ML20133P868
| ML20133P868 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 01/22/1997 |
| From: | Thomas K NRC (Affiliation Not Assigned) |
| To: | NRC (Affiliation Not Assigned) |
| References | |
| NUDOCS 9701270136 | |
| Download: ML20133P868 (29) | |
Text
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LICENSEE: Union Electric Company FACILITY:.Callaway Plant, Unit 1 SUNECT:
MEETING WITH UNION ELECTRIC COMPANY TO DISCUSS FUTURE PLANS FOR CORE RELOAD DESIGN ANALYSIS FOR THE CALLAWAY PLANT On-January 14, 1997, a meeting was held with Union Electric Company (UE) 'to discuss UE's future plans for core reload design analysis for the Callaway Plant. Attachment 1 is a list of meeting attendees. Attachment 2 is the handout material presented by UE and Westinghouse in the meeting.
Westinghouse currently prrforms the core reload analysis for the Callaway Plant.
During the meeting, UE informed the staff that beginning early 1997, UE will begin obtaining.the Westinghouse reload design and safety analysis In the area of core physics, UE plans to complete the technology technology.
transfer by 1999.
In the area of safety analysis'and thermal hydraulics, UE plans to complete the technology transfer by 2001.
UE informed the staff that they did not plan to request NRC approval to acquire the responsibility for performing core reload design and safety analysis activities for the.Callaway Plant. The staff informed UE that NRC review and approval of these activities would be required.
ORIGINAL SIGNED BY Kristine M. Thomas, Project Manager Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Reg lation Docket No. 50-483
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WASHINGTON, D.C. 20086 4 001 January 22, 1997 LICENSEE: Union Electric Company FACILITY: Callaway M u., Unit 1
SUBJECT:
MEETING WITH UNION ELECTRIC COMPANY TO DISCUSS FUTURE PLANS FOR CORE RELOAD DESIGN ANALYSIS'FOR THE CALLAWAY PLANT On January 14, 1997, a meeting was held with Union Electric Company (UE) to discuss UE's future plans for core reload design analysis for the Callaway Plant. Attachment 1 is a list of meeting attendees. Attachment 2 is the handout material presented by UE and Westinghouse in the meeting.
Westinghouse currently performs the core reload analysis for the Callaway Plant. During the meeting, UE informed the staff that beginning early 1997, UE will begin obtaining the Westinghouse reload design and safety analysis technology.
In the area of core physics, UE plans to complete the technology transfer by 1999.
In the area of safety analysis and thermal hydraulics, UE plans to complete the technology transfer by 2001.
UE informed.the staff that they did not plan to request NRC approval to acquire the responsibility for performing core reload design and safety analysis activities for the Callaway Plant. The staff informed UE that NRC review and approval of these activities would be required.
Q M Tho6tML Kristine M. Thomas, Project Manager Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Docket No. 50-483 Attachments:
1.
List of Meeting Attendees 2.
Meeting Slides cc w/atts: See next page
8 s cc w/atts:
Professional Nuclear Mr. Neil S. Carns l
Consulting, Inc.
President and Chief Executive Officer 19041 Raines Drive Wolf Creek Nuclear Operating Corporation Derwood, Maryland 20855 P.O. Box 411 Burlington, Kansas 66839 Gerald Charnoff, Esq.
Thomas A. Baxter, Esq.
Mr. Dan I. Bolef, President Shaw, Pittman, Potts & Trowbridge Kay Drey, Representative 2300 N. Street, N.W.
Board of Directors Coalition Washington, D.C.
