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Category:MEETING MINUTES & NOTES--CORRESPONDENCE
MONTHYEARML20207G5151999-06-0808 June 1999 Summary of 990422 Meeting with Ue & NRC Staff Re Electrosleeved Repaired SG Tubes During Beyond Design Basis Accidents.List of Meeting Attendees,Nrc Staff Meeting Presentation Matls & Ue Meeting Presentation Matls Encl ML20205J6591999-04-0606 April 1999 Summary of 990318 Meeting with Union Electric & Framatome Technologies Re Electrosleeve Amend Application for Callaway Npp.List of Telcon Participants & Union Electric Fax with Callaway Probability Info Encl ML20199G9871999-01-20020 January 1999 Summary of 981014 & 15 Meetings with WCNOC & Ue Re Proposed TS Amend That Supports Mod to Increase Sfp.List of Attendees & Summary of Each Topic Discussed Encl ML20198M3111998-12-29029 December 1998 Summary of 981203 Meeting with Wolf Creek Nuclear Operating Co Re Amend Application Requesting Approval to Increase SFP Capacity at Wolf Creek & Callaway Plants.List of Attendees & Licensee Presentation Matl Encl ML20248H0551998-06-0101 June 1998 Summary of 980513 Meeting W/Utils Re Proposed Amends to TSs to Support Planned Mods to Spent Fuel Pools at Plants ML20217A0261998-03-18018 March 1998 Summary of 980129 Meeting W/Util to Discuss Licensee Interpretation of Allowance to Perform TS Required Shutdown Surveillance Testing While at Power.Oversize Drawings Encl ML20198H5661997-12-31031 December 1997 Summary of 971209 Meeting W/Union Electric & Framatome Technologies,Inc in Rockville,Md Re Electrosleeving Process in Support of Union Electric Proposed TS Amend That Would Allow Electrosleeving of SG Tubes at Plant ML20198G2211997-12-22022 December 1997 Summary of 971120 Meeting W/Util in Rockville,Md,Re Electrosleeving Process in Support of UE-proposed TS Amend That Would Allow Electrosleeving of Steam Generator Tubes at Callaway Plant.List of Attendees Encl ML20199F2691997-11-19019 November 1997 Summary of 971008 & 09 Meetings W/Union Electric & Westinghouse Electric Corp to Discuss Effects of Axial Offset Anomaly Currently Being Experienced by Plant.List of Attendees & non-proprietary Versions of Handout Matls Encl ML20217E0411997-09-24024 September 1997 Summary of 970813 Meeting W/Une & Framatome Technologies Re Electrosleeving Process in Support of UNE-proposed TS Amend That Would Allow Electrosleeving of SG Tubes at Plant.List of Attendees & Meeting Handout Matl Encl ML20149G3231997-07-18018 July 1997 Summary of 970506 & 07 Meetings W/Listed Attendees in Toronto,Ontario,Canada to Discuss FTI SG Electrosleeving Process.Nonproprietary Version of Handout Matl Presented at Meeting Encl ML20149H2751997-07-17017 July 1997 Summary of 970513-15 Meeting W/Util in Lynchburg,Va Re Licensee Steam Generator Electrosleeving Process.Meeting Attendees & Meeting Slides Encl ML20147G8311997-03-27027 March 1997 Summary of 970220 Meeting W/Util Re June 1997 Operational Safeguards Response Evaluation at Plant ML20133P8681997-01-22022 January 1997 Summary of 970114 Meeting W/Util Re Future Plans for Core Reload Design Analysis for Plant.List of Attendees & Matls Used in Presentation Encl ML20059G5761994-01-12012 January 1994 Summary of 931209 Meeting W/Representatives of Util & Licensee Contractors to Discuss Planned Elimination of SG Hydraulic Snubbers at Plants.List of Attendees & Licensee Presentation Handout Encl ML20059F9021994-01-11011 January 1994 Summary of 931208 Meeting W/Representatives of Wcnoc,Une & Licensees Contractor to Discuss TS Changes Being Considered by Licensees.List of Attendees Encl ML20149D6051993-09-15015 September 1993 Summary of 930708 Region III Annual Training Managers Conference in Glen Ellyn,Il.Purpose of Meeting to Provide Forum for Discussion on