Text

Emergency Operating Procedure, Loss of Reactor Coolant, Vol 5,Revision 0
	ML19318D233
Person / Time
Site:	Farley
Issue date:	05/14/1980
From:	; ALABAMA POWER CO.
To:	;
Shared Package
ML19318D229	List: ML19318D228; ML19318D231; ML19318D233; ML19318D237; ML19318D240; ML19318D246;
References
	FNP-2-EOP-1.0, NUDOCS 8007080232
	Download: ML19318D233 (42)
	v • d • e

VOLUME 5 FNP-2-EOP-1.0 O

May 14, 1980 Revision 0 FARLEY NUCLEAR PLANT EMERGENCY OPERATING-PROCEDURE FNP-2-EOP-1.0 S

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LOSS OF REACTOR COOLANT R

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UNCONTii0LLED COPY CAUTION: m Approved:

maintained Current. Do not use i Safety Related Activity.

h Operations Superint ent Date Issued:

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Diskette EOP-3 i

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VOLUME 5 LIST OF EFFECTIVE PAGES ENP-2-EOP-1.0 REVISION NO. 0 PACE NO.

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VOLUME 5 LIST OF EHECTIVE PAGES FNP-2-EOP-1.0 REVISION NO. O PAGE N6.

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VOLUME 5 FNP-2-EOP-1.0 UNIT 2 EMERGENCY OPERATING PROCEDURE EO'P-1.0'~~

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LOSS OF REACTOR COOLANT l.0 Purpose The purpose of this procedure is to describe the

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required actions following a loss of reactor coofant of such magnitude that maximum charging flow and

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reactor coolant pump seal injection flow cihnot militaih'-

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pressurizer level.

The objectives of these actions ~

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re as follows:

a 1.1 Provide immedirte core cooling hid' shut'down

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reactivity.

l.2 Maintain long term shutdown and core _ cool _ing._

1.3 Minimize radioactivity released to the, environment _.

_l 2.0 Symotoms Refer to Section=2.1 of FNP-2-EOP-0.

2.0 Autcmatic Actions Refer to Section 3.1 of FNP-2-EOP-0.

4.0 Immediate Operator Actions Refer to Section 4.0 of FNP-2-EOP-0.

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5.0 Subsequent Operator Actions j

CAUTION No single plant parameter should be relied upon for

-evaluating the plant status under accid ~ent conditions'.

NOTE

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---The process variables referred to in this procedure" are typically monitored by more than one instrumentation

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channel.

The redundant channels should"be checked ~for--

consistency while performing the steps of this procedure.

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5.1 Actuate the PLANT EMERGENCY ALARM and announce over the public address system the"fo-llowingT-~

ALL PERSONNEL REPORT TO YOUR DESIGNATED ASSEMBLY AREAS.

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1 Rev. 0

VOLUME S ENP-2-EOP-1.0 5.2 Monitor the following:

RCS pressure pressurizer level wide range RCS temperature BIT flow steam generator pressure steam generator water level auxiliary feedwater flow to steam generators CTMT pressure accumulator levels RER flow RWST level CTMT spray flow spray additive tank flow Margin to Saturation (PSIA)

I to assess the nature and severity of the accident and' tb verify proper operation of safety systems.

CAUTION l

System pressure, containment temperature and post-accident radiation levels all affect the accuracy of level indicating instruments inside containment.

Steam generator level should not be f-used as sole indication of adequate level in the S/G to provide a heat sink nor should pressurizer level be used as sole indication of proper pressu-rizer level.

Parameters such as AUXILIARY FEED-WATER FLOW, STEAM PRESSURE, RCS PRESSURE, response of RCS PRESSURE to pressurizer heater operation, and RCS WIDE RANGE T and T should also be The min b and maximum allowed e

evaluated.

levels necessary to ensure that actual level is between the instrument's lower tap and upper tap

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are shown for various pressures, containment temperature conditions and accident conditions in tables 2-5.

NOTE The pressurizer water level indication should always be used in conjunction with other reactor coolant system indications to evaluate system response and to initiate manual operator actions.

5.3 If any ESF acutating parameters exceed their actuation setpoint without acutation, manually initiate that ESF system.

5.4 Stop ALL Reactor Coolant Pumps after the high head safety injection pump operation has been verified and when the wide range reactor coolant pressure decreases to 1300 psig.

2 Rev. 0

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VOLUME 5 FNP-2-EOP-1.0 5.5 If CTMT Phase B Isolation occurs, all Reactor Coolant Pumps should be stopped within 5 minutas because of loss of motor bearing cooling.

NOTE If reactor coolant pumps are tripped in steps 5.4 or 5.5, frequently monitor WR RCS hot leg temperature, WR RCS cold leg temperature, and incere thermoccuples to verify circulation and core cooling as indicated by:

The AT between WR RCS hot leg and cold leg ~<

64*F in the unaffected loops, or J

Incore thermocouples at or near RCS WR hot leg temperature in the unaffected loops and decreasing.

If these conditions do not exist, maintain Auxiliary Feedwater flow rate and increase steam dump rate to enhance the establishment of natural circulation.

p The above conditions may be continuously monitored r

by use of the AT function on the core Subcooling Monitoring Panel.

5.6 Momentarily place both containment purge isolation handswitches to the close position (HS 3198 and HS 3196).

5.7 If a SMALL pipe break is evident as indicated by stable or increasing pressurizer pressure and pressure above saturation conditions in Table 1, Colume II, and increasing pressurizer level, proceed to step 6.0.

5.8 Initiate EIP-9, Radiation Exposure Estimation and Classification of Emergencies.

5.9 If RCS pressure appears to be stabilizing at 1000 psig or above within 2 or 3 minutes after safety injection actuation, initiate the followin, action.

If pressure does not appear to be stabilizing, proceed to step 5.10.

5.9.1 If the main condenser is available and the main steam isolation valves are open, transfer the steam dump to steam pressure control mode And dump steam to maximize ~ core cooling.

3 Rev. 0

VOLUME 5 FNP-2-EOP-1.0 l

5.9.2 If the main condenser is not available, or the main steam isolation valves are closed, dump steam to the atmosphere with atmospheric relief valves to maximize core cooling.

