ML20084H027

Rev 3J to Draft BWR Owners Group Generic Emergency Procedure Guidelines, BWR 1-6

ML20084H027
Person / Time
Site:	Clinton
Issue date:	11/10/1983
From:	BWR OWNERS GROUP
To:
Shared Package
ML20084G928	List: ML20084G926 ML20084G959 ML20084G988 ML20084G998 ML20084H018 ML20084H027
References
PROC-831110, NUDOCS 8405070425
Download: ML20084H027 (82)

Text

DRAFT BWR OWNER'S GROUP GENERIC EMERGENCY PROCEDURE GUIDELINES Revision 3J BUR 1 through 6 November 10, 1983

'I I

B405070425 840501 PDR ADOCK 05000461-F PDR

f 1

INTRODUCTION l

l l

Based on the various BWR system designs, the following generic symptomatic emergency procedure guidelines have been developed:

e RPV Control Guideline o Primary Containment Control Guideline e Secondary Containment Control Guideline Radioactivity Release Control Guideline e

The RPV Control Guideline maintains adequate core cooling, shuts down the reactor, and cools down the RPV to cold shutdown conditions. This guideline is entered whenever low RPV water level, high RPV pressure, high drywell pressure, or a condition which requires MSIV isolation has occurred, or whenever a condition which requires reactor scram exists and reactor power is above the APRM downscale trip or cannot be determined.

The Primary Containment Control Guideline maintains primary containment integrity and protects equipment in the primary containment. This guideline is entered whenever suppression pool temperature, drywell temperature, containment temperature, drywell pressure, suppression pool water level, or primary containment hydrogen concentration is above its high operating limit or suppression pool water level is below its low operating limit.

The Secondary Containment Control Guideline protects equipment in the secondary containment, limits radioactivity release to the secondary containment, and either maintains secondary containment integrity or limits radioactivity release from the secondary containment. This guideline is entered whenever a secondary containment temperature, radiation level, or water level is above its maximum normal operating value or secondary containment differential pressure reaches zero.

The Radioactivity Release Control Guideline limits radioactivity release into areas outside the primary and secondary containments.

This guideline is entered whenever offsite radioactivity release rate is above that which requires an Alert.

(I-l) Rev. 3G hh,k

l Figure 1, Operator Actions Flowchart, illustrates all operator actior.J within the emergency procedure guidelines. Each action block states i

briefly the operator action and its purpose. The blocks are generally correlated from top (high RPV pressure) to bottom (RPV cold shutdown j

conditions) with a vertical RPV pressure / temperature scale to show continuity of the linked operator actions. Each block is.further identified by a numbered symbol (e.g., kfI)whichiskeyedtothe guideline steps.

Table I is a list of abbreviations used in the guidelines.

Brackets [ ] enclose plant unique setpoints, design limits, pump shutoff pressures, etc., and parentheses (

) within brackets indicate the source for the bracketed variable.

Illustrated in these guidelines are variables for a typical BWR/4 or BWR/6 as appropriate.

At various pofnts throughout these guidelines, precautions are noted by the symbol The number within.the box refers to a numbered

" Caution" contained in the Operator Precautions section. These

" Cautions" are brief and succinct red flags for the operator. Where the basis for the " Caution" or a step is not completely evident from the text, a full discussion of the basis is contained in Appendix A.

Other system details which pertain to the guidelines are also included in this appendix.

The emergency procedure guidelines are generic to CE-BWR 1 through 6 designs in that they address all major systems which may be used to respond to an emergency. Because no specific plant includes all of the systems in these guidelines, the guidelines are applied to individual plants by deleting statements which are not applicable or by substituting equivalent systems where appropriate. For example, plants with no low pressure injection system will delete statements referring to LPCI, and plants with Low Pressure Core Flooding will substitute LPCF for LPCI.

hk*[h (I-2) Rev. 3G

i At various points within these guidelines, limits are specified beyond which certain actions are required. While conservative, these limits are derived from engineering analyses utilizing best-estimate (as opposed to licensing) models. Consequently, these limits are not as conservative as the limits specified in a plant's Technical Specifications. This is not to imply that operation beyond the Technical Specifications is recom-sended in an emergency. Rather, such operation may be required under certain degraded conditions in order to safely mitigate the consequences of those degraded conditions. The limits specified in the guidelines establish the boundaries within which continued safe operation of the plant can be assured. Therefore, conformance with the guidelines does not ensure strict conformance with a plant's Technical Specifications or other licensing bases.

The entry conditions for these emergency procedure guidelines are symptomatic of both emergencies and events which may degrade into emergencies. The guidelines specify actions appropriate for both.

Therefore, entry into procedures developed from these guidelines is not conclusive that an emergency has occurred.

D W..

(I-3) Rev. 3G k

TABLE I ABBREVIATIONS ADS Automatic Depressurization System APRM Average Power Range Monitor CRD Control Rod Drive l

ECCS Emergency Core Cooling System Hydraulic Control Unit HCU KPCI High Pressure Coolant Injection EPCS High Pressure Core Spray KVAC Heating, Ventilating and Air Conditioning IC Isolation Condenser LCO Limiting Condition for Operation LOCA Loss of Coolant Accident LPCI Low Pressure Coolant Injection LPCS Low Pressure Core Spray MSIV Main Stesaline Isolation Valves NDTT Nil-Ductility Transition Temperature NPSH Net Positive Suction Head RCIC Reactor Core Isolation Cooling RHR Residual Heat Removal RPS Reactor Protection System RPV Reactor Pressure Vessel RSCS Rod Sequence Control System RWCU Reactor Water Cleanup SBGT Standby Gas Treatment SLC Standby Liquid Control SORV Stuck Open Relief Valve SPMS Suppressica Pool Makeup System SRV Safety Relief Valve DR F' (I-4) Rev. 3c

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_0PERATOR FRECAUTIONS

\\

_CFNERAL s

x s

s

'h This section lists " Cautions"',%1ch are generally applicable at all times, y

x o

CAUTIONhl.

q; s

Monitor the general state of sthe ' plant.

If an entry condition for a

[procedsre developed frca the' Emergency Procedure Guidelines] occurs, 1

enter that arecedure. Een it is'd termined that an emergency no longer exists, enter [i1ormal operating procedureJ.

=_

m a

CAUTION #2 i

Monitor RPV water level' and pressure and pris.ary containnent temperatures

)

and pressure from multiple indications.,.

l

s CAUTION.93

- s If a safety function initiates automatically, andume a true initiating l

event has occurred unless otherwise confirmed by at least two independent indications.

~

CAUTION f4 Whudvir.RMR is in the LPCI mode, inject through the heat exchangers as soon as possible.

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CAUTION #5 Suppression pool temperature is determined by [ procedure for determining bulk suppression pool water temperature]. Drywell temperature is determined by [ procedure for determining dryvell atmosphere average temperature]. Containment temperature is determined by [ procedure for determining Mark III containment atmosphere average temperature].

l l

CAUTION #6 Whenever [ temperature near the instrument reference leg vertical runs]

exceeds the temperature in the table and the instrument reads below the indicated level in the table, the actual F.PV water level may be anywhere below the elevation of the lower instrument tap.

Indicated Temperature [*]

Level Instrument any 617 in.

Shutdown Range Level ( 500 to 900 in.)

I l

1070F

-107 in.

Wide Range Level

(-150 to +60 in.)

0 310 F 19 in.

Narrow Range Level

(

0 to +60 in.)

5450F 168 in.

Fuel Zone Level

( 200 to 500 in.)

[* List in order of increasing temperature.]

CAUTION #7

[ Heated reference leg instrument] indicated levels are not reliable during rapid RPV depressurization below 500 psig. For these conditions, utilize

[ cold reference leg instruments] to monitor RPV water level.

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(I-6) Rev. 3G l,'t.

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---

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1 CAUTION #8 Observe NPSH requirements for pumps taking suction from the suppression pool.

i 240-1 10 psig ou oo 5 psig ee o 6.

220 - -

s

-a mW m=

=b O psig

5. ca s o.

CL E 3e 200-.

RHR NPSH Limit 2

4 6

8 10 RHR Pump Flow (X1000 gpm)

I0 psig 240 -

-- y N.

5 psig s

a~

s ee o6 a-

-m 220 m4 ma O psig m.

e 6.

bo

==

an aE no LPCS NPSH Limit 200-l 2

4 6

LPCS Pump Flow (X1000 gpm) i

• Suppression chamber pressure 1

Suppression pool at normal water level 1

)

l n.,... ;- 1 g $,j.

(I-7) Rev. 3G i

i

CAUTION #9 If signals of high suppression pool water level [12 f t. 7 in. (high level suction interlock)] or low condensate storage tank water level [0 in. (low level suction interlock)) occur, confirm automatic transfer of or manually trans fer HPCI, HPCS, and RCIC suction from the condensate storage tank to the suppression pool.

SPECIFIC This section lists " Cautions" which are applicable at one or more specific points within the guidelines. Where a " Caution" is applicable, it is identified with the symbol CAUTION #10 Do not secure or place an ECCS in MANUAL mode unless, by at least two independent indications, (1) misoperation in AUTOMATIC mode is confirmed, or (2) adequate core cooling is assured. If an ECCS is placed in MANUAL mode, it will not initiate automatically. Make frequent checks of the initiating or controlling parameter. When manual operation is no longer required, restore the system to AVIOMATIC/ STANDBY mode if possible.

CAUTION #11 If a high drywell pressuse ECCS initiation signal [2.0 psig (drywell pressure which initiates ECCS)] occurs or exists while depressurizing, 1

prevent injection from those LPCS and LPCI pumps not required to assure adequate core cooling prior to reaching their maximum injection pressures.

When the high drywell pressure ECCS initiation signal clears, restore LPCS and LPCI to AUTOMATIC / STANDBY mode.

(I-8) Rev. 3G p ry, ;! 1,(

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CAUTION #12 Do not throttle HPCI or RCIC systems below [2200 rpm (minimum turbine speed limit per turbine vendor manual)].

CAUTION #13 Cooldown rates above [100 F/hr (RPV cooldown rate LCO)] may be required to accomplish this step.

CAUTION #14 Do not depressurize the RPV below [100 psig (HPCI or RCIC low pressure isolation setpoint, whichever is higher)] unless motor driven pumps sufficient to maintain RPV water level are running and available for injection.

CAUTION #15 Open SRVs in the following sequence if possible: [SRV opening sequence).

CAUTION #16 Bypassing low RPV water level [ ventilation system and] MSIV isolation interlocks may be required to accomplish this step.

CAUTION #17 Cooldown rates above [100 F/hr (RPV cooldown rate LCO)] may be required to conserve RPV water inventory, protect primary containment integrity, or limit radioactive release to the environment.