Rev 7 of Operator Licensing Examiner Stds & to Discuss Operator Licensing Issues ML20128F0731993-02-0808 February 1993 Summary of 921215 Meeting W/Util in Rockville,Md Re Deletion or Modification of Boron Dilution Mitigation Sys.List of Attendees & Viewgraphs Encl ML20246J7081989-07-12012 July 1989 Trip Rept of 890619-23 Visit to Plant & Training for Unescorted Site Access to Nonradiological & Radiological Areas.Training Completed by Passing Two Exams ML20246L7281989-05-0505 May 1989 Summary of 890503 Meeting W/Util in Rockville,Md Re Containment Vessel Structural Integrity Tech Specs for Plants.List of Attendees & Licensee Presentation Encl ML20235R2211989-02-23023 February 1989 Summary of 890214 Meeting W/Util & Westinghouse Re Licensee Reload Application.Licensee Proposed Tech Spec Changes Include Increased Peaking Factors,Positive Moderator Temp Coefficient & Increased Boron Concentration.Viewgraphs Encl ML20153G5481988-05-0404 May 1988 Summary of 880427 Telcon W/Utils in Region III Re Personnel Changes,Follow Up on Previous Items,Items of Interest from Sites & New Items ML20151N4711988-04-13013 April 1988 Summary of 880407 Meeting W/Util & Westinghouse Re Reload for Cycle 4.Meeting Attendees & Nonproprietary Presentation Encl ML20148P5881988-04-0101 April 1988 Summary of 880316 Meeting W/Utils Re Containment Tendon Tech Specs for Facilities.Attendance List & Licensees Presentation Encl ML20148H6621988-01-15015 January 1988 Summary of Operating Reactors Events Meeting 88-02 on 880112 Re Events Which Occurred Since Last Meeting on 880105.List of Attendees,Significant Elements of Events & Tabulation of long-term Followup Assignments to Be Completed Encl ML20236P2841987-11-0505 November 1987 Summary of Operating Reactors Events Meeting 87-38 on 871103.List of Attendees,Viewgraphs & Summary of Reactor Scrams Encl ML20236K8011987-11-0202 November 1987 Summary of 871023 Meeting W/Util Re Stuck Reactor Vessel Head Closure Bolts at Plant.Util Requested to Submit Analysis of Three Adjacent Bolts & Listed Commitments, Including Strict Leakage Limit on Vessel Flange ML20236A4901987-10-14014 October 1987 Summary of 871006 Meeting W/Util & Westinghouse to Discuss Transition Core Departure from Nucleate Boiling Ratio Penalty for Cycle 3 Operation.Attendee List,Util Ltr & Proprietary & Nonproprietary Viewgraphs Encl.Record Copy ML20236A4861987-10-14014 October 1987 Summary of 871006 Meeting W/Util & Westinghouse to Discuss Transition Core Departure from Nucleate Boiling Ratio Penalty for Cycle 3 Operation.Attendee List,Util Ltr & Proprietary & Nonproprietary Viewgraphs Encl ML20237L1111987-08-28028 August 1987 Summary of Operating Reactors Events Meeting 87-28 on 870825 Re Events Which Occurred Since 870818 Meeting.List of Attendees & Significant Elements Encl ML20213F8021987-05-0404 May 1987 Summary of 870429 Meeting W/Util & Westinghouse Re Reload for Cycle 3 & Power Uprating Amend Requests.List of Attendees & Viewgraphs Encl ML20212F2921986-12-30030 December 1986 Summary of Operating Reactors Events Meeting 86-45 on 861222 Re Events Which Occurred Since Last Meeting on 861215.List of Attendees & Significant Elements of Events Discussed Encl ML20211G7781986-06-13013 June 1986 Summary of Operating Reactor Events Meeting 86-19 on 860609. List of Attendees,Events Discussed & Status of Previous Assignments Encl ML20154K2171986-03-0505 March 1986 Summary of Allegation Review Board 860210 Meeting.Listed Actions to Close Allegations RIII-86-A-002,RIII-86-A-0007, RIII-86-A-011,RIII-85-A-0188,RIII-85-A-0208 & RIII-86-A-003 Agreed Upon ML20138J8441985-12-12012 December 1985 Summary of 851205 Meeting W/Util & Westinghouse Re 851115 Reload Submittal for Cycle 2.Non-LOCA Transient Analysis, LOCA Analysis,Tech