on 971102-1213.Violation Noted:Since Initial Startup of Both Units 1 & 2,procedures 14420-1/2 & 14421-1/2 Inadequate ML20198M3681998-01-12012 January 1998 Notice of Deviation from Insp on 971102-1213.Deviation Noted:Since Initial Startup of Both Units 1 & 2,licensee Failed to Perform 18-month Surveillance Testing on Reactor Coolant Pump 125V Direct Current non-1E Control Breakers IR 05000424/19970111998-01-12012 January 1998 Insp Repts 50-424/97-11 & 50-425/97-11 on 971102-1213. Violations Noted.Major Areas Inspected:Operations & Maint ML20202E1971997-11-26026 November 1997 Notice of Violation from Insp on 970921-1101.Violation Noted:On 971003,10 Unit Heater Breakers on MCC 1NBG Were Found Open & Not Tagged ML20212F3471997-10-20020 October 1997 Notice of Violation from Insp on 970803-0920.Violations noted:54 Fire Extinguishers W/Insp Sticker ,were Issued Between 970730 & 0815 & Did Not Meet Insp Criteria of Procedure 92020-C IR 05000424/19970991997-09-15015 September 1997 SALP Repts 50-424/97-99 & 50-425/97-99 for Vogtle Electric Generating Plant for 960128-970802 IR 05000424/19970071997-08-28028 August 1997 Insp Repts 50-424/97-07 & 50-425/97-07 on 970706-0802. Violations Noted.Major Areas Inspected:Licensee Operations, Engineering,Maint & Plant Support ML20210S0551997-08-28028 August 1997 Notice of Violation from Insp on 970706-0802.Violation Noted:On 970708,during Maint on Shaft Seal in Unit 1 Personnel Airlock,Licensee Failed to Document Entry Into Appropriate Action Condition for TS LCO 3.6.2 IR 05000424/19970081997-08-14014 August 1997 Insp Repts 50-424/97-08 & 50-425/97-08 on 970623-27. Deviations Noted.Major Areas Inspected:Qa in Operations, Maint,Engineering & Health Physics ML20210N6521997-08-14014 August 1997 Notice of Deviation from Insp on 970623-27.Deviation Noted: Incidents or Events Associated W/Ufsar Section 17.2.1.1.1.F & H Were Not Reviewed on 961218 & 970430 Srb Meetings ML20198F8631997-08-0404 August 1997 Insp Repts 50-424/97-06 & 50-425/97-06 on 970601-0705. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support ML20198F8551997-08-0404 August 1997 Notice of Violation from Insp on 970601-0705.Violation Noted:Six Individuals Reported for Duty to ERFs & Failed to Complete sign-in Sheets on 970527,during Performance of Recall Emergency Drill ML20141F7031997-06-24024 June 1997 Insp Repts 50-424/97-05 & 50-425/97-05 on 970427-0531. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support Re Scenario for off-hour Emergency Response Drill ML20141F6971997-06-24024 June 1997 Notice of Violation from Insp on 970427-0531.Violation Noted:Time Between Performances of Procedure 29100-C,for Visual Insp of Fire Extinguishers & Fire Hose Stations, Exceeded 31 Days ML20140B3951997-05-21021 May 1997 Notice of Violation from Insp on 970316-0426.Violation Noted:Between 970329 & 0404,numerous Examples of Unattended & Unevaluated Debris Have Been Identified & Eight EPIP Revs Had Not Been Distributed ML20140B4071997-05-21021 May 1997 Insp Repts 50-424/97-04 & 50-425/97-04 on 970316-0426. Violations Noted.Major Areas Inspected:Operations, Maintenance,Engineering & Plant Support & Emergency Preparedness Area ML20138J4161997-04-25025 April 1997 Notice of Violation from Insp on 970210-0307.Violation Noted:Licensee Offered for Transportation by exclusive-use, Closed Transport Vehicle,Package Which Arrived Having Max Surface Radiation Levels Exceeding 10 Msv/Hr ML20137X3811997-04-14014 April 1997 Integrated Insp Repts 50-424/97-01 & 50-425/97-01 on 970202- 0315.Violations Noted.Major Areas Inspected:Operations, Maint,Engineering & Plant Support ML20137X3751997-04-14014 April 1997 Notice of Violation from Insp on 970202-0315.Violation Noted:Positions of Valves 2-1302-U4-180 - 185 Not Verified Every 31 Days as Required ML20137T7111997-04-0404 April 1997 Insp Repts 50-424/97-03 & 50-425/97-03 on 970303-07. Violations Noted.Major Areas Inspected:Fitness for Duty & Physical Security Program for Power Reactors ML20137T6731997-04-0404 April 1997 Notice of Violation from Insp on 970303-07.Violation Noted:Plant Security Response Plan Rev 3 Phase 2 Defined Deployment Strategy That Allowed CAS to Be Left Unmanned During Contingency ML20137U6741997-03-27027 March 1997 Insp Repts 50-424/97-02 & 50-425/97-02 on 970210-0307.No