|
---|
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
~~
F ,
ft 'q UNITED STATES 7"'
( f ,,n NUCLEAR REGULATORY COMMISSION d 3 $ WASHING TON, D. C. 20S55 t, . .E October 14, 1987
- 0 L . Docket ho. 50-483 l C
li u n 2. a0 MATERIAL Decontrohd )
when separated from enclosures.
LICENSEE: Union Electric FACILITY: _ Callaway Plant
SUBJECT:
SUMMARY
OF MEETING WITH UNION ELECTRIC REGARDING THE TRANSITION CORE DNBR PENALTY FOR CYCLE 3 On October 6, 1987, the licensee and representatives from Westinghouse met with the staff to discuss the transition core departure from nucleate boiling ratio (DNBR) penalty for Cycle 3 operation at Callaway. Partici-pants at the meeting are listed in Enclosure 1. The licensee's letter documenting their findings is provided in Enclosure 2. Nonproprietary slides used during the meeting are in Enclosure 3. The proprietary slides used during the meeting are being withheld from public disclosure under 10 CFR 2.790 of the Connissions regulations.
The licensee stated that as a result of a generic assessment which affects the magnitude of the Vantage 5 DNBR transition core penalty, an evaluation was performed for Callaway Cycle 3 which indicated the need for a small (1.5 percent) increase to the DNBR transition core penalty. However, the licensee stated that the small increase continues to be offset by the margin which is maintained between the design and safety limit DNBR's, and that the safety evaluation and significant hazards evaluation conclusions provided in the original reload submittal (dated March 31,1987) remain valid.
The staff indicated that this new information will be included in the review of the reload application. The staff did not identify any outstanding issues at the meeting.
G g ;< ?>
~
Mhfal& v< lI Thomas W. Alexion, Proje t Manager Project Directorate 111-3 Division of Reactor Projects
Enclosures:
- 1. Participants DESIGNA ED ORlGINAL: .. /
- 2. Licensee's letter \
- 3. Non proprietary slides CMilied By- / ~~--- '
(proprietary slides withheld - 2.790) cc: See next page Enclosure (s) contain(s)
.10 CFR 2.E^ MATERIAL Decontrc!!ed 1 EA 2288M 8U>8! dea when separated from enclosures.
P PDR
y, .
e i
i 4 ll , ;
o '
. .]
l
'.I Mr. D. F. Schnell- Callaway Plant Union Electric Company Unit No. 1 l
l - cc: .
! Dr. J. O. Cermack- Mr. Bart D. Withers CFA Inc. President and Chief =
4 Professional Dr., Suite 110 Executive Officer I
' Gaithersburg, MD 20879 Wolf Creek ' Nuclear Operating .l
. Corporation' .)
Gerald Charnoff, Esq. P. O. Box 411 ;
Thomas A. Baxter, Esq.
Shaw, Pittman, Potts & Trowbridge Burlington, Kansas 66839 l
2300 N Street, N. W. 'Mr. Dan I. Bolef, President 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 1 Post Office Box 620 University City, Missouri 63130 ,
Fulton, Missouri 65251 l U. S. Nuclear Regulatory Commission Resident Inspectors Office RR#1 Steedman, Missouri 65077 i
Mr. Alan C. Passwater, Manager !
Licensing and Fuels
-Union Electric Company Post Office Box 149 St. Louis, Missouri 63166 Manager - Electric Department Missouri Public Service Comission 301 W. High Post Office Box 360 Jefferson City, Missouri 65102 Regional Administrator 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 l Jefferson City, Missouri 65102 l l
_.___m _ _ . _ _ . . _ .
. _ . _ -. - J
. u.
Enclosure 1 TRANSITION CORE DNBR PENALTY MEETING )
OCTOBER 6, 1987 l- -
ATTENDANCE LIST l
NAME ORGANIZATION-T. Alexion NRC/PD III-3 ;
! M. Hodges- NRC/SRXB l L. Phillips NRC/SP.XB W. Brooks NRC/SRXB F Orr NRC/PDI-4 A. Passwater UE/ Licensing & Fuels W..Bobnar UE/ Licensing & Fuels K. Connelly UE/ Licensing & Fuels P. Loftus W/ Nuclear Safety ..
