Letter Sequence RAI |
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MONTHYEARML20153B9311998-09-16016 September 1998 Forwards RAI Re GL 97-01, Degradation of Crdm/Cedm Nozzle & Other Vessel Closure Head Penetrations, Responses for Plant,Units 1 & 2 Project stage: RAI 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 Project stage: Other 1998-12-16
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217P3791999-10-21021 October 1999 Forwards NRC Form 396 & NRC Form 398 for Renewal of Licenses SOP-20607-1 & SOP-20610-1.Without Encls ML20217N2521999-10-20020 October 1999 Provides Supplemental Info Re 990405 Containment Insp Program Requests for Relief RR-L-1 & RR-L-2,in Response to 991013 Telcon with NRC ML20217K7541999-10-15015 October 1999 Forwards Rev 1 to Unit 1,Cycle 9 & Unit 2 Cycle 7 Colrs,Iaw Requirements of TS 5.6.5.Figure 5, Axial Flux Difference Limits as Function of Percent of Rated Thermal Power for RAOC, Was Revised for Both Units ML20217G6751999-10-13013 October 1999 Requests Withholding of Proprietary Info Contained in Application for Amend to OLs to Implement Relaxations Allowed by WCAP-14333-P-A,rev 1 ML20217G1071999-10-0707 October 1999 Informs That on 990930,NRC Staff Completed mid-cycle PPR of Vogtle & Did Not Identify Any Areas in Which Performance Warranted More than Core Insp Program.Nrc Plans to Conduct Core Insps at Facility Over Next Six Months ML20216J9041999-10-0101 October 1999 Forwards Response to RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves ML20216J9161999-10-0101 October 1999 Forwards Response to NRC 990723 RAI Re GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves ML20217B0141999-10-0101 October 1999 Forwards Insp Repts 50-424/99-06 & 50-425/99-06 on 990725- 0904 at Vogtle Units 1 & 2 Reactor Facilities.Determined That One Violation Occurred & Being Treated as non-cited Violation ML20212E8751999-09-20020 September 1999 Forwards Response to NRC GL 99-02, Lab Testing of Nuclear Grade Activated Charcoal. Description of Methods Used to Comply with Std Along with Most Recent Test Results Encl ML20212E7481999-09-20020 September 1999 Requests Approval Per 10CFR50.55a to Use Alternative Method for Determining Qualified Life of Certain BOP Diaphragm Valves than That Specified in Code Case N-31.Proposed Alternative,Encl ML20212C2191999-09-16016 September 1999 Forwards NRC Form 536, Operator Licensing Exam Data, Which Is Current Need for NRC Operator Licensing Exams for Years 2000 Through 2003 of Plant Vogtle,Per Administrative Ltr 99-03 ML20211Q4801999-09-0101 September 1999 Informs That on 990812-13,Region II Hosted Training Managers Conference on Recent Changes to Operator Licensing Program. List of Attendees,Copy of Slide Presentations & List of Questions Received from Participants Encl ML20211J5291999-08-30030 August 1999 Forwards Snoc Copyright Notice Dtd 990825,re Production of Engineering Drawings Ref in VEGP UFSAR ML20211J5251999-08-30030 August 1999 Forwards Response to NRC 990727 RAI Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions ML20211J7381999-08-27027 August 1999 Informs That Licensee Vessel Data Is Different than NRC Database Based on Listed Info,Per 990722 Request to Review Rvid ML20211E9251999-08-23023 August 1999 Forwards fitness-for-duty Performance Data for Jan-June 1999,as Required by 10CFR26.71(d).Data Reflected in Rept Covers Employees at Vogtle Electric Generating Plant ML20210V0881999-08-16016 August 1999 Forwards Insp Repts 50-424/99-05 & 50-425/99-05 on 990620- 0724.No Violations Noted.Vogtle Facility Generally Characterized by safety-conscious Operations,Sound Engineering & Maintenance Practices ML20210Q4611999-08-0505 August 1999 Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licensing Exam on 991006 for Vogtle.Requests Info Re Individuals Who Will Take Exam. Sample Registration Ltr Encl ML20210L2181999-08-0202 August 1999 Forwards NRC Form 396 & Form 398 for Renewal of Listed Licenses,Iaw 10CFR55.57.Without Encl ML20210N1191999-08-0202 August 1999 Discusses 990727 Telcon Between Rs Baldwin & R Brown Re Administration of Licensing Exam at Facility During Wk of 991213 ML20210G3351999-07-27027 July 1999 Forwards Second Request for Addl Info Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions ML20210E0121999-07-23023 July 1999 Forwards Second Request for Addl Info Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves ML20210D9341999-07-22022 July 1999 Discusses Closure of TACs MA0581 & MA0582,response to Requests for Info in GL 92-01,rev 1,suppl 1, Reactor Vessel Structural Integrity ML20210C8011999-07-21021 July 1999 Provides Response to NRC AL 99-02,which Requests That Addressees Submit Info Pertaining to Estimates of Number of Licensing Actions That Will Be Submitted for NRC Review for Upcoming Fy 2000 & 2001 ML20210E0431999-07-15015 July 1999 Forwards Insp Repts 50-424/99-04 & 50-425/99-04 on 990502- 0619.Two Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20209H3881999-07-14014 July 1999 Forwards Revs 1 & 2 to ISI Program Second 10-Year Interval Vogtle Electric Generating Plant Unit 1 & 2 ML20209C4041999-07-0101 July 1999 Forwards Rev 29 to VEGP Units 1 & 2 Emergency Plan.Rev 29 Incorporates Design Change Associated with Consolidation of Er Facilities Computer & Protues Computer.Justifications for Changes & Insertion Instructions Are Encl ML20196H8081999-06-28028 June 1999 Discusses 990528 Meeting Re Results of Periodic PPR for Period of Feb 1997 to Jan 1999.List of Attendees Encl ML20212J2521999-06-21021 June 1999 Responds to NRC RAI Re Yr 2000 Readiness at Nuclear Power Plants.Gl 98-01 Requested Response on Status of Facility Y2K Readiness by 990701 ML20196F9171999-06-21021 June 1999 Forwards Owner Rept for ISI for Vogtle Electric Generating Plant,Unit 1 Eighth Maint/Refueling Outage. Separate Submittal Will Not Be Made to NRC on SG Tubes Inspected During Subj Outage ML20195F8031999-06-11011 June 1999 Forwards Changes to VEGP Unit 1 Emergency Response Data Sys (ERDS) Data Point Library.Changes Were Completed on 990308 While Unit 1 Was SD for Refueling Outage ML20207E7421999-06-0303 June 1999 Refers to from NRC Which Issued Personnel Assignment Ltr to Inform of Lm Padovan Assignment as Project Manager for Farley Npp.Reissues Ltr with Effective Date Corrected to 990525 ML20207F6201999-06-0202 June 1999 Sixth Partial Response to FOIA Request for Documents.Records in App J Encl & Will Be Available in Pdr.App K Records Withheld in Part (Ref FOIA Exemptions 7) & App L Records Completely Withheld (Ref FOIA Exemption 7) ML20207D9861999-05-28028 May 1999 Informs That,Effective 990325,LM Padovan Was Assigned as Project Manager for Plant,Units 1 & 2 ML20207D2701999-05-19019 May 1999 Forwards Insp Repts 50-424/99-03 & 50-425/99-03 on 990321- 0501.One Violation of NRC Requirements Identified & Being Treated as non-cited Violation Consistent with App C of Enforcement Policy ML20206M5141999-05-11011 May 1999 Informs That NRC Ofc of Nuclear Regulation Reorganized Effective 990328.As Part of Reorganization,Div of Licensing Project Mgt Created.Rl Emch Section Chief for Vogtle. Reorganization Chart Encl ML20206U4061999-05-11011 May 1999 Confirms Telcon with J Bailey Re Mgt Meeting Scheduled for 990528 to Discuss Results of Periodic Plant Performance Review for Plan Nuclear Facility Fo Period of Feb 1997 - Jan 1999 05000424/LER-1998-006, Forwards LER 98-006-03 Re Motor Control Ctr Breaker Buckets Not Being Seismically Qualified.Rev Is Submitted to Document Results of Seismic Testing That Demonstrated That No Condition Outside Design Basis of TS Requirements Exi1999-05-10010 May 1999 Forwards LER 98-006-03 Re Motor Control Ctr Breaker Buckets Not Being Seismically Qualified.Rev Is Submitted to Document Results of Seismic Testing That Demonstrated That No Condition Outside Design Basis of TS Requirements Existed ML20206D6411999-04-29029 April 1999 Forwards Vogtle Electric Generating Plant Radiological Environ Operating Rept for 1998 & Vogtle Electric Generating Plant Units 1 & 2 1998 Annual Rept Annual Radioactive Effluent Release Rept ML20206D5881999-04-29029 April 1999 Forwards Rept Which Summarizes Effects of Changes & Errors in ECCS Evaluation Models on PCT for 1998,per Requirements of 10CFR50.46(a)(3)(ii).Rept Results Will Be Incorporated Into Next FSAR Update ML20206D6951999-04-28028 April 1999 Provides Update of Plans for VEGP MOV Periodic Verification Program Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs ML20206C2241999-04-21021 April 1999 Forwards Revised Monthly Operating Repts for Mar 