CAUTION #18 If continuous LPCI operation of any RHR pump is required to assure adequate core cooling, do not divert that pump f rom the LPCI mode.

(I-9) Rev. 3G

i l

CAUTION #19 Confirm automatic trip or manually trip SLC pumps at [0% (low level trip)] in the SLC tank.

l l

CAUTION #20 Defeating RSCS interlocks may be required to accomplish this step.

CAUTION #21 Elevated suppression chamber pressure may trip the RCIC turbine on high exhaust pressure.

CAUTION #22 Defeating isolation interlocks may be required to accomplish this step.

CAUTION #23 Do not initiate drywell sprays if suppression pool water level is above

[17 ft. 2 in. (elevation of bottom of Mark I internal suppression chamber to drywell vacuum breakers less vacuum breaker opening pressure in feet of water)].

CAUTION #24 Bypassing high drywell pressure and low RPV vater level secondary contain-ment HVAC isolation interlocks may be required to accomplish this step.

CAUTION #25 A rapid increase in injection into the RPV may induce a large power excursion and result in substantial core damage.

CAUTION #26 Large reactor power oscillations may be observed while executing this step.

(I-10) Rev. 3G h

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RPV C0tTIROL CUIDELINE P URPOSE The purpose of this guideline is to:

e Maintain adequate core cooling, o

Shut down the reactor, and e

Cool down the RPV to cold shutdown conditions ([100 F < RPV water temperature < 212 F (cold shutdown conditions)]).

ENTRY CONDITIONS The entry conditions for this guideline are any of the following:

e RPV water level below [+ 12 in. (low level scram setpoint)]

RPV pressure above [1045 psig (high RPV pressure scram setpoint)]

e Drywell pressure above [2.0 psig (high drywell pressure scram setpoint )]

e A condition which requires MSIV isolation e

A condition which requires reactor scram, and reactor power above [3%

e (APRM downscale trip)] or cannot be determined OPERATOR ACTIONS RC-1 If reactor scram has not been initiated, initiate reactor scram.

Irrespective of the entry condition, execute [ Steps RC/L, RC/P, and RC/Q]

concurrently.

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(RC-1) Rev. 3G

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i

RC/L Monitor and control RPV water level.

RC/L-1 Confirm initiation of any of the following:

e Isolation e

ECCS

[e Emergency diesel generator]

Initiate any of these which should have initiated but did not.

If while executing the following step:

Boron Injection is required, enter [ procedure developed from e

CONTINGENCY #7].

RPV water level cannot be determined. RPV FLOODING IS REQUIRED; e

enter [ procedure developed from CONTINCENCY #6].

RPV Flooding is required, enter [ procedure developed from e

CONTINCENCY #6].

RC/L-2 Restore and maintain RPV water level between [+ 12 in. (low level scraa setpoint)]

1. 9 and [+58 in. (high level trip setpoint)]

1. 10 with one or more of the following systems:

1. 11 Condensate /feedwater system [1110 - O psig (RPV pressure e

range for system operation))

CRD system [1110 - O psig (RPV pressure range for system e

operation))

i e

RCIC system [1110 - 50 psig (RPV pressure

1. 12 range for system operatica))

(RC-2) Rev. 3G f *

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e HPCI system [1110 - 100 psig (RPV pressure range for system operation)]

HPCS system [1110 - O psig (RPV pressure range for system e

operation)]

LPCS system (425 - O psig (RPV pressure range for system e

operation)]

LPCI system [250 - O psig (RPV pressure range for system e

operation)]

If RPV water level cannot be restored and maintained above

[+12 in. (low level scram setpoint)], maintain RPV water level above [-164 in. (top of active fuel)].

If RPV water level can be maintained above [-164 in. (top of active fuel)] and the ADS timer has initiated, prevent automatic RPV depresssrization by resetting the ADS timer.

If RPV water level cannot be maintained above [-164 in. (top of active fuel)], enter [ procedure developed from CONTINGENCY #1].

If Alternate Shutdown Cooling is required, enter [ procedure developed from CONTINGENCY #5].

RC/L-3 When (procedure for cooldown to cold shutdown conditions] is entered from [ Step RC/P-5] in this procedure, proceed to cold shutdown in accordance with [ procedure for cooldown to cold shutdown conditions].

f. r;.-

(I rit i (RC-3) Rev. 3G

RC/P Monitor end ccntrol RPV pressure.

If while executing the following steps:

e Emergency RPV Depressurization is anticipated and Boron

1. 13 Injection is not required, rapidly depressurize the RPV with the main turbine bypass valves.

e Emergency RPV Depressurization or RPV Flooding is required and less than [7 (number of SRVs dedicated to ADS)] SRVs are open, enter (procedure developed from CONTINGENCY #2].

e RPV Flooding is required and at least [7 (number of SRVs dedicated to ADS)] SRVs are open, enter (procedure developed from CONTINGENCY #6).

I RC/P-1 If any SRV is cycling, initiate IC and manually open SRVs until RPV pressure drops to [935 psig (RPV pressure at which all turbine bypass valves are fully open)].

l DRAFT (RC-4) Rev. 3G L..

If while executing the following steps:

e Suppression pool temperature cannot be maintained

1. 8 below the Heat Capacity Temperature Limit, maintain

1. 13 RPV pressure below the Limit.

1. 14 E

( 188 I eo <

l i

/

g Meet Capacity Temperature Limit 1

o e

is ano to,o NT PMemm (pela) e Suppression pool water level cannot be maintained

1. 13 below the Suppr6ssion Pool Load Limit, maintain

1. 14 RPV pressure below the Limit.

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7/-

12.5 e

neo Isoo 8.V Pressure (psig)

Steam Cooling is required, enter [ procedure developed from e

CONTINGENCY #3J.

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(nC-5) nev. 3c

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If while executing the following steps:

Boron Injection is required, and e

The main condenser is available, and e

There has been no indication of gross fuel failure or e

steam line break, open MSIVs to re-establish the main condenser as a heat sink.

816 RC/P-2 Control RPV pressure below [1090 psig (lowest SRV

1. 14 lifting pressure)] with the main turbine bypass valves.

RPV pressure control may be augmented by one or more of the following systems:

e IC SRVs only when suppression pool water level

1. 15 e

is above [4 f t. 9 in. (elevation of top of SRV discharge device)]. If the continuous SRV pneumatic supply is or becomes unavailable, place the control switch for each SRV in the [CLOSE] position.

e HPCI

1. 12 e

RCIC l

[0ther steam driven equipment]

e (RC-6) Rev. 3G

-k!

injected RWCU (recirculation mode) if no boron has been o

into the RPV.

Main steam line drains e

j ted into RWCU (blowdown mode) if no boron has been in e Refer to (sampling procedures] prior to e

the RPV.

initiating blowdown.

R l~

tor is not If while executing the following steps the reac shutdown, return to (Step RC/F-2].

a L

RC/P-3 When either:

(06 All control rods are inserted beyond position

)], or I

(maximum subcritical banked withdrawal position I

have (280 pounds (Cold Shutdown Boron Weight)] of boron e

f been injected into the RPV, or j ted The reactor is shutdown and no boron has been e

into the RPV, R

1. 14, #17 f

r-depressurize the RPV and maintain cooldown l

rate below (100 F/hr (RPV cooldown rate 0

LCO)].

i the RPV If one or more SRVs are being used to depressur ze is or becomes and the continuous SRV pneumatic supply d SRV opening.

unavailable, depressurize with sustaine I

l~

1. 18 When the RRR shutdown cooling interlocks clear,w RC/P-4 initiate the shutdown cooling mode of RHR.

.,n

[)f?l (RC-7) Rev. 3G k

~-

If the RRR chutdswn cooling toda ccnsst be ost0blish2d cnd further cooldown is required, continue to cool down using one or more of the eyetens used for depressurization.

If RPV cooldown is required but cannot be accomplished and all control rods are inserted beyond position [06 (maximum suberitical banked withdrawal position)], ALTERNATE SHUTDOWN COOLING IS REQUIRED; enter [ procedure developed from CONTINGENCY #5].

RC/P-5 Proceed to cold shutdown in accordance with

[ procedure for cooldown to cold shutdown conditions).

RC/Q Monitor and control reactor power.

If while executing the following steps:

All control rods are inserted beyond position [06 (maxiana e

subcritical banked withJrawal position)], terminate boron injection and enter [scran procedure].

The reactor is shutdown and no boron has been injected into e

the RPV, enter [ scram procedure].

RC/Q-1 [ Confirm or place the reactor mode switch in SHUTDOWN.]

RC/Q-2 If the main turbine-generator is on-line [and the MSIVs are open], confirm or initiate recirculation flow runback to minimum.

RC/Q-3 If reactor power is above [3% (APRM downscale trip)] or cannot be determined, trip the recirculation pumps.

(RC-8) Rev. 3G

}

• ~

Execute (Steps RC/Q-4 and RC/Q-5] concurrently.

i RC/Q-4 If the reactor cannot be shutdown before

1. 19 suppression pool temperature reaches [the Boron Injection Initiation Temperature),

BORON INJECTION IS REQUIRED; inject boron into the RPV with SLC and prevent automatic initiation of ADS.

////

I'ar!!//

/

B on

/

130 Injection Initiation Suppression Pool 120

[ Temperature

/

Temperature

/

(=F) 110 N

100 0

1 2

3 4

5 6

7 Reactor Power (%)

If boron cannot be injected with SLC, inject boron into the RPV by one or more of the following alternate methods:

e CRD e

HPCS e

RWCU e

Feedwater e

HPCI e

RCIC e

Hydro pump (RC-9) Rev. 3G

I RC/Q-4.1 If boron is not being injsetsd into tha RPV by RWCU, confirm automatic isolation of or manually isolate RWCU.

RC/Q-4.2 continue to inject boron until [280 pounds (Cold Shutdown Boron Weight)] of boron have been injected into the RPV.

RC/Q-4.3 Enter [ scram procedure].

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(RC-9A) Rev. 3G

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RC/Q-5 Insart centrol redo as follews:

RC/Q-5 1 If any scras valve is not open:

e

[ Remove:

H11-P609 C71-F18A,E C.G R11-P611 C71-F188,F,D,H (fuses which de energize RPS scram solenoids)].

e Close [Cll-F095 (scras air header supply valve)] and open [C11-F008 (scram air header vent valve)].

When control rods are not moving inward:

o (Replace:

Hil-P609 C71-F18A,E,C G Hil-P611 C71-F188, F, D,H (fuses which de energize RPS scram solenoids)].

Close [C11-F008 (scram air header vent e

valve)] and open [C11-F095 (scras air header supply valve)].

RC/Q-5 2 Reset the reactor scraa.

If the reactor scram cannot be reset:

j 1.

