ML20053A293

Loss of Coolant/Rc Pressure

ML20053A293
Person / Time
Site:	Arkansas Nuclear
Issue date:	10/26/1981
From:	ARKANSAS POWER & LIGHT CO.
To:
Shared Package
ML20053A281	List: ML20053A280 ML20053A293
References
1202.6, NUDOCS 8205250179
Download: ML20053A293 (8)

Text

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PLANT M ANUAL SECTION:

PROCEDURE / WORK PLAN TITLE:

NO:

l l

EFIERGENCY OPERATING LOSS OF COOLANT /RC PRESSURE 1202.06 p

PAGE 12 ot~ 25 ARKANSAS NUCLEAR ONE aEvisioN lioATE 1o/20f81 CHANGE DATE 4.0 FOLLOW-UP ACTIONS: NO F.W. AVAILABLE 4.1 If RCP's are operating, stop all but 1 RCP per loop.

4.2 flanually open turbine bypasses if condenser is under vacuum, otherwise, open the atmospheric dump valves to allow feed from a condensate pump (if one is available, even though the auxiliary FW pump is not).

If no condensate pump is available for OTSG feed, fully open dump or bypass valves and align SW feed to the OTSG's through the idle EFW pumps as follows:

CAUTION IF ONLY A CONDENSATE PUMP IS AVAILABLE, CLOSE LO-LOAD VALVES AND ?!0DU-LATE SU VALVES TO FEED SLOWLY, t!0NITORING RCS TEt!PERATURE AND PRESSURE; FEED TO CONTROL TEt1PERATURE AND RCS PRESSURE UNTIL RCS IS COOLED T0 r

s 420 F, WHEN LEVEL CONTROL tiAY BE ESTABLISl[ED.

4.2.1 Open SW supply valves to EFW suction and select "SW" position on both P-7A and P-7B suction select switches.

4.2.2 Verify both EFW block and bypass valves to each OTSG open.

NOTE If RCS leakage is greater than normal makeup capacity, refer to 1903.10 to determine EAL.

p 4.3 tionitor RCS pressures and temperatures; maintain at least 50 F margin to saturation by holding RCS pressure near the minimum allowable pressure within the cooldown pressure-temperature curve (Figure 2 if RCP's are operating, Figure 3 if no RCP's are operating).

NOTE If margin to saturation is less than 20 F for greater than 5 minutes, refer to 1903.10 to determine EAL.

4.4 Open the ERV and its block valve (if closed) under either of the following circumstances:

4.4.1 No RCP's are operating.

4.4.2.

RCS re pressurizes (indicating HPI flows are insufficient for core cooling)

NOTE If ES actuation occurs before llPI can be manually established and the RCS pressure recovers, do not reset ES analog channels, as this would delay restart of actuated c<1uipment in the event of a loss of of f-site power as pressure would have to fall again to actuation setpoint.

NOTE If ESAS actuates automatically, refer to 1903.10 to determine EAL.

4.5 If, at any time during the ensueing steps, emergency feedwater is made available, proceed as follows to restore OTSG levels.

4.5.1 Close atmospheric dumps and turbine bypasses.

4.5.2 Close all EFW block and bypass valves by placing Auto /tlanual sele-ctor switches in "banual, then close the block and bypass valves.

8205250179 920505 PDR ADOCK 05000313 i

p PDR l

E PLANT M ANUAL SECTION:

PROCEDURE / WORK PLAN TITLE:

NO:

EMERGENCY OPERATING LOSS OF COOLANT /RC PRESSURE 1202.06 O

PAGE 12 of 25 ARKANSAS NUCLEAR ONE WsiDN tioATE 1o/2o/81 CHANGE DATE 4.0 FOLLOW-UP ACTIONS:

NO F.W. AVAILABLE 4.1 If RCP's are operating, stop all but 1 RCP per loop.

4.2 Manually open turbine bypasses if condenser is under vacuum, otherwise, open the atmospheric dump valves to allow feed from a condensate pump (if one is available, even though the auxiliary FW pump is not).

