ML19317E670
| ML19317E670 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 08/29/1975 |
| From: | Purple R Office of Nuclear Reactor Regulation |
| To: | Parker W DUKE POWER CO. |
| Shared Package | |
| ML19317E672 | List: |
| References | |
| NUDOCS 7912180836 | |
| Download: ML19317E670 (3) | |
Text
.
Docket Nos.
50-270 andi 50-287 Duke Power Company ATl?i: Mr. William O. Parker, Jr.
Vice President Steam Production P. O. Box 2178 422 South Church Street Charlotte, North Carolina 28242 Gentlemen:
f By letter dated July 22, 1974, we requested that you furnish, as an j
amendment to the PSAR, additional infonnation on the Oconee Nuclear Station design and operating procedures related to spent fuel handling.
You responded to this request by submitting Revision 35 to the PSAR, dated Septenber 30, 1974.
We have found that this revision does not contain sufficient analysis, including calculations, to support your conclusionson spent fuel cask handling system acceptability.
Specifically, in reference to the necessary consideration No. 1 in our
}
July 22, 1974 letter, you have not addressed the possibility of the deflection of a spent fuel cask onto spent fuol stored in the pool and its resultant radiological consequences. Additionally, you should pro-vide your analysis, including supportive calculations, of the effects on the spent fuel pool liner should tho fuel cask strike it during the above postulated accident.
Finally, a dotalled description of the spent fuel cask path of movement should be provided, detailing the elevations and direction of travel.
You should also provide calcula-tions to support any conclusion regarding the radiological consequences in the event the cask should accidentally fall from the highest point I
in its path of travel.
't i
Should.your evaluation of these postulated accidents indicate the need for pinnt modifications, you are requested to proceed with the necessary actions, pursuant to 10 CFR Part 50, Saction 50.59.
i i
As an alternative to the above requirements, you may elect to demonstrate I
I that the overhead crane used for spent fuel cask handling meets the single failure proof criteria set forth in Branch Technical Position FCSB 9-1, " Overhead !!andling Systems for Nuclear Power Plants", a copy of which is enclosed for your guidance.
l 4
u,e
,., y k A n~ m.
~NN W 3 91 z 180 M~M***%"
Duke Power Company 4(IG 2 91975 In order to continue our review of your analyses and evaluation of the Oconee spent fuel handling system, you are requested to respond to this request for additional information within 60 days of receipt of this letter.
Sincerely, 4ce n
Robert A. Purple, Chief Operating Reactors Branch #1 Division of Reactor Licensing i
Enclosure:
Branch Technical Position APCSB 9-1 i
cc w/ enclosure:
See next page DISTRIBUTION Docket Files (3)
NRC PDRs(3)
Local PDR ORB #1 Reading KRGoller TJCarter j
RAPurple GGZech SMSheppard DEisenhut SVarga' ACRS(16)
OISE(3)
OELD TBAbernathy, TIC JRBuchanan 1
I I
i RL:0RB#1 RL:0RB#1 TR:ASB
..GGZ.ech:dc_
, RAPurple.
SuRNa 8/29/75 8/24/75 8/ff75 7
l Persa ABC 318 (Rev. 9-53) ABW 0240 W u. s. e=3vsRNMENT PRIN91NS OPPICEs t074 538 984
Duke Power Company 3-A,ugust 29, 1975 cc: -Mr. William L. Porter Duke Power Company P. O. Box 2178 422 South Church Street Charlotte, North Carolina 28242 5
Mr. Troy B. Conner Connor, lladlock &.Knotts 1747 Pennsylvania Avenue, IN Washington, D. C.
20006 Oconce Public Library 201 South Spring Street Walhalla, South Carolina 29691 I
O e
G D
1 I
j.
Q-i 1
'l