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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217P3791999-10-21021 October 1999 Forwards NRC Form 396 & NRC Form 398 for Renewal of Licenses SOP-20607-1 & SOP-20610-1.Without Encls ML20217N2521999-10-20020 October 1999 Provides Supplemental Info Re 990405 Containment Insp Program Requests for Relief RR-L-1 & RR-L-2,in Response to 991013 Telcon with NRC ML20217K7541999-10-15015 October 1999 Forwards Rev 1 to Unit 1,Cycle 9 & Unit 2 Cycle 7 Colrs,Iaw Requirements of TS 5.6.5.Figure 5, Axial Flux Difference Limits as Function of Percent of Rated Thermal Power for RAOC, Was Revised for Both Units ML20217G6751999-10-13013 October 1999 Requests Withholding of Proprietary Info Contained in Application for Amend to OLs to Implement Relaxations Allowed by WCAP-14333-P-A,rev 1 ML20217G1071999-10-0707 October 1999 Informs That on 990930,NRC Staff Completed mid-cycle PPR of Vogtle & Did Not Identify Any Areas in Which Performance Warranted More than Core Insp Program.Nrc Plans to Conduct Core Insps at Facility Over Next Six Months ML20216J9041999-10-0101 October 1999 Forwards Response to RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves ML20216J9161999-10-0101 October 1999 Forwards Response to NRC 990723 RAI Re GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves ML20217B0141999-10-0101 October 1999 Forwards Insp Repts 50-424/99-06 & 50-425/99-06 on 990725- 0904 at Vogtle Units 1 & 2 Reactor Facilities.Determined That One Violation Occurred & Being Treated as non-cited Violation ML20212E8751999-09-20020 September 1999 Forwards Response to NRC GL 99-02, Lab Testing of Nuclear Grade Activated Charcoal. Description of Methods Used to Comply with Std Along with Most Recent Test Results Encl ML20212E7481999-09-20020 September 1999 Requests Approval Per 10CFR50.55a to Use Alternative Method for Determining Qualified Life of Certain BOP Diaphragm Valves than That Specified in Code Case N-31.Proposed Alternative,Encl ML20212C2191999-09-16016 September 1999 Forwards NRC Form 536, Operator Licensing Exam Data, Which Is Current Need for NRC Operator Licensing Exams for Years 2000 Through 2003 of Plant Vogtle,Per Administrative Ltr 99-03 ML20211Q4801999-09-0101 September 1999 Informs That on 990812-13,Region II Hosted Training Managers Conference on Recent Changes to Operator Licensing Program. List of Attendees,Copy of Slide Presentations & List of Questions Received from Participants Encl ML20211J5291999-08-30030 August 1999 Forwards Snoc Copyright Notice Dtd 990825,re Production of Engineering Drawings Ref in VEGP UFSAR ML20211J5251999-08-30030 August 1999 Forwards Response to NRC 990727 RAI Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions ML20211J7381999-08-27027 August 1999 Informs That Licensee Vessel Data Is Different than NRC Database Based on Listed Info,Per 990722 Request to Review Rvid ML20211E9251999-08-23023 August 1999 Forwards fitness-for-duty Performance Data for Jan-June 1999,as Required by 10CFR26.71(d).Data Reflected in Rept Covers Employees at Vogtle Electric Generating Plant ML20210V0881999-08-16016 August 1999 Forwards Insp Repts 50-424/99-05 & 50-425/99-05 on 990620- 0724.No Violations Noted.Vogtle Facility Generally Characterized by safety-conscious Operations,Sound Engineering & Maintenance Practices ML20210Q4611999-08-0505 August 1999 Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licensing Exam on 991006 for Vogtle.Requests Info Re Individuals Who Will Take Exam. Sample Registration Ltr Encl ML20210L2181999-08-0202 August 1999 Forwards NRC Form 396 & Form 398 for Renewal of Listed Licenses,Iaw 10CFR55.57.Without Encl ML20210N1191999-08-0202 August 1999 Discusses 990727 Telcon Between Rs Baldwin & R Brown Re Administration of Licensing Exam at Facility During Wk of 991213 ML20210G3351999-07-27027 July 1999 Forwards Second Request for Addl Info Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions ML20210E0121999-07-23023 July 1999 Forwards Second Request for Addl Info Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves ML20210D9341999-07-22022 