TXX-6936, Forwards Info Associated W/Wcap 11331 Re Plant Thermal/ Hydraulic Analysis of Fire Safe Shutdown Scenario,Per NRC 871104 Request.Record of 871104 Telcon W/Westinghouse Encl

Forwards Info Associated W/Wcap 11331 Re Plant Thermal/ Hydraulic Analysis of Fire Safe Shutdown Scenario,Per NRC 871104 Request.Record of 871104 Telcon W/Westinghouse Encl

ML20236M512
Person / Time
Site:	Comanche Peak
Issue date:	11/05/1987
From:	Counsil W, Woodlan D TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
TXX-6936, NUDOCS 8711130157
Download: ML20236M512 (6)

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i nlELECTRIC A

l wmi s c. c=nsit November 5,.1987'

' Encuive Vice President ~

N U. S~ Nuclear Regulatory Commission

. Attn:

Document Control Desk--

Washington, DC 20555 i

SUBJECT:

COMANCHE PEAK STEAM' ELECTRIC STATION'(CPSES)

DOCKET NOS. 50-445 and 50-446' l

-TRANSMITTAL OF INFORMATION ASSOCIATED WITH WCAP 11331, COMANCHE 1

PEAK STEAM. ELECTRIC STATION' THERMAL / HYDRAULIC ANALYSIS.0F FIRE SAFE SHUTDOWN-SCENARIO-Gentlemen:

I

~

i Attached are copies of a comparison. of time frames used for' WCAP 11331 and

. EPM.-P0257-167-000 - and a. telephone. conversation record containing data used to, calculate PRTc rupture time ~ with ~ spurious Safety Injection in the WCAP.

Please' note the WCAP calculation of PRT rupture time' represents a conservative l

estimate and-is'not. intended to be a~best estimate.

~

i Thi's information ~is provided in response to our. telephone conversation of November,4, 1987, with your staff.

Very truly yours.

W. G. cA W. G. Counsil By:

D. R. Woodlan j

Supec.Isor Docket Licensing R08/vjt Attachment

~ c1-Mr. A. Fresco, BNL Mr. R.'D. Martin,' Region IV 1

J Mr. A. Singh, OSP.

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- Resident Inspectors, CPSES (3) 0y

' 8711130157 871105 i

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. Sheet 2 of 3 COMPARISON OF CALCU'.ATION NO. EPM-P0257-167-000 TIMEFRAMES' TO WESTINGHOUSE SPURIOUS SI ANALYSIS (WCAP 11331, p. 67 and 106)

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Time (sec)

Westinghouse Cale No. EPM-P0257-167-000 0

Offsite power available (Same)

Trip Reactor (manual)

Trip-Main FW Pumps 120-1270 RCS Pressure at Safety (Same)

Valve Setpoint 180 Close MSIVs Trip RCPs (Same) 300 Stop One Charging /SI Pump 720 Initiate AFW Flow at (Same) 235 gpm/SG to Genera-tors 1 and 2 780 Terminate Safety Injection Flow 840 Stop One Charging /SI Pump 1020 Terminate PRZ Heater (Same)

Operation.

1050 Pressurizer Level at 100%

1140 Terminate Safety Injec-tion Flow 2290 Approximate Time of In-(Same) active Loop SG Dryout (SGs 3 and 4) 2290-3870 RCS Pressure at Safety RCS Pressure at Safety Valve Setpoint (Liquid Valve Setpoint Break Flow Discharge) 2800 Throttle AFW (Same) 3120 PRT Rupture (WCAP 11331 p.

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Time-(sec):

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PRT..Does ~ Not ' Rupture'

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_ Transient'.Terminati.on (Same)'

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TXX-6936 Attachm*Ht 2' ELEPHONE CONVERSATION. RECORD

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Date: 11/04287 Time: 4:10pm' CST l

. Call;by:

A. F. cannon of Westinghouse

'4 (Name) 1 (Company)-

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Answer.by H.

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Beck of CPE, Fire Protection (Name)

-(Company)

' Subject discussed COMANCHE PEAK STEAM ELECTRIC STATION WESTINGHOUSE CALCULATION OF PRT RUPTURE TIME IN WCAP-11331

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I

SUMMARY

OF DISCUSSION, DECISIONS AND COMMITMENTS.

Andy' Gagnon called to give data concerning the calculation of PRT rupture I

t time.

At the beginning of the transient there is capacity in the PRT for

the addition'of 19926 lba of fluid discharge..The following fluid contribu-tions to the~PRT were assumed

Seal Leakoff 0-600~ seconds 705.8 lb 600-1140 seconds 4447 lb 1140-2800 seconds 1952.9 lb Seal Iniection_

1140-2800 seconds 2752 lb Safety Valve Discharge (Intermittent) 0-2800 seconds 4140 lbm A contribution of 2166 lbm is added to account for density change of the fluid in the PRT.

Therefore, at 2800 seconds allowable discharge mass remaining = 19926 - (705.8

+ 4447 + 1952.9 + 2752 + 4140 + 2166) = 3762 lbm (still available)

After 2800 seconds:

Safety Valve Flow

= 10.2 lbm/see Seal Leakoff Flow 1.18 lbm/sec

=

Seal Injection Flow =

1.66 lbm/sec 13.04 lbm/sec

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