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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217P3791999-10-21021 October 1999 Forwards NRC Form 396 & NRC Form 398 for Renewal of Licenses SOP-20607-1 & SOP-20610-1.Without Encls ML20217N2521999-10-20020 October 1999 Provides Supplemental Info Re 990405 Containment Insp Program Requests for Relief RR-L-1 & RR-L-2,in Response to 991013 Telcon with NRC ML20217K7541999-10-15015 October 1999 Forwards Rev 1 to Unit 1,Cycle 9 & Unit 2 Cycle 7 Colrs,Iaw Requirements of TS 5.6.5.Figure 5, Axial Flux Difference Limits as Function of Percent of Rated Thermal Power for RAOC, Was Revised for Both Units ML20217G6751999-10-13013 October 1999 Requests Withholding of Proprietary Info Contained in Application for Amend to OLs to Implement Relaxations Allowed by WCAP-14333-P-A,rev 1 ML20217G1071999-10-0707 October 1999 Informs That on 990930,NRC Staff Completed mid-cycle PPR of Vogtle & Did Not Identify Any Areas in Which Performance Warranted More than Core Insp Program.Nrc Plans to Conduct Core Insps at Facility Over Next Six Months ML20216J9041999-10-0101 October 1999 Forwards Response to RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves ML20216J9161999-10-0101 October 1999 Forwards Response to NRC 990723 RAI Re GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves ML20217B0141999-10-0101 October 1999 Forwards Insp Repts 50-424/99-06 & 50-425/99-06 on 990725- 0904 at Vogtle Units 1 & 2 Reactor Facilities.Determined That One Violation Occurred & Being Treated as non-cited Violation ML20212E8751999-09-20020 September 1999 Forwards Response to NRC GL 99-02, Lab Testing of Nuclear Grade Activated Charcoal. Description of Methods Used to Comply with Std Along with Most Recent Test Results Encl ML20212E7481999-09-20020 September 1999 Requests Approval Per 10CFR50.55a to Use Alternative Method for Determining Qualified Life of Certain BOP Diaphragm Valves than That Specified in Code Case N-31.Proposed Alternative,Encl ML20212C2191999-09-16016 September 1999 Forwards NRC Form 536, Operator Licensing Exam Data, Which Is Current Need for NRC Operator Licensing Exams for Years 2000 Through 2003 of Plant Vogtle,Per Administrative Ltr 99-03 ML20211Q4801999-09-0101 September 1999 Informs That on 990812-13,Region II Hosted Training Managers Conference on Recent Changes to Operator Licensing Program. List of Attendees,Copy of Slide Presentations & List of Questions Received from Participants Encl ML20211J5291999-08-30030 August 1999 Forwards Snoc Copyright Notice Dtd 990825,re Production of Engineering Drawings Ref in VEGP UFSAR ML20211J5251999-08-30030 August 1999 Forwards Response to NRC 990727 RAI Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions ML20211J7381999-08-27027 August 1999 Informs That Licensee Vessel Data Is Different than NRC Database Based on Listed Info,Per 990722 Request to Review Rvid ML20211E9251999-08-23023 August 1999 Forwards fitness-for-duty Performance Data for Jan-June 1999,as Required by 10CFR26.71(d).Data Reflected in Rept Covers Employees at Vogtle Electric Generating Plant ML20210V0881999-08-16016 August 1999 Forwards Insp Repts 50-424/99-05 & 50-425/99-05 on 990620- 0724.No Violations Noted.Vogtle Facility Generally Characterized by safety-conscious Operations,Sound Engineering & Maintenance Practices ML20210Q4611999-08-0505 August 1999 Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licensing Exam on 991006 for Vogtle.Requests Info Re Individuals Who Will Take Exam. Sample Registration Ltr Encl ML20210L2181999-08-0202 August 1999 Forwards NRC Form 396 & Form 398 for Renewal of Listed Licenses,Iaw 10CFR55.57.Without Encl ML20210N1191999-08-0202 August 1999 Discusses 990727 Telcon Between