ML20084H018

Emergency Operating Procedure, Operator Training Program

ML20084H018
Person / Time
Site:	Clinton
Issue date:	05/01/1984
From:	ILLINOIS POWER CO.
To:
Shared Package
ML20084G928	List: ML20084G926 ML20084G959 ML20084G988 ML20084G998 ML20084H018 ML20084H027
References
PROC-840501, NUDOCS 8405070421
Download: ML20084H018 (35)

Text

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! Illinois Power Ctmpany

{ Clinton Power Station Unit 1

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j INEHGENCY OPERATING PN -

a TERMOR TRMNDO PROGRM

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Learning Objectives

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N/ ) Upon receiving EOP training the student should be able to:

1. State the entry conditions for each of the EOP's.

2. Explain the bases for any given general or specific caution associated with the EOP'S.

3. Explain the bases for any given operator action prescribed in the EOP's. ,

4. List the basic steps for controlling any of the parameters addressed by the EOP's.

5. Describe the display location of any parameter addressed in the EOP's. -

Operational Objectives During the EOP training the Shift / Assistant Shift Supervisor and the course instructor should:

1. Document perceived deficiencies in the EOP's and submit them to the Supervisor-Operations for review.

2. Identify abnormal system lineups utiHzed in the EOP's and ensure operators are trained to respond.

3. Ensure training in areas the EPG takes credit for is adequate.

Training Methods _ ,

Lecture Group discussion Student flandout A portion of the student handout is attached. Each procedure step is explained in the text and the whole procedure is summarized in the flowchart at the end. The steps are taken verbatim from'the EOP's.

The discussions are f rom the gencric EPG's and include the required Clinton specific information. The dowcharts are taken from the pro-cedures but include additional training information.

TN The course will be taught in a lecture and group discussion format.

(_) The instructor's primary teaching device will be the marked up flow-chart. Instructor guides will be developed to aid the delivery of the q detailed discussion associated with.the procedure steps. "

w-_-___ _ _ _ _ _ _ _ - _ - - - _ _ _ - - - _ - _ _ - - - _.

, Safety Parameter Display System (SPDS) o General SPDS displays are concise displays of critical plant i

parameters intended to enable the operator to rapidly assess the safety status of the plant. There are three parts to SPDS:

1. #5 CRT in P680 in which 11 critical safety functions are displayed,

2. Alarm Initiated Display (AID) which appears on the bottom of all active DCS CRT's if any of the AID parameters reach an alarm setpoint, i

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3. PRMS/CRT Status Grid display of plant radiological

. conditions.

o Access The SPDS display (SS) on P680 is the designated display on CRT #5 during all plant operating activities as shown on the Plant Operating Activity Format Matrix incorporated in DCS.

(Figure 1) This does not preclude the operator from selecting other displays for brief periods, but provides for

, * ') normal utilization of #5 CRT for SPDS. Access to the SPDS display is available on any other DCS CRT and on all PMS consoles, including the TSC and EOF, via the Video Services function.

The SPDS AID is a transient display of parameters which duplicate or support SPDS parameter values. The AID does not appear on PMS CRT's but all the data is available from PMS via the Single Point on Group Point functions.

The PRMS CRT is tapped for display in the TSC. The TSC and EOF have access to PRMS information via the Spectral Analysis and Recording System (SAARS).

o Display Formats Color coding in the SPDS and E0P Support Displays is consistent with DCS displays. Alarm conditions in are indicated by the color red, with normal or non general alarm conditions indicated by the color green for digital values, 3 and yellow for analog values and bar graphs.for Calpha-numeric dynamic labels, bord

'. portion of the background. White is used to denote low confidence data.

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3 The SPDS graphic display (Figure 6) consists of 11 s_j horizontal bar graphs for dynamic display of data, with quantitative information displayed adjacent to each bar graph. Trend information is represented by a rate of change with a negative number indicating a decreasing value.

l Containment Isolation is represented by a line of letters indicating I (inboard) or 0 (outboard) isolation for each of the 11 groups. Successful isolation is indicated by the letters changing from red to green.

The AID (Figure 7) is a simple list of 12 parameters with alarm conditions indicated in red. The AID ap7 ears only in the bottom 12 lines of the display area of each DCS CRT when any one of the parameters alarms.