CAUTION Coordinate the dumping of steam and the addition of Auxiliary Feedwater to establish a maximum cooldown rate within limits specified in Technical Specifications.

4 5.10 If the RER pumps run for 15 minutes without flow indication on FI-605A or FI-605B and RCS pressure is greater than 130 psig, open CCW to RER Ex 2A and 2B valves 2-CCW-MOV-3185A and B.

5.11 On receipt of the RWST low level alarm (150,000 gal), RESET the SAFETY INJECTION and CTMT PHASE A ISOLATION signals.

Verify that CTMT sump level has increased.

Initiate COLD LEG RECIRCULATION as follows: '

CAUTION b

Do'not reset the Safety Injection signals'on the containment sump to RHR valves or the diesel generator sequencers.

CAUTION Do not' reopen the CTMT sump pump or the RCDT pump discharge CTMT isolation valves unless the effects of pumping high activity water from the i

CTMT have been analyzed.

CAUTION i

Automatic reinitiation of safety injection will not occur since the reactor trip breakers are not reset.

5.11.1 Stop RER pumps 2A and 2B.

NOTE Steps 5.11.2, 5.11.8, 5.11.12 and 5.13 assume that 2A and 2C charging pumps are both operable.

If either of these two pumps is inoperable, these steps should be modified to achieve operation of two separate trains (e.g.43.f 2C is inoperable, then step 5.11.2 would not be performed;

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4 Rev. 0 l

VOLUME 5 FNP-2-EOP-1.0 charging pump suction header isolation valves 2-CVC-MOV-8131A and B would not be closed; and charging pump discharge header isolation. valves 2-CVC-MOV-8133A and B would not be closed.)

5.11.2 Stop 2B charging pump.

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5.11.3 Open CCW to RER Ex 2A and 2B valves 2-CCW-MOV-31SSA and B.

5.11.4 Close RWST to RER pump 2A and 2B valves 2-RER-MOV-8809A and B.

5.11.5 Open CTMT sump to RER pump 2A and 2B valves 2-RHR-MOV-8811A and B; 2-RHR-MOV-8812A and B.

5.11.6 Close RHR to RCS hot legs xconn valves 2-RHR-MOV-8887A and B.

5.11.7 Start RER pumps 2A and 23.

5.11.8 Close charging pump suction header isolation valves 2-CVC-MOV-8130A and B; 2-CVC-MOV-8131A and B.

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5.11.9 Open RHR Ex 2A and 2B to charging pump suction valves 2-CVC-MOV-8706A and B.

5.11.10 Close RWST to charging pump header valves 2-CVC-MOV-115B and D.

5.11.11 Open charging pump recirc to RCS cold legs valve 2-CVC-MOV-8885.

S.11.12 Unlock and close FUJ2 and FVJ2, then close charging pump discharge header isolation valves 2-CVC-MOV-8132A and B; 2-CVC-MOV-8133A and B.

5.12 If CTMT SPRAY was initiated, perform the following:

5.12.1 RESET CTMT SPRAY signal.

5.12.2 When the spray additive tank level indicates less than 10%, close spray additive outlet valves 2-CS-MOV-8836A and B.

5.12.3 On receipt of the RWST low-low alarm (50,000 pl), transfen CTMT SPRAY to the sump recirculation mode as follows:

5 Rev. 0

VOLUME 5 FNP-2-EOP-1.0 5.12.3.1 Open CS pump 1A and 1B CTMT sump suction isolation valves 2-CS-MOV-8826A and B; 2-CS-MOV-i 8827A and B.

5.12.3.2 Close CS pump 2A and 2B RWST sitction isolation valves 2-CS-MOV-8817A and B.

5.13 Verify the following for cold leg recirculation:

COMPONENT CONDITION REQUIRED

CHG Pump 2B OFF 2-CCW-MOV-3185A & B OPEN 2-RHR-MOV-8809A & B CLOSED 2-RER-MOV-8811A & B OPEN 2-RHR-MOV-8812A & B OPEN 2-RHR-MOV-8887A & B CLOSED i

RER Pump 2A & 2B ON

2-CVC-MOV-8130A & B CLOSED

2-CVC-MOV-8131A & B CLOSED 2-CVC-MOV-8706A & B OPEN 2-CVC-MOV-115B & D CLOSED 2-CVC-MOV-8885 OPEN

2-CVC-MOV-8132A & B CLOSED I-s

2-CVC-MOV-8133A & B CLOSED e

Assumes 2A and 2C charging pumps operable.

See NOTE in step 5.11.2.

5.14 Establish manual control of Auxiliary Feedwater flow and maintain steam generator levels as follows:

5.14.1 Stop the TDAFW pump.

5.14.2 Operate the MDAFW pumps as required to.

maintain steam generators above the no-load level (33%) and below upper indication (100%).

If narrow range water level increases in an unexplained manner in one steam generator, go to FNP-2-EOP-3.0, Steam Generator Tube Rupture.

NOTE Monitor the Condensate Storage Tank level.

If the condensate Storage Tank level decreases to four (4) feet, and auxiliary feedwater is. required by plant conditions, shift the ^ auxiliary feedwater pumps. suction to the Service Water System per FNP-2-SOP-22.0, Section 4.7.

6 Rev. O

VOLUME 5 FNP-2-EOP-1.0 5.15 Align the PRF ventilation system to the LOCA mode by closing FBV to PRV dampers 2-FBV-HV-3538A and B.

5.16 If off-site power is reliable as verified by the availability of two independent off-site sources, then shutdown'the diesel generators and align for automatic operation per SOP-38.0.

5.17 Periodically check auxiliary building area radiation monitors for detection of leakage during Cold Leg / Hot Leg Recirculation.

If significant leakage has been identified, attempt to isolate the leakage.

However, Recirculation flow to the RCS must be maintained at all times.

5.18 within one hour from the time of the accident, perforzr, the following:

5.18.1 Sample the RCS as per FNP-0-EIP-25.

5.18.2 Place both hydrogen recombiners in service as follows:

NOTE b

This instruction places one hydrogen reccabiner in service.

Place the second hydrogen recombiner in service by repeating steps 5.18.2.1 through 5.18.2.8.