Rs Baldwin & R Brown Re Administration of Licensing Exam at Facility During Wk of 991213 ML20210G3351999-07-27027 July 1999 Forwards Second Request for Addl Info Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions ML20210E0121999-07-23023 July 1999 Forwards Second Request for Addl Info Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves ML20210D9341999-07-22022 July 1999 Discusses Closure of TACs MA0581 & MA0582,response to Requests for Info in GL 92-01,rev 1,suppl 1, Reactor Vessel Structural Integrity ML20210C8011999-07-21021 July 1999 Provides Response to NRC AL 99-02,which Requests That Addressees Submit Info Pertaining to Estimates of Number of Licensing Actions That Will Be Submitted for NRC Review for Upcoming Fy 2000 & 2001 ML20210E0431999-07-15015 July 1999 Forwards Insp Repts 50-424/99-04 & 50-425/99-04 on 990502- 0619.Two Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20209H3881999-07-14014 July 1999 Forwards Revs 1 & 2 to ISI Program Second 10-Year Interval Vogtle Electric Generating Plant Unit 1 & 2 ML20209C4041999-07-0101 July 1999 Forwards Rev 29 to VEGP Units 1 & 2 Emergency Plan.Rev 29 Incorporates Design Change Associated with Consolidation of Er Facilities Computer & Protues Computer.Justifications for Changes & Insertion Instructions Are Encl ML20196H8081999-06-28028 June 1999 Discusses 990528 Meeting Re Results of Periodic PPR for Period of Feb 1997 to Jan 1999.List of Attendees Encl ML20212J2521999-06-21021 June 1999 Responds to NRC RAI Re Yr 2000 Readiness at Nuclear Power Plants.Gl 98-01 Requested Response on Status of Facility Y2K Readiness by 990701 ML20196F9171999-06-21021 June 1999 Forwards Owner Rept for ISI for Vogtle Electric Generating Plant,Unit 1 Eighth Maint/Refueling Outage. Separate Submittal Will Not Be Made to NRC on SG Tubes Inspected During Subj Outage ML20195F8031999-06-11011 June 1999 Forwards Changes to VEGP Unit 1 Emergency Response Data Sys (ERDS) Data Point Library.Changes Were Completed on 990308 While Unit 1 Was SD for Refueling Outage ML20207E7421999-06-0303 June 1999 Refers to from NRC Which Issued Personnel Assignment Ltr to Inform of Lm Padovan Assignment as Project Manager for Farley Npp.Reissues Ltr with Effective Date Corrected to 990525 ML20207F6201999-06-0202 June 1999 Sixth Partial Response to FOIA Request for Documents.Records in App J Encl & Will Be Available in Pdr.App K Records Withheld in Part (Ref FOIA Exemptions 7) & App L Records Completely Withheld (Ref FOIA Exemption 7) ML20207D9861999-05-28028 May 1999 Informs That,Effective 990325,LM Padovan Was Assigned as Project Manager for Plant,Units 1 & 2 ML20207D2701999-05-19019 May 1999 Forwards Insp Repts 50-424/99-03 & 50-425/99-03 on 990321- 0501.One Violation of NRC Requirements Identified & Being Treated as non-cited Violation Consistent with App C of Enforcement Policy ML20206M5141999-05-11011 May 1999 Informs That NRC Ofc of Nuclear Regulation Reorganized Effective 990328.As Part of Reorganization,Div of Licensing Project Mgt Created.Rl Emch Section Chief for Vogtle. Reorganization Chart Encl ML20206U4061999-05-11011 May 1999 Confirms Telcon with J Bailey Re Mgt Meeting Scheduled for 990528 to Discuss Results of Periodic Plant Performance Review for Plan Nuclear Facility Fo Period of Feb 1997 - Jan 1999 05000424/LER-1998-006, Forwards LER 98-006-03 Re Motor Control Ctr Breaker Buckets Not Being Seismically Qualified.Rev Is Submitted to Document Results of Seismic Testing That Demonstrated That No Condition Outside Design Basis of TS Requirements Exi1999-05-10010 May 1999 Forwards LER 98-006-03 Re Motor Control Ctr Breaker Buckets Not Being Seismically Qualified.Rev Is Submitted to Document Results of Seismic Testing That Demonstrated That No