The PRMS Status Grid display (Figure 17) is an outline drawing of the Fuel, Containment, Auxiliary, Turbine, -

Control, and Radwaste buildings. Monitors are indicated by the presence of the respective unit numbers within the building outline. The color of the unit number indicates the alarm status. Red indicates a high radiation alarm, yellow indicates an alert or trend alarm. Normally unit numbers are displayed in green.

o SPDS Parameters (Figures 6 and 7)

() Parameters were chosen for display in SPDS on the basis of their usefulness to the operator in assessing plant conditions in the following areas:

Reactivity Control Reactor Core Cooling and Heat Removal from the Primary System Reactor Coolant System Integrity Radioactivity Control Reactivity Control Parameters on the permanent SPDS display which assist the operator in confirming the net negative reactivity of the core are: ,

SRM Flux Reactor Period APRM Power The AID includes SDV Level to assist the operator in determining his ability to scram the reactor. _

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( Reactor Core Cooling and Heat Removal from the Primary System Parameters on the permanent SPDS display associated with core cooling and heat removal from the primary system include:

Reactor Wide Range Level Reactor Feed Flow Reactor Wide Range Pressure Total, Core Flow Reactor Steam Flow The AID includes Reactor Wide Range Level since level is the primary indication of the ability to remove heat from the core.

Reactor Coolanc System Integrity Parameters on the permanent SPDS display which provide indication of reactor coolant system integrity include:

Reactor Wide Range Pressure Reactor Feed Flow Narrow Range Drywell Pressure Total Core Flow Drywell Floor Drain Sump Flow The AID includes Drywell Floor Drain Sump Flow since this is 0 the most sensitive indication of leakage.

Containment Conditions Parameters on the permanent SPDS display which provide information on conditions within the containment include:

Containment Pressure .

Suppression Pool Temperature Containment Isolation status The AID includes:

Drywell Temperature Containment Pressure ,

Drywell Pressure Suppression Pool Level Suppression Pool Temperature-Containment Hydrogen Concentration Radioactivity Control (Figure 16)

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The PRMS Status Grid disolays the status of 90 permanent monitors (APM's, CAM's, ?RM's) and 22 portable monitors (ARM's, CAM's) located throughout the plant. l

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l The SPDS parameters listed below are derived from 4

() redundant signals and displayed according to an algorithm:

APRM Power Reactor Wide Range Level SRM Counts Suppression Pool Temperature SRM Period The four signals are compared to each other such that if all four are within 10%, an average of the four will be calculated and displayed. If any one is outside the 10%, an annunciator indicating a PMS internal alarm is displayed.

The operator may clear the alarm through appropriate entries at the PMS console disabling the faulty input.

A comparison of the remaining three values occurs and if all are within 10% an average is computed and displayed. If any value is outside of 10% the annunciator occurs. The ~

oaerator will not be able to disable the faulty input from t2e PMS console.

All aarameters on the permanent SPDS display are represented in three forms. Quuatitatively as a digital value in engineering units, qualitatively as a dynamic bar graph, and as a transformed variable indicating rate of change (trend).

The trend calculation is performed in PMS. SRM Period is used to trend source range flux in lieu of a PMS transformed variable.

Containment isolation status is derived from a truth table in which the open/close status of each inboard and outboard valve in a group is monitored. The I(0) is displayed in red until successful inboard (outboard) isolation has occurred.

The I(0) then changes to green.

Data Validation ,,

a Continuous data validation is performed by DCS/PMS on the hardware and software associated with the displayed parameter. For invalid signals the last good value is substituted and displayed in white to indicate low confidence. An asterisk adjacent to the parameter name on the SPDS display or AID identifies a validated parameter. '

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Data Updates

! The response time of DCS for display updates is less than 250 ms. Variables which are derived are updated at an i operator selected rate of 2 to 10 seconds. Signals in this category are:

APRM Power SRM Flux *

! Reactor Wide Range Level Reactor Steam Flow

! Narrow Range Drywell Pressure

! Containment Temperature 1 Drywell Temperature i Suppression Pool Temperature .

22 Containment Isolation Signals

Trend Information l

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EOP Support Displays o General The purpose of the EOP support displays is to provide the operators with the information necessary for the performance of functions required by the upgraded Emergency Operating Procedures. The display formats incorporated into the EOP support system contribute to a significant reduction of risk and an enhancement in the safety of operation.

