ML17291B214
| ML17291B214 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 01/30/1996 |
| From: | Steven Bloom NRC (Affiliation Not Assigned) |
| To: | NRC (Affiliation Not Assigned) |
| References | |
| NUDOCS 9602050101 | |
| Download: ML17291B214 (48) | |
Text
P January 30, 1996 LICENSEE:
Washington Public Power Supply System FACILITY:
WPPSS Nuclear Project No.
2
SUBJECT:
SUMMARY
OF MEETING HELD ON OCTOBER 26,
- 1995, WITH ABB/CE AND WNP-2 TO DISCUSS CENPD 300 The NRC staff met with ABB/Combustion Engineering and WNP-2 on October 26, 1995, to discuss CENPD 300, which presents ABB/CE's methodology for analyzing the mixed fuel that will be in the WNP-2 core.
Attendees are listed in Attachment l.
ABB/CE summarized the CENPD 300 methodology and its use in the upcoming refueling outage at WNP-2.
ABB/CE's presentation slides are in Attachment 2.
Some of the slides contain ABB/CE proprietary information and are withheld from public disclosure pursuant to 10 CFR 2.790.
Original signed by:
Steven D. Bloom, Project Manager Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Docket No. 50-397 Attachments:
1.
List of Attendees 2.
Slides cc w/atts:
See next page DISTRIBUTION (w/atts 1 and 2):
Docket File PUBLIC PDIV-2 Reading JClifford
- KPerkins, WCFO DISTRIBUTION (w/att 1):
WRussell/FHiraglia RZimmerman JRoe EAdensam WBateman EPeyton OGC EJordan ACRS JHitchell SBloom DOCUMENT NAME:
DC1026.HTS OFC PDIV-2 LA PDI -2 PM NAME Efeey Yn DATE 12 lg 95 S
oom:
k 12 @/95 OFFICIAL RECORD COPY 9602050i0i.960i30 PDR ADQCKE..050003'P7 P
PDR I
january 30, 1996 LICENSEE:
Washington Public Power Supply System FACILITY:
WPPSS Nuclear Project No.
2
SUBJECT:
SUMMARY
OF MEETING HELD ON OCTOBER 26,
- 1995, WITH ABB/CE AND WNP-2 TO DISCUSS CENPD 300 The NRC staff met with ABB/Combustion Engineering and WNP-2 on October 26, 1995, to discuss CENPD 300, which presents ABB/CE's methodology for analyzing the mixed fuel that will be in the WNP-2 core.
Attendees are listed in Attachment l.
ABB/CE summarized the CENPD 300 methodology and its use in the upcoming refueling outage at MNP-2.
ABB/CE's presentation slides are in Attachment 2.
Some of the slides contain ABB/CE proprietary information and are withheld from public disclosure pursuant to 10 CFR 2.790.
Original signed by:
Steven D. Bloom, Project Manager Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Docket No. 50-397 Attachments:
1.
List of Attendees 2.
Slides cc w/atts:
See next page DISTRIBUTION (w/atts 1 and 2):
Docket File PUBLIC PDIV-2 Reading JClifford
- KPerkins, WCFO DISTRIBUTION (w/att 1):
QRussell/FMiraglia RZimmerman JRoe.
EAdensam QBateman EPeyton OGC EJordan ACRS JHitchell SBloom DOCUMENT NAME:
oom:
k 12/P /95 PDIV-2 LA OFC MANE EPeeyn DATE 12/Ig /95 OFFICIAL RECORD COPY
~S REgg Cy E
O I
e Cy 0
gO
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055&0001 January 30, 1996 LICENSEE:
Washington Public Power Supply System FACILITY:
WPPSS Nuclear Project No.
2
SUBJECT:
SUMMARY
OF MEETING HELD ON OCTOBER 26,
- 1995, WITH ABB/CE AND WNP-2 TO DISCUSS CENPD 300 The NRC staff met with ABB/Combustion Engineering and WNP-2 on October 26, 1995, to discuss CENPD 300, which presents ABB/CE's methodology for analyzing the mixed fuel that will be in the WNP-2 core.
Attendees are listed in Attachment 1.
ABB/CE summarized the CENPD 300 methodology and its use in the upcoming refueling outage at WNP-2.
ABB/CE's presentation slides are in Attachment 2.
Some of the slides contain ABB/CE proprietary information and are withheld from public disclosure pursuant to 10 CFR 2.790.
Docket No. 50-397 Attachments:
1.
List of Attendees 2.
Slides cc w/atts:
See next page 5,
S ven D. Bloom, Project Manager Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Washington Public Power Supply System Nuclear Project No.
2 cc w/atts:
Mr. J.
H. Swailes WNP-2 Plant General Manager Washington Public Power Supply System P.O.
Box 968
- Richland, Washington 99352-0968 Chief Counsel (Mail Drop 396)
Washington Public Power Supply System 3000 George Washington Way
- Richland, Washington 99352-0968 Mr. Frederick S. Adair, Chairman Energy Facility Site Evaluation Council P.O.
Box 43172 Olympia, Washington 98504-3172 Mr. D. A. Swank (Mail Drop PE20)
WNP-2 Licensing Manager Washington Public Power Supply System P.O.
Box 968
- Richland, Washington 99352-0968 Mr. Paul R. Bemis (Mail Drop PE20)
Director, Regulatory and Industry Affairs Washington Public Power Supply System P.O.
Box 968
- Richland, Washington 99352 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission Harris Tower 5 Pavilion 611 Ryan Plaza Drive, Suite 400 Arlington, Texas 76011-8064 Chairman Benton County Board of Commissioners P.O.
Box 69
- Prosser, Washington 99350-0190 Mr. R.
C. Barr, Senior Resident Inspector U.S. Nuclear Regulatory Commission P.O.
Box 69
- Richland, Washington 99352-0968 M. H. Philips, Jr.,
Esq.
Winston 8 Strawn 1400 L Street, N.W.
Washington, DC 20005-3502 Mr. J.
V. Parrish (Mail Drop 1023)
Vice President Nuclear Operations 3000 George Washington Way Washington Public Power Supply System P.O.
Box 968 Richland, Washington 99352-0968
Attachment 1
ATTENDEES MEETING WITH WASHINGTON PUBLIC POWER SUPPLY SYSTEM CENPD 300 October 26, 1995 NRC S.
Bloom E. Meiss M. Chatterton E. Kendrick T. Huang L. Phillips R. Jones S. Matthews Washin ton Public Power Su 1
S stem M. C. Wockenhauer D. Swank
~ABB CE D. Ebeling-Koning B. Harris
Attachment 2
Attachment B
BWR RELOAD LICENSING TECHNICAL MEETING
~
Thermal Margins in Transition Cores
~
Summary Status Since October 5th Meeting Bill Harris and Derek Ebeling-Koning October 26, 1995 Non-Proprietary Version ABB Combustion Engineering Nuclear Operations Combustion Engineering, Inc. Proprietary N Ihlk PRIII'IN
t, t
I f
i'
MCPR OPERATING LIMIT PROCESS Plant Process Computer Monttors Assembly NCPRs Using Fuel-Specff)c Correlations To Nafntatn Nargtn to OLMCPRs OLEIC P R ABB Fuel OLMCPR Non-ABB Fuel STEP 3 hCP R ABB Fuel hCPR Non-ABB Fuel STEP 2 SLNCPR ABB Fuel SLNCPR Non-ABB Fuel STEP 1
ABB Combustion Engineering Nuclear Operations ki ITIN WWIStr
RELOAD CYCLE OLMCPR PROCESS Steps in Reload Cycle Design and Licensing Analysis
- 1. Establish SLMCPR
- 2. Determine Fuel Type Specific ACPRs
- 3. Establish OLMCPR for Each Fuel Type in the Core Margins to OLMCPR are Monitored by Plant Core Supervision System
~
Uses NRC-approved CPR correlations ABB Combustion Engineering Nuclear Operations iL I1Ik
/%ININ
RELOAD CYCLE OLMCPR PROCESS Process Outlined in CENPD-300-P
~
Chapter 5, 6, and 7
~
Example in Appendix D Today, Summarize
- process, and illustrate treatment of transition core including non-ABB Fuel
~
ABB Combustion Engineering Nuclear Operations Ah ITIN P%IIIN'
14 f
1 t
STEP 1 - SLMCPR SLMCPR Established for ABB Fuel Assuming All Locations Occupied by ABB Fuel
~
Methodology presented in CENPD-300-P, Section 5.3.2 and response to Question F11.
SLMCPR for Non-ABB Fuel Based on Previous Cycle Results ABB Combustion Engineering Nuclear Operations 4 NIk P%1PIN
STEP 2 - ACPR Limiting Transient 4CPR Established for Each Fuel Type NRC-approved Licensing Analysis used to determine ACPRs
~
Analysis of ABBfuel based on NRC-approved CPR Correlation r
e Analysis of non-ABB fuel based ABB Combustion Engineering Nuclear Operations 4L 158 P%INiIN
l
STEP 3 - OLitliCPR OLMCPR = SLMCPR + h,CPR Core Minimum CPR Operating Margin Uncertainty in Calculated hCPR Operating LimitMCPR Calculated hCPR SLMCPR CPR = $.0 ABB Combustion Engineering Nuclear Operations 4L IRIk P'LINIS
CPR TREATMENT FOR TRANSITION CORES NEED CPR PERFORMANCE OF NON-ABB FUEL TYPES
~
[
TREAT ACPR PERFORMANCE OF NON-ABB FUEL CONSERVATIVELY ABB Combustion Engineering Nuclear Operations kl %SIN 8'LIIPIN
I
0 CPR TREATMENT EOR TRANSITION CORES FIRST CYCLE FUEL ASSEMBLIES Typical First Cycle Fuel MCPR Trend MCPR CPR Margin Typical First Cycle Fuel OLMCPR Umiting Slow Transient Delta CPR with Uncertainty First Cycle Fuel SLMCPR Limiting Fast Transient Delta CPR with Uncertainty MOC EOC Cycle Exposure ABB Combustion Engineering Nuclear Operations ALIIIk
/%IIII
CPR TREATMENT FOR TRANSITION CORES SECOND CYCLE FUEL ASSEMBLIES Typical Second Cycle Fuel MCPR Trend CPR Margin NCPR Typical Second Cycle Fuel OLMCPR Second Cycle Fuel SLMCPR BOG MOC EOC Cycle Exposure ABB Combvsten Engineering Nuclear Operations N II'l 8'KININ
I P
f
CPR TREATMENT IN ANALYSIS FOR NON-ABB FUEL ABB Combustion Engineering Nuciear Operations fk %ilk P%51IN
7 I
IV
TYPICAL CORRELATION MATRIX FOR NON-ABB FUEL CPR PERFORMANCE ABB Combustion Engineering Nuclear Operations liRblk P%RNIN
I I
CONSERVATIVE hCPR PERFORMANCE FOR NON-ABB FUEL INSURE CALCULATED hCPR PERFORMANCE IS TREATED CONSERVATIVELY (A) I Or (8)
[
CONSERVATISM INCLUDED IN RESULTANT d CPR ABB Combustion Engineering Nuclear Operations AL lhlN P'LI9lN
I 1
hCPR PERFORMANCE FOR NON-ABB FUEL METHOD A Actual CPR/Predicted CPR
~
~
4
~
~
~
0 App l i cab I e Mat r i x" Cases ABB Combustion Engineering Nuclear Operations 4L IkN P'LIPID
ACPR PERFORMANCE FOR NON-ABB FUEL METMOD A Assumes Maximum Effect of Uncertainty during Transient ABB Combustion Engineering Nuclear Operations Combustion Engineering, Inc. Proprietary illlIk P%INIIN
ACPR PERFORMANCE FOR NON-ABB FUEL METHOD A ABB Combustion Engineering Nuciear Operations iLOII P'LIIISl
EXAMPLE APPLICATION PROCESS FOR TRANSITION CORE Illustrate:
~ Determining CPR Performance fer Non-ABB Fuel
~
[
ABB Combustion Engineering Nuclear Operations ALIIIk P%IIIIN
EXAMPLE APPLICATION CPR MATRIX SINGLE PARAMETER VARIATION TO CAPTURE SENSITIVITIES ABB Combustion Engineering Nuclear Operations iLlklk P%IIII
EXAMPLE APPLICATION ABB Combustion Engineering Nuclear Operations ik 51lk P'LINIS
l
EXAMPLE APPLICATION ABB Combustion Engineering Nuclear Operations ih. INlk i"LINIS
EXAMPLE APPLlCATION ABB Combustion Engineering Nuclear Operations iA Ikwk P'lISII
e
EXAMPLE APPLICATION ABB Combustion Engineering Nuclear Operations kiAll 8'LINIS
EXAMPLE APPLICATION ABB Combustion Engineering Nuclear Operations fL RNRN P%lNIN
'I 4
II
SUMMARY
~
Discussed ABB Process for Addressing Thermal Margins in Transition Cores
~ ABB Approach Consistent with Industry Standard
~ Following Industry Standard:
~
Avoids Severe Fuel Cycle Cost Penalties
~
Maintains Safety Margins ABB Combustion Engineering Nuclear Operations IL I%IN
/%I@IN