1999 for Vogtle Electric Generating Plant,Units 1 & 2.Page E2-2 Was Iandvertently Omitted from Previously Submitted Rept on 990413 ML20206A6371999-04-21021 April 1999 Forwards SE Authorizing Licensee Re Rev 9 to First 10-yr ISI Interval Program Plan & Associated Requests for Relief (RR) 65 from ASME Boiler & Pressure Vessel Code ML20205Q3351999-04-15015 April 1999 Forwards Insp Repts 50-424/99-02 & 50-425/99-02 on 990214-0320.Three Violations Identified & Being Treated as Non-Cited Violations ML20205T2351999-04-0909 April 1999 Informs That on 990317,B Brown & Ho Christensen Confirmed Initial Operator Licensing Exam Scheduled for Y2K.Initial Exam Date Scheduled for Wk of 991213 for Approx 10 Candidates ML20205K7501999-04-0505 April 1999 Informs That Effective 990329,NRC Project Mgt Responsibility for Plant Has Been Transferred from Dh Jaffe to R Assa ML20209A3741999-04-0505 April 1999 Submits Several Requests for Relief for Plant from Code Requirements Pursuant to 10CFR50.55a(a)(3) & (g)(5)(iii).NRC Is Respectfully Requested to Approve Requests Prior to Jan 1,2000 ML20205H3481999-03-31031 March 1999 Forwards Georgia Power Co,Oglethorpe Power Corp,Municipal Electric Authority of Ga & City of Dalton,Ga Status of Decommissioning Funding for Each Reactor or Part of Reactor Owned for OLs NPF-68 & NPF-81 ML20205F9091999-03-29029 March 1999 Submits Rept of Number of SG Tubes Plugged During Plant Eighth Maintenance/Refueling Outage (1R8).Inservice Insps Were Completed on SGs 1 & 4 on 990315.No Tubes Were Plugged ML20205G0761999-03-26026 March 1999 Provides Results of Individual Monitoring for 1998.Encl Media Contains All Info Required by Form NRC 5.Without Encl 1999-09-20
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217G1071999-10-0707 October 1999 Informs That on 990930,NRC Staff Completed mid-cycle PPR of Vogtle & Did Not Identify Any Areas in Which Performance Warranted More than Core Insp Program.Nrc Plans to Conduct Core Insps at Facility Over Next Six Months ML20217B0141999-10-0101 October 1999 Forwards Insp Repts 50-424/99-06 & 50-425/99-06 on 990725- 0904 at Vogtle Units 1 & 2 Reactor Facilities.Determined That One Violation Occurred & Being Treated as non-cited Violation ML20211Q4801999-09-0101 September 1999 Informs That on 990812-13,Region II Hosted Training Managers Conference on Recent Changes to Operator Licensing Program. List of Attendees,Copy of Slide Presentations & List of Questions Received from Participants Encl ML20210V0881999-08-16016 August 1999 Forwards Insp Repts 50-424/99-05 & 50-425/99-05 on 990620- 0724.No Violations Noted.Vogtle Facility Generally Characterized by safety-conscious Operations,Sound Engineering & Maintenance Practices ML20210Q4611999-08-0505 August 1999 Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licensing Exam on 991006 for Vogtle.Requests Info Re Individuals Who Will Take Exam. Sample Registration Ltr Encl ML20210N1191999-08-0202 August 1999 Discusses 990727 Telcon Between Rs Baldwin & R Brown Re Administration of Licensing Exam at Facility During Wk of 991213 ML20210G3351999-07-27027 July 1999 Forwards Second Request for Addl Info Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions ML20210E0121999-07-23023 July 1999 Forwards Second Request for Addl Info Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves ML20210D9341999-07-22022 July 1999 Discusses Closure of TACs MA0581 & MA0582,response to Requests for Info in GL 92-01,rev 1,suppl 1, Reactor Vessel Structural Integrity ML20210E0431999-07-15015 July 1999 Forwards Insp Repts 50-424/99-04 & 50-425/99-04 on 990502- 0619.Two Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20196H8081999-06-28028 June 1999 Discusses 990528 Meeting Re Results of Periodic PPR for Period of Feb 1997 to Jan 1999.List of Attendees Encl ML20207E7421999-06-0303 June 1999 Refers to from NRC Which Issued Personnel Assignment Ltr to Inform of Lm Padovan Assignment as Project Manager for Farley Npp.Reissues Ltr with Effective Date Corrected to 990525 ML20207F6201999-06-0202 June 1999 Sixth Partial Response to FOIA Request for Documents.Records in App J Encl & Will Be Available in Pdr.App K Records Withheld in Part (Ref FOIA Exemptions 7) & App L Records Completely Withheld (Ref FOIA Exemption 7) ML20207D9861999-05-28028 