ML20072A735

Anticipated Transient W/O Trip, Rev 0

ML20072A735
Person / Time
Site:	Comanche Peak
Issue date:	12/30/1982
From:	Rosalyn Jones, Sadil R TEXAS UTILITIES SERVICES, INC.
To:
Shared Package
ML20072A720	List: ML20072A735 TXX-3613, Forwards Rev 0 to Procedure, Anticipated Transient W/O Trip, to Facilitate Review of Items 1.C.1 & 1.C.8 of SER (NUREG-0797)
References
ECA-1.0, NUDOCS 8301240115
Download: ML20072A735 (5)

Text

-

)

O COMANCHE PEAK STEAM ELECTRIC STATION EMERGENCY RESPONSE GUIDELINES

~ O. D

n ~~' n r p

d

=

1 l-1<

V V

..memas ANTICIPATED TRANSIENT WITHOUT TRIP SAFETY-RELATED d

PROCEDURE NO. ECA - 1.0 REVISION NO. 0

/3,W

,2.44 os1E zuS,,111eo sY OPERATIONS SUPERINTENDENT W

APPROVED BY

/.

DATE /M B

7-MANAGER, Pp OPERATIONS 6301240115 830118

~

PDR ADOCK 05000445 A

PDR

CPSES ISSUE DATE PROCEDURE NO.

EMERGENCY RESPONSE GUIDELINE JAN 051983 ECA - 1.0 ANTICIPATED TRANSIENT WITHOUT TRIP REVISION No. O Page 2 of 5 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED A. PURPOSE The purpose of this guideline is to add negative reactivity to the core when the control / shutdown banks are not inserted upon demand, to establish and caintain a heat sink for conditions amenable to long term cooling, and to prevent or minimize damage to the fuel and release of excessive radioactivity.

B. SYMPTOMS Tollowing are symptoms of an anticipated transient without scram condition:

1.

Reactor trip breakers fail to open 2.

Rod position indicators show failure of CRDMs to insert 3.

Rod bottom lights not lit 4.

Neutron level not decreasing rapidly corresponding to large negative reactivity insertion h

l f

m w - * -*

ene

.M.,,e.-%.,v,,4,,,,,em g,

y

.-ms,,,,

,,*_m___

PROCEDURE NO.

ISSUEDdTEJAN 51983 ECA - 1.0 CPSES EMERGE!!CY RESPONSE GUIDELINE ANTICIPATED TRANSIENT WIT 110UT TRIP REVISION No. O Page 3 of 5 STEP ACTIOf4/ EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE:

If at any time a reactor trip occurs, icznediately go to E0P-0.0, REACTOR TRIP OR SAFETY INJECTION, STEP 2.

1 Perform Following Actions From Control Room:

a. Try to t rip reactor canually

a. Try to canually insert control rods.

b. Try to trip turbine manually

b. Try to runback turbine.

2 Check AFW Ptnps Running:

a. Motor-driven pump breaker

a. Manually start pumps, indicator lights - LIT

b. Turbine-driven pump steam

b. Manually open valves, supply valves - OPIN 3

Check AFW Valve Alignment:

a. AFW valves - PROPER EMERGENCY

a. Manually open or close ALIGNMEhT:

valves as appropriate.

e M0T DRV AUX FW PMP-1 TO SG-1 FLOW CNTR, 1-FK-2453A e M0T DRV AUX FW PMP-1 TO SG-2 FLOW CNTR, 1-FK-2453B e MOT DRV AUX FW PMP-2 TO SG-3 FLOW CNTR,1-FK-2454A e MOT DRV AUX FW PMP-2 TO SG-4 FLOW CNTR, 1-FK-24 54B e TURB DRV AUX FW PMP TO SG-1 FLOW CNTR,1-FK-2459A e TURB DRV AUX FW PMP TO SG-2 FLOW CNTR, 1-FK-2460A e TURB DRV AUX FW PMP TO SG-3 FLOW CNTR, 1-FK-2461A e TURB DRV AUX FW PHP TO SG-4 FLOW CNTR,1-FK-2462A

• e e

CPSES ISSUE DATE PROCEDURE NO.

EMERGENCY RESPONSE GUIDELINE JAN 051983 ECA - 1.0 ANTICIPATED TRANSIENT WITHOUT TRIP REVISION No. O Page 4 of 5 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 4

Check If The Following Trips Have Occurred:

a. Reactor trip a.

If not, try to trip reactor 3

locally:

e REACTOR TRIP BREAKER A e

REACTOR TRIP BREAKER B f

e BYPASS BREAKER A e BYPASS BREAKER B e MOTOR BREAKER MG SET 1 k

e MOTOR BREAKER MG SET 2 p'

e GEN BREAKER MC SET 1 i

e GEN BREAKER MG SET 2

b. Turbine trip

b. If not, try to trip turbine locally:

o CNTR FLUID PMP "A",

(1-HS-6550) e CNTR FLUID PMP "B",

(1-HS-6551) e CNTR FLUID PMP "C",

(1-HS-6552) e LOCAL TRIP VALVE 5

Verify AFW Flow:

a. AFW flow indicators - CHECK

a. Perform actions of steps 2 and 3 locally.

FOR FLOW l

• CAUTION:

Charging pump miniflow valves must remain open when

• RCS pressure is greater than (LATER) i p

5

CPSES ISSUE DATE PROCEDURE NO.

EMERGENCY RESPONSE CUIDELINE JEd{ 051983 ECA - 1.0 ANTICIPATED TRANSIENT WITHOUT TRIP REVISION No. O Page 5 of 5 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 6

Initiate Rapid Boration of RCS To Obtain Adequate Shutdown Margin:

a. Initiate emergency boration:

1) Open the Emergency Boration

1) ))[ valve 1-8104 does not Valve:

open, THEN open the boric e EMER BORATE VLV (1/1-8104) acid to blender valve 1-FCV-110A and manual emergency boration valve 1-8439.

2) Start both Boric Acid Transfer Pumps:

e BA TRANS PMP 1, (1/1-APBA 1)

BA TRANS PMP 2, (1/1-APBA 2) e

3) Verify PD charging pump running

3) Start PD charging pump.

4) Adjust letdown flow to 120 GPM NOTE: This will require additional charging pumps

(

to be run in order to maintain PZR level.

5) Determine boron addition by observing emergency borate flow:

e EMERG BORAT FLOW, (1-FI-183)

AND the time duration of the emergency boration

6) Monitor the following parameters to determine adequate boration:

o Control rod bank position e Tave e Neutron flux level Emergency boration flow rate e

7 Verify Containment Ventilation

))[ isolation has NOT occurred, Isolation THEN manually isolate containment ventilation.

8 Maintain Adequate Shutdown Borate as necessary.

l Margin per OPT-301, CALCULATING SHUTDOWN MARGIN.

9 Go to E0P-0.0, REACTOR TRIP OR SAFETY INJECTION, STEP 2.

-END-

........ _.. -