|
---|
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
. - .
-N *
' Georgia Fbwer Company Fbst Offics Box 282 Wayrtisboro, Georgia 30830 Telephone 404 554-9961 404 724-8114 Southern Company Services,Inc.
Fbst Office Box 2625 Birmingham, Alabama 35202 Telephone 205 870-6011 VOgtie Project October 17, 1986 Director of Nuclear Reactor Regulation File: X4AK01 B. J. Youngblood X4BA17 Attention:
Licensing Branch #4 Log: GN-1121 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D.C. 20555 REF: (1) LETTER GN-1072 DATED SEPTEMBER 5, 1986 (2) LETTER GN-1080 DATED SEPTEMBER 19, 1986 NRC DOCKET NUMBERS 50-424 AND 50-425 CONSTRUCTION FERMIT NUMBERS CPPR-108 AND CPPR-109 V0GTLE ELECTRIC GENERATING PIANT - UNITS 1 AND 2 DESIGN REVIEW / QUALITY REVALIDATION REPORT l TDI DIESEL GENERATORS i
Dear Mr. Denton:
As requested by your staff we have reviewed the issues concerning reliability of TDI Diesel Generators at VEGP. In response to these issues Georgia Power Company provides the following attachments:
Attachment 1: VEGP Position on SER Recommendations Attachment 2: _ Phase II Component Inspection Status Attachment 3: Justification for DR/QR Report Deviation Should you require additional information, please do not hesitate to call.
l Sincerely, i
. ' 4. [
J. A. Bailey Project Licensing Manager JAB /sm xc: List attached.
8610230217 861017 PDR ADOCK 05000424 E pm i
i
,_..,,.,m. _ . _ _ __ . _ ___, -__._._. - -.- , - _._ ,__,_ .._ ,.. ,,.. ,...,_-. __ ._.. ...._ - ,- ._, _ _ , _ _ . _ , _ _ _ _ - , , .
Director of Nuclear Reactor Regulation File: X4AK01 October 17, 1986 X4BA17 Page 2 Log: GN-1121 xc: .R. E. Conway R. A. Thomas l B. W. Churchill, Esquire J. E. Joiner, Esquire M. A. Miller L. T. Gucwa G. Bockhold, Jr.
B. Jones, Esquire O. Batum D. Feig NRC Regional Administrator NRC Resident Inspector 0793V
ATTACHMENT 1 VEGP Position SER Recommendations (NUReg-1216)
A. S4 ction 2.1.2 - Components that Warrant Special Emphasis The following table (Table 2.I' of Section 2.1.2 reproduced) shows applicability to VEGP. Specific applicability and implementation is discussed in Section 2.1.3.
Table 2.1 Components requiring engine load limits and/or special routine maintenance and surveillance Special maintenance Engine and load surveillance Applicability Component limited required to VEGP Crankshaft DSR-48 Yes Yes No DSRV-20 Yes* Yes No Cylinder block DSR-48 (Shoreham) No Yes No DSRV-16 (Comanche Peak) No Yes Yes Cylinder heads No Yes Yes Connecting rods DSRV engines, 1-7/8 in, bolts Yes Yes No DSRV engines,1-1/2-in. bolts No Yes Yes Piston skirts Type AF Yes Yes No Turbocharger No Yes Yes
- Limitations on engine testing have been established to minimize crankshaft torsional stresses during startup transients.
B. Section 2.1.3 Clarifications, Exceptions and Licensing Considerations Pertaining to PNL Reconsnendations in PNL-5600.
- 1. Section 2.1.3.1 Engine Overhaul Frequency VEGP concurs with Revision 2 of the DR/QP. and will perform engine overhaul at approximate 10-year intervals, for. the two engines, and the one-time 5 year inspection on a sample basis.
- 2. Section 2.1.3.2 Air Start Capscrews VEGP has verified all airstart capscrews are 2-3/4 inches in length.
.The capscrews were torqued to.150 ft-lbs initially and retorqued to 150 ft-lbs every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of engine operation until no change in torque was noted. Permanent plant procedures are in place to ensure.this practice is continued. No outstanding items remain.
- 3. Section 2.1.3.3 Auxiliary Module Wiring and Terminations VEGP has implemented TDI SIM 361 and verified period of manufacture of states-type sliding link terminal blocks. No outstanding items remain.
- 4. Section 2.1.3.4 Connecting Rod Bearing Shells VEGP concurs with Revision 2 of the DR/QR and will inspect all connecting rod bearings at 10-year intervals, and the one-time 5 year inspection of a sample of the bearings. VEGP engine oil analysis will be performed monthly for the first three months of operation, then quarterly. Oil analysis will include a " wear analysis" looking at cooper, chromium, iron, aluminum, tin and silicon content. VEGP has inspected all connecting rod bearings radiographically to the acceptance criteria adpoted by the Owners Group. Permanent plant procedures are in place that require all new connecting rod bearings shells be radiogrphically examined prior to use.
- 5. Section 2.1.3.5 DSR-48 Connecting Rods Not applicable to VEGP.
- 6. Section 2.1.3.6 DSRV Connecting Rods The VEGP connecting rods (with 1-1/2 inch connecting rod bolts) have been subjected to at least the following inspections:
- a. Link pin to link rod clearance
- b. Connecting rod centerline bow
- c. Eddy current inspection of all connecting rod threaded bolt holes.
- d. Magnetic particle inspection of connecting rod bolts.
- e. Liquid penetrant inspection of the rod eye bushing.
- f. Adequate contact between the rack joints of connecting rod box.
- g. Visual inspection of bolts and washers for galling.
- h. Connecting rod. bolts torqued to 1700 ft-lbs using a mixture of graphite and oil for lubrication.
VEGP will perform the connecting rod bolt baseline ultrasonic elongation measurements on a 25% sample at the 5-year inspection and all the connecting rods at the 10-year inspection. VEGP will also incorporate the recommendation of the staff, to include in the M/S program provisions to take corrective actions if bolt preload is found to be less than 93% of its initial valve during any connecting rod disassembly. VEGP will also require ultrasonic measurements of connecting rod bolts following assembly and prior to disassembly.
VEGP will include in its N/S program the requirement to reinspect the contact at the serrated joint of the rod box if inspections reveal a loss of preload on the rod bolts, fretting of the serrated surfaces or evidence of other connecting rod distress.
VEGP will also follow the DR/QR recommendations to MT the connecting rod bolts and inspect the connecting rod bolt holes using an appropriate NDE method each time a connecting rod is disassembled and at 10-year intervals.
- 7. Section 2.1.3.7 Crankshaft VEGP has performed the required NDE examination of the crankshaft oil holes. and fillers. The material certification reports for the crankshafts have been reviewed and it has been verified that the mechanical properties of the crankshafts are within design specifications. The torsiograph test is scheduled to be performed during ESFAS testing (ie, prior to fuel load) VEGP has incorporated into its M/S program provisions to monitor cylinder balance (exhaust temperatures) on at least an hourly basis and to monitor maximum cylinder exhaust temperatures.
- 8. Section 2.1.3.8 DSR-48 Crankshaft - Shoreham and River Bend Not applicable to VEGP.
- 9. Section 2.1.3.9 Other DSR-48 Crankshafts Not applicable to VEGP.
- 10. Section 2.1.3.10 DSRV-16 Crankshafts See item 7 above
- 11. Section 2.1.3.11 DSRV-20 Crankshafts Not applicable to VEGP
- 12. Section 2.1.3.12 Engine Block VEGP has performed the inspections recommended by the Owners Group and has found all blocks to be free of ligament cracks, stud-to-stud cracks and circumferential cracks in the liner bore (camshaft gallery cracks not applicable to VEGP).
All of the blocks at VEGP have been metallurgically examined and
. verified to be characteristic of typical grey cast iron (ie., no degraded microstructure was found). VEGP has incorporated into its M/S program procedures to require inspection of the cylinder blocks per Oweners Group recommended techniques at a frequency based on the cumulative damage index model.