5.18.2.1 Verify that the white light "PWR. IN AVAIL" is ON.

5.18.2.2 Set "PWR. ADJ." potentiometer at zero (000).

1 5.18.2.3 Turn "PWR. OUT SW." to the ON position.

Verify that the red pilot light is ON.

5.18.2.4 Obtain CTMT pressure from Pressure Indicator PI 950 or 952.

Obtain the pre-LOCA CTMT temperature ar d pressure.

5.18.2.5 Determine pressure factor (Cp) from Recombiner Power Correction Factor vs. Containment Pressure Curve, Figure 2.

A 7

Rev. 0 l

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VOLUME 5 FNP-2-EOP-1.0 i

1 5.18.2.6 Multiply reference power (obtain from the latest recombiner heat up and air flow surveillance j

test, STP-19.2) by pressure factor (Cp) to determine the calculated power output setting.

5.18.2.7 Slowly turn "PWR. ADJ." potentio-

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meter in the clock-wise direction until the "PWR OUT" meter indicates the calculated power output setting.

5.18.2.8 Monitor the following Hydrogen Recombiner Control Panel indicators to verify proper operation.

5.18.2.8.1 "PWR OUT" meter continues to indicate the calculated power output setting or the last adjusted power output.

IT 5.18.2.8.2

" TEMP. OUT*: meter indicates a normal recombiner output temperature of 0

1150 to 1400 F.

5.18.3 Sample CTMT atmosphere and determine the volumetric hydrogen concentration (C) per SOP-10.0, section 4.5.

Plot hydrogen concentration (C) on the Post LOCA Containment Hydrogen Concentration Graph, Figure 3.

5.19 Sample the recirculated coolant for boron concen-tration and pH every 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

The following limits should be maintained:

pH - 8.5 to 10.5 Boron Concentration - > cold shutdown value 5.20 Continue to recirculate the CTMT sump contents to the spray header for at least 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

5.21 Initiate EOT LEG RECIRCULATION approximately 20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months after COLD LEG RECIRCULATION was initiated

'as follows:

8 Rev. 0

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VOLUME 5 FNP-2-EOP-1.0 5.21.1 Unlock and close the following breakers:

Breaker No.

Description Location a.

FU-R2 Charging pump EL. 139' Pen. Rm.

recirc to RCS hot MCC-2U legs 2-CVC-MOV-8886 b.

FV-B2 RER to RCS hot EL. 139' Pen. Rm.

legs isolation MCC-2V 2-RER-MOV-8889 c.

FV-T2 Charging pump EL. 139' Pen. Rm.

recirc to RCS hot MCC-2V legs 2-CVC-MOV-8884 5.21.2 Close RER Ex to RCS cold legs isolation valves 2-RHR-MOV-8888A & B.

5.21.3 Open RER to RCS hot legs xconn valves 2-RHR-MOV-8887A & B.

5.21.4 Open RHR to RCS hot legs isolation valve i

2-RHR-MOV-8889.

S.21.5 Stop charging pump 2A.

5.21.6 Close boron injection tank.utlet valves i

2-CVC-MOV-8801 A and B.

5.21.7 Close boron injection tank inlet isolation valves 2-CVC-MOV-8803A and B.

5.21.8 Open charging pump recirc to hot legs valve 2-CVC-MOV-8886.

5.21.9 Start charging pump 2A.

5.21.10 Stop charging pump 2C.

5.21.11 Close charging pump recirc to RCS cold legs valve 2-cVC-MOV-8885.

5.21.12 Open charging pump recirc to RCS hot legs valve 2-CVC-MOV-8884.

5.21.13 Start charging pump 2C.

A 9

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VOLUME 5 FNP-2-EOP-1.0 5.22 Verify the following for hot leg recirculacion:

COMPONENT CONDITION REQUIRED 2-RER-MOV-8888A & B CLOSED 2-RER-MOV-8887A & B

OPEN 2-RER-MOV-8889 OPEN 2-CVC-MOV-8801A & B CLOSED j

2-CVC-MOV-8803A & B CLOSED l

2-CVC-MOV-8886 OPEN 2-CVC-MOV-8885 CLOSED 2-CVC-MOV-8884 OPEN

CHG Pump 2A ON

CHG Pump 2C ON

Assumes 2A and 2C charging pumps operable.

See NOTE in step 5.11.2.

5.23 Approximately 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after placing the hydrogen recombiners in service and at least once every 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , perform the following:

5.23.1 Sample CTMT atmosphere and determine the volumetric hydrogen concentration (C) per SOP-10.0, section 4.5.

Plot hydrogen concentration (C) on the Post LOCA Iu.

Containment Hydrogen Concentration Graph, Figure 3.

5.23.2 If hydrogen concentration had decreased or remained constant during the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period, adjust recombiner 2A and 2B power, repeating steps 5.18.4 thru 5.18.8.

5.23.3 If hydrogen concentration has increased by greater than 0.4 volume percent during the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period or if CTMT concentration exceeds 3.5 percent, increase recombiner power setting by 4 KW above previous setting.

5.24 If hydrogen concentration exceeds 3.0 volume i

percent, consider (and evaluate the effects of) placing the Post LOCA Containment Pressurization and Vent System in service per SOP-10.0.

5.25 Approximately 24 hrs. after initiating HOT LEG RECIRCULATION establish COLD LEG RECIRCULATION as follows:

5.25.1 Close RHR to RCS hot 14gs xconn valves 2-RHR-MOV-8887A and B.

10 Rev. 0

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VOLUME 5 FNP-2-EOP-1.0 5.25.2 Open RER to RCS cold legs isolation valve 2-RER-MOV-8888A and B.

5.25.3 Close RHR to RCS hot legs isolation ~'- ~-

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valve 2-RER-MOV-8889.

5.25.4 Stop charging pump 2A.

5.25.5 Close charging pump recirc to RCS hot legs 2-CVC-MOV-8886.

5.25.6 Open baron injection tank outlet valves 2-CVC-MOV-8801A and B.

5.25.7 Open boron injection tank inlet valves 2-CVC-MOV-8803A and B.

5.25.8 Start charging pump 2A.

S.25.9 Stop charging pump 2C.