20037 for the Environment 6267 Delmar Boulevard Mr. H. D. Bono University City, Missouri 63130 Supervising Engineer, Site Licensing Mr. Lee Fritz Union Electric Company Presiding Comissioner j
Post Office Box 620 Callaway County Court House Fulton, Missouri 65251 10 East Fifth Street Fulton, Missouri 65151 U.S. Nuclear Regulatory Comission Resident Inspector Office Mr. Alan C. Passwater, Manager 8201 NRC Road Licensing and Fuels Steedman, Missouri 65077-1302 Union Electric Company Post Office Box 149 Mr. G. L. Randolph, Vice President St. Louis, Missouri 63166 Nuclear Operations Union Electric Company Mr. J. V. Laux, Manager P.O. Box 620 Quality Assurance Fulton, Missouri 65251 Union Electric Company Post Office Box 620 Manager - Electric Department Fulton, Missouri 65251 Missouri Public Service Comission i
301 W. High Mr. Donald F. Schnell Post Office Box 360 Senior Vice President - Nuclear i
Jefferson City, Missouri 65102 Union Electric Company Post Office Box 149 Regional Administrator, Region IV St. Louis, Missouri 63166 U.S. Nuclear Regulatory Comission Harris Tower & Pavilion 611 Ryan Plaza Drive, Suite 400 Arlington, Texas 76011-8064 Mr. Ronald A. Kucera, Deputy Director Department of Natural Resources P.O. Box 176 Jefferson City, Missouri 65102 i
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ATTENDEES AT MEETING ON JANUARY 14. 1997_
bel,0AD DESIGN ANALYSIS FOR THE CALLAWAY PLANT. UNIT 1 UNION ELECTRIC D. Shafer K. Hock R. Irwin N. Slaten T. Michalek M. Walz S. Lo NBC K. Thomas J. Lyons F. Orr i
L. Kopp.
WESTINGHOUSE B. Johansen J. Sechrist l
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RELOAD DESIGN ANAT YSIS i
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l UNION ELECTRIC COMPA:SY Meeting with NRC January 14,1997 i
.I AGEXDA
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a Introduction Dave Shafer i
a UE Background / Schedule Goals Randy Invin L
m Core Physics Experience / Future Plans / Benchmarking Keith Hock a
Safety Analysis Experience / Future Plans / Benchmarking Mark Walz a
Training / Quality Assurance Prog,.u/ Design Interface Neal Slaten h
a Westinghouse Technology Licensing Status Jim Sechrist l
l L
m Summary Neal Slaten s
Open Discussion All l
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l-l O
d CALLAWAY NUCLEAR PLANT w
i m Westinghouse 4-Loop PWR 4
- Located near Fulton, MO
- Commercial Operation: 12/19/84
- Uprated to 3565 MWth i
a Long Term Westinghouse Fuel Fabrication Contract 1
- Reload Design Currently Performed by Westinghouse i
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l m 18 Month Fuel Cycle 1
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ww wmg_m.-spammm. mm m. ma _www.wmm w- - - - -.umur.* e%namuuk s. mJo.ww.a p. Md a-Wh & AM ems.h6WMM quhM4 heh. h e.4 h _3 <MW"
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6 LICENSING & FUELS ORGANIZATION mai i
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RELOAD DESIGN TECHNOLOGY f
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1 u UE obtaining Westinghouse Reload Design and Safety Analysis Technology 1
Nuclear Design Codes-PHOENIX-P/ANC l
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l Thermal Hydraulic Codes-VIPRE-W l
Non-LOCA Safety Analysis Codes-RETRAN-02/ TWINKLE /FACTRAN l
l Design Procedures-Physics, Safety Analysis and Thermal Hydraulics 1
s Technology transfer scheduled to begin 1st Qtr '97 i
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RELOAD DESIGN TECHNOLOGY il a STRENGTHS OF UE/W TECHNOLOGY PARTNERSHIP
- SAME CODES AND METHODS USED BY FUEL VENDOR
- ONGOING VENDOR TECHNOLOGY SUPPORT n Code maintenance n Training Error reporting i
l n
User group meetings