Spec Changes & Radiological Consequences Discussed.Viewgraphs & List of Attendees Encl ML20136G9081985-11-15015 November 1985 Summary of 850522 Meeting W/Kansas Gas & Electric Co,Union Electric Co & Snupps in Bethesda,Md Re Snupps Spds.List of Attendees & Proposed Agenda Encl ML20138R6711985-11-0707 November 1985 Summary of 851105 Meeting W/Util & Snupps at Site Re Proposed Mods to Low Temp Overpressure Protection Sys. Attendee List & Slides Used During Presentation Encl ML20141E5521985-09-26026 September 1985 Summary of ACRS Subcommittee on Reactor Operations 850910 Meeting in Washington,Dc to Discuss Recent Operating Occurrences.Fr Notice,Meeting Schedule & List of Meeting Slides Encl ML20209G6871985-09-0909 September 1985 Summary of Operating Reactor Events Meeting 85-14 on 850826 to Brief Director & Div Directors on Events Which Occurred Since 850813 Meeting.Computer Printout of 1985 Operating Reactor Events Meeting Topics to Date Encl IA-85-160, Trip Rept of Site Visit During Wk of 831031 Re Physical Arrangement & Installation of Electrical,Instrumentation & Control Equipment.Compliance W/Nrc Design Criteria Confirmed1984-04-13013 April 1984 Trip Rept of Site Visit During Wk of 831031 Re Physical Arrangement & Installation of Electrical,Instrumentation & Control Equipment.Compliance W/Nrc Design Criteria Confirmed ML20127B5101984-04-13013 April 1984 Trip Rept of Site Visit During Wk of 831031 Re Physical Arrangement & Installation of Electrical,Instrumentation & Control Equipment.Compliance W/Nrc Design Criteria Confirmed ML20054J0301982-06-17017 June 1982 Summary of 820430 Meeting W/Utils & Bechtel in Bethesda,Md Re Alternate Shutdown Panel & Related Fire Protection 1999-06-08
[Table view] Category:MEETING SUMMARIES-INTERNAL (NON-TRANSCRIPT)
MONTHYEARML20207G5151999-06-0808 June 1999 Summary of 990422 Meeting with Ue & NRC Staff Re Electrosleeved Repaired SG Tubes During Beyond Design Basis Accidents.List of Meeting Attendees,Nrc Staff Meeting Presentation Matls & Ue Meeting Presentation Matls Encl ML20205J6591999-04-0606 April 1999 Summary of 990318 Meeting with Union Electric & Framatome Technologies Re Electrosleeve Amend Application for Callaway Npp.List of Telcon Participants & Union Electric Fax with Callaway Probability Info Encl ML20199G9871999-01-20020 January 1999 Summary of 981014 & 15 Meetings with WCNOC & Ue Re Proposed TS Amend That Supports Mod to Increase Sfp.List of Attendees & Summary of Each Topic Discussed Encl ML20198M3111998-12-29029 December 1998 Summary of 981203 Meeting with Wolf Creek Nuclear Operating Co Re Amend Application Requesting Approval to Increase SFP Capacity at Wolf Creek & Callaway Plants.List of Attendees & Licensee Presentation Matl Encl ML20248H0551998-06-0101 June 1998 Summary of 980513 Meeting W/Utils Re Proposed Amends to TSs to Support Planned Mods to Spent Fuel Pools at Plants ML20217A0261998-03-18018 March 1998 Summary of 980129 Meeting W/Util to Discuss Licensee Interpretation of Allowance to Perform TS Required Shutdown Surveillance Testing While at Power.Oversize Drawings Encl ML20198H5661997-12-31031 December 1997 Summary of 971209 Meeting W/Union Electric & Framatome Technologies,Inc in Rockville,Md Re Electrosleeving Process in Support of Union Electric Proposed TS Amend That Would Allow Electrosleeving of SG Tubes at Plant ML20198G2211997-12-22022 December 1997 Summary of 971120 Meeting W/Util in Rockville,Md,Re Electrosleeving Process in Support of UE-proposed TS Amend That Would Allow Electrosleeving of Steam Generator Tubes at Callaway Plant.List of Attendees Encl ML20199F2691997-11-19019 November 1997 Summary of 971008 & 09 Meetings W/Union Electric & Westinghouse Electric Corp to Discuss Effects of Axial Offset Anomaly