ML20210B484

From kanterella
Jump to navigation Jump to search
Partially Withheld Rept Re ACRS 631107-08 Review of Proposal for Startup & Low Power Operation of Hanford Reactor.Load & Operation to Max 400 Mwt Power Level for Initial Testing Program Approved
ML20210B484
Person / Time
Issue date: 11/19/1963
From: Hall D
Advisory Committee on Reactor Safeguards
To: Seaborg G
US ATOMIC ENERGY COMMISSION (AEC)
Shared Package
ML20210B278 List:
References
FOIA-86-346 ACRS-GENERAL, NUDOCS 8609180094
Download: ML20210B484 (2)


Text

-

y

~ - -

t AFEGUARDS ADVISORY COMMITTEE ON

{

UNITED STATES ATOMIC ENERGY COMMISSION WASHINGTON 25. D. C.

NOV 191963 Ecoorable Glenn T. Seaborg g

Chairman U. S. Atomic Energy Commaission Washingten, D. C.

REPOR ON BAEFORD N-REACTOR (EV FROIIJCTION REACTO Sub,)ect:

Dear Dr. Seaborg:

1 At its fifty-first m2eting, November T-8,1963, the Advisory Committee 1

j on Beactor Safeguards reviewed the proposal for start-up and low power Discussions were held with representatives operation of the N-Heactor.

The documents refer.

of the General Electric Company and the AEC staff.

j enced below were available.

Since 1958, the N-Senactor has been oor.sidered at a ausber of Commaittee

)

At the earlier ametings, attention was ami Subcommittee meetings.

directed to the novel confinement scheme which is based on release of

(

8[

excess building pressum from a possible accident before fission pro-ducts are released from the fuel. The complete design of the plaat 14-15,1963, was reviewed at a Subcommittee meeting at Banford om August and the design was considered further at this fifty-first Committee meeting.

The Coznittee cournented on aspects of the New Production Anactor in 14, 1960 and April 10, 1962. These letters letters written on March stated that the proposed confinement scheme was an improvement en the protection at the other Emnford reactors against fission product release; that the operation of NPR will not significantly increase the present hasards of the Hanford operations; and that.the RPR on this site appears acceptable as a power mactor, assuming that the pmposed ecafinement Review of the complete sjuteni has not systes operates as intended.

changed these conclusions.

The success of the confinement sehene depends la part en a number of seals and dampers that close the building vents esce the pressun release At an early stage, before the fission product inventory has ended.

reaches a significant level, tests abould be unde to establish the re.

Liability of these systems.

lone uncertainty in the proposed emergemey system eomeeras the ability to use the last-ditch cooling systen without seven fuel damage and The question should be esplored farther, with

' fission product release.

is

, t.be aim of developing a definitive naswer befom full power operation approached.

t 0609100094 06091D PDR FOIA nob

% **3 %

TAYLOR 06-346 POR y

'.N 191963 2-(

Eonorable Glenn T. Seaborg the N-Reactor as Decause of the site, it was not necessary to des f uards, as most d

Seversi of its civilian power reactors the Committee has reviewe.

larger zuleases features raise questions as to the possibility of ammercial power from a severe accident than are believed endible for can reach a conclusion as to the acceptability o the confinement nactors.

Among these features arelevels of radioactivity full power operation.

scheme; the possibility of release of sizeableto the ditch; some uncertainty -

as to reliability of the last-ditch raw watersite of poss tion of the other If the N-Reactor is operated for power only, and operateriminates, t i

lations appli-i Hanford reactors for military product on' the N. Reacto g

t The present cable to commercial nactor plants.10 CFR Part 20 limits if any.

exclusion radius could not be reduced much, safeg nection with the last.

ditch cooling system.

d and opersted to The Comittee believes that the N-Reactor can be loadeitial testin a mximum power level of 400 MW(t) for the inwith ds of the Banford l

operation.

Sincerely yours, criE n31 D. B. Itall i

signed D. 3. En11 I

Chairann t", dated NW-7ti930, Volumes 1-),

"N. Reactor Basards Sunsary Repor Referencent l Elements",

l 1.

April 15,1963(8/RD).NW-77470, " Burnout Beat Fluxes f l

12,1963(C/RD).

No. 2"

.3 2.

HW-78837, "N. Reactor Hazards Sunusary Report - Supplement dated June datedSeptember4,1963(S/RD).

3 i


_n,,m,.

--s--..,

,4 m,

_,,___,,e_, _ -

,,,_,.__,,_,,.,,g-

,,-,,_,.,-_,,,_,,e, w

-