May 1999 Informs That,Effective 990325,LM Padovan Was Assigned as Project Manager for Plant,Units 1 & 2 ML20207D2701999-05-19019 May 1999 Forwards Insp Repts 50-424/99-03 & 50-425/99-03 on 990321- 0501.One Violation of NRC Requirements Identified & Being Treated as non-cited Violation Consistent with App C of Enforcement Policy ML20206M5141999-05-11011 May 1999 Informs That NRC Ofc of Nuclear Regulation Reorganized Effective 990328.As Part of Reorganization,Div of Licensing Project Mgt Created.Rl Emch Section Chief for Vogtle. Reorganization Chart Encl ML20206U4061999-05-11011 May 1999 Confirms Telcon with J Bailey Re Mgt Meeting Scheduled for 990528 to Discuss Results of Periodic Plant Performance Review for Plan Nuclear Facility Fo Period of Feb 1997 - Jan 1999 ML20206A6371999-04-21021 April 1999 Forwards SE Authorizing Licensee Re Rev 9 to First 10-yr ISI Interval Program Plan & Associated Requests for Relief (RR) 65 from ASME Boiler & Pressure Vessel Code ML20205Q3351999-04-15015 April 1999 Forwards Insp Repts 50-424/99-02 & 50-425/99-02 on 990214-0320.Three Violations Identified & Being Treated as Non-Cited Violations ML20205T2351999-04-0909 April 1999 Informs That on 990317,B Brown & Ho Christensen Confirmed Initial Operator Licensing Exam Scheduled for Y2K.Initial Exam Date Scheduled for Wk of 991213 for Approx 10 Candidates ML20205K7501999-04-0505 April 1999 Informs That Effective 990329,NRC Project Mgt Responsibility for Plant Has Been Transferred from Dh Jaffe to R Assa ML20205B9601999-03-24024 March 1999 Seventh Partial Response to FOIA Request for Documents. Records in App N Already Available in Pdr.App O Records Being Released in Entirety & App P Records Being Withheld in Part (Ref FOIA Exemptions 7C,2 & 5) ML20205A2771999-03-19019 March 1999 Advises of NRC Planned Insp Effort Resulting from Vogtle PPR on 990208.PPR for Plant Involved Participation of All Technical Divs in Evaluating Insp Results & Safety Performance Info for Period of Dec 1997 - Jan 1999 ML20207L8281999-03-0808 March 1999 Forwards Partially Withheld Insp Repts 50-424/99-01 & 50-425/99-01 & Notice of Violation ML20207J0431999-03-0303 March 1999 Forwards Insp Repts 50-424/98-10 & 50-425/98-10 on 981227- 990213.No Violations Noted.Licensee Conduct of Activities at Vogtle Facility Generally Characterized by safety-conscious Operations,Sound Engineering & Maint Practices ML20203G5691999-02-0505 February 1999 Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licensing Exam on 990407. Representative of Facility Must Submit Ltr Indicating No Candidates or Ltr Listing Names of Candidates for Exam ML20202H9691999-01-29029 January 1999 Forwards Safety Evaluation Authorizing Rev 8 to First 10-year Interval Inservice Insp Program & Associated Requests for Relief for Vogtle Electric Generating Plant, Unit 1 ML20199J7931999-01-20020 January 1999 Forwards Insp Repts 50-424/98-09 & 50-425/98-09 on 981115-1226 at Vogtle Units 1 & 2.No Violations Were Identified.Conduct of Activities at Vogtle Was Generally Characterized by safety-conscious Operations ML20199K1381999-01-12012 January 1999 Informs That on 990117,Region II Implemented Staff Reorganization as Part of agency-wide Streamlining Effort, Due to Staffing Reductions in FY99 Budget.Organization Charts Encl ML20198S1601998-12-31031 December 1998 Forwards SER of Licensee Second 10-year Interval Inservice Insp Program Plan & Associated Requests for Relief for Vogtle Electric Generating Plant Submitted on 970529. INEEL/EXT-98-01007 Rept Also Encl ML20199E4741998-12-23023 December 1998 Provides Summary of 981105 Training Managers Conference Held in Atlanta,Georgia.Conference Agenda,List of Conference Attendees,Presentation Slides & Preliminary Schedule for FY99 & FY00 Encl ML20199J9781998-12-22022 December 1998 Responds to 981209 Meeting Re Installation of Seismic Clips on Cutler Hammer Electrical Circuit Breakers.Forwards List of Attendees & Handouts ML20198F6711998-12-11011 December 1998 Forwards Insp Repts 50-424/98-08 & 425/98-08 on 980927-1114. No Violations Identified ML20198N9431998-12-10010 December 1998 Ack Receipt of Response, to NOV Issued on 980112 Re Surveillance Testing of Reactor Trip Sys P-4 Interlock Feature at Licensee Facility.Nrc Agrees That Surveillance