If no condensate pump is available for OTSG feed, fully open dump or bypass valves and align SW feed to the OTSG's through the idle EFW pumps as foliows:

CAUTION IF ONLY A CONDENSATE PUMP IS AVAILABLE, CLOSE LO-LOAD VALVES AND MODU-LATE SU VALVES TO FEED SLOWLY, MONITORING RCS TEMPERATURE AND PRESSURE; FEED TO CONTROL TEMPERATURE AND RCS PRESSURE UNTIL RCS IS COOLED TO 420 F, WiiEN LEVEL CONTROL MAY BE ESTABLISIIED.

N 4.2.1 Open SW supply valves to EFW suction and select "SW" position on both P-7A and P-7B suction select switches.

4.2.2 Verify both EFW block and bypass valves to each OTSG open.

NOTE If RCS leakage is greater than normal makeup capacity, refer to 1903.10 to determine EAL.

/"'N 4.3 Monitor RCS pressures and temperatures; maintain at least 50 F margin to saturation by holding RCS pressure near the minimum allowable pressure within the cooldown pressure-temperature curve (Figure 2 if RCP's are operating, Figure 3 if no RCP's are operating).

NOTE If margin to saturation is less than 20 F for greater than 5 minutes, refer to 1903.10 to determine EAL.

4.4 Open the ERV and its block valve (if closed) under either of the following circumstances:

4.4.1 No RCP's are operating.

4. 4. 2.

RCS re pressurizes (indicating IIPI flows are insufficient for core cooling)

NOTE If ES actuation occurs before llPI can be manually established and the RCS pressure recovers, do not reset ES analog channels, as this would delay restart of actuated equipment in the event of a loss of off-site power as pressure would have to fall again to actuation setpoint.

NOTE If ESAS actuates automatically, refer to 1903.10 to determine EAL.

4.5 If, at any time during the ensucing steps, emergency feedwater is made available, proceed as follows to restore OTSG levels.

4.5.1 Close atmospheric dumps and turbine bypasses.

O 4.5.2 Close all EFW block and bypass valves by placing Auto / Manual sel-ctor switches in " Manual, then close the block and bypass valves.

PLANT M ANU AL SECTION:

PROCEDUREN/ORK PLAN TITLE-NO:

EMERCENCY OPERATING LOSS OF COOLANT /RC PRESSURE 1202.06 PAGE 13 of 25 P

ARKANSAS NUCLEAR ONE aevision icoATE 6/18/81 CHANGE DATE 4.5.3 Select " Condensate" position on EFW pump suction selectors (if CST is available, otherwise, remain on SW feed) for both P-7A and P-7B.

4.5.4 Start P-7A or P-7B; slowly open EFW bypass valves while monitoring RCS pressure and temperature, feeding slowly to prevent gross cooldown.

4.5.5 Establish OTSG 1evels between 90% and 95% operate range if RCP's are not operating, or > 22" S.U.

range if RCP's are running with EFW bypasses and control OTSG pressure and RCS cooldown with atmospheric dumps or turbine bypasses.

NOTE Refer to 1102.10 for cooldown with RCP's running.

Refer to 1203.13 (Natural Circulation Cooldown) if no RCP's are run-ning.

4.5.6 If RCP's are running, attempt to close the ERV and allow system pressure to stabilize, then proceed to section 3.0 of this procedure for all further action.

• 5 4.5.7 If RCP's are not available, proceed to section 5.0 of this procedure for all further action.

4.6 Continue maximum IIPI flow for cooldown without EFW until RCS is >50 F subcooled.

4.7 Monitor RB pressure; if pressure reaches 4 psig, verify reactor building isolation and cooling actuation (E.S. channels 5 & 6) and llPI and LP1 actuation (channels 1, 2, 3 & 4).

NOTE As a back-up or in case of an exceptionally high containment pressure, additional wide range (0 to 210 PSIA) instrumenta-tion is installed. Two safety grade indicators (PI-2412 &

PI-2413) and a non-safety grade wide range pressure re-corder (PR-2412) are located on control panels C-486-1 &

C-486-2.

NOTE Proper ES actuation is verified by noting that the colors of components' indicating lamps on the ES panels C-16, C-18, and on C-26 correspond to the color of the switch nameplate.

Proper flow ranges for IIPI and LPI are marked on the meter faces.