Condition Outside Design Basis of TS Requirements Existed ML20206D6411999-04-29029 April 1999 Forwards Vogtle Electric Generating Plant Radiological Environ Operating Rept for 1998 & Vogtle Electric Generating Plant Units 1 & 2 1998 Annual Rept Annual Radioactive Effluent Release Rept ML20206D5881999-04-29029 April 1999 Forwards Rept Which Summarizes Effects of Changes & Errors in ECCS Evaluation Models on PCT for 1998,per Requirements of 10CFR50.46(a)(3)(ii).Rept Results Will Be Incorporated Into Next FSAR Update ML20206D6951999-04-28028 April 1999 Provides Update of Plans for VEGP MOV Periodic Verification Program Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs ML20206C2241999-04-21021 April 1999 Forwards Revised Monthly Operating Repts for Mar 1999 for Vogtle Electric Generating Plant,Units 1 & 2.Page E2-2 Was Iandvertently Omitted from Previously Submitted Rept on 990413 ML20206A6371999-04-21021 April 1999 Forwards SE Authorizing Licensee Re Rev 9 to First 10-yr ISI Interval Program Plan & Associated Requests for Relief (RR) 65 from ASME Boiler & Pressure Vessel Code ML20205Q3351999-04-15015 April 1999 Forwards Insp Repts 50-424/99-02 & 50-425/99-02 on 990214-0320.Three Violations Identified & Being Treated as Non-Cited Violations ML20205T2351999-04-0909 April 1999 Informs That on 990317,B Brown & Ho Christensen Confirmed Initial Operator Licensing Exam Scheduled for Y2K.Initial Exam Date Scheduled for Wk of 991213 for Approx 10 Candidates ML20205K7501999-04-0505 April 1999 Informs That Effective 990329,NRC Project Mgt Responsibility for Plant Has Been Transferred from Dh Jaffe to R Assa ML20209A3741999-04-0505 April 1999 Submits Several Requests for Relief for Plant from Code Requirements Pursuant to 10CFR50.55a(a)(3) & (g)(5)(iii).NRC Is Respectfully Requested to Approve Requests Prior to Jan 1,2000 ML20205H3481999-03-31031 March 1999 Forwards Georgia Power Co,Oglethorpe Power Corp,Municipal Electric Authority of Ga & City of Dalton,Ga Status of Decommissioning Funding for Each Reactor or Part of Reactor Owned for OLs NPF-68 & NPF-81 ML20205F9091999-03-29029 March 1999 Submits Rept of Number of SG Tubes Plugged During Plant Eighth Maintenance/Refueling Outage (1R8).Inservice Insps Were Completed on SGs 1 & 4 on 990315.No Tubes Were Plugged ML20205G0761999-03-26026 March 1999 Provides Results of Individual Monitoring for 1998.Encl Media Contains All Info Required by Form NRC 5.Without Encl 1999-09-20
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217P3791999-10-21021 October 1999 Forwards NRC Form 396 & NRC Form 398 for Renewal of Licenses SOP-20607-1 & SOP-20610-1.Without Encls ML20217N2521999-10-20020 October 1999 Provides Supplemental Info Re 990405 Containment Insp Program Requests for Relief RR-L-1 & RR-L-2,in Response to 991013 Telcon with NRC ML20217K7541999-10-15015 October 1999 Forwards Rev 1 to Unit 1,Cycle 9 & Unit 2 Cycle 7 Colrs,Iaw Requirements of TS 5.6.5.Figure 5, Axial Flux Difference Limits as Function of Percent of Rated Thermal Power for RAOC, Was Revised for Both Units ML20217G6751999-10-13013 October 1999 Requests Withholding of Proprietary Info Contained in Application for Amend to OLs to Implement Relaxations Allowed by WCAP-14333-P-A,rev 1 ML20216J9161999-10-0101 October 1999 Forwards Response to NRC 990723 RAI Re GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves ML20216J9041999-10-0101 October 1999 Forwards Response to RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves ML20212E7481999-09-20020 September 1999 Requests Approval Per 10CFR50.55a to Use Alternative Method for Determining Qualified Life of Certain BOP Diaphragm Valves than That Specified in Code Case N-31.Proposed Alternative,Encl ML20212E8751999-09-20020 