4, K. Mc Atee W/ Thermal-Hydraulic Design 1 E. Novendstern W/ Thermal-Hydraulic Design !
l i
i l
i
{ .
Enclosure 2 t901 Grealot Street St. Lode ConsM f. Schnell Woe Prseident October 6, 1987 U.s. Nuclear Regulatory Commission ATTN Document Control Desk Washington, D.C. 20555 Gentlemen: ULNRC-1643 DOCKET NUMBER 50-483 CALLAWAY PLANT REVISED VANTAGE 5 TRANSITION CORE EFFECTS FOR CYCLE 3
References:
- 1) ULNRC 1470 dated March 31, 1987
- 2) Westinghouse Letter NS-NRC-87-3268 dated October 2, 1987 from W. J. Johnson to M. W. Bodges Reference 1 transmitted the Reload License Amendment Application for callaway Plant using Westinghouse 17 x 17 VANTAGE 5 fuel assemblies. As part of the application, Union Electric referenced NCAP-10444-P-A, " Westinghouse Reference Core Report, VANTAGE 5 Fuel Assembly" as the-approved methodology for assessing the transition to VANTAGE 5 fuel.
Westinghouse has recently completed an assessment which affects the magnitude of the VANTAGE $ DNB transition core ;
penalty. The results of this generic assessment were provided to (
- NRC via Reference 2. An evaluation has been performed for Callaway Cycle 3 which demonstrates the safety evaluation ;
conclusions presented in Reference 1 remain valid, but in'dicates )
the n'eed for a small (1.5 percent) correction to the magnitude of the DNB transition core penalty. The small increase in the q magnitude of the DNB transition core penalty continues to be i offset by the margin which is maintained between the design and safety 1 hit DNBRs made available due to the improved DNB performance of the IFM grids described in WCAP-10444 The VANTAGE 5 DNB transition core penalty increases from 11 percent to 12.5 percent and the DNB margin decreases from 5.5 percent to 4 percent. The revised transition core penalty and revised DNB l margin are provided in the enclosed replacement pages to Reference 1.
' Y Meane A6ttene: Fo. non 149, st. Loun, MO s3166 N N *N ,
EG:0T 48/90/0T
2 '-
The results of the Significant Hazards Evaluation transmitted by Reference 1 remain unchanged. If there are any questions with respect to this subject, please contact us.
Very truly yours, Donald F. Schnell DS/kea Attachments: ULNRC-1470, dated March 31, 1987, Replacement Pages
- 1) Attachment 1, Safety Evaluation, Paga 17 Attachment 2, Technlcal Specification Changes, 2)
Bases page B3/4.2-4
- 3) Attachment 3, References, page 40 I
1 t
l
}
(. ,
\
STATE OF MI5800RI')
. )- as CITY OF ST. LOUIS )
Donald F. Schnell, of lawful age, being first duly sworn upon oath says that he is Vice President-Nuclear and an officer of Union Electric Company; that he has read the foregoing document and
'knows the content thereof; that he has executed the same for and on 1 I
behalf of said company with full power and authority to do so; and
'that the facts therein stated are true and correct to the best of his knowledge, information and belief.
Sy d J Donald F. 5thnell ,
Vice President .
Nuclear
' SUBSCRIBED and sworn to before me this b day of ![MV , 198 '/.
=
hJ's>A. l BAR8 ARA (PFM 8 i N0fARY PUBUC. STATI Of Miss00m m couwssion wints APAn 22. taas
- 87. Loull COUNTY.
f 4
- _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ - _ . _ A Oh w opg fj Q M sg
9 cc Gerald Charnoff, Esq. .
f, haw, Pittman, Potts & Trowbridge M300 N. Street, N.W.
Washington, D.C.' 20037 Dr. J. O. Cermak CFA, Inc. i 4 Professional Drive (suite 110)
Gaithersburg, MD 20879 W. L. Porney Chief, Reactor Project Branch 1 .
U.S. Nuclear Regulatory Commission Region III 799 Roosevelt Road i Clen Ellyn, Illinois 60137 Bruce Little 2 Callaway Resident office U.S. Nuclear Regulatory Commission i
RR$1 {
steedman, Missouri 65077 Tom Alexion (2)
Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop 316 j 7920 morfolk Avenue Bethesda, MD 20014 .
