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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] |
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February 28, 1991 !
ELV-02543 l 0846 Docket Nos. 50-424 50-425 )
l Director, Office of Enforcement 1
'J. S. Nuclear Regulatory Commission Washington, D. C. 20555 Gentlemen:
1 V0GTLE ELECTRIC GENERATING PLANI REPLY TO NOTICE OF VIOLATION AND PROPOSED IMPOSITION OF civil PENALTY m
Pursuant to 10 CFR 2.201, Georgia Power Compt.ny submits the enclosed reply to the results identified in inspection Report Nos. 50-424/90-27 and 50-4P5/90-27 where safeguards information was found unsecured, unprotected or unattended. A transcription of the violation precedes GPC's response, and a check in the amount of $50,000 is enclosed in response to the civil pennity.
Mr. C. K. McCoy states that he is a Vice President of Georgia Power Company and is authorized to execute this oath on behalf of Georgia Power Company and that, to the best of his knowledge and belief, the facts set forth in this letter and enclosure are true.
GEORGIA POWER COMPANY By: e.
C. K. McCoy Sworntoandsubscribedbeforemethisd[dayof de se , 1991.
J ff U CtfA NothyPublic L
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pg
Enclosure:
Violation 50-424/90-27 and 50-425/90-27, GPC Response and Check for Civil Penalty xc: (see next page) 9103060115 910228 PDR ADOCK 05000424 k
g PDR
I Georgialbwer d U. S. Nuclear Regulatory Commission Director, Office of Enforcement ELV-02543 Page 2 c(w): Georoia Power Comoany Mr. C. K. McCoy Mr. W. B. Shipman Mr. R. M. Odom Mr. P. D. Rushton N0PMS U. S. Nuc.leir Reaulatory Commission Mr. S. D. Ebneter, Regional Administrator Mr. D. S. Hood, Livensing Project Manager, NRR Hr. B. R. Bonser, Senior Resident inspector, Vogtle Document Control Desk l
l l
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ENCLOSURE V0GTLE ELECTRIC GENERATING PLANT - UNITS 1 & 2 REPLY TO A NOTICE OF VIOLATION AND PROPOSED IMPOSITION OF civil PENALTY NRC INSPECTION REPORT NOS. 50-424/90-27 AND 50-425/90-27 AND GPC RESPONSE 1
'During an NRC inspection conducted on October 16-17, 1990, a violation of NRC !
! requirements was identified. In accordance with the " General Statement of I i Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2 Appendix C ,
t (1990), the Nuclear Regulatory Commission proposes to impose a civil penalty '
pursuant to Section 234 of the Atomic Energy Act of 1954, as amended (Act),
42 U.S.C. 2282, and 10 CFR 2.205. The particular violation and associated civil penalty are set forth below:
10 CFR 73.21(a) requires, in part, that Safeguards Information (SGI) be protected against unauthorized disclosure, and that licensees establish and maintain an information protection system that includes certain measures to protect SGl.
10 CFR 73.21(d)(2) requires, in part, that while unattended, SGI shall be stored in a locked security storage container.
Contrary to the above, the licensee failed to provide adequate protection for documents and materials containing Safeguards Information as evidenced by the following examples:
- 1. On August 29, 1990, an unlocked and unattended container used to store SGI was discovered by a Southern Company Services employee in the Vogtle Project Engineering Support Office document file room, located in Birmingham, Al t.bama ,
- 2. On October 11, 1990, unsecured and unattended documents containing SGI relating to training tasks were found in the Security Training Ofrice, Vogtle Electric Generating Plant.
- 3. On October 16, 1990, two elementary drawings of the Vogtle security poser supply containing SGI were found unsecured and unattended in the Vogtle Project Engineering Office, Birmingham, Alabama.
- 4. On October 19, 1990, four documents containing Safeguards Information were found unsecured and unattended in the Security Training Office, Vogtle Electric Generating Plant.
- 5. On November 9, 1990, aperture cards containing SGI were discovered unmarked and unprotected as SGI in the offices of Document Control, Vogtle Electric Generating Plant.
This is a Severity Level !!! violation (Supplement III).
Civil Penalty - $50,000."
El-1
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, ENCLOSURE (CONTINUED)
. REPLY TO A NOTICE OF VIOLATION AND PROPOSED IMPOSITION OF CIVIL PENALTY NRC INSPECTION REPORT NOS. 50-424/90-27 AND 50-425/90-27 AND GPC RESPONSE l Admission or Denial of the Violation The violation occurred as stateo except for clarifications to the cited examples listed below.
Examole 3 On October 17, 1990, instead of the cited date of October 16, 1990, two elementary drawings of the Vogtle security power-supply containing safeguards information were found unsecured and unattended in the Southern 1- Company Services (SCS) Vogtle Project Engineering Office in Birmingham, Alabama.
1-Examole 5 On November.9, 1990, aperture cards containing safeguards informat4on were discovered unmarked and unprotected as safeguards information in tqe Engineering Satellite Office on the third floor of the Service Building, and not in the VEGP Document Control Office as stated in the cited violation, n it is noted that all five examples cited were licensee identified and reported in Licensee Event Reports 50-424/1990-07S, 085,10S for cited examples 1, 2, and 5, while-examples 3 and 4 were recorded on the VEGP Safeguards Event tog for the Fourth Quarter 1990.
Reason for the Violation The reason for the violations cited in examples 1, 2, and 4 was cognitive personnel error. The reason for_ the occurrences cited in examples 3 and 5 was programmatic / procedural inadequacies. The root cause of the continuing problems is attributed to personnel error and procedural inadequacies, items which have contributed to the recurrence of this problem are listed below. ,
- 1. Lack of sensitivity and adequate procedural guidance for controlling safeguards information during construction and startup.
- 2. Differing degrees.of interpretation of safeguards information categorization-criteria..
- 3. No' specific guidance given to determine which person / organization had-the authority to categorize a document as safeguards.
- 4. A rela;ively his turnover of individuals making safeguards information categornatun determinations leading to a lack of consistency-in safeguards
- categorization.
El-2 4
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1 ENCLOSURE (CONTINUED)
REPLY TO A N011CE Of VIOLATION AND PROPOSED IMPOSITION Of civil PENALTY NP.C INSPECTION REPORT NOS, 50-424/90-27 AND 50-425/90-27 AND GPL RESP.QH.SI Cor*ective Steos That Have 3een Taken and the Result Achieved
- 1. Once safeguards information was found to be unsecured, unprotected or unattended, audits were immediately con Scted and in all cases it was determined that no material was missing.
- 2. The individuals determined to be responsible for the safeguards lef t unsecured, unprotected and unattended have been counseled.
- 3. A letter from the Vice President Nuclear and A/E Project Managers describing the responsibilities for proper safeguards information control has been sent to employees at the site, and at corporate and A/E Offices. This letter also emphasized that individuals will be held personally accountable for any safeguards information control incidents.
- 4. The appropriate site, VEGP Corporate Office, SCS, and Bechtel procedures have been revised to include adequate guidance on retrieval of previously issued copies of documents which are recategorized as safeguards information.
- 5. A safeguards information review task force was appointed on November 30, 1990, to serve as a review and advisory group to the Vice President, Nuclear, in the implementation of a safeguards program designed to establish a baselir+ for the VEGP safeguards information control program. This effort includes determination of whether documents are properly classified and properly stored. Two members of this task force are from the Hatch and Farley Projects to provide expertise from outside the Vogtle Project. The farley member is also a participsat on the NUMARC Security Working Group.
- 6. Guidelines for safeguards document categorization have been developed for ese by those conducting the ongoing reviews described in GPC letter ELV-02507 dated February 11, 1991. An outside consultant was employed to assist GPC in developing these guidelines and conducting training for the members of the review team and classification team.
- 7. The number of containers containing safeguards information has been reduced and the number of individuals having access to this information has been reduced.
Corrective Stens Which Will Be Taksn to Avoid Further Violations
- 1. A comprehensive review of documents has been implemented to ensure proper safeguards categorization. The overall focus of the review is to establish a baseline of safeguards material for VEGP. This review is scheduled to be completed by March 31, 1991.
l El-3 l
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l 9
ENCLOSURE (CONTINUED)
REPLY TO A NOTICE OF VIOLATION AND PROPOSED IMPOSITION OF CIVIL PENALTY NRC INSPECTION REPORT N05, 50-424/90-27 AND 50-425/90-27 l AND GPC RESPONSE
- 2. Georgia Power Company is in the process of auditing vendors who supply
- safeguards information for security-related hardware to ensure this information is properly controlled at the vendors' offices. This effort is scheduled to be completed by March 31, 1991. To date the two major vendors which supply security-related hardware to VEGP have been audited. The
-audits determined that these vendors have acceptable safeguards information
-control programs. No audit findings were issued, but some program enhancements were suggested by the auditors.
- 3. An expanded review of documents in areas off project is in process. This review includes the site SCS Offices in Birmingham, the Corporate Offices in Birmingham, and the Bechtel Offices in Gaithersburg to ensure no safeguards information exists in these uncontrolled storage locations. This effort- is scheduled to be completed by March 31, 1991.
Date When Full Como11ance Will Be Achieved Ter the cited examples full compliance was achieved on November 9, 1990, with the discovery and proper disposition of the unsecured safeguards information aperture cards.
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