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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
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11 arch 20,1992 Lty.03551 001325 Docket Nos. 50 424 50-425 TAC h68621 M73447 U. S. Nuclear Regulatory Comission ATTN: Document Control Desk Washington, D. C. 20555 Gentlemen:
V0GTLE ELECTRIC GENERATING PLAN 1 REPLY TO NRC SAFETY EVALUATION AND RECOMMENDATIONS FOR VEGP STATION BtACKOUT COPING ANAL 111]i Georgia Power Company (GPC) letters ELV 00432, ELV 01474, and ELV-02867, dated A)ril 12,1989, March 28,1990, and June 7, 1991, transmitted GPC's response to tie station blackout (S80) rule for Vogtle Electric Generating Plant (VEGP). On February 20, 1992, the NRC staff issued its safety evaluation (SC) for that response. In the SE, the NRC staff stated that VEGP's proposed method of coping with a station blackout (SBO) conforms to the SB0 rule, subject to the satisfactory resolution of certain items. The attachment to this letter addresses each SE item of concern and provides our plans and schedule for implementing your recommendations or the justification why the recommended action is not required.
Please contact us if you have any questions or need further information regarding this matter.
Sincerely.
$1f ' '
0C. K. McCoy '
j CKM/AFS/gmb /
At t ac ht,'.ent : Reply to NRC SE for VEGP SB0 Coping Analysis xc: Georaia Power Comoany Mr. W. B. Shipman Mr. M. Sheibani NORMS U. S. Nuclear Regglatory Commision Mr. S. D. Ebneter, Regional Administrator l
Mr. D. S. Hood, Licensing Project Manager, NRR gh-Mr. B. R. Bonser, Senior Resident inspector, Vogtle .
j[j33[$$ck0 0 4 L J
ATTACHMENT V0GTLE ELECTRIC CENERAllNG PLANT REPLY .10_SE FOR STAT 10N BLM1QQ1 2.2.2 CLASS _lE BATTERY (APACITY Staff Evalwltion of_ licensee RESE2H11'1 The review of the battery sizing calculations for SB0 loads provided by the licensee reveals the following concerns:
- 1. The licensee needs to verify that the battery room tem 3erature of 700F as used in the battery capacity calculations is tie lowest anticipated electrolyte temperature during normal operation per NUMARC 87-00, Section 7.2.2.
- 2. The licensee did not consider any design margin (10 percent to 15 percent per IEEE Ltd. 485) in its battery capacity calculation.
- 3. The inverter 100114 full lead efficiency of 74.5 percent as used in the calculation is non conservative since the load is 80 percent of the rating.
- 4. The no load loss of 1800W for 25KVA inverters (100115 and 10D116) is non conservative.
Based on the above, the staff cannot conclude on the adequacy of the battery capacity.
EECpmmqpig11gjl1 The licensee needs to re-evaluate the battery capacity considering the above concerns. The battery capacity verification and any resulting modification should be included in the documentation that is to be maintained by the licensee in support of the 500 submittals.
Reinsfis.1 With the information provided below which addresses the four specific concerns about SB0 battery sizing calculations, VEGP is c.onfident the batteries meet the requirements for coping with a 4-hour station blackout without requiring any modifications or load stripping.
- 1. Per VEGP Technical Specification section 4.8.2.1.b battery electrolyte temperatures are nionitored to ensure that electrolyte temperatures do not fall below 700F during normal plant operation.
In addition, the daily control building operator surveillance rounds verify that the temperature for the class IE battery rooms is not below 700f during normal plant operation.