Proper Penetration Room ventilation is verified by f~h noting all room isolation damper lamps out, flow indicated, and negative Penetration Room pressure indicated.

PLANT M ANU AL SECTION:

PROCEDUREN!ORX PLAN TlVtE:

NO:

EMEFGENCY j

OPERATING LOSS OF COOLANT /RC PRESSURE 1202.06 P

d PAGE 14 of 25 ARKANSAS NUCLEAR ONE aEviSiON 10o^tE 4/is/81 CHANGE DATE Verify both emergency diesels autostart and their SW supply MOV'r open. Over-ride (using E.S. manual over-ride pushbuttons) and re-open the following valves to allow continued RCP and instrument air system operation:

4.7.1 Nuclear loop ICW RB isolation valves CV-2233, CV-2215 and CV-2214.

4.7.2 Non-nuclear loop ICW valves CV-2235, CV-2234, CV-2221 and CV-2220.

4.7.3 SW supply valves to the-ICW heat exchangers CV-3811 and CV-3820.

4.7.4 Verify two ICW pumps and a control rod drive booster pump running and ICW flows indicated for both loops.

4.8 Prepare for LPI boost to MU pump suction and RB sump recire as follows:

4.8.1 Vetify MU tank outlet MU-13 closed.

4.8.2 0 pen DH-7A and DH-7B, LPI discharge to MU pumps suction, verify MU pump suction crossover valves MU-14, MU-15, MU-16, and MU-17 open, and verify MU pump discharge crossover valv s

[~\\

MU-23, MU-24, MU-25, and MU-26 open.

4.8.3 Isolate the DH rooms by cleeing both DH room floor drain valves, ABS-13 and ABS-14, securing room purge dampers CV-7621, CV-7622, CV-7637, and CV-7638 from ventilation control panel (east wall of 404' Ventilat. ion Room) and closing watertight doors.

4.8.4 Verify both DH pumps operating and both LPI Mov's open (CV-1400 and CV-1401).

4.9 Once a 50 F margin to saturation is attained, continue HPI cooldown without purposefully depressnrizing the RCS until operation is within the pressure / temperature cooldown curve limits (Figure 2 of this procedure).

Continue with plant cooldown and depressurize by throttling HPI P3V's af ter achieving operation with the p res su re/ t empe*:a ture curve limits while holding >50 F margin to saturation.

flot cooldown rate and pressure / temperature relationship as required by 1102.10, Attachment B.

CAUTION DO NOT DECREASE MAKEUP PUMP FLOW RATE BELOW 50 GPM WITH THE RECIRC VALVES (CV-1300 AND CV-1301) CLOSED. STOP THE ES STANDBi MAKEUP PUMP IF NECESSARY TO PREVENT GOING SOLID IN THE PRESSURIZER (MUST BE >50 SUBC00 LED).

PLANT M ANU AL SECTION:

PROCEDURE /WORR PLAN TITLE:

NO:

Et!ERGENCY 2I *M OPERATING LOSS OF COOLANT /RC PRESSURE 1202.06 d

l, k 4

PAGE 15 of 25 D.

F'E ARKANSAS NUCLEAR ONE aavision 9 oaTE 1/i7/8i CHANGE DATE CAUTION HPI components are not to be over-ridden unless the following criteria are met:

1) The HPI system has been in operation for 20 minutes, and all hot and cold leg temperatures are at least 50"F below saturation temperature for the existing RCS pressure, or

2) The RCS is > 50 F subcooled, and throttling of HPI is necessary to prevent going solid in the pressurizer (with no break detected in p,zr. steam space),

or

3) The RCS is > 50 F subcooled, and HP1 throttling is necessary to remain within the plant cooldown pressure / temperature curve limits, or

4) D.ll. or LPI has been operating for > 20 minutes with flow rates of > 2650 gpm per train, or > 3100 gpm with one train operating.

gIf margin to saturation drops below 50 F after HPI override, re-initiate maximum HPI until > 50 F subcooled.

(Refer to r

figure 1.)

UNDER NO CIRCl'MSTANCES IS HPI TO BE OVER-RIDDEN IF RCS IS

,NOT SUBC00 LED.