September 1999 Forwards Response to NRC GL 99-02, Lab Testing of Nuclear Grade Activated Charcoal. Description of Methods Used to Comply with Std Along with Most Recent Test Results Encl ML20212C2191999-09-16016 September 1999 Forwards NRC Form 536, Operator Licensing Exam Data, Which Is Current Need for NRC Operator Licensing Exams for Years 2000 Through 2003 of Plant Vogtle,Per Administrative Ltr 99-03 ML20211J5291999-08-30030 August 1999 Forwards Snoc Copyright Notice Dtd 990825,re Production of Engineering Drawings Ref in VEGP UFSAR ML20211J5251999-08-30030 August 1999 Forwards Response to NRC 990727 RAI Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions ML20211J7381999-08-27027 August 1999 Informs That Licensee Vessel Data Is Different than NRC Database Based on Listed Info,Per 990722 Request to Review Rvid ML20211E9251999-08-23023 August 1999 Forwards fitness-for-duty Performance Data for Jan-June 1999,as Required by 10CFR26.71(d).Data Reflected in Rept Covers Employees at Vogtle Electric Generating Plant ML20210L2181999-08-0202 August 1999 Forwards NRC Form 396 & Form 398 for Renewal of Listed Licenses,Iaw 10CFR55.57.Without Encl ML20210C8011999-07-21021 July 1999 Provides Response to NRC AL 99-02,which Requests That Addressees Submit Info Pertaining to Estimates of Number of Licensing Actions That Will Be Submitted for NRC Review for Upcoming Fy 2000 & 2001 ML20209H3881999-07-14014 July 1999 Forwards Revs 1 & 2 to ISI Program Second 10-Year Interval Vogtle Electric Generating Plant Unit 1 & 2 ML20209C4041999-07-0101 July 1999 Forwards Rev 29 to VEGP Units 1 & 2 Emergency Plan.Rev 29 Incorporates Design Change Associated with Consolidation of Er Facilities Computer & Protues Computer.Justifications for Changes & Insertion Instructions Are Encl ML20196F9171999-06-21021 June 1999 Forwards Owner Rept for ISI for Vogtle Electric Generating Plant,Unit 1 Eighth Maint/Refueling Outage. Separate Submittal Will Not Be Made to NRC on SG Tubes Inspected During Subj Outage ML20212J2521999-06-21021 June 1999 Responds to NRC RAI Re Yr 2000 Readiness at Nuclear Power Plants.Gl 98-01 Requested Response on Status of Facility Y2K Readiness by 990701 ML20195F8031999-06-11011 June 1999 Forwards Changes to VEGP Unit 1 Emergency Response Data Sys (ERDS) Data Point Library.Changes Were Completed on 990308 While Unit 1 Was SD for Refueling Outage 05000424/LER-1998-006, Forwards LER 98-006-03 Re Motor Control Ctr Breaker Buckets Not Being Seismically Qualified.Rev Is Submitted to Document Results of Seismic Testing That Demonstrated That No Condition Outside Design Basis of TS Requirements Exi1999-05-10010 May 1999 Forwards LER 98-006-03 Re Motor Control Ctr Breaker Buckets Not Being Seismically Qualified.Rev Is Submitted to Document Results of Seismic Testing That Demonstrated That No Condition Outside Design Basis of TS Requirements Existed ML20206D5881999-04-29029 April 1999 Forwards Rept Which Summarizes Effects of Changes & Errors in ECCS Evaluation Models on PCT for 1998,per Requirements of 10CFR50.46(a)(3)(ii).Rept Results Will Be Incorporated Into Next FSAR Update ML20206D6411999-04-29029 April 1999 Forwards Vogtle Electric Generating Plant Radiological Environ Operating Rept for 1998 & Vogtle Electric Generating Plant Units 1 & 2 1998 Annual Rept Annual Radioactive Effluent Release Rept ML20206D6951999-04-28028 April 1999 Provides Update of Plans for VEGP MOV Periodic Verification Program Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs ML20206C2241999-04-21021 April 1999 Forwards Revised Monthly Operating Repts for Mar 1999 for Vogtle Electric Generating Plant,Units 1 & 2.Page E2-2 Was Iandvertently Omitted from Previously Submitted Rept on 990413 ML20209A3741999-04-0505 