5.25.10 Close charging pump recirc to RCS hot legs 2-CVC-MOV-8884.

5.25.11 Open chargiiig pump recirc to RCS cold legs 2-CVC-MOV-8885.

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5.25.12 Start charging pump 2C.

5.25.13 verify the following for cold leg recir-culation:

COMPONENT CONDITION REQUIRED 2-RER-MOV-8887A & B CLOSED 2-RHR-MOV-8888A & B OPEN 2-RER-MOV-8889 CLOSED 2-CVC-MOV-8886 CLOSED 2-CVC-MOV-8801A & B OPEN 2-CVC-MOV-8803A & B OPEN 2-CVC-MOV-8884 CLOSED 2-CVC-MOV-8885 OPEN

CHG Pump 2A ON

CHG Pump 2C ON

Assumes 2A and 2C charging pumps are operable.

1 See NOTE in step 5.11.2.

5.26 Approximately 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after initiating COLD LEG RECIRCULATION establish HOT LEG RECIRCULATION as follows:

5.26.1 Close RER to RCS cold degs isolation valves 2-RHR-MOV-8888A and B.

11 Rev. O

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VOLUME 5 FNP-2-EOP-1.0 5.26.2 Open RER to RCS hot legs xconn valves 2-IER-MOV-8887A and B.

5.26.3 Open RER to RCS hot legs isolation valve 2-RHR-MOV-8889.

5.26.4 Stop charging pump 2A.

s 5.26.5 Close boron injection tank outlet valves 2-CVC-MOV-8801A and B.

5.26.6 Close boron injection tank inlet valves 2-CVC-MOV-8803A and B.

5.26.7 Open charging pump recirc to RCS hot legs valve 2-CVC-MOV-8886.

5.26.8 Start charging pump 2A.

5.26.9 Stop charging pump 2C.

5.26.10 Close charging pump recirc to RCS cold legs valve 2-CVC-MOV-8885.

5.26.11 Open charging pump recirc to RCS hot legs valve 2-CVC-MOV-8884.

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5.26.12 Start charging pump 2C.

5.26.13 Verify the following for hot leg recircu-lation:

COMPONENT CONDITION REQUIRED 2-RHR-MOV-8888A & B CLOSED 2-RHR-MOV-8887A & B OPEN 2-RHR-MOV-8889 OPEN 2-CVC-MOV-8801A & B CLOSED 2-CVC-MOV-8803A & B CLOSED 2-CVC-MOV-8886 OPEN 2-CVC-MOV-8885 CLOSED 2-CVC-MOV-8884 OPEN

CHG Pump 2A ON

CHG Pump 2C ON

Assumes 2A and 2C charging pumps are operable.

See NOTE in step 5.11.2.

5.27 Alternate HOT and COLD LEG RECIRCULATION every 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by performing steps 5.25 or 5.26 as applicable.

A 12 Rev. 0

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VOLUME 5 FNP-2-EOP-1.0 6.0 Subsequent Operator Actions for a SMALL LOCA NOTE The. intent of this procedure is to achieve and maintain an equilibrium between injection flow'and break flow while maintaining RCS pressure above the saturation pressure for RCS wide range temperature, thus minimizing the potential for void formation which could impede

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cooling.

While it is highly desirable to achieve this condition without filling the pressurizer solid, it could be necessary, under some break conditions, to fill solid in order to maintain system pressure above saturation pressure.

If this occurs, extreme caution should be taken with respect to cooldown to prevent exceeding limitations on the reactor vessel.

6.1 Initiate EIP-9 Radiation Exposure Estimation and Classification of Emergencies 6.2 If plant conditions have stabilized as indicated by:

6.2.1 RCS pressure > 2000 psig and increasing and 6.2.2 Pressurizer level > 50%, and 6.2.3 RCS pressure greater than 50'F subcooled per Table 1, Column I or_ by subtracting RCS temperature from Saturation Temperature calculated by the Core Subcooling Monitor in the PSAT/TSAT mode and 6.2.4 Adequate heat sink available as indicated by a stable or increasing level in at least one steam generator in the narrow range span, or in the wide range span at a level sufficient to assure that the U-tubes are covered (54%).

Then RESET SAFETY INJECTION and CTMT PHASE A ISOLATION signals, and go to step 6.4.

CAUTION i

DO NOT reset the Safety Injection signals on the CTMT sump to RER suction valves or the diesel generator sequencers.

CAUTION A

Do not reopen the CTMT sump pump or the RCDT pump discharge CTMT isolation valves unless the effects of pumping high activity water from the CTMT have been analyzed.

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13 Rev. O I

VOLUME 5 FNP-2-EOP-1.0 CAUTION Automatic reinitiation of safety injection will not occur since the reactor trip breakers are

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not reset.

6.3 If the injection flow and breakflow equalize at a pressure greater than saturation conditions in Table 1, column II but.less than 2000 psig, perform step 7.0 thru 7.8.

6.4 Closely monitor RCS pressure and pressurizer level for evidence of additional pressure. boundary degredation.

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6.5 If the RER pumps run for 15 minutes without flow indication on FI-605A or FI-605B open CCW to RER Ex 2A and 2B valves 2-CCW-MOV-3185A and B.

6.6 Verify operation of the pressurizer heaters.

If an LOSP has occurred, re-establish pressurizer heater control per FNP-2-EOP-7.0, Section 5.3.

6.7 Stop one charging pump and observe RCS pressure and pressurizer level to ensure:

I" 6.7.1 RCS pressure does not decrease bdlow 1850 psig, and 6.7.2 Pressurizer level remains above 20%.

CAUTION If at any time during the performance of step 6.7 or there after (unless it is a controlled evolution) RCS pressure drops l

to 1850 psig or pressurizer level drops below 20%, or WR RCS hot leg temperature exceeds 602*F Then:

1 Manually initiate SAFETY INJECTION and restart the charging pump stopped in step 6.7, and go to stcp 5.7.

6.8 Establish letdown by:

6.8.1 Open letdown line CTMT isolation valve 2-CVC-HV-8152 and letdown line isolation valves 2-CVC-HV-459 and 2-CVC-HV-460.

