ML19312E568

Reactor Trip, Revised Emergency Procedures

ML19312E568
Person / Time
Site:	North Anna
Issue date:	12/15/1979
From:	Harvey S VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML19312E567	List: ML19312E566 ML19312E568 ML19312E570 ML19312E574 ML19312E579 ML19312E581
References
2-EP-1, NUDOCS 8006050330
Download: ML19312E568 (8)

Text

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2-EP-1

~3 Page 1 of 5 (d 12-t5-19 VIRGINIA ELECTRIC AND POWER COMPAW NORTH ANNA POWER STATION UNIT NO. 2 REACTOR TRIP

REFERENCES:

1. Westinghouse Logics 5655D33 series.

2. 12050-LSK-1.4

3. FSAR, Section 15 REV. NO. 1 PAGE: E*1 TIRE DATE: 12-15-79 APPROVAL: Y\

RIV. NO. 2 PAGE: 3 DATE: 03-13-80 APPRCVAL: MU j' N REV. NO. 3 PAGE:3-5,ATT.1, DATE: 05-22-80 APPROVAL: M ATT. 2 U

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APPROVED BY: \.D ".is CHAIRMAN ST.3 TION NUCLEAR SAFETY AND OPERATING COMMITTEE SAFETY RELATED 80 0605 0 33d

2-EP-1 Page 2 of 5 12-15-79 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) indi' ate 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,yg decreases below 554 and then will trip closed (P-4).

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2-EP-1 Page 3 of 5 05-22-80 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 not 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 Dump Control Valyes or the Steam Generator Power Operated Relief Valves and that' rave 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 Generator levels are recovering. (33% narrow range level) 3.5 Verify that pressurizer level is recovering. (21%)

3.6 Verify that Pressurizer pressure is recovering. (2235 PSIG) 3.7 Announce on Gaitronics Reactor Trip Unit #2.

3.8 If any of the above parameters are deteriorating (step 3.3 thru l 3.6) and/or a Safety Injection is imminent, proceed to the appropriate EP and request that SR0/STA evaluate the accident i

l utilizing the attached diagnostic checklist. If all parameter:

are returning to normal, proceed to Section 4.0, Long Term d

Operator Action.

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

i 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 I

2-EP-1 Page 4 of 5 05-22-80 Initials 4.0 Long Term Operator Actions 4.1 Verify all full length 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 inter-cepts valves closed.

4.3 Close 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 the auto transfer of power from station service to reserve station service transformers and transformers are not overloaded. (Tiem delay of 30 seconds except upon thrust bearing or generator trips.)

4.6 Verify generator breakers G2T-575 and G-202 open.

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

4.7 Close and lock 2-CH-140.

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

4.9 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 *he aux feed pumps in "AUT0".

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

4.11 Verify the Vital busses, Semi Vital Busses, and DC busses are energized as per Attachment 2.

2-EP-1 Page 5 of 5 05-22-80 4.0 Long Term Operator Actions (cont.)

4.13 Determine the cause of the trip, from first-out indication, compiter post-trip review, and/or sequence of evnets recorder, and refer to the appropriate emergency or abnormal procedures.

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

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

4.15 Initiate reactor shutdown and trip report form.

4.16 Return the emergency borate system to normal as per 2-0P-8.7, if necessary.

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

4.18 Inform chemistry to perform 2-PT-53.5 (reactor coolant system specific activity and isotopic analysis for iodine) following a trip from above 15% rated thermal react- power.

4.1? Establish proper load shedding as per 1-0P-26.7.

I 4.20 Proceed to 2-0P-1.5 or 2-OP-3.2 and re-establish initial condi-tions as appropriate. If a fast recovery is desired proceed to

( 2-OP-1.6.

Completed By:

Date:

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2-EP-1 Attachment 1 Page 1 of 1 05-22-80 p DOMINANT PAR E TIR h -

H e f- ASSOCIATED PARAMETER ff ~e{gg Z# n

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,fj /4- 7 j High Cont. Radiation Levels Low Steamline Pressure (one Generator)

High Air Ejector Radiation Level High Cont. Press.

High Cont. Recire. Sump Level High Cont. Temp.

High Steam F' low Steam Flow / Feed Flow Mismatch High Steam Generator Blowdown Radiation Level Incident Diagnosed as:

By:

SR0/STA

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2-EP-1 Attachment 2 Page 1 of 2 05-22-80 ELECTRICAL BUS VERIFICATION Initial 120 VOLT VITAL BUSSES Verify vital Bus 2-I energized Indication: Voltmeter for Bus 2-1 on backboard.

Verify vital Bus 2-II energized Indication: Voltmeter for Bus 2-2 on9backbsard.

Verify vital Bus 2-III energized Indication: Voltmeter for Bus 2-3 on backboard.

Verify vital Bus 2-IV energized Indication: Voltmeter for Bus 2-4 on backboard.

125 VOLT DC BUSSES NOTE: Associated DC bus voltage indication will be lost if its associated 120V vital bus is lost. The Control board voltage indication for the DC buses comes from a transducer powered from the associated 120V vital bus.

Verify 125 VDC distribution cabinet 2-I energized Indication: Primary, voltmeter for Batt. 2-1 on backboard back-up, light indication on BKR 25C1 (control PWR l

available).

, Verify 125 VDC distribution cabinet 2-II energized Indication- Primary, voltmeter for Batt. 2-II on backboard back-up, :.2ght indication on BDR 25B1 (Control PWR availabl .) or power available for emergency turnine oil pump.

Verify 125VDC distribution cabinet 2-III energized Indication: Primary, voltmeter for Batt. 2-III on backboard back-up, ligh indication on BKR 25A2 (control PWR available),

j Verify 125VDC distribution cabinet 2-IV energized l

l Indication: primary voltmeter for Batt. 2-IV on backboard l back-up power available for air sife seal oil back-up l pump.

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1 2-EP-1 Attachment 2 Page 2 of 2 05-22-80 Initial SEMI-VITAL BUSSES Verify semi-vital bus 1A energized Indication: Subcooling monitoring syste.a (Panel A) energized.

Verify semi-vital bus 1B energized Indication: Subcooling monitoring system (Panel B) energized.

If the power is lost to any of the above buses refer to 2-AP-10.1.

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