April 1999 Submits Several Requests for Relief for Plant from Code Requirements Pursuant to 10CFR50.55a(a)(3) & (g)(5)(iii).NRC Is Respectfully Requested to Approve Requests Prior to Jan 1,2000 ML20205H3481999-03-31031 March 1999 Forwards Georgia Power Co,Oglethorpe Power Corp,Municipal Electric Authority of Ga & City of Dalton,Ga Status of Decommissioning Funding for Each Reactor or Part of Reactor Owned for OLs NPF-68 & NPF-81 ML20205F9091999-03-29029 March 1999 Submits Rept of Number of SG Tubes Plugged During Plant Eighth Maintenance/Refueling Outage (1R8).Inservice Insps Were Completed on SGs 1 & 4 on 990315.No Tubes Were Plugged ML20205G0761999-03-26026 March 1999 Provides Results of Individual Monitoring for 1998.Encl Media Contains All Info Required by Form NRC 5.Without Encl ML20205H4051999-03-25025 March 1999 Forwards Info on Status of Decommissioning Funding for Each Reactor or Part of Reactor Owned for OLs NPF-68 & NPF-81,as Requested IAW 10CFR50.75(f)(1) ML20205H3891999-03-25025 March 1999 Forwards Info on Status of Decommissioning Funding for Each Reactor or Part of Reactor Owned for OLs NPF-68 & NPF-81,as Requested IAW 10CFR50.75(f)(1).Page 2 in Third Amend Power Sales Contract of Incoming Submittal Not Included ML20205A9441999-03-25025 March 1999 Forwards VEGP Unit 1 Cycle 9 Colr,Per TS 5.6.5.d ML20205H3811999-03-24024 March 1999 Forwards Info on Status of Decommissioning Funding for Each Reactor or Part of Reactor Owned for OLs NPF-68 & NPF-81,as Requested IAW 10CFR50.75(f)(1) ML20205H3621999-03-22022 March 1999 Forwards Info on Status of Decommissioning Funding for Each Reactor or Part of Reactor Owned for OLs NPF-68 & NPF-81, as Requested IAW 10CFR50.75(f)(1) ML20204G4361999-03-18018 March 1999 Forwards Summary Rept of Present Level & Source of on-site Property Damage Insurance Coverage for Vegp,Iaw Requirements of 10CFR50.54(w)(3) ML20204C0591999-03-17017 March 1999 Forwards Rev 0 to WCAP-15160, Evaluation of Pressurized Thermal Shock for Vegp,Unit 2 & Rev 0 to WCAP-15159, Analysis of Capsule X from Vegp,Unit 2 Reactor Vessel Radiation Surveillance Program ML20207K9551999-03-11011 March 1999 Forwards Response to Rai,Pertaining to Positive Alcohol Test of Licensed Operator.Encl Info Provided for NRC Use in Evaluation of Fitness for Duty Occurrence.Encl Withheld,Per 10CFR2.790(a)(6) ML20207L9721999-03-10010 March 1999 Forwards Rev 15 to EPIP 91104-C of Manual Set 6 of Vogtle Epips.Without Encl ML20207B0191999-02-25025 February 1999 Forwards Fitness for Duty Performance Data for six-month Reporting Period 980701-1231,IAW 10CFR26.71(d) 05000424/LER-1998-009, Forwards LER 98-009-00 Re Event in Which Improper Testing Method Resulted in Inadequate Surveillances on 9812291999-01-27027 January 1999 Forwards LER 98-009-00 Re Event in Which Improper Testing Method Resulted in Inadequate Surveillances on 981229 ML20199F7701999-01-13013 January 1999 Submits Revised Response to RAI Re Licensee 980713 Proposed Amend to Ts,Eliminating Periodic Response Time Testing Requirements on Selected Sensors & Protection Channels. Corrected Copy of Table,Encl ML20199F7981999-01-13013 January 1999 Forwards Corrected Pages to VEGP-2 ISI Summary Rept for Spring 1998 Maint/Refueling Outage. Change Bar in Margin of Affected Pages Denotes Changes to Rept ML20199G1381999-01-13013 January 1999 Forwards Copy of Permit Renewal Application Package for NPDES Permit Number GA0026786,per Section 3.2 of VP Environ Protection Plan 05000424/LER-1998-007, Forwards LER 98-007-00,re Inadequate Surveillances Due to Improperly Performed Response Time Testing,On 981215,IAW 10CFR50.731999-01-13013 January 1999 Forwards LER 98-007-00,re Inadequate Surveillances Due to Improperly Performed Response