ML20214G914
| ML20214G914 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 04/25/1978 |
| From: | Check P Office of Nuclear Reactor Regulation |
| To: | Vassallo D Office of Nuclear Reactor Regulation |
| References | |
| CON-WNP-0213, CON-WNP-213 NUDOCS 8605230035 | |
| Download: ML20214G914 (2) | |
Text
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N FILES NRR RDG FILE B RDG FILE APR 2 51978 l
MEMORANDUM FOR:
D.B.
Vassallo, Assistant Director for Light Water Reactors, DPM FROM:
P.S. Check, Chief, Core Performance Branch, DSS
SUBJECT:
ACCEPTANCE REVIEW FOR WPPSS, UNIT 2 Plant Names Washington Public Power Supply System. Unit 2 Docket Nos:
0-397 Milestone Number:
O-4 Licensing Stage:
'OL
~~
Responsible Branch
' LWR # 4 "
and Project Macager:
'M.D.
Lynch"~ '
Systems Safety Branch
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Description of Review:
' ~~~ ' tore Perf'o'rma' ace Banach Involved:
~ Acc'eptance Reviev
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Requested Completion Date:] 'Apr11,]19.,1978',',,
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The Reactor Fuels and Reactor Physics Sections of the Core Perf ormance Branch have reviewe'd ' sections 4.2,' 4.'3,' T5.4.1,
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15.4.2, 14.4.7, and 15.4.9'.
We" find 'these~secitons to be acce p t able f or do cke ting a.n. d.h. a. v..'e. e.nc1.'o s'.ad..qu_e s t' ions for the
~
h Paul S.
Check, Chief d' ore Performanco Branch ~'
i d.ivision of Systems Safety
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I Enclosure
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{
As stated
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cc:
S. Hanauer R. Mattson/F. Schroeder
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S.
Varga M.D. Lynch
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D.
Ross W. Mcdonald Jt. Meyer D.
Fieno
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T ~ ~ ~ W' C D.
Eouston W. Brooks
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CORE PERFORMANCE BRANCl!
ACCEPTANCE REVIEW' QUESTIONS WPPSS-2 Reactor Fuels Section
.231.1 Section 4.2 of the WPPSS-2 FSAR references (4.2)
NED0-20944 as the sole input for fuel design.
In our review of this GE topical, one further report was generated, "BWR/4 and BWR/S Fuel Design. Amendment 1,"
NEDE-20944-1P, January, 1977.
This report should be applicable to WPPSS 2 and should be referenced.
231.2 Recently NRC has questioned the validity of (4.2) fission gas release calculations in most fuel performance codes including GEGAP-III for a burnup greater than 20,000 mwd /tU.
General Electric was informed on this concern on November 23, 1976 and was provided with a method of correcting gas release calculations for burnups greater than 20,000 mwd /tU.
Since there was no q,uestion of the adequacy of GEGAP-III for burnups below 20,000 mwd /tU, the WPPSS-2 calculations are acceptable for operation early in life until the peak local burnup reaches 20,000 mwd /tU.
For burnups in excess of that value, GEGAP-III calculations (and other affected analyses) must be redone using the correction method mentioned above or such modified methods that might be submitted by Washington Public Power or General Electric and approved by the NRC.
Reactor Physics Section 132.1 General Electric has performed a generic analysis
-(15.4.1) of the consequences of continuous withdrawal of an out-of-sequence control rod during reactor startup.
This analysis has been documented on the fla tch-2 docke t (50-366).
Please provide a reference or repeat the analysis on the WPPS-2 docket.