ML20205C946

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Rev 3 to Fitzpatrick Emergency Procedure Guidelines
ML20205C946
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 09/06/1985
From:
POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:
Shared Package
ML20205C937 List:
References
PROC-850906, NUDOCS 8509230368
Download: ML20205C946 (58)
v • d • e


Text

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NEW YORK POWER AUTHORITY James A. FitzPatrick Nuclear Power Plant

' ATTACHMENT NO. 2 TO JPN-85-66 1

FitzPatrick Emergency Procedure Guidelines - Revision No. 3 1

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Prepared By / Date / $1' 6 .

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Revicion 3 incorporated changes which resulted frow the verification of draft revision 2 and are indicated. The verification of this EPG was done to Revision 3 of the BWR Owners Group Ceneric Emergency Procedure Guideline which has received a safety evaluation from the NRC. =

s Rev. No. 3 Date 08/85 Page I of $7 L -_ _ _ _ _ - - _ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

TABLE OF CONTENTS PAGE REV. NO.

COVER SHEET 1 3 TABLE OF CONTENTS 2 3 INTRODUCTION 3 3 OPERATOR PRECAUTIONS 6 3 GENERAL 6 3 SPECIFIC 11 3 RPV CONTROL GUIDELINE 14 3 RC/L 14 3 RC/P 16 2 RC/Q 20 3 PRIMARY CONTAIh?iENT CONTROL OUTLINE 24 2 SP/T 24 2 DW/T 25 3 l PC/P 27 2 SP/L 31 1 SECONDARY CONTAIhHENT CONTROL GUIDELINE 34 2 SC/T 35 1 SC/R 36 1

. SC/L 36 1 RADI0 ACTIVITY RELEASE CONTROL GUIDELINE 41 2 CONTINGENCY #1 LEVEL RESTORATION 42 2 CONTINGENCY #2 EMERGENCY RPV DEPRESSURIZATION 46 0 CONTINGENCY #3 STEAM COOLING 47 1 CONTINGENCY #4 CORE COOLING WITHOUT LEVEL RESTORATION 48 1 CONTINGENCY #5 ALTERNATE SIIUTDOWN COOLING 49 1 CONTINGENCY #6 RPV FLOODING 50 3 CONTINGENCY f7 LEVEL / POWER CONTROL 54 3 Rev. No. 3 Date 08/85 Page 2 of 57 L__.-____________-.--___________________

,, INTRODUCTION Based on the BWR Owner's Group Emergency Procedures Guidelines, the following symptomatic emergency procedure guidelines have been developed for FitzPatrick:

. RPV Control Guideline

. Primary Containment Control Guideline

. Secondary Containment Control Guideline

. Radioactive Release Control Guideline 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 or high drywell pressure conditions exist, a condition which requires MSIV isolation has occurred, or whenever a condition which requires a 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, drywell pressure, or suppression pool water level 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.

Figure 1, Operator Actions Flowchart, illustrates operator actions within the emergency procedure guidelines. Each action block states briefly the operator action and its purpose. The blocks are generally correlated from top (high RPV pressure) to bottom (RPV cold shutdown conditions) with a vertical RPV -

pressure / temperature scale to show continuity of the linked operator actions.

Eachblockisfurtheridentifiedbyanumbersymbol(e.g.,1Q[ ) which is keyed to the guidance steps.

Rev. No. 3 Date 08/85 Page 3 of 57

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

At various points through these guidelines, precautions are noted by the symbol

((l . The number within the box refers to a numbered " Caution" contained in the Operator Precautions section. These " Cautions" are brief and succinct red i

flags for the operator. '

l l 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 the Technical Specifications. This is not to imply that operation beyond the J

Technical Specifications is recommended 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 guide-lines 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 FitzPatrick's Technical Specifications or other licensing

, bases.

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The entry conditions for these emergency procedure guidelines are symptomatic of l l both emergencies and events which may degrade into emergencies. The guidelines specify actions appropriate for both. Therefore, entry into procedures developed i from these guidelines is not conclusive that an emergency has occurred. L i

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i Date 12/10/84 Page 4 of 57 '

TABLE I ABBREVIATIONS ADS -

Automatic Depressurization System APRM -

Average Power Range Monitor CRD -

Control Rod Drive CS -

Core Spray ECCS -

Emergency Core Cooling System HCU - Hydraulic Control Unit HPCI -

High Pressure Coolant Injection HVAC - Heating, Ventilating and Air Conditioning LCO -

Limiting Condition for Operation LOCA - Loss of Coolant Accident LPCI - Low Pressure Coolant-Injection MSIV - Main Steam line 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 SRV - Safety Relief Valve e

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Rev. No. 0 Date 06/15/83 Page 5 of $7

y OPERATOR PRECAUTIONS GENERAL This section lists " Cautions" which are generally applicable at all times.

CAUTION #1 Monitor general state of the plant. If an entry condition for the Emergency Procedure Guidelines occurs, enter that guideline. When it is determined that an emergency no longer exists, enter normal operating procedures.

CAUTION #2 Monitor RPV water level and pressure and primary containment temperatures and pressure from multiple indications.

CAUTION #3 If a safety function initiates automatically, assume a true initiating event has occurred unless otherwise confirmed by at least two independent indications.

CAUTION #4 Whenever RHR is in the LPCI mode, inject through the heat exchangers as soon as possible.

CAUTION #5 Drywell average temperature is obtained from computer point C005, utiliz-ing a weighted average of drywell area temperatures. It is the normal source for determining drywell temperature. A computer value of -999 from this point indicates insufficient instrumentation input to the computer to calculate a valid value. With cooling fans operating, drywell average temperature may also be obtained by averaging drywell cooler air inlet and outlet temperatures, 68-TE-102 and 103, or 105 and 106 (Panel 09-75, 68-TI-100 and 101). Suppression pool temperature is determined by averaging torus bay temperatures from 16TM-131, panel 25-9 or by reading 16-TI-131, panel 09-3.

Rev. No. 3 Date 08/85 Page 6 of 57 L

CAUTION #6 Whenever Drywell Temperature Detector 16-1-RTD-107 or 108 (M089 and M090),

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

Indicated Temperature Level Instrument any 263 h in. Refueling GEMAC (164 to 564 h in.)

169'F 70 in. Wide Range Yarway (14 to 224 in.)

310*F 166 in. Feedwater GEMAC (164 to 224 in.)

547'F -100 in. Fuel Zone Yarway (-100 to +200 in.)

