ML15223A756
| ML15223A756 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 08/31/1981 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Parker W DUKE POWER CO. |
| References | |
| NUDOCS 8109170010 | |
| Download: ML15223A756 (3) | |
Text
AUGUST 3 1 1981
~DIRTRTTAN BKSun Fil-e LPhillips L PDR TERA NSIC Dockets Nos. 50-269, 50-270 ORB#4 Rdg and 50-287 DEisenhut cI OELD f
IE-3 ACRS-10 Mr. William 0. Parker, Jr.
AEOD Vice President --Steam Production JStolz ILI Duke Power Company PWagner 9
P. 0. Box 33189 RIngram 422 South Church Street Gray File Charlotte, Nort4 Carolina 28242 EBlackwood
Dear Mr. Parker:
The NRC staff is continuing the review of your May 29, 3981 application related to Cycle 7 operation of Oconee Unit 1. As discussed with representatives of your staff, additional information is needed for us to complete our review of the rod bow penalty. Therefore, we request that you respond to the question attached to this letter within 30 days of its receipt.
Should further information be required, we will contact you in future correspondance. If you have any questions on this subject, 91 ase contact your NRC Project Manager.
Sincerely, A 0R I GIT AL S IGNED'BY B
J t
o i~ -zChief Operating Reactors Branch #4 Division of Licensing
Enclosure:
Request for Additional Information cc w/enclosure:
See next page 8109170010 810631 PDR ADOCK 05000269 P
- PDAB, OFFICE
..... O.#..
C..4..I I
PWaanek JS SURNAMEr DATE)
NRC FORM 318 (10-80) NRCM 0240 OFFICIAL RECORD COPY USGPO: 1981-335-se
Duke Power Company cc w/enclosure(s):
Mr. William L. Porter Duke Power Company P. 0. Box 33189 422 South Church Street Office of Intergovernmental Relations Charlotte, North Carolina 28242 116 West Jones Street Raleigh, North Carolina 27603 Oconee County Library 501 West Southbroad Street Walhalla, South Carolina 29691 Honorable James M. Phinney County Supervisor of Oconee County Walhalla, South Carolina 29621 Regional Radiation Representative EPA Region IV 345 Courtland Street, N.E.
Atlanta, Georgia 30308 Mr. Francis Jape U.S. Nuclear Regulatory Commission Route 2, Box 610 Seneca, South Carolina 29678 Mr. Robert B. Borsum Babcock & Wilcox Nuclear Power Generation Division Suite 420, 7735 Old Georgetown Road Bethesda, Maryland 20014 Manager, LIS NUS Corporation 2536 Countryside Boulevard Clearwater, Florida 33515 J. Michael McGarry, III, Esq.
DeBevoise & Liberman 1200 17th Street,, N.W.
Washington, 0. C. 20036
to ltr. dtd. 8/31/81 QUESTION ON OCONEE 1, CYCLE 7 RELOAD 492.1 The DNBR rod bow penalty for the Cycle 7 core was calculated based on the design parameters of Batch 9 only, which contains the limiting (maximum radial peaking factor) 1 assembly. The assumed burnup was the maximum value (17,649 F-) for any assembly in that batch. You are requested to rovide a justifi cation that the calculated rod bow penalty for a Batch 9 assembly is the worst case. Consider the DNBR values with the rod bow penalty for the most limiting assembly for each batch in the Cycle 7 core in conjunction with maximum burnup in the respective batch. Your justification should indicate the results of DNBR calculations which indicate batch number, maximum burnup and rod bow penalty, radial peaking factor and estimated DNBR, and DNBR less rod bow penalty.
Change the proposed Technical Specifications to reflect any change in rod bow penalty as a result of these calculations.