Ron Rucera, Deputy Director Department of Natural Resources P.O. Box 176 1 Jefferson City, MO 65102 Manager, Electric Department
. Missouri Public Service Commission ,
P.O. Box 360' Jefferson City, MO 65102 l
t
'l i
- il i
n a q
1 I
_-____-__m we m ce m mR@AM
i 1
ATTACHMENT 1 l
follows. A fraction of the margin is utilized to accomodate the transition-
- core DNBR penalty (2% for OFA fuel and 12.5% for VANTAGE 5 fuel) and the appropriate fuel rod bow DNBR penalty, Reference 11, which is less than 1.5%.
The existing 7% margin in the DFA fuel and 18% margin in the VANTAGE 5 fuel between the design and safety analysis DNBR limits also includes a greater ;
than 3% DNBR margin in the DFA fuel and 4% DNBR margin in the VANTAGE 5 fuel reserved for flexibility in the design. The VANTAGE 5 transition
- core penalty is discussed in Refe'rences 27 and 28. .
The LOPAR, and 0FA, and VANTAGE 5 designs have been shown to be hydraulically compatible in Reference 1. ,
The phenomenon of fuel rod bowir.g; e, described in Reference 11, must be accounted for in the DNBR safety analysis of Condition I and Condition II i events for each plant application. Applicable generic credits for margin 1 resulting from retained conservative in the evaluation of DNBR and/or margin j obtained from measured plant operating parameters (such as F,"H or core j flow) which are more restrictive than those required by the plant safety analysis, can be used to offset the effect of rod bow. The safety analysis for the Callaway Plant maintains sufficient margin between the safety analysis limit DNBRs and the design limit DNBRs to accomodate full-flow and low-flow DNBR penalties.
The transition core DNB methodology given in References 2 and 17 has been approved by the NRC via Reference IB. Using this methodology, transition cores are analyzed as if they were full' cores of one assembly type (full 0FA or full VANTAGE 5), applyin,g the applicable transition core penalties of two percent for OFA fuel and eleven percent for VANTAGE 5 fuel. The safety analyses for the Callaway Plant maintains sufficient margin between the safety analysis limit DNBRs and the design limit DNBRs to accomodate the transition core DNBR penalty and the appropriate rod bow DNBR penalty.
The fuel temperatures for use in safety analysis calculations for the VANTAGE 5 fuel are the same as those used for the OFA fuel. Westinghouse uses the PAD fuel performance code, Reference 6, to perform both design and licensing calculations. When the code is used to calculate fuel temperatures to be used as initial conditions in safety analyses, a conservative thermal safety model, Reference 7, is used, wA
. . . ULNRC-1643
. Attachment 2 RA$ts __
_ '""*"*"" b - - -
3/4.2,2 and 314.2.3 NEAT FLUX NOT CHANNEL FACTOR AND MUC1. TAR ENTHALPY R!$t --
ngT ="5_ h am (Goritinued) , , , g Each of tigese is measurable but will normally onl ically as spe:19ted in Specifications 4.2.2 and 4.2.3. y This be detemined period-periodic surveil.
Iance is suffic$pnt to ensure that the limits are ma,intained provided:
- a. Cent 1 tods in a single group move together with no individual ref sortion differiac by more than +"' 12 steps. indicated, from
.the p demand posit <on.
I lh b. Can 1 red banks are sequenced with overlapping groups as described j
- F in ification 3.1.3.5. -
- c. The entrol rod insertion limits of Specification 3.1.3.8 are anta$$ned.. -.
- d. The miel power distribution, expressed in terms of AX1AL FLUX
.- D @-, is maintained within the limits.
dwiT) maintained within its 1 its provided conditions a. through d.
eb6ve aM antn ned. The relaxath of as a function of THUMAL POWER allows'sheness , the radial power shape
. all pesissible rod insertion limits.
Whe6 an FE measurement is taken, an allemence for both experimental errer ene yngrecturil s tolerence must'be ande. An allowance of 55 is appropriate for a ful .coes anp taken with the incers detector flux mapping system and a 35 allemnce is . appropriate for annufacturing tolertnee.