CAUTION #7 Wide Range Yarway indicated levels are not reliable during rapid RPV depressurization below 500 psig. For these conditions, utilize GEMAC and Fuel Zone instruments to monitor RPV water level.

Rev. No. 3 Date 08/85 Page 7 of 57 t - . . , _ _ _

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

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

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

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I CAUTION #9 1 If signals of high suppression pool water level (< 0 ft. 6 in. above normal) or low condensate storage tank water level (> 59.5 in.) occur, confirm automatic transfer of or manually transfer HPCI and RCIC suctions 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 l7l .

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 AUTOMATIC / STANDBY mode if possible.

CAUTION #11 If a high drywell pressure (< 2.7 psig) ECCS initiation signal occurs or exists while depressurizing, prevent injection from those CS and LPCI pumps not required to assure adequate core cooling prior to reaching their maximum injection pressures. When the high drywell pressure ECCS initiation signals clear, restore CS and LPCI to AUTOMATIC / STANDBY mode.

CAUTION #12 Do not throttle HPCI system below 2000 rpm. Do not throttle RCIC system below 2200 rpm.

CAUTION #13 Cooldown rates above 100*F/hr may be required to accomplish this step.

l Rev. No. 3 Date 08/85 Page 11 of 57

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CAUTION #14 Do not depressurize the RPV below 100 psig unless motor driven pumps sufficient to maintain RPV water level are running and available for inj ection.

CAUTION #15 Open SRV's in the following sequence if possible: AJKGEDCFHLB.

If it can be determined that a particular SRV has opened on high RPV pressure, continue operation with the next SRV in the sequence.

CAUTION #16 .

Bypassing low RPV water level MSIV isolation interlocks may be required to accomplish this step.

CAUTION #17 Cooldown rates above 100*F/hr may be required to conserve RPV water inventory, protect primary containment integrity, or limit radioactive releace 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 from LPCI mode.

CAUTION #19 Manually trip SLC pumps at 0% in the SLC tank.

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

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Rev. No. I Date 12/10/84 Page 12 of 57

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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 Bypassing high drywell pressure and low RPV water level secondary containment isolation interlocks may be required to accomplish this step.

CAUTION #24 A rapid increase in injection into the RPV may induce a large power excursion and result in substantial core damage.

CAUTION #25 Large reactor power oscillations may be observed while executing this step.

Rev. No. O Date 06/15/83 Page 13 of 57

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. RPV CONTROL GUIDELINE PURPOSE The purpose of this guideline is to:

. Maintain adequate core cooling,

. Shut down the reactor, and

. Cool down the RPV to cold shutdown conditions (100*F < RPV water temperature

< 212*F).

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

. RPV water level below 177 in.

. RPV pressure above 1045 psig

. Drywell pressure above 2.7 psig

. A condition which requires MSIV isolation

. A condition which requires reactor scram, and reactor power above 2.5% 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.

RC/L Monitor and control RPV water level.

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

. Isolation

. ECCS .

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

Rev. No. 3 Date 08/85 Page 14 of 57 L

If while executing the following step:

. Boron Injection is required, enter CONTINGENCY #7.

. RPV water level cannot be determined, RPV FLOODING IS REQUIRED; enter CONTINGENCY #6.

. RPV Flooding is required, enter CONTINGENCY #6.

RC/L-2 Restore and maintain RPV water level between f9 I

177 in and 222.5 in. with one or more of the #10 following systems: fil

. Condensate /feedwater (1200 - O psig)

. CRD (1600 - O psig)

I . RCIC (1120 - 50 psig) l #12 l

. HPCI (1120 - 100 psig)

. CS (335 - O psig)

. . LPCI (250 - O psig)

If RPV water level cannot be restored and maintained above 177 in.,

maintain RPV water level above 0.0 in.

If RPV water level can be maintained above 0.0 in. and the ADS timer has initiated, prevent automatic RPV depressurization by overriding ADS with the Override Switch.

If RPV water Icvel cannot be maintained above 0.0 in. enter CONTINGENCY #1.

If Alternate Shutdown Cooling is required, enter CONTINGENCY f5.

, n' RC/L-3 When OP-65, Startup and Shutdown Procedure, is entered from step

  • RC/P-5 of this procedure, proceed to celd shutdown in accordance with OP-65,-Startup and Shutdown Procedure.

t Rev. No. 3 Date 08/85 Page 15 of 57 l'

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. RC/P Monitor and control RPV pressure.

If while executing the following steps:

. EmergencyRPVDepressurizationisanticipated,andBoronl #13 l i Injection is not required, rapidly depressurize the RPV with the main turbine bypass valves.

. Emergency RPV Depressurization or RPV Flooding is required and less than 7 SRV's are open, enter CONTINGENCY #2.

. RPV Flooding is required and at least 7 SRV's are open, enter CONTINGESLY #6.

RC/P-1 If any SRV is cycling, manually open SRV's until RPV pressure drops to 920 psig.

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.. Date 01/85 Page 16 of 57 L.

If while executing the following steps:

. Suppression pool temperature cannot be maintained #8 below the Heat Capacity Temperature Limit, maintain #13

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Rev. No. 1 Date 12/10/84 Page 17 of 57

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., If while executing the following steps:

. Suppression pool water levela cannot be maintained f/13 below the Supression Pool Load Limit, maintain #14 RPV pressure below the Limit.

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. Steam Cooling is required, enter CONTINGENCY #3.

Rev. No. 3 Date 08/85 Page 18 of 57

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f If while executing the following steps:

. Boron Injection is required, and

. The main condenser is available, and

. There has been no indication of gross fuel failure or steam line break, Open MSIV's to re-establish the main condenser as a heat sink. l#16 l RC/P-2 Control RPV pressure below 1090 psig with the main l#14 l turbine bypass valves.

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

. SRV's only when suppression pool water level is l#15 l above 5.5 ft. If the continuous SRV pneumatic supply is or becomes unavailable, close each SRV.

. HPCI l#12 l l

. RCIC '

. RHR Steam Condensing Mode

. RWCU (recirculation mode) if no boron has been injected into the RPV.

. Main steam line drains

. RWCU (blowdown mode) if no boron has been injected into the RPV. If the core has been uncovered, sample the reactor coolant system prior to blow down.

If while executing the following steps the reactor is not shutdown, return to Step RC/P-2.

