ML19211C716

to Emergency Procedure EP-1, Reactor Trip.

ML19211C716
Person / Time
Site:	North Anna
Issue date:	12/04/1979
From:	VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML19211C714	List: ML19211C713 ML19211C716
References
1-EP-1, NUDOCS 8001140274
Download: ML19211C716 (6)

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1-EP-1 Page 1 of 5 12-04-79 VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA PohTR STATION -

LWIT NO. 1 REACTOR TRIP [. < . , J.12.' :. ~

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REFERENCES:

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1. Westinghouse Logics 5655D33 series.

2. 11715-LSK-1.4

3. FSAR, Section 15 REV. NO. 4 PAGE: Entire DATE: 12-04-79 APPRGAL:\

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1741 084 RECOMMEND APPROVAL- .,

N i M APPROVED BY: hi hwO CHA E.'jg STATION NUCLEAR SAFETY ANI) OPERATING COMMITTEE DATE. 12-04-79 C A Fi~'TY REL ATED 8001l'1 anj '

1-EP-1 Page 2 of 5 12-04-79 1.0 Indications 1.1 The annunciation of any alarm light on the reactor trip first-out portion of panels D or E.

1.2 The individual rod position indication system show all full length rods on the bottom.

1.3 Reactor trip breakers (Train A & B) indicate open.

2.0 Automatic Actions 2.1 Train "A" and "B" reactor trip breakers are opened simul-taneously.

2.2 Turbine trip by reactor trip (P-4).

2.3 The steam generator feedwater regulating valves will control level, until T ava decreases below 554' and then will trip

([ closed (P-4).

1741 085

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1-EP-1 Page 3 of 5 12-04-79 3.0 Immediate Operator Actions 3.1 Manually trip the reactor, verify all full length rods are fully inserted and that power level has decreased to 2 zero.

NOTE: If any required automatic action has ner. occurred, it shall be manually initiated.

NOTE: If the reactor has not tripped following the opening of the Reactor Trip Breakers, manually initiate' safety injection.

3.2 Manually trip the turbine.

3.3 Verify proper operation of the Steam Du=p Control Valves or the Steam Generator Power Operated Relief Valves and that Tave is decreasing and/or stabilizing at 547'F.

NOTE: If it is determined that an uncontrolled RCS cooldown is in progress, simultaneously close all three MSTV's.

3.4 Verify Main or Auxiliary Feedwater Flow and that Steam Ger.erator

( levels are recovering.

3.5 Verify that pressurizer level is recovering.

3.6 Verify that Pressurizer pressure is recovering.

3.7 If any of the above parameters are deteriorating (step 3.3 thru

,o ;id 3.6) and/or a Safety Injection is immenant, proceed to the appropriate EP and request that SRO/STA evaluate the accident utilizing the attached diagnostic checklist. If all parameters are returning to normal, proceed to Section 4.0, Long Term Operator A-tion.

CAUTION: Do not make operational decisions based solely oc a single plant parameter when one or more confirming indications are available.

1) EP-2 Loss of Reactor Coolant (high Cont. radiation level)

2) EP-3 Loss of Secondary Coolant (rapid increase or decrease in Tave)

3) EP-4 Steam Generator Tube Rupture (high air ejector rad. level)

( 4) EP-5 Safety Injection 1741 086

1-EP-1 Page 4 of 5 12-04-79 Initials 4.0 Long Term Operator Actions 4.1 Verify all full lecgth rods are fully inserted.

NOTE: Emergency borate 7 minutes for each full length rod not fully inserted.

4.2 Verify all turbine throttle, governor, reheat stops and intercepts valves closed.

4.3 Clou the " Reheater" inlet valves by pushing the " Reset" push-button on the reheater control panel.

4.4 Verify all turbine drains open.

4.5 Verify generator breakers G1T568 and GIO2 open.

4.6 Verify the auto transfer of power from station service to reserve station service transfomers not overloaded. (Time delay of 30 seconds except upon thrust bearing or generator trips.)

4.7 Close and lock 1-CH-217.

4.8 Control Steam generator level at "N0 LOAD" level (33%) on feedwater bypass FCV's or on auxiliary feedwater system. If a main feed pump is running, place the aux feed pumps in "Ab"IO".

4.9 Verify steam dump steam pressure control setpoint at 1005 psig (the pot setting should be 71.78%) and shift steam dumps to pressure mode.

4.10 Stop or verify stopped one main feed pump, the LP heater drain pumps and the HP Heater drain pumps.

4.11 Isolate auxiliary steam loads and shift auxiliary steam supply from the affected unit as necessary.

4.12 Determine the cause of the trip, from first-out indication, k computer post-trip review, and/or sequence of events recorder, and refer to the appropriate emergency or abnormal procedures.

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1-EP-1 Page 5 of 5 12-04-79 4.0 Long Term Operator Actions (cont.)

4.13 Verify source range unblock when below P-6 reset at 5 x 10 -11 amps.

NOTE: Manual reset of source ranges c:ay be required on a malfunction of an Intermediate Range Channel.

4.14 Initiate reactor shutdown and trip report form.

4.15 Return the emergency borate syst s to normal as per 1-0P-8.8, if necessary.

4.16 If the unit is to be shutdown for an extended period of time, re-establish a ring bus lineup in t1:- switchyard in accordance with system operators instructions.

4.17 Inform chemistry to perform 1-PT-53.5 (reactor coolant system specific activity and isotopic analysis for iodine) following a trip from above 15*. rated thermal reactor power.

( 4.18 Establish proper load shedding as per 1-OP-26.7.

4.19 Proceed to 1-OP-1.5 or 1-0P-3.2 and re-establish initial condi-tions as appropriate. If a fast recovery is riesired proceed to 1-0P-1.6.

Completed By:

Date: _

1741 088

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• 1-EP-1 Attachment 1 Page 1 of 1

( m 12-04-79 DOMINANT PARAMETER 4- ASSOCIATED PARAMETER

/ e4 / /c 4,5 44 S .:P a t> 9y e 4 4+ d e Low Press. Press.

Low Press. Level High Press. Level High Cont. Press.

GidMS High Cont. Radiation Levels s

? High Air Ejector Radiation Level 1 3 High Steam Generator Blowdown Radiation Level Steam Flow / Feed Flow Mismatch Letdown Isolation /Htr Cutoff Decreasing Tave r Increasing Tave Stable Tave

/ High Cont. Recire. Sump Level Low Steamline Pressure (One Generator)

Low Steam Generator Level Increasing Steam Generator Level Increased Charging Flow High Steam Flow High Cont. Temp.

WS!9&

PS8703: Low Feedwater Pump Discharge Press.

Incident Diagnozed as: g

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By:

SR0/ STA

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