Time Testing,On 981215,IAW 10CFR50.73 ML20198F6131998-12-18018 December 1998 Forwards Revised Certification of Medical Exam Form for License SOP-21147.Licensee Being Treated for Hypertension. Util Requests That Individual License Be Amended to Reflect Change in Status ML20198L6631998-12-18018 December 1998 Forwards Amend 37 to Physical Security & Contingency Plan. Encl 1 Provides Description & Justification for Changes & Encl 2 Contains Actual Amend 37 Pages.Amend Withheld,Per 10CFR73.21 ML20198D9291998-12-16016 December 1998 Forwards Requested Info Re Request to Revise TSs Elimination of Periodic Pressure Sensor Response Time Tests & Elimination of Periodic Protection Channel Response Time Tests ML20198D9991998-12-16016 December 1998 Forwards Responses to 980916 RAI Re Response to GL 97-01, Degradation of Control Rod Drive Mechanism Nozzle & Other Vessel Closure Head Penetrations ML20198D8171998-12-14014 December 1998 Forwards NRC Form 396 & Form 398 for Renewal of License OP-20993.Without Encls ML20206N3051998-12-0808 December 1998 Submits RAI Re Replacement of Nuclear Instrument Sys Source & Intermediate Range Channels & post-accident Neutron Flux Monitoring Sys 1999-09-20
[Table view] |
Text
-. _.
. , . i*: Georgia Pdwu Company
.' 333 Piedmont AYonue
. Atlanta, Georgia 30308 ' !
-Telephona 404 526 3195 jMailing Address '
40 invemess Center Parkway, Post Office Box 1295 ^ .
, CJrmingham. Alabama 35201 Twlephone 205 868-5086 -
' the Southe'n electic system
Senior Vee Piesident '
July 2,.1996 LCV-0136-L '
[
Docket Nos.: 50-424' 50-425
, U. S. Nuclear Regulatory Commission ' j ATTN: Document Control Desk Washington, D. C. 20555 1
Gentlemen: ,
VOGTLE ELECTRIC GENERATING PLANT i GENERIC LETTER 89 '
CLOSE-OUT SUBMITTAI CLARIFICATION
- Georgia Power Company (GPC) transmitted a Close-Out document to the NRC on January 31,1996 to facilitate the closure of the Vogtle Electric Generating Plant (VEGP) ,
Generic Letter 89-10 program. The document provided a detailed description of the ;
- program undertaken to implement the recommendations contained in the generic letter, as well as a discussion of the basis forjustifying that each of the 256 valves included in the program is capable of performing its design-basis function.
Included in Volume 1 of the submittal is Table 10-1 entitled Post Close-Out Activities. ;
- This table identifies all of the modifications which were scheduled to be performed subsequent to the transmittal of the Close-Out document. In conjunction with the installation of these modifications during the spring 1996 outage, it was determined that certain modifications identified in this table could not be implemented as originally stated.
Specifically, the spring packs on valves 1HV-8508A/B and 1HV-8509A/B, the
~ centrifugal charging pump miniflow valves, were not replaced. In conjunction with the implementation of the planned modification on the 1HV-8509A valve, it was d' etermined '
- that an acceptable valve setup could not be achieved with the new spring pack installed.
The enclosure to this letter discusses the problems associated with the installation of the
, L new spring pack and the basis for maintaining spring packs of the original configuration. >
i 9607090198 960702 4/f . h(CN g/ H DR ADOCK 0
. l
. GeorgiaPower 1 L U. S. Nuclear Regulatory Commission Page 2 !
In addition, it is anticipated that problems may be encountered relative to the
. implementation of similar modifications on the corresponding valves on Unit 2. The Unit j 2 modifications are scheduled to be installed during the fall 1996 outage, and a j determination of the feasibility ofinstalling the spring pack modification on the 2HV- l 8508A/B and 2HV-8509A/B valves will be made at that time.