Violations Noted.Major Areas Inspected:Plant Support,Solid Radwaste,Radioactive Liquid & Gaseous Waste & Radioactive Matl Transportation Programs ML20137T0521997-03-25025 March 1997 Notice of Violation from Insp on 961222-970201.Violations Noted:Licensee Failed to Implement Procedures 11429-1 & 11429-2 in That Breakers Were Improperly Positioned ML20135C8511997-02-24024 February 1997 Insp Repts 50-424/96-14 & 50-425/96-14 on 961222-970201. Violations Noted.Major Areas Inspected:Aspects of Licensee Operations,Engineering,Maintenance & Plant Support ML20134H1391997-01-17017 January 1997 Notice of Violation from Insp on 961110-1221.Violation Noted:On 961205,measures Assuring That Nonconformances Were Promptly Identified & Corrected Were Not Established as Evidence by Insp of Safety Related IE 480 Volt ML20134H1601997-01-17017 January 1997 Insp Repts 50-424/96-12 & 50-425/96-12 on 961110-1221. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support 1999-08-16
[Table view] |
Inspection Report - Vogtle - 1999002 |
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U. S. NUCLEAR REGULATORY COMMISSION (NRC)
REGIONll I
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Docket Nos. 50-424 and 50-425 License Nos. NPF-68 and NPF-81 l
Report No:
50-424/99-02 and 50-425/99-02 i
Licensee:
Southern Nuclear Operating Company, Inc.
Facility:
Vogtle Electric Generating Plant Units 1 and 2 Location:
7821 River Road Waynesboro, GA 30830 l
Dates:
February 14 through March 20,1999 Inspectors:
J. Zeiler, Senior Resident inspector K. O'Donohue, Resident inspector W. Kieinsorge, Maintenance Inspector (Section M2.1)
D. Forbes, Radiation Specialist (Section R1)
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Approved by: P. Skinner, Chief
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Reactor Projects Branch 2
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Division of Reactor Projects l
Enclosure
$4ko k
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EXECUTIVE SUMMARY Vogtle Electric Generating Plant Units 1 and 2 NRC Inspection Report 50-424/99-02 and 50-425/99-02 This integrated inspection included aspects of licensee operations, engineering, maintenance, and plant support. The report covers a five-week period of resident inspection and inspections in the area of Maintenance and Health Physics by region based inspectors.
Operations In general, the conduct of operations during major evolutions of the Unit 1 refueling
outage 1R8 was satisfactory. Management was involved in the daily activities, especially various contingency plans which included management walkdowns. Good controls and control room attention were noted when the unit entered a planned fueled midloop condition (Section 01.1).
Operator actions to initiate a manual reactor trip of Unit 2 were appropriate following the
inadvertent closure of a main feedwater isolation valve. The failure to follow the independent verification procedure resulting in the inadvertent closure of the Unit 2 loop 3 main feedwater isolation valve was identified as a violation of 10 CFR 50, Appendix B, Criterion V, Instructions, Procedures, and Drawings (Section O1.3).
e Improper feedwater heater level maintenance and non-conservative calibration of feedwater flow computer input resulted in two examples where reactor core thermal power violated license condition 2(C). During one instance, the magnitude and duration above the licensed thermal power limit was caused by operator deficiencies in following abnormal operating procedures (Section 08.1).
Enaineerina The licensee's failure to identify the Unit 2 sequencer as inoperable in a timely manner e
resulted in a violation of Technical Specifications (TS) 3.3.2 (Section E8.1).
Report Details
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Summary of Plant Status Unit 1 operated at full power until February 14,1999, at which time the licensee commenced a coast down for the eighth refueling outage (1R8). On February 27, a shutdown to begin 1R0 was initiated from 87 percent power. At 18.5 percent power, a manual reactor trip was initiated due to non-conservative Intermediate Range Nuclear instrumentation readings. At the end of the inspection period, the unit was in Mode 5 with preparations for Mode 4 in progress.
