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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
. . _ _ . . . . - .
'* J. Bamie Beasley, Jr, P.E. Southern Nuclear
- - - Vice President Operating Company,Inc.
Vogtle Project c inverness Center Parkway P0. Box 1295 Birmingham. Alabama 35201 Tel 205.992.7110 Fcx 205.992.0403 SOUTHERN COMPANY Enery to Serve YourWorld" December 16, 1998 LCV-l l75-A Docket Nos. 50-424 I 50-425-U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555 Ladies and Gentlemen:
VOGTLE ELECTRIC GENERATING PLANT l REQUEST TO REVISE TECHNICAL SPECIFICATIONS ELIMINATION OF PERIODIC PRESSURE SENSOR RESPONSE TIME TESTS AND ELIMINATION OF PERIODIC PROTECTION CHANNEL RESPONSE TIME TESTS l
By letter dated July 13,1998, (LCV-1175) Southern Nuclear Operating Company (SNC) proposed to revise the Vogtle Electric Generating Plant (VEGP) Unit I and Unit 2 Technical Specifications (TS) to eliminate periodic response time testing requirements on selected
. sensors and selected protection channels. In support of their review of the proposed amendment, the NRC staff has requested additionalinformation. The requested information .
is provided in the enclosed Response to Request for Additional Information. ;
Sincerely.
d's
. B. Beasley, Jr.
\
JBBMJS
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I' OS 9812230292 981216 PDR ADOCK 05000424-N P
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U. N. Nuclur Regulitory Commission d'
LCV-I l75-A
- Page 2 l
Enclosure:
. Response to Request for Additional Information l-xc: Southern Nuclear Operating Company Mr. J. T. Gasser Mr. M. Sheibani
. NORMS l ..
U. S. Nuclear Regulatory Commission Mr. L. A. Reyes, Regional Administrator Mr. D.'ll. Jaffe, Senior I-roject Manager, NRR i Mr. John Zeiler, Senior Resident inspector, Vogtle State of Georgia Mr. L. C. Barrett, Commissioner, Department of Natural Resources -
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I DTechnical Specifications \TECllSPEC\RTT_ELIMilfV i l 75.A. DOC
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Enclosure Vogtle Electric Generating Plant Request to Revise Technical Specifications Elimination Of Periodic Pressure Sensor Response Time Tests And Elimination Of Periodic Protection Channel Response Time Tests Response to Request for Additional Information Questions:
- 1. Please state which protection channel equipment is in the RPS and ESF systems.
- 2. Do the model versions and the printed circuit board revision level match the equipment analyzed in the WOG submittal? ;
1
- 3. For sensors where RTT will no longer be performed, w hat assumed response time is being used, and how was that number derived? If the assumed response time value was derived from historical data, please provide that data.
j Answers:
- 1. The requested information is provided in the following table.
- 2. Yes, the Failure Modes and Effects Analysis (FMEA) in WCAP- 14036 Rev.1, is applicable to the equipment actually installed at Vogtle Units I and 2, and the analysis is valid for the versions of boards utilized. <
l
- 3. The requested information is provided in the following table.
1 i
l 1
l I
l E-1
. +
J VOGTLE UNITS 1 AND 2 !
PROCESS / FUNCTION / ENGIN EERED SAFETY FEATURE / ALLOCATION / TABLE ' [
~i FUNCTION - SENSOR TIME 7300/NIS STRING TIME SSPS RELAYS - TIME -+
CONT. PRESS 111-1 Barton 764/351 1.Osec NLP+NAL 65ms input + Master + Slave =88ms -
CONT. PRESS 111-2 Barton 764/351 1.0sec NLP+NAL 65ms Input + Master + Slave $8ms l CONT. PRESS 111-3 Barton 764/351 1.0sec NLP+NAL 65ms input + Master + Slave 88ms )
STEAM LINE PRESS Tobar 32PA 200ms NLP+NAL 65ms input + Master + Slave - 88ms ,
LO Veritrak 76PG 200ms r
,~ Rosemount i154S119 200ms
[
Rosemount 1153GB9 200ms j STEAM LINE PRESS Tobar 32PA 200ms NLP+NAL 65ms input + Master + Slave 88ms
- . til NEG RATE Veritrak 76PG 200ms [
Rosemount 1154Sil9 200ms Rosemount i153GB9 200ms -
PZR PRESS LO SI Tobar 32PG 200ms NLP+NAL ~ 65ms input + Master + Slave - 88ms -l Veritrak 76Pil 200ms -[
i Rosemount i154S119 200ms !
i-RWST LEVEL LO-LO Tobar 32DP 400ms NLP+NAL 65ms input + Master + Slave 88ms ,
Veritrak 76DP 400ms [
Rosemount i153DB5 200ms '!
SG LEVEL LO-LO Tobar 32DP 400ms NLP+NAL 65ms input + Master + Slave 88ms !
, Veritrak 76DP 400ms !
Rosemount i154D115 - 200ms [
i SG LEVEL 111-111 Tobar 32DP 400ms NLP+NAL 65ms input + Master + Stave 88ms Veritrak 76DP 400ms 'I Rosemount i154Dil5 200ms 4
i i [
l I i t i
- -r- * -
- *p . ;
-VOGTLE UNITS I AND 2 .-
PROCESS / FUNCTION / REACTOR TRIP / ALLOCATION / TABLE / (Continued) ' 4 a
- FUNCTION SENSOR . TIME 7300/NIS STRING TIME SSPS RELAYS - TIME -*
NIS RATE lil Detectors Exempt - N/A NIS FMEA 200ms Input 20ms CONTAINMENT - Barton 764/351 1.0sec NLP+NAL 65ms Input 20ms PRESS. REACTOR TRIP FROM (SI) -
STEAMLINE PRESS Tobar 32PA 200ms NLP+NAL 65ms input 20ms LO REACTOR TRIP Veritrak 76PG 200ms FROM (SI) Rosemount 1154S119 200ms Rosemount i153GB9 200ms
. (Note 1) Al!ocated sensor times not used for these variables. These components will continue to be tested as required. !