Start all CRD pumps.

If no CRD pump can be started, continue in this procedure at [ Step RC/Q-5 6 1].

(RC-10) Rev. 3G J R AF._,:

2.

Close [C11-F034 (HCU accumulator charging water header valve)].

3.

Rapidly insert control rods

1. 20 manually until the reactor scram can be reset.

4 Reset the reactor scram.

5.

Open [C11-F034 (HCU accumulator charging water header valve)].

RC/Q-5.3 If the scram discharge volume vent and drain valves are open, initiate a manual reactor scram.

1.

If control rods moved inward, return to

[ Step RC/Q-5.2].

2.

Reset the reactor scram.

If the reactor scram cannot be reset, continue in this procedure at [ Step RC/Q-5.5.1].

3.

Open the scram discharge volume vent and drain valves.

RC/Q-5.4 Individually open the scram test switches for control rode not inserted beyond position [06 (maximus suberitical banked withdrawal position)].

When a control rod is not moving inward, close its scram test switch.

\\

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(RC-11) Rev. 3G

3 RC/Q-5.5 Reset the reactor scras.

If the reactor scram cannot be reset:

1.

Start all CRD pumps.

If no CRD pump can be started, continue in this procedure at [ Step RC/Q-5.6.1].

2.

Close [Cil-F034 (HCU accumulator charging water header valve)].

RC/Q-5.6 Rapidly insert control rods manually

1. 20 until all control rods are inserted beyond position [06 (maximum subcritical banked withdrawal position)].

If any control rod cannot be inserted beyond position [06 (maximum subcritical banked withdrawal position)]:

1.

Individually direct the effluent from

[C11-F102 (CRD withdraw line vent valve)]

to a contained radwaste drain and open

[C11-F102 (CRD withdraw line vent valve))

for each control rod not inserted beyond position [06 (maximum subcritical banked withdrawal position)].

2.

When a control rod is not moving inward, i

close its [C11-F102 (CRD withdraw line vent valve)].

(RC-12) Rev. 3G l

..._ ~

o o

Document 9390-4 Emergency Procedure Guidelines 1

PRIMARY CONTAINMENT CONTROL GUIDELINE PURPOSE The purpose of this guideline is to:

4 o

Maintain primary containment integrity, and o

Protect equipment in the primary containment.

ENTRY CONDITIONS The entry conditions for this guideline are any of the following:

o Suppression pool temperature above C95=F (most limiting suppression pool temperature LCO)3 o

Drywell temperature above [135=F (drywell temperature LCO or maximum normal operating temperature, whichever is higher)3 o

Containment temperature above C90=F (containment temperature LCO)3 o

Drywell pressure above C2.0 psig (high drywell pressure scram setpoint)3 o

Suppression pool water level above C12 ft. 6 in. (maximum suppression pool water level LCO)3 o

Suppression pool water level below [12 ft. 2 in. (minimum suppression pool water level LCO)3 Primary containment hydrogen concentration above C2*/. (high o

hydrogen alarm setpoint)3 I

OPERATOR ACTIONS Irrespective of the entry condition, execute CSteps SP/T, I DW/T, CN/T, PC/P, SP/L, and PC/H 3 concurrently.

I I

PC-1 Revision 3J

SP/T Monitor end control cuppr2 Scion pool truperztura.

SP/T-1 Close all SORVs.

If any SORV cannot be closed [within 2 minutes (optional plant-specific time interval)], scram the reactor.

SP/T-2 When suppression pool temperature exceeds

1. 18

[95 F (most limiting suppression pool temperature LCO)], operate available suppreasion pool cooling.

SP/I-3 Before suppression pool temperature reaches [the Boron Injection Initiation Temperature], scram the reactor.

////

/ 'ar! ! / /

/

B on

/

130 Injection Initiation Suppression Temperature Pool 120

/

Temperature

(=F) 110 100 0

1 2

3 4

5 6

7 Reactor Power (%)

(PC-2) Rev. 3G 3Rht-I

f, SP/I-4 If suppression pool temperature cannot be maintained

1. 8 below the Heat capacity Temperature Limit, maintain

1. 13 RPV pressure below the Limit; enter [ procedure developed

1. 14 from the RPV Control Guideline] at [ Step RC-1] and execute it concurrently with this procedure.

197< -

of188*

E 160 <

i

/

g Heat Capacity Temperature Limit

{ 122 <

.i,

^

9 0

135 240 logo M Preemu's (poig)

If suppression pool temperature and RFV pressure cannot be restored and maintained below the Heat Capacity Temperature Limit, EMERGENCY RPV DEPRESSURIZATION IS REQUIRED.

j (PC-2A) Rev. 3A

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l l

1 i

W/T Monitor and control drywell temperature.

W/T-1 When drywell temperature exceeds [135 F (drywell temperature LCO or maximum normal operating temperature,

1. 6 whichever is higher)], operate available drywell cooling.

Execute [ Steps W /T-2 and DW/T-3] concurrently.

W/T-2 If drywell temperature (near the cold reference leg instrument vertical runs] reaches the RPV Saturation Temperature, RPV FLOODING IS REQUIRED; enter [ procedure developed from the RPV Control Guideline] at [ Step RC-1] and execute it concurrently with this procedure.

550

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RPV Saturation jEI N Temperature 22" N

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[*h 5

s 6.5 212 O

RPV Pressure (psig) 1000 (PC-3) Rev. 3G i

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l.

DW/T-3 Before drywell temperature reaches [340 F (maximum

1. 18 temperature at which ADS qualified or drywell design terperature, whichever is lower)] but only if

[suppres',fon chamber temperature and drywell pressure are be12w the Drywell Spray Initiation Pressure Limit],

[ shut down recirculation pumps and drywell cooling fans and) initiate dryvell sprays [ restricting flow rate to le<,s than 720 spa (Maximum Dryvell Spray Flow Rate Limit)].

400 <-

[ 300 2~

"E 85 0 2' 200 E E.

\\

Drywell Spray Initiation m

Pressure Limit 100 10 20 30 40 50 60 Drywell Pressure (psig)

~

If drywell temperature cannot be usintained below [340 F (maximum temperature at which ADS qualified or drywell design temperature, whichever is lower)], EMERGENCY RPV DEPRESSURIZATION IS REQUIRED; enter [ procedure developed from the RPV Control Guideline) at

[ Step RC-1] and execute it concurrently with this procedure.

(PC-4) Rev. 3G e

l CN/T Monitor and control containment temperature.

CN/T-1 When containment temperature exceeds [90 F

1. 6 (containment temperature LCO)], operate available containment cooling.

If while executing the following steps suppression pool sprays have been initiated, when suppression chamber pressure drops below 0 psig, terminate suppression pool sprays.

J i

CN/T-2 Before containment temperature reaches [185 F

1. 18 (containment design temperature)] but only if I

[ suppression chamber pressure is above 1.7 psig (Mark III Centainment Spray Initiation Pressure Limit)], initiate suppression pool sprays.

CN/T-3 If containment temperature cannot be maintained below

[185 F (containment design temperature)], EMERGENCY RPV DEPRESSURIZATION IS REQUIRED; enter [ procedure developed from the RPV Control Guideline] at [ Step RC-1]

and execute it concurrently with this procedure.

CN/T-4 If containment temperature [near the cold reference leg instrument vertical runs] reaches the RPV Saturation Temperature, RPV FLOODING IS REQUIRED.

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212 0

SPV Pr.ss.r. (psig) 1000 DN. / i. l q,. g..

(PC-5) Rev. 3G 1

1 PC/P Monitor and control primary containment pressure.

PC/P-1 Operate [the following systems, as required:

e Containment pressure control systems.

Use containment pressure control system operating procedure. ]

[e] SBGT [and drywell purge }, only when the temperature in the s pace being evacuated is below [212 F (Maximum Noncondensible Evacuation Tem perature} }. Use [SBGT and

1. 21 drywell purge operating procedures).

If while executing the following steps suppression pool sprays have been initiated, when suppression chamber pressure drops below 0 psig, terminate suppression pool sprays.

PC/P-2 Before suppression chamber pressure reaches [the

1. 8, #18 Pressure Suppression Pressure] [17.4 psig (Suppression Chamber Spray Initiation Pressure)}, but only if

[ suppression chamber pressure is above 1.7 psig (Mark III Containment Spray Initiation Pressure Limit)} [ suppression pool water level is below 24 ft. 6 in. (elevation o f suppression pool spray nozzles} }, initiate suppression pool sprays.

PC/P-3 If suppression chamber pressure exceeds [17.4 psig

1. 18 (Suppression Chamber Spray Initiation Pressure} }

but only if [ suppression chamber temperature and drywell pressure are below the Drywell Spray Initiation Pressure Limit}, [ shut down recirculation Pumps and drywell cooling fans and) initiate drywell sprays [ restricting flow rate to less than 720 gpm (Maximum Drywell Spray Flow Rate Limit)}.

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(PC-6) Rev. 3G L

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400 N

g [ 300 < -

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\\

Drywell Spray Initiation m

Pressure Limit 100 10 20 30 40 50 60 Drywell Pressure (psig)

PC/P-4 If suppression chamber pressure cannot be maintained belov [the Pressure Suppression Pressure], EMERGENCY RPV DEPRESSURIZATION IS REQUIRED.

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Pressure Suppression U

Pressure m

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0 12.2 17 34.5 Primary Containment Water Level (f t.)

(PC-7) Rev. 3ck{T

PC/P-5 If suppression chamber pressure cannot be maintained below [the Primary Containment Design Pressure], RPV FLOODING IS REQUIRED. ^ as / e E 56 7 I // 2 46.5 < w Primary Containment u Design Pressure E I I $.Io 0 12.5 34.5 Primary Containment Water Level (ft.) PC/P-6 If suppression chamber pressure cannot be maintained below the Primary Containment Pressure Limit, then irrespective of whether adequate core cooling is assured ^ es l 5 / I // g Primary Containment i G Prassure Limit .I. I* 1 t a o 0 12.5 34.5 Primary Containment Water Level (ft.) DRAF' (PC-8) Rev. 3G l

c, y,, 1 N [If suppressiori posi. water I vel is below 24 f t. 6 in. (elevation l e ? of suppression pool spray noza.'le's). ] initiate suppression pool l sprays. ~ I s \\ If [ suppression chambe't temperature and drywell pressure are below e the Drywell Spray Initiation Pressure Limicl, [ shut down 8 tecirculation pumps and drywell cooling fans and] initiate drywell \\ si, rays,(restricting flow rate to less than 720 gpm (Maximum Dryvell s Spray Flow 3 ate Limit)].' I s i { s 400 [ 300 - I $5 \\ e5 hb 0 E',200 kB \\'* g-Drywell Spray Initiation to Pressure Limit 100 6 I 10 20 30 40 50 60 Orywell Pressure (psig) k PC/P-7 If suppression chamber pressure exceeds the Primary Containment Pressure Limit, vent the primary containment

1. 22 in accordance with [ procedure for containment venting]

l to reduce,snd meintain pressure below the Primary l Containaent Pressure Limit. (PC-9) Rev. 3G .t ! L

SP/L ifonicor and control suppression pool water level. l SP/L-1 Maintain suppression pool water level between (12 ft. 6 in. (maximum suppression pool water level LCO)] and [12 ft. 2 in. (mininua suppression

1. 8, #9 pool water level LCO)]. Refer to [ sampling I

\\ procedure] prior to discharging water. [ Suppression pool makeup may be augmented by SPMS). If SPMS has been initiated, maintain suppression pool water level between [23 f t. 9 in. (SPMS initiation setpoint plus suppression pool water level increase which results from SPMS operation)] and [19 ft. 11 in. (minfaua suppression pool water level LCO)]. If suppression pool water level cannot be maintained above [12 f t. 2 in. (minimum suppression pool water level LCO)] execute [ Step SP/L-2]. If suppression pool water level cannot be maintained below [12 f t. 6 in. (maximum suppression pool water level LCO)] ([23 ft. 9 in. (SPMS initiation setpoint plus suppression pool water level increase which results from SPMS operation)] if SPMS has bean initiated), execute [ Step SP/L-3]. I l D Q 3 f;;- i dit (PC-10) Rev. 3G L

tr/L-2 SUPPRESSION POOL WATER LEVEL BELOW [12 ft. 2 in. (minimum suppression pool water level LCO)} Maintain suppression pool water level above the Heat Capacity Level Limit. l emma i 3 12'2" - t / -f Heat Capacity Level Limit t u

I "o

8'2" s2 8 'm m m 5 0 27 6T N) HC Where AT = Ilest Capacity Temperature T,imit minus HC suppression pool temperature If suppression pool water level cannot be maintained above the Heat Capacity Level Limit EMERGENCY RPV DEPRESSURIZATION IS REQUIRED; enter [ procedure developed from the RPV Control Guideline) at [ Step RC-1] and es.ecute it concurrently with this procedure. DRACT I (PC-ll) Rev. 3G [

SP/L-3 SUPPRESSION POG. WATER LEVEL ABOVE [12 f t. 6 in. (maximum suppression pool water level LCO)] ([23 f t. 9 in. (SPMS initiation setpoint plus suppression pool water level increase whic.5 results from SPMS operation)] if SPMS has been initiated) Execute [ Steps SP/L-3.1 and SP/L-3.2] concurrently. SP/L-3.1 Maintain suppression pool water level below the Suppression Pool Load Limit. 7 7 20 " / = 3 4 / Suppresssion Pool y / e .o Load Limit / e / 12.5 l 0 400 1200 RPV Pressure (psig) If suppression pool water level cannot be

1. 13 j

maintained below the Suppression Pool Load

1. 14 Limit, maintain RPV pressure below the Limit.

(PC-12) Rev. 3G

If suppression pool water level and RPV pressure cannot be maintained below the Suppression Pool Load Limit but only if adequate core cooling is assured, terminate injection into the RPV from sources external to the primary containment except from boron injection systems and CRD. If suppression pool water level and RPV pressure cannot be restored and maintained below the Suppression Pool Load Limit, EMERGENCY RPV DEPRESSURIZATION IS REQUIRED; enter [ procedure developed from the RPV Control Guideline) at (Step RC-1] and execute it concurrently with this procedure. SP/L-3.2 Before suppression pool water level reaches [17 ft. 2 in. (Maximus Primary Containment Water Level Limit or elevation of bottom of Mark I internal suppression chamber to drywell vacuum breakers less vacuum breaker opening pressure in feet of water, whichever is lower)] but only if adequate core cooling is assured, terminate injection into the RPV from sources external to the primary containment except from boron injection systems and CRD.

1. When suppression pool water level reaches

[17 ft. 2 in. (elevation of bottom of Mark I

1. 18 internal suppression chamber to drywell vacuum breakers less vacuum breaker opening pressure in feet of water)] but only if

[ suppression chamber temperature anc drywell pressure are below the Drywell Spray Initiation Pressure Limit], [ shut down recirculation pumps and drywell cooling fans and) initiate drywell sprays [ restricting flow rate to less than 720 spa (Maximum Drywell Spray Plow Rate Limit)]. l (PC-13) Rev. 3G

400 <- I l g[2 300 < .E ~ vg 83 !;2 E E. 200 EE \\ 8 *- Drywell Spray Initiation Pressure Limit 100 < - 10 20 30 40 50 60 Drywell Pressure (psig)

2. If suppression pool water level exceeds

[17 ft. 2 in. (elevation of bottom of Mark I

1. 23 internal suppression chamber to drywell vacuus breakers less vacuum breaker opening pressure in feet of water)], continue to operate drywell sprays [below 720 gpa (Maximum Drywell Spray Flow Rate Limit)].

3. When primary containment water level reaches

[104 ft. (Maximus Primary Contrainment Water Level Limit)], terminate injection into the RPV from sources external to the primary containment irrespective of whether adequate core cooling is { assured. D r *. r 7 f (PC-14) Rev. 3G

Document 8390-4 Emergency Procedure Guidelines PC/H Monitor and control hydrogen and oxygen concentrations. l If while executing the following

steps, drywell or suppression chamber hydrogen concentration cannot be :

determined to be below the Erespective] Hydrogen :

Deflagration Overpressure Limit and the Hydrogen !

Deflagration Temperature Limit and drywell or i suppression chamber oxygen concentration cannot be !

determined to be bel ow the Crespective] Oxygen :

Deflagration Overpressure Limit and the Oxygen :

Deflagration Temperature

Limit, secure and prevent

operation of hydrogen mixing systems, recombiners, and :

ignitors until drywell and suppression chamber hydrogen concentrations can be determined to be below the :

[ respective]

Hydrogen Deflagration Overpressure !

Limitts]

and the Hydrogen Deflagration Temperature Limit or drywell and suppression chamber oxygen ! concentrations can be determined to be below the

[ respective] Oxygen Deflagration Overpressure Limit [s] l l and the Oxygen Deflagration Temperature Limit.

15

• Hydrogen Deflagration Overprescure Limit Hydrogen 10 +

Concentration (%) i 5+ i 0 +----+----+----+----+----+--- l l 0 5 10 15 20 25 Drywell Pressure (psig) 15 + Oxygen Deflagration Overpressure Limit 1. Oxygen 10 +. Concentration (%) 5+ O +----+----+----+----+----+--- l l 0 5 10 15 20 25 Drywell Pressure (psig) PC,)(16 Revision 3J L

+. Document 8390-4 Emergency Procedure Guidelines 15 + Hydrogen Deflagration Temperature Limit Hydrogen 10 + Concentration (%) 5+ l l l l 0 +----+----+----+----+----+--- 150 160 170 180 190 200 Containment Temperature (aF) 15 + Oxygen Deflagration Temperature Limit Oxygen 10 +. Concentration (%) l 5+ 0 +----+----+----+----+----+--- l l l 150 160 170 180 190 200 Containment Temperature (=F) Execute Steps PC/H-1 and PC/H-2 concurrently. I l l PC/H-1 When RPV water level cannot be determined to be above C-164 in. (top of active fuel)] but onl y,i f drywell and suppression chamber hydrogen concentrations are below the [ respective] Hydrogen Deflagration Overpressure Limit [s] and the Hydrogen Deflagration Temperature Limit or drywell and l l suppression chamber oxygen concentrations are below the [ respective] Oxygen Deflagration Overpressure Limit [s] and the Oxygen Deflagration Temperature Limit, operate hydrogen ignitors. PC-)q{lg, Revision 3J E 2

4 I Document 8390-4 Emergency Procedure Guidelines PC/H-2 When hydrogen concentration in the drywell or suppression chamber reaches CO.5% (minimum detectable hydrogen concentration)], but only if the site radioactivity release rate is expected to remain below the site release ! #22 rate LCO, vent and purge the primary containment to restore and maintain the drywell and suppression chamber hydrogen concentrations below [0.5% (minimum detectable hydrogen concentration)] as follows: l If while executing the following steps the site 1

radioactivity release rate reaches the site 1

release rate

LCO, isolate the primary

! containment vent and purge. PC/H-2.1 Refer to Esampling procedure]. PC/H-2.2 If suppression pool water level is below [26 ft. 9 in. (elevation of the bottom of the suppression chamber vent)], vent the suppression chamber. If suppression pool water level is at or above C26 ft. 9 in. (elevation of the bottom of the suppression chamber vent)J cr if the suppression chamber cannot be vented, vent the drywell Eto atmosphere]. PC/H-2.3 If the suppression chamber or drywell can be vented Cto atmosphere], initiate and maximize the [ nitrogen] Ccontainment and) drywell purge flow. l Execute Steps PC/H-3 and PC/H-4 concurrently.. l PC,h(}7 Revision 3J L

Document 8390-4 Emergency Procedure Guidelines PC/H-3 Monitor and control hydrogen and oxygen concentrations in the drywell. PC/H-3.1 When drywell hydrogen concentration reaches [1% (minimum hydrogen concentration for recombiner operation or minimum detectable hydrogen concentration, whichever is higher)3: 1. If drywell hydrogen concentration is below [6% (maximum hydrogen concentration for recombiner operation or the lowest hydrogen concentration which can support a deflagration, whichever is lower)3 or drywell oxygen concentration is below [5% (maximum oxygen concentration for recombiner operation er the lowest oxygen concentration which can support a deflagration, whichever is lower)3, place hydrogen recombiners in service taking suction directly on the drywell. 2. If drywell and suppression chamber hydrogen concentrations are below the [ respective] Hydrogen Deflagration Overpressure Limit [s] and the Hydrogen Deflagration Temperature Limit or drywell and suppression chamber oxygen concentrations are below the [ respective] Oxygen i Deflagra' ' on Overpressure Limit [s] and the w,ygen Deflagration Temperature Limit, operate hydrogen ignitors. PC,h( g Revision 3J

a Document 8390-4 Emergency Procedure Guidelines PC/H-3.2 When drywell hydrogen concentration reaches [4% (lowest hydrogen concentration which can support an upward flame propagation)J but only if ERPV pressure is below the Primary Containment Pressure Limit and either] drywell and suppression chamber hydrogen concentrations are below the [ respective] Hydrogen Deflagration Overpressure Limit [s] and the Hydrogen Deflagration Temperature Limit or drywell and suppression chamber oxygen concentrations are below the Erespective] Oxygen Deflagration Overpressure LimitEs3 and the Oxygen Deflagration Temperature Limit, operate the drywell hydrogen mixing system. 50 + Suppression Chamber Pressure 25 + Primary Containment (psig) Pressure Limit O +----+----+----+----+---- 0 10 20 30 40 Primary Containment Water Level (ft.) PC/H-3.3 When drywell hydrogen concentration reaches E6% (maximum hydrogen concentration for recombiner operation or the lowest hydrogen concentration which can support a deflagration, whichever is lower)] and drywell oxygen concentration reaches [5% (maximum oxygen concentration for recombiner operation or the lowest oxygen concentration which can support a ( deflagration, whichever is lower)], secure any hydrogen recombiner taking suction on the drywell. ,pa I PC-p(gg Revision 3J i

Document 8390-4 Emergency Procedure Guidelines 4 PC/H-3.4 [When drywell hydrogen concentration reaches 6% (lowest hydrogen concentration which can support a deflagration) and drywell oxygen concentration reaches 5% (lowest oxygen concentration which can support a deflagration),3 EMERGENCY RPV DEPRESSURIZATION IS REQUIRED; enter [ procedure developed from the RPV Control Guideline] at [ Step RC-13 and execute it concurrently with this procedure. PC/H-3.5 Continue in this procedure at [ Step PC/H-53. 4 f 1 } PC-kgg-Revision 3J L

Document 8390-4 Emergency Procedure Guidelines PC/H-4 Monitor and control hydrogen and oxygen concentrations in the suppression chamber. i PC/H-4.1 When suppression chamber hydrogen concentration reatnes [1% (minimum hydrogen concentration for recombiner operation or niinimum detectable hydrogen concentration, whichever is higher)J: 1. If suppression chamber hydrogen concentration is below [6% (maximum hydrogen concentration for recombiner operation or the lowest hydrogen concentration which can support a deflagration, whichever is lower)] or suppression chamber oxygen concentration is below E5% (maximum oxygen concentration for recombiner operation or the lowest oxygen concentration which can support a deflagration, whichever is lower)3, place hydrogen recombiners in service taking suction directly from the suppression chamber. If no hydrogen recombiner car. be placed in service taking suction directly from the suppression chamber but only if the drywell hydrogen concentration is below [6% (maximum hydrogen concentration for recombiner operation or the lowest hydrogen concentration which can support a deflagration, whichever is lower)J or dr ywel l oxygen concentration is below Eu% (maximum oxygen concentration for recombiner operation or the lowest oxygen concentration which can support a deflagration,-whichever is lower)], place hydrogen recombiners in service taking suction indirectly from the suppression chamber by way of the drywell. l l l l l PC,fy'g[ Revision 3J L

Document 8390-4 Emergency Procedure Guidelines 2. If drywell and suppression chamber hydrogen concentrations are below the [ respective] Hydrogen Deflagration Overpressure Limit [s] and the Hydrogen Deflagration Temperature Limit or drywell and suppression chamber oxygen concentrations are below the [ respective] Oxygen Deflagration Overpressure LimitEs3 I and the Oxygen Deflagration Temperature Limit, operate hydrogen I ignitors. PC/H-4.2 When suppression chamber hydrogen concentration reaches [6% (maximum hydrogen concentration for recombiner operation or the lowest hydrogen concentration which can support a deflagration, whichever is lower)3 and suppression chamber oxygen concentration reaches C5% (maximum oxygen concentration for recombiner operation or the lowest oxygen concentration which can support a deflagration, whichever is lower)], secure any hydrogen recombiner taking suction directly on the suppression chamber. f 1 l PC,hp'f f, Revision 3J l

Document 8390-4 Emergency Procedure Guidelines PC/H-5 When hydrogen concentration in either the drywell or the suppression chamber reaches [6% (lowcst hydrogen concentration which can support a deflagration)J[8% (maximum hydrogen concentration expected when ignitors are functioning properly)J and the drywell or suppression chamber oxygen concentration is above C5% (maximum oxygen concentration for recombiner operation or the lowest oxygen concentration which can support a deflagration, whichever is lower)J but only if the offsite radioactivity release rate is expected to remain below the offsite release rate which requires an Alert, vent and purge the primary containment to restore and maintain the drywell and suppression chamber hydrogen concentrations below [6% (maximum hydrogen concentratior, ter recombiner operation or the lowest hydrogen concentration which can support a deflagration, whichever is lower)] [or the drywell and suppression chamber oxygen concentrations below 5% (maximum oxygen concentration for recombiner operation or the lowest oxygen concentration which can support a deflagration, whichever is lower)] as follows: If while executing the following steps the offsite radioactivity release rate reaches the

offsite release rate which requires an Alert, i

isolate the primary containment vent and purge. :

PC/H-5.1 Refer to [ sampling procedure]. PC/H-5.2 If suppression pool water level is below [24 ft. 6 in. (elevation of suppression pool spray no::les)], : #18 : initiate [Mk I/IIJ suppression pool sprays. l PC/H-5.3 If suppression pool water level is below [26 ft. 9 in. (elevation of the bottom of the suppression chamber vent >], vent the suppression chamber. l l If suppression pool water l evel is at or above [26 ft. 9 in. (elevation of the bottom of the suppression chamber vent)] f or if the suppression chamber cannot be j vented, vent the drywell. PC-kQ,3 Revision 3J

~. Document 8390-4 Emergency Procedure Guidelines PC/H-5.4 If the suppression chamber or drywell can be vented Eto atmosphere], initiate and maximize the [ nitrogen] [ containment and] drywell purge flow. PC/H-5.5 If Esuppression chamber temperature and drywell pressure are below the Drywell Spray Initiation Pressure Limit], Eshut down recirculation pumps and drywell cooling fans and] initiate drywell sprays trestricting flow rate to less than 720 gpm (Maximum Drywell Spray Flow Rate Limit)]. 400 + l Drywell Spray Initiation Pressure 300 + Limit Suppression l Chamber 200 + Temperature (oF) 1. 100 + l l 0 +----+----+----+----+-- 0 10 20-30 40 Drywell Pressure (psig) l l PC-)(gjl Revision 3J t

Document 8390-4 Emergency Procedure Guidelines PC/H-6 When the drywell or suppression chamber hydrogen concentration reaches the [ respective] Hydrogen Deflagration Overpressure Limit or the Hydrogen i Deflagration Temperature Limit and the drywell or i suppression chamber oxygen concentration reaches the [ respective 1 Oxygen Deflagration Overpressure Limit or the Oxygen Deflagration Temperature Limit, secure hydrogen mixing systems and ignitors and, irrespective of the offsite radioactivity release rate, vent and purge the primary containment to restore and maintain the drywell and suppression chamber hydrogen concentrations below the [ respective] Hydrogen Deflagration Overpressure LimitEs] and the Hydrogen Deflagration Temperature Limit [or the drywell and suppression chamber oxygen concentrations below the Crespective] Oxygen Deflagration Overpressure Limit [s] and the Oxygen Deflagration Temperature Limit] as follows: l PC/H-6.1 If [ suppression chamber pressure it above 1.7 psig (Mark III Containment Spray Initiation Pressure Limit)3 Esuppression pool water level is l #18 : below 24 f t. 6 in. (elevation of suppression pool spray nozzles)], initiate suppression pool sprays. PC/H-6.2 If suppression pool water level i s below [26 ft. 9 in. (elevation of the cottom of the suppression chamber vent)], vent the suppression chamber. If suppression pool water level is at or above C26 ft. 9 in. (elevation of the bottom of the suppression chamber vent) or if the suppression chamber cannot be i vented, vent the drywell. l PC/H-6.3 If the suppression chamber or drywell can be vented Eto atmosphere], initiate and maximize the Cnitrogen] Ccontainment and] drywell purge flow. PC-ggp Revision 3J

Document 8390-4 Emergency Procedure Guidelines 1 PC/H-6.4 If Esuppression chamber temperature and drywell pressure are below the Drywell Spray Initiation Pressure Limit], Eshut down recirculation pumps and drywell cooling fans and] initiate drywell sprays [ restricting flow rate to less than 720 gpm (Maximum Drywell Spray Flow Rate i Limit)]. PC/H-7 If the drywell or suppression chamber hydrogen I concentration cannot be restored and maintained below the Crespective] Hydrogen Deflagration Overpressure Limit and the Hydrogen Deflagration Temperature Limit and the drywell cr suppression chamber oxygen concentration cannot be restored and maintained below the [ respective] Oxygen Deflagration Overpressure Limit and the Oxygen l Deflagration Temperature Limit, then irrespective of whether adequate core cooling is assured: PC/H-7.1 If Esuppression chamber pressure is above 1.7 psig (Mark III Containment Spray Initiation Pressure Limit)J [ suppression pool water level is below 24 ft. 6 in. (elevation of suppression pool spray nozzles)], initiate suppression pool sprays. PC/H-7.2.If Esuppression chamber temperature and ,drywell pressure are below the Drywell Spray Initiation Pressure Limit], Eshut down recirculation pumps and drywell cooling fans and] initiate drywell sprays Crestricting flow rate to less thar 720 gpm (Maximum Drywell Spray Flow Rate Limit)]. l l PC-g2h Revision 3J L

SECONDARY CONTAINMENT CONTROL CUIDELINE i i PURPOSE The purpose of this guideline is to: o Protect equipment in the secondary containment, Limit radioactivity release to the secondary containment, and either: e Maintain secondary containment integrity, or e Limit radioactivity release from the secondary containment. e ENTRY CONDITIONS The entry conditions fer this guideline are any of the following secondary containment conditions: Differential pressure at or above 0 in. of water e An area temperature above the maximum normal operating temperature e A HVAC cooler differential temperature above the maximum normal operating e dif ferential temperature e A HVAC exhaust radiation level above the maximum normal operating radiation level An area radiation level above the maximum normal operating radiation level e A floor drain sump water level above the maximum normal operating water level e An area water level above the maximum normal operating water level e ) l a, (SC-1) Rev. 3G

OPERATOR ACTIONS ) 1 If while executing the following steps secondary containment HVAC exhaust radiation level exceeds [20 ar/hr (second-fry containment HVAC isolation set point)): Confirm or manually initiate isolation of secondary containment o HVAC, and Confirm initiation of or manually initiate SBGT [only when the e space being evacuated is below 212 F]. If while executing the following steps: e Secondary containment HVAC isolates, and e Secondary containment HVAC exhaust radiation level is below [20 mr/hr (secondary contair. ment HVAC isolation setpoint)], restart secondary containment HVAC. , f,24, Irrespective of the entry condition, execute (Steps SC/T, SC/R, and SC/L] concurrently. SC/T Monitor and control secondary containment temperatures. SC/T-1 Operate available area coolers. D {;T /~ E ', .r (SC-2) Rev. 3G L-

SC/ T-2 If secondary containment HVAC exhaust radiation level is below [20 ar/hr (secondary containment HVAC isolation setpoint)], operate available secondary containment HVAC. SC/T-3 If any area temperature exceeds its daximum normal operating temperature, isolate all systems that are discharging into the area except systems required to shut down the reactor, assure adequate core cooling, or suppress a working fire. SC/T-4 If a primary system is discharging into an area, then before any area temperature reaches its maximum safe operating temperature, enter [ procedure developed from the RPV Control Guideline] at [ Step RC-1] and execute it concurrently with this procedure. SC/T-5 If a primary system is discharging into an area and an area temperature exceeds its maximum safe operating temperature in more than one area, EMERGENCY RPV DEPRESSURIZATION IS REQUIRED. SC/R Monitor and control secondary containment radiation levels. SC/R-1 If any area radiation level exceeds its maximum normal operating radiation level, isolate all systems that are discharging into the area except systems required to shut down the reactor, assure adequate core cooling, or suppress a working fire. SC/R-2 If a primary system is discharging into an area, then before any area radiation level reaches its maximum safe operating radiation level, enter [ procedure developed from the RPV Control Guideline] at [ Step RC-1] and execute it concurrently with this procedure. (SC-3) Rev. 3G L

SC/R-3 If a primary system is discharging into an area and an area radiation level exceeds its maximum safe operating radiation level in more than one area, EMERGENCY RPV DEPRESSURIZATION IS REQUIRED. SC/L Monitor and control secondary containment water levels. SC/L-1 If any floor drain sump or area water level is above its maximum normal operating water level, operate available sump pumps to restore and maintain it below its maximum normal operating water lavel. If any floor drain sump or area water level cannot be restored and maintained below its maximum normal operating water level, isolate all systems that are discharging water into the sump or area except systems required to shut down the reactor, assure adequate core cooling, or suppress a workirg fire. SC/L-2 If a primary system is discharging into an area, then before any floor drain sump or area water level reaches its maximum safe operating water level, enter [ procedure developed from the RPV Control Guideline] at [ Step RC-1] and execute it concurrently with this procedure. SC/L-3 If a primary system is discharging into an area and a floor drain sump or area water level exceeds its maximum safe operating water level in more than one area, EMERGENCY RPV DEPRESSURIZATION IS REQUIRED. (f [.,h j (SC-4) Rev. 3G

i I l l TABLE 1 OPERATING VALUES OF SECONDARY CONTAI!PTf7 FARAMETERS l Martaus Normal Maniaua Safe Secondaty Costainment Parameter / location Alaru Operating value Operating value o Differential pressure (La. water) (ie. water) (in. water) - Basetor Building /outside air 0 - Refuel Floor /outside air 0 o Area temperature M M b - RWCU "A" pg room 158' - 130 - RWCU "B" pump roce 158' 130 - - RWCU Rs room 158' at Es.- 130 - - RWCU na room 158' disch-E.V.- 120 - - RWCU phase sep. room 158' -- 130 =- - RWCU holding Pump room 185 - 130 - NE Diagonal -- 175 - - - SE Dissonal ----- 175 ~~ - MFCI room, area A - 175 - - MFCI toon, area 3 - 175 - EPCI room, area C - 175 - Torus room, westwall 200 - Torus room, eastwell 200 - Torus roce, northws11 -- 200 - Torus room, southwall 200 - Mais steam tunnel - 160 - SE, teactor 130 elev., area A - 200 - St. Reactor 130 elev., area B - 200 - WW Diagonal, area A - 200 - WW Diagonal, area 3 200 - WW Diagonal, area C 200 l i i hicalvaluesnotavailabl,e. DRf

I l l I l I l t TABLE 1 OPERATING VALUES OF SECONDART CONTAINMENT FARAMETERS (Continued) Secondary Containment Parameter / Location Maximan Normal' Maziam Safe 1 Alarm Operatine Value Operating value o IVAC cooler differential temperature M M b - EWCD "A" P ep Rose 75 -- - EWCU "B" Pump Room - 75 - RWCU Es Room 158 at Esa 75 - BWCU Em Room ISR' disch. to Botwell 75 - RWCU phase separator room 150' 75 - RWCU holdint pump room 185' 75 - NE diagonal ---- 50 - SE diagonal -- 30 - EPCI Room. Cooler A - 40 - EPCI Room. Cooler R 40 - W Diagonal. Cooler A - 40 - W Diagonal. Cooler 3 - 40 - W Diagonal. Cooler C - 40 - Torue Room. W -- - - Torue Rooe. West - 40 - Torue Room. W ---- 40 - Torus Room. West - 40 - Torus. Room W - 40 - - Torua Roon West -- 40 - - ~ ~ - - Torve Room. W ---- 40 - - Torue Room. West 40 - - Main Steam Tunnel. Cooler A - 70 - Maie Steam Tunnel. Cooler R 70 M l ) (SC-6) Rev. 3G ical values not available. I i+ b-

t TABLE 1 OPERATING VALUES OF SECONDARY CONTAINMENT FARAMETERS (Continued) Secondary Centstament Parameter /locaties Alars Maximum Normal Maxim e Safe l operating Value operating value e ET&C sahaust radiation level above (ar/hr) (ar/hr) (ar/hr) - Basetor Building 20 - Refuel Floor - 20 e Area radiation level (gr/ht) Car /hr) (ar/hr) ~ - 150' Southeast Area - 154' Northeast Area 15 - 150' Northwest Area - 15 - 130' Northeast Work Area - -- 15 - 130' Southeast Work Area - - Decontaminetton Pump & Equipment Roos -- 20 - - South CRD Eydraulic Unita - 15 - Spent Fuel Pool Passageway ' _ _ 15 - 195' operating Floor 15 - 185' Sample Panel Area 15 - CRD Repair Area - 20 - - 195' BWCU control Panel Area ----- 15- - RCIC Iquipment Area - 20 - CRD F mp Room SW ~ 20 - EER & Core Spray Room Northeast - 20 - RER & Core Spray Room Southeast 20 - Fuel Peel,Denia Panel Area 20 4 (SC-7) Rev. 3G ical values not available. Dpj'~-

b TAsLE 1 OPERATING VALUES OF SECONDART CONTAINMENT PARAMETERS (Continued) 1 1 Maximun Normal Maniaua Safe secondary Containeest Paramster/tacation Alara Operating value operating value e Floor drain svar water level M M g - Suny A (5.E. Dissonal) 47 - same n (s.v. Dissonal) 32 e Area water level M M 11M - CRD Compartment 7 - RCIC Compartment 7 - R3 NE Corner RM 7 - 13 SE Corner RM 7 - IFCI Compartment 7 - Torus Compartment NW -- 7 -- - Torus Compartment NE - 7 --. ~~ - Torus Cosportment SE - 7 -- .- Torus Compartment SW - 7-l l (sC-s) Rev. 3G teal values not available. D%

l e' Document B390-4 Emergency Procedure Guidelines j RADIOACTIVITY RELEASE CONTROL GUIDELINE PURPOSE The purpose of this guideline is to limit radioactivity release into areas outside the primary and secondary containments. ENTRY CONDITIONS The entry condition for this guideline is: Offsite radioactivity release rate above the offsite release o I rate which requires an Alert. OPERATOR ACTIONS RR-1 Isolate all primary systems that are discharging into areas outside the primary and secondary containments except systems required to assure adequate core cooling or shut t down the reactor. RR-2 If ot f site radioactivity release rate appr oaches or exceeds the offsite release rate which requires a General Emergency and a primary system is discharging into an area outside the primary and secondary containments, EMERGENCY RPV DEPRESSURIZATION IS REQUIRED; enter Cprocedure developed from the RPV Control Guideline] at [ Step RC-13 and execute it concurrently with this procedure. i l l l l RR-1 Revision 31

l CONTINGENCY #1 LEVEL RESTORATION If while executing the following steps: Boron Injection is required, enter [ procedure developed from e CONTINCENCY #7]. RPV water level cannot be determined, RPV FLOODING IS REQUIRED; e enter [ procedure developed f rom CONTINGENCY #6]. RPV Flooding is reqaired, enter [ procedure developed from e CONTINGENCY #6]. Cl-1 Initiate IC. Cl-2 Line up for injection and start pumps in 2 or more of the following injection subsystems: l e Condensate o EPCS e LPCI-A e LPCI-B e LPCI-C e LPCS-A e LPCS-B {} f)L }' ' *' (CJ-1) Rev. 3G I

If less than 2 of the injection subsystems can be lined up, commence lining up as many of the following alternate injection subsystems as possible: o RHR service water crosstie e Fire system o Interconnections with other units e ECCS keep-full systems e SLC (test tank) e SLC (boron tank) Cl-3 Monitor RPV pressure and water level. Continue in this procedure at the step indicated in the following table. RPV PRESSURE REGION [425 psig]1 [100 psig]2 HIGH INTERMEDIATE LOW i$ INCREASING Cl-4 Cl-5 Cl-6 is: h DECREASING Cl-7 Cl-8 1(RPV pressure at which LPCS shutoff head is reached) (HPCI or RCIC low pressure isolation setpoint, whichever is higher) If while executing the following steps: The RPV vater level trend reverses or RPV pressure changes region, e return to [ Step Cl-3]. RPV water level drops belov [-146 in. (ADS initiation setpoint)), e prevent automatic initiation of ADS. (cl-2) Rev. 3G DRG i

Cl-4 RPV WATER LEVEL INCREASING, RPV PRESSURE HIGH Etter [ procedure developed from the RPV Control Guideline) at [ Step RC/L]. Cl-5 RPV WATER LEVEL INCREASING, RPV PRESSURE INTERMEDIATE Tf HPCI and RCIC are not available and RPV pressure is increasing, EMERGENCY RPV DEPRESSURIZATION IS REQUIRED. When RPV pressure is decreasing, enter [ procedure developed from the RPV Control Guideline] at [ Step RC/L]. If HPCI and RCIC are not available and RPV pressure is not increasing, enter [ procedure developed from the RPV Control Guideline] at [ Step RC/L]. Otherwise, when RPV water level reaches [+12 in. (lov level scram setpoint)], enter (procedure developed from the RPV Control Guideline] at [ Step RC/L]. Cl-6 RPV WATER LEVEL INCREASING, RPV PRESSURE LOW If RPV pressure is increasing, EMERGENCY RPV DEPRESSURIZATION IS REQUIRED. When RPV pressure is decreasing, enter [ procedure developed from the RPV Control Guideline] at [ Step RC/L]. Otherwise, enter [ procedure developed from the RPV Control Guideline) at [ Step RC/L]. Cl-7 RPV WATER LEVEL DECREASING, RPV PRESSURE HIGH OR INTERMEDIATE If HPCI or RCIC is not operating, restart whichever is not operating. l If no injection subsystem is lined up for injection with at least one pump { running, start pumps in alternate injection subsystems which are lined up for injection. DR F' (Cl-3) Rev. 3G N

\\.. l l - When RPV water level drops to [-164 in. (top of active fuel)]: e If no system, injection subsystem or alternate injection subsystem is lined up with at least one pump running, STEAM COOLING IS REQUIRED. When any system, injection subsystem or alternate injection subsystem is lined up with at least one pump running, return to [ Step C1-3]. Otherwise, EMERGENCY RPV DEPRESSURIZATION IS REQUIRED. e When RPV water level is increasing or RPV pressure drops below [100 psig (HPCI or RCIC low pressure isolation setpoint, whichever is higher)], return to [ Step C1-3]. Cl-8 RPV WATER LEVEL DECREASING, RPV PRESSURE LOW [If no RFCS or LPCS subsystem is operating,] start pumps in alternate injection subsystems which are lined up for injection. If RPV pressure is increasing, EMERGENCY RPV DEPRESSURIZATION IS REQUIRED. When RPV water level drops to [-164 in. (top of active fuel)], enter [ procedure developed from CONTINGENCY #4]. i (]I git. (Cl-4) Rev. 3G b - I

Cl-3 MONITOR RPV PRESSURE AND WATER LEVEL. CONTINUE IN TilIS PROCEDURE AT Tile STEP INDICATED IN Tile FOLLOWING TABLE: RViMSIR KGlai ir(25 PSIG (*) IE D PSIb (') HIGI INTEiMlllATE LiW c E1:3 EM EL4 BIB IIRIIIRE ID0ml) FRH TIE IF El 40 REIC NE IUT AmilARE A0 WV IF NV IW39K IS Il0EAS14, DGDEY h RV (DITRL WIEllEl Ai ISTIP IE/LI. iW33E IS IMOEASil0, DUGKY RV IIFESSlRIZ-RV (URSSRilATl04 IS EWIG. lHJi m All01 IS EEllD. IKA RV IMS3R IS ECRAS-EV IRSSE IS EUEASli, EJfD IIW)- E a Illi, DfD IIMIIIIR EMlmIl FM11 TE RV (Il1R KM11HI) FRH TK WV (D(TRL D

== M (IIIIRL WlElliti Al ISTIP K/LI. WlEllEl Ai ISTIP K/LI. p IF IRI NO EIC AE M)T AVAllAlti 40 RV IW3SE 01)UWlE, DiB llWIIIIK EMIRD 0 IS iUF IKKASli, GliiR liMI111K ILMlfHl) FMH FMll TK RV GIITRL WlEllEl At h TK RV QUIRL WilIlliEl Al ISlIP K/LI. IsrJ' K/Lt. H Ol}UNISE, IKH NV IRD LIM 1 KA00) 1*12 trl. (LDi o O LIML SOWI SETIVlill)l, O(B flWIIIIR ILMimD h FMM TK RV QMIRL WidLIEl Al ISitP K/LI. y y g W M 3 IF IFCI OR llCIC IS IIOT OPERATillG, RESTART WHICHEVER IS NOT OPERATING. I ARTIUf5 E IF 110 tilJECTlall SUBSYSTEM IS LillED UP FOR INJECTION WITH AT LEAST OE PUlf h pg ggg RUllfillIG, START PulFS IN ALTERNATE INJECil0ll SUBSYSTEMS WHICH ARE LINED UP FON o IN E TION. gpgypggggggg g gg,ggggy gy ggpg39,g737lg, g3 gggg, g E WHEN RPV MTER LEVEL DROPS TO l-IFA IN, (TOP OF ACTIVE FUEL)l: lH11 RV WB LIWL DRPS TO I-ifA I;I. O h GIP & EllE fML)I Di1IR llWIIIRE 4, Q $IFA0 SYSTEM,INJECTI0ltSUBSYSTEMORALTERNATEINJECil0NSUBSYSTENISLidED RMlDID IMM QNillGKY fiel. UP WiiH AT LEAST ONE PUlf RtMNillG, STEAfl C00LiflG IS REQUIRED. WHEN ANY SYSTEH, lllJECil0ll SUBSYSTEM OR ALTERNATE INJECil0N SUBSYSTEM IS LINED UP WliH Al LLAST OllE PUlf RUNfilllG, RETURN TO STEP Cl-31. $0TETollSE, EERGENCY RPV DEPRESSURIZATI0ll IS REQUIRED, WHEd RPV WATER LLVEL IS lilCREASillG OR RPV PRESSUE DROPS KLOW 1100 PSIG (HPCI OR RCIC LOW PHLSSUNE P lSOLAil0M SETPoldi, WHICEVER IS HIGHER)l,.'IEIUitd TO STEP Cl-31. IF WHILE EXECUTING THE FOLLOWING STEPS TIIE RPV WATER LEVEL TREND REVERSES OR RPV PRESSURE CHANGES REGION, RETURN TO (STEP Cl-3). O y

• RPV PRESSURE AT WilICil LPCS SIIUTOFF llEAD IS REACllED. +11PCI CR RCIC LOW PRESSURE IS0ll. TION SETPOINT, WHICllEVER 7.:=

IS IIIGilER. ..3

CONTINCENCY #2 EMERGENCY RPV DEPRESSURIZATION C2-1 When either: 813,f14 Boron Injection is required and all injection into the e RPV except from boron injection systems and CRD has been I terminated and prevented, or Boron Injection is not required, e i C2-1.1 Initiate IC. C2-1.2 If suppression pool water level is above [4 f t. 9 in. (elevation of top of SRV discharge device)]: i e Open all ADS valves. e If any ADS valve cannot be opened, open other SRVs until [7 (number of SRVs dedicated to ADS)] valves are open. C2-1.3 If less than [3 (Minimum Number of SRVs Required for Emergency Depressurization)] SRVs are open [and RPV

1. 22 pressure is at least 50 psig (Minimum SRV Re-opening Pressure) above suppression chamber pressure], rapidly depressurize the RPV using one or more of the following systems (use in order which will minimize radioactive release to the environment):

e Main condenser RER (steam condensing mode) e [0ther steam driven equipment] e e Nsin stesa line drains e HPCI steam line i e RCIC steam line e Bead vent ) e IC tube side vent (C2-1) Rev. 3G <T r..

l j l If RPV Flooding is required, enter [ procedure developed from CONTINGENCY #6]. C2-2 Enter [ procedure developed from the RPV Control Guideline]. at [ Step RC/P-3]. (C2-2) Rev. 3G k-

CONTINCENCY #3 STEAM COOLING C3-1 Confirm initiation of IC. I If while executing the following steps Emergency RPV Depressurisation is required or any system, injection subsystem, or alternate injection subsystem is lined up for injection with at least one pump running, enter [ procedure developed from CONTINGENCY #2]. If IC cannot be initiated: When RPV water level drops to [-272 in. (Minimum Zero-Injection RPV Water Level)] or if RPV vater level cannot be determined, open one SRV. When RPV pressure drops below [700 psig (Minimum Single SRV Steam Cooling Pressure)], enter [ procedure developed from CONTINGENCY #2]. (C3-1) Rev. 3G ) AFT m

CONTINGENCY #4 CORE COOLING WITHOUT LEVEL RESTORATION C4-1 Open all ADS valves.

1. 13 I

If any ADS valve cannot be opened, open other SRVs until [7 (number of SRVs dedicated to ADS)] valves are open. C4-2 Operate HPCS and LPCS subsystems with suction from the suppression pool. When at least one cora spray subsystem is operating with suction from the suppression pool and RPV pressure is below [310 psig (RPV pressure for rated LPCS or HPCS flow, whichever pressure is lower)], terminate injection into the RPV from sources external to the primary containment. C4-3 When RPV vater level is restored to [-164 in. (top of active fuel)], enter [ procedure developed from the RPV Control Guideline) at [ Step RC/L]. i l l l (ffff{f-l (C4-1) Rev. 3G l

i l 5 CONTINCENCY #5 l ALTERNATE SHUTDOWN COOLING l C5-1 Initiate suppression pool cooling. C5-2 Close the [RPV head vents,] MSIVs, main steam line drain valves, and HPCI and RCIC isolation valves. C5-3 Place the control switch for [one (Minimus Number of SRVs Required for Alternate Shutdown Cooling)] SRV[s] in the OPEN position. C5-4 Slowly raise RPV water level to establish a flow path through the open SRV back to the suppression pool. C5-5 Start one LPCS or LPCI pump with suction from the suppression pool. C5-6 Slowly increase LPCS or LPCI injection into the RPV to the maximum. C5-6.1 If RPV pressure does not stabilize at least [94 psig (Minimum Alternate Shutdown Coolins' RPV Pressure)] above suppression chamber pressure, start another LPCS or LPCI pump. C5-6.2 If RPV pressure does not stabilize below [172 psig (Maximum Alternate Shutdown Cooling RPV Pressure)], open another SRV. C5-6.3 If the cooldown rate exceeds [100 F/hr (maximum RPV cooldown rate LCO)], reduce LPCS or LPCI injection into the RPV until the cooldown rate decreases below [100 F/hr (maximum RPV cooldown rate LCO)] [or RPV pressure decreases to within 1 50 psig (Minimus SRV Re-opening Pressure) of suppression chamber pressure, whichever occurs first). C5-7 Control suppression pool temperature to maintain RPV water temperature above [70 F (RPV NDTT or head tensioning limit, whichever is higher)]. C5-8 Proceed to cold shutdown in accordance with [ procedure for cooldown to cold shutdown conditions). O' (C5-1) Rev. 3G U i'n C J 7; u

Document C390-4 Emsrgsney ProcOdure Guid31inco CONTINGENCY #6 RPV FLOODING C6-1 If at least [3 Minimum Number of SRVs Required f or j Emergency Depressuri:ation)3 SRVs can be opened or if HPCS or motor driven feedwater pumps are available for injection, close the MSIVs, main steam line drain valves, IC, HPCI, RCIC and RHR steam condensing isolation valves. C6-2 If any control rod as not inserted beyond position [O6 (maximum subcritical banked withrawal position)3: C6-2.1 Terminate and prevent all injection into the RPV except f rom boron injection systems and CRD until RPV pressure is below the Minimum Alternate RPV Flooding Pressure. l Minimum Alternate RPV Number of open SRVs i Flooding Pressure (psig)!