Unit 2 operated at full power until February 19, at which time the licensee commenced a reduction in power to 28 percent in order to take the turbine-generator offline to replace a generator stator cooling flow strainer. On February 20, the generator was connected to the grid and the unit returned to 100 percent power on February 21. On March 2, a manual reactor trip was initiated following the inadvertent closure of a main feedwater isolation valve due to a personnel error installing a Unit 1 outage clearance. Following corrective actions, a reactor startup was initiated and full power operation was attained on March 4.
1. Operations
Conduct of Operations 01.1 General Conduct of Operations Durina Unit 1 Refuelina Outaae 1R8 (71707)
The inspectors conducted frequent reviews of ongoing refueling outage activities.
These activities included the unit shutdown and entry into Modes 4,5 and 6. In addition, core offload, fuel assembly sipping, core reload, core verification, and re-entry into Mode 5 were reviewed.
The inspectors noted management involvement in the daily activities. Pre-job briefings were performed consistently, frequently led by a manager. When the unit entered a planned fueled midloop condition, the licensee limited other outage activities to ensure that operational focus remained on the midloop condition. The inspectors also noted management involvement with the various contingency plans developed for periods of high shutdown risk activities and that the contingency plans of ten included management walkdowns. The inspectors concluded that control room performance was enhanced due to the level of management involvement.
O1.2 Unit 1 Manual Reactor Trio durina Shutdown for 1R8 a.
Inspection Scoce (71707) ( 93702)
The inspectors reviewed the manua' reactor trip that was initiated during the Unit 1 shutdown to begin refueling outage 1R8 b.
Observations and Findinas On February 27, Unit 1 was being shutdown to begin refueling outage 1R8. As power was reduced, the operators noted that the intermediate range nuclear instrurnentation was reading high in comparison to the power range instrumentation. A concern was j
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raised that the intermediate range high flux trip (25 percent) may not reset before the Power Range (P-10) reset setpoint occurred which would automatically unblock the intermediate range channei trips. After discussions with management, a decision was made to manually trip the reactor. At 11:40 p.m., following an evolution pre-briefing, the reactor was tripped at 18.5 percent power. Post-trip plant response was normal with no significant complications identified.
The inspectors reviewed the post-event and sequence of events logs and noted no significan. abnormalities. The inspectors witnessed the conduct of the event review team meetings and concluded that these activities were appropriately performed. The I
licensee determined that the intermediate range instrumentation channels were working properly and the higher indication at end of core life than at beginning of core life for a given power level was an expected phenomenon. A calibration is generally not l
l performed on the intermediate channels during the operating cycle to account for the power distribution profile changes that result in higher indicated flux levels toward end of life reactor operation. During the shutdown for refueling outage 2R6, a similar overlap concern was identified Reactor engineering personnel were aware of the potential for inadequate intermediate to power range instrument overlap.
With the installation of Gamma Metrics Neutron Flux Monitoring System during this outage, the intermediate channels can be adjusted during the operating cycle to account for these changes. During the upcoming Unit 2 shutdown for refueling outage 2R7, the licensee plans to adjust the intermediate range channels, if necessary, prior to initiation of the shutdown to ensure that a similar condition does not occur.
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Conclusions The inspectors concluded that the decision to manually trip the unit was prudent.
Although the licensee was aware of the potential for inadequate overlap between the immediate range and power range instruments, no calibrations were performed to preclude this potential overlap condition.
01.3 Unit 2 Manual Reactor Trio Due to inadvertent Closure of a Main Feedwater Isolation Valve a.
Inspection Scope (71707)(93702)
The inspectors reviewed the circumstances for a Unit 2 manual reactor trip on March 2.
b.
Observations and Findinas A manual reactor trip of Unit 2 was initiated following the inadvertent closure of the loop 3 main feedwater isolation valve (MFIV). The plant response to the trip was normal with no significant complications identified.
The MFIV c'osed when two plant equipment operators (PEOs) erroneously remosed control power fuses to the Unit 2 loop 3 MFIV instead of the intended Unit 1 valve. The inspectors reviewed clearance 19915714 documentation for removing the Unit 1 MFIV from service and determined that it was clear and precise with respect to specific
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component identification and required actions. The inspectors also determined there was no indication of ambiguity in the instructions provided to the PEOs regarding which unit was to be affected. The work control supervisor had directed the use of a second qualified person to verify the proper implementation of this clearance. The licensee determined that the root cause of the error was poor self-checking and verification by the PEOs.