- WESTINGHOUSE HAS ESTABLISHED SIMILAR PARTNERSHIPS WITH OVER 30 UTILITIES About 1/3 have licensed use of W core design technology i
n Five U.S. utilities are licensed to use W core design technology n
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SCHEDULE GOALS 1
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a TECHNOLOGY TRANSFER (1ST QTR '97)
CORE PHYSICS SCHEDULE Training (1997)
Benchmarking (4/1997 - 9/1997) l l
Parallel design with Westinghouse for Cycle 10 (startup 5/1998)
UE design for Cycle 11 (startup 11/1999) i
SCHEDULE GOAT S (CONT'D)
_ REDI i
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l SAFETY ANALYSIS AND THERMAL i
l HYDRAULIC SCHEDULE 1
Training (1997) l Benchmarking (1/1998 - 9/1998)
UE design for Cycle 12 (startup 5/2001) i l
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CORE PHYSICS EXPERIENCE i
EEE m 10+ years experience with CASMO/ SIMULATE m Wide Range of Design Features
- LOPAR, OFA, V5, V+ fuel types
- Pyrex, WABA, IFBA absorber types
- Axial blankets (natural and enriched, solid and annular pellets) l i
- Enrichments from 2.1 to 4.6 w/o U-235
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m 8 Cycles of Benchmark Data (currently in Cycle 9) j
- Power Distributions (172 flux maps)
- Boron letdown curves
- Startup physics testing data
- ECC data (14 mid-cycle startups)
- Plant transients m
CORE PHYSICS CAPABILITIES t
' E EHI a Enrichment Setting a Loading Pattern Design i
a NRC Approved Rod Swap Methodology m Startup and Operations Package I
a SIMULATOR Input Data a Core Follow m Plant Support
- Axial OfTset Anomaly Modeling Methodology
- ECC predictions
- Power maneuver predictions i
a NRC Approved Spent Fuel Pool Criticality Analysis
i
-i CORE PHYSICS FUTURE PLANS Elli r
a Enrichment Setting a Loading Pattern Design m Input to Safety Analysis and T/H Analysis
- FAC Analysis (RAOC) and RSAC j
u Complete Startup Physics Testing Predictions l
m Nuclear Design Report
- Verification of Shutdown Margin (Modes 1-5) m Peaking Factor Surveillance j
- W(z) factors for F Surveillance q
m
CORE PHYSICS FL TURE PLANS Ell
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m SIMULATOR Data a Core Operating Limits Report (COLR) m Core Follow m Plant Support
- Axial Offset Anomaly (AOA) modeling methodology
- ECC predictions
- Power maneuver predictions i
a Online Monitor (BEACON) Input Data I
CORE PHYSICS BENCHMARKING 11 l
m Callaway cycles 6,7 and 8 will be modeled with the Westinghouse t
methods and the results compared to plant data.
a Previous Westinghouse calculations for these cycles will be compared i
to the Union Electric results.
1 m
Westinghouse prescribed acceptance criteria will be used to evaluate the results of the Union Electric calculations.
a Westinghouse will review Union Electric calculations to insure proper model setup and usage.
m Comparison calculations will be documented and available for NRC audit l
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l PAST CALLAWAY CYCLES 1,
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Feed Assemblies Bumup Bumable Absoiber Axial Blankets Axial Offset (MWD /MTU)
An maly j
88 assemblies 20932 IFBA (1.5 x)
Natural U (0.74 w/o)
YES gYg g 120 in. (centered)
Solid 44 @ 4.0 w/o 7168 total All feed assemblies i
44 @ 4.4 w/o l
i 96 assemblies 20656 IFBA (1.0x & l.5x)
Enriched U (2.6 w/o)
NO I
gYg 7 126 in. (ofTset +3 in)
Solid 60 @ 3.8 w/o 132 in. (centered)
All but 4 feed assemblies 36 @ 4.2 w/o 8080 total i
1 96 assemblies 21769 IFBA (2.0 x)
Enriched U (2.6 w/o)
YES
{Yg g 120 in. (centered)
A nnular 36 @ 4.0 w/o 126 in. (ofTset +3 in)
All feed assemblies 60 @ 4.4 w/o 6272 total I
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CORE PHYSICS BENCHMARKING i.