July 1999 Discusses Closure of TACs MA0581 & MA0582,response to Requests for Info in GL 92-01,rev 1,suppl 1, Reactor Vessel Structural Integrity ML20210C8011999-07-21021 July 1999 Provides Response to NRC AL 99-02,which Requests That Addressees Submit Info Pertaining to Estimates of Number of Licensing Actions That Will Be Submitted for NRC Review for Upcoming Fy 2000 & 2001 ML20210E0431999-07-15015 July 1999 Forwards Insp Repts 50-424/99-04 & 50-425/99-04 on 990502- 0619.Two Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20209H3881999-07-14014 July 1999 Forwards Revs 1 & 2 to ISI Program Second 10-Year Interval Vogtle Electric Generating Plant Unit 1 & 2 ML20209C4041999-07-0101 July 1999 Forwards Rev 29 to VEGP Units 1 & 2 Emergency Plan.Rev 29 Incorporates Design Change Associated with Consolidation of Er Facilities Computer & Protues Computer.Justifications for Changes & Insertion Instructions Are Encl ML20196H8081999-06-28028 June 1999 Discusses 990528 Meeting Re Results of Periodic PPR for Period of Feb 1997 to Jan 1999.List of Attendees Encl ML20212J2521999-06-21021 June 1999 Responds to NRC RAI Re Yr 2000 Readiness at Nuclear Power Plants.Gl 98-01 Requested Response on Status of Facility Y2K Readiness by 990701 ML20196F9171999-06-21021 June 1999 Forwards Owner Rept for ISI for Vogtle Electric Generating Plant,Unit 1 Eighth Maint/Refueling Outage. Separate Submittal Will Not Be Made to NRC on SG Tubes Inspected During Subj Outage ML20195F8031999-06-11011 June 1999 Forwards Changes to VEGP Unit 1 Emergency Response Data Sys (ERDS) Data Point Library.Changes Were Completed on 990308 While Unit 1 Was SD for Refueling Outage ML20207E7421999-06-0303 June 1999 Refers to from NRC Which Issued Personnel Assignment Ltr to Inform of Lm Padovan Assignment as Project Manager for Farley Npp.Reissues Ltr with Effective Date Corrected to 990525 ML20207F6201999-06-0202 June 1999 Sixth Partial Response to FOIA Request for Documents.Records in App J Encl & Will Be Available in Pdr.App K Records Withheld in Part (Ref FOIA Exemptions 7) & App L Records Completely Withheld (Ref FOIA Exemption 7) ML20207D9861999-05-28028 May 1999 Informs That,Effective 990325,LM Padovan Was Assigned as Project Manager for Plant,Units 1 & 2 ML20207D2701999-05-19019 May 1999 Forwards Insp Repts 50-424/99-03 & 50-425/99-03 on 990321- 0501.One Violation of NRC Requirements Identified & Being Treated as non-cited Violation Consistent with App C of Enforcement Policy ML20206M5141999-05-11011 May 1999 Informs That NRC Ofc of Nuclear Regulation Reorganized Effective 990328.As Part of Reorganization,Div of Licensing Project Mgt Created.Rl Emch Section Chief for Vogtle. Reorganization Chart Encl ML20206U4061999-05-11011 May 1999 Confirms Telcon with J Bailey Re Mgt Meeting Scheduled for 990528 to Discuss Results of Periodic Plant Performance Review for Plan Nuclear Facility Fo Period of Feb 1997 - Jan 1999 05000424/LER-1998-006, Forwards LER 98-006-03 Re Motor Control Ctr Breaker Buckets Not Being Seismically Qualified.Rev Is Submitted to Document Results of Seismic Testing That Demonstrated That No Condition Outside Design Basis of TS Requirements Exi1999-05-10010 May 1999 Forwards LER 98-006-03 Re Motor Control Ctr Breaker Buckets Not Being Seismically Qualified.Rev Is Submitted to Document Results of Seismic Testing That Demonstrated That No Condition Outside Design Basis of TS Requirements Existed ML20206D6411999-04-29029 April 1999 Forwards Vogtle Electric Generating Plant Radiological Environ Operating Rept for 1998 & Vogtle Electric Generating Plant Units 1 & 2 1998 Annual Rept Annual Radioactive Effluent Release Rept ML20206D5881999-04-29029 April 1999 Forwards Rept Which Summarizes Effects of Changes & Errors in ECCS Evaluation Models on PCT for 1998,per Requirements of 10CFR50.46(a)(3)(ii).Rept Results Will Be Incorporated Into Next FSAR Update ML20206D6951999-04-28028 April 1999 Provides Update of Plans for VEGP MOV Periodic Verification Program Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs ML20206C2241999-04-21021 April 1999 Forwards Revised