Openletdownorificei$olationvalve i

6.8.2 2-CVC-HV-8149B(C).

14 Rev. 0

VOLUME 5 FNP-2-EOP-1.0

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6.9 Establish charging flow by:

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4.1 Open charging pumps to regenerative heat exchanper valves 2-CVC-MOV-8107 and 2-CVC-McV-8108.

6.9.2 Place charging flow control valve.2-CVC-FCV-122 in MANUAL and throttle as necessary to maintain pressurizer level between 25-50%.

6.9.3 If pressurizer level continues to rise:

6.9.3.1~

Open charging pump A, B and C miniflow valves 2-CVC-MOV-8109A, B and C and 2-CVC-MOV-8106.

6.9.3.2 Close BIT inlet valves 2-CVC-MOV-8803A and B.

6.10 Control Auxiliary Feedwater flow and dumping of steam to establish stable RCS temperature at or 0

below 547 F.

6.11 Compare WR.RCS hot leg, WR RCS cold leg temperature to incore thermocouple temperatures to verify k

circulation and core cooling as indicated by:

6.11.1 The AT between WR RCS hot leg and cold leg <_ 64*F, or 6.11.2 Incore thermocouples at or near RCS WR hot leg temperature and decreasing.

If these conditions do not exist, maintain Auxiliary Feedwater flow rate and increase steam dump rate to enhance the establishment of natural circulation.

The conditions listed above can be continuously monitored by use of the AT function on the Core Subcooling Monitoring Panel.

6.12 Open RCP seal water return isolation valves 2-CVC-MOV-8100 and 2-CVC-MOV-8112.

6.13 Perform a flow balance on the CVCS; monitor Pressurizer Relief Tank temperature, pressure and level; and monitor CTMT sump level and CTMT pressure to determine if the LOCA has been terminated.

A l

15 Rev. 0

VOLUME 5 FNP-2-EOP-1.0

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l 6.14 If the results of 6.13 indicate that the LOSS OF COOLANT has definitely been terminated.

Perform steps 6.14.1 through 6.14.9, otherwise go to step 6.15.

6.14.1 RESET the SAFETY INJECTION signal on the B2F and B2G sequencers.

6.14.2 RESET the SAFETY INJECTION signal for the Diesel Generators.

6.14.3 RESET the SAFETY INJECTION signal on the CTMT sump to RER suction valves.

6.14.4 Verify reliable sources of off-site power then shutdown the Diesel Generators and re-align for automatic operation per SOP-38.0.

6.14.5 Verify level in VCT greater than 15% and reactor makeup in automatic with blended flow set for the hot shutdown boron concentration.

6.14.'6 Open VCT outlet isolation valves 2-CVC-LCV-115C and E.

H.

6.14.7 Close RWST to charging pump headei-valves 2-CVC-LCV-115B and D.

6.14.8 Stop both RER pumps.

6.14.9 Return all ESF systems for Hot Shutdown operarions.

Refer to UOP for continued operation.

6.25 Within one hour from the time of the accident, perform the following:

6.15.1 Sample the RCS as per FNP-0-EIP-25.

6.15.2 Place both hydrogen recombiners in service per step 5.18 of this procedure.

6.15.3 Initiate CTMT hydrogen monitoring per steps 5.19, 5.24, and 5.25 of this procedure.

6.16 Establish long term cooldown as follows:

6.16.1 Isolate letdown by closing letdown orifice isolation valves 2-CVC-HV-8149A, B and C.

^

16 Rev. 0

VOLUME 5 FNP-2-EOP-1.0 6.16.2 Close RCP seal water return isolation valves 2-CVC-MOV-8100 and 2-CVC-MOV-8112.

6.16.3 Establish a controlled cooldown by dumping steam.

During.the cooldown closely monitor RCS pressure, RCS temperature' and pressurizer level.

Maintain at least 500F subcooling as indicated by Table I Column I.

6.16.4 Control RCS pressure using pressurizer heaters and sprays as necessary to maintain at least 500F subcooling (Table I Column I or by subtracting RCS temperature from Saturation Temperature calculated by the Core Subcooling Monitor in PSAT/TSAT i

mode) and NPSE for RCP as indicated by Figure I.

When > 50*F subcooling is verified, initiate a controlled RCS depressurization while maintaining >

50*F subcooling.

Ensure Tech. Spec.

Temperature / Pressure limitations are complied with.

l CAUTION F

If 50*F subcooling cannot be maintained, then manually reinitiate SAFETY INJECTION and go to Section 5.0 of FNP-2-EOP-0.

6.16.5 Control charging flow rate to maintain pressurizer level between 25% and 50%.

6.16.6 On receipt of the RWST low level alarm (150,000 gal), initiate MODIFIED COLD LEG RECIRCULATION by aligning Low Head Safety Injection to supply suction to the running charging pump by:

G.16.6.1 Stop RER pumps 2A and 2B.

6.16.6.2 Verify charging pump 2A or 2C rimni ng.

6.16.6.3 Verify open CCW to RER heat exchanger 2A or 2B valves 2-CCW-MOV-3185A or B.

6.16.6.4 Close RWST to RER pump 2A and 2B valves 2-RHR-MOV-8809A and B.

6.16.6.5 Open CTMT sump to RER pump 2A and 2B valves 2-RBR-MOV-8811A and B; 2-RER-MOV-8812A and B.

17 Rev. 0

VOLUME 5 FNP-2-EOP-1.0 6.16.6.6 Close RHR to RCS hot legs xconn valves 2-RER-MOV-8887A and B.

6.16.6.7 Start RHR pumps 2A or 2B.

6.16.6.8 Close charging pump suction header isolation valves 2-CVC-MOV-8130A and B; 2-CVC-MOV-8131A and B.

6.16.6.9 Open RER Ex 2A and 2B to charging pump suction valves 2-CVC-MOV-8706A and B.

6.16.6.10 Close RWST to charging pump header valves 2-CVC-MOV-115B and D.

Assumes 2A and 2C charging pumps are operable.

See NOTE in Step 5.11.2.

6.16.7 Prior to a controlled depressurization below 650 PSIG, energize and close accumulator 2A, 2B, 2C discharge isolation values.

i--

6.16.8 When RCS temperature decreases ton the point where steam dumping is not available for heat removal, control Auxiliary Feedwater to maintain no-load level of 33% narrow range S/G level.

Continue cooldown using the lineup established in step 6.16 until the RCS is stable at 0

1200 F and 500 psig with a bubble in the pressurizer.

7.0 Closely monitor RCS pressure and pressurizer level for evidence of additional pressure boundary degredation.

7.1 If the RER pumps run for 15 minutes without flow indication on FI-605A or FI-605B, open CCW to RER Ex 2A and 2B valves 1-CCW-MOV-3185A and B.

7.2 On receipt of the RWST low level alarm (150,000 gal), RESET the SAFETY INJECTION and CTMT PHASE A ISOLATION signals.

Initiate COLD LEG RECIRCULATION by performing steps 5.11.1 through 5.13.

CAUTION DO NOT reset the Safety Injection signals on the CTMT sump to RER valves or the diesel generators.

18 Rev. O

VOLUME 5 FNP-2-EOP-1.0 CAUTION Do not reopen the CTMT sump pump or the RCDT pump discharge CTMT isolation valves unless the effects of pumping high activity water from the CTMT have been analyzed.

CAUTION Automatic reinitiation of safety injection will not occur since the reactor trip breakers are not reset.

7.3 Within one hour from the time of the accident, perform the following:

7.3.1 Sample the RCS per FNP-0-EIP-25.

7.3.2 Place both hydrogen recombiners in service per step 5.18 of this procedure.

7.3.3 Initiate CTMT hydrogen monitoring per steps 5.18, 5.23, and 5.24 of this procedure.

7.4 Compare WR RCS hot leg temperature, WR RCS cold f."

leg temperature and incore thermocouple temperatures to verify circulation and core cooling as indicated by:

7.4.1 The AT between WR RCS hot leg and. cold leg 1 64*F, or 7.4.2 Incore thermocouples at or near RCS hot leg temperature and decreasing.

If these conditions do not exist, maintain Auxiliary Feedwater flow rate and increase steam dump rate to enhance the establishment of natural circulation.

The conditions listed above may be continuously monitored by use of the AT function on the Core Subcooling Monitoring System.

7.5 Establish a controlled cooldown by dumping

)

steam.

During the cooldown closely monitor RCS pressure, RCS temperature and pressurizer level.

0 Maintain at least 50 F subcooling (Table 1 Column I or as indicated by subtracting RCS temperature from Saturation Temperature calculated by the Core Subcooling Monitori,ng Panel in PSAT/TSAT mode).

19 Rev. 0 l

VOLUME 5 FNP-2-EOP-1.0 7.6 Control RCS pressure using pressurizer heaters and sprays as necessary to maintain at least 500F subcooling (Table 1 Column I or by subtracting RCS temperature from Saturation Temperature calculated by the Core Subcooling Monitoring System in the PSAT/TSAT mode) and NPSH for RCP as indicated by Figure 1.

When > 50*F subcooling is verified, initiate a controlled RCS depressur-ization to reduce break flow while maintaining >

50*F subcooling.

Ensure Tech. Spec. Temperature /

Pressure limitations are complied with.

1 CAUTION If 50*F subcooling cannot be maintained, then manually reinitiate SAFETY INJECTION and go to Netion 5.0 of FNP-2-EOP-0.

7 NOTE _

If an LOSP has occurred, re-establish pressurizer heater control per FNP-2-EOP-7.0, Section 5.3.

7.7 When injection flow exceeds break flow as indicated by stable RCS pressure and increasing pressurizer level, stop one charging pump.

j_.,

When less than one charging pump flow is Sequired 7.8 to maintain level, switch the injection flow path from COLD LEG RECIRCULATION flow path to the normal charging line by:

7.8.1 Open charging pump discharge header.

isolation valves 2-CVC-MOV-8132A and B; 2-CVC-MOV-8133A and B.

7.8.2 Open charging pumps to regenerative heat exchanger valves 2-CVC-MOV-8107 and 2-CVC-MOV-8108.

7.8.3 Place charging flow control valve FCV-122 in MANUAL and throttle to minumum ? low.

7.8.4 Open charging pump A, B and C miniflow valves 2-CVC-MOV-8109A, B and C, and 2-CVC-MOV-8106.

7.8.5 Close BIT inlet valves 2-CVC-MOV-8803A and B.

7.8.6 Close charging pump recirc to RCS cold legs valve 2-CVC-MOV-8885.

20 Rev. O

I VOLUIE 5 FNP-2-EOP-1.0

.i 7.8.7 Manually throttle charging flow control valve FCV-122 to maintain pressurizer level between 25-50%.

7.9 Prior to a controlled depressurization below 650 PSIG, energize and close accumulator 2A, 2B, 2C discharge isolation values.

7.10 When RCS temperature decreases to the point where steam dumping is not available for heat removal, control Auxiliary Feedwater to maintain no-load level of 33% Narrow Range S/G level.

Continue cooldown using the lineup established 0

in step 7.8 until the RCS is stable at < 200 F and 500 psig with a bubble in the pressurizer.

j-n l

i

~

d i

21 Rev. O

FNP-2-EOP-1.0 TABLE 1 SUBC00 LED CONDITIONS SATLTATED STEMi RCS PRESSURE MAX. TH-W.R. (*F)

TH-W.R.

RCS PRESSURE (PSIG)

(PSIG) 50'

(*F) 0 162 50 248 220 3

100 288 230 6

150 316 240 10 200 338 250 15 250 356 260 21 300 372 270 27 350 386 280 35 400 398 290 43 450 410 300 52 500 420 310 63 550 430 320 75 600 439 330 88 650 447 340 103 700 456 350 120 750 463 360 138 800 470 370 159 850 477 380 181 900 484 390 206 950 490' 400 233 h--

1000 496 410

-262 1050 502 420 294 1100 508 430 329 1150 514 440 367 1200 519 450 408 1250 524 460 452 1300-529 470 500 1350 534 480 551 1400 539 490 607 1450 543 500 666 1500 548 510 730 1550 552 520 798 1600 556 530 871 1650 560 540 948 1700 564 550 1031 1750 568 560 1119 1800 572 570 1212 1850 576 580 1311 1900 580 590 1417 1950 583 600 1529 2000 587 610 1647 2050 590 620 1772 2100 594 630 1905 2150 597 640 2046 2200 600 650 2194 2250 604 660 2352

^

2300 607 670 2518 2350 610 680 2698 2400 613 690 2880 2450 616 700 3079 Rev. 0

,,m

s 2500:

N.

