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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:INCOMING CORRESPONDENCE
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 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 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 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 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 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 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 ML20210L2181999-08-0202 August 1999 Forwards NRC Form 396 & Form 398 for Renewal of Listed Licenses,Iaw 10CFR55.57.Without Encl 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 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 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 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 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 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 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 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 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 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 ML20205H4051999-03-25025 March 1999 Forwards Info on Status of Decommissioning Funding for Each Reactor or Part of Reactor Owned for OLs NPF-68 & NPF-81,as Requested IAW 10CFR50.75(f)(1) ML20205H3891999-03-25025 March 1999 Forwards Info on Status of Decommissioning Funding for Each Reactor or Part of Reactor Owned for OLs NPF-68 & NPF-81,as Requested IAW 10CFR50.75(f)(1).Page 2 in Third Amend Power Sales Contract of Incoming Submittal Not Included ML20205A9441999-03-25025 March 1999 Forwards VEGP Unit 1 Cycle 9 Colr,Per TS 5.6.5.d ML20205H3811999-03-24024 March 1999 Forwards Info on Status of Decommissioning Funding for Each Reactor or Part of Reactor Owned for OLs NPF-68 & NPF-81,as Requested IAW 10CFR50.75(f)(1) ML20205H3621999-03-22022 March 1999 Forwards Info on Status of Decommissioning Funding for Each Reactor or Part of Reactor Owned for OLs NPF-68 & NPF-81, as Requested IAW 10CFR50.75(f)(1) ML20204G4361999-03-18018 March 1999 Forwards Summary Rept of Present Level & Source of on-site Property Damage Insurance Coverage for Vegp,Iaw Requirements of 10CFR50.54(w)(3) ML20204C0591999-03-17017 March 1999 Forwards Rev 0 to WCAP-15160, Evaluation of Pressurized Thermal Shock for Vegp,Unit 2 & Rev 0 to WCAP-15159, Analysis of Capsule X from Vegp,Unit 2 Reactor Vessel Radiation Surveillance Program ML20207K9551999-03-11011 March 1999 Forwards Response to Rai,Pertaining to Positive Alcohol Test of Licensed Operator.Encl Info Provided for NRC Use in Evaluation of Fitness for Duty Occurrence.Encl Withheld,Per 10CFR2.790(a)(6) ML20207L9721999-03-10010 March 1999 Forwards Rev 15 to EPIP 91104-C of Manual Set 6 of Vogtle Epips.Without Encl ML20207B0191999-02-25025 February 1999 Forwards Fitness for Duty Performance Data for six-month Reporting Period 980701-1231,IAW 10CFR26.71(d) 05000424/LER-1998-009, Forwards LER 98-009-00 Re Event in Which Improper Testing Method Resulted in Inadequate Surveillances on 9812291999-01-27027 January 1999 Forwards LER 98-009-00 Re Event in Which Improper Testing Method Resulted in Inadequate Surveillances on 981229 ML20199F7701999-01-13013 January 1999 Submits Revised Response to RAI Re Licensee 980713 Proposed Amend to Ts,Eliminating Periodic Response Time Testing Requirements on Selected Sensors & Protection Channels. Corrected Copy of Table,Encl ML20199F7981999-01-13013 January 1999 Forwards Corrected Pages to VEGP-2 ISI Summary Rept for Spring 1998 Maint/Refueling Outage. Change Bar in Margin of Affected Pages Denotes Changes to Rept ML20199G1381999-01-13013 January 1999 Forwards Copy of Permit Renewal Application Package for NPDES Permit Number GA0026786,per Section 3.2 of VP Environ Protection Plan 05000424/LER-1998-007, Forwards LER 98-007-00,re Inadequate Surveillances Due to Improperly Performed Response Time Testing,On 981215,IAW 10CFR50.731999-01-13013 January 1999 Forwards LER 98-007-00,re Inadequate Surveillances Due to Improperly Performed Response Time Testing,On 981215,IAW 10CFR50.73 ML20198F6131998-12-18018 December 1998 Forwards Revised Certification of Medical Exam Form for License SOP-21147.Licensee Being Treated for Hypertension. Util Requests That Individual License Be Amended to Reflect Change in Status ML20198L6631998-12-18018 December 1998 Forwards Amend 37 to Physical Security & Contingency Plan. Encl 1 Provides Description & Justification for Changes & Encl 2 Contains Actual Amend 37 Pages.Amend Withheld,Per 10CFR73.21 ML20198D9291998-12-16016 December 1998 Forwards Requested Info Re Request to Revise TSs Elimination of Periodic Pressure Sensor Response Time Tests & Elimination of Periodic Protection Channel Response Time Tests ML20198D9991998-12-16016 December 1998 Forwards Responses to 980916 RAI Re Response to GL 97-01, Degradation of Control Rod Drive Mechanism Nozzle & Other Vessel Closure Head Penetrations ML20198D8171998-12-14014 December 1998 Forwards NRC Form 396 & Form 398 for Renewal of License OP-20993.Without Encls ML20206N3051998-12-0808 December 1998 Submits RAI Re Replacement of Nuclear Instrument Sys Source & Intermediate Range Channels & post-accident Neutron Flux Monitoring Sys 1999-09-20
[Table view] |
Text
e -' Georgia Power Company
..- - 40 invemess Center Parkwar Post Offce Box 1295
- BJmingham, Alabama 35201
' Telephone 205 877 7122 C. K. Mccoy Georgia Power Vce Presdent, Nuclear i the southem electic system l Vogne Pro;cct October 27, 1995
. LCV-0645-B l
Docket No. 50-424 l 50-425 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555 Ladies and Gentlemen:
VOGTLE ELECTRIC GENERATING PLANT BEPLY TO A NOTICE OF VIOLATION Pursuant to 10 CFR 2.201, Georgia Power Company (GPC) submits the enclosed information for Vogtle Electric Generating Plant (VEGP). This submittal is in response to .
violations identified in Nuclear Regulatory Commission (NRC) Inspection Reports 50-424;425/ 95-19, dated September 29,1995, which documents the inspection conducted at VEGP during August 28 - September 1,1995.
As specifically requested in the NRC Inspection Report and Notice of Violation, this response also indicates the planned short term corrective actions related to GPC's use of the T2 and T3 transformers at VEGP until their replacement.
Should you have any questions feel free to contact this office.
1 Sincerely, C. K. McCoy 1
CKM/AFS i
Enclosure:
Reply to NOV 50-424;425/ 95-19-01 & 02 j t
cc: (Continued next page) 00011 [
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'9511010015 951027 PDR P. DOCK.05000424 ,.
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Gebrgia PowerA .
' U. S. Nuclear Regulatory Commission -
LCV-0645-B Page 2 ,
r cc: Georgia Power Company Mr. J. B. Beasley, Jr.
Mr. M. Sheibani NORMS U. S. Nuclear Regulatory Commission
. Mr. S. D. Ebneter, Regional Administrator Mr. L. L. Wheeler, Licensing Project Manager, NRR Mr. C. L. Ogle, Senior Resident Inspector, Vogtle l
l 70077$ -
ENCLOSURE VOGTLE ELECTRIC GENERATING PLANT- UNITS 1 & 2 REPLY TO A NOTICE OF VIOLATION NRC INSPECTION REPORTS 50-424:425/95-19 VIOLATION A. 50-424:425/95-19-01 The following is a transcription of violation A as cited in the Notice of Violation (NOV):
"During an NRC inspection conducted on August 28 through September 1,1995, violations of NRC requirements were identified. In accordance with the " General Statement ofPolicy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C, the violations are listed below:
4 A. 10 CFR 50, Appendix B, Criterion XVI, " Corrective Actions", as implemented by the Vogtle Electric Generating Plant Operations Quality Assurance Policy Manual, Revision 12, requires, in part, that measures be established to assure that conditions adverse to quality, such as failures, malfunctions, deficiencies, defective material and equipment, are promptly identified and corrected.
Contrary to the above, the licensee failed to promptly identify and correct significant conditions adverse to quality, namely the degradation and failure of transformers in safety-related diesel generator voltage regulators. These failures are evidenced by the following l examples: 1 1
I
- 1. Voltage regulator, S/N 3271, failed on March 13,1995. The cause of the failure was determined on May 2,1995 by the manufacturer. However, the licensee failed to take prompt corrective actions to inspect the other diesel generator voltage regulators for defective T3 transformers.
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- 2. During the performance of Diesel Generator (DG) Operability Test for DGI A per procedure 14980-1 on June 28,1995, severe voltage excursions were noted. Even though conditions adverse to quality were indicated prompt corrective actions were not taken to determine the cause of the voltage excursions. The surveillance was continued and completed as satisfactory.
This is a Severity Level IV violation (Supplement I)"
1 1
RESPONSE TO VIOLATION A (50-424:425/95-19-01) )
l Admission or Denial of the Violation- l Georgia Power Company admits this violation.
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- ENCLOSURE VOGTLE ELECTRIC GENERATING PLANT - UNITS 1 & 2 REPLY TO NOTICE OF VIOLATION NRC IN'iPECTION REPORTS 50-424
- 425/95-19 Reason for the Violation:
A(1). On March 13,1995, EDG 2B voltage regulator #1 was removed during troubleshooting after experiencing a voltage anomaly during post-modification testing. A deficiency card was initiated to address the problem. The EDG 2B voltage anomaly was caused by the modification miswiring of the transfer switch utilized to select either of the redundant
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automatic voltage regulators. Although there were no suspected problems with the voltage regulator, it was sent to the vendor test facility to verify that it was acceptable for
- return to warehouse stock. During testing in May 1995, at the vendor test lab, a defective T3 transformer was identified. The voltage regulator with the failed T3 transformer was returned to the site for repair but was inadvertently returned to stock. Actions were initiated to procure and replace the defective T3 transformer.
Since the EDG 2B voltage anomaly had been caused by the modification miswiring and l
the modification miswiring was specific to EDG 2B, there was no sense of urgency nor was it considered necessary to perform a failure analysis on the T3 transformer or to 4 perform inspections of the T3 transformers in the other EDG voltage regulators. It was assumed that the T3 transformer failure could have resulted from the modification .
miswiring. In hindsight, further immediate investigation to determine if the T3 failure was caused by the modification miswiring would have been appropriate, since engineering i-reviews later determined that the modification miswiring could not have caused the T3 failure. The improper material" return-to-stock" also potentially contributed to a missed
- opportunity to further investigate the T3 failure mechanism.
! A(2). Within minutes after opestors observed the EDG 1 A voltage anomaly on June 28,1995, the system engineer was dispatched to observe and investigate the problem. A known problem associated with oxidation on the power driven potentiometers was suspected due to similar symptoms. Under the direction of the system engineer, the diesel operator adjusted voltage higher and lower several times, until the problem was no longer evident.
Previous vendor and engineering recommendations to adjust the potentiometer in tiss manner had been proceduralized on an interim basis until replacement potentiometers could be procured and installed.
Following the EDG 1 A voltage anomaly that same morning, corporate and site engineering and management personnel held discussions to further analyze the anomaly and determine a course of action, if required. The adverse voltage condition was recognized and actions were initiated to comply with Technical Specifications (due to the brief period ofinoperability). Upon receipt of a further unexpected EDG trouble alarm, the EDG was immediately declared inoperable and an investigation started to determine the cause of the failure. Subsequent to this failure, an exhaustive event review was conducted.
2
ENCLOSURE VOGTLE ELECTRIC GENERATING PLANT - UNITS 1 & 2 REPLY TO NOTICE OF VIOLATION NRC INSPECTION REPORTS 50-424:425/95-19 Corrective Steos Which Have Been Taken and the Results Achieved:
- 1. A successful surveillance test was performed utilizing the other redundant automatic voltage regulator and EDG 1 A was returned to service on June 29,1995. The redundant automatic voltage regulator with the failed T3 transformer which caused EDG 1 A to experience the severe voltage excursions, was replaced on July 7,1995. The "Information only" LCO was cleared on the same day after satisfactory completion of the EDG's operability test.
- 2. The automatic voltage regulator power driven potentiometers (PDP) for all EDGs were replaced and a preventive maintenance checklist has been generated to insure EDG PDPs are replaced periodically. l
- 3. Since all the EDG's voltage regulator's PDPs have been replaced, the EDG operability test procedures have been revised to remove the steps which were added pending their replacement. These procedures had previously directed operators to manually adjust voltage in order to " wipe-clean" the potentiometer prior to EDG loading.
- 4. All of the EDG's T2 and T3 transformer voltage taps were tested to detect improper I voltage output. EDG 1B voltage regulator # 1 was replaced because of a low voltage measurement on the 600V tap and all of the other EDG voltage regulator T2 and T3 transformer tap settings were found to have acceptable voltage output on all of their taps.
- 5. Materials Department personnel have been trained concerning the inadequate handling practices as identified in this violation and personnel have been made aware of the applicable material control procedure revisions.
Corrective Steos Which Will Be Taken to Avoid Further Violations:
- 1. The Unit 2 EDG voltage regulator T2 and T3 transformers will be replaced with an improved design as soon as practical. Material delivery to support installation is anticipated by February 29,1996. The Unit 1 EDG transformers will be replaced during the next refueling outage, which is currently scheduled to begin March 10, l 1996.
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- 2. Until the new transformers are installed, the planned short term corrective action includes performing preventive maintenance to ensure the T2 and T3 transformers are tested for proper output voltage. This will begin by October 31,1995, and periodically tisxeafter until replacement.
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ENCLOSURE )
l 1
VOGTLE ELECTRIC GENERATING PLANT - UNITS 1 & 2 REPLY TO NOTICE OF VIOLATION NRC INSPECTION REPORTS 50-424:425/95-19 I
1
- 3. This event will be included in the Licensed Operator Requalification Program. All applicable individuals will be made aware of this event by December 31,1995.
. I Date When Full Compliance Will Be Achieved:
Full compliance was achieved on July 7,1995, when the defective voltage regulator which had been inadvertently re-installed, was replaced and a satisfactory EDG operability surveillance test !
was performed. {
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) VIOLATION B. 50-424:425/95-19-02 The following is a transcription of violation B as cited in the Notice of Violation (NOV): )
"During an NRC inspection conducted on August 28 through September 1,1995, violations of l 3
NRC requirements were identified. In accordance with the " General Statement of Policy and l Procedures for NRC Enforcement Actions," 10 CFR Part 2, Appendix C, the violations are listed !
l below: l B. 10 CFR 50, Appendix B, Criterion XV, " Nonconforming Materials, Parts, or Components", as implemented by the Vogtle Electric Generating Plant Operations Quality Assurance Policy Manual, Revision 12, requires, in part, that measures be established to I control materials, parts, or components which do not conform to requirements in order to prevent their inadvertent use or installation.
Contrary to the above, on May 26,1995, measures to control a defective voltage regulator, S/N 3271, were not clearly established to prevent its return to warehouse stock and subsequent issue for installation in diesel generator DGI A June 29,1995.
i This is a Severity Level IV violation (Supplement I)."
RESPONSE TO VIOLATION B (50-424:425/95-19-02)
Admission or Denial'of the Violation: ,
1 l Georgia Power Company admits this violation.
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I ENCLOSURE i
VOGTLE ELECTRIC GENERATING PLANT - UNITS 1 & 2 )
REPLY TO NOTF S CJ ,10LATION ;
NRC INSPECTION REPO[iTS 50-424:425/95-19 Reason for the Violation: i On March 13,1995, EDG 2B's voltage regulator #1 was removed due to a voltage drop experienced during post-modification testing. On March 27,1995, EDG 2B voltage reguh lor #2 l was removed following a voltage drop during Engineered Safety Features Actuation System (ESFAS) testing. As part of the investigation to determine the cause of the voltage anomalies, both voltage regulators were shipped to the vendor for testing. Since the vendor no longer had an approved 10 CFR 50 Appendix B Quality Assurance program in place, testing was conducted and documented through VEGP Work Order (WO) practices and procedures. Vogtle Electric i Generating Plant maintenance support personnel were present during all testing.
On May 2,1995 the voltage regulators were unpacked by VEGP maintenance support personnel
- at the vendor's facility. Testing indicated that one voltage regulator was working properly while the other had a defective T3 transformer. The VEGP maintenance support personnel present during the testing were not qualified to perform the work needed to replace the T3 transformer; therefore both the acceptable and the defective voltage regulators were shipped back to VEGP.
VEGP material control procedures did not adequately provide a method to control safety-related material being sent and received from an offsite vendor with work being controlled by VEGP procedures and personnel. Procedures did not address receipt of defective material designated to be repaired by VEGP personnel and procedures. Additionally, specific guidance for control of the safety-related material was not adequately documented or included with the voltage regulator return shipment to VEGP. 1 l
- Corrective Stcos Which Have Been Taken and the Results Achieved
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- 1. The defective voltage regulator which had been inadvertently re-installed on EDG 1 A was replaced and a satisfactory EDG operability surveillance test was performed on July 7,1995.
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- 2. VEGP material control procedures have been revised to incorporate specific instruction and guidance for performing repairs / testing of safety-related materials sent offsite using VEGP work control procedures. l
- 3. Materials Department personnel have been trained concerning the inadequate materials handling practices as identified in this violation and personnel have been made aware of the applicable new material control procedure revisions.
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r ENCLOSURE VOGTLE ELECTRIC GENERATING PLANT - UNITS 1 & 2 REPLY TO NOTICE OF VIOLATION NRC INSPECTION REPORTS 50-424:425/95-19 Corrective Steos Which Will Be Taken to Avoid Further Violations:
No further corrective actions are planned at this time.
Date When Full Comoliance Will Be Achieved:
Full compliance was achieved on September 13,1995, when the Materials Department personnel were trained on the applicable material control procedure revisions.
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