ML20148H175

From kanterella
Jump to navigation Jump to search
Forwards Request for Addl Info Re Review of Westinghouse ECCS Evaluation Model.Info to Be Submitted by 741201
ML20148H175
Person / Time
Site: Yankee Rowe
Issue date: 11/04/1974
From: Purple R
US ATOMIC ENERGY COMMISSION (AEC)
To: Andognini G
YANKEE ATOMIC ELECTRIC CO.
References
NUDOCS 8011170375
Download: ML20148H175 (4)


Text

- - - - _ _ _ _ _ _ _ _ _ - _ _

P I

NOV 0 41974 w

Dochet No, 50-29 [p

Yankee Atomic Electric Company -

i ATDI: Mr. Carl Andognini, Assistant to the Vice President '~

20 Turnpike Road Westboro, FMseachusetts 01581 C

E Gentlemen:

As a result of our generic review of the Westinghouse ECCS Evaluation Model, we have identified information which must be provided on a  ;

case-by-case basis to enable us to complete our review of individual E plant compliance with the criteria set forth in paragraph 50.46(b), -

" Acceptance Criteria for Emergency Core Cooling System for Light- 7-Water Cooled huclear Power Reactors," of 10 CFR Part 50. The infor- iv

=ation required is identified in the enclosure to this letter. P p

In order to maintain our review schedule for the Yankee Rowe plant, ,

ve need information requested by December 1, 1974.

Picase contact us if you desire any discussion or clarification of t,ho information required.

Sincerely, Original si:nud by:

Robert A. Purple Robert A. Purple, Chief Operating Reactors Eranch #1  ;

Directorate of Licensing

Enclosure:

Request for Additional Information cc: See next page THIS DOCUMENT CONTAINS POOR QUAUTY PAGES go1pno 3I

a- .. ,

p; ,

Yankee Atomic Ilectric Company' - 2-

% 0 4 1974 ,

. i

, cc w/ enclosure:

Mr. Donald C. ' Allen, Preside.nt --

Yankee' Atomic Electric Cocipany 20 Turnpike Road L'ostboro, Massachusetts 01581 ,

t DISTRIBUTION f- ' I.-

Docket File #

AEC PDR-OR-1 Reading  ;

ACRS (16) g:, z., .

RO (3) -

occ- h TBAberanthy 0  :)

I3 JRBuchanan f2Goller .

i ABurger l.'

S11Sheppard {

f t

?

L r,

t

. i 1

t 3, , . e s ,. L:0R-1 L:0R- [g:5 es--s* .ABurgpr*de,.

,,,.R6P,9,,rple fb- ]

o a r **

11/1/74,,@

11/4/74 . . .. j ,

rarm A1 Cats new. 9 53) AICM O24') W u. s. nov e === s at easatma or rec ti s e74.sa .i..

I

.- --,/-.mr- .--.-.,m.

e, o.' . ,

~~

a .

ADDITIONAL' INTOR'!ATION FIOUIRED , l TROM ALL UTILITIES R I

. UTILIZING WESTINGHOUSE NUCLEAR STEA'4 SUPPLY SYSTD!S q

1. Provide justification for the following input parameters t. sed in the ECCS evaluation model: ,

1 a) Net Free Containment Volume - Justification should include '.l

.U the total gross internal containment volume and the internal structures and equipment and their volumes which are sub-

~

'.: n tracted to obtain the net free containment volume. A

  • discussion of the uncertainties should be provided. i.

[.

h b) Passive Heat Sinks - Discuss .

the method of determining the ..

--a passive containment heat sinks. Identify each heat sink by . !;

. . lE ..

category (i.e. , cabfc tray, equipment supports, floor N p

grating, crane vall, etc.) and provide surf ace arca, thickness, Ik materials of construction, thermal conductivity and volumetric heat capacity, by component category used in the containment  !

transient analysis code.

c) Startinr, Time of Contcinment Cooldne Svstem(s) - Discuss the factors thct show that the start time (r) assumed in the con-tcinment response analysis represent the earliest possibic initiation of system (s) operation.

d) Containment Initial Conditions - Compare the initial values of te=perature, pressure and relative humidity in the con-tainment with the range of values that vill be permitted durin-  :

s r

plant operation. ')

e s

'- . -.. o , . .. , s

[ :'  ;. l.j

. .< .I l}

t' .O f.

. +

l

\

Containment Spray Water Temperature - Show that tile value of

^

response analysis is the lower bound te=perature consistent

^

with plant operating conditions. ....

^

2., For the most severe break provide the following information: ,

h li.

. a) Fan-cooler heat removal rate as a funhion of containment .

1 atmosphere temperature. Show that minimum operational values ,

of service water temperature have been used in deter =ining the .

, , .  :. +=,

. fan-cooler heat removal rate. }"

p -

b) Mass and energy release rates to the containment as a function E I.':

of time during the blowdown, refill and reflooding periods of  ;.

1 the accident. Ine_lude any spilled ECCS vater.  :.. >

l' 0

. :}

s 4

e O

e n

i 9

a

~

a

, i i

i

- w --. -- eei-