Should you require any additional information regarding this response, please contact my i
office.
Sincerely, -
Woodard A
J.
Semor Vice President JDW/IIET/het - :
Enclosure ;
xc: - Georgia Power Company :
Mr. J. B. Beasley, Jr.
Mr. M. Sheibani NORMS U. S. Nuclear Regulatory Commission
- Mr. S. D. Ebneter, Regional Administrator Mr. L L. Wheeler, Licensing Project Manager, NRR Mr. C. R. Ogle, Senior Resident Inspector, Vogtle i i
1 l
. i
. LCV-0136-L ;
a.
)
Enclosure l 1
Valves 1/2HV-8508A/B & 1/2HV-8509A/B Spring Pack 0301-112 versus 0301-113 Evaluation 1
- In conjunction with the completion of Generic Letter 89-10 related upgrades at VEGP, j valves llIV-8508A/B and 1HV-8509A/B were scheduled for modifications during the i spring 1996 outage. Valves 1HV-8508A/B and 1HV-8509A/B are Velan globe valves l which are equipped with Limitorque SMB-00 operators with 10 fl-lb motors. The valves are installed in the Chemical and Volume Control System (CVCS) and are utilized in Centrifugal Charging Pump (CCP) miniflow applications. Valves 1HV-8508A/B were l scheduled to have new motor pinion and worm shaft gears installed to increase the overall i ratio, and a heavier spring pack installed to enable the torque switch setting to be l increased. Valves 1HV-8509A/B were scheduled to have the heavier spring pack i installed. l The afore mentioned modifications were installed on valve IHV-8509A, and an attempt ,
was made to setup the valve utilizing VOTES diagnostic equipment. It was determined ,
that the heavy spring pack did not allow for a sulliciently low torque switch setting to ;
enable the valve to be setup within its design window. In reviewing the test data it was determined that the actual stem factor for this valve was substantially better than the design stem factor which is based on a 0.15 stem friction coefficient. The better than design stem factor meant that less operator output torque was required to produce the required amount of valve thrust. In this particular case, the stem factor was such that the ;
output torque of the operator could not be limited to a low enough value by the torque ;
switch, with the heavy spring pack installed, to prevent the valve thrust from being ;
outside the design range. ;
Valve 1HV-8509A was originally equipped with spring pack No. 0301-112. According to the Limitorque generic spring pack curves, this spring pack has a useable range of 115 I ft-lb to 185 ft-lb. The original spring pack was replaced by spring pack No. 0301-113 in -
) conjunction with the modifications. The useable range of the new spring pack is 170 ft-lb 4 to 240 R-lb according to Limitorque's generic data. As is apparent from reviewing the
- design ranges, there is very little overlap between the 112 spring pack and the 113 spring
. pack. Ideally, a spring pack with a useable range between that of the 112 and 113 spring i
! packs would have been most appropriate for this application.
4 To resolve the problem with the 1HV-8509A valve, a 112 spring pack was reinstalled in the operator. The operator was subsequently setup within the der,ign range utilizing i i VOTES diagnostic equipment. In anticipation of similar proble ns with the 1HV- l 8508A/B and the IHV-8509B valves, the 113 spring packs were not installed in these ;
g valves. The new motor pinion and worm shan gears were installed in the IHV-8508A/B valves as originally planned. Each of these valves was also setup successfully utilizing ,
VOTES test equipment. In reviewing the test data for these valves, it was noted, that in j
- - each case the actual stem factor was better than the design stem factor.
i 5
1
While the valves were successfully setup with the 112 spring packs installed, the use of this spring pack substantially impacts the valve rnargins included in Volume 2 of the Close-Out Submittal. The current analytical methodology considers the rating of the spring pack, in terms of thrust, and the resulting evaluations indicate that these valves are very marginal when evaluated based on the 112 spring pack rating. To illustrate this point the llIV-8509A valve will be evahtated with both the 112 and 113 spring pack.
When determining the design window in the closing direction, a total of five potential limitations are considered in establishing the upper bound. Table 1 identifies those potential limitations and includes the applicable values for the 1HV-8509A valve assuming the 113 spring pack is installed.