Rev. No. 1 Date 12/10/84 Page 19 of 57 t

RC/P-3 When either:

. All control rods are inserted to position 00, or

. The Standby Liquid Control tank has been pumped down to less than 3% level (640 pounds of boron injected into RPV), or

. The reactor is shutdown and no boron has been injected into the RPV, depressurize the RPV and maintain cooldown rate below 100*F/hr.

If one or more SRVs are being used to depressurize the RPV and the continuous SRV l#14, #17 l pneumatic supply is or becomes unavailable, depressurize with sustained SRV opening.

RC/P-4 When the RHR shutdown cooling interlocks clear, l#18 l initiate the shutdown cooling mode of RHR.

If the RHR shutdown cooling mode cannot be established and further cooldown is required, continue to cool down using one or more of the systems used for depressurization.

If RPV cooldown is required but cannot be accomplished and all control rods are inserted to position 00, ALTERNATE SHUTDOWN COOLING IS REQUIRED; enter CONTINGENCY #5.

RC/P-5 Proceed to cold shutdown in accordance with OP-65, Startup and Shutdown Procedure.

RC/Q Monitor and control reactor power.

If while executing the following steps:

. All control rods are inserted to position 00, terminate boron injection and enter AOP-1, Reactor Scram.

. The reactor is shutdown and no boron has been injected into the RPV, enter AOP-1, Reactor Scram.

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.

Rev. No. 3 Date 08/85 Page 20 of 57

RC/Q-3 If reactor power is above 2.5% or cannot be determined, trip the ,

recirculation pumps.

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

. RC/Q-4 If the reactor cannot be shutdown before suppression l #19 l

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pool temperature reaches 110*F, BORON INJECTION IS REQUIRED; inject boron into the RPV with SLC and prevent automatic initiation of ADS. i If boron cannot be injected with SLC, inject boron into i the RPV using the CRD system. -

RC/Q-4.1 Confirm automatic isolation of or manually isolate RWCU.

t RC/Q-4.2 Continue to inject boron until 640 lbs injected or SLC tank level is less than 3%. .

RC/Q-4.3 Enter AOP-1, Reactor Scram.

RC/Q-5 Insert control rods as follows:

RC/Q-5.1 If any scram valve is not open:

. Remove RPS scram solenoid fuses:

t SA-F18A, C, E. G (Panel 09-15)

SA-F18B, D F. H (Panel 09-17) i . Close CRD-2030 and 2031, scram air filter inlets, j and open the scram air filter drains.

When control rods are not moving inward:

. Replace RPS scram solenoid fuses:

5A-F18A, C, E, G (Panel 09-15) i SA-F18B, D. F. H (Panel 09-17)

. Close the scram air filter drains and open CRD-2030 and 2031, scram air filter inlets.

RC/Q-5.2 Reset the reactor scram. "

If the reactor scram cannot be reset:

1

1. Start all CRD pumps.

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

Rev. No. 2 Date - 01/85 Page 21 of_ 57

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2. Close CRD-56, Charging Water Supply.
3. Rapidly insert control rods manually l#20 l until the reactor scram can be reset.
4. Reset the reactor scram.

! 5. Open CRD-56, Charging Water Supply.

RC/Q-5.3 If the scram discharge volume vent and drain valves, 03-A0V-32 through 39, 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, i

! If the reactor scram cannot be reset, continue

in this procedure at Step RC/Q-5.5.1.

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! 3. Open the scram discharge volume vent and drain

] valves, 03-A0V-32 through 39.

RC/Q-5.4 Individually open the scram test switches for control rods not inserted to position 00.

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

RC/Q-5.5 Reset the reactor scram.

If the reactor scram cannot be reset:

1. Start all CRD pumps.

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

l 2. Close CRD-56, Charging Water Supply.

RC/Q-5.6 Rapidly insert control rods manually until l#20 l all control rods are inserted to position 00.

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Rev. No. 1 l Date 12/10/84 Page 22 of 57 I

, If any control rod cannot be inserted to position 00:

1. Individually direct the effluent from a CRD withdraw line vent valve to a floor drain. Open the CRD withdraw line vent

. valve for each control rod not inserted to position 00.

, 2. When a control rod is not moving inward, close its withdraw line vent valve.

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I Rev. No. O Date , 06/15/83 Page 23 of 57

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

. Maintain primary containment integrity, and

. Protect equipment in the primary containment.

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

. Suppression pool water average temperature above 95'F.

. Average Drywell temperature above 135*F.

. Drywell pressure above 2.7 psig.

. Suppression pool water level above 0.0 in.

1

. Suppression pool water level below -1.5 in.

< OPERATOR ACTIONS a

1 Irrespective of the entry condition, execute Steps SP/T, DW/T, PC/P.

f and SP/L concurrently.

SP/T Monitor and control suppression pool temperature.

SP/T-1 Close all SORVs.

SP/T-2 When suppression pool temperature exceeds 95'F, l#18 l operate available suppression pool cooling.

SP/T-3 Before suppression pool temperature reaches 110*F, scram the reactor.

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Rev. No. 2 Date 01/85 Page 24 of 57 l

SP/T-4 If suppression pool temperature cannot be maintained below the Heat Capacity Temperature #8 4 . Limit, maintain RPV pressure below the Limit; #13 enter RPV Control Guideline at Step RC-1 and #14 execute it concurrently with this procedure.

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DW/T Monitor and control drywell temperature.

DW/T-1 When average drywell temperature exceeds 135'F, #5 operate available drywell cooling. #6 Execute Steps DW/T-2 and DW/T-3 concurrently.

I Rev. No. 3

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Date 08/85 Page 25 of 57

DW/T-2 If drywell temperature near the RPV water level instrument cold reference leg vertical runs, 16-1-TE-107 and 108 (M089 and M090 respectively), reaches the RPV Saturation Temperature, RPV FLOODING IS REQUIRED; enter the RPV Control Guideline at Step RC-1 and execute it concurrently with this procedure.

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Rev. No. 1 Date 12/10/84 Page 26 of 57 l

e If dryvell temperature cannot be maintained below 309'F, EMERGENCY RPV DEPRESSURIZATION IS REQUIRED; enter the RPV Control Guideline at Step RC-1 and execute it concurrently with this procedure.

PC/P Monitor and control primary containment pressure.

PC/P-1 Operate SECT only witen the temperature in the space being evacuated is below 212*F.

Use OP-37, section E.1.b, " Reducing Drywell Pressure"orSectionG.2.,"Ventingthesuppres-l#21 l sion pool to maintain drywell to suppression pool differential pressure."

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 _

18.5 psig, but only if suppression pool l #8. #18 l water level is below 26.3 ft., initiate suppression pool sprays.