.,..l... i

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l... :.m..i. i.ii.

...gn.

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......r..

24

.r...

...,i..

1...

!:E

'Lg.... r.

1..y: ~ +t :.

0. c.. s!... >l E

RCS Saturnted Pressure vs.

.t..

mt e

2300,--

Sacuratcd Temporaturc.

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.4.

a.

3 i

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...t..

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=. :.. r

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2000 a. l_. m.. :.....

l..

....u............

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6... r.... i.

...i......--......

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19

... 0 0.m.. _......

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100 200 200 4t:0 500 GOO 700 m, -n 1

u s.s.

4-o.,

, =.

Level Indientiens Requl ired tri Er,I t

l sura Actunt Leval is' Ablsva Lower Tcp.rnd Belowl Uppelr Tcp If I

l l.

i !

I i

i i

,g STEANGENER$YOR[.EVELI I

PRESSURIZER LEVEL I

I i

i i

l VIDE RANGE I,EVEL*

RCS HINIHUN 6

HAX1 HUN STEAH NARROW RANGE LEVEL.

PRESSURE INI)ICATED,

INDICATEDi

~ GENERATOR HINI,HUti,

ilAXIHUH '.l HitlIH1Ri

' HAXIHIRt 4

PR lINDICATfD,

. INDICATED :

INDICATED

.INDICATEI)

(PSIG)

I.EVEL '

LEVEL

. '(fSSUREi ILEVEL ! !

!I.EVEL LEVEL PSIG) i LEVELi I

, e t

i t

i l

0

>0%

<100%

O l

2.31%l

$100%;

4,971 ;

92.75%

'3 8

i I

i j

' 85.J7%

5{291 '

200

>0%

41001 1

100

' j 4.341

<100%i i

.I l

I i l

t

- i 400

>01

<100%

200

2.82%

<100%

5.65%

81.751 500

>0%

<100%

300 3.12%

<100%,

6.04%

18.59%

600

>0%

<100%

400 3.47%

<100%

6.46%

75.65%

800

>0%

<100%

500 3.85%

99.73%

6.91%

73.00%

1000

>0%

<100%

600 4.27%

97.891 7.40%

70.43%

1200

>0%

<150%

700 4.73%

96.03%

7.921 67.97%

~1500

>0%

<100%

800 5.22%

94.14%

8.48%

65.47%

1500 0.2%

<100%

900 5.75%

92.23%

9.06%

62.911 9.68%

60.39%

, 90. 29%,-

2000 2.1%,

<100% :

1000 6.31%

i

.g i

e 3

10.34%

57.74%

2235 5.0%

97.1%

1100 p.91%

88.33%

y B

2385 7.5%

97.9%,

l 7

2485 9.6L 89.4%

Wide' Raniae Level Lower Tap is '431l inches bjlow Harrow Range O'

r i

Lower Tap I

I I 120 F.

f 8

ablo 1 - NORMAL CONDITIONS OR SECONDARY SYSTEH BREAK OUTSIDE CONTAINHENT,.CONTAINHE p TEMPER TURE l

I t

I Rev. 0 I

6

-t I

0 g

e a

4 I.,.

i i

l

i g

ABLE 3 POST ACCIDENT CONDITIOWS (BREAK INSIDi' CONTAINHENT) - Sil0RT TERH (0-5 t-IN AFTER ACCIDENT),1CONTAINHENT TEllPERATURE..

T i

+.

120 - 280 D 4

Level Indications Required to Ensure Actual Level is Abov Lower Tap and IIelow Upper Tap j

1

,l PRESSURIZER LEVEL STEAN GENERATOR LEVEL PCS HINIllut!

HAXIMUH STEAH NARHOW RANGE LEVEi.

WIDE RANGE I.EVEL*

PRESSURE INDICATED i INDICATED GENERATOR HINIllUH HAXillUN HINltlUN l

HAX1 Hull (PSIG)

LEVEL LEVEL '

PRESSURE INDICATED INDICATED INDICATED INDICATEli (PSIO)

LEVEL LEVEL LEVEL LEVEL 0

UNRELIABLE UNRELIAlli.E 0

UNRELIABLE UNRELIABLE UNRELIABLE UNRELIABLF 200 9.8%

<100%

100 17.86%

<100%

20.I31 84.75%

400 10.4%

<100%

200 18.36%

<100%

20.711 80.89%

l 500 10.7%

<100%

300 18.88%

<100%

21.311 77.95%

600 11.1%

<100%

400 19.43%

<100%

21.93%

75.201 800 12.0%

<100%

500 20.01%,

98.99%

22.581 72.66%

1000 12.9%

<100%

600 20.61%

97.26%

23.25%

70.33%

1200 14.It

<100%

700 7

21.25%

95.52%

2.f.~9.%

67.9}i-I 1500 16.2%

' <100%

800 21.91%

93.79%

24.66%

65.5T1]

1800 19.1%

' < 100%.. '..

.I 900 72.60%

92.05%

25.40%

63.19%l 3

g 2000

21. 6%-

i

<100%

1000 l

t3.33%

90.31%

26.I61 60.85%

i, i

y 2235 25.5%

<100%

1100 24.07%

j 84.57%

26.95%

58.40%

'l 2385 28.8%

97.1%

{

3 l

l l

2485 t

31.7%

94.5%

Wide Range Level Lower Tap is 431.inchesbel,owNarrowRangel.