Table 1 Valve 1HV-8509A Closine Uoner Bound Limitations Thrust Valve Allowable 33,326 lb Operator Allowable (Thrust) 19,600 lb Operator Allowable (Torque) 20,492 lb Operator Spring Pack Rating 19,672 lb Operator Reduced Voltage 18,770 lb Capability The values presented in the table are in terms of thrust since this is the relevant unit with regard to establishing an acceptable valve setup in the field. The operator torque allowable and the spring pack rating are normally referenced in terms of torque, but for the purposes of this evaluation, have been converted to thrust by dividing by the design stem factor of 0.0122. As can be seen by reviewing the table, the limiting parameter for this valve is the operator reduced voltage capability of I8,770 lb.
The VEGP Close-Out Submittal includes a detailed discussion of the methodology utilized to determine capability margins and setup margins for torque switch controlled valves. Evaluating the IllV-8509A valve based on this methodology, utilizing the 113 spring pack, results in calculated capability and setup margins of 75% and 29%
respectively.
Performing a similar analysis with the 112 spring pack installed results in subtentially different results. The maximum torque rating of the 112 spring pack is 185 ft-lb which is equivalent to 15,164 lb of thrust based on the design stem factor of 0.0122. In this case the spring pack rating replaces the operator reduced voltage capability as the upper limit with respect to closing the valve. Analyzing the valve based on the 112 spring pack
I p 8
.?
e
- rating results in a Capability Margin of 42% and a Setup Margin of 4%. Based on the results of this analysis the valve appears to be very marginal with the 112 spring pack. I Table 2 Valve 1HV-8508A ,
Sprme Canability Setup Eack Marvin Margin 0301-113 75 % 29%
0301-112 42% 4%
Ilowever, in the case of these valves, this analysis does not accurately reflect the actual capabilities. While there are limitations imposed by the spring pack on the capability of a torque switch controlled valve, the " nameplate" rating of the spring pack is not necessarily an accurate measure of those limitations. There are several reasons for this, including the following:
- 1. The actual useable range of a given size spring pack can vary substantially from the range identified in the Limitorque generic spring pack curves. With the advent of spring pack test equipment, such as the B&W test equipment utilized at ;
VEGP, it is possible to evaluate each spring pack individually. By performing a spring pack test it is possible to develop a torque versus displacement curve for each individual spring pack which provides an accurate assessment of the spring packs actual range in terms of torque.
- 2. To utilize the spring pack rating in the cabulations it is necessary to convert '
the torque rating to thrust. At VEGP this conversion is performed by dividing by the design stem factor which is based on a stem friction coefficient of 0.15. ,
In practice, the actual stem friction coefficient is often significantly lower. l Diagnostic testing allows the actual stem factor to be determined and in doing so provides an accurate assessment of the installed spring pack's actual capability in terms of thrust.
As a result of this review, the process for evaluating the margins of valves which are controlled by the torque switch in the closing direction will be revised. The spring pack rating will be excluded from the limitations which are considered when performing an analytical evaluation of valve margins. In the case of the 1HV-8509A valve, the j calculated capability and setup margins with the 112 spring pack installed will be 75%
und 29% respectively, which is equivalent to the margins calculated for the 113 spring pack. The actual spring pack capability will continue to be considered in conjunction j with the valve setup. However, the setup will not be arbitrarily limited based on the !
i .
Limitorque spring pack torque rating and the theoretical conversion of this rating from torque to thrust.
If a valve is determined to be limited by the spring pack in conjunction with a valve setup, the spring pack can be replaced at that time to facilitate an acceptable setup. The spring pack will be replaced under the normal design change process with all of the associated controls including a 10 CFR 50.59 safety evaluation.
In summary, the spring pack is a mechanical device which is utilized in combination with a torque switch to control the torque output of an operator within a predetermined range.
The spring pack limits operator capability only when it does not have sufficient range to allow for a torque switch setting which utilizes the capabilities otherwise inherent in the valve and operator. Torque switch limitations of this nature are readily apparent in conjunction with the valve setup process and can be easily resolved at that time.
Including the Limitorque spring pack rating in analytical evaluations does not provide a realistic assessment of motor-operated valve capabilities.