ML20215L300

Nonproprietary, Main Steam Line Break Info Used for Superheat Study for Vogtle Units 1 & 2

ML20215L300
Person / Time
Site:	Vogtle
Issue date:	09/30/1986
From:	Bass J, Morrison R WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
To:
Shared Package
ML19292G141	List: ML20215L281 ML20215L300 ML20215L388
References
WCAP-11286, NUDOCS 8610280565
Download: ML20215L300 (12)

Text

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WCAP-11286 WESTINGHOUSE CLASS 3 l

MSLB Information used For Superheat Study for Vogtle Units 1 and 2 1

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September,1986 J. C. Bass R. J. Morrison -

This document contains information proprietary to Westinghouse Electric Corporation; it is submitted in confidence and is to be used solely for the purpose for which it is furnished and returned upon request. This document and such information is not to be reproduced, transmitted, disclosed or used otherwise in whole or in part without authorization of Westinghouse Electric Corporation.

Westinghouse Electric Corporation Nuclear Energy Systems P. O. Box 355 Pittsburgh, Pennsylvania 15230-0355 8610280565 861020 PDR '

E ADOCK 05000424 PDR I __ _ _ _ _ _ _ _ _ _ _

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The following information was used in the Vogtle Main Steamline Break Outside of Containment study for the effects of superheated steam. The mass / energy l releases were calculated using the methods described in Reference 1 and applied to the Vogtle plant. The LOFTRAN code, modified for the calculation of superheated steam mass / energy releases, was used for the calculations and is described in Reference 2.

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1) WCAP-10961, "Steamline Break Mass / Energy Releases for Equipment Environmental Qualification Outside Containment," October 1985.

2) WCAP-8822-SI-P-A, " Mass and Energy Releases Following a Steamline j Rupture." Supplement 1 " Calculations of Steam Superheat in Mass / Energy l Releases Following a Steamline Rupture," January 1985.

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TABLE 1 I

V06TLE SUPERHEAT MASS & ENERSY STUDY MR BREAK AUIFEED REACTOR SAFETY REACTOR FEEDWATER SAFETY STEAMLINE AUI!LIARY S6 TUBE M/E EVEL $1IE ASSUMPTION TRIP INJECT!DN TRIP ISOLATION INJECTION ISOLAT!DN FEEDWATER UNC0VERY TABLE (8) (FT2) USED ON ON (SEC) (SEC) (SEC) (SEC) (SEC) (SEC) I

__ _ + 4., b C-82.0 1.0 V-01 02.0 0.7 V-02 02.0 0.5 V-07

0.0 1.0 V-09 70.0 0.7 V-10 70.0 0.5 V-Il

'0. 0 0.5 V-15 (1) SUPERPIPE (3 AFW PUMPS) LSP - LOW STEAM PRESSURE OPDT - OVERPCWER DELTA-T (2) SINGLE LS6L - LOW LOW STEAM GENERATOR WATER LEVEL L FA! LURE LPP - LOW PRESSURIZER PRESSURE (2 AFW PUMPS)

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I TABLE V-01 1008 PWER - 1.0 W STEAHLINE BREAK Time Flow Enthalpy Superheat Lgggl (1bm/sec ) (B tu/1bm) (B ru/1bml

+ s, b , c 4.

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.)

• - above saturation enthalpy e

I TABLE V-0.2 1008 POWER - 0. 7 ET 2STEAHLINE BREAK Time

• Flow Enthalpy Superheat

.(.pse.g.). (1bm/sec) (B tu/1bm) (B tu/1bm)

- ~

+ A, b ; C

'l l

\

• - above saturation enthalpy

i TABLE V-07 1008 POWER - 0.5 ET 2STEAHLINE BREAK l

Time Flav Enthalpy Superheat (sec) (1bm/sec) (B tu /s ec) (Btu /sec) l

- ~

+% bd i

I i

L

• - above saturation enthalpy

TABLE V-09 708 POWER - 1.0 W STEAHLINE BREAK

)

l Time Flow Enthalpy Superheat i

(Sec) (1bm/sec) (B ru/1bm) (B tu/lbm)

~ #

+ a,, b , f i

i i

1 1

above saturation enthalpy

d TABLE V-10 E

j 708 PC5lER - 0.7 FT STEAMLINE BREAK Time Flow

• Enchalpy Superheat S.E.tG). (1bm/sec) c'B tu/1bm) (B tu/1bm)

~ ~

YC o b,6

• - above saturation enthalpy

TABLE V-11 708 POWER - 0.5 W STEAHLINE BREAK Time Flow Enthalpy Superheat*

(sec) (1bm/sec) (B eu/1bm) (B ru/1bm)

+ A , o, c

~

~

• - above saturation enthalpy

TABLE V-15 I

j 708 POWER - 0.5 ET STEAHLINE BREAK Time Flov Enthalpy Superheat

.{.1121 (1bm/sec) (B ru/1bm) (B ru/1bm)

- + d.,j b, C.

above saturation enthalpy

. _ .