ML20245C306
| ML20245C306 | |
| Person / Time | |
|---|---|
| Issue date: | 01/14/1977 |
| From: | Rusche B Office of Nuclear Reactor Regulation |
| To: | Pollard R AFFILIATION NOT ASSIGNED |
| References | |
| TAC-8593, NUDOCS 8710220133 | |
| Download: ML20245C306 (2) | |
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UNITED STATES i
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January 14, 1977 0-Mr. Robert D. Pollard 12C3 llassachusetts Avenue Ca-bridge, Massachusetts 02138
Dear Mr. Pollard:
This is in response to your letter of January 3, 1977, which we are treating as a Request for Action pursuant to 10 CFR 2.206 with regard to all nuclear power reactors having an operating license.
Your request is under consideration, and within a reasonable time we will inform you of our final decisich on this r_atter.
A copy of the Notice that is being filed with the Office of the FEDERAL REGISTER is enclosed for your information.
Among other things, your letter recommended that the NRC review each operating nuclear power plant with respect to the consequences of fuel handling accidents inside containment and, until such reviews are ecm-pleted, issue orders to prohibit refueling operation at these facilities.
This postulated accident is similar to a fuel handling accident in the spent fuel storage building.
Such an accident in the spent fuel storage building has been analyzed for all operating reactors (See Regulatory Guide 1.25), and generally similar equipment and procedures would be used to mitigate the consequences of a similar accident inside con-tainment.
In fact, for all boiling water reactors licensed to operate since August 1967, the analyses of the two accidents would be identical and the equipment used to mitigate its potential consequences would be the same.
Since receipt of your letter we have completed a preliminary assessment f.j) of a fuel handling accident inside containment for all nuclear power pip' reactors licensed for operation.
This assessment shows that, for all sixty-three nuclear power reactors presently licensed to operate, qon.
servatively calculated potential exposures from this postulated accident are7Elow the 10 CFR Par't 100 gufdeline values when certain(lin~owD oi a
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- chara0teristics of the containment isolation _or_ effluent filtration ~~
gh systems of'these faciliti W srT 6 E n into account". 'Ba dd o fthe re'-
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sults of this assessment, and because a fuel handling accident resulting
.p in the large releases assumed in this assessment is not of high proba-
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bility, we have concluded that no prohibition on fuel handling opera-tions for any nuclear power plant licensed to operate is necessary or appropriate at this time.
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1 JU.' 14 $77 Mr. Roberts. Follard 2-In order to confirn the results of our preliminary assesscent, we intend to obtain additional infor. nation fro: affected licensees en which t_o__bM L and do p t our fir.a1 course of action, appropriate to the potential hazard, for each facility.
This action may involve additional technical specification require =ents or the relocation or addition of radiation monitors for optimizing their performance during fuel handling operations.
Tour request for an investigation under Section 206 of the Energy Re-organization Act is also under consideration.
j Sincerely, C
Ben C. Busche, Director '7 Office of Nuclear Reactor Regulation
Enclosure:
Copy of liotice DISTRIBUTION:
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T.Rehm T.J. Carter l
B.Rusche B. Grimes E. Case Attorney, OELD R.Minogue M.Groff (01318)
E.Volgenau G. Ertter (01318)
H.Shapar E. Tamburello J. Miller Secy. Mail Facility (77-0018)
R.Boyd 3 copies H.Denton NRC PDR R.Heineman V.Stello OR*
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