1
ATTACH!iENT (C0t411NUED)
V0GTLE ELECTRIC GENERATING PLANT REPLY 10 SLJAR_11A110N Bt ACK0VI 2.2.2 CLASS lE BATTERY CAPACITY Response (contimteni
- 2. Additional design margins as recommended in IEEE Standard 485 were not factored into the 580 battery sizing calculation because the SB0 battery profiles as current'y modeled in conjunction with the applied IEEE methodology are conservative. As an example, the loads fed from the Class 10 inverters used in the calculation are at least 40-percent greater than the actual field loads recorded at i VEGP Units 1 and 2 during 100 percent power operation. The actual 100-percent power inverter load is a good representative inverter load for SB0 conditions. If actual inverter load currents recorded during 100 percent unit power operation, were used in the calculation, it would show that design margins in excess of 10 aercent are available. Design margin is used in initial plant aattery design calculations, and is applied to compensate for load expansion, temperature, and maintenance factors. Additionally, temperature correction factors are independently accounted for in the SB0 battery sizing calculation. The SB0 battery sizing calculations will be revised by february 1993 to document these justifications as the basis for not using the IEEE-recommended ,
design margins and to incorporate changes outlined in 3 and 4 below. Also, note that as currently stated in the 500 battery sizing calculation, all future load additions will be evaluated against this calculation to determine acceptability of the <
modification.
- 3. The calculation will be revised to account for an inverter efficiency commensurate with an 80 percent load for inverter ,
1D0114. This small additional load, however, will not preclude the battery from performing its intended SB0 design function.
- 4. The no load loss of 1800 W for 25-kVA inverters (1C0115 and-IDDl!6) will be deleted from the SB0 battery calculation because these inverters are secured by locking open their corresponding feeder ,
breakers during normal plant operation. Administrative controls 1 are in place during normal plant operatinn to ensure that these inverters 'and their loads (residual heat removal isolation valves) are deenergized, i
r 2-l l
i l
A1TAtletENT (*0NTINUED)
V0GTLE ELECTRIC GENERATING PLANT reply 10 SE FOR $1AUgWM@yl 2.2.4 EffECTLOf LOSS Of VENTILAUM itsff Evaluation of Licenne_Rurmttet With the exception of the calculated temperature (1190f) for the control building inverter and switchgear rooms, the calculated temperatures for all areas are within the acceptance limits described in NUMARC 87-00 for the equipment required to cope with an SB0 event.
The licensee used the normal room temperature as the initial temperatures for the control building inverter and switchgear rooms heat up calculations. The staff finds that the licensee should either use as an initial temperature the maximum allowed by TS or the maximum value allowed under administrative procedures. If the licensee's administrative procedures do not specify an operating temperature limit, the licensee should revise their administrative procedures to maintain the normal operating temperatures in these areas at or below the value used in their SB0 heat up analysis.
The licensee has not addressed the containment temperature during an ,
SB0 event and the 500 equipment operability inside the containment.
RecommendAttons:.
The licensee should verify that the containment temperature profile during an SB0 event is bounded by that of the LOCA/High Energy Line Break temperature profile. This verification should be included with other dccumentation that is to be maintained by the licensee in support of the SB0 submittals. The licensee should use an initial temperature for the SB0 control building coniplex heat-up calculation no lower than that allowed by the TS or the administrative procedures.
Resoonser Given the information arovided below, VEGP SB0 coping equipment can be reasonably assured to )e operational during the 4-hour coping duration with respect to the effects of loss of ventilation.
Containment Temperature:
Based on a review of VEGP normal containment heat loads, anticipated SB0 heat loads, and the loss of coolant accident (LOCA)/high energy line break accident (HELBA) heat loads, it was determine! that the containment SB0 environment would be enveloped by the LOCA/HELBA environment. Since all safety-related containment equipment-is quallfled to VEGP's design bases LOCA/HELBA environment, containment equipment will not be adversely affected by the SB0 containment environment.