PC/P-3 If suppression chamber pressure exceeds 18.5 psig but only if suppression chamber air temp-erature and suppression chamber pressure are l#18 l below the Drywell Spray Initiation Pressure Limit.

Shut down recirculation pumps and drywell cooling fans and initiate dr>vell sprays restricting flow rate to less than 10,000 gpm.

see

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Rev. No. 2 Date 01/85 Page 27 of 57

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

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Rev. 'No. 1 Date 12/10/84 Page 28 of 57

. I 9

i 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:

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, Rev. No. 1 Date 12/10/84 Page 29 of 57 t-

- - - _ . - = - . ._- . _ .

. If suppression chamber air temperature and suppression chamber pressure are below the Drywell Spray Initiation Pressure Limit, shut down recirculation pumps and drywell cooling fans and initiate dr>vell sprays restricting flow rate to less than 10,000 gpm.

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, PC/P-7 If suppression chamber pressure exceeds the Primary l#22 l

Containment Pressure Limit, vent the primary containment in accordance with F-A0P-35. Post Accident Venting of Containment, to reduce and maintain pressure below the Primary Containment Pressure Limit.

1 4

4 i

Rev. No. 2 Date 01/85 Page 30 of 57

SP/L Monitor and control suppression pool water level.

SP/L-1 Maintain suppression pool water level between l#8,#9 l 0.0 and -1.5 in.

If suppression pool water level cannot be maintained above -1.5 in, execute Step SP/L-2.

If suppression pool water level cannot be maintained below 0.0 (normal water level),

execute Step SP/L-3.

1 SP/L-2 SUPPRESSION POOL WATER LEVEL BELOW -1.5 in.

Maintain suppression pool water level above the Heat Capacity Level Limit.

! u HEAT CAPACITY LEVEL LIMIT to 38 i

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If su).pression pool water level cannot be maintained above the Heat Capacity Level Limit, EMERGENCY RPV DEPRESSURIZATION IS REQUIRED; enter the RPV Control Guideline at Step RC-1 and execute it concurrently with this procedure.

SP/L-3 SUPPRESSION POOL WATER LEVEL ABOVE 0.0 in. (normal water level)

J

, Rev. No. 1

.Date 12/10/84 Page 31 of 57 i

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.

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If suppression pool water level cannot be #13 maintained below the Suppression Pool Load #14 Limit, maintain RPV pressure below the Limit.

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 containnent 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 the RPV Control Guideline at Step RC-1 and execute it concurrently with this procedure.

1 Rev. No. 1 Date 12/10/84 Page 32 of 57

. SP/L-3.2 Before primary containment water level reaches 104 ft., but only if adequate core cooling is assured, terminate injection into the RPV from sources external to the primary containment except from boron injection and CRD.

SP/L-3.3 When primary containment water level reaches 104 ft., terminate injection into the RPV from sources external to the primary containment irrespective of whether adequate core cooling is assured.

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, Rev. No. 3 Date 08/85 Page 33 of 57

1

,' SECONDARY CONTAINMENT CONTROL GUIDELINE PURPOSE The purpose.of this guideline is to:

. Protect equipment in the secondary containment,

. Limit radioactive release to the secondary containment, and either:

. Maintain secondary containment integrity, or

. Limit radioactivity release from the secondary containment.

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

. Differential pressure at or above 0 in of water

. An area temperature above the maximum normal operating temperature

. A unit cooler inlet temperature above 104*F

. A ventilation exhaust radiation level above the maximum normal operating radiation level -

. An area radiation level above the maximum normal operating radiation level

. A floor drain' sump water level above the maximum normal operating water level

. An . area water level above the maximum normal operating water level Refer to Table 1 for a listing of maximum normal operating values.

x I

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l Rev. No. 2 Date 01/85 Page 34 of 57 l 1

i OPERATOR ACTIONS If while executing the following steps Reactor Building ventilation exhaust radiation levels (main exhaust duct or Refueling Floor exhaust duct) exceed the high-high trip setpoint:

. Confirm or manually initiate isolation of the Reactor Building ventilation system and

. Confirm initiation of or manually initiate SBGT l'

If while executing the following steps:

a

. TheReactorBukidingventilationsystemisolates,and

. The Reactor Building ventilation main exhaust duct and refuel-ing floor exhaust duct radiation levels are below the high-high trip set point,

restore from a Reactor Building ventilation isolation in l#23 l accordance with F-AOP-15. Recovery from Isolations.

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 unit coolers.

1 SC/T-2 If Reactor Building ventilation main exhaust duct and refueling floor exhaust duct radiation levels are below the high-high trip setpoint restore Reactor Building ventilation in accordance with F-A0P-15. Recovery from Isolation.

SC/T-3 If any area temperature exceeds its maximum normal operating value, isolate or confica automatic isolation of 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 reactor coolant system is discharging into an area, then before any area temperature reaches its maximum safe operating value, enter the RPV Control Guideline at Step RC-1 and execute it concurrently with this procedure.

Rev. No. 1

~

Date 12/10/84 Page 35 of 57

, SC/T-5 If a reactor coolant system is discharging into an area and an area temperature exceeds its maximum safe operating value in more than one area, EMERGENCY RPV DEPRESSURIZATION IS REQUIRED.

SC/R Monitor and control secondary containment radiation levels.

SC/R-l If any Reactor Building ventilation exhaust or area radiation level exceeds its maximum normal operating value, 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 reactor coolant system is discharging into an area, then before any area radiation level reaches its maximum safe opera-ting value, enter the RPV Control Guideline at Step RC-1 and execute it concurrently with this procedure.

SC/R-3 If a reactor coolant system is discharging into an area and an area radiation level exceeds its maximum safe operating value in more than ene 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 value, operate available sump pumps to restore and maintain it below its maximum normal operating value.

If any floor drain sump or area water level cannot be restored and maintained below its maximum normal operating value, 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 working fire.

SC/L-2 If a reactor coolant system is discharging into an area, then before any area water level reaches its maximum safe operating value, enter the RPV Control Guidelir at Step RC-1 and execute it concurrently with this procedure.

SC/L-3 If a reactor coolant system is discharging into an area and area water level exceeds its maximum safe operating value in more than one area, EMERGENCY RPV DEPRESSURIZATION IS REQUIRED.

