ML17341B196

Emergency Operating Procedure 20002 (E-2), Loss of Secondary Coolant.

ML17341B196
Person / Time
Site:	Turkey Point
Issue date:	02/17/1982
From:	FLORIDA POWER & LIGHT CO.
To:
Shared Package
ML17341B195	List: ML17341B194 ML17341B196
References
20002.2, IEB-80-04, IEB-80-4, NUDOCS 8206020390
Download: ML17341B196 (16)

Text

FLORIDA POWER AND LIGHT COllPANY TURKEY POINT UNITS 3 AND 4 EislERGENCY OPERATING PROCEDURE 20002 (E-2)

FEBRUARY 8 1982

1.0 Title

LOSS OF SECONDARY COOLANT 2.0 A royal and List of Effective Pa es:

2.1 ~Ao rova'I:

Change dated 2/8/82 Reviewed by PNSC Februar 8 1982 Approved by ~

"-- Plant b1gr-N iowa. l7 19/2.

2,2 List of Effective Pages:

~Pa e Date ~Pa e Date ~Pa e Date ~a<ac Date 2/8/82 3 3/5/81 5 3/5/81 7 3/5/81 2 2/8/82 4 2/8/82 6 2/8/82 8 2/8/82 The objectives of these instructions are as follows:

3.1 To establ ish stabi1 i zed reactor coolant system and steam generator conditions prior to plant cooldown.

3.2 To minimize the energy release due to the break by isolation of the break where possible.

3.3 To prevent the pressurizer safety valves from lifting by dumping steam from all steam generators to the main condenser when possible or to the atmosphere from the unaffected steam generators.

3.4 To isolate the auxi 1'iary feedwater flow to the affected steam generator, to maximize auxiliary feedwater flow to the intact steam generators, and minimize the energy release.

3.5 To borate the reactor coolant to establish and maintain reactor shutdown margi n.

4A.O, ~S toms:

Refer to sect i on on Symptoms, Emergency Operating Procedure 20000 (E-O),

Irrmediate Actions and Diagnostics.

82060203'ii0 820527 PDR ADOCK 05000250 8 PDR ~

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2/8/82 EMERGEi'ICY OPOTYNG PROCEDURE 20002, {2-2), lc 2 LOSS OF SECONDARY COOLANT 5.0 Immediate Actions:

JNOTE: A loss of secondary coolant is an UNUSUAL EYEiYT. Notify the i'luclear 5.1 On Affected Unit:

Refer to section on Immediate Actions of Emergency Operating Procedure 20000 (E-O), Immediate Actions and Diagnostics, if not already performed.

NanuaI Actions:

If safety injection actuation occurred as a result of high steam line flow with low Tavg or low steam generator pressure, steam line isolation should have occurred.

In that case verify the actuation of steamline isolation. If not actuated, manually initiate steam'line isolation.

NOTE: If the steam line isolation valves fail to close, this 5.2 On Non-affected Unit:

It is considered to be advantageous to maintain the non-affected unit in operation during the initial phases of this type accident, as long as the requirements of Technical Specifications, Section 3.4 (R>IST level > 320,000 gallons), are not violated.

5.2.1 Maintain the non-affected unit as near as possible to steady state conditions during initial phase of accident.

5.2.2 Close steam generator blowdowns on non-affected unit to conserve condensate storage tank water.

5.2.3 After verifying that the high head SIS pumps on the non-affected unit are operating, close SIS sectional izing val ves l~iOV-"-878A and EMOV-*-8788. Mhen the SIS signal has been reset stop the high head SIS pumps on the non-affected unit and return their switches to auto.

CAUTION: It is imperative that a minimum of two safety injection pumps remain operating to supply injection to the affected unit. If one or two safety injection pumps are out of service on the affected unit., continue operating the pumps from the non-affected unit. Do not close SIS sectionalizing valves NOV-*-878A and L~10V-*-8788.

If RWST level on the non-affected unit drops below 320,000 gallons begin an orderly shutdown of that unit at a rate prescribed in Administrative Procedure 0103.8, Shutdown Rate Guidelines.

5.3 Subsequent Actions:

CAUTION: The diese1s should not be operated at idle or minimum load for longer than 15 minutes. If the diesels are shut down, they should be prepared for res art.

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3/5/81 EIIERGENCY 0 TING PROCEOURE 20002, LOESS OF SECONDARY COOLANT.

(2-2), fQ 3 NOTE: The process variables referred to in ,this Instruction are typically monitored by more than one instrumentation channel.

The redundant channels should be checked for consistency while performing the steps of this Instruction.

NOTE: The pressurizer water level indication should always be used in conjunction with other specified reactor coolant system i,ndications to evaluate system cond'itions and to initiate manual operator actions.

5.3.1 If reactor coolant pressure is above the low head safety injection pump shut-off head (approx. 185 psig), manually reset safety injection so that safeguards equipment can be controlled by manual action. Ensure that containment isolation is maintained. Stop the low head safety injection pumps and. place, in the standby mode.

CAUTION: Whenever the wide range reactor coolant pressure decreases below the low head safety injection shutoff head, the low head safety injection pumps should be manually restarted to deliver fluid to the reactor coolant system.

CAUTION: Automatic reinitiation of safety injection may not occur so the operator must carefully monitor plant parameters during subsequent evolutions to determine manual safety injection exists.

if the need for CAUTION: Subsequent to this Step should loss of offsite power occur, manual action (e.g., manual safety injection initiation) wil be required'o load the safeguards 1

equipment onto the diesel powered emergency busses.

5.3.2 Stop all reactor coolant pumps, after high head safety injection pump operat>on has been veri ied and when the wide range reactor coolant pressure is at ~1400 psig as seen on PI-*-403, YPA or PI-*-40E YPG.

CAUTION: If component .cooling water to the reactor coolant pumps is isolated on a containment pressure signal, all reactor coolant pumps should be stopped lDELETEDt because of loss of motor bearing cooling and ~therma barrier cooling.

Increased component cooling water, requi rements, resulting from safety injection may cause closure of FCV-*-626.

Verify that FCV-*-626 is open.

NOTE: The conditions given above for stopping reactor coolant pumps should be continuouslv monitor ed throughout this instruction.

NOTE: If reactor. coolant pump termination is necessary, verify the steam dump to condenser auto manual controll r potentiometer setpoint is correct and place the steam dump selector switch to manual prior to tripping the reactor coolant pumps.

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2/8/82 EMERGENCY OP~TING LMS PROCEDURE 20002, (E-2),

OF S ECONOAR Y COOLANT F+ 4 CAUTION: If component cooling water to the reactor coolant pumps is lost while there is no seal water injection, close

• -2930 and +-2398, charging flow to seal, water injection filters. This will preclude thermal shocking the RCP's on restart of the charging pumps. If component cooling water to the reactor coolant pumps is subsequently regained, *-2930 and *-2938 may be reopened.

5.3.3 Oetermine which steam generator is affected by observing the individual steaml ine pressures '(PANS) . A 1 ow steaml ine, pressure compared to the others denotes the faulted loop; terminate. auxiliary feedwater to that steam generator.

NOTE: tf all steam generators are depressurized or depressuri zing, the auxiliary feedwater flow must not be terminated to any steam generator until the faulted loop is identified.

NOTE: If no loop has a low steamline pressure compared to the others and all steamlines have been .isolated, determine -if a break has occurred i.n the steamline, or in any piping system that connects with the secondary pressure boundary. If no indication of a break in the pressure boundary is found, go to Section 5.2 of Emergency Operating Procedure 20000 (E-0) and re-evaluate the accident with particular emphasis on the Loss of Reactor Coolant. If a leak from the secondary systems is found, continue to follow these instructions.

J NOTE: If the problem cause is determined to be. a stuck open steam generator safety or steam dump valve resulting in rapid RCS cool down or steam generator depressuri zation, this is'n UNUSUAL E~/ENT. Notify the Nuclear Pl'ant Supervisor .

5.3.4 If the water level in the non-faulted steam generators i,s in the narrow .range span, regulate the auxiliary feedwater flow to those steam generators to maintain an indicated narrow range steam generator water level. If water level increases in an unexplained manner in one steam generator., go to Emergency Operating Procedure 20003 (E-3), Steam Generator Tube Rupture.

l'lOTE: Monitor the Condensate Storage Tank level and before reaching a low level, notify the A.E.O. to put the water treatment plant in service (if available).

5.3.R If containment spray has been actuated, and containment coolers are operating, reset containment spray.

if the emergency Spray pumps should be shut off and placed in the standby mode with operable flow paths.

52 3.6 NOTE: The conditions given below for termination of safety injection shou'Id be continuously monitored throughout this instruction.

A. If, l. Ane 'wide range reactor coolant temperature TH as confirmed by. core exit thermocouples, less than 350', F, AND if avai'lable, is

2. Mide range reactor coolant pressure is greater than 700 psig and is stable or increasing ANO

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3/5/8j EMERGENCY 0+AT)NG PROCEDURE 20002, (E-2),

MOSS OF S ECONOAR Y COOL'AN)T QE 5

3. Pressurizer water level is greater than 20> of span and rising (heaters covered) AND

4. The reactor coolant indicated subcooling is greater than

~60' (Subcool ed Margin Monitor), AND

5. Auxiliar feedwater flow is isolated to all depressuri zed steam generators and at 1 east 570 gpm i s injected into the non-faulted steam generators or indicated narrow range water level in at least one non-faulted steam generator is greater than 15 percent of

~san .

Stop all safety injection pumps and place in the standby mode and maintain operable flow paths.

CAUTION: If wide range reactor coolant pressure decreases more than 200 psi or pressurizer water level decreases by 10~> of span following termination of safety injection or the reactor coolant subcooling drops below 60' , MANUALLY REINITIATE safety injection pump operation to maintain reactor coolant pressure and pressurizer water level. Go to Section 5.2 of Emergency .Operating Procedure 20000 (E-0) to reevaluate the event, unless this reevaluation has already been performed.

NOTE: If all wide range reactor coolant temperature indicators go above 350'F when attempting to satisfy the conditions of ~5.3.6.A, initiate safety injection pump operation and continue operation until conditions of J5.3.6.8 and ~5.3.6.C are satisfied.

THEN Go to Step 5.3.6.7 JBB lF (l) Al 1 wi'de range reactor coolant temperature TN (PAMS) are greater than 350', AND (2) Reactor coolant pressure is above the shutoff head of the safety injection pumps, ANO (3) Safety injection flow to the Reactor Coolant System is zero, THEN attempt to reestablish the reactor coolant pressure to greater than 2000 psig and pressurizer water level to greater than 50% of span by (1) Resetting safety injection, and (2) Establishing full charging flow.

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2/8/82 EHEROEHCv ORWTrHO M

RROCEDURE EOOOE, (E-E),

S OF SE CONDARY COOLANT r E NOTE: Ensure that water addition during this process does not result in di"lution of the reactor coolant system water.

C. WHEN (1) All wide .range reactor coolant temperature TH are greater than 350 F, AND (2) Wide range reactor. coolant pressure is greater than 2000 psig and is stable or increasing ANiD (3) Auxiliary feedwater flow is isolated to all depressurized steam generators .and. at least 570 gpm i's injected into the non-faulted steam generators or indicated narrow range water level in at least one non-faulted steam generator is greater than 15$ of span, AND (4) Pressurizer water level is greater than 50 percent of span, AND (5) The rector coolant indicated subcooli ng is greater than 50 . (Subcooled i~largin iYonitor s)

NOTE: If all steam generators are depressurized or depressuring, the safety injection flow must not be terminated unti.l the faulted steam generator is identified.

THEN go to Step 5.3.6.D D. Stop all safety injection pumps and place i,n the standby mode and maintain operable safety injection flowpaths.

CAUTION: If wide range reactor coolant pressure decreases by 200 psi or pressurizer water. level drops by 10 of span following termination of safety injection or the reactor coolant MANUALLY REINITIATE subcooling drops below safety injection pump operation 50',

to maintain reactor coolant, pressure and pressuri zer level. Go to Section 5.2 of Emergency, Operating Procedure 20000 (E-0) to reevaluate the event, unless this reevaluation has already been performed.

JHOTE: Loss of reactor subcooling margin is an UHUSURL E'IEHT.

Notify the Nuclear Plant Su ervisor .

E.'eset containment isolation (Phase A). Re-establish normal makeup to maintain pressurizer level i'n the normal operating range and to maintain system pressure at a nominal value of 2000 psig. Ensure that water addition during this process does not result in dilution o the reactor coolant system boron concentration.

~l 3/5/81 EMERGENCY OlATING PROCEDURE 20002, (2-2), NIE 7 LOSS OF SECONOARY COOLANT

~F. Re-establish operation of the pressurizer heaters after verification of sufficient pressurizer ,level to assure coverage of the pressurizer heaters, e.g. through comparisons of pressurizer surge line, water space, and vapor space temperatures. ilhen system pressure can be controlled by pressurizer heaters, and containment temperatures are ,low enough to assure proper operation of control systems, restore normal pressurizer 1'evel control.

5.3.7 Monitor either the average temperature indication of core exit thermocouples (if available) or all wide range reactor coolant temperature TH to verify that RCS temperature is at least 50'F less than saturation temperature at RCS indicated pressure.

If 50'F indicated subcooling is not present, then attempt to establish 50'F indicated subcooling by steam dump from the steam generators to the condenser or the atmosphere.

CAUTION: 'If steam dump is necessary, maintain a reactor coolant cooldown rate of no more than 50'F/HR, consistent with plant make-up capability.

Steam dump should be initiated in the following manner to stabilize reactor coolant system temperature:

l. Establish a flow path in at least one steamline in an intact loop (if possible) IF the main condenser is available and IF an uncontrolled steam release is not reinitiated upon opening the NSIV. Transfer the steam dump system to steam header pressure control. Set the steam header pressure control setpoint to the pressure in the intact steam generator(s) at the time safety injection is .terminated.

OR

2. Oump steam to the atmosphere from the intact loops using the steam generator atmospheric dump val ves. Set each steam generator atmospheric dump valve pressure control setpoint to the pressure in the intact steam generator(s) at the time safety injection is terminated.

If 50'F indicated subcooling cannot be established or maintained, then manuall reinitiate safet i n 'ection. Go to Section 5. 2 of Emergency Operating Procedure 20000 'E-0) to re-evaluate the event, unless the re-evaluation has already been performed.

5.3.8 Mhen the reactor coolant -temperature and pressure are stable, borate the reactor coolant system to cold shutdown conditions, as necessary.

5.3.9 Refer to Operating Procedure 20000 (E-O), Steps 5.2.7.13 - 5.2.7. 15 to evaluate .plant status affected by safeguards actuation.

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2/8/82 EMERGENCY OPERYNG PROCEOVRE 20002, (2-2), PAoc 8 LOSS OF SECONDARY COOLANT 5.3.10 After of f site power i s ava i abl e, establ i sh the auxi i ary systems 1 1 necessary for a controlled cooldown to cold shutdown. If offsite power is available and all reactor coolant pumps are stopped, restart at least one reactor coolant pump in an intact loop (with the pressurizer spray line if possible) for cooldown purposes in accordance with procedures. Maintain subcooled conditions in the reactor coolant system consistent with the normal cooldown curve. If these subcooled conditions cannot be maintained, restart safety injection pumps; NOTE: If there is significant radioactivity in one or more steam generator's secondary side due to tube leaks and steam is being dumped to the atmosphere, immediately isolate the steam generator associated with the break. If all steam generators with significant radioactivity cannot be isolated, begin cooldown and depressurization of the reactor coolant system to limit the release of radioactivity to the environs.

J NOTE: Greater than 10 gps primary to secondary leakage is an ALERT. Greater than gpm primary to secondary leakage with high RCS activity ( I f)I ) 300 qCi/ml) is a SITE EMERGENCY.

Notify the Nuclear Plant Su ervisor 5.3. ll After establishing operation of auxiliary systems, initiate a controlled cooldown and depressurization to cold shutdown conditions using Operating Procedure 0205.2, Reactor Shutdown, Hot Shutdown to Cold Shutdown Conditions.

NOTE: Safety Injection should be reinitiated i f an uncontrolled reactor cool ant system depressuri zati on or an uncontrol ed 1 drop in pressur izer water level occurs during the cooldown process.

NOTE: During the cooldown, the reactor coolant system pressure will decrease below 1400 psig. Tripping the operating reactor coolant pump(s) due to the pressure criterion of Step 5.3.2 is not required. Other criteria of Step 5.3.2 are stil 1 applicable at this time.

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References:

6.1 FSAR 14.2.5, 8reak of a Steam Pipe 6.2 Westinghouse Emergency Operating Procedure (E-2), Loss of Secondary Coolant 6.3 Emergency Operating Procedure 20000 (E-O), Immediate Actions and Diagnostics 6.4 Emergency Operating Procedure 20003 (E-3), Steam Generator Tube Rupture 6.5 Operating Procedure 0205.2, Reactor Shutdown, Hot Shutdown to Cold Shutdown Conditions Records Reports and Notifications 7,. 1 Sequential log entries in the Nuclear Plant Supervisor's Log 8ook of the significant events pertaining to the Loss of Secondary Coolant.

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