ML20148H875

From kanterella
Jump to navigation Jump to search
Approves Proposed Change 36 to Tech Specs,Authorizing Proposed Loading Configuration for Core 3 & Use of Boric Acid During Power Operation W/Core
ML20148H875
Person / Time
Site: Yankee Rowe
Issue date: 09/13/1963
From: Lowenstein R
US ATOMIC ENERGY COMMISSION (AEC)
To: Coe R
YANKEE ATOMIC ELECTRIC CO.
Shared Package
ML20148H881 List:
References
NUDOCS 8011200119
Download: ML20148H875 (2)


Text

'

, /-

y. . _ , t p*""4 UNITED STATES (5 d ATOMIC ENERGY COMMISSION WASH INGTON, D.C. 20545

_ [*

%, o,',n ' ,/ -

og i 1 i Ly.t

~

-% 50 29 y

q

\

k Yankee Atomic Electric Company Change No. 36  :-

441 Stuart Street 5 11oston 16, Massachusetts Attention? Mr. Roger J. Coe Vice President Gentlemen:

This refers to your request, dated June 7, 1963, and supple-ments thereto, dated July 1 and 25, 1963, designated Proposed jx.

Change No. 36, requesting authorization to amend the Technical Specifications of Facility License No. DPR-3 pursuant to the  ;

provisions of Section 50,59, 10 CFR 50. Proposed Change No. 36 ,

would authorize the proposed loading configuration for Core III ,

and the use of boric acid during power operation with this core.

The Proposed Change was reviewed by the Advisory Committee on Reactor Safeguards at its July 11-13, 1963, meeting. In its

[M g g

1ctter to the Commission regarding the matter, the Committee y stated that, on the basis of the information presented, they 3; believed the proposed Core III loading and operation up to full ~

71 -

power with boric acid in the primary coolant,may be carried out ,

without undue hazard to the health and safety of the public, c, A copy of their letter is enclosed. -

Ne have also reviewed Proposed Change No. 36, pursuant to the provisions of Section 50,59, 10 CFR 50, and have concluded i' there is reasonable assurance that the health and safety of the public will not be endangered thereby, Ne believe, however, ,

that the proposed reporting requirements to be incorporated n' into the Technical Specifications should be revised as set forth below, A copy of our related hazards analysis is en.

closed -

In view of the foregoing, Proposed Change No. 36 is hereby nuthori cd pursuant to Section 50,59, 10 CFR 50, except that Secticr.' D,2,a,(8) of the Technical Specifications as proposed therein is nodified to read as follows:

THIS DOCUMENT CONTA1NS POOR QUAUTY PAGES 801120o//f

C .

.=

3 "The Commission. shall be immediately notified should an unex-plained . reactivity change greater than 0.8's A K/K take place at any time subsequent to the first week of full power opera- ..

4 tion. . ' This reporting requirement shall be in effect only when the boron concentration in the primary system exceeds 80 ppm and within one week after a reduction to a boron con-centration' of. less than 80 ppm." ,.

Sincerely yours, H

(SiPed) _

Eber R. Price, Assistant Director Division of Licensing and Regulation R. .Lowenstein, Director Division of Licensing 6 Regulation -

Enclosures:

ACRS Report .

Ilazards Analysis 6 :e Distribution l1 ._

11. J. McAlduff, OR00 [ . . .

E. G. Case H. Shapar ;_ ,

P '

L. Kornblith - 2 P. Travelstead . . ,

E. Tremmel H. Steele G. Page -

R. Huard N. D. !!ason Document Room Formal Supplemental <

DLGR Reading RGPRSB Reading [

I  :

n y I

'l

.- d. , . ~ i)

DLGR S)p A DLGR

[DLG D

yf[ .

ND>1ason/daf ME PJ1B 'd\ ~aCbe RLowenstein 9/13/63 9 9/@63 9 '\'// 63 9/ fy63 9//M63 i

l