Testing Not Required ML20196J2181998-12-0101 December 1998 Advises of Planned Insp Effort Resulting from 981102 Insp Planning Meeting.Historical Listing of Plant Issues Called Plant Issues Matrix & Insp Plan,Including Specific Insps Such as in Security & Radiological Protection Areas Encl ML20196J2581998-12-0101 December 1998 Confirms Arrangements Made Between J Bailey & B Holbrook, Re Info Meeting Scheduled for 990210 to Discuss Licensee Performance,New Initiatives & Other Regulatory Issues Pertaining to Listed Facilities ML20196B1231998-11-23023 November 1998 Confirms Telephone Conversation Between J Bailey & P Skinner on 981120 Re Info Meeting Which Has Been Scheduled for 981209 in Atlanta,Ga,To Discuss Issues Re Seismic Retainer Clips ML20196D4981998-11-13013 November 1998 Informs That on 981007,NRC Administered Gfes of Written Operator Licensing Examination.Copy of Answer Key & Master Bw/Pwr GFE Encl,Even Though Facility Did Not Participate in Exam.Without Encl ML20195B3391998-11-0909 November 1998 Forwards Partially Withheld Insp Repts 50-424/98-12 & 50-425/98-12 on 981005-09 (Ref 10CFR73.21).No Violations Noted.Conduct of Activities Generally Characterized by safety-conscious Operations & Sound Engineering ML20155H2501998-10-21021 October 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-424/98-05 & 50-425/98-05 Issued on 980723.Concluded for Reasons Stated That Example 2 Violation Occurred as Stated in NOV ML20155A7491998-10-15015 October 1998 Forwards Insp Repts 50-424/98-07 & 50-425/98-07 on 980816-0926 & Nov.Insp Generally Characterized by Safety Conscious Operations,Sound Engineering & Maint Practices & Appropriate Radiological Controls ML20155B7771998-10-0909 October 1998 Extends Invitation to Attend Training Manager Conference on 981105 in Atlanta,Georgia.Conference Designed to Inform Regional Training & Operations Mgt of Issues & Policies That Effect Licensing of Reactor Plant Operators ML20155B4621998-09-25025 September 1998 Discusses OI Investigation Which Completed on 980728. Investigation Reviewed Circumstances Surrounding Apparent Disabling of Fire Computer Trouble Alarm by Unit Shift Supervisor.Concludes Enforcement Discretion Warranted ML20153B0401998-09-17017 September 1998 Responds to 980904 e-mail Message Making Certain Observations Re Apparent Increase in Reactor Trips at Plant, Units 1 & 2.NRC Concluded That Licensee post-trip Reviews Adequately Conducted & That No Adverse Trends,Apparent ML20153B9311998-09-16016 September 1998 Forwards RAI Re GL 97-01, Degradation of Crdm/Cedm Nozzle & Other Vessel Closure Head Penetrations, Responses for Plant,Units 1 & 2 ML20153F7081998-09-11011 September 1998 Provides Summary of 980909 Meeting Held to Discuss TS & Other Regulatory Issues Re Vogtle Electric Generating Plant. List of Meeting Attendees & Copy of Presentation Slides Encl ML20154C4871998-09-10010 September 1998 Forwards Insp Repts 50-424/98-06 & 50-425/98-06 on 980628-0815 & Nov.One Violation Involved Failure to Implement Adequate C/As for Repeated Failures to Enter Applicable TS Limiting Conditions for Operation ML20151U7901998-09-0909 September 1998 Discusses 980615 Request for Exemption from Requirement of 10CFR73.55(e)(1) & (f)(1) to Provide Continuous Staffing of Plant CAS During Contingency Events.Request Denied ML20151S7291998-09-0202 September 1998 Discusses Evaluation of Util Response to GL 97-05 for Plant, Units 1 & 2.NRC Did Not Identify Any Concerns W/Sg Tube Insp Techniques Employed at Plant ML20239A4251998-08-27027 August 1998 Informs of Change Being Implemented by Region II Re Administrative Processing of Licensee Responses to Nov.Nov Responses Will Be Formally Ack as Part of Periodically Issued Integrated Insp Repts 1999-09-01
[Table view] |
Text
, _ - _ . _ _ - . . _ ___. . __ _ _ _ _ _ . _ . ,
. y ,,
p 4 UNITED STATES
- r
{ NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 3000H001
%*****# September 16, 1998 [8 d[ #[$5 Mr. J. B. Beasley, Jr.
Vice President Southern Nuclear Operating Company, Inc. -
Post Office Box 1295
- Birmingham, Alabama 35201-1295
SUBJECT:
GENERIC LETTER (GL) 97-01, " DEGRADATION OF CRDM/CEDM NOZZLE AND OTHER VESSEL CLOSURE HEAD PENETRATIONS" RESPONSES FOR VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2 (TAC NOS.