m . _ _ . _ - . . . . _ . . . _ _ . _ _ . _ _ - - _ _ _ _ _ _ _ _ . - _ _ _ _ _ . _ _ _
A1TACHMENT (CONTINUED)
V0GTLE ELECTRIC GENERATING PLANT REPLY 10 SE FOR STATION.JMZQQl Control Building Complex float Up Calculations: l l
E.WRC 87 00, section 7.2.4, " Effects of loss of Ventilation," l states that the upper bounds for wall temperatures should be determined prior to loss of ventilation, in performing the VEGP SB0 heat up calculations, all upper bound wall j temperatures utilized were the VEGP design bases normal :
I maximum room temperatures. At VEGP the normal maximum room temperatures are those temperatures which would not be i exceeded when all normal heating, ventilation, and ,
air condi'.ioning (llVAC) is in operation, and the normal design maximum outside ambient conditions, maximum cooling water temperatures, maximum equipment heat loads, etc., exist. _As recommended by NUMARC 87 00, VEGP used the highest calculated normal ambient room temperatures, at the onset of the loss of ventilation, to calculate the final SB0 room temperatures.
This methodology provides reasonable assurance that calculated SB0 mar.imum average ambient temperature will not be exceeded.
2.2.5 CMIAllLMENT ISOLATION Staff Evaluation of Liernseo Response:
The licensee stated that the plant list of containment isolation valves '
(CIVs) had been reviewed to verify that valves which must be capable of being closed or that mus, be operated (cycled) under SB0 conditions can be positioned (with indication) independent of the preferred and blacked out unit's Class IE power supplies. The licensee further stated that no plant modifications or procedure changes are recuired to ensure appropriate containment integrity under SB0 concitions.
Based on its review of SAIC's TER and the list of CIVs provided by the licensee, the staff concurs with the SAIC TER that with the exception of the excess letdown and sealwater line penetration (X 49), the containment isolation valve design and operativa at Vogtle plant have met the intent of the guidances described in RG 1.155.
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4 A11ACitMLNT (CONilNU[D)
V0 GILE ELECTRIC GENERAllNG PLANT M.PtY 1Q. SE FOR STA110t{JLQiOLQ Recommendation; l
, I 1he licensee needs to list the normally open ac motor operated globe l valves in the excess letdown and seal water leakoff line (X 49) in an l aapropriate procedure and identify the actions necessary to ensure that ;
taese valves can be fully closed during an 5110 event. The valve i closure needs to be confirmed by position indication (local, ,
mechanical, remote, process information, etc.). ?'ils information i should be included with the other documentation that is to be i maintained by the licensee in support of the 500 submittals.
Remonse:
The excess letdown and seal water line containment isolation valves are nominal 2 inch diameter valves. In accordance with the criteria i presented in Regulatory Guide 1.155, paragraph 3.2.7, valves less than 3 inch nominal diameter are excluded from further consideration of l containment isolation capabilities. Therefore, containment integrity is maintained under SB0 conditions.
2.3 PROCEDURES AND 1rAIM M Staff Evalyalion of Unnsee Responsn the liccnsee stated that the procedural requirements for co)ing with an ,
S00 have been reviewed sad the grid restoration procedures iave been u3 dated to meet the requirements of the SB0 Rule. The licensee added tlTe following documents to the SB0 procedures: '
Black Start Procedures for Plant Vogtle; Restoration of Offsite AC Power for the Shutdown of VEGP.
The licensee also stated that the plant procedures have been reviewed, ,
and changes, if necessary to meet NUMARC 87-00, will be implemented in !
the following areas:
Loss of all AC; Severe Weather; and System Operating Procedures for Diesel Generator Operation. !
S-I i
e,e.r-+-*,.s,---:e - -
s l ATTACliMENT (CON 11NUED)
V0GTLE ELECTRIC GENERATING ptANT reply TO SE FOR JJATION BLACKQ21 4
The licensee indicated that these procedure changes will be completed !'
within one year af ter the issuance of the SE.
The staff did not review the affected procedures or training. The staff expects the Ticensee to maintain and implement these procedures ,
including any others that may be required to ensure an appropriate '
response to an 500 event. Although persnnnel training requirements for an SB0 response were not specifically addressed in the licensee's submittals, the staff expects the licensee to implement the appropriate training to ensure an effective response to an SBO.
Recormendation:
Not Applicable.