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B[l m HZP CRITERIA
- Critical Boron Concentrations i
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- Isothermal Temperature CoefTicients
- Control Rod Worths
- Differential Boron Worths j
i u HFP CRITERIA
- Boron Letdown Curves i
- Power Peaking Factors
- Radial and Axial Power Distributions
- Axial Offsets l
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SAFETY ANALYSIS EXPERIENCE l
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RETRAN CODE APPLIED FOR LICENSING AND PLANT l
SUPPORT ANALYSES l
a Licensed to perform Steam Generator Tube Rupture (SGTR) Analysis m Analysis of Turbine Trip Event to Support Relaxation of l
Lift Setting Tolerance of Main Steam Safety Valves a Analysis of Main Steamline Break Event to Support the Main Steam and Feed Isolation Syste;n (MSFIS) Evaluation
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4 SAFETY ANALYSIS FUTURE PLANS i
Ell i
PERFORM FSAR CHAPTER 15 NO~N-LOCA SAFETY ANALYSES WITH NRC APPROVED CODES AND METHODOLOGY (W) l u
Utilize RETRAN-02 for System Transient Analysis u
Utilize VIPRE-W for Sub-Channel Analysis l
m Utilize FACTRAN/ TWINKLE for analysis of fast reactivity l
events (RWFS/ Rod Ejection) j m
OTDT/OPDT Setpoint Methodology
1 1
SAFETY ANALYSIS FUTURE PLANS
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PERFORM FSAR CHAPTER 15 NON-LOCA SAFETY ANALYSES WITH NRC APPROVED CODES AND METHODOLOGY (W) s Westinghouse will continue to supply LOCA analyses i
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Westinghouse will continue to provide fuel assembly mechanical design and fuel performance suppert l
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l SAFETY ANALYSIS BENCHMARKING l
El PERFORM COMPARISON CALCULATIONS TO DEMONSTRATE COMPETENCY u
Operating data from previous plant transients will be used for computer model qualification u
Selected RETRAN/VIPRE-W analysis results will be compared to those obtained from other NRC approved codes a
Comparison calculations will be documented and available for NRC audit
TRAISIN G l
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a We are in the process of establishing a training program to i
ensure each user:
l
- Is competent in the setup and use of the applicable codes and i
methods i
- Can interpret and understand the output results
- Is cognizant of the limitations associated with the codes and methods a Documentation of each user's qualifications and training records will be available for NRC audit i
4 e
i QA PROGRAM E!!
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e A program is in place to validate computer codes from j
outside vendors t
a This program msures that each code is verified on the Union Electric platform before it is used i
a Provisions will be established to insure Union Electric informs Westinghouse of any errors i
DESIGN ENTERFACE AGREEMENT 1
i a PURPOSE 1
i Define and communicate interfaces between Westinghouse and Union Electric I
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m CONTENTS l
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List of reload design interface activities t
Schedules Detailed descriptions of transmittals, including example transmittals j
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DESIGN fSTERFACE AGREEME:ST (CONT'D) 53
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u Activities could include the following
- Selection of reload engineering services (UE to W)
- Tentative and final scheduled fuel delivery date (UE to W)
- Final fuel loading, enrichments, BA requirements and configuration (UE to W)
- Fuel rod design input data (UE to W)
Large break LOCA input assumptions (W to UE)
- Confirmation oflarge break LOCA input assumptions (UE to W)
Projected allowable burnups for fuel rod ( W to UE)
- Reload safety evaluation input (W to UE)
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l WESTINGHOUSE TECHNOLOGY LICENSING STATUS l
l Ell l
u CORE DESIGN PHOENIX-P/ANC based methodology Approved by NRC 6/88 i
a SAFETY ANALYSIS TWINKLE based methodology Approved by NRC 7/74 FACTRAN based methodology Approved by NRC 9/86 OTDT/OPDT setpoint methodology Approved by NRC 4/86 RETRAN based methodology Submit to NRC 3/97 l
VIPRE-W based methodology Submit to NRC 3/97 l
u UTILITY APPLICATIONS 1
HL&P Replacement Steam Generator Submit to NRC 2 QTR '98 i
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SCMMARY h
a Union Electric's reload design applications will be based on NRC-approved codes and Westinghouse reload design methodology.
m Union Electric will establish and implement procedures for reload design applications, ensuring that the use of approved methods is consistent with the code qualification and j
approved application of the methodology.
i n
Union Electric will institute a program for which Westinghouse will provide training in l
reload design applications to Union Electric personnel.
a Union Electric will demonstrate competency by perfonning comparison calculations (i.e., benchmarking against vendor results and/or plant operating data).
m All safety-related licensing calculations performed by Union Electric will be conducted l
under the control of a QA program which complies with the requirements of Appendix B to 10CFR50.
m Union Electric will inform the NRC prior to acquiring responsibility in any of the previously mentioned areas i.
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