ML20238E238

PWR Main Steam Line Break W/Continued Feedwater Addl Northwest Nuclear Energy Co Millstone Unit 2. Request for Addl Info

ML20238E238
Person / Time
Site:	Millstone
Issue date:	04/05/1982
From:	Vosbury F FRANKLIN INSTITUTE
To:	Peter Hearn NRC
Shared Package
ML20053C317	List: ML20238E238 ML20244B910
References
TAC-46844, NUDOCS 8709140229
Download: ML20238E238 (3)

Text

- - - - - - - - - - - - - - - - - - - - - --

~

, Enclosure

/,..

REQUEST FOR ADDITIONAL INFORMATION PWR MAIN STEAM LINE BREAK WITH CONTINUED FEEDWATER ADDITION -

NORTHEAST NUCLEAR ENERGY COMPANY MILLSTONE NUCLEAR POWER STATION UNIT 2

' NRC DOCKET NO. 50-336 FRC PROJECTC5506 NRC TAC NO. 46844 FRCASSIGNMENT6 NRC CONTRACT NO. NRC-03-81 130 FRCTASK 154 Preparedby Franklin Research Center Author: F. Vosbury 1 20th and Race Street  !

Philadelphia, PA 19103 FRC Group Leader: R. C. Herrick Preparedfor Nuclear Regulatory Commission Washington, D.C. 20555 Land NRC Engineer: P. Hearn 4

April 5, 1982 w%

.00. Franklin Research Center 8709140229 820520 A Division of The Frank!!n Institute PDR ADOCK 050 6 The Ber$ wren Frankan Portmey. Phus, Pa. 19103 (21S) 444 1000

l * .

s

., ; a ? "l .

BACEGROUND f'

o Evaluation of the information contained in the March 5,1980 letter [1]

from Northeast Nuclear Energy Company (MNECO) to the Nuclear Regulatory C:;.sstssicn (NRC) relating to IE Bulletin 80-04, " Analysis of a PWR Nain Steam

-Line Break wl,th Continued Feedwater Addition," revealed an ite,m of.ooncern.

~i~

, Additiona1'information relating to this concern is needed before a final evaluation can be made'regarding the potential for exceeding containment j design pressure.

The concern and the additional information needed to resolve this concern is. identified in this Request for Additional Information.

. ITEM CONCERN 1 IE Bulletin 80-04 directs the Licensee to review containment pressure ,

response to a main steam line break (MSLB) accident to determine the impact of runout flow from the auxiliary feedwater (AFW) system and other' energy sources.

NNECO's MSLB analysis [2] for Millstone Nuclear Power Station Unit 2 indicated that, after:a MSLB, runout APW flow to the affected' steam generator was not considered to be isolated for 30 minutes. In order for FRC to complete the evaluation of the potential for exceeding contaisunent design pressure, further information is required regarding the design of the AFW system.

REQUEST Please provide the following information concerning the design of the feedwater systems o An evaluation of the capability of the AFW pumps to continue at runout flow for 30 minutes without sustaining damage.

l li I

00AomFranklin Research n etm rm e.m , Ce.nter '

/ :

l ,

1 7, 1

.,,c=

i 1

l l

l

]

f .. REFERENCES

, l t .)

i

,~ i f.

1. W. G..Counsil (NNECO) -

i Letter to B. H. Grier (NIC) ' d

March 5, 1980 ~ l

2. W. G. Counsil (NNE00) '

' Letter to R. Reid (NBC) -

January 25, 1980

\

I 1

i 1

. j l

)

y I

1 t

1 I

. t e

.2-g u Franklin Research Center <

Athemen of The Fm m

_ _ _ . _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _