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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
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l November 19, 1997 Mr. C. K. McCoy Vice President Southern Nuclear Operating 1 Company, Inc. l P O. Box 1295 I Birmingham, Alabama 35201 l
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION ON THE INDIVIDUAL PLANT EXAMINATION OF EXTERNAL EVENTS VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2 (TAC NOS. M83690 AND M83691)
Dear Mr. McCoy:
The NRC staff, in conjunction with Sandia National Laboratories and Brookhaven National Laboratory, has developed the enclosed request for additional information (RAl) based on its review of the Individual Plant Examination of External Events (IPEEE) for the Vogtle Electric Generating Plant, Units 1 and 2 (Vogtle). The RAI pertains to the IPEEE information on fire and seismic vulnerabilities. There are no questions in the high wind, flood, and other external events (HFO) area of the submittal. The enclosed questions have all been reviewed by the Senior Review Board (SRB). The SRB includes NRC staff and consultants with probabilistic risk assessment expertise in external events.
You are requested to provide a response to the enclosed questions not later than January 16, 1998. If there are any questions regarding this RAI, please have your representative contact me at (301) 4151444.
Sincerely.
ORIGINAL SIGNED BY:
Louis L. Wheeler, Senior Project Manager .
Project Directorate ll 2 Division of Reactor Projects - l/Il y)I Office of Nuclest Reactor Regulation Docket Nos. 50-424 and 50-425
Enclosure:
Request for Additionallnformation cc: See next page myw g EM s "ppqgtr n opqp DISTRIBUTION M O 'u b #
9eshetMew LBerry BBoger EChow PUBLIC OGC Heerkow PDil 2 RF ACRS DWheeler OFFICE PDil 2/PM PDil 2/LA 9f) PDll 2/mg NAME LWHEELER:en L. BERRY ((7 H.B,ERK0k DATE ll)M /97 /l//l/g / /
///,k/97 COPY (VES)NO YES /b0) ES [NO/
Document Name: VOG83690.RAI OFFICIAL REDORD COPY 9711240199 971119 PDR ADOCK 05000424 PM I P i , - --- -. ,_ . - - _ .
p 7"% \ UNITED STATES l
i g
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]f NUCLEAR REGULATORY COMMISSION WASHINGTON. D.C. 3000HeH
%, / November 19, 1997 Mr. C. K. McCoy Vice President Southem Nuclear Operating Company, Inc.
P. O. Box 1295 -
Birmingham, Alabama 35201
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION ON THE INDIVIDUAL PLANT EXAMINATION OF EXTERNAL EVENTS VOGTLE ELECTRIC GENERATING ;
PLANT, UNITS 1 AND 2 (TAC NOS. M83690 AND M63691)
Dear Mr. McCoy:
The NRC staff, in conjunction with Sandia National Laboratories and Brookhaven National Laboratory, has developed the enclosed request for additionalInformation (RAl) based on its review of the Individual Plant Examination of Extemal Events (IPEEE) for the Vogtle Electric Generating Plant, Units 1 and 2 (Vogtle). The RAI pertains to the IPEEE information on fire and seismic vulnerabilities. There are no questions in the high wind, flood, and other extemal events (HFO) area of the submittal. The enclosed questions have all been reviewed by the Senior Review Board (SRB). The SRB includes NRC staff and consultants with probabilistic risk assessment expertise in extemal events.
You are requested to provide a response to the enclosed questions not later than January 16, 1998, if there are any questions regarding this RAI, please have your representative contact me at (301) 415-1444.
Sincerely, aw< . -
Louis L. Wheeler, Senior Project Manager Project Directorate ll 2 Division of Reactor Projects 1/ll Office of Nuclear Reactor Regulation Docket Nos. 50-424 and 50-425 inclosure: Request for Additional Information i
cc w/ encl: See next page
.s- . , _ _ . , , , , _., y _.-.., _ y ., _ _, ,
i s
Vogtle Electric Generating Plant oc: 1 Mr. J.' A. Bailey Harold Rehels, Director I Manager, Licensing . Departmor
- of Natural Resources Southem Nuclear Operating 205 Butler Street, SE. Suite 1252 l
Company, Inc. i_ Atlanta, Georgia 30334 P. O. Box 1295 1 ;
l Blimingham, Alabama 352011295 Attomey General l Law Department ;
Mr. J. B. Bsasley 132 Judicial Building .
e General Manager, Vogtle Eleo'ric Atlanta, Georgia 30334 !
Generating Plant ,
Southem Nuclear Operating Mr. R. D. Barker l Company, Inc. Program 'tasi;+r- - '
P. O. Box 1600 Fossil & Nuclear Operations .
Waynesboro, Gecrgia 30830 Oglethorpe Power Corporation 2100 East Exchange Place ,
Regional Administrator, hegion il P. O. Box 134g U. S. Nuclear Regulatory Tucker, Georgia 30085134g Commission Atlanta Federal Center _ Charies A. Patrizia. Esquire 61 Forsyth Street, SW., Suite 23T85 Paul, Hastings, Janofsky & Walker Atlanta, Georgia 30303 10th Floor 1299 Pennsylvania Avenue Office of Planning and Budget Washington, DC 20004 9500 ,
Room 6158 '
270 Washington Street, SW, Arthur H. Domby, Esquire
' Atlanta, Georgia 30334 Toutman Sanders NationsBank Plaza !
Mr. J. D. Woodard 600 Peachtree Street, NE. t Executiva Vice President Suite 5200 -
Southem Nuclear Operating Atlanta, Georgia 30308-2216 '
Company, Inc.
P. O. Box 1295 _ Resident inspector Birmingham, Alabama 352011295 Vogtle _
8805 River Road Steven M. Jackson Waynesboro, Georgia 30830 Senior Engineer. Power Supply
-Municipal Electric Authority Office of the County Commissioner i of Georgia Burke County Cornmission 1470 Riveredge Parkway. NW. Waynesboro, Georgia 30830 Atlanta, Georgia 30328-4684 :
E i
?
.,,...m..~,. ,, . , , . ,,,;,,.,,...-,_,__--,,_-,..,,,- _.,..--J
I o !
Request for Additional information (RAl) Related to the Vogtle individual Plant Examination of External Evente (IPEEE) i i
Vulnerabuities to Firee
- 1. The screening of propagation pathway boundaries on the basis of combustible contents is !
inappropriate for barriors rated at less than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. The submittal lists the barrier rating j between some adjacent fire zones as 1.0 and 0.25 hour2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br />. There is no technical justification (as supported by NUREG 1547,
- Methodology for Developing and .
implementing Altemative Temperature Time Curves for Testing the Fire Resistance of !
Barriers for Nuclear Power Plant Applications") to allow screening of propagation
, pathways when the only ortterion satisfied is that the estimated fire severity (in hours) is ;
less than 75% of a 1.0 or 0.25-hour rated barrier. Please reevaluate the propagation e pathways when this ortterion is eliminated for these barriers, and assess the assoolated ;
impact on the results. ;
, i
- 2. There is an apparent error in the numbers listed in Table 4.1 3 for the scenario frequencies, conditional core damage probabilities, and core damage frequencies I (CDFs). Each column of numbers appears to be high by a factor of 10. This is noted :
when comparing the numbers in the table to the description for Are zone 120 in the text, as well as when comparing the CDF values of the scenarios that were screened with the ;
screening CDF value of 4.45E 8/yr. Please confirm the correct values for these !
frequencies and probabilities. l t
- 3. Qualitative screening of some fire zones with safety-related equipment was based on the ;
argument that the fire initiation frequencies are bounded by intomal events transient and loss of offsita power initiation frequencies. This argument is valid only if the anticipated conditional core damage probabilities for the fire initiators is less than or equal to the r conditional core damage probabilities for the intamal events initiators. Please justify the scresning that was performed in this manner.
- 4. The submittal notes that automatic fire detection systems and fire suppression systems were assumed to be installed per design specifications, following National Fire Protection Association and NRC guidelines, and were assumed to be maintained regularly. The
! submittal also indicates that fire detectors were assumed to be able to detect Are signatures at their location per design specifications. Also, automatic fire suppression systems were assumed to be sized to effectively mitigate a fire of the maximum postulated size at that location. Please provide the bases for these assumptions.
r
- 5. It is important that the human error probabilities (HEPs) used in the screening phase of the analysis property renect the potential effects of flre (e.g., smoke, heat, loss of lighting, -
and poor communication), even if these effects do not directly cause equipment damage in the scenarios being analyzed, if these effecta are not treated, the HEPs may be -
optimistic and result in the improper screening of scenarios. Note that HEPs which are realistic with respect to an intomai events analysis could be optimistic with respect to a fire risk analysis, Please identify: (a) the scenarios screened out from further analysis whose quantification g
involved one or more HEPs, (b) the HEPs (descriptions and numerical values) for each of s these scenarios, and (c) how the effects (e.g., smoke, heat, loss of lighting and poor i communication) of the posWlated fires on HEPs were treated. ,
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Seismic Vulnerabilities ;
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- 1. The refueling water storage tank (RWST) is a single component with no redundancy that is used in both success paths described in the submittal. Functional failure of this tank !