Currently Being Experienced by Plant.List of Attendees & non-proprietary Versions of Handout Matls Encl ML20217E0411997-09-24024 September 1997 Summary of 970813 Meeting W/Une & Framatome Technologies Re Electrosleeving Process in Support of UNE-proposed TS Amend That Would Allow Electrosleeving of SG Tubes at Plant.List of Attendees & Meeting Handout Matl Encl ML20149G3231997-07-18018 July 1997 Summary of 970506 & 07 Meetings W/Listed Attendees in Toronto,Ontario,Canada to Discuss FTI SG Electrosleeving Process.Nonproprietary Version of Handout Matl Presented at Meeting Encl ML20149H2751997-07-17017 July 1997 Summary of 970513-15 Meeting W/Util in Lynchburg,Va Re Licensee Steam Generator Electrosleeving Process.Meeting Attendees & Meeting Slides Encl ML20147G8311997-03-27027 March 1997 Summary of 970220 Meeting W/Util Re June 1997 Operational Safeguards Response Evaluation at Plant ML20133P8681997-01-22022 January 1997 Summary of 970114 Meeting W/Util Re Future Plans for Core Reload Design Analysis for Plant.List of Attendees & Matls Used in Presentation Encl ML20059G5761994-01-12012 January 1994 Summary of 931209 Meeting W/Representatives of Util & Licensee Contractors to Discuss Planned Elimination of SG Hydraulic Snubbers at Plants.List of Attendees & Licensee Presentation Handout Encl ML20059F9021994-01-11011 January 1994 Summary of 931208 Meeting W/Representatives of Wcnoc,Une & Licensees Contractor to Discuss TS Changes Being Considered by Licensees.List of Attendees Encl ML20149D6051993-09-15015 September 1993 Summary of 930708 Region III Annual Training Managers Conference in Glen Ellyn,Il.Purpose of Meeting to Provide Forum for Discussion on Rev 7 of Operator Licensing Examiner Stds & to Discuss Operator Licensing Issues ML20128F0731993-02-0808 February 1993 Summary of 921215 Meeting W/Util in Rockville,Md Re Deletion or Modification of Boron Dilution Mitigation Sys.List of Attendees & Viewgraphs Encl ML20246L7281989-05-0505 May 1989 Summary of 890503 Meeting W/Util in Rockville,Md Re Containment Vessel Structural Integrity Tech Specs for Plants.List of Attendees & Licensee Presentation Encl ML20235R2211989-02-23023 February 1989 Summary of 890214 Meeting W/Util & Westinghouse Re Licensee Reload Application.Licensee Proposed Tech Spec Changes Include Increased Peaking Factors,Positive Moderator Temp Coefficient & Increased Boron Concentration.Viewgraphs Encl ML20153G5481988-05-0404 May 1988 Summary of 880427 Telcon W/Utils in Region III Re Personnel Changes,Follow Up on Previous Items,Items of Interest from Sites & New Items ML20151N4711988-04-13013 April 1988 Summary of 880407 Meeting W/Util & Westinghouse Re Reload for Cycle 4.Meeting Attendees & Nonproprietary Presentation Encl ML20148P5881988-04-0101 April 1988 Summary of 880316 Meeting W/Utils Re Containment Tendon Tech Specs for Facilities.Attendance List & Licensees Presentation Encl ML20148H6621988-01-15015 January 1988 Summary of Operating Reactors Events Meeting 88-02 on 880112 Re Events Which Occurred Since Last Meeting on 880105.List of Attendees,Significant Elements of Events & Tabulation of long-term Followup Assignments to Be Completed Encl ML20236P2841987-11-0505 November 1987 Summary of Operating Reactors Events Meeting 87-38 on 871103.List of Attendees,Viewgraphs & Summary of Reactor Scrams Encl ML20236K8011987-11-0202 November 1987 Summary of 871023 Meeting W/Util Re Stuck Reactor Vessel Head Closure Bolts at Plant.Util Requested to Submit Analysis of Three Adjacent Bolts & Listed Commitments, Including Strict Leakage Limit on Vessel Flange ML20236A4901987-10-14014 October 1987 Summary of 871006 Meeting W/Util & Westinghouse to Discuss Transition Core Departure from Nucleate Boiling Ratio Penalty for Cycle 3 