- 13. Section 2.1.3.13 Cylinder Heads Vogtle has installed all Group III Cylinder Heads and performed all required preservice inspections including PT of valve seating surfaces and MT and UT of the firing deck.
Verified none of the cylinder heads have through wall weld repair.
Plant procedures include requirements to Air Roll Engine at least 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> but not more than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> after eng. shutdown, with cylinder l cocks open. Second air roll to be performed after 24 hrs. Also, air rolls are performed shortly before any planned start.
- 14. Section 2.1.3.14 Cylinder Head Studs Vogtle has cylinder head studs with necked down shanks. The modification referred to in the September 24, 1984 Owners Group letter (C. Ray) which requires the bottom two threads of the ' stud to be removed, has been performed.
Vogtle will update the TDI Parts Manual to incorporate the new
! TDI part no. 03-315-01-0A Rev. G which reflects the new design change. Plant procedures already include instructions for proper installation and torquing.
- 15. Section 2.1.3.15 Engine Base Vogtle will perform a visual inspection of the engine base at each 10 year overhaul and each of the first three refueling outages.
Samples from each engine base will be taken and checked for degenerate widmanstaetten graphite. Samples will be submitted for analysis prior to fuel load.
- 16. Section 2.1.3.16 Fuel Oil Injection Tubing Vogtle has performed eddy current testing on all fuel injection tubing for each engine. Eddy current testing was performed by FaAA.
Vogtle has installed shrouded fuel oil lines.
Fuel injection lines were inspected for leakage after engine operation.
Manufacturer's instructions on installing fitting for the injection tubing.
- 17. Section 2.1.3.17 Jacket Water Pump Vogtle has visually inspected the jacket water pump gear for chipped or broken teeth, excessive wear, pitting or other abnormal conditions.
Checked key to keyway interface for tight fit.
Checked torque on castle nut that drives the external spline on its taper.
- 18. Section 2.1.3.18 Piston Skirts - Type AE Vogtle has replaced all of the originally supplied AN piston skirts with AE skirts.
Performed visual inspection of rib area near wristpin and rib at intersection of wrist pin boss.
- 19. Section 2.1.3.19 Piston Skirts - Type AF Does not apply to Vogtle
- 20. Section 2.1.3.20 Piston Skirts - Type AH and AN Does not apply to Vogtle
- 21. Section 2.1.3.21 Push Rods Vogtle has installed all friction welded push rods and performed liquid penetrant testing on them.
- 22. Section 2.1.3.22 Rocker Ann Capscrews Vogtle has performed a magnetic particle test on the thread root area of all capscrews for linear indications.
Verified proper torque.
- 23. Section 2.1.3.23 Turbochargers VEGP has installed the drip lubrication system, with a flow between 0.10 gph and 0.35 gph, and the full-flow prelubrication system for each of the turbochargers. VEGP has incorporated into its M/S program provisions to monitor individual cylinder exhaust
temperature. Should any cylinder exhaust temperature exceed 1050 F appropriate instrumentation will be required to be installed to ensure turbocharger inlet temperature does not exceed 1200 F.
As discussed in item 4, oil analysis will be performed on a quarterly basis, including a " wear analysis". The nozzle ring inspection for all four turbochargers will be performed following ESFAS testing (ie, prior to Fuel Load), at which time a total turbocharger inspection will be performed.
VEGP concurs with the Owners Group (DR/QR) recommended inspections and recommended frequencies and will incorporate these into the M/S program. Additionally VEGP will reinspect any turbocharger in which any nozzle ring anomalies were found at the next E0C inspection. Even if nozzle rings of an appropriate redesign are installed in the VEGP turbochargers, the 5-year inspections will be continued.
C. Section 2.2 Technical Resolution of Phase II VEGP has completed the vast majority of the DR/QR recommendations for Phase II components. Attachment 2 of this letter delineates those items which are open at this time.