due to earthquakes willlead to an unsuccessful shutdown in both paths. Although the ,
RWST is described as being highly f eliable in the submittal, quantification in terms of a !
high confidence low probability of failure (HCLPF) value, which is requested for all safe shutdown equipment list components in reduced-scope plants, is not provided. Please l provide the HCLPF calculation or some other quantitative justification why the RWST has j en HCLPF at or above the Review Level Eerthquake (RLE) of 0.30 ;
- 2. In the descript on of the primary success path, the IPEEE states that *RCP (reactor coolant pump) seal injection is established using manual valves 1206 06152/151 to preclude the occurrence of a seal LOCA [ loss of coolant accident).' No further discussion is provided. Since the development of a seal LOCA would eliminate this success path, the prevention of a seal LOCA is very important. Please discuss the systems required to prevent a seal LOCA, the operator actions required to establish the functions of these systems, and the estimated failure rates of the operator actions (considering the existing j~
plant procedures, operator training, and the time allowed for the actions). Please include in the discussion the operation of the above-mentioned manual valves.
i
- 3. For deeply embedded structures, the Vogtle IPEEE states that the original seismic analyses for a design basis es:thquake of 0.2g was sufficiently conservative to meet the requirements of an RLE of 0.3g, due to a scaling factor of 1.5 applied to the in structure response spectra. However, the purpose of the 1.5 scaling factor was to satisfy the NRC's concem, at the time of licensing, that the Standard Review Plan requirement for the deconvoluted motion to be no less than 60 percent of input motion at grade may not l have been met in the design basis analyses for deeply embedded structures. Therefore, in order to justify that sufficient margin exists in the original seismic analyses to meet an RLE of 0.30, the licensee should demonstrate that the deconvoluted motions at the foundation levels are no less than 60 percent of the input motion at grade without the annlication of the 1.5 factor. Please provide a comparison of the deconvoluted motions at the foundation levels with the specified input motion at the grade from the original seismic analyses without the scaling factor of 1.5. If the deconvoluted motions at foundation levels are less than 60 percent of the input motion at grede, please provide additional justification of why the plant HCLPF is 0.3g, or revise your estimate of the plant HCLPF ,
as appropriate. '
- 4. The following questions pertain to the shallow / surface mounted structures: ,
(a) Conflicting statements were made in the submittal regarding scaling factors applied i for shallow / surface-mounted structures. Section 3.1.3 of the submittal states *(t]he
- Instructure response spectra (IRS) were conservatively scaled up by a factor of 1.5 ,
for use in the IPEEE program.' However, Section 3.1.3.1 states "[fjor the shallow-embedded structures, the original demand peak ground acceleration (pga) equals 0.2g. If the equipment to be analyzed is flexible and the static equivalent method is used, then the peak acceleration mdtiplied by a factor from 1.0 to 1.5 could have i
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been used. For those osses, wherein the equipment is rigid, the ZPA (aero period ecceleration) could have been used.* Please provide clarification of the above :
statements and provide the scaling factor actually applied to shallow / surface.
mounted structures. ;
t'u) Per EPRI NP4041-SL requirement, linear scaling is applicable to rock sites, and .
therefore may not be applicable to the Vogtle site, which is a soil site. For soil ;
sNes, a new analysis is recommended by EPRI. To justWy the use of linear scaling, a licensee should demonstrate that the changes in composite modal damping due to l the soil-structure interaction effects will not lead to optimistic structural responses, f ,
Please provide quantified justification for the application of the scaling method to the :
Vogtle site. t
- 5. The turbine building was evaluated for seismic interaction concems because of its -
proximity to the control building. However, the screening criteria designed for Category 1 structures appear to oe improperty applied in the Vogtle IPEEE to the turbine building, !
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which is a Category ll structure. Since Category 11 structures are not designed to the -
same criteria applied to Category I structures, there is less confidence regarding the
= inherent seismic margin in the original design. Therefore, using the screening criteria for j - Categnry I structures to screen out the turbine building as having an HCLPF of 0.3g i appears to be incorrect. For the turbine building, please follow the guidance for
- evaluation of Category ll structures, as recommended in EPRI NP4041 SL and provide your results.
l- 6. The submittal states that several open items documented in Appendices 3.J and 3.K were
- scheduled for closure by August 1,1996, i.e., after the IPEEE submittal had been l completed and forwarded to the NRC. Please provide the status of these items scheduled for closure. For the closed items please provide the details of their resolution.
High Wind, Flood, and Other External Events (HFO) ?
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i There is no RAIin the HFO area.
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