Operation.Attendee List,Util Ltr & Proprietary & Nonproprietary Viewgraphs Encl.Record Copy ML20236A4861987-10-14014 October 1987 Summary of 871006 Meeting W/Util & Westinghouse to Discuss Transition Core Departure from Nucleate Boiling Ratio Penalty for Cycle 3 Operation.Attendee List,Util Ltr & Proprietary & Nonproprietary Viewgraphs Encl ML20237L1111987-08-28028 August 1987 Summary of Operating Reactors Events Meeting 87-28 on 870825 Re Events Which Occurred Since 870818 Meeting.List of Attendees & Significant Elements Encl ML20213F8021987-05-0404 May 1987 Summary of 870429 Meeting W/Util & Westinghouse Re Reload for Cycle 3 & Power Uprating Amend Requests.List of Attendees & Viewgraphs Encl ML20212F2921986-12-30030 December 1986 Summary of Operating Reactors Events Meeting 86-45 on 861222 Re Events Which Occurred Since Last Meeting on 861215.List of Attendees & Significant Elements of Events Discussed Encl ML20211G7781986-06-13013 June 1986 Summary of Operating Reactor Events Meeting 86-19 on 860609. List of Attendees,Events Discussed & Status of Previous Assignments Encl ML20154K2171986-03-0505 March 1986 Summary of Allegation Review Board 860210 Meeting.Listed Actions to Close Allegations RIII-86-A-002,RIII-86-A-0007, RIII-86-A-011,RIII-85-A-0188,RIII-85-A-0208 & RIII-86-A-003 Agreed Upon ML20138J8441985-12-12012 December 1985 Summary of 851205 Meeting W/Util & Westinghouse Re 851115 Reload Submittal for Cycle 2.Non-LOCA Transient Analysis, LOCA Analysis,Tech Spec Changes & Radiological Consequences Discussed.Viewgraphs & List of Attendees Encl ML20136G9081985-11-15015 November 1985 Summary of 850522 Meeting W/Kansas Gas & Electric Co,Union Electric Co & Snupps in Bethesda,Md Re Snupps Spds.List of Attendees & Proposed Agenda Encl ML20138R6711985-11-0707 November 1985 Summary of 851105 Meeting W/Util & Snupps at Site Re Proposed Mods to Low Temp Overpressure Protection Sys. Attendee List & Slides Used During Presentation Encl ML20141E5521985-09-26026 September 1985 Summary of ACRS Subcommittee on Reactor Operations 850910 Meeting in Washington,Dc to Discuss Recent Operating Occurrences.Fr Notice,Meeting Schedule & List of Meeting Slides Encl ML20209G6871985-09-0909 September 1985 Summary of Operating Reactor Events Meeting 85-14 on 850826 to Brief Director & Div Directors on Events Which Occurred Since 850813 Meeting.Computer Printout of 1985 Operating Reactor Events Meeting Topics to Date Encl ML20054J0301982-06-17017 June 1982 Summary of 820430 Meeting W/Utils & Bechtel in Bethesda,Md Re Alternate Shutdown Panel & Related Fire Protection 1999-06-08
[Table view] |
Text
,
. . April 13, 1988 Docket No. 50-483 . DISTRIBUTION:
' DOCRet rJIes ,NRC & Local PDRs LICENSEE: Union Electric Company PDIII-3 r/f XPerkins TAlexion OGC-WF1 FACILITY: Callaway Plant EJordan JPartlow ACRS(10) HRichings YGHsii
SUBJECT:
SUMMARY
OF MEETING WITH UNION ELECTRIC COMPANY REGARDING THE RELOAD FOR CYCLE 4 On April 7,1988, the NRC staff met with Union Electric Company and Westinghouse regarding the reload for Cycle 4. Meeting attendees are listed in Enclosure 1.
Non-proprietary slides presented by the licensee are in Enclosure 2. Proprietary slides presented are in Enclosure 3.
The Cycle 4 core is expected to have 88 new Vantage 5 (V-5) fuel assemblies, 96 once-burned V-5 fuel assemblies and 9 twice-barned optimized fuel assemblies.
Projected technical specification change proposals include a positive moderator temperature coefficient and increased nuclear enthalpy rise hot channel and heat flux hot channel factors. Other projected proposals include a revised fuel rod design methodology (PAD 3.4, described in WCAP-10851) and a revised V-5 DNB transition core cenalty (the WCAP will be submitted in May 1988).
