ML20148F709
| ML20148F709 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 01/14/1977 |
| From: | Schwencer A Office of Nuclear Reactor Regulation |
| To: | Groce R YANKEE ATOMIC ELECTRIC CO. |
| Shared Package | |
| ML20148F710 | List: |
| References | |
| NUDOCS 8011060702 | |
| Download: ML20148F709 (3) | |
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L JAN 141977 l
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t Yankee Atomic Electric Company
~ ATTH: Mr. -Robert. )f. Groce r' B;.
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Enclosedtl'or your jnformation:.fs a copy of'a letter dated Janua y 3, f 41977 from Robert'DrPollard,.which'is being' considered.as a. Request for
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'. JAction pursua.nt.Lto 10 CFR 2.206.. regarding yo.ur License No DPR-3~and.
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i A copy off the Notice we are filing;with,the office of'the. Federal As
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f :The letter from MrrPollard among other things,9 states: Nat a refseling. '
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i accident inside the; containment building may not-have beenfadequately I
considered during the licensing review'of your' facility.. As you are
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' aware,'worecen.tly contacted members offyour staff to obtain -information '
. for~ an: independent' assessment off such a postu1~ated accident at your b-l
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J " facility. - Based on our pre.11minarmreview, potential: site' boundary l,
- radiation exposures due lto" sbch.an: accident at'your~ facility:would be "
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s relatively loi(and we11+1 thin-10$FR Part;100? guidelines:.even' assuming a
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iprelin.tnary review we;expechthatAsidtfications,to yourf fasilitypill'
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order'to' confirm.these -resu.lts andito document thesfactors involved ~
In the evaluation,'yo request;that;you,, provide 'a detailed; evaluation c
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~ tilize? assumptions _ comparable tolthose sfven;1N Regulatory. Guide ' " df
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<;ConseruencesLof,i Fue11. Hand 11ngsAccidentiin:the Fuel Handling Jand, c
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,1'l' ! Stor.E. Fac111tylfor3 Boiling and Pressurized-Water Reactors
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' conside'W.in' a co'nserv'ative mannerMamyfaixir g. in' thatcontainment7 N m
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atmosphere which would delay release of material, Ony filtration of i
effluent which would reduce releases and any automauc isolation of
the containment which would limit releases.
Your evaluation should consist of two parts:
(1) a conservative analysis using parameters (e.g., maximum allowable valve closure times) as limited by the technical specifications and (2) an analysis using parameters associated with current.known facility oper6 ting conditions (e.g.,7 -
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. j actus! valve' closure;. times).*.% Clearly, indicate the enviroment f'
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Yankee Atomic Electric Company January 14, 1977 cc: Mr. Donald G. Allen, President Yankee Atomic Electric Company 20 Turnpike Road Westboro, Massachusetts 01581 Greenfield Public Library i
402 Main Street Greenfield, Massachusetts 01581 2
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