Rev. No. I Date 12/10/84 Page 36 of 57

. TABLE 1 OPERATING VALUES OF SECONDARY CONTAINMENT PARAMETERS Secondary Containment Parameter / Location Isolation Maximum Normal Maximum Safe or Alarm Operating Value Operating Value

. Differential pressure (in water) (in water) (in water)

. Reactor Building /outside air 09-75 +0.25 in. -0.25 in. +1.0 in.

. Area Temperature (*F) (*F) (*F)

- Below Refuel Floor Exhaust Air Temp. None 104 113 66-TI-105 (Panel 09-75)

)' - Refuel Floor Air Temperature None 104 111 66-TI-106 (Panel 09-75)

- Elevation 369 Air Temperature None 104 111 4

66-TI-108 (Panel 09-75)

- West Crescent Area Air Temperature None 104 137 66-TI-109A (Panel 09-75)

- East Crescent Area Air Temperature None 104 137 66-TI-109B (Panel 09-75)

- A RWCU Pump Room 135 104 214 12-TE-117A & B (Panel 09-21)

- B RWCU Pump Room 135 104 225 12-TE-117C & D (Panel 09-21)

- RWCU Heat Exchanger Room 135 104 203 a

12-TE-117E & F (Panel 09-21)

- RCIC - Drywell Entrance 135 104 100A - 218 13-TE-100A (Panel 09-21)

- Torus Area Ambient 135 104 100B - 280 13-TE-100B (Panel 09-22)

- HPCI - Drywell Entrance 135 104 100C - 251 13-TE-100C & D (Panel 09-21) 100D - 251

! - RCIC Turbine Area 135 104 137 l 13-TE-88A & B (Panel 09-21)

- Torus Area Ambient 135 104 106A - 280 13-TE-106A (Panel 09-21)

- RCIC - Drywell Entrance 135 104 106B - 280 13-TE-106B (Panel 09-21)

- Torus Area Ambient 135 104 106C - 280 13-TE-106C & D (Panel 09-21) 106D - 280

- RCIC Turbine Area 135 104 137 13-TE-73A & B (Panel 09-21)

- RCIC Turbine Area 135 104 137 13-TE-77 (Panel 09-21)

- A RHR Heat Exchanger Room 135 104 244 10-TE-99A and 104A (Panel 09-21)

- B RHR Heat Exchanger Room 135 104 242 10-TE-99B and 104B (Panel 09-21)

- HPCI Turbine Area 135 104 137 23-TE-105A, 114A&B, 92A&B (Panel 09-21) l Rev. No. 2 Date 01/85 Page 37 of 57

a*

. TABLE 1 i OPERATING VALUES OF SECONDARY CONTAINMENT PARAMETERS (Cont'd.)

SecondaryContaknmentParameter/ Location Isolation Maximum Normal Maximum Safe

! or Alarm Operating Value Operating Value

. Unit cooler temperature. ("F) (*F) *F

- UC-16 Rx Bldg 344' el South 104 104 113

- UC-17A Rx Bldg 326' el SE 104 104 132

- UC-17B Rx Bldg 326' el NE 104 104 132 j - UC-18 Rx Bldg 300' el West 104 104 157

- UC-19A Rx Bldg 300' el South 104 104 173

, - UC-19B Rx Bldg 300' el East 104 104 173

- UC-21A Rx Bldg 272' el SE 104 104 147 l - UC-21B Rx Bldg 272' el West 104 104 144

- UC-21C Rx Bldg 272' el NE 104 104 '24

- UC-21D Rx Bldg 272' el NW 104 104 130

- UC-22A West Crescent 104 104 137 1

- UC-22B East Crescent 104 104 137

- UC-22C West Crescent 104 104 137

- UC-22D East Crescent 104 104 137 l

l - UC-22E West Crescent 104 104 ...,. 137 i - UC-22F East Crescent 104 104 137 i - UC-22G West Crescent 104 104 137

- UC-22H East Crescent 104 104 137

- UC-22J West Crescent 104 104 137

~

- UC-22K East Crescent 104 104 137 i

4 i

1 4 Rev. No. I j Date 12/10/84 Page 38 of 57

l

, TABLE 1 OPERATING VALUES OF SECONDARY CONTAINMENT PARAMETERS (Cont'd.)

1 Secondary Containment Parameter / Location Isolation Maximuu Normal Maximum Safe or Alarm Operating Value Operating Value

. Reactor Building Isolation / Ventilation CPM CPM CPM exhaust radiation level

- Main Exhaust 104 103 2.7 x 105 j - Refuel Floor Exhaust Duct 10 4 103 2.7 x 105 a . Area radiation level (mr/hr) (mr/hr) (mr/hr) i'

- Spent Fuel Pool 18-RIA-051-12 25 1 103 1

- Rx Bldg 344 18-RIA-051-13 20 6 103

- New Fuel Vault 18-RIA-051-14 20 6 103

- Cleanup Precoat Area 18-RIA-051-15 80 10 103

- RWCU Ex Room 18-RIA-051-16 50 5 103

- Fuel Pool Pump Room 18-RIA-051-17 300 90 103

- Contaminated Equipment Storage 18-RIA-051-18 50 15 103

- RWCU Pump Area 18-RIA-051-19 30 10 103

- Rx Sa=ple Area 18-RIA-051-20 30 10 103

- RBCLC HC Area 18-RIA-051-21 5 1 103

- Rx Bldg Access 272' el 18-RIA-051-23 40 6 103

- TIP Cubicle 18-RIA-051-24 125 20 103

- East CRD Accumulators 18-RIA-051-25 30 6 103

- West CRD Accumulators 18-RIA-051-26 35 10 103

, - Equipment Drain Sump 18-RIA-051-27 110 25 103 l - CRD Removal Hatch 18-RIA-051-28 25 8 103

- Floor Drain Sump 18-RIA-051-29 100 30 103

- South Refuel Floor 18-RIA-051-30 1000 200 2 x 105 i

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Rev. No. 2 Date 01/85 Page 39 of 57

_- . - . -. . . ~ _ ._ _ _ . . . . . - _ . _ _ = . . - . . . . - .

[ . TABLE 1

{ OPERATING VALUES OF SECONDARY CONTAINMENT PARAMETERS (Cont'd.)

i ~

Secondary Containment Parameter / Location Isolation Maximum Normal Maximum Safe or Alarm Operating Value Operating Value 4

j . Floor drain sump water level (in.) (in.) (in.)

- East Crescent 42 42 None

- West Crescent 42 42 None t

j . Area water level (in.) (in.) (in.)