The licensee planned to implement several corrective actions which included briefings I
on the self-verification process, lessons learned training on the event in licensed and l
non-:! censed operator classes, a plant evaluation to identify areas and processes where l
similar wrong unit human performance errors could occur, revise the concurrent l
verification policy to require 3-way verbalization of complete equipment tag numbers, and require operations and maintenance management to increase field observation of activities to reinforce management expectations on proper self-verification.
l The inspectors reviewed procedure 00308-C, Verification Policy, Revision 11, which provides the methods for verifying correct performance of activities that affect the alignment of safety-related components. Section 4.2.2 prescribed the performance of concurrent verification and required that the " positioner" and " verifier" must independently read the clearance and correctly identify the component to be manipulated. Contrary to the requirements of procedure 00308-C, the PEOs failed to identify the correct MFIV fuses on Unit 1 and erroneously pulled the Unit 2 MFIV fuses
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resulting in the manual trip. The inspectors determined that the failure to follow i
procedure 00308-C constituted a violation of 10 CFR 50, Appendix B, Criterion V, I
instructions, Procedures, and Drawings. This Severity Level IV violation is being treated l
as a Non-Cited Violation (NCV) 50-425/99-02-01, " Failure to Follow Verification I
Procedure Results in MFIV Closure and Manual Reactor Trip," consistent with Appendix
C of the NRC Enforcement Policy. This violation is in the licensee's corrective action program as Event Report 2-99-001.
c.
Conclusions The inspectors concluded that the operator's action to initiate a manual reactor trip of Unit 2 was appmpriate following the inadvertent closure of the loop 3 main feedwater isolation valve. The failure of PEOs to properly verify that they were on the correct
equipment prior to removing fuses to the Unit 2 MFIV was identified as a NCV.
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Miscellaneous Operations issues (92901)
08.1 (Closed) Unresolved item (URI) 50-424/98-10-01: Review of Unit 1 Overoower Event The inspectors reviewed Event Report 1-98-001 which documented the licensee's investigation of this event. The direct cause of the initiating event was attributed to online calibration of the 4B feedwater heater level transmitter under maintenance work l
order (MWO) 19801128. During the work planning for this MWO, work planners l
identified that the 4A and 4B feedwater heaters did not allow bypassing of the controlling level transmitter while it was being calibrated. However, work planners failed to ensure that these feedwater heater level transmitters were removed from the MWO. When the technicians removed the 4B feedwater heater level transmitter from service, a false high
water level signal was generated csusing the 4B feedwater heater to automatica'ly isolate. Neither the technicians performing the work, nor operations personnel wr.c authorized the work, recognized the potential impact on 48 feedwater level control. The licensee determined that this, in part, was attributed to inadequate maintenance and control room briefings.
The licensee's planned corrective actions included briefing all work planners on the event, emphasizing the need for thorough work order reviews of online work, review of lessons learned from this event, and conduct pre-briefing seminars to emphasize the expectations of material covered in these briefings.
When the 4B feedwater heater isolated, the reactor operator reduced turbine load about 4 percent and inserted control rods several steps in anticipation of the expected reactor power increase from the colder feedwater. After these initial actions, the operating crew did not reduce reactor power by any substantial amount for about 50 minutes. The licensee identified numerous factors that contributed to the operators' response. These included the operators' failure to recognize that lower reactor coolant system (RCS)
temperature caused indicated Power Range Nuclear instrument (PRNI) readings to be less than actual reactor power; ineffective crew communications between the Shif t Supervisor (SS) and Unit Shift Supervisor (USS) which resulted in a 30 minute delay in using RCS loop differential temperature to control reactor power; Abnormal Operating Procedure (AOP) 18016-C, Condensate and Feedwater Malfunction, Revision 11, was confusing regarding the power indication to monitor since thermal power indication was inaccurate and there were no cautions or warnings that the PRNis will not be accurate when RCS tempera'ure was below normal; and the lessons learned from a Unit 1
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overpower transient on February 25,1997, were not effective in preventing this event.
The licensee identified numerous corrective actions to enhance operator response.