I '
When isseasured.(i.e.. inferred).noadditionalallowancesare necessary pr r to comparison with the limits of Section 3.2.3. An error allow-ance of 45- has toen included in the limits of Section 3.2.3. 3E
/2.5 % -~
Margin be n the safety lysis DN5a limits Optimited fuel table and 1 sells respectively(1.42 , and 1.81 and andT.'45 1.69 for for -the cal cells),and the design DNBA limits (1.32 and t w ttWITAtt I able and 1.84 for the mised fuel table and typical cells and 1.32 and 1.33 for the VANTAtt 8 thi and typt 1 sells, respectively) is maintained. A traction j of this enrotn is util >' acsammodata the transition core DNBR penalty 25 for Opt'aised fue "
or VAKTAGE 8 fuel) and th appropriate fuel rod l b(ow DN8R penalty (lessW.. l.55 per WCAp 0691. Rev.1. The margin between -
. . des.1 and safety. analysis M8R limits of 75 for Optia med fuel and 181 for VANT fuel includes greater than 35 margin for Optimized fuel and p::t:5
//% rgin for VANTA415 fuel for plant design flexibility. { l The het channel factor )ismeasuredperiodicallyandincreasedby a cycle and heitht dependent r factor appropriate to either ennal Operation or RESTRICT!B AFD OPERATION.
lief t en the het channel facter,s).k(or is W(t)E. to provide assurance tiat thew (z
-8!)/ c gy,y CALLANAY - ! 1 3/4t-i Amenenent No. H.
ATTACHMENT 3 l 22. Lee, N., Rupprecht, S. D., Schwartz, W. R., Tauche, W. D., " Westinghouse Small Break ECCS Evaluation Nodel Using the NOTRUMP Code," WCAP-10054-P-A (Proprietary) and WCAP-10081-A (Non-Proprietary) August 1985.
- 23. Esposito, V. J., Kesavan, K., and Maul, 8. J.; "W-FLASH-A Fortran-IV Computer Program for Simulation of Transients in a Multi-Loop PWR,"
WCAP-8200 (Proprietary), July 1973.
- 24. Meyer, P. E., "NOTRUMP, A Nodal Transient Small Break and General Network
- Code," WCAP-10079-P-A (Proprietary) and WCAP-10080-A (Non-Proprietary),
August 1985. ,
- 25. Letter C. E. Rossi (NRC) to E. P. Rahe, Jr. (W), " Acceptance for Referencing of Licensing Topical Report WCAP-10266," November 1986.
- 26. Letter W. Johnson 3) to J. Lyons (NRC), " Submittal of WCAP-10266 l
' Addendura 1, BASH Power Shape Sensitivity Studies," January 1987.
- 27. Letter from W. J. Johnson (Westinghouse) to M. W. Hodges (NRC) dated October 2, 1987, NS-NRC-87-3268,
Subject:
" VANTAGE 5 I
Transition Core Effects".
- 28. ULNRC - 1643 dated October 6, 1987, " Revised Vantage 5 Transition Core Effects for Cycle 3". :
e D
, F . . . ,m ,. -
Enclosure 3 1
CALLAWAY CYCLE 3 LICENSING MEETING NRC/ UNION ELECTRIC / WESTINGHOUSE OCTOBER 6, 1987 I. INTRODUCTION -
UNION ELECTRIC o BACKGROUND AND PURPOSE OF THE MEETING I
- 11. CALLAWAY LICENSING ACTIVITIES STATUS AND SCHEDULE OVERVIEW -
UNION ELECTRIC III. VANTAGE 5 DNB TRANSITION CORE EFFECTS o BACKGROUND (INCLUDING GENERAL INFORMATION/
LICENSING STATUS) -
WESTINGHOUSE o THERMAL 8 HYDRAULIC CONSIDERATIONS -
WESTINGHOUSE o LICENSING CONSIDERATIONS -
WESTINGHOUSE IV. CALLAWAY CYCLE 3 LICENSING APPROACH /
ISSUE RESOLUTION -
UNION ELECTRIC V.
DISCUSSION / WRAP-UP
{
)
C0sC _US O N EFFECT OF SMALL INCREASE IN THE VANTAGE 5 TRANSm0N CORE PENALTY DOES NOT ALTER ANY CONCLUSIONS REPORTED IN'BOTH THE CALLAWAY UCENSING SUBMITTAL NiD WCAP-10444.
i
-