Monthly Operating Repts for Mar 1999 for Vogtle Electric Generating Plant,Units 1 & 2.Page E2-2 Was Iandvertently Omitted from Previously Submitted Rept on 990413 ML20206A6371999-04-21021 April 1999 Forwards SE Authorizing Licensee Re Rev 9 to First 10-yr ISI Interval Program Plan & Associated Requests for Relief (RR) 65 from ASME Boiler & Pressure Vessel Code ML20205Q3351999-04-15015 April 1999 Forwards Insp Repts 50-424/99-02 & 50-425/99-02 on 990214-0320.Three Violations Identified & Being Treated as Non-Cited Violations ML20205T2351999-04-0909 April 1999 Informs That on 990317,B Brown & Ho Christensen Confirmed Initial Operator Licensing Exam Scheduled for Y2K.Initial Exam Date Scheduled for Wk of 991213 for Approx 10 Candidates ML20205K7501999-04-0505 April 1999 Informs That Effective 990329,NRC Project Mgt Responsibility for Plant Has Been Transferred from Dh Jaffe to R Assa ML20209A3741999-04-0505 April 1999 Submits Several Requests for Relief for Plant from Code Requirements Pursuant to 10CFR50.55a(a)(3) & (g)(5)(iii).NRC Is Respectfully Requested to Approve Requests Prior to Jan 1,2000 ML20205H3481999-03-31031 March 1999 Forwards Georgia Power Co,Oglethorpe Power Corp,Municipal Electric Authority of Ga & City of Dalton,Ga Status of Decommissioning Funding for Each Reactor or Part of Reactor Owned for OLs NPF-68 & NPF-81 ML20205F9091999-03-29029 March 1999 Submits Rept of Number of SG Tubes Plugged During Plant Eighth Maintenance/Refueling Outage (1R8).Inservice Insps Were Completed on SGs 1 & 4 on 990315.No Tubes Were Plugged ML20205G0761999-03-26026 March 1999 Provides Results of Individual Monitoring for 1998.Encl Media Contains All Info Required by Form NRC 5.Without Encl 1999-09-20
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217G1071999-10-0707 October 1999 Informs That on 990930,NRC Staff Completed mid-cycle PPR of Vogtle & Did Not Identify Any Areas in Which Performance Warranted More than Core Insp Program.Nrc Plans to Conduct Core Insps at Facility Over Next Six Months ML20217B0141999-10-0101 October 1999 Forwards Insp Repts 50-424/99-06 & 50-425/99-06 on 990725- 0904 at Vogtle Units 1 & 2 Reactor Facilities.Determined That One Violation Occurred & Being Treated as non-cited Violation ML20211Q4801999-09-0101 September 1999 Informs That on 990812-13,Region II Hosted Training Managers Conference on Recent Changes to Operator Licensing Program. List of Attendees,Copy of Slide Presentations & List of Questions Received from Participants Encl ML20210V0881999-08-16016 August 1999 Forwards Insp Repts 50-424/99-05 & 50-425/99-05 on 990620- 0724.No Violations Noted.Vogtle Facility Generally Characterized by safety-conscious Operations,Sound Engineering & Maintenance Practices ML20210Q4611999-08-0505 August 1999 Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licensing Exam on 991006 for Vogtle.Requests Info Re Individuals Who Will Take Exam. Sample Registration Ltr Encl ML20210N1191999-08-0202 August 1999 Discusses 990727 Telcon Between Rs Baldwin & R Brown Re Administration of Licensing Exam at Facility During Wk of 991213 ML20210G3351999-07-27027 July 1999 Forwards Second Request for Addl Info Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions ML20210E0121999-07-23023 July 1999 Forwards Second Request for Addl Info Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves ML20210D9341999-07-22022 July 1999 Discusses Closure of TACs MA0581 & MA0582,response to Requests for Info in GL 92-01,rev 1,suppl 1, Reactor Vessel Structural Integrity ML20210E0431999-07-15015 July 1999 Forwards Insp Repts 50-424/99-04 & 50-425/99-04 on 990502- 0619.Two Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20196H8081999-06-28028 June 1999 Discusses 990528 Meeting Re Results of Periodic PPR for Period of Feb 1997 to Jan 1999.List of Attendees Encl ML20207E7421999-06-0303 June 1999 Refers to from NRC Which Issued Personnel Assignment Ltr to Inform of Lm Padovan Assignment as Project Manager for Farley Npp.Reissues Ltr with Effective Date Corrected to 990525 ML20207F6201999-06-0202 June 1999 Sixth Partial Response to