Other proposed considerations include modification of the steam generator 10-10 level trip function (based on NRC-approved WCAP's-11325 and 11342) and elimina-tion of the negative flux rate trip function (described in WCAP-11394).
The licensee expects to submit the reload application by November 1, 1988 and is requesting NRC approval by April 22, 1989. The NRC staff made no commitment regarding the review of WCAP-10851, the V-5 DNB transiticq core penalty WCAP (which will be submitted in May), or WCAP-11394. The staff did, however, offer to provide feedback to the licensee regarding the rev!ews of the various WCAP's, hl Thomas W. Alexion, Project Manager Project Directorate III-3 Division of Reactor Projects - III, IV, V and Special Projects
Enclosures:
As stated cc: With Enclosures 1 and 2 Enclosure 3 to licensee only See next page 8904250300 000413 DR ADOCK 0500 3 Office: LA/PDIII-3 PM/P h 3 SRXB/]h SRXB I
Surname: PKPeutzer Tfle? /tg HRicMngs YHsii/f Date: 4/j;/88 /p/ y/g88 f/p/88 Office: SR PD/P ' gIi-3 Surname: R KPdr os Date: g /f 68 q/p/88
Mr. D. F. Schnell Callaway Plant Union Electric Company Unit No. 1 cc:
Dr. J. O. Cermack Mr. Bart D. Withers CFA Inc. President and Chief 4 Professional Dr., Suite 110 Executive Officer Gaithersburg, "9 20879 Wolf Creek Nuclear Operating Corporation Gerald Charhoff, Esq. P. O. Box 411 Thomas A. Baxter, Esq. Burlington, Kansas 66839 Shaw, Pittman, Potts & Trowbridge 2000 N Street, N. W. Mr. Dan I. Bolef, Presioent Washington, D. C. 20037 Kay Drey, Representative Board of Directors Coalition Mr. T. P. Sharkey for the Environment Supervisor, Compliance St. Louis Region Union Electric Company 6267 Delmar Boulevard Post Off. ice Box 620 . University City, Missouri 63130 Fulton, Missouri 65251 U S. Nuclear Regulatory Commission Resident Inspectors Office RRt1 Steedman, Missouri 65077 Mr. Alan C. Passwater, Manager Licensing 6nd Fuels l
i Union Electric Company l Post Office Box 149 St. Louis, Missouri 63166 Manager - Electric Department Missouri Public Service Commission 301 W. High Post Office Box 360 Jefferson City, Missouri 65102 1
Regional Administrator l U. S. NRC, Region III 799 Roosevelt Road Glen Ellyn, Illinois 60137 Mr. Ronald A. Kucera, Deputy Director Department of Natural Resources P. O. Box 176 Jefferson City, Missouri 65102 l
ENCLOSURE 1 CYCLE 4 RELOAD MEETING APRIL 6, 1988 NAME ORGANIZATION Tom Alexion NRC/PDIII-3 Howard Richings NRC/SRXB Y. Gene Hsif NRC/SRXB Al Passwater IJnion Electric Co.
Dave Shafer Union Electric Co.
Carole Leach Westinghouse-Nuclear Safety Al Abels Westinghouse-Nuclear Safety Barb Samardzich Westinghouse-CNFD l
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- . ENCLOSilRE 2 CALLAWAY CYCLE 4 APRIL 6, 1988 NRC MEETING AGENDA I, INTRODUCTION II, PLANT OPERATION UPDATE Ill, CYCLE 4 LICENSING OVERVIEW AND SUBMITTAL SCHEDULE A. LICENSING SUBMITTAL
SUMMARY
1 PMTC 2 FUEL ROD DESIGN
- 3. VANTAGE 5 TRANSITION CORE PENALTY
- 4. PEAKING FACTOR INCREASES B. TECHNICAL SPECIFICATION CHANGES IV, CYCLE 4 RELOAD CONSIDERATIONS A. VANTAGE 5 TRANSITION CORE PENALTY B. PEAKING FACTOR INCREASES V. OTHER CONSIDERATIONS A. SG LO-LO LEVEL TRIP SETPOINT AND LOGIC MODIFICATIONS B. NEGATIVE FLUX RATE TRIP REMOVAL VI.