-_---_---_--___--_-_--:--___--------_---------__-g

[ 7 or more i 110 3 [ 6 i 135 3 I I i i [ 5 1 165 3 1 l E 4 l 210 3 I I I [ 3 l 280 3 I i E2 430 3 I I I i [ 1 870 3 i If less than [1 (minimum number of SRVs for which the Minimum Altarnate RPV Flooding Pressure is below the lowest SRV lifting pressure)3 SRVCs3 can be opened, continue in this procedure. l l C6-1 Revision 31 l

Document 8390-4 Emergency Procedure Guidelines \\ l l If while executing the following step, RPV water level I

can be determined and RPV Flooding is not required, I

enter Cprocedure developed from CONTINGENCY

1. 73 and I

[ procedure developed from the RPV Control Guideline] at I

[ Step RC/P-43 and execute these procedures 1 I

concurrently.

C6-2.2 Commence and slowly increase injection into the RPV with the following systems until at least [1 1 (minimum number of SRVs for which the Minimum Alternate RPV Flooding Pressure is ! #25 : below the lowest SRV lifting pressure)3 SRVCs3 are open and RPV pressure is above the Minimum Alternate RPV Flooding Pressure: o Motor driven feedwater pumps o Condensate pumps o CRD [o LPCI] If at least [1 (minimum number of SRVs for which the Minimum Alternate RPV Flooding Pressure is below the lowest SRV lifting pressure)3 SRVEs3 are I not open or RPV pressure cannot be increased to above the Minimum Alternate RPV Flooding Pressure, commence and slowly increase injection into the RPV with the f ollowing systems until at least [1 I (minimum number of SRVs f or which the Minimum Alternate RPV Flooding Pressure is below the lowest SRV lifting pressure)3 SRVEs3 are open and RPV I pressure is above the Minimum Alternate RPV Flooding Pressure: o HPCS o LPCS to RHR service water crosstie 3 to Fire System 3 [o Interconnections with other units 3 [o tCCS keep-full systems 3 C6-2 Revision 31

Document 8390-4 Emergency Procedure Guidelines et i C6-2.3 Maintain at least [1 (minimum number of SRVs for I which the Minimum Alternate RPV Flooding Pressure is below the lowest SRV lif ting pressure) 3 SRVEs3 I and RPV pressure above the Minimum Alternate i open RPV Flooding Pressure but as low as practicable by I throttling injection. C6-2.4 When: o All control rods are inserted beyond position EO6 (maximum subcritical banked withdrawal position)3, or o The reactor is shutdown and no baron has been injected into the RPV, continue in this procedure, t ( C6'-3 Revision 3I

9 Document 8390-4 Emergency Procedure Guidelines C6-3 If RPV water level cannot be determined: C6-3.1 Commence and increase injection into the RPV with the f ollowing systems until at least E3 (Minimum Number of SRVs Required for Emergency Depressurization)3 SRVs are open and RPV pressure is not decreasing and is C77 psig (Minimum RPV i Floeding Pressure)3 or more above suppression I chamber pressures o HPCS o Motor driven feedwater pumps o LPCS o LPCI o Condensate pumps o CRD [o RHR service water crosstie 3 [o Fire System 3 [o Interconnections with other units 3 [o ECCS Leep-full systems 3 [o SLC (test tank) 3 [o SLC (boron tank) 3 C6-3.2 Maintain at least C3 (Minimum Number of SRVs Required for Emergency Depressurization)3 SRVs open and RPV pressure at least [77 psig (Minimum RPV Flooding Pressure)] above suppression chamber pressure but as low as practicable by throttling i injection. l I 1 C6-4 Revision 3I

Document 8390-4 Emergency Procedure Guidelines C6-4 If RPV water level can be determined, commence and increase injection into the RPV with the following systems until RPV water level is increasing: o HPCS o Motor driven feedwater pumps o LPCS o LPCI o Condensate pumps o CRD [o RHR service water crosstie 3 [o Fire System 3 [o Interconnections with other units 3 to ECCS keep-full systems 3 [o SLC (test tank) 3 [o SLC (boron tank) 3 C6-5 If RPV water level cannot be determined: C6-5.1 Cor.inue injecting water into the RPV until [ temperature near the cold reference leg instrument vertical runs 3 is below 212=F and RPV water level instrumentation is available. l If while executing the following steps, RPV water level I

can be determined, continue in this procedure at EStep i

! C6-63. I C6-5.2 If it can be determined that the RPV is filled or if RPV pressure is at least [77 psig (Minimum RPV Flooding Pressuro)3 above suppression chamber . pressure, terminate all injection into the RPV and reduce RPV water level. l l l C6-5 Revision 3I

Document 9390-4 Emergency Procedure Guidelines C6-5.3 If RPV water level indication is not restored within the Ma>:imum Core Uncovery Time Limit af ter commencing termination of injection into the RPV, return to [ Step C6-33. i 1 i C6-6 Revision 31 L_ l

Document 3390-4 Emergency Procedure Guidelines C6-6 When suppression chamber pressure can be maintained below the Primary Containment Design Pressure, enter [ procedure developed from the RPV Control Guideline 3 at [ Steps RC/L and RC/P-43 and execute these steps concurrently. i C6-7 Revision 31 t

r Document 8390-4 Emergency Procedure Guidelines CONTINGENCY #7 LEVEL / POWER CONTROL 1 I l If while executing the following steps: 1 i ! o RPV water level cannot be determined, RPV FLDODING IS I I REDUIRED; enter [ procedure developed from CONTINGENCY I i 1 I

1. 63.

I I I o RPV Flooding is required, enter Eprocedure developed i I from CONtTINGENCY #63. _____________________________________________________==_-===___ C7-1 If: o Reactor power is above E 3*/. (APRM downscale trip)3 or cannot be determined, and o Suppression pool temperature is above [the Boron Injection Initiation Temperature 3, and I l t Baron i 130 + Injection i 1...... Initiation i Suppression Temperature i Pool 120 + 1 Temperature I ("F) I I I 110 + i i l i 100 +- -+---+---+---+---+---+---+ 1 0 1 2 3 4 5 6 7 i Reactor Power (%) I o Either an SRV is open or opens or drywell pressure is above [2.0 psig (high drywell pressure scram i setpoint)3, lower RPV water level by terminating and preventing all injection into the RPV except from boron I #26 i injection systems and CRD until either 1 .l C7-1 Revision 31 i ) l

r-Document 8390-4 Emergency Procedure Guidelines o Reactor power drops below E3% (APRM downscale trip)3, or o RPV water level reaches E-164 in. (Flow Stagnation I I Water Level)], or o All SRVs remain closed and drywell pressure remains bel ow [2.0 psig (high drywell pressure scram setpoint)]. 1 If while executing the following steps Emergency RPV ! ! Depressurization is required, continue in this procedure at ! 1 I CStep C7-2.13. 1 ! If while executing the following step: I I I o Reactor power is above [3% (APRM downscale trip)3 or ! l cannot be determined, and i I I ! o RPV water level is above C-164 in. (Flow Stagnation I i l Water Level)], and I 1 I o Suppression pool temperature is above Cthe Boron i i Injection Initiation Temperature], and i I I I l o Either an SRV is open or opens or drywell pressure is ! I above [2.0 psig (high drywell pressure scram setpoint)3, I I I ! return to [ Step C7-13. C7-2 Revision 31 L

( Document 8390-4 Emergency Procedure Guidelines l C7-2 Maintain RPV water level either: I #9, #10, #11, #25 1 o If RPV water level was deliberately lowered in [ Step C7-13, at the level to which it was lowered, or o If RPV water level was not deliberately lowered in [ Step C7-13, between [+12 in. (Iow level scram setpoint)3 and [+59 in. (high level trip setpoint)3, with the following systems: o Condensate /feedwater system [1110 - O psig (RPV pressure range f or system operation) 3 o CRD system C1110 - O psig (RPV pressure range for system operation)3 o RCIC system E1110 - 50 psig (RPV pressure I #12 I range f or system operation)] [o HPCI system [1110 - 100 psig (RPV pressure range for 3 [ system operation)J J Co LPCI system [250 - O psig (RPV pressure range for 3 [ system operation)J J If RPV water level cannot be so maintained, maintain RPV water level above [-164 in. (top of active fuel)]. i C7-3 Revision 31

l Document 9390-4 Emergency Procedure Guidelines l If RPV water level cannot be maintained above [-164 in. (top of active fuel)3, EMERGENCY RPV DEPRESSURIZATION IS REQUIRED: C7-2.1 Terminate and prevent all injection into the RPV except from boron injection systems and CRD until RPV pressure is below the Minimum Alternate RPV Flooding Pressure. 1 1 Minimum Alternate RPV i I Number of open SRVs i Flooding Pressure (psig)! __________________________g I C 7 or mora i 110 3 1 1 I I I [ 6 1 135 3 I I I i l [ 5 1 165 3 I I I I I i [ 4 1 210 3 I I I I I '80 3 I I [ 3 I i i C2 1 430 3 1 1 I I I I C 1 1 870 3 I i If less than C1 (minimum number of SRVs for which I the Minimum Alternate RPV Flooding Pressure is below the lowest SRV lifting pressure)3 SRVCs3 can I be opened, continue in this procedure. C7-2.2 Commence and slowly increase injection into the RPV with the following systems to I #25 1 restore and maintain RPV water level above t-164 in. (top of active fuel)3: o Condensate /feedwater system o CRD o RCIC to HPCI 3 to LPCI 3 C7-4 Revision 3I k

Document 8390-4 Emergency Procedure Guidelines If RPV water level cannot be restored and maintained above C-164 in. (top of active fuel)3, commence and slowly increase injection into the RPV with the following systems tc restore and maintain RPV water level above C-164 in. (top of active fuel)3: o HPCS l o LPCS to RHR service water crosstie 3 Co Fire System 3 Co Interconnections with other units 3 Co ECCS keep-full systems 3 ! If while executing the following step reactor power commences !

and continues to increase, return to CStep C7-13.

I C7-3 When C204 pounds (Hot Shutdown Baron Weight)3 of boron have been injected or all control rods are inserted beyond position CO6 (maximum subcritical banked withdrawal position)3, restore and maintain RPV water level between C+12 in. (low level scram setpoint)3 and C+5B in. (high level trip setpoint)3. If RPV water level cannot be restored and maintained above C+12 in. (low level scram setpoint)3, maintain RPV water level above C-164 in. (top of active f uel) 3. If RPV water level cannot be maintained above C-164 in. (top of active fuel)3, EMERGENCY RPV DEPRESSURIZATION IS REQUIRED; return to CStep C7-2.13. I 1 ternate Shutdown Cooling is required enter i

Cprocedure developed from CONTINGENCY #53.

I C7-4 When [ procedure f or cooldown to cold shutdown conditions 3 I is entered from Cprocedure developed from the RPV Control i Guideline 3 at CStep RC/P-53, proceed to cold shutdown in I accordance with Cprocedure for cooldown to cold shutdown conditions 3. l C7-5 Revision 31 k ~}}