- East Crescent None 0 18

- West Crescent None 0 18 4

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-Rev. No. 1 Date 12/10/84 Page 40 of 57

B 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 10 times the Technical Specification limits.

OPERATOR ACTIONS RR-1 Isolate all reactor coolant systems'that are discharging into areas outside the primary and secondary containments except systems required to assure adequate core cooling or shut down the reactor.

4 RR-2 If offsite radioactivity release rate approaches or exceeds the following and a reactor coolant system is discharging into an area outside the primary and secondary containments, EHERGENCY RPV DEPRESSURIZATION IS REQUIRED;

, enter the RPV Control Guideline at Step RC-1 and execute it concurrently with this procedure,

]

j a. Off-site whole body dose is projected to exceed one (1) rem OR

b. Off-site child thyroid dose is projected to exceed 5 rem OR
c. Site boundary whole body dose rate exceeds 50 mR/hr for hour or 500 mR/hr for 2 min'utes OR 4 d. Site boundary thyroid dose rate exceeds 250 mR/hr for hour or 2500 i mR/hr for 2 minutes.

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Rev. No. 2 Date 01/85 Page 41 of 57

- _- - - , , - _ - . _ _ . . - ~ _ ... _ -

. CONTINGENCY #1 LEVEL RESTORATION If while executing the following Steps:

. Boron Injection is required, enter CONTINGENCY #7.

. RPV water level cannot be determined, RPV FLOODING IS REQUIRED; enter CONTINGENCY #6.

f

. RPV Flooding is required, enter CONTINGENCY #6.

e t

Cl-1 Line up for injection and start pumps in 2 or more of the following injection subsystems:

. Condensate

. A LPCI

. B LPCI

. A CS

. B CS j If less than 2 of the injection subsystems can be lined up, commence lining j up as many of the following alternate injection subsystems as possible:

. RHR service water crosstie

. RHR keep-full

. CS keep-full

. SLC (test tank)

. SLC (boron tank)

. Condensate Transfer l

l 4

Rev. No. 2 Date 01/85 Page 42 of 57

,---n, - - - - , , - - - - - ,. , . , - - . - ..r.- -, ,, e

6 4

1, Cl-2 Monitor RPV pressure and water level. Continue in this procedure at the step indicated in the following table.

RPV PRESSURE REGION 300 psig 100 psig HIGH INTERMEDIATE LOW i

i -

INCREASING Cl-3 Cl-4 Cl-5 4

~

DECREASING -

Cl-6 Cl-7 If while executing the following Steps:

, . The RPV water level trend reverses or RPV pressure changes region, 3

return to Step Cl-2.

l . .RPV water level drops below 59.5 in.. prevent automatic initiation of ADS.

I 1

  • Cl-3 RPV WATER LEVEL INCREASING, RPV PRESSURE HIGH
Enter the RPV Control Guideline at Step RC/L.

7 g Cl-4.RPV WATER LEVEL INCREASING, RPV PRESSURE INTERMEDIATE 'j i

! If HPCI and RCIC are not available and RPV pressure is increasing, EMERGENCY RPV DEPRESSURIZATION IS REQUIRED. When RPV pressure is decreasing, enter l j the RPV Control Guideline at Step RC/L. _

i If HPCI and RCIC are not available and RPV pressure is not increasing, enter l the RPV Control' Guideline at Step RC/L.

Otherwise, when RPV water level reaches 177 in., enter the RPV Control

._ Guideline at Step RC/L.

4-j Cl-5 RPV WATER LEVEL INCREASING, RPV PRESSURE' LOW

If RPV pressure is increasing, EMERCENCY RPV DEPRESSURIZATION IS REQUIRED.

When RPV_ pressure is decreasing, enter the RPV Control Guideline at Step j RC/L. .,

Otherwise, enter the RPV Control Guideline at Step RC/L.

i l

Rev. No. 3-

! Date 08/85 ~Page 43 of 57

Cl-6 RPV WATER LEVEL DECREASING, RPV PRESSURE HIGH OR INTERMEDIATE If HPCI or RCIC is not operating, restart whichever is not operating.

4 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.

When RPV water level drops to 0.0 in.

i

. 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 Cl-2.

. Otherwise, EMERGENCY RPV DEPRESSURIZATION IS REQUIRED. When RPV water 4 level is increasing or RPV pressure drops below 100 psig, return to

. Step Cl-2.

Cl-7 RPV WATER LEVEL DECREASING, RPV PRESSURE LOW Start pumps in alternate injection subsystems which are lined up for inj ection.

If RPV pressure is increasing EMERGENCY RPV DEPRESSURIZATION IS REQUIRED.

When RPV water level drops to 0.0 in. enter CONTINGENCY #4 I

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l Rev. No. 1 Date 12/10/84 Page 44 of 57

' I

_ - - - - . - - . . . - - - - . _- . . - - . - - _ - ..-..- -_~ . - - - - _ _ - _ _ - -. - ~. . . . ..

e e C1-2 Moniter RPV pressurs and eratar 1: vel. Continue in this proce r3 tt step indicated in the following tables t2 :o

$4 #D E .

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If while cuecut ing the following abp:,2 J

. the RPV water level trend reverses or RPV pressure changes region, return to Step C1-2.

O

! co . RPV water level drops below 59.5 in., prevent automatic initiation of ADS.

N w a

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RPV PRESSURC REGION M k

l 300 psig 100 psig l m i  !

HICH INTERE DIAIC LOW o C1-3 C1-4 C1-5 H

Enter the RPV Control Guidelines If HPCI and RCIC are not available and if RPV pressure is increasing, n1 e at Step RCA. RPV pressure is increasing, EMERCENCY O EKRCENCY RPV DEPRESSURIZA!!ON IS g i RPY DEPRESSURIZA!!(N IS REQUIRED. REQUIRED. When RPV pressure is

g When RPV pressure is decreasing, enter decreasing, enter the RPV Control y
g the RPV Control Guidelines at Step Cuidelines at Step RC/L. m l y

~

RCA. N j Otherwise, enter the RPV Control a

if HPCI and RCIC are not available and Guidelines at Step RC/t.. O RPV pressure is not increasing, enter 7

, the RPV Control Guideline at Step RCA. N 4

Y w H Otherwise, e en RPV water level reaches :C

[ 177 in., enter the RPV Control Guide-w line at Step RCA. ,

a c:

  • c1

} C1-6 C1-7 l If HPCI or RCIC is not operating, restart whichever is not operating. O start 1

N pumps in alternate injection subsystems "

8 g if no injection subsystem is lined up for injection with at least one pump which are lined up for injection.

o running, start pugs in alternate injection subsystems which are lined up 1 -d =

for injection. If RPV pressure is increasing, EKRCENCY 3 g RPV D[PRESUR124Tl0N IS REQUIRED.

Ut g When RPV wyter level drops to 0.0 in.:

a u

) U If no system, injection subsystem or alternate injection autrsystem in When RPV water level drops to o lined up with at 1 cast one pump running, STEAM COOLING IS REQUIRED. When 0.0 in. enter CONI!NCENCY #4 m any system, injectim wbsystem or alternate injection subsystem is lined l up with at least one pump running, return to Step C1-2.

j U . Otherwise, EKRCENCY RPV DEPRESSURIZA!!ON IS REQUIRED, when RPV water i' level is increasing or RPV pressure drops below 100 psig, return to Step C1-2.

1 i

CONTINGENCY #2 EMERGENCY RPV DEPRESSURIZATION C2-1 When either:

l #13, #14 l

. Baron Injection is required and all injection into the.

RPV except from boron injection systems and CRD has been terminated and prevented, or

, . Boron Injection is not required C2-1.1 If suppression pool water level is above 5.5 ft:

. Open all ADS valves.

. If any ADS valve cannot be opened, open other SRV's until 7

] valves are open.

C2-1.2 If less than 3 SRVs are open and RPV pressure is at least 50 psig above suppression chamber l #22 l pressure, rapidly depressurize the RPV using one or more of the following systems (use in i order which will minimize radioactive release to the environment):

. Main Condenser

. RHR (steam condensing mode)

. HPCI turbine

. . RCIC turbine

. Main steam line drains

. HPCI steam line drains

. RCIC steam line drains

. Head vent If RPV Flooding is required, enter CONTINGENCY #6.

C2-2 Enter the RPV Control Guideline at Step RC/P-3.

I l

Rev. No. 0 Date 06/15/83 ' Page 46 of 57

i

+

< CONTINGENCY #3 STEAM COOLING 1

If while executing ti.e following step Emergency RPV Depressurization is required or any system, injection subsystem or alternate injection i

subsystem is lined up for injection with at least one pump running, enter CONTINGENCY #2.

C3-1 When RPV water level drops to -100 in, or if RPV water level cannot be determined, open one SRV.

I J

1 i When RPV pressure drops below 700 psig, enter CONTINGENCY #2.

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Rev. No. 1 Date - 12/10/84 Page 47 of 57 i

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{ .

I . CONTINGENCY #4 CORE COOLING WITHOUT LEVEL RESTORATION I

i 4 C4-1 Open all ADS valves. l #13 l l .

EIf any ADS valve cannot be opened, open other SRVs until 7 valves are open.

I C4-2 Operate CS subsystems with suction from the suppression pool.

i [

j When at least one core spray subsystem is operating with suction from the

suppression pool and RPV pressure is le ss than 130 psig above suppression 4 pool pressure, terminate injection into'the RPV.from sources external to the j primary containment. ,

i i C4-3 When RPV water level is restored to 0.0 in. enter the RPV Control Guideline l at Step RC/L.

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Date 12/10/84 Page 48 of 57 e

,-v-m. -,,--,.,,%-.,- g------w-,--....-------,,e ,,<%.v- -,.------m,-y-*t<+-* **-- e --w ev ' ' - - - * = ' ' ----w-*W--mW'-c'W***'mw-e--"-e****8N's-MT w e *v ~ ~

-. . . - - . - - . . - . . - ~ - _ - . _ . . . - . . . . _ - - . - . . . . - .

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. CONTINGENCY #5  ;

ALTERNATE SHUTDOWN COOLING {

! C5-1 Initiate suppression pool cooling.

l l C5-2 Close the RPV head vents, MSIVs, main steam line drain valves, and HPCI and  ;

! RCIC isolation valves.

j C5-3 Place the control switch for one SRV in the OPEN position.

1 i C5-4 Slowly raise RPV water level to establish a flow path through the open.SRV back to the suppression pool.

! i C5-5 Start one CS or LPCI pump with suction from the suppression pool.

l j C5-6 Slowly increase CS or LPCI injection into the RPV to the maximum. ,

. C5-6.1 If RPV pressure does not stabilize at least 93 psig above l j suppression chamber pressure, start another CS or LPCI pump.

j C5-6.2 If RPV pressure does not stabilize below 174 psig, open another ,

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SRV.

l C5-6.3 If the cooldown rate exceeds 100*F/hr, reduce CS or LPCI injection l J into the RPV until the cooldown rate decreases below 100*F/hr or  ;

RPV pressure decreases to within 50 psig of suppression chamber pressure, whichever occurs first.

l C5-7 Control suppression pool temperature to maintain RPV water temperature above 100*F.

i CS-8 Proceed to cold shutdown in accordance with OP-65, Startup and Shutdown i Procedure.

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-_ _ = -. _ . .

CONTINGENCY #6 RPV FLOODING

, C6-1 If at least 3 SRVs can be opened, close the MSIVs, main steam line drain valves HPCI and RCIC isolation valves.

C6-2 If any control rod is not inserted to position 00:

J j C6-2.1 Terminate and prevent all injection into the RPV except from boron i injection systems and CRD until RPV pressure is below the Minimum Alternate RPV Flooding Pressure.

]

4 MINIMUM Alternate RPV 1 Number of open SRVS Flooding Pressure (psig) i

! 7 or more 79 6 95 j 5 116 4 149 3 204 2 313 j 1 640 If less than one SRV can be opened, continue in this procedure, i

If while executing the following step, RPV water level can be determined and RPV Flooding is not required, enter CONTINGENCY #7 and the RPV Control Guideline at Step RC/P-4 and execute these procedures concurrently, i

C6-2.2 Commence and slowly increase injection into the RPV with the following systems until at least one SRV is l #24 l

open and RPV pressure is above the Minimum Alternate RPV Flooding Pressure

. Condensate booster pumps

. Condensate pumps

. CRD

. LPCI I

Rev. No. 3 l Date 08/85 Page 50 of 57

. If less than one SRV is open or RPV pressure cannot be increased to l above the Minimum Alternate RPV Flooding Pressure, commence and slowly increase injection into the RPV with the following systems until at least one SRV is open and RPV pressure is above the Minimum Alternate RPV Flooding Pressure:

. CS

. RHR service water crosstie

. RHR keep-full systems

. CS keep-full systems

. Condensate Transfer System C6-2.3 Maintain at least one SRV open and RPV pressure above the Minimum Alternate RPV Flooding Pressure but as low as practicable by throttling injection.