Allocated sensor times are derived from method (3; section (9) WCAP-13632 rev. 2 (Vendor Engineering Specifications). Tobar, Veritrak, and Barton times were provided on Table 9-1. Rosemount times are from Rosemount manuals 4302 and 4631. The Rosemount response time specifications may also be found in NUREG/CR-5333. Transmitter FMEAs are based upon EPRI report NP-7243 rev 1.
Values for 7300 cards are from tables 4-7 through 4-12 of WCAP-14036 rev.1. Cards installed are 4NCII,4NRA,6NLP,4NSA, and 9NAL or older artwork l
levels. NIS components installed are; Summing and Level Amp (3359C48G01), Isolation Amp (6%5D75G01), Rate Circuit Assy(3359C41G01), and Bistable
- Relay Driver Assy (3359C39G01). These were evaluated per NIS FMEA schematic diagram 6065D99.
i SSPS Input and Master relays are Potter & Brumfield Kil series relays. SSPS Slave relays are Pott; i Brumfield MDR relays. Values are tabulated from section 4.8 Westinghouse SSPS FMEA.
t t
5
. _ _ _ . _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ ___m__.______.___._______-___m._______ .___.-m_ - _ . , , . - - . _ _ , _ < . , , . _ . . - _ , . _,,r . . ...m.- -.. . - .
VOGTLE UNITS I AND 2 .
PROCESS / FUNCTION / REACTOR TRIP / ALLOCATION / TABLE ;
FUNCTION SENSOR TIME 7300/NIS STRING TIME SSPS RELAYS TIME -
PZR. PRESS. til Tobar 32PG 200ms NLP+NAL 65ms input 20ms Veritrak 76Pil 200ms Rosemount 1154S119 200ms PZR. PRESS. LO Tobar 32PG 200ms NLP+NAL 65ms input 20ms Veritrak 76Pil 200ms Rosemount i154S119 200ms SG LEVEL LO-LO Tobar 32DP 400ms NLP+NAL 65ms input 20ms Veritrak 76DP 400ms Rosemount i154Dil5 200ms RCS FLOW LO fobar 32DP 400ms NLP+NAL 65ms input 20ms Veritrak 76DP 400ms Rosemount 115311B5 200ms OPDT (Vary Tavg) Weed N9004E-2B (Note 1) N RA+NSA+NSA +NSA+NS A+N AL 368ms Input 20ms OPDT (Vary DeltaT) Weed N9004E-2B (Note 1) NRA+NSA+NSA+ NAL 293ms Input 20ms OTDT(Vary Tavg) Weed N9004E-2B (Note 1) NRA+NSA+NSA+NSA+NAL 330.5ms input 20ms OTDT (Vary DeltaT) Weed N9004E-2B (Note 1) NRA+NSA+NSA+ NAL 293ms Input 20ms OTDT (Vary Press) Tobar 32PG 200ms NLP+ NSA+NS A+ NAL 145ms input 20ms Veritrak 76Pil 200ms Rosemount i154Sil9 200ms OTDT (Vary Flux) Detectors Exempt N/A NIS (Ims) + NSA+NCil+NSA+NAL 148.5ms input 20ms RCP VOLTAGE LO GE NGV/ SAM (Note 1) N/A N/A Input 20ms RCP FREQ. LO ABB (Note 1) N/A N/A Input 20ms NIS LEVEL 111 Detectors Exempt N/A NIS FMEA 65ms input 20ms
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' VOGTLE UNITS 1 AND 2 - _ , ,. .
PROCESS / FUNCTION / ENGINEERED SAFETY FEATURE / ALLOCATION / TABLE . ',
FUNCTION SENSOR TIME 7300/NIS STRING TIME SSPS RELAYS TIME .
- CONTAINMENT Westinghouse . (Note 1) N/A N/A Input + Master + Slave - #8ms AREA RADIATION "
, LEVEL 111 CONTAINMENT Westinghouse (Note 1) N/A N/A Input + Master + Slave + Slave 124ms ,
VENT RADIATION . i LEVEL HI ~
(Note 1) Allocated sensor times not used for these variables. These components will continue to be tested as required. [
Allocated sensor times are derived from method (3) section (9) WCAP-13632 rev. 2 (Vendor Engineering Specifications).' Tobar, Veritrak, and Barton times were . ,
provided on Table 9-l. Rosemount times are from Rosemount manuals 4302 and 4631. He Rosemount response time specifications may also be found in l NUREG/CR-5383. Transmitter FMEAs are based upon EPRI report NP-7243 rev 1. !
Values for 7300 cards are from tables 4-7 through 4-12 of WCAP-14036 rev.1. Cards installed are 4NCII,4NRA,6NLP,4NSA. and 9NAL or older artwork -
levels.
i SSPS Input and Master relays are Potter & Brumfield Kil series relays. SSPS Slave relays are Potter & Brumfield MDR relays. Values are tabulated from section 4.8 Westinghouse SSPS FMEA.
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