Some of the major corrective actions included training on lessons learned and operator instrymentation and secondary response knowledge deficiencies with all operators in reos "kation Mning, management and supervisory monitoring of effective 3-way comniunications in the control room, enhance AOP 18016-C for more effective response to this type of event, evaluate and improve if necessary the simulator response to feedwater heater transients, and add more simulator training on loss of feedwater heating transients.
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License Condition 2(C) of the Vogtle Unit 1 Facility Operating License NPF-68, authorizes the licensee to operate the unit at reactor core power levels not in excess of 3565 megawatts thermal (100 percent). The inspectors determined that this issue
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constituted a violation of License Condition 2(C), in that, between 11:32 p.m. and 12:26
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a.m., on December 29,1998, reactor core rated thermal power exceeded 3565
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megawatts thermal following a feedwater temperature transient that was initiated by improper feedwater heater level transmitter maintenance. Reactor power peaked at 103.85 percent power and frequently exceeded 102 percent power during the transient period. This Severity Level IV violation was identified as an example of NCV 50-424, 425/99-02-02," Licensed Power Limit Exceeded Due to improper Maintenance Activities
- Multiple Examples, consistent with Appendix C of the NRC Enforcement Policy. This violation is identified in the licensee's corrective action program as Event Report 1-98-00.
ll. Maintenance M2 Maintenance and Material Condition of Facilities and Equipment M2.1 inservice inspection (ISI) (73753)
The inspectors evaluated the licensee's ISI program and the ISI program's implementation. The inspectors concluded that the procedures reviewed were concise l
and well written. Inservice examinations observed or reviewed were conducted in
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accordance with p,operly approved procedures, by qualified examiners using calibrated equipment and certified materials.
M8 Miscellaneous Maintenance issues (92700) (92902)
M8.1 (Closed) Licensee Event Report (LER) 50-425/98-10-00: Reactor Overpower Event Followina Instrument Calibration This LER involved the non-conservative calibration of a feedv.ater flow computer point input to the reactor power calculation. Following the calibration activity, reactor power was increased slightly to the new indicated 100 percent power level. The condition existed for five days. The licensee determined that reactor power had actually operated at an average power of 100.12 percent during the five day period in violation of Facility Operating License NPF-81, Section 2C, which requires that the licensed reactor thermal power limit not be exceeded. This violation of NRC regulatory requirements was identified as an example of NCV 50-424,425/99-02-02," Licensed Power Limit Exceeded Due to Improper Maintenance Activities - Multiple examples," consistent with Appendix C of the NRC Enforcement Policy. This violation is in the licensee's corrective actions program as LER 50-425/98-10-00.
111. Enaineerina E8 Miscellaneous Engineering issues (92700)(92903)
E8.1 (Closed) LER 50-425/98-09-00: Seauencer inoperability Leads to Operation Outside of Technical Specification The Inspectors reviewed the LER, and condition reports (CRs) 219980557 and 219980559. The inspectors noted that the LER stated the cause of the event was ".an inability to interpret the initial conditions that caused the alarm and their impact on sequencer operability." Because neither the LER nor the CRs included additional training, the inspectors questioned the adequacy of the corrective actions. Interviews with operations personnel revealed that system engineers were assumed to be experts on their assigned systems. Therefore, the system ec,gineer assigned to the Engineered Safety Features Actuation System (ESFAS) soquencer was assumed to have detailed knowledge about the operation of the ESFAS sequencer. However, the inspectors determined that the ESFAS system engineers had only received general training provideu to all system engineers and operators on the operation of the ESFAS sequencer. As a result of insufficient knowledge or training, the system engineer provided incorrect information which operations personnel used to determine that the
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personnel used to determine that the ESFAS sequencer was operable. The licensee revised CR 219980557 to include sequencer training for the system engineers.
TS 3.3.2, Condition C, required that the inoperable ESFAS train be restored to operable status in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or place the unit in Mode 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and be in Mode 5 within 42 hours4.861111e-4 days <br />0.0117 hours <br />6.944444e-5 weeks <br />1.5981e-5 months <br />. Since Train B ESFAS Sequencer was r ot returned to operable status within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> nor the unit placed in Mode 3 within twelve hours, Unit 2 was operated in a condition prohibited by Technical Specifications. This Severity Level IV violation is being treated as NCV 50-425/99-02-03, " Sequencer inoperability Leads to Operation Outside f
of Technical Specifications," consistent with Appendix C of the NRC Enforcement Policy.