D. Section 2.3 Maintenance / Surveillance Program VEGP commits to the M/S program as given in Appendix II of the VEGP DR/QR, with corrections as listed in Table 1 (these were previously transmitted to the staff in a September 19, 1986 letter as Attachment 2), and as discussed throughout Attachment 1. This commitment is made with the understanding that changes may be made to the program as necessary and as additional operating experience is gained, under the provisions of 10 CFR50.59.
I 1
. , , _ _ _ _ . _ , - - . , - . . y- -- _-,-- -.- _.-
. , . - - , _ _ . . - _ _ . _ , _ __ ..._,. .. . . , . _ _ _ - _ , - . , - - , - - . y, e
- i. PAGE 1 0F 3 ,
TABLE 1
, CORRECTIONS TO APPENDIX II 0F VEGP DR/QR i
! COMPONENT ITEM PM PAGE NUMBER DESCRIPTION NO. RECOMMENDATION FREQUENCY COMMENTS II-B-9 02-425A 3. Castle nut minimum and *
- Torque valves will be checked l
j Jacket Water torque valves, each time pump is disassembled.
3 Pump Gear i
II-C-2 CP-102 5. Check meter calibrations. E0C Generator Control Panel
} II-C-12 02-371A Check and lubricate. Monthly j Fuel Pump j Control Shaft II-C-15 02-413A 1. Install locking hardware *
- Frequency will be based on the l Governor to the lever arm clamp results of the monthly inspec-j Linkage bolt heads and shaft roll tion for loose parts on the j pins. linkage assembly.
l 3. Lubricate cross shaft Monthly j bearings.
i 3
II-C-17 02-475A, C 1. Inspect bracket bolting. E0C
- Turbocharger l
Bracket Bolting II-C-19 02-500C 3. Trip check circuit breakers. 5 Yr.
l Circuit
] Breakers II-C-20 02-525B 1. Replace control valve "0" 5 Yr.
Barring Device rings and lube shaft. , ,
- 2. Replace press regulator N/A VEGP has no press regulator.
j elastomeric parts.
1 I II-C-20 02-525C 1. Replace filter element. E0C ,
Barring Device I
Air Filter
! 2. Drain barrring device air Monthly l filter.
l
PAGE 2 0F 3
- TABLE 1 CORRECT 10N TO APPENDIX If 0F VEGP DR/QR ,
COMPONENT # ITEM PM PAGE NUMBER DESCRIPTION NO. -REQUIREMENT FREQUENCY COMMENTS II-C-21 02-540A 3. Visually inspect sump tank level E0C Lube Oil switch floats. Check switch set Sump Tank points.
II-C-22 02-695C 1. Check switch setpoints. E0C Engine Control Pneumatic Trip Switches 2. Replace elastomeric parts. 5 Yr.
II-C-22 02-7008 1. Replace elastomeric parts in 5 Yr.
Jacket Water valves.
Stand Pipe II-C-24 02-810E 1. Check calibration and inspect Alt. E0C Jacket Water thermostat.
Heaters II-C-25 02-820A 2. Check calibration and inspect Alt. E0C Lube Oil Sump condition of thermostat.
Tank Heaters II-C-26 02-820F 3. Lube oil filter gauge - calibration Alt. E0C Full Flow Lube check. '
Oil Filters II-C-26 02-820H 3. Lube oil strainer pressure gauge - Alt. E0C Full Press Lube calibration check.
Oil Strainer II-C-28 02-835J 2. Starting air tank pressure gauges - Alt. E0C Starting Air calibration check.
Storage Tank
- 3. Starting air tank pressure switches - Alt. E0C calibration check.
II-D-V3 02-315A Perform inspections per DR/QR E0C* *A review will be performed of Cylinder Block Report 02-315A. the hours logged on the engine since the last inspection.
Inspection will be performed '
at the E0C following 490 hours0.00567 days <br />0.136 hours <br />8.101852e-4 weeks <br />1.86445e-4 months <br /> from the previous inspection.