The EOP display system will be used by the operators to determine specific actions required to prevent or minimize core damage or prevent release of radioactivity to the environment. This system consists of eight DCS Displays and five PMS displays which can be selected at the NUCLENET and used specifically to support the E0Ps in conjunction with the SPDS.

o Access Operational control of the EOP support system is normally through the DCS Selection Matrix with the individual CRT selector switches in master. By selecting the E0P Support sc Integrated Plant Operating Activity the operator can Q'w simultaneously call up each of the eight E0P DCS Support displays. Figure 1 provides the new Plant Operating Activity Format Matrix for E0P Support. The use of the selector switches or selectior. matrix has no effect upon the displays in the Technical Support Center (TSC) or Emergency Operations Facility (EOF).

o Alarm Initiated Display (Figure 7) _ ,

This is the same AID as described before. This transient display is only visible at the bottom of the CRT when one of the parameters in the display is in the alarm state. At that time all the parameters will be displayed with the alarming one(s) in red. The AID will be visible on all ,

active DCS CRTs and provides an indication to the operator that he should consider initiating the E0Ps.

o 1S Reactor Core Cooling Display (Figure 2)

The purpose of the Reactor Core Cooling Display is to show the reactor water level in relation to the core height and _

at the same time present the operator with information on the sources of water available. The display alerts the rm 6

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t operator that the level has exceeded various limits 4

requiring various automatic actions. The display of all j channels and reference leg temperatures aids the operater in i

validating water level information. The operator can also-j verify the automatic transfer of RCIC and HPCS to the '

, suppression pool for suction to prevent.overstressing

] containment with excess water inventory.

1 j o 2S Containment Support Display (Figure 3) l The Containment Support Display allows the operator to verify the operability of containment and aids the operator

in taking the required actions to preserve the integrity of containment through the use of E0Ps.

l l Safety Relief Valves display is normally green and changes to red when the SRV opens.

! The dynamic values A and B are normally not displayed but i appear in red when the associated Containment Spray Loop

activates.

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o 3S Time History Display (Figure 4) i The level / pressure display versus time is the controlling j- display for level control actions. The actions are based on

pressure, level, and the direction of change. This and the .

injection status dictate actions in the Level Control E0P.

} The plot displays reactor level in blue and. reactor pressure 5

in red. The lines (tic marks) represent one minute, the j update interval. The right side of the plot is.the most recent point and each update moves the plot to the left.

} When called up the display provides plots of the most recent ,.

30 minute period.

} o 4A Recirc Flow Display (Figure 5) l The Recire Flow display provides the information necessary .,

i for the operator to evaluate recire flow and the condition of the rectre pumps.

Valves 60A and 60B are throttle valves in which half of the j valve will be green, the other half red in any but full'open

! or full closed positions.

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] o 6S Reactivity Control Display (Figure.8)

The purpose of the Reactivity Control display is to. allow-the operator to-trace reactor power during-all types of

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, 7-7 transients without having to switch displays. Control rod g_) drive information is included to provide the op.erator with ,

information on the ability to manually insert rods.

o 7S Steam Supply and Bypass System Display (Figure 9)

The Steam Supply and Bypass Syst.n display is used by the operator to ensure the steam system operates properly.

l o 8S Electrical Distribution Display (Figure 10)

The Electrical Distribution Display provides the operator with a status summary of the lE electrical distribution system. Some main turbine parameters are included to ensure

, the turbine is not-inadvertently damaged. _

The breakers change from green to red when closed.

When the Turning Gear is not engaged the word "NOT" appears in red. The "NOT" is normally absent from the display.

i' o 9S Containment Isolation Display (Figures 11 - 16)

The Containment Isolation display provides the operator with s a summary of the status of the containment isolation groups 1 from which the operator can quickly determine the status of any group isolation.

Blocks for each group change from red to green when isolation occurs.

The "PMS Display Number" at the top of the display refers to i the PMS Display which must be called up. and each Grou?

j notes the page of the display, to provide details on the _,

valves and conditions that make up the isolation group. '

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Integrated Plant DCS CRT Operating Assigned Activity to Sys.

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COLD S"L1RTUP IC 2A 3C 4A SS 6S 7A 83 9A ACHIEVE CRITICALITY IC 2A 3C 4A SS -6S 7A 83 9A SRM/IRM OVERLAP 1C 2A 3C 4A SS 65 7A 83 9A HEATUP/C00LDN IC 2A 3C 4A 5S 6S 73 83 9A IRM/APRM OVERLAP IJ 2J 3E 4A 6S SS 73 83 9B HOT STARTUP/ RESTART 1C 2A 3C 4A 5S 6S 7F 83 93