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This violation was in the licensee's corrective action program as LER 50-425/98-09-00 and CR 219980557.
IV. Plant Support R1 Radiological Protection and Chemistry (RP&C) Controls R1.1 Tour of Radioloaical Protected Areas (83750)
During tours of the Radiological Control Area (RCA), the inspectors reviewed saey data and observed activities in progress. Radiological surveys reviewed were well documented. The licensee had effectively posted radiological areas and radioactive material observed was labeled as required. Locked High Radiation Aieas were controlled as required by licensee procedures. Calibrations for "in use" direct radiation instrumentation, frisking monitcrs, whole body counters, and air sampler instrumentation were current for those instruments observed.
Selected Radiation Work Permits (RWPs) were reviewed. The inspectors noted that appropriate protective clothing arW dosimetry were required. During plant tours adherence of workers to the RWP requirements was verified. The inspectors noted efforts to reduce personnel contaminations during the Unit 1 outage had been aggressive. As of March 12,1999, the licensee had documented approximately 30 Personnel Contamination Reports.
The inspectors reviewed and discussed with the licensee representatives the program for testing and qualifying breathing air as Grade D. Breathing air met Grade D or better quality requirements. All respiratory protection equipment observed during facility tours was being maintained in a satisfac;ory condition.
R1.2 Occupational Radiation Exposure Control Proaram (83750)
The inspectors reviewed the licensee's implementation of radiation protection principles to achieve occupational doses and doses to members of the public As Low As Reasonably Achievable (ALARA).
The inspectors review of the licensee's ALARA program determined that the !!censee had established an aggressive Unit 1 outage goal of 114 person-rem. The i!:ensee had tracked and trended outage exposures for purposes of future outage pluning. Outage maintenance briefings observed focused on dose reduction efforts and contamination
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control practices. The inspectors also observed the effective use of communication equipment se,h as microphones, cell phones, and camera coverage of containment and refueling floor work to minimize worker exposures. Health physics personnei debriefed workers to incorporate lessons learned into the ALARA program and the ALARA suggestion program had resulted in ALARA program improvements being implemented.
The inspectors noted that collective dose continued to trend downward based on these ALARA initiatives. The inspectors concluded that the ALARA program continued to be effective in controlling overall collective dose. All personnel radiation exposures during 1999 to date were below regulatory limits.
V. Manaaement Meetinos and Other Areas X1 Exit Meeting Summary The inspectors presented the inspection results to members of licensee management at the conclusion of the inspection on March 19, and April 13,1999. The licensee acknowledged the findings presented.
j PARTIAL LIST OF PERSONS CONTACTED
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Licensee
R. Brown, Manager, Training and Emergency Preparedness W. Burmeister, Manger Engineering Support S. Chesnut, Plant Operations Assistant General Manager G. Frederick, Manager Operations J. Gasser, Nuclear Plant General Manager K. Holmes, Manager Maintenance P. Rushton, Plant Support Assistant General Manager M. Sheibani, Nuclear Safety and Compliance Supervisor C. Tippins, Jr., Nuclear Specialist i A. Maze, NDE Process Supervisor SNC INSPECTION PROCEDURES USED IP 71707:
Plant Operations IP 73753 Inservice Inspection IP 83750:
Occupational Exposure IP 92700:
Onsite Followup of Written Reports of Nonroutine Events at Power Reactor Facilities IP 92901:
Followup - Operations IP 92902:
Followup - Maintenance / Surveillance IP 92903:
Followup - Engineering IP 93702:
Prompt Onsite Response to Events at Operating Power Reactors
ITEMS OPENED AND CLOSED ITEM NUMBER TYPE DESCRIPTION l
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Closed 50-425/99-02-01 NCV Failure to Follow Verification Procedure
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l Results in MFIV Closure and Manual i
Reactor Trip (Section 01.3)
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50-424/98-10-01 URI Review of Unit 1 Overpower Event (Section l
08.1)
50-425/99-02-02 NCV Licensed Power Limit Exceeded Due to improper Maintenance Activities - Multiple Examples (Sections 08.1 and M8.1)
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50-425/98-10-00 LER Reactor Overpower Event Following l
Instrument Calibration (Section M8.1)
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50-425/98-09-00 LER Sequencer Inoperability Leads to Operation Outside of Technical Specifications (Section E8.1)
50-425/99-02-03 NCV Sequencer Inoperability Leads to Operation Outside of Technical Specifications (Section E8.1)
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