ML19317D942
| ML19317D942 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 12/18/1975 |
| From: | Parker W DUKE POWER CO. |
| To: | Purple R, Rusche B Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7912100625 | |
| Download: ML19317D942 (3) | |
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NRC C.. iRIBUTION FOR PART_SO DOCKE[1ATERI AL (TEMPOR ARY FORM)
FILE: INCIDE!7r REronT rn FROM: Duke Power Co.
DATE OF DOC DATE REC'D LTR TWX RPT OTHER Charlotte, N.C.
12-18-75 12-22-75 XXX ORlG CC OTHER SENT AEC PDR W1114nm O. Pnrkor TO:
SENT LOCAL PDR vyx Benard C. Rusche 1 Sign'ed CLASS UNCLASS PROPINFO INPUT NO CYS REC'D DOCKET NO:
0-26 270/287 1
XXX ENCLOSURES:
DESCRIPTION:
their Itr. 5-23-75 and our ltr. of 9 Ltr. re 75.... Furnishing additional info regarding Un-ACKNOWLEDGED
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usual Event # 270/75-7 regarding ineasured re-actor coolant flow.....
DO NOT REMOVE PLANT NAME:
Dennno 1;7_1 w.n n _3 n _ v e.
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Mr. Benard C. Rusche N
Director of Nuclear Reactor Regulation 0
U U. S. Nuclear Regulatory Commission
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Washington, D. C.
20555 6 %. g'g-8. /gjS ji k *,;J,p %,u,1 Attention:
Mr. R. A. Purple G/
k' Re: Oconee Nuclear Station
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gg s Docket Nos. 50-269, -270, -287
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Dear Sir:
In a May '23, 1975 letter to Mr. Norman C. Moseley, NRC Office of Inspection and Enforcement Region II, a report of primary reactor coolant flow in excess of design value was reported as Unusual Event UE-270/75-7.
It was stated that the value of prinury reactor coolant flow at which fuel assembly lif t could be expected to occur was 112.1 percent of design flow.
This value did not include information which had been obtained from the Post-Irradiation Examination of Oconee Unit 1, Cycle 1 fuel. The measured reactor coolant flow for Oconee Unit 2 has been determined to be 111.5 percent of design flow.
Mr. R. A. Purple's letter dated September 24, 1975 requested that additional information be provided concerning the predicted margin to core lift.
It was requested that the results of the post-irridated analysis of Oconce Unit 1, Cycle 1 fuel be included in the predicted margin calculations. The requested I
information, which also supplements Unusual Event Report UE-270/75-7, is provided in the following discussion.
8 The maximum allowable system flow rate with respect to lift is dependent l
upon a number of parameters. These are holddown spring characteristics, fuel assembly characteristics, fuel assembly weight, whole core mix of different fuel assembly types, power level and core leakage flow. Therefore, i
i the lift limit is not a simple function of holddown spring type, but must be I
calculated for each specific situation, taking into account all of these factors.
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l 14113 i
t Mr. Benard C. Rusche December 18, 1975 Page 2 4
Current calculations, which include feedback from Oconec Unit I holddown spring measurcments made at the end of Cycle 1, indicate that fuel assembly lift will not occur below the following limits:
Maximum Allowable System Flow Rate (% of 352,000 GPM) i Cycle Unit 1 Unit 2_
Unit 3 112 115 1
2 112 113 116 3
112 13 116 j
4 116 120 120 5
120 120 120 As can be seen from the above data, the present margin to core lift is satisfactory, and this margin will be considerably increased as older fuel designs are replaced by the newer designs.
In addition, the examinations q
I requested of Oconee Unit 2 fuel assemblies to provide confirmatory evidence that fuel assembly motion is not occurring will be performed at the next scheduled refueling.
Very truly yours, W Jis' r
vv William O. Parker, Jr. #A N MST:mmb CC }:r. Norman C. Moseley l
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