SUMMARY
A. LICENSING SCHEDULE B. NRC COMMENTS t
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PLANT OPERATION UPDATE 0 CYCLE 3 CONFIGURATION VANTAGE 5 28 (3,6) 32 (3,8) 36 (4.2) 0FA 84 LOPAR 13 0 DESIGN TO 440 EFPD 0 CURRENT CYCLE PERFORMANCE (4/1/88)
GENERATED 119 EFPD 90% CAPACITY rACTOR 0 PROJECTED CYCLE END DATE CAPACITY FACTOR CYCLE END DATE 85% 4/15/89 90% 3/24/89 95% 3/17/89
SCHEDULE CONSIDERATIONS 11/1/88 -
CYCLE 4 SUBMITTAL To NRC 3/17/89 -
REFUEL 3 EARLY START DATE 4/22/89 -
CYCLE 4 REQUESTED APPROVAL DATE 5/8/89 -
CYCLE 4 EARLY RESTART DATE i
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9 CYCLE 4 CHANGES CYCLE 4 CONFIGURATION j VANTAGE-5 t 64 (3,6) (NEW) 124 (4.0) (NEW) 96 (ONCE BURNED) :
i 0FA ;
i 9 (TWICE BURNED)
P O POSITIVE MODERATOR TEMPERATURE COEFFICIENT 0 REVISED PEAKING FACTCRS (F0, F-DELTA-H) 0 INCORPORATE AXIAL BLANKETS 0 ALL IFBA CORE I
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POSITIVE MODERATOR TEMPERATURE COEFFICIENT (PMTC)
CURRENT TECH SPEC LIMIT:
0 PCM/*F MTC OR LESS AT ALL TIMES WHILE REACTOR IS CRITICAL
- PROPOSED AMENDMENT:
+$ PCM/*F MTC FROM 0 TO 70% RATED THERMAL POWER, RAMP DOWN LINEARLY TO 0 PCM/*F MTC AT 100% POWER
, PURPOSE:
FUEL CYCLE COST ADVANTAGC FUEL CYCLE DESIGN FLEX 1BILITY LICENSING SUBMITTAL PACKAGE:
FSAR CHAPTER 15 SAFETY EVALUATION (VS LICENSING SUBMITTAL) 1 RWST/ ACCUMULATOR BORON CONCENTRATION INCREASE O POST-LOCA HOT LEG SWITCHOVER TIME o POST-LOCA SUMP AND CONTAINMENT SPRAY PH CONSIDERATIONS
- TECH SPEC CHANGES CONCLUSION
CURRENT CHAPTER 15 ANALYSES REMAIN APPLICABLE MAGNITUDE / TYPE OF TECH SPEC CHANGES ARE SIMILAR TO PREVIOUSLY APPROVED LICENSING AMENDMENTS FOR OTHER H NSSSS PROPOSED AMENDMENT SUPPORTS INTENDED CYCLE 4 FUEL CYCLE DESIGN AND OPERATION
_r___ . - _ _ _ _ _ _
CYCLE 4 FUEL R0D DESIGN 0 SECOND CYCLE OF VANTAGE-5 FUEL ANALYZED AT UPRATED CONDITIONS 0 REQUIRE REVISED FUEL ROD DESIGN METHODOLOGY - PAD 3.4
! WCAP 10851:
"IMPROVED FUEL PERFORMANCE MODELS FOR WESTINGHOUSE FUEL ROD DESIGN AND SAFETY EVALVATION"
! O WCAP 108b1 NRC REVIEW IN PROGRESS l (CRGR COMMITTEE REVIEW) l J
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CYCLE 14, TRANSITION CORE PENALTY DNB o REDUCEVANTAGb-5IRANS('l10NCOREPENALTYBASEDON CYCLE 4 CORE INJENTORY l 0 fidFIRE9CE NESTINGHOUSE REPORT OC i u REMAINS 50Y (SAME As CYCLE 3) l 1
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4 PEAKING FACTOR INCREASES NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR (F-DELTA-H) 0FA VANTAGE 5 TSL SAL TSL SAL CURRENT (CYCLE 3) 1.49 1,55 1,49 1.65 PROPOSED (CYCLE 4) 1,49 1,55 1,59 1.65 TECHNICAL SPECIFICATIONS WILL USE A SINGLE VALUE OF 1.59 FOR CYCLE 4.