PAGE 3 0F 3 TABLE 1 CORRECTION T0 APPENDIX II 0F VEGP DR/QR V0GTLE PAGE NUMBER COMPONENT DESCRIPTION COMPONENT NUMBER COMMENTS I I-E-2 Barring Device Air Filter 02-525B II-E-2 Barring Device Control 02-525B Valve and Press Regulator II-E-3 Crankcase Vacuum Fan 02-387A II-E-6 Flywheel Bolting N/A Matrix does not require maintenance on Vogtle engine II-E-6 Gear Train N/A Matrix does not require maintenance on Vogtle engine II-E-7 Hydraulic Valve Lifters N/A Vogtle does not have hydraulic valve lifters II-3-8 Lube Oil Keep-Warm Strainer SE-031
1 1
ATTACHMENT II PHASE II COMP 0NENT INSPECTION STATUS The vast majority of Phase II inspections has been completed. Most cf these
. inspections were documented in the VEGP DR/QR. At the time the DR/QR was finalized for VEGP several items were pending or incomplete. Our letter to the staff dated September 19, 1986, contained in Attachment I, information concerning questions the staff had concerning the VEGP DR/QR. The. following is a comprehensive list of all known outstanding inspections within .the scope of the DR/QR.
- 1. Component - MP-022/23 - Turbochargers (a) Inspect thrust bearings following 100 starts -
Will be performed prior to fuel load following ESFAS testing.
(b) Perform liquid penetrant test on the stationary nozzle ring following 100 starts -
Will be performed prior to fuel load following ESFAS testing.
- 2. Component 02-310A - Crankshaft (a) Perform torsiograph testing - Will be performed during ESFAS testing prior to fuel load.
- 3. Component 02-442A - Starting Air Distributors (a) Verify installation _of folicwer lobe on camshaft -
Will be performed prior to fuel load following ESFAS testing.
(b) Evaluate wear of air distributors cam lobes and valve spools - Will be performed prior to fuel load following ESFAS testing.
- 4. Component 02-455C - Fuel Oil Filters and Strainers (a) Visually inspect the as-installed condition of mounting handware - Will be performed prior to fuel load following ESFAS testing.
ATTACHMENT III Plant Vogtle will take exception to the following two items of the DR/QR with justifications provided.
- 1. The Owner's Group recommends per task description No.
Dr-11-02-420-1 that a dresser coupling be added on the pump suction line to mitigate the thermal expansion loading and stresses on the pump inlet nozzle.
Bechtel Power Corporation performed an analysis on this line to determine the pump loads on the pump nozzle (Ref. Calc. X4C2403G0309 Rev. 1). TDI engineer, T. Bridge, Wds contacted to verify the design assumptions used were in agreement with TDI design.
The result of the analysis showed that no revision to the piping is required as all loads are within allowable limits.
- 2. The Owner's Group recommends per task description No.
DR-11-02-380A-0 to replace one slip joint at the end of each of the sliding spans on the exhaust manafold, with a slip-on flange.
Duke Power has analyzed the original design and the Owner's Group proposed modification per Supplement Report No. 1 Rev. 1 for component 02-380A (Attached).
The result of the analysis showed that the exhaust manifold piping as designed and installed by TDI is adequate to perform its intended design function.
h V DUKE POWER COMPANY e, s. e e s a s e s e GENERAL OFFICES """'s'll.',!!!
4:s seets snescu steest l CHARLOTTE. N. C. 28242 November 5,1985 Mr 0 Batur:, General Manager Engineering Department Georfia Power Company Route 2, Box 299A Waynesboro, GA 30830 5e: Management and Technical f ervices !
T0! wiesel Gercator Owners Group I Vogtle Electric G*nerating Plant - Unit 1 Exhaust Manifcid Piping Supplemental Report, Revistan 1 File: MTS-4086
Dear Mr Batum:
Attached please find one copy of Supplemental Report No.1. Rev.1 for Component 02-380A. This revision adds References 3 and 4 If you have any questions or require additional information, please contact S E Eckert at 704-373-3818.
Very truly yours, A P Cobb, Jr. Manager -
Project Management Olvision y: AM st Sen r Engineer AMS/SEE/gla/E10-22/2 cc: C L Ray (w/o attach)
DUKE I MANAGEMENT AND POWER I TECHNICAL SERVICES
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _