ML20058M596
| ML20058M596 | |
| Person / Time | |
|---|---|
| Issue date: | 09/20/1993 |
| From: | Alexion T Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| GL-93-04, GL-93-4, NUDOCS 9310060246 | |
| Download: ML20058M596 (5) | |
Text
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NUCLEAR REGULATORY COMMISSION
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September 20 1993 i
WESTINGHOUSE OWNERS GROUP-
SUBJECT:
SUMMARY
OF MEETING ON AUGUST 26, 1993 WITH WESTINGHOUSE REGARDING i
WCAP-13803 (PROPRIETARY), " GENERIC ASSESSMENT OF ASYMMETRIC ROD
-l CLUSTER CONTROL ASSEMBLY WITHDRAWAL" On_ August 26, 1993, representatives from Westinghouse met with the NRC st'aff to present WCAP-13803, which was submitted.in response to Generic Letter'(GL)'
l 93-04, " Rod Control System Failure and Withdrawal of Rod Control Cluster:
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- Assemblies, 10 CFR 50.54(f)." This also provided the NRC with,an opportunity l
to-ask questions in order to better understand the WCAP.. Meeting attendees-'
j are listed the enclosure.
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The meeting began with an overall outline of the methodology in terms -of a _
flow chart. The sample departure from nucleate boiling ratio (DNBR)
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tabulation for a specific asymmetric rod-cluster-control-assembly (RCCA)
-withdrawal statepoint (i.e., conditions associated with the limiting time in the transient) was reviewed step by step.
Plant-specific application.of the methodology was briefly discussed.
After this introductory part, the report was dis. cussed section by section.
First the approach to the accident analysis was discussed..This included the LOFT 5 analysis (a _three-dimensional spatial kinetics / systems transient code)~,
initial conditions and assumptions, cases analyzed, and results and DNBR evaluation.
The next'part dealt with the neutronic considerations including the methodology, sensitivity, and applicability. Thermal-hydraulic-considerations were the next topic. These included DNBR methodology and limits, analysis of base cases, and DNBR sensitivity.
The remainder of the meeting was spent on plant-specific application. This discussion centered on the application of this methodology to plants with' Westinghouse-reload designs, non-Westinghouse-reload designs, and DNBR -
analysis of asymmetric' RCCA withdrawal for non-Westinghouse fuel. _. Plant-specific DNBR values were calculated by Westinghouse for each plant using the information supplied by each utility. These calculations assumed use of the.
WRB-1 heat flux correlation and that another vendor's fuel-would -behave as Westinghouso fuel.
It was-pointed out by the NRC that additional justification would be.needed.
for various steps of the process, if'the results.of a WCAP-13803-type analysis form the basis for licensees' long-term resolution of GLl93-04.
The-NRC staffk gy [.4(OttJ Q k bkgb[
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I 1 thanked Westinghouse for their time and effort in helping the staff attain a-better understanding of the WCAP.
ORIGINAL SIGNED BY:
Thomas W. Alexion, Project Manager Project Directorate IV-1 Division of Reactor Projects - III,IV,V Office of Nuclear Reactor Regulation
Enclosure:
List of attendees
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....... thanked Westinghouse for their time and effort in helping the staff attain a better understanding of the WCAP.
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./ W Thomas W. Alexion, Project Manager Project Directorate IV-1 Division of Reactor Projects - III,IV,V Office of Nuclear Reactor Regulation
Enclosure:
List of attendees
ENCLOSURE HEETING WITH WESTINGHOUSE REGARDING WCAP-13803
[BME ORGANIZATION PHONE Tom Alexion NRC/NRR 301-504-1326 Margaret Chatterton NRC/NRR 301-504-2889 Eric Benner NRC/NRR 301-504-1171 Christine Vertes Westinghouse 412-374-4481 Baard Johansen Westinghouse 412-374-2184 Daniel Risher Westinghouse 412-374-5774 David Huegel Westinghouse 412-374-5424 Rick Kohrt Wisconsin Electric 414-221-3964
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0 DISTRIBUTION - Meetina Summary
.i Docket file NRC & Local PDRs PD4-1 Reading T. Murley/F. Miraglia
- J. Partlow J. Roe E. Adensam W. Beckner T. Alexion P. Noonan OGC E. Jordan NRC Participants ACRS (10)
V. McCree, ED0 L. Plisco, ED0 G. Grant, EDO J. Mitchell, ED0 R. Cooper, RI E. Merschoff, RII E. Greenman, RIII A. B. Beach, RIV K. Perkins, RV t
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