4.10 Monitor BWST level; when BWST level has fallen to N6' indicated level, or when the corresponding BWST lo-lo-level alarm is re-ceived, verify suf ficient water inventory via the RB sump (Refer to sump level indicator LI-1405 & Rx Bldg. Level indicators LI-5645 &

LI-5646) and transfer suction to RB sump by verifying RB sump suc-tion valves inside containment CV-1414 and CV-1415 open, opening RB sump suction valves outside containment CV-1405 and CV-1406 (a slight upward perturbation should be noted on pump flows indicat-ing suction transfer); then close both BWST outlets CV-1407 and CV-1408 (Refer to 1104.04 for RCS temperature control methods).

Close NaOH tank outlets CV-1616 and CV-1617. MANUAL OVERRIDE PUSilBUTTONS MUST BE DEPRESSED FOR ALL VALVE MANIPULATIONS IF ES ACTUATION HAS OCCURRED. Monitor the RB water level indicators LI-5645,and LI-5646 during the entire recirculation phase.

4.11 When RCS pressure is reduced to s600 psig, continue slow depressurization (control discussed in step 4.9) and allow CFT's to discharge.

Monitor HPI flows closely; maintain

> 100 gpm per pump.

~

PLANT MANUAL SECVION:

PROCEDUREMORK PLAN TITLE:

NO-p 9

Et1ERGENCY bi k OPEPATING LOSS OF COOLANT /RC PRESSURE 12n2.06 Ll i

PAGE 16 of 25 hG ARKANSAS NUCLEAR ONE aEvisioN 9 oArE 3/i7/si CHANGE DATE 4.12 Initiate R.B. If s mPling per section 9.0 of OP 1104.33.

2 4.13 When IIPI flow is approaching 100 gpm per loop, stop 1 IIPI pump and align for ffU and purification as follows:

4.13.1 Close LPI boost to secured HPI pump (Dif-7A or Dil-7B).

4.13.2 Close suction cross-connect valve (ttU-14 or ffU-15 for B to C) or (tfU-16 or ?!U-17 for A to B) isolating the running IIPI pump from the MU tank.

4.13.1 Close running IIPI pump' manual recirculation valve (ffU-21A, B or C).

4.13.4 Open t!U-13 (FIU tank outlet).

4.13.5 Over-ride ES signal and open CV-1300 and CV-1301.

4.13.6 Over-ride ES signal and open CV-1214, CV-1216 and CV-1221.

4.13.7 Verify ICW available and establish letdown, p

4.13.8 Verify ?!U tank level > 40" and start tfU pump which was aligned for t!U & P.

4.13.9 Stop IIPI pump whose suction is aligned to LPI pump discharge.

4.13.10 t!odulate makeup and letdown to control press / temp.

If > 50 F

, margin to saturation cannot be maintained, restart HPI pump.

4.13.11 Stop the DH pump (which is not aligned for boost for HPI pump) and align its manual valves for normal decay heat mode per 1104.04.

NOTE If only one LPI pump is operating, initiate repairing on the failed pump and align it for D.H. operation af ter repairs; meanwhile, continue IIPI/LPI cooling.

4.13.12 Continue HPI/LPI cooldown to within limits of decay heat system.

4.13.13 Place decay heat system in service and stop IIPI pump (if running) and its associated (booster) decay heat pump.

I-l

PLANT M ANUAL SECTION:

PROCEDURUWORK PLAN TITLE:

NO:

FMFRGFNrV OPERATTNG T OSS OF C00I. ANT /RC PRESSURE 1: 02.06 P

_PAGE 17 of 25 ARKANSAS NUCLEAR ONE

. n svisiON iloat=0/26/8i CHANGE DATE 4.14 Select " Manual" and close all emergency FW feed valves and bypass valves; close all steam supply M0V's to P-7A to secure emergency feed.

4.15 Close main FW isolation valves.

4.16 Close MS isolation valves (if not previously closed by SLBIC) whenever OTSG'r are dry.

5.0 FOLLOW-U'P ACTION - No Reactor Coolant Pumps 5.1 Initiate manual EFW feed to OTSG's and slowly increase levels to between 90% and 95% on cperate range. Attempt to maintain a continuous feed rate while raising levels.

NOTE If RCS leakage is greater than normal makeup capacity, refer to 1903.10 to determine EAL.

NOTE If ES actuation occurs before HPI can be manually established and the RCS pressure recovers, do not reset ES analog channels, as this would delay restart of actuated equipment in the event of a loss of off-site power as pressure would have to fall again to actuation setpoint.

NOTE If ESAS actuates automatically, refer to 1903.10 to determine EAL.

I 5.2 Monitor RCS pressures and temperatures; maintain at least 50 F margiu to saturation by holding RCS pressure within the cooldown pressure-tempera-ture curve (Figure 3) if possible.

NOTE As a back-up or in case of an exceptionally high containment pressure, additional wide range (0 to 210 PSIA) instrumentation is installed.

Two safety grade indicators (PI-2412 & PI-2413) and a non-safety grade wide range pressure recorder (PR-2412) are located on control panels C-486-1 & C-486-2.

5.3 Monitor RB pressure; if pressure reaches 4 psig, verify reactor building isolation and cooling actuation (E.S. channels 5 & 6 and IIPI & LPI actua-tion-(channels 1, 2, 3 & 4).

NOTE Proper ES actuation is verified by noting that the colors of components' indicating lamps on the ES panels C-16, C-18 and on C-26 correspond to the color of the switch nameplate.

Proper flow ranges for llPI & LPI are marked on the meter faces.

Pt,per Penetration Room ventilation is verified by noting all room isolation damper lamps out, flow indicated and negative Penetration Room pressure indicated.

+

PLANT M ANUAL SECTION:

PROCEDURE /WORX PLAN TITLE:

NO:

FFfERCENCY OPERATING LOSS OF COOLANT /RC PPESSURE 1: 02.06

_PAGE 17 of 25 P

ARKANSAS NUCLEAR ONE REvisio N 11 oATa 0/26/ai CHANGE DATE 4.14 Select " Manual" and close all emergency FW feed valves and bypass valves; close all steam supply MOV's to P-7A to secure emergency feed.

4.15 Close main FW isolation valves.

4.16 Close MS isolation valves (if not previously closed by SLBIC) whenever OTSG's are dry.

5.0 FOLLOW-UP ACTION - No Reactor Coolant Pumps 5.1 Initiate manual EFW feed to OTSG's and slowly increase levels to between 90% and 95% on operate range. Attempt to maintain a continuous feed rate while raising levels.

NOTE If RCS leakage is greater than normal makeup capacity, refer to 1903.10 to determine EAL.

NOTE If ES actuation occurs before HPI can be manually established and the RCS pressure recovers, do not reset ES analog channels, as thic would delay restart of actuated equipment in the event of a loss of off-site power as pressure would have to fall again to actuation setpoint.

NOTE If ESAS actuates automatically, refer to 1903.10 to determine EAL.

I 5.2 Monitor RCS pressures and temperatures; m'intain at least 50 F margin to saturation by holding RCS pressure within the cooldown pressure-tempera-ture curve (Figure 3) if possible.

NOTE As a back-up or in case of an exceptionally high containment pressure, additional wide range (0 to 210 PSIA) instrumentation is installed.

Two safety grade indicators (PI-2412 & PI-2413) and a non-safety grade wide range pressure recorder (PR-2412) are located on control panels C-486-1 & C-486-2.

5.3 Monitor RB pressure; if pressure reaches 4 psig, verify reactor building isolation and cooling actuation (E.S. channels 5 & 6 and IIPI & LPI actua-tion (channels 1, 2, 3 & 4).

NOTE Proper ES actuation is verified by noting that the colors of components' indicating lamps on the ES panels C-16, C-18 and on C-26 correspond to the color of the switch nameplate.

Proper flow ranges for llPI & LPI are marked on the meter faces.

Proper Penetration Room ventilation is verified by noting all room isolation damper lamps out, flow indicated and negative Penetration Room pressure indicated.

b w

PLANT MANUAL SECTION:

PROCEDUREiWORK PLAN TITLE:

. =)

NO:

/

l EMERG. OPEP.ATING LOSS OF C00i. ANT /RC PRESSURE 1202.06 n

PAGE Wh

~4 Ot 93 7

ARKANSAS NUCLEAR ONE nevisio" 9

oAie 3/16/81 mM CHANGE DATE I

n 7

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