M98608 AND M98609)
Dear Mr. Beasley:
i On April 1,1997, the staff issued Generic Letter (GL) 97-01, " Degradation of CRDM/CEDM
[ Control Rod Drive Mechanism / Control Element Drive Mechanism) Nozzle and Other Vessel l Closure Head Penetrations," to the industry requesting, in part, that addressees provide a description of the plans to inspect the vessel head penetration (VHPs) nozzles at their respective pressurized water reactor (PWR) designed plants. With respect to the issuance of the GL, the staff required the addressees to submit an initial response within 30 days of issuance informing the staff of the intent to comply with the requested information and a followup response within 120 days of issuance containing the technical details to the staff's information requests. In the discussion section of the GL, the staff stated that " individual .
licensees may wish to determine their inspection activities based on an integrated industry I inspection program...," and indicated that it did not object to individual PWR licensees basing their inspection activitik on an integrated industry inspection program. /
As a result, the Westinghouse Owners Group (WOG) determined that it was appropriate for its I members to develop a cooperative integrated inspection program in response to GL 97-01.
The WOG program is documented in two Topical Reports issued by the Westinghouse Electric Corporation (WEC), WCAP-14901, Revision 0, " Background and Methodology for Evaluation ofh Reactor Vessel Closure Head Penetration integrity for the Westinghouse Owners Group " and WCAP-14902, Revision 0, " Background Material for Response to NRC Generic Letter 97-01: l Reactor Vessel Closure Head Penetration integrity for the Westinghouse Owners Group."
The WOG submitted the integrated programs desenbed in WCAP-14901 and WCAP-14902 to l the staff on July 25,1997.
)
i The staff has determined by letters dated April 28,1997, and July 24,1997, that you were a '
member of the WOG and a participant in the WOG integrated program that was developed to ,
address the staffs requests in GL 97-01. In your letters of April 28,1997, and July 24,1997, l you also indicated that the information in WEC Topical Report WCAP-14901 is applicable with j respect to the assessment of VHP nozzles at Vogtle, Units 1 and 2.
9809230289 980916 PDR ADOCK 05000424 p PDR o f
J. B. Beasley, Jr. September 16, 1998 l
The staff has reviewed your responses to GL 97-01, dated April 28,1997, and July 24,1997, and requires further information to complete its review of your responses as they relato to the WOG's integrated program for assessing VHP nozzles at WOG member plants, and to the contents of Topical Report WCAP-14901. The enclosure to this letter forwards the staff's inquiries in the form of a request for additional information (RAI).
l The staff requests a response to the RAI within 90 days of the receipt of this letter. It should be l noted that similar staff requests have been issued to other WOG member utilities. As was the staff's position before, the staff encourages you to address these inquiries in integrated fashion l with the WOG and the Nuclear Er>ergy Institute; however, the staff also requests that you identify any deviations from the WOG's integrated program that may be specific to your facilities. The staff appreciates the efforts expended with respect to this matter.
Sincerely, l ORIGINAL SIGNED BY:
David H. Jaffe, Senior Project Manager Project Directorate 11-2 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation Docket Nos. 50-424 and 50-425
Enclosure:
Request for Additional Information cc w/enci: See next page DISTRIBUTION-Docket File EJSullivan PSkinner, Rll PUBLIC OGC PD 11-2 Rdg. ACRS JZwolinski LPlisco, Ril DOCUMENT NAME: G:WOGTLE\M98608.RAI To receive a copy of this document, indicate in the box: "C" = Copy without enclosure "E" = Copy with cttachmenMgdre "N" = No copy s OFFICE P%Pp)[ E LA:PD R ly D:P h l NAME DJ@l$r%) LBerry, Vly' HBefko$/
DATE Q 4Q98 4 /l998 O Iip /9b i '
OFFICIAL RECORD COPY
4 J. B. Beasley, Jr. The staff has reviewed your responses to GL 97-01, dated April 28,1997, and July 24,1997, and requires further information to complete its review of your responses as they relate to the WOG's integrated program for assessing VHP nozzles at WOG member plants, and to the contents of Topical Report WCAP-14901. The enclosure to this letter forwards the staff's inquiries in the form of a request for additional ihformation (RAI).
The staff requests a response to the RAI within 90 days of the receipt of this letter. It should be noted that cimilar staff requests have been issued to other WOG member utilities. As was the staff's position before, the staff encourages you to address these inquiries in integrated fashion with the WOG and the Nuclear Energy Institute; however, the staff also requests that you identify any deviations from the WOG's integrated program that may be specific to your facilities. The staff appreciates the efforts expended with respect to this matter.
