ML20213C791
| ML20213C791 | |
| Person / Time | |
|---|---|
| Site: | Columbia |
| Issue date: | 11/07/1978 |
| From: | Kniel K Office of Nuclear Reactor Regulation |
| To: | Vassallo D, Vassalo D Office of Nuclear Reactor Regulation |
| References | |
| CON-WNP-0230, CON-WNP-230 NUDOCS 7811170126 | |
| Download: ML20213C791 (2) | |
Text
____ _ _ _ _ _ _ _
W DQcKET FilF i
NRR RDG FILE
{
NOV 7 1978 CPB RDG FILE Docket Ho. 50-397 i
MEMORANDUM FOR:
D. B. Vassallo, Assistant Director for Licht Water 3
l Reactors. DPM
~
FROM:
K. Kniel, Chief. Core Perforinance Bra,nch, DSS
SUBJECT:
FIRST ROU:10 OUESTIONS FOR WPPSS., UNIT 2 i
i Plant Name:
WPPSS-2 Docket Number:
50-397 Milestone Number:
'05-24 Licensing Stage:
OL Responsible Branch
~ LWR #4 and Project Manager:
D. Lynch Systems Safety Branch Involved: Core Performance ~ Branch
~~
Description of Review:
First Round Questions '
(
Requested Completion Date:
November B 1978 Review Status:
Complete
~
The Reactor Fuels and Reactor Physics Sections of the Core Perforuance Branch have prepared the enclosed ~first round ' questions for the WPPSS.'~
i i
Unit 2 BWR.
~~
~'
~
~
i I
Karl Kniel, Chief Core Performance Branch Division of Systems Safety
Enclosure:
i First Round Questions I
cc:
S. Hanauer R. Mattson/F. Schroeder I
R. Boyd S. Yarga I
D. Lynch R. Tedesco QIVRl l
R. Meyer D. Fieno
~
T l
D. Houston W. Brooks (T 11170/EXA 24 2
_nyyces swcrd,..osstdcP,d_. osS a g._ontcepc Daouaikqt wB4 w e.
rugs
_unta
.....m._
11/1/78 11/p78 11/z)/78 11/h_/78 11// 7/78 e....
NAC PORM $le (p.74) NRO4 0240 b us e.eovsamm.wt enemme omess ee,s eas4a4
~
FIRST ROUND QUESTIONS - WPPSS-2 l
232.
Reactor Physics Section 4
232.1 (Table 4.3-5)
Provide values of the azimuthal peaking factor and uncertainty used in this Table.
In what manner was the peaking factor determinedY 232.2 (p15.4-8)
The RBM setting of 107% given here is inconsistent with the value given in Table 15.4-2.
Please clarify.
232.3 (Table 15.4-12)
Is the average enrichment in this Table (2.33) correct or should it be 2.23 as in NE00-20944?
232.4 Comment on the manner in which the process computer program is mbdified to eccommodate the 150-inch fuel length. Has the TIF travel been increased to cover the extended fuel? Are there still 24 nodes (of slightly gredter ifngth) or has an additional nodp been included?
In what manner are the core averaged and peak heat generation rates defihed?
i t
4 1
.