ML19312C837
| ML19312C837 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 01/26/1977 |
| From: | Long F NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| Shared Package | |
| ML19312C835 | List: |
| References | |
| NUDOCS 8001100753 | |
| Download: ML19312C837 (1) | |
Text
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UNITE D ST ATES 8,
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NUCLEAR REGULATORY COMMIS..;N 2.$($
.p REGION il 230 PEACHTREE STRE ET, N.W. SUITE 815
- . [I ATLANTA, GEORGIA 30303 e...*
January 26, 1977 4
ME40RANDUM TO:
K. V. Seyfrit, Cnief, Reactor Technical Assistance Branch, Office of Inspection and Enforcement, Headquarters
[ON. C. Moseley, Director, Office of Inspection and THRU; Enforcement, Region II FROM:
F. J. Long, Chief, Reactor Operations and Nuclear Support Branch, Region II
SUBJECT:
OCONEE POWER DOPPLER COEFFICIEIT l
The attached memo from P. T. Burnett identifies the issue of whether I
a plant should be permitted to operate with a more r gative value of the power Doppler coefficient than that used in the analysis of the steam line break accident. His memo also identifies some I
differences in the Westinghouse and B&W power coefficients. We a
g recommend this matter be reviewed to assure an unreviewed safety
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question does not exist.
I w
1
(
'3 F. J. Long, Chief
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Reactor Operations and Nuclear Support Branch
Attachment:
As stated I-cc:
H. C. Dance P. T. Burnett CONTACT:
P. T. BURNETT 2k2-6323 N'
l 8001100---
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