Sincerely, m ,
\'
\
\
_'+r '
_( fj
'./
David H. Jaffe, Senior Project Manager Project Directorate 11-2 Division of Reactor Projects - 1/ll Office of Nuclear Reactor Regulation i Docket Nos. 50-424 and 50-425 l
Enclosure:
Request for Additional Information cc w/ encl: See next page
, Vogtle Electric Generating Plant i
f cc: Harold Reheis, Director Mr. J. A. Bailey Department of Natural Resources Manager, Licensing 205 Butler Street, SE. Suite 1252 Southem Nuclear Operating Atlanta, Georgia 30334 Company, Inc.
P. O. Box 1295 Attomey General i Birmingham, Abbama 35201-1295 Law Department 132 Judicial Building
- Mr. J. Gasser. Atlanta, Georgia 30334
- General Manager, Vogtle Electric Generating Plant Mr. R. D. Barker
. Southem Nuclear Operating Program Manager Company, Inc. Fossil & Nuclear Operations P. O.. Box 1600 Oglethorpe Power Corporation j Waynesboro, Georgia 30830 2100 East Exchange Place P. O. Box 1349 ,
Regional Administrator, Region ll Tucker, Georgia 30085-1349 U. S. Nuclear Regulatory '
Commission Charles A. Patrizia, Esquire Atlanta Federal Center Paul, Hastings, Janofsky & Walker.
61 Forsyth Street, SW., Suite 23T85 10th Floor Atlanta, Georgia 30303 1299 Pennsylvania Avenue Washington, DC 20004-9500 Office of Planning and Budget Room 615B Arthur H. Domby, Esquire 270 Washington Street, SW. Troutman Sanders Atlanta, Georgia 30334 NationsBank Plaza 600 Peachtree Street, NE.
Mr. J. D. Woodard Suite 5200 Executive Vice President Atlanta, Georgia 30308-2216 Southem Nuclear Operating
. Company, Inc. Resident inspector P. O. Box 1295 Vogtle Plant j Birmingham, Alabama 35201-1295 8805 River Road i Waynesboro, Georgia 30830 Steven M. Jackson Senior Engineer - Power Supply Office of the County Commissioner Municipal Electric Authority Burke County Commission of Georgia Waynesboro, Georgia 30830 1470 Riveredge Parkway, NW.
Atlanta, Georgia 30328-4684 l
1 t
', 1 l
Raouest for Additional Information Reaardina Utilities Particioatina Resoonse to Generic Letter 97-01 "Backaround and Methodoloav for Evaluation of Reactor Vessel Closure Head Penetration Intearity for the Westinohouse Owners Grouo" Tooical Report WCAP-14901. Revision 0 l
l
- l. Relationship and Appiicability of WCAP-14901, Revision 0, to Generic Letter 97-01 and the Westinghouse Owners Group (WOG)
On April 1,1997, the staff issued Generic Letter (GL) 97-01, " Degradation of CRDM/CEDM
[ Control Rod Drive Mechanism / Control Element Drive Mechanism] Nozzle and Other Vessel ,
i Closure Head Penetrations," to the industry requesting, in part, that addressees provide a l description of the plans to inspect the vessel head penetration (VHPs) nozzles at their respective pressurized water reactor (PWR) designed pints. With respect to the issuance of the GL, the staff required the addressees to submit an initial response within 30 days of l !ssuance informing the staff of the intent to comply with the requested information and a l
followup response within 120 days of issuance containing the technical details to the staff's information requests. In the discussion section of the GL, the staff stated that " individual licensees may wish to determine their inspection activities based on an integrated industry inspection program...," and indicated that it did not object to individual PWR licensees basing l their inspection activities on an integrated industry inspection program.
As a result, the WOG determined that it was appropriate for its members to develop a cooperative integrated inspection program in response to GL 97-01. The WOG program is l
' documented in two Topical Reports issued by the Westinghouse Electric Corporation (WEC),
WCAP-14901, Revision 0, " Background and Methodology for Evaluation of Reactor Vessel Closure Head Penetration Integrity for the Westinghouse Owners Group," and WCAP-14902, Revision 0, " Background Material for Response to NRC Generic Letter 97-01: Reactor Verel Closure Head Penetration Integrity for the Westinghouse Owners Group."
The technical content provided in WCAP-14901, Revision 0, is basically the same as that provided in WCAP-14902. The difference with regard to the reports is that WOG member plants subscribing to the content of WCAP-14901 have opted to rank the susceptibility of their VHPs according to a probabilistic Weibull analysis method that was developed by WEC. In contrast, the WOG member plants subscribing to the content of WCAP-14902, Revision 0, have l opted to rank the VHPs for their facilities according to a probabilistic methodology that was developed by another vendor of choice. The staff has determined by letters dated April 28,
~ 1997, and July 24,1997, that you were a member of the WOG and a participant in the WOG integrated program that was developed to address the staff's requests in GL 97-01. In your I letters dated April 28,1997, and July 24,1997, you also indicated that the information in WEC
! Topical Report WCAP-14901 is applicable with respect to the assessment of VHP nozzles at
[ Vogtle, Units 1 and 2.
l
( Enclosure
e- :'
The staff has reviewed your responses to GL 97-01, dated April 28,1997, and July 24,1997, and requires further information to complete its review of your responses as they relate to the
' WOG's integrated program for assessing VHP nozzles at WOG member plants, and to the contents of Topical Report WCAP-14901. The staff requests the following information with respect to the content of your responses to GL 97-01, and to the content of WCAP-14901 as it relates to these responses:
- 1. In WCAP-14901, WEC did not provide any conclusions as to what the probabilistic failure model would lead the WOG to conclude with respect to the assessment of primrry water stress-corrosion cracking (PWSCC) in WEC-designed vessel head penetrations. W;th respect to the probabilistic susceptibility model (e.g., probabilistic failure model) provided in WCAP-14901:
- a. Provide the susceptibility rankings compiled for the WOG member plants for which WCAP-14901 is applicable. In regard to other WOG member plants to which WCAP-14901 is applicable, include the basis for establishing the ranking of your plant relative to the others.
- b. Describe how the probabilistic failure model in WCAP-14901 for assessinq postulated flaws in VHP nozzles was benchmarked, and provide a list and discussi' of the standards the model was benchmarked against.
- c. Provide additional information regarding how the probabilistic failure mcJels in l WCAP-14901 will be refined to allow the input of plant-specific inspection data into the model's analysis methocology.
- d. Describe how the variability in product forms, material specifications, and heat treatments used to fabricate each CRDM penetration nozzle at the WOG member utilities are addressed in the probabilistic crack initiation and growth models described or ,
referenced in Topical Report WCAP-14901.
- 2. Table 1-2 in WCAP-14901 provides a summary of the key tasks in WEC's VHP nozzle assessment program. The table indicates that the Tasks for (1) Evaluation of PWSCC Mitigation Methods, (2) Crack Growth Data arid Testing, and (3) Crack initiation Characterization Studies have not been completed and are stillin progress. In light of the fact that the probabilistic susceptibility models appear to be dependent, in part, on PWSCC crack initiation and growth estimates, provide your best estimate when these tasks will be completed by WEC, ar'd describe how these activities relate to and will be used to update the probabilistic susceptibility assessment of VHP nozzles at your plant.
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- 3. In the NEl letters of January 29,1998 (Ref.1), and April 1,1998 (Ref. 2), NEl Indicated that inspection plans have been developed for the VHP noules at the Farley Unit 2 plant in the year 2002, and at the Diablo Canyon Unit 2 plant in the year 2001, respectively. The staff has noted that although you have endorsed the probabilistic susceptibility model described in WCAP-14901, Revision 0, other WOG member licensees have endorsed a probabilistic susceptibility model developed by an alternate vendor of choice. The WOG's proposal to inspect the VHP nonles at the Farley Unit 2 and Diablo Canyon Unit 2 plants appears to be based on a composite assessment of the VHP nozzles at all WOG member plants. Verify that such a composite ranking assessment has been applied to the evaluation of VHP nonles at your plant. If composite rankings of the VHP nonles at WOG member plants have been obtained from the composite results of the two models, justify why application of the probabilistic susceptibility model described in WCAP-14901, Revision 0, would yield the same comparable relative rankings of the VHP nonles for your plant as would application of the altemate probabilistic susceptibility model used by the WOG member plants not subscribing to WCAP-14901, Revision 0. Comment on the susceptibility rankings of the VHP noules at your plant relative to the susceptibility rankings of the VHP nonles at the Farley Unit 2 and Diablo Canyon Unit 2 plants.
REFERENCES
- 1. January 19,1998 - Letter from David J. Modeen, Director of Engineering, Nuclear Generation Division, Nuclear Energy Institde, to Mr. G. C. Lainas, Acting Director, Division I of Engineering, Office of Nuclear Reactor Re.gulation, U.S. Nuclear Regulatory Commission I (Untitled). ,
- 2. April 1,1995 - Letter from David J. Modeen, Director of Engineering, Nuclear Generation ,
Division, Nuclear Energy Institute, to Mr. G. C. Lainas, Acting Director, Division of I Engineering, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission,
SUBJECT:
Generic Letter 97-01, ' Degradation of Control Rod Drive Mechanism Nonle and Other Vessel Head Penetrations.'"
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