ML19322C165
| ML19322C165 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 09/24/1975 |
| From: | Purple R Office of Nuclear Reactor Regulation |
| To: | Parker W DUKE POWER CO. |
| Shared Package | |
| ML19322C163 | List: |
| References | |
| NUDOCS 8001090574 | |
| Download: ML19322C165 (2) | |
Text
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UN11[D ST ATFS
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JCLEAft flEGULATOfiY COf.t'.ilSSION W AsHlf4C T oti. D.
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SEP 2 41575 9
ocket Nos. 50-270/287 D
Duke Power Company KITN: Mr. William O. Parker, Jr.
Vice President Steam Production' g rP @
p rq Post Office Box 2178 6
J1J 422 South Church Street Charlotte, North Carolina 28242 Gentlemen:
In earlier correspondence dated October 22 and November 26, 1974, between you and Mr. Norman C. Moseley of our Office of Inspection and Enforcement, you discussed the condition of primary coolant-
~
flow rates in Oconce Units 2 f, 3 which were in excess of the system design flow rates.
In his letter of April 17,1975, Mr. Mosc1cy
-indicated that a review of Babcock and Wilcox's safety evaluation of this item would be conducted before action could be considered complete.
The Division of. Reactor. Licensing is presently condbeting the review of the high coolant flow rate condition and of the associated potential
-for vertical displacement of fuel assemblies.
We have concluded based on the inforuation availabic, that an unsafe condition does not exist.
llowever, to provide confirmatory evidence that fuel element motion is not occurring, it is requested that you conduct an examination and evaluation of the follo.<ing items during the next scheduled refueling of Oconce Unit 2 and submit a report sumarizing the results:
1.
Fuel asset.bly position prior to removal - conduct a random check of those assemblics being removed and note any abnormalitics.
4 2.
Tuc1 rod fretting at spacer locations - examine two of the assemblics being removed.
3.
Wear on the fuel assembly lower end fitting - exanine two of the asscublics being reme.ed.
It is aiso requested that you submit th'c results of.your post-irradiated analysis of the B-4 type holddown springs as well as the predicted margin to core lift with the newer type B-5 and B-6 holddown springs being installed as replacements during refueling periods, Finally, we are reouesting that.any abnormal condition noted with the loose parts monitoring systems for either Unit 2 or 3 be reported.
4 8 0010 908 7p'
1 i
Duke-Power Company
~2 -
SEP. 2 4 $7C-liased on the data you provide, a final determination will be made
, rugarding the need for any subsequent fuel assembly inspections in Units 2 G 3.
Please. indicate within 15 days of receipt of this letter your intentions to comply with the.above requests.
Sincercly, bC yL C-(
Robert A. Purple, Chief Operatinn Reactors Branch #1 Division of Reactor Licensing cc:
Mr. William L. Porter Duke Power Company P. O. Box 2178 422 South Church Strcot Charlotte, North Carolina 28201 Mr. Troy 11 Conner-Conner, lladlock 6 1:notts 1747 Pennsylvania Avenue, NN.
Washington, D.C.
20006 Oconce County Library 201 South Spring Street 9**
'Q' Walhalla, South Carolina 29691 4
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