LTR UNDER REVIEW STATUS RPA 89-053&112, CENPD-284-P ABBSubmit Reyort NRC Issue RAI ASBEh.sponse to RAI ABBSubmit HAIrevision AHRAIResponses Resolved Contractor Issue TER NRC Issue SER Control Rod DroyAccident Analysis Methodology January 80, 1990 4 October 1, 1993 May 19, 1994 8~ August 5, 1994 October 4, 1994 May 9, July 25, September 28, 1995 October 5, 1995 Estimate October 30, 1995 Estimate November 30, 1995 STATUS - CONTRACTOR AND NRC DRAFTING TER AND SER ABB Combustion Engineering Nuclear Operations lLIIIl P%IQRS
LTR UNDER REVIEW STATUS CENPD-285-P ABBSubmitRqport NRC Issue RAI ABBResponse to RAI ABBSubmit RAlrevision ABBFuel Rod Design Methods forBWR Fuel June 8, 1994 February 7, 1995 June 9, July 13, 1995 Seytember 21, 1995, October 13, 1995 AllRAIResponses Resolved Estimate October 31, 1995 Contractor Issue TER NRC Issue SEE Estimate November 13, 1995 Estimate December 11, 1995 CENPD-287-P ABBSakaait Repmt NRC Issue RAX ABBHesyonse toRAI ABBSubmit RAXrevision AllRAXResponses Resolved Contractor Issue TER NRC Issue SEE ABBMechanical Design Methodology for BWR Fuel June 17, 1994 May 9, 1995 August 8, Seytember 8, 1995 October 13, 1995 Estimate October 31, 1995 Estimate November 13, 1995 Estimate December 11, 1995 STATUS - ABB Submitted Revised Respones ABB Combustion Engineering Nuclear Operations il Iklk P%IIIRN
LTR UNDER REVIEW STATUS CENPD-288-P ABBSubmit Repave NRC Issue RAI ABBResponse toEAI ABBSubmit HAIrevision AllRAIResponses Resolved Contractor Issue 'TER NRC Issue SER ABBSeismic)LOCA Evaluation Methodology forBWRFuel May 2V, 1994 June 20, 1995 July 1V, 1995 October 16, 1995 Estimate October 27, 1995 Estimate October 27, 1995 Estimate November 22, 1995 STATUS - ABB Submitted Revised Respones and Audit Information CENPD-292-P ABBSubmit Repaet NRC Issue RAI ABBResponse toRAI ABBSubmit HAXxevision Supplement to Transient Armlysis Methods:
Description and Quali6cation August 2, 1994 March 23, 1995 May 1V, 1995 August 25, 1995 AHHAIReqmnsesResolved August 25, 1995 Contractor Issue TER NRC Issue SER September 30, 1995 October 16, 1995 STATUS - SER Received ABB Combustion Engineering Nuclear Operations AL Iklk
/%I@IN
LTR UNDER REVIEW STATUS CENPD 288 P ABBSubmit Report NRC Issue RAI ABBResponse to HAI ABBSubmit RAYrevision AllRAIResponses Resolved contractor Issue TER NRC Issue SER pp for SV&M-96 March 80, 1993 March 20, revised March 28, 1995 July 7, 1995 August 25, 1995 August 9, 1995 September 14, 1995 Estimate October 30, 1995 Su lement to LOCASensitivities Studi STATUS - NRC Issuing SER CZNPD-800-P ABBSubmit Report NRC Issue RAI ABBResponse to RAI ABBSubmit RAIrevision AHRAIResponses Resolved Centractor Issue TER NRC Issue SER Reference Safety Report for8%RReload Fuel December 8, 1994 May 16, 1995 August 6, 1995, August 28, 1995 September 12, 1995 September 12, 1995 September 80, 1995 Estimate December 11, 1995 STATUS - Today, Discussed Transition Core Treatment.
ABB Combustion Engineering Nuclear Operations ZL ann P%kNINN
C:s t
LTR UNDER REVIEW STATUS CENPD-294-P ABBSubmit Report NRC Issue RAI ABBResponse to RAI AllRAIResponses Resolved Contractor Issue TER NRC Issue SER CENPD-295-P ABB&AmitReport NRC Issue RAI ABBResponse to RAI ABBResponse withRev. 1 AllRAIResponses Resolved Contractor Issue TER NRC Issue SER ABBAdvanced StabilityMethods June 19, 1995 Estimate October 31, 1995 Estimate November 10, 1995 Estimate December 1, 1995 ABBAdvanced StabiTity Methodology September 12, 1995 Estimate October 30, 1995 Estimate November 17, 1995-Estimate November 17, 1995 Estimate December 1, 1995 STATUS - ABB Proposing Revisions to CENPD-295-P per Oct. 5th Meeting.
ABB Combustion Engineering Nuciear Operations iL IN%0 P%5NIN
0 P
Cj
/ I