ML19323A863

Emergency Procedure 2-AP-21,Revison 3, Loss of Feedwater Flow.

ML19323A863
Person / Time
Site:	North Anna
Issue date:	10/24/1979
From:	Harvey S VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML19323A861	List: ML19323A860 ML19323A863 ML19323A865 ML19323A871 ML19323A874 ML19323A878 ML19323A883 ML19323A896 ML19323A897
References
2-AP-21, NUDOCS 8005060149
Download: ML19323A863 (4)

Text

~

go05060l 7 i g ._ ___>_ .. _ .- _ ..

ser . co- - : .r_En 2-AP-21 3

/ - Page 1 of 4 10-24-78 s_ , c.i

_. _.. ,N VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNIT NO. 2 LOSS OF FEEDVATER FLOW

REFERENCES:

1. FSAR Chapter 10.4.3, Condensate and Feedwater Systems

2. FSAR Chapter 15.2.8, Loss of Feed

3. 12050-FM-74A Feedwater

4. Westinghouse Logic Diagram 5655D33, Sheets 13 and 14

5. 12050-LSK-5-13A, Aux. Feed Pumps t 1 "

REV. NO.: PAGE: DATE: APPROVAL:Mk REV. NO. 2 PAGE: 4 DATE: 05-21-79 APPROVAL: >

REV. NO.: 3 PAGE: 3&4 DA"E:_09-05-79 APPROVAL:M m , .

I V E P C O P 3' .; ; ? 3 ? - l i - c e pr -- g

~~

a eni ... l

.r... v. . .

• . 'v ;

_, , ; l 1

R

.E_COM$. ENDED _APPROVAE . O M,. . Ms APPROVED BY: MFJM CCLEAR SAFETY CHAIRMAN AND OPERATING STATION {CMCIITTEE SAFETY RELATED o.m. a z# 24

'f3.. t . . . . .. . . . - . -

2-AP-21 Page 2 of 4 10-24-78 1.0 Purpose 1.1 This procedure provides the indications of, probable causes for, and the ic:r ediate and long term actions to be taken in the event of a complete or partial loss of feedwater flow.

2.0 IndicatioQ.

The following indications, in sequence, typify the conditions resulting from a loss of feedwater flow:

2.1 Decreasing steam generator level.

2.2 Increasing reactor coolant T,yg.

2.3 Increasing pressurizer pressure, level and temperature.

2.4 Steam flow / feed flow mismatch in one or crore operating loops.

2.5 Automatic start of stand-by feedwater pump.

f 3.0 Probable Causes 3.1 Lot.s of feedwater pumps.

3.2 Loss of condensate pumps.

3.3 Hupture of feedwater or condensate niping.

3.4 Failure in the steam generator level control system resulting in the closure or one or more feedwater control valves.

i I

1

- L.:. 4.._ _. . . . .__ . . . - . . .

7 e

2-AP-21 Page 3 of 4 09-05-79 4.0 Immediate Operator Actions 4.1 Attempt to re-establish feed flow:

4.1.1 Verify or start the standby condensate and feed pumps if pressure is low.

4.1.2 Place feedwater control valves in " MANUAL" if necessary (FCV-2478, 2488, 2498).

4.2 If steam generator level cannot be controlled, trip the reactor when steam generator level decreases below 25%, coincident with steam flow / feed flow mismatch.

Completed By:

Date:

.. o a s .. . _. _ _ . . __ _ _ _ ._ .__. . _

2-AP-21 Page 4 of 4 09-05-79 Initials 5.0 Long Term Operator Action 5.1 If the Reactor was tripped, carry out 2-EP-1.

5.2 Verify all auxiliary feedwater pumps started on trip of all main feedwater pumps or on steam generator level < 15%, and control steam generator level at the no load valve (33%) by throttling at the control board:

"A" S/G MOV-W-200D "B" S/G MOV-FW-200B "C" S/G HCV-FW-200C 5.3 Conduct an investigation to determine the cause of the loss of feedwater flow.

5.4 If the loss of feedwater flow is due to a feedwater or cort-l densate piping rupture:

5.4.1 Verify or trip all main feedwater pumps.

5.4.2 Verify or trip all condensate pumps.

5. 4. 3. Trip all high pressure heater drain pumps.

5.4.4 Trip all low pressure heater drain pumps.

5.4.5 Isolate the break.

5.4.6 If turbine building flooding exists, carry out 2-AP-39.

5.5 When cause of feedwater " Loss of Flow" is corrected, connnence normal feed flow as per 2-Op-31 and proceed to 2-OP-1 for start-up. If nature of feed water problem requires a plant shutdown refer to 2-OP-3.

Completed By:

l Date:

l l

l

,