Lower Tap i

I l

l I

a -

i ble 3 POST ACCIDENT CONDITI0lfS (LJEAK INSIDE. CONTAINHENT) - S110RT TERH (< 5 HJN f.'TER ACCIDENT), CONTAINHENT pHPERATURE j

l 120-2800F g

Rev. 0 i

ABLE 4 POS r ACCIDENT CONDI IONS BREAK INLIDE CONTAINIIENT) - LONG TElul () SHINAFTERACCIDENT),CONTAI'NifENhTEllPERA1 0

120 - 280 F l

t l

l l

o Levet Indications Required to 2nsure ActualiLevel is Above Lower Tap and Below Upper Tap i

l

.i PRESSURIZER LEVEL J

' STEAt! GENERATOR LE, VEL 1

I WIDE RANGE LEVEL

_

.e RCS filNIHUll flAKillUti STEAll.I NAl(HO'd RANGE LEVEL tlAX1tlUll' flillI!!Uffi ilAXIllUli

.tilNillUll

, PRESSURE

INDICATEI INDICATED GENERATOR o'.

(PSIC)

LEVEL LEVELl PRESSURE INDICATED INDICATED INDICATEb INDICATEl LEVEI)

. LEVELi LEVEL '

LEVEL 8

-(PSIC)I

'y 1

q i e.

O UNRELIABLE UNRELIABLE O

UNRELIABLE UNRELIABLE UNRELIADLE UNRELIADl.!

l

,C 200 2,4.8%

<100%

100 32.86%

92.57%

20.13%

84.751 u.

25.4%

<100%

200 33.35%

90.32%

20.71%

80.89%

400 500 25.77.

<iOO%

300 33.88%

88.15%

21.31%

11.95%

600 26.1%

<100%

400 34.43%

86.06%

21.931 75.20%

i 800 27.0%

<100%

500 35.01%

84.06%

22.58%

12.66%

1000 27.9%

(100%

600 35.61%

82.15%

23.251 70.33%

1200 29.1%

<1001 700 36.25%

80:32%

23.94%

67.97%

1500 31.2%

97.3%

800 36.91%

78.58%

24.66%

65.57%

1800 34.1%

93.2%

900 37.60%

76.92%

25.40%

63.19%

200c 36.61 90.1%

1000 38.33%

75.34%

26.16%

60.85%

26.95%

58.40%

2235

'40.5%~

85.7%

1100

'~ 39.07%

'73.85%-

i 2385

,43.8%,,

82.,1,%

2485 46.7%

79.5%

Wide Range Level Lower Tap is $431 inches.below Narrow Range j

I l

i Lower Tap

)

l l

I j

l Tcble 4 POST ACCIDENT CONDLTIONS (BREAK INlilDE CONTAINtIENT) - L0tl0 TERif (> 5 HIN AFTER ACCIDENT), CONTAINt1Etr TEtif'ERATURE 0

120-280 F i..

Rev. 0 1

i l

I

~

i 3

i

. i-.

W. > r a.a.

-.u

.,..~,...

l i.

Level Indications Required to Ensure Actual Level is Above Lower Tap and Below Upper Tap I.

l

. STEM 1 GENERATQR, LEVEL iPRESSURIZER LEVEL' u

i RCS HINltfUH HAXIHUN STEAN NARROW RANGE LEVEL WIDE RANGE LEVEL *

. INDICATED.

GENERATOR HININUH HAXItfUN

, tilN!!!Wi.

HAXlifLAt

?RESSURE lNDICATED (PSIG) 1.EVEI.

LEVEL PRESSURE INDICATED INDICATED INDICATED INDICATEL l

(PSIG).

LEVEL 1.EVEL LEVEL LEVEL ___

0 18.1%

<100%

0 25.81%

89.96%

12.971 84.75%

~

.. lots 26.04%

86.86%

13.2')1 77.87%

200 17.7%

<100%

400 17.'J1

<100%

200 26.32%

83.93%

13.65%

73.75%

500 18.1%

<100%

300 26.62%

81.18%

14.04%

70.597.

600 18.3%

99.7%

400 26.97%

78.61%

14.46%

67.65%

800 18.8%

97.2%

500 27.35%

76.22%

14.91%

65.00%

1000 19.4%

94.7%

600 27.77%

74.00%

15.40%

62.43%

1200

20. 2'}.

92.0%

700 28.23%

71.97%

15.92%

59.97%~

1500 21.6%

87.8%

800 28.72%

70.11%

iC48%

57.47%

1800 23.7%

82.9%

900 29.25%

68.43%

17.06%

54.91%

L I

1 2000 25.6%

',79.1%

1000 29.81%'

66.94% i 17.68%

52.39%

!El

).

'L, 2235 28.5%

73.6%

1100 30.41%

65.62%

18.34%

49.74%

h I

l l

l 1'

I t,

2385 1

31.0%

69.4%j o

l 2485 33.1%

65.9%

Wide Range Level Lower Tap is $431 incia.i 1 elow Harroh sta'n.ge Lower Tap i

1 i

I l

I ble 5 POST ACCIDENT COND: TIONS (BREAK INSIDE CONTAINHENT) -1.ONGTERH(>hHINAFTERACCI' DENT);CONTAINHENrTEMPEgATURE 0

-120 F i

I l

Rev. 0 g

1 i

~ '

FITP-2-EOP-1.0 YOL. 5 v l-....

~

DRY C0itTAltiMEftTS

?

RECOMattiCR PC' ER C':RRECT!Ott FACTOR

~

,VS. C0ttTAltl tE!!T PRESSURE i,

(14.7 PSIA IHITI AL PRESSURE)

. Pressure Fictor

- (C ) '

p

~.

1.6-

. p g gg,,

Containe.ar.

Temp..

60 c r..

f s s*

g-

',/

1.5 f

/

1d

/

t -.-

/

r r'

7

./

1,

/

/.

1.3 ;

/

~

d' W

/

p

_-... -. 1.2 s

i

.., s,

1 1.1 i

1.0 13.7 1G.7 18.7 20.7 22.7 24.7 2G.7 n

me POST-LOCA CO:: TAI l!'.E!iT PRESSURE (PSI A)

Figure 2 Rev. 0

FNP-2-EOP-1.0

, ".-- -pg^, 7 '

e FOST I.CCA CNMT !!YDP.Odfu ' CONC 5NTRATIOli

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f i

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. Figure. 3 - ' -

o Rev. 0

__m

-,__--s

ML19318D233

Text

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