Respon s The applicable plant procedures will be revised by february 1993 and [
appropriate training completed by June 1993 to meet NUMARC 87-00 and 10 CFR 50.63 requiren.cnts for satisfactorily coping with a station ,
blackout event.
2.4 PROPOSED _]iQDlf! CATIONS t
Staff Evaluation of LicefSee Resngnin The licensee stated that the following modifications would be required to attain the proposed 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> SB0 coping duration:
- 1. Lighting in the common main control room will be augmented to
, assure sufficient lighting after the 90 minutes of initial lighting j provided by self-containoa gel-cell tattery packs.
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- 2. Six circuP hreakers in Unit 1 and seven circuit breakers in Unit 2 will be reblaced with larger size circuit breakers to avoid the potential of spurious tripping due to a temperature induced shift 1 in tripping characteristics at elevated ambient temperatures.
The licensee indicated that the above modifications will be completed within one year after the issuance nf the SE.
Secommendation:
L The licensee should include a full description including the nature and I objectives of the required modifications in the documentation that is l to be maintained by the licensee in support of the SB0 submittals.
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A11ACHMENT(CONTINUED) .
l V001tE LLECTRIC GEN [ RATING PLAN 1 RELL10.JiLLQ1L11al10Ll!1ACraul 1 Bucanin Both proposed modifications needed for coping with SB0 are being processed and implemented per plant procedures and will become a Quality Assurance (QA) record retained for the life of the plant.
- 1. The additional emergency lighting will be installed in the control room by February 1993.
- 2. The circuit breaker replacements required to avoid spurious trips due to a temperature induced shift in tripping chtracteristics l during SBO, for both Unit I and Unit 2, are complete. l 2.5 01A.LjiY ASSURA4 CLAW _ILCIE(ICALSPECILLCA110fis llaff Evaluation of iktDHt_J!tip.cniu The licensee did not address quality assurance (QA) or 15 pertaining to i the SB0 equipment.
I The TS for the 500 equipment are currently being considered generically by the NRC in the ntext of the TS Improvement Program and remains an open item at this time, llowever, the staff would expect that the plant procedures will reflect the appropriate testing and surveillance requirements to ensure the operability of the necessary SB0 equipment. i If the staff later determit.es that a TS regarding the 500 equipment is warranted, the licensee will be notified of the implementation requirements.
RcU Andal.igni ;
The licensee should verify that the 580 equipment is covered by an appropriate QA program consistent with the guidance o' RG 1.155, -
A>pendix A. Furthur, this verification should be documented as part nf :
tle package supporting the 500 Rule response.
Response
Station blackout coping equipment was procured as safety related; therefore, it is covered by an appropriate QA program.
Nonsafety related equipment ultitzed by operators during an 500 is emergency lighting and surveillance procedures are in place and performed to verify its continued operability. Therefore, the QA requirements of Regulatory Guide 1.155 are met with 500 coping equipment.
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4 ATTACHMElli (C0rJTINVED)
V0 GILE ELECTRIC GENERATING PLAN 1 REPLY 10 SE FOR STA110N BLA%QQ1 2.6 [QG REllABILITY PROGRAM
$1aff Evaluation of Licensee Eningnin The licensee's submittals on 5B0 did not specifically 4ddress the commitment to implement an EDG *eliability pregram to conform to the guidance of RG 1.155, Position 1.2. However, in the submittal of March 28, 1990, the licensee coramittt>d to maintain the EDG target reliability of 0.95. Although the licensee has committed to a reliability program pending resolution of Gl B 56, " Diesel Generator Reliability," they should implement a program that meets as a minimum the guidance of RG 1.155, Pesition 1.2.
Becommendalini lhe licensee should provide confirmation and include in the documentation supporting the 500 submittalt that is to be maintained by the licensee that such a program meeting the guidance of Regulatory Guide 1.155, Position 1.2, is in place or will be implementad.
EUMDin A procedure for the diesel generator reliability program is being developed to implement the guidelines of NUMARC 87-00 Appendix 0, which incorporates the requirements of Regulatory Guide 1.155. This procedure will be completed by June 1992.
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