FOIA Request for Documents.Records in App J Encl & Will Be Available in Pdr.App K Records Withheld in Part (Ref FOIA Exemptions 7) & App L Records Completely Withheld (Ref FOIA Exemption 7) ML20207D9861999-05-28028 May 1999 Informs That,Effective 990325,LM Padovan Was Assigned as Project Manager for Plant,Units 1 & 2 ML20207D2701999-05-19019 May 1999 Forwards Insp Repts 50-424/99-03 & 50-425/99-03 on 990321- 0501.One Violation of NRC Requirements Identified & Being Treated as non-cited Violation Consistent with App C of Enforcement Policy ML20206M5141999-05-11011 May 1999 Informs That NRC Ofc of Nuclear Regulation Reorganized Effective 990328.As Part of Reorganization,Div of Licensing Project Mgt Created.Rl Emch Section Chief for Vogtle. Reorganization Chart Encl ML20206U4061999-05-11011 May 1999 Confirms Telcon with J Bailey Re Mgt Meeting Scheduled for 990528 to Discuss Results of Periodic Plant Performance Review for Plan Nuclear Facility Fo Period of Feb 1997 - Jan 1999 ML20206A6371999-04-21021 April 1999 Forwards SE Authorizing Licensee Re Rev 9 to First 10-yr ISI Interval Program Plan & Associated Requests for Relief (RR) 65 from ASME Boiler & Pressure Vessel Code ML20205Q3351999-04-15015 April 1999 Forwards Insp Repts 50-424/99-02 & 50-425/99-02 on 990214-0320.Three Violations Identified & Being Treated as Non-Cited Violations ML20205T2351999-04-0909 April 1999 Informs That on 990317,B Brown & Ho Christensen Confirmed Initial Operator Licensing Exam Scheduled for Y2K.Initial Exam Date Scheduled for Wk of 991213 for Approx 10 Candidates ML20205K7501999-04-0505 April 1999 Informs That Effective 990329,NRC Project Mgt Responsibility for Plant Has Been Transferred from Dh Jaffe to R Assa ML20205B9601999-03-24024 March 1999 Seventh Partial Response to FOIA Request for Documents. Records in App N Already Available in Pdr.App O Records Being Released in Entirety & App P Records Being Withheld in Part (Ref FOIA Exemptions 7C,2 & 5) ML20205A2771999-03-19019 March 1999 Advises of NRC Planned Insp Effort Resulting from Vogtle PPR on 990208.PPR for Plant Involved Participation of All Technical Divs in Evaluating Insp Results & Safety Performance Info for Period of Dec 1997 - Jan 1999 ML20207L8281999-03-0808 March 1999 Forwards Partially Withheld Insp Repts 50-424/99-01 & 50-425/99-01 & Notice of Violation ML20207J0431999-03-0303 March 1999 Forwards Insp Repts 50-424/98-10 & 50-425/98-10 on 981227- 990213.No Violations Noted.Licensee Conduct of Activities at Vogtle Facility Generally Characterized by safety-conscious Operations,Sound Engineering & Maint Practices ML20203G5691999-02-0505 February 1999 Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licensing Exam on 990407. Representative of Facility Must Submit Ltr Indicating No Candidates or Ltr Listing Names of Candidates for Exam ML20202H9691999-01-29029 January 1999 Forwards Safety Evaluation Authorizing Rev 8 to First 10-year Interval Inservice Insp Program & Associated Requests for Relief for Vogtle Electric Generating Plant, Unit 1 ML20199J7931999-01-20020 January 1999 Forwards Insp Repts 50-424/98-09 & 50-425/98-09 on 981115-1226 at Vogtle Units 1 & 2.No Violations Were Identified.Conduct of Activities at Vogtle Was Generally Characterized by safety-conscious Operations ML20199K1381999-01-12012 January 1999 Informs That on 990117,Region II Implemented Staff Reorganization as Part of agency-wide Streamlining Effort, Due to Staffing Reductions in FY99 Budget.Organization Charts Encl ML20198S1601998-12-31031 December 1998 Forwards SER of Licensee Second 10-year Interval Inservice Insp Program Plan & Associated Requests for Relief for Vogtle Electric Generating Plant Submitted on 970529. INEEL/EXT-98-01007 Rept Also Encl ML20199E4741998-12-23023 December 1998 Provides Summary of 981105 Training Managers Conference Held in Atlanta,Georgia.Conference Agenda,List of Conference Attendees,Presentation Slides & Preliminary Schedule for FY99 & FY00 Encl ML20199J9781998-12-22022 December 1998 Responds to 981209 Meeting Re Installation of Seismic Clips on Cutler Hammer Electrical Circuit Breakers.Forwards List of Attendees & Handouts ML20198F6711998-12-11011 December 1998 Forwards Insp Repts 50-424/98-08 & 425/98-08 on 980927-1114. No Violations Identified ML20198N9431998-12-10010 December 1998 Ack Receipt of Response, to NOV Issued on 980112 Re Surveillance Testing of Reactor Trip Sys P-4 Interlock Feature at Licensee Facility.Nrc Agrees That Surveillance Testing Not Required ML20196J2181998-12-0101 December 1998 Advises of Planned Insp Effort Resulting from 981102 Insp Planning Meeting.Historical Listing of Plant Issues Called Plant Issues Matrix & Insp Plan,Including Specific Insps Such as in Security & Radiological Protection Areas Encl ML20196J2581998-12-0101 December 1998 Confirms Arrangements Made Between J Bailey & B Holbrook, Re Info Meeting Scheduled for 990210 to Discuss Licensee Performance,New Initiatives & Other Regulatory Issues Pertaining to Listed Facilities ML20196B1231998-11-23023 November 1998 Confirms Telephone Conversation Between J Bailey & P Skinner on 981120 Re Info Meeting Which Has Been Scheduled for 981209 in Atlanta,Ga,To Discuss Issues Re Seismic Retainer Clips ML20196D4981998-11-13013 November 1998 Informs That on 981007,NRC Administered Gfes of Written Operator Licensing Examination.Copy of Answer Key & Master Bw/Pwr GFE Encl,Even Though Facility Did Not Participate in Exam.Without Encl ML20195B3391998-11-0909 November 1998 Forwards Partially Withheld Insp Repts 50-424/98-12 & 50-425/98-12 on 981005-09 (Ref 10CFR73.21).No Violations Noted.Conduct of Activities Generally Characterized by safety-conscious Operations & Sound Engineering ML20155H2501998-10-21021 October 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-424/98-05 & 50-425/98-05 Issued on 980723.Concluded for Reasons Stated That Example 2 Violation Occurred as Stated in NOV ML20155A7491998-10-15015 October 1998 Forwards Insp Repts 50-424/98-07 & 50-425/98-07 on 980816-0926 & Nov.Insp Generally Characterized by Safety Conscious Operations,Sound Engineering & Maint Practices & Appropriate Radiological Controls ML20155B7771998-10-0909 October 1998 Extends Invitation to Attend Training Manager Conference on 981105 in Atlanta,Georgia.Conference Designed to Inform Regional Training & Operations Mgt of Issues & Policies That Effect Licensing of Reactor Plant Operators ML20155B4621998-09-25025 September 1998 Discusses OI Investigation Which Completed on 980728. Investigation Reviewed Circumstances Surrounding Apparent Disabling of Fire Computer Trouble Alarm by Unit Shift Supervisor.Concludes Enforcement Discretion Warranted ML20153B0401998-09-17017 September 1998 Responds to 980904 e-mail Message Making Certain Observations Re Apparent Increase in Reactor Trips at Plant, Units 1 & 2.NRC Concluded That Licensee post-trip Reviews Adequately Conducted & That No Adverse Trends,Apparent ML20153B9311998-09-16016 September 1998 Forwards RAI Re GL 97-01, Degradation of Crdm/Cedm Nozzle & Other Vessel Closure Head Penetrations, Responses for Plant,Units 1 & 2 ML20153F7081998-09-11011 September 1998 Provides Summary of 980909 Meeting Held to Discuss TS & Other Regulatory Issues Re Vogtle Electric Generating Plant. List of Meeting Attendees & Copy of Presentation Slides Encl ML20154C4871998-09-10010 September 1998 Forwards Insp Repts 50-424/98-06 & 50-425/98-06 on 980628-0815 & Nov.One Violation Involved Failure to Implement Adequate C/As for Repeated Failures to Enter Applicable TS Limiting Conditions for Operation ML20151U7901998-09-0909 September 1998 Discusses 980615 Request for Exemption from Requirement of 10CFR73.55(e)(1) & (f)(1) to Provide Continuous Staffing of Plant CAS During Contingency Events.Request Denied ML20151S7291998-09-0202 September 1998 Discusses Evaluation of Util Response to GL 97-05 for Plant, Units 1 & 2.NRC Did Not Identify Any Concerns W/Sg Tube Insp Techniques Employed at Plant ML20239A4251998-08-27027 August 1998 Informs of Change Being Implemented by Region II Re Administrative Processing of Licensee Responses to Nov.Nov Responses Will Be Formally Ack as Part of Periodically Issued Integrated Insp Repts 1999-09-01
[Table view] |
See also: IR 05000424/1990019
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DRAFT
PREDECISIONAL INFORMATION
NOT FOR RELEASE WITHOUT THE APPROVAL OF THE DIRECTOR, OE l
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Rev. 7: VOGCOVER.R7 2/22/94
Docket No. 50-424
License No. NPF-68
EA 93-304, and EA 94-036 l
Georgia Power Company l
ATTN: Mr. C. K. McCoy i
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Vice President -
Vogtle Project
Post Office Box 1295
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Birmingham, Alabama 35201
SUBJECT: NOTICE OF VIOLATION
MAND FOR INFORMATION (NRC
TIGATIONS REPORT NO. 2-90-020 AND NRC l
INSPECTION REPORT NO. 50-424,425/90-19, SUPPLEMENT 1) i
This refers to the investigation conducted by the Nuclear
Regulatory Commission's Office of Investigatione (OI) at Georgia
Power Company's (GPC) Vogtle Electric Generating Plant (VEGP)
which was completed on December 17, 1993. The investigation was
initiated as a result of information received in June 1990 by
Region II alleging, in part, that material false statements were
made to the NRC by senior officials of GPC regarding the
reliability of the Diesel Generators (DGs). The pertinent events
involved in this matter are described below.
On March 20, 1990, during a refueling outage at VEGP Unit 1, GPC l
declared a Site Area Emergency (SAE) when offsite power was lost l
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concurrent with the failure of the only Unit 1 DG that was
available (1A). The other Unit 1 DG (1B) was unavailable due to
maintenance activities.
The NRC immediately responded to the SAE at the VEGP site with an
Augmented Inspection Team (AIT). The NRC effort was upgraded to
an Incident Investigation Team (IIT) on March 23, 1990. The IIT
was composed of NRC Headquarters technical staff and industry
personnel. The results of this investigation are documented in
NUREG-1410, " Loss of Vital AC Power and the Residual Heat Removal
System During Mid-Loop Operations at Vogtle Unit 1 on March 20,
1990."
On March 23, 1990, the NRC issued a Confirmation of Action Letter
(CAL) to GPC that, among other things, confirmed that GPC had
agreed not to return VEGP Unit 1 to criticality until the
Regional Administrator was satisfied that appropriate corrective
actions had been taken, and that the plant could safely return to
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power operations,
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Information in this record was deleted
in arrordance with the fjeedom of Information '
9610090107 960827 *m
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PDR FOIA
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On April 9, 1990, GPC made a presentation to the NRC in the
Region II offices in support of GPC's request to return VEGP l
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Unit 1 to power operations. As part of this presentation, GPC
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provided information on DG starts in response to a specific NRC
request that GPC address DG reliability in its April 9 i
presentation. GPC submitted a written summary of its April 9
presentation in an April 9, 1990 letter, "Vogtle Electric
Generating Plant Confirmation of Action Letter."
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On April 12, 1990, the NRC formally granted permission for VEGP l
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Unit 1 to return to criticality and resume power operations.
On April 19, 1990, pursuant to 10 CFR 50.73, GPC submitted
Licensee Event Report (LER) 50-424/90-06, " Loss of Offsite Power
Leads to Site Area Emergency."
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On June 29, 1990, GPC submitted a revised LER, 50-424/90-06-01. l
The purpose of the submittal was to clarify information related
to successful DG starts that were discussed in the April 9, 1990
letter and the April 19, 1990 LER, and to update the status of 1
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corrective actions in the original LER.
From August 6 through August 17, 1990, the NRC conducted a
Special Team Inspection at VEGP, as a result of NRC concerns l
about, and allegations related to VEGP operational activities. l
This inspection examined the technical validity and safety
significance of the allegations, but did not investigate alleged
wrongdoing. The Special Team informed GPC that the June 29, 1990
submittal failed to address the April 9, 1990 data and requested
that GPC clarify DG starts reported on April 9, 1990. Results of
this inspection are documented, in part, in NRC Inspection Report
No. 50-424,425/90-19, Supplement I, dated November 1991.
1
On August 30, 1990, GPC submitted a letter, " Clarification of
Response to Confirmation of Action Letter." The purpose of the
submittal was to clarify the diesel start information that was
addressed in the April 9, 1990 submittal.
The NRC has carefully reviewed the evidence associated with these
events, submittals, and representations to the NRC.
Specifically, the NRC reviewed information gathered as part of
the OI investigation, informat' gathered during the IIT, NUREG-
1410, Supplement 1 of NRC Inspr , ion Report 90-19, discovery
responses in the Vogtle operating license amendment proceeding
l (Docket Nos. 50-424 OLA-3, 50-425 OLA-3), and other related
gformation.
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inrormation was
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presentation by the VEGP General Manager and in an April 9,
1990 letter that there were 18 and 19 successful consecutive
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- or failures.
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the 19 troub e-free star s for the 1B
at GPC reported in the presentation and letter included
j three starts with problems that occurred during DG
overhaul / maintenance activities (a high lube oil temperature
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trip on March 22, 1990; a low jacket water pressure / turbo
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lube oil pressure low trip on March 23, 1990; and a failure
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' to trip on a high jacket water temperature alarm occurring
on March 24, 1990). The correct number of consecutive
successful starts was 12 for the 1B DG--a number
less than that reported by GPC to the NRC on
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] instruments and controls is derived from the starting air
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system. The starting air system contains dryers designed to
J maintain moisture content (i.e., dew point) at acceptable
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maintenance records and deficiency cards associated with
l Ursit I would have revealed that high dew points were also
attributable to system air dryers occasionally being out of
l service for extended periods and to system repressurization i
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following maintenance, as documented in NRC Inspection
! Report No. 50-424,425/90-19, Supplement 1, dated November 1,
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1991.
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During the preparation of the LER, the Acting VEGP Assistant
General Manager questioned the accuracy of the April 9
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letter given that there were trips on the 1B DG after
j March 20, 1990.
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In later discussions regarding the draft LER,
the General Manager, Technical Support Manager and Acting
)' VEGP Assistant General. Manager acknowledged that they could
not identify the specific DG start that represented the
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starting point for the count presented to the NRC, i.e., the
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first start following completion of the CTP. There were
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also different interpretations about what testing tha term
l CTP encompassed. The General Manager - Plant Support
! (Vogtle Project), the VEGP Technical Support Manager, and
the Acting VEGP Assistant General Manager were aware that
- the VEGP General Manager had earlier stated that his April 9
count began after instrument recalibration. The Acting VEGP
Assistant General Manager stated that his understanding of
i the CTP was that it would be a test program to determine
root causes and restore operabili
l , Superintende o
l acquired the data a ised Mr. Mosbaugh and Mr. Aufdenkampe
} that he started his counts on March 20, prior to the time
! when a CTP could have been completed.
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' the 1A and 1B DG start counts
reported on April 19, (and earlier on April 9),
overstated the actual counts by including starts that were
part of the test program.
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the Acting VEGP Assistant General Manager - Plant Support
gave the VEGP General Manager a listing of 1B DG starts
t
! After being informed that the April 19 DG start counts were ,
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j in error, the Senior Vice President - Nuclear Operations
l informed the Regional Administrator that a revision to the
i April 19 LER would be submitted, in part, to correct the DG
- start counts. After being provided conflicting data for the
i second time, the Senior Vice President - Nuclear Operations .
I
{ again notified the Regional Administrator. He also
requested that an audit be conducted to establish the
correct data and to determine why the errors were made. The
j audit, completed June 29, narrowly focused on a review of
- diesel records (Test Data Sheets, Shift Supervisor's Log,
j and Diesel Generator Start Log) to verify the number of DG
j starts. The audit did not identify any specific cause for
j the error in the number reported in the LER. The audit
i stated, however, that the error appeared to result from
) incomplete documentation. The audit also noted that there
apparently was some confusion about the specific int at
which the test program was completed.
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On June 29, 1990, the draft cover letter for the LER
i revision was being reviewed at the site. The draft had
- originated in GPC corporate headquarters and included
i language personally developed by the Senior Vice President -
j Nuclear Operations and the Vice President - Vogtle Project.
j During the site review, a VEGP Technical Assistant (TA)
l (formerly the Acting VEGP Assistant General Manager - Plant
j Support) noted that the letter was incomplete and challenged
j the accuracy of the reasons stated in the draft cover letter
j in conversations with the Supervisor - Safety Audit and
i Engineering Review (SAER), the VEGP Assistant General
Manager - Plant Support, the VEGP Manager - Engineering
<
Support, and a Licensing Engineer - Vogtle Project. The
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VEGP TA stated that: (1) the letter failed to clarify the DG
starts reported on April 9, (2) DG record keeping practices
were not a cause of the difference in the DG starts reported
in the April 19 LER because adequate information was
available when the counting errors were made, and (3) the
erroneous counts resulted from personnel errors in
l d a'ta l an i nrv +ho r tiin nt .
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The Vice President - Vogtle Project and the
Senior Vice President - Nuclear Operations were actively
involved in the preparation of the June 29 cover letter.
The VEGP General Manager and Vice President - Vogtle Project
reviewed, and the Senior Vice President - Nuclear Operations
signed, the June 29 cover letter which stated that its
purpose was, in part, to clari information provided to the
NRC on April 9.
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the April 9, 1990 letter. The letter
stated that the errors in the April 9 letter and
presentation and the April 19 LER were caused, in part, by
confusion in the distinction between a successful start and
During the August 29, 1990
Plant Review Board meeting, the VEGP Manager - Technical
Support questioned if the Unit Superintendent (the
individual who originally collected the DG start data) was
confused in the distinction between a successful start and a
valid test. The VEGP General Manager admitted that the Unit
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Superintendent was not confused about the distinction when
he collected the data which was used to prepare the April 9
letter, but stated that the sentence was not in error
because other people were confused. The VEGP General
Manager acknowledged that there was confusion among
individuals after April 9, but admitted that the Unit
Superintendent was not confused when he developed the
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The i
August 30 letter states that the error in the April 9 letter '
and presentation and the April 19 LEP were caused, in part,
by an error made by the individual who performed the count
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submittal.
While un ertoo
e April 19 LER, it narrowly focused only on that
For example, GPC conducted an audit, the scope
of which was limited to review of DG records, in an attempt
to correct the start count reported in the April 19 LER.
efforts to
!
Furthermore, in its June 29 submittal, while GPC referred to
both the April 9 letter and the April 19 LER, it attempted
to explain only the reasons for the error in the April 19
LER. The Senior Vice President - Nuclear Operations and the
Vice President - Vogtle Project were directl involved in
the development of the June 29 letter.
Subsequently,
,
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the NRC requested that GPC make a submittal addressing the
April 9 letter. As of August 17, 1990, the VEGP General
Manager and the Vice President - Vogtle Project were aware
i of NRC concerns regarding the errors in, and the misleading
l nature of, the April 9 letter. The Vice President - Vogtle
l Project committed during the August 17 meeting with the NRC
4
special inspection team to provide clarification to the NRC
l regarding the April 9 letter.
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! evaluation was initiated. cause
!
Rather, GPC forwarded a submittal
!
regarding the April 9 letter on August 30 that was drafted
at corporate headquarters under the direction of the Vice
President - Vogtle Project, without an assessment of the
actions of the VEGP General Manager and the Unit
Superintendent who developed erroneous information for the
AJril 9 letter.
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It is our understanding that
Mr. Bockhold is currently working T'or Southern Nuclear as the
General Manager of Nuclear Technical Servic
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investigation primarily focused on actions and communications
involving the DGs, OI also reviewed other communications within a
j particular time-frame and made a general observation that GPC
avbihirad a closed. adversarial attitude toward the NRC. M
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l Sincerely,
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James L. Milhoan
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Deputy Executive Director
for Nuclear Reactor Regulation,
Regional Operations, and Research
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l Enclosures *
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2. Demand For Intornation
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