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HOT STANDBY 1C 2A 3C 43 SS 65 7F 83 93 POTc.R VARIATION (10-30") IJ 2J 3E 4A SS 6S 7F SC 93 POWER VARIATION (30-10%) lJ 2J 3D 4J 5S 6S 7F 8C 93 HORMAL SHL"IDOWN PREP 1C 2J 3J 4J 5S 65 7F 8C 9B EMERG. SHUTDOWN 1C 2A 3E 4A 55 6S 7F. 83 93 '

EOP SUP? ORT IS 2S 3S 4A SS 65 7F 85 9S COLD RESTART 1C 2A 3C 4A SS 6S 7A 83 93

• TUR3 ROLL / SYNC IC 2J 3C 4A SS 6S 73 8C 93 BASE LOAD SURVEILLANCI IJ 2J 3J 4J SS 6S 7J 8J 9J l

t FIGURE 1 INTEGRATED PLANT OPERATING ACTIVITY MATRIX

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REACTOR CORE CCOLING DISPLAY (13)

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Q FIGURE 10 .

i ELECTRICAL DISTRIBUTION DISPLAY (85) l l

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CONTAINMENT ISCLATICN SU.TARY PMS DISPLAY NUMBER (l at es-)

• INBCARD CUT 30ARD INBCARD CUTECARD M GRCUP 1 M M GRCUP 7 M PAGE 1 PAGE 2 M GRCUP 2 M M GRCUP S M PAGE 1 PAGES 3/4 M GRCUP 3 M M GRCUP

• M PAGE 1 PAGE 5 M GRCUP 4 M M GRCUP 10 M PAGE 1 PAGE 4 M GRCUP 5 m M GRCUP 11 M PME2 PME5 M GRCUP b M PAGE 2

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FIGURE 11 Q CONTAINMENT ISOLATION DISPLAY (9S) i l . _ . . . . . - . -

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l GROUP 1 INBCARD CUT 3 CARD E 321.' " 4 A MN STM LINE CONMT ISCL SO1.*C2SA E E B21FO~' 3 MN STM LINE CCNMT ISCL 321FC SS E E 221FCOOO C .% STM LINE CONMT ISCL 201F " C E E SO1FOCOD D MN STM LINE CCNMT ISCL S21FC09D E E S21FOl6' NN STM DRN/MSIV BYP CONMT ISCL B21.8019 E A MN STM LINE DRAIN ISCL

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Q E E11:049 RHR S TC RADWASTE ISCLAT!CN E10F040 E E E11cO60A R!-R A HX SAMPLE ISCLATICN E10FO75A E

, B E1 FC608 RHR S HX SAMPL: ISCLATICN E12.CO753 5 GRCUP E E10.CC09 SHUTOCWN CCCLING SUCT ISCL ElleOCS E RHR A TO SMUTDCWN CCCLING RTM E12FC50A B RHR S TC SHUTDCWN COOLING RTN E11'C533 5 ,

E E10F007A RHR A TO CNMT PCOL CLG SHTCFF E E10cc ,< .: RHR S TO CNMT PCCL CLG SHTCFF RHR S TO REACTCR HEAD SPRAY E10.'000 5 i

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G FIGURE 12 i PMS DISPLAY - CCNTAINMENT ISOLATION - PAGE 1

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. GRCUP 4 INSCARD ,CUTSCARD E 5-COOL RWC SUCT ISCL u a OO4 5 E Gua-CC9 DRN FLCW HDR CNMT ISCL GCFOO4 5 E w cO40 RWC RTN HDR CNMT ISCL S-cOOo E 5 G3;F05: RWC PUMPS DISH CNMT ISCL ' h eO54 5 GRCLP 5 x -

E B30F01? ReCIRC SYS SAMPLE ISCL B,7, 0C0 5 GRCUP 6 T

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A RCIC PUMP SUPP PL SUCT VLV E51.2001 E E E51F06: RHR / RCIC ST SUPP -ISCL VLV EE1.2064 5 E E51F076 RHR / RCIC ST SUPP WARM UP ISCL VLV ,

GRCUP 7 i

i 5 E51F07S RCIC EXH VAC SKR ISCL VLV S51.2077 5 '

FIGURE 13 PMS DISPLAY - CONTAIN'ENT ISOLATION - PAGE 9 I 1 i

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. INBCARD CUTSCARD E 1CCF050 CNMT A SUPPLY E 1COFOEO 1CCe049 5 CNMT COW RETURN ' 1CCF054 5 E 1CCFC 7 CNMT COW SUPPLY TO NRHX E 1CCF060 5 1COF1 3 CNMT C RETURN FRCM NRHX B 1CCF127 CNMT COW RETURN FROM NRHX CNMT COW SUPPLY TO NRHX 5 1FCFOO7 CNMT hC ISCLATICN 5 1FCF007 CNMT ~FC 1FCFOO6 5 CUTLE ISCLATICN 1FCF009 5 3 1FPF050 CNMT FP SUPPLY ISCLATICN 5 1FPF052 CNMT FP 1.CFF092 5 E 1FPF050 SUPPLY ISCLATION IFPF051 E CNMT FP SUPPL.Y ISCLATICN IFPF054 5 5 IIAF0103 CNMT COMPRESS C-AS E LIAF0103 IIAF012A E CNMT COMPRESS SAS IIA 010A E E IIAF006 ,CNMT INST AIR SUPPLY E ISA 000 C.%"1T 12AF005 E

- SERVICE AIR SUPPLY ISAFOO? E M) E iSXF08?A CNMT SX SUFFLY ISCLATICN 1.SXFOSSA E E ISXF0599 CNMT EX SUPPLY E ISXF006A ISCLATICN ISXFOGES E CNMT SX SUMLY ISCLATICN ISXF097A E E ISX.00963 C?c 7 EX SUPPLY ISCLATION ISXFO?TS E E ISFF000 CNMT SF RETU.cJ4 ISCLATICN 1SF 001 5 CNMT

• F SUPPLY ISCLATICN 1SF:004 E - -

5 1WCF0013 E 1WCF002S CNMT CHILL WTR SUPeLY ISCL 1WC.2001A E CNMT CHILL WTR RETURN ISCL 1NC.2000A 5 R OMCF010 9 E 1CYC017 CNMT MAKE UP CONDENSATE ISCL CMCF009 E CNMT CYCLE CONDENSATE ISCL. ICyeo:3 3

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FIGURE 14

?MS DISPLAY ~- COMA. Nit:.x ISOLATION - PAGE 3 t

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INBCARD CUT 3 CARD E IVRFOOC3 ,

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d 3.2 Drywell Temperature and Pressure Control (DW/T)

Section DW/T attempts to maintain drywell temperatures and pressure within desirable limits by operation of CGCS compressors and drywell coolers. If temperatures increase high enough to affect the accuracy of RPV water level instruments, RPV flooding .is required. If temperatures increase high enough to jeopardize the pressure suppression function or challenge containment integrity, the RPV is depressurized.

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A simplified flow diagram of DW/T is illustrated in Figure DW/T-1.

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\_) STEPS OBJECTIVES Initiate Auto action which did not occur Scram, isolate, initiate ECCS (DW/T-1) 1F Start a CGCS compressor Reduce drywell pressure (DW/T-2)

Y Operate available drywell cooler Reduce drywell temperature (DW/T-3)

Y If temp. reaches RPV saturation ~, flood RPV (DW/T-4) Assure core cooling lf If temp. can't be maintained 330*F, Depressurize RPV Terminate energy addition (DW/T-5) l l

l Figure DW/T-1 Drywell Temperature and Pressure Control, _

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(_ NOTE Perform step 3.6 (PC/P) concurrently with this procedure.

CAUTION #6 Whenever Drywell temperatures exceed the temperature in Table 1 and the instrument reads below the indicated level listed in Table 1, the actual RPV water level may be anywhere below the elevation of the lower instrument tap.

TABLE 1 ,

Temoerature Level Instrument Any 66 Shutdown Range 232 73 Upset Range

" 545 -160 Wide Range q

545 0 Narrow Range 545 -150 Fuel Zone 3.2.1 IF 2 psig Drywell pressure is reached (DW/T-1)

THEN Verify the appropriate automatic actions have occurred and manually perform any that have ,

not.

Objective: Initiate appropriate scram, isolation and ECCS initiation signals. _

! Discussion: High drywell pressure is indicative of a LOCA and certain automatic responses are incorporated in the plant design, i

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/' Scram initiation, containment isolation, and ECCS initiation are

('-') verified because of their importance in the plant's response to a LOCA.

General Caution #6 is applied here to remind the operator that elevated drywell temperature may affect the validity of displayed water level trends. _.

F 3.2.2 IF The high drywell pressure of 2 psig (Dw/Y-t) was due to a loss of the Drywell Cooling System THEN Start Combustible Gas Control System Compressors lA & IB, lHG02CA & B, per CPS No.

3316.01, CONTAINMENT COMBUSTIBLE GAS CONTROL (HG).

Objective: Reduce drywell pressure to below the containment isolation setpoint.

lh Discussion: The use of the CGCS compressor to reduce drywell pressure is permitted if the cause of the drywell high pressure is loss of normal cooling. At this pressure, all normal means of cooling and reducing drywell pressure would be isolated. Without utilizing the RPV had been sufficiently cooled down.

CGCS is not directed to be used until after the drywell pressure scram / isolation setpoint is reached to ensure the automatic actions associated with a LOCA condition, which may exist, are not __ _

overridden. Also when drywell pressure is less chan 2 psig the normal cooling and ventilation methods should be available.

3.2.3 Operate all available Drywell Coolers as per CPS No.

3320.01, DRYWELL COOLING (VP).

(bw/T-3) l Objective: Reduce drywell temperatures to below normal limits. - -

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( Discussion: If elevated drywell temperatures exist, the operator should attempt to reduce the temperature to within the normal operating range by using available drywell coolers. If available cooling is sufficient to prevent further temperature increases, the operator need progress no further in Section DW/T. Similarly, if some other condition required entry to the Containment Control Guideline (e.g., low suppression pool water level) and drywell temperature is already within acceptable limits, no action need be taken in DW/T.

NOTE Perform steps 3.2.4 and 3.2.5 concurrently. .

3.2.4 IF Drywell temperature reaches the RPV (DW/T-4) ~~ saturation temperature shown on Graph 2.-

THEN RPV Flooding is required, en'ter section 4.1 EMERGENCY RPV DEPRESSURIZATION and section 4.2 RPV FLOODING. Execute them concurrently with this section.

O Objective: Assure core cooling under conditions in which.RPV water level instrumentation cannot be relied upon.

Discussion: As discussed in Caution #6, BWR water level instruments sense liquid level in the downcomer region by measuring the pressure differential between a variable leg water column and a ~'

reference leg water column. If reference leg water temperatures reach saturation (defined by the curve in step DW/T-4), the column of water will begin to boil, and the reference leg water inventory will gradually be depleted. As the level of water in the reference leg drops, the differential pressure sensed by the level instrument will decrease, and the indicated RPV water level will become '

erroneously high. The effect is slow, but nonetheless suggests potentially serious consequences. The. operator might gradually throttle injection. systems in response to the perceived slow increase in water level until,. ultimately, the actual water level-may fall below the lower instrument top.

With the loss of these instruments, the operator no longer has the -

capability of ascertaining RPV water level. It is then appropriate to flood the vessel so that core cooling may be O

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<'T assured, even though the actual water level in unknow. The

( operator is therefore directed to enter the RPV Level Control Guideline at the beginning, whether or not he has already performed actions in that section. In accordance with directions preceding Step RC/L-2, he will enter Contingency #6 and flood the vessel.

Section RC/P will establish the mode of pressure control appropriate for these actions in accordance with the instructions preceding Step RC/P-1. '

Because the reference leg pressure is equal to RPV pressure, a reference leg temperature above saturation requires d drywell temperature above the RPV temperature. Since the reactor is the primary heat input to the containment, this an unlikely set of circumstances , but by no means impossible. For instance, if drywell coolers are lost, the drywell temperature will increase until, assuming no further action, it ultimately equals the RPV _

temperature. If, subsequently, emergency RPV depressurization is required, RPV pressure could be reduced below the saturation curve, and reference leg boiling could occur.

3.2.5 IF Drywell temperature cannot be maintained (DW/T-5) -- below 330*F

() THEN EMERGENCY RPV DEPRESSURIZATION is required, enter section 4.1 EMERGENCY RPV DEPRESSURIZATION and execute it concurrently with this section.

Objective: (1) Terminate energy addition to drywell. _,

(2) Prevent inopportune loss of pressure suppression function.

Discussion: If drywell temperatures cannot otherwise be maintained below design limits, the energy addition to the drywell ,

should be terminated by rapidly depressurizing the RPV. This will transfer energy from the RPV to the suppression pool, lowering RPV temoeratures to approximately 300*F (assuming the RPV~is depressurized to 50 psig) and reducing any existing break flow.

Continued heacup of the drywell is thereby avoided.

Once the necessity for emergency RPV depressurization has been ~_

established, the operator is directed to enter the RPV Control Guideline at the beginning, whether or not he has already performed l actions in that section. He will then scram the reactor (if not i ,

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i l already done) and execute Sections RC/L, RC/P, and RC/Q concurrently. Contingency #2 will' be entered in accordance with  ;

the instructions preceding Step RC/P-1. l r

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