KEY: SAL = SAFETY ANALYSIS LIMIT TSL = TECH SPEC LIMIT
\ . . . . -
HEAT FLUX HOT CHANNEL FACTOR Fo(Z)
CURRENT: FQ AS A FUNCTION OF CORE HEIGHT - 3 SEGMENT ENVELOPE MAX Fo = 2.32 PROPOSED: FQ AS A FUNCTION OF CORE HEIGHT - 2 SEGMENT ENVELOPE MAX Fo = 2.50 TECHNICAL SPECIFICATIONS WILL USE A SINGLE VALUE OF 2.50 FOR CYCLE 4.
EXPECTED / POTENTIAL TECH SPEC CHANGES
- 1. PMTC 3/4.1 REACTIVITY CONTROL SYSTEMS 3.1.1.3 MODERATOR TEMPERATURE COEFFICIENT (MTC AS A FUNCTION OF POWER) 3.1.2.5 BORATED WATER SOURCE - SHUTDOWN (RWST BORON CONCENTRATION) 3.1.2,6 BORATED WATER SOURCE - OPERATING (RWST BORON CONCENTRATION) 3/4.5 EMERGENCY CORE COOLING SYSTEMS 3,5,1 ACCUMULATORS (ACCUMULATOR BORON CONCENTRATION) 3.5.5 REFUELING WATER STORAGE TANK i:
(RWST BORON CONCENTRATION) 3/4,6 CONTAINMENT SYSTEMS 3,6,2,2 SPRAY ADDITIVE SYSTEM (CHEMICAL ADDITION TANK NA0H SOLUTION VOL UME) .
2 (CHEMICAL ADDITION TANK NA0H SOLUTION % WElGHT)
I 3/4,9 REFUELING OPERATIONS
! 3,9,1 BORON CONCENTRATION (MODE 6 RCS MINIMUM BORON CONCENTRATION)
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. . . . _ . - , . - - , , . _ . - - - - . _ _ _ . . _ _ --._- . _._- _. - - --_ _ .._ _ - - _. --..- - ~
I EXPECTED / POTENTIAL TECH SPEC CHANGES
- 2. PEAKING FACTOR INCREASES
-3/4.2 POWER DISTRIBUTION LIMITS 3.2.2 - HEAT FLUX HOT CHANNEL FACTOR (Fo As A FUNCTION OF CORE HEIGHT) 3.2.3 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR (F-DELTA-H) 4
(
e .
i OTHER CONSIDERATIONS l
h 1 STEAM' GENERATOR LO-L0 LEVEL-TRIP FUNCTION o TRIP TIME DELAY AS A FUNCTION OF POWER LEVEL CONCEPT: NRC APPROVED WCAP-11325 0 ENVIRONMENTAL ALLOWANCE MODIFIER ,
CONCEPT: NRC APPROVED WCAP-11342 IMPLEMENTATION: MODIFICATION OF Ex! STING 7300 PROCESS i EQUIPMENT SCHEDULE: 7/1/88 LICENSING SUBMITTAL !
REFUEL 3 OUTAGE PLANT MODIFICATIONS 4
NRC APPROVAL REQUESTED - 1/1/89 l OPERABLE IN CYCLE 4 i
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NEGATIVE FLUX RATE TRIP FUNCTION O DISABLE TRIP FUNCTION CONCEPT: WCAP-11394 SUBMITTED BY H FOR NRC REvlEW 7/87 SCHEDULE: CONCURRENT WITH 11/88 LICENSING SUBMITTAL REFUEL 3 CUTAGE, PLANT MODIFICATIONS REQUEST NRC APPROVAL 3/1/89 APPLICABLE FOR CYCLE 4 OPERATION e
d
SUMMARY
e CYCLE 4 SCHEDULE SUBMITTAL 11/1/88 APPROVAL DATE 4/22/89 e CYCLE 4 ISSUES
- PMTC - USED IN V5 SUBMITTAL, SIMILAR TO PREVIOUSLY APPROVED PLANTS PEAKING FACTORS USED IN V5 LICENSING SUBMITTAL PAD 3.4-RELIES ON GENERIC APPROVAL OF WCAP 10851 DNB TRANSITION CORE PENALTY-RELIES ON APPROVAL OF NEW WESTINGHOUSE TOPICAL REPORT
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