C6-2.4 When:

. All control rods are inserted to position 00, or

. The reactor is shutdown and no boron has been injected into the RPV, continue in this procedure. '

I C6-3 If RPV water level cannot be determined:

1 C6-3.1 Commence and increase injection into the RPV with the following systems until at least 3 SRVs are open and RPV pressure is not

decreasing and is 84 psig or more above suppression chamber pressure.

. Condensate Booster Pumps

] . CS

. LPCI I . Condensate pumps

. CRD

. RHR service water crosstie 1

4

. RHR keep-full systems

. CS keep-full systems

. SLC (test tank)

] . SLC (boron tank) l . Condensate Transfer System C6-3.2 Maintain at least 3 SRVs open and RPV pressure at least 84 psig above suppression chamber pressure by throttling injection.

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j Date 08/85 Page 57 51 of

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:

. Condensate booster pumps

. CS

. LPCI

. Condensate pumps

. C1D

. RHR service water crosstie

. RHR keep-full systems

. CS keep-full systems

. SLC (test tank) '

. SLC (boron tank)

. Condensate Transfer System C6-5 If RPV water level cannot be d'etermined:

C6-5.1 Continue injecting' water into the RPV until the temperatures near the RPV water level cold reference leg instrument vertical run (detectors 16-1-RTO-107 and 108 (M089 and M090) are below 212*F and RPV water level instrumentation is available.

If while executing the following steps, RPV water level can be determined, continue in this procedure at Step C6-6.

C6-5.2 If it can be determined that the RPV is filled or if RPV pressure is at least 84 psig above suppression chamber pressure, terminate all injection into the RPV and reduce RPV water level.

C6-5.3 If RPV water level indication is not restored within the Maximum Core Uncovery Time Limit after commencing termination of injection into the RPV, return to Step C6-3.

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I 5 MAXIMUM CORE UNCOVERY TIME

" 50 a 6 . . . . . . . . ,

a E 40 I' ' '

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20

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. l 5 le i E g 7 1 3, R 1 1 10 100 1000 10000 TIME AFTER REACTOR SMUTDOWN (nela)

Rev. No. -3 Date 08/85 Page 52 of 57

C6-6 When suppression chamber pressure can be maintained below the Primary Containment Design Pressure, enter the RPV Control Guideline at Steps RC/L and RC/P-4 and execute these steps concurrently.

I 80 l /

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a. 70

/ / / / / / / / / / /

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/ PRIMARY CONTAIN, MENT DESIGN PRES:5URE

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16 P e r-toa g 16-1-071T-182 5

40 4 3 l

0 10 20 30 40 50 60 70 80 90 100 110 PRIMARY CONTAINMENT WATER LEVIL (FT)

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Date 12/10/84 Page 53 of 57

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[ . CONTINGENCY #7 [

LEVEL / POWER CONTROL l t

If while executing the following steps RPV water level cannot be determined, RPV FLOODING IS REQUIRED; If RPV Fl0ODING is required enter ,

CONTINGENCY #6.

C7-1 If: !t

. Reactor power is above 2.5% or cannot be determined, and

. Suppression pool temperature is above 110*F, and f- . Either an SRV is open or opens or drywell pressure is above 2.7 psig, i lower RPV water level by terminating and preventing all l injection into the RPV except from boron injection systems l #25 l and CRD until either:

i l . Reactor power drops below 2.5%. or i a

! . RPV water level reaches 0.0, or 1

. All SRVs remain closed and drywell pressure remains below 2.7 psig i r

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i: If while executing the following steps Emergency RPV Depressurization is

required, continue in this procedure at Step C7-2.1
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! Rev. No. 3 Date . 08/85 Page 54 of 57

e If while executing the following step:

. Reactor power is above 2.5% or cannot be determined, and

. RPV water level is above 0.0 in., and

. Suppression pool temperature is above '10*F, and

. Either an SRV is open or opens or drywell pressure is above 2.7 psig, return to Step C7-1.

C7-2 Maintain RPV water level either: l #9. #10. #11. #24 l

. If RPV water level was deliberately lowered in Step C7-1, at the level to which it was lowered, or

. If RPV water level was not deliberately lowered in Step C7-1, between 177 and 222.5 in.,

with the following systems:

. Condensate /feedwater (1200 - O psig)

. CRD (1600 - O psig)

. RCIC (1120 - 50 psig) l #12 l

. HPCI (1120 - 100 psig)

. LPCI (250 - O psig)

If RPV water level cannot be so maintained, maintain RPV water level above 0.0 in.

If RPV water level cannot be maintained above 0.0 in., 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.

d Rev. No. 3 Date 08 /85 Page 55 of $7

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, 6 MINIMUM Alternate RPV j Number of open SRVS Flooding Pressure (psig)

7 or more 79 6 95 5 116 1 4 149 3 204
2 313

! 1 640 i [

l If less than one SRV can be opened, continue in this procedure. ,

)

1 C7-2.2 Commence and slowly increase injection into l #24 l l the RPV with the following systems to restore and "

] maintain RPV water level above 0.0 in. '

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l . Condensate /feedwater

. CE j . RCIC

. HPCI l . LPCI If RPV water level cannot be restored and maintained above 0.0 1 in., commence and slowly increase injection into the RPV with the j following systems to restore and maintain RPV water level above j 0.0 in.

i . CS

. RHR service water crosstie

. RHR keep-full systems

. CS keep-full systems s

. Condensate Transfer System i

i If while executing the following step reactor power commences and continues to increase, return to Step C7-1.

l C7-3 When boron has been injected, resulting in a Standby Liquid Control tank level of 45% or less (285 pounds of boron), or all control rods have been inserted to position 00, restore and maintain RPV water l 1evel between 177 and 222.5 in.

If RPV water level cannot be restored and maintained above 177 in.,

j maintain RPV water level above 0.0 in.

Rev. No. 3 i

l Date 08/85 Page $6 of 57

0 s

e If RPV water level cannot be maintained above 0.0 in., EMERCENCY RPV DEPRESSURIZATION IS REQUIRED; return to Step C7-2.1.

If Alternate Shutdown Cooling is required, enter CONTINCENCY #5.

C7-4 When OP-65, Startup and Shutdown Procedure is entered from the RPV Control Guideline at step RC/P-5, proceed to cold shutdown in accordance with OP-65, Startup and Shutdown Procedure.

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