ML18051A550

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Rev 15 to Emergency Operating Procedure EOP 8.1, Loca.
ML18051A550
Person / Time
Site: Palisades Entergy icon.png
Issue date: 08/15/1983
From:
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML18051A543 List:
References
TASK-15-02, TASK-15-2, TASK-RR EOP-8.1, NUDOCS 8308230404
Download: ML18051A550 (16)
v • d • e


Text

ENCLOSURE 2 ATTACHMENT 4 CONSUMERS POWER COMPANY PALISADES PLANT DOCKET 50-255 Emergency Operating Procedure EOP 8.1 "Loss Of Coolant Accident" (Abridged)

August 15, 1983 15 Pages

(--8308230464 830815 I ~DR ADOCK 05000255

'l PDR NU080983-NL01

PALISADES NUCLEAR PLANT Proc No EOP 8.1 EMERGENCY OPERATING PROCEDURE Revision 15 Page 1 of 8 TITLE: LOSS OF COOLANT ACCIDENT Definition: Leak rate exceeds capacity of operable charging pumps.

1.0 SYMPTOMS Any one or more of the following symptoms may be present.

a. Standby Charging Pumps start.

CAUTION Pressurizer level may not be a true indication of PCS fluid inventory.

b. Pressurizer level abnormal. (Low or High)
c. Pressurizer low pressure.
d. Containment high radiation.
e. Containment high pressure and/or temperature.
f. Containment high humidity.
g. Containment sump level increasing.
h. Volume Control Tank level decreasing.
i. Quench Tank high level, temperature or pressure.
j. High startup rate alarm (Control Rod ejection).
k. High power level Reactor trip (Control Rod ejection).

2.0 AUTOMATIC ACTIONS

  • a. Standby Charging Pumps start.
b. Reactor trip.
c. Safety injection actuation.
d. Containment spray actuation.
e. Containment isolation.
f. Auxiliary Feedwater initiated.
g. Main Steam Isolation Valves close on Containment High Pressure (5.3 psig) -k;'*E-50A, ;':;'*CV-0510, and ;':;'*E-5013, ;':;'*CV-0501.

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PALISADES NUCLEAR PLANT Proc No EOP 8.1 EMERGENCY OPERATING PROCEDURE Revision 15 Page 2 of 8 TITLE: LOSS OF COOLANT ACCIDENT

  • 3.0 3.1 3.2 IMMEDIATE ACTIONS Trip the reactor; perform EO~ 1 Immediate Actions.

Verify safety injection actuated. Initiate manually, if PCS pressure is less than or equal to 1605 psia or containment pressure is greater than 5 psig.

.3,3 At PCS pressure of 1250 psia, or if containment pressure reaches 5 psig, manually actuate containment isolation:

Push the manual initiate push buttons for Containment High Radiation (Left and Right Channels) located on the front of panel ;':;':EC-13.

3.4 If containment pressure increases to 5 psig, verify Containment Spray initiated, If necessary, manually initiate Containment Spray.

3.5 Attempt to locate and isolate the break if possible:

a. Isolate letdown line by closing **CV-2009 (outside containment) or
'
;'i"CV-2001 (inside containment).
b. Verify PORVs and isolation MOVs* closed* .
  • c.

d.

Isolate PCS sample lines. (Close ;b':CV-1910 and ;'n':CV-1911).

Check Acoustical Monitor Panel ;':;':EC-51 and Pressurizer Relief Valves Discharge Temperature Indicators for symptoms of pressurizer relief valve leakage.

e. Check Quench Tank level, pressure and temperature indications normal.

3.6 Check that the Main Steam Isolation Valves have closed on Containment High Pressure (5 psig) -::;':E-50A, -:d:CV-0510 and -::;':£-SOB, ;':;'*CV-0501.

3.7 Place Turbine Generator Turning Gear Motor **K-2 Control Switch in "PULL TO LOCK".

3.8 ACTIVATE SITE EMERGENCY PLAN. REFER TO SITE EMERGENCY IMPLE}illNTING PROCEDURE EI-1.

4-.0 SUBSEQUENT ACTIONS NOTE: Use Attachment 6 as a guide only for subsequent action items. If break has been isolated and criteria in Attachment 6 are satisfied, proceed as shown in Attachment 6.

4.1 Verify all immediate actions have been initiated .

NOTE: This procedure is to be performed in conjunction with EOP 1.

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PALISADES NUCLEAR PLANT Proc No EOP 8. I EMERGENCY OPERATING PROCEDURE Revision 15 Page 3 of 8 TITLE: LOSS OF COOLANT ACCIDENT

  • CAUTION If a SIS signal is received or priamry pressure drops below 1605 psia after the start of a Loss of Offsite Power, the equipment on this checklist shall be started by placing the NOfil1AL SHUTDOw'N SEQUENCER switches to the TEST position and holding them for 45 seconds (until the DBA sequencers timeout).

4.2 Verify minimum operating safety injection equipment using checksheet.

(Attachment 1) 4.3 Verify minimum operating safeguards equipment if Containment High Pressure Trip is activated. (Attachment 2) 4.4 When the containment high pressure signal has cleared, stop containment spray:

a. Reset the Containment High Pressure Isolation Signal (this will close the iodine removal valves "l;*kCV-0437A and ;b'*CV-0437B) .
  • . - * ~ J.
b. Turn off the Containment Spray Pumps ;'d*P-54A, °ld*P-54B and ;'d*P-54C.
c. Close the Containment Spray Header Valves ;'d*CV-3001 and ;b'*CV-3002.

4.5 Verify containment isolation. (Attachment 3) 4.6 Review diagnostic sheet (Attachment 4) to confirm accident diagnosis.

4.7 Attempt to establish and maintain hot and cold leg temperature and PCS pressure within the operating region of the 50°F subcooling saturation curve (Use EOP 1, Attachment 2 or the subcooling curve posted in the Control Room.)

NOTE: Use all available indications in determining 50°F subcooling, ie, use hot and cold leg temperatures, several incore thermocouples, and PCS pressure.

4.8 If 50°F subcooling cannot be maintained, assume that there have been voids formed within the PCS:

a. Substantial void formation would be indicated by one or more of the following:
1. Core outlet temperature readings higher than saturation conditions.
2. Increased core nT above full power (47°F).
3. Startup neutron detectors showing erratic indication.
4. Incore thermocouples showing erratic indication.

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PALISADES* NUCLEAR PLANT Proc No EOP 8. 1 EMERGENCY OPERATING PROCEDURE Revision 15 Page 4 of 8 TITLE: LOSS OF COOLANT ACCIDENT

  • b.

5.

6.

Th increasing or erratic.

T c

erratic.

If void formation exists, increase PCS pressure by ensuring:

1. All pressurizer heaters on.
2. Pressurizer Spray Valves closed C-:;-;',CV-1057 and ;'n'<CV-1059 ) .
3. Maximum charging and minimum letdown.
4. HPSI pumps running ;';;'<P-66A, ;b'*P-66B, and ;'d'P-66C.

NOTE: A reduction in the subcooled margin is preferable to violation of PCS boundary through excess pressure for existing temperature.

c. If 50°F subcooling is established but voids remain, vent the Reactor Vessel head in accordance with Step 4.0 (18) of ONP 21.

CAUTION There is a possibility of excessive radiation if a sample line is opened.

Extreme care and caution must be used.

4.9 Periodically notify the Chemistry Department to sample containment atmosphere for Hydrogen and Primary Coolant for assessment of fuel damage. Perform ONP 22 and ONP 11 as necessary.

4.10 30 MINUTES AFTER LOCA, STOP BORIC ACID INJECTION VIA THE CHARGING PUl1PS:

a. Turn selector switch for Charging Pumps **P-55B and **P-55C from auto to manual and turn HS for ;'d*P-55B and ;b'<P-55C to off.
b. Turn HS for Charging Pump **P-SSA to off.

NOTE: If there is a low level indicated in the pressurizer, it may be necessary to rack out breaker ;';;'*052-1205 for ;';;'*P-55A in order to stop ;'<;'*P-55A.

c. Turn HS for Boric Acid Pumps **P-56A and **P-56B to off.
d. Close Boric Acid Pump Feed Valve **M0-2140 and Gravity Feed Valves
';;'*M0-2169 and id*M0-2170.
e. Check closed VCT Outlet Valve **M0-2087 .
  • f.

g.

Open SIRW Outlet to Charging Pumps ;'n'*M0-2160.

Run each Charging Pump ;';;'*P-55A, ;';;'<P-55B and ;'d:p-55c for at least five (5) minutes to flush the concentrated boric acid through the lines. Turn Charging Pumps off or run as needed to control pressure.

pa0480-0015a-89-93

PALISADES NUCLEAR PLANT Proc No EOP 8.1 EMERGENCY OPERATING PROCEDUHE Revision 15 Page 5 of 8 TITLE: LOSS OF COOLANT ACCIDENT NOTE: If PCS pressure is g:t;"eater than 275 psig, LPSI pumps may be stopped.

Do not attempt to ope-rate LPSI valve "i'd*M0-3008 *when containment sump level is greater thari 85% indicated.

4.11 ONE HOUR AFTER LOCA, BEGIN PLANT COOLDOWN:

a. Open Steam Bypass to Condenser Valve "i'*kCV-0511.
b. Open Steam Dumps to Atmosphere, Valves *'*"i'*CV-0779, *'d.*CV-0780, "i'd*CV-0781, and "i'd*CV-0782 as necessary to establish and maintain plant cooldown at 75°F per .hour.

NOTE: Steam flow through two of the four Steam Dumps should be adequate to establish an initial cooldown rate of 75°F per hour.

4.12 IF THE RECIRCULATION ACTUATION SIGNAL rs RECEIVED:

CAUTION Prior to receipt of RAS, place handswitches for i**CV-3027 and ""'*CV-3056 (HS-3027A f""'*HS-3056A) to the closed position.~ .

a. Verify the following:
1. Low Pressure Safety Injection Pumps stop. (-,'d<P-67A and

.,...,.,P-67B)

2. Containment Sump Isolation Valves open. (-,',-,'<CV-3029 and

-,'d*CV-3030)

3. Safety Injection and Refueling Tank Isolation Valves close.

(**CV-3031 and **CV-3057)

4. Each running HPSI pump has a minimum flow of at least 30 gpm.
5. SI Pump Minimum Flow Stop Valves close permissive lights are lighted.
6. Component Cooling Heat Exchanger Service Water Outlet Valves transfer to alternate supply *'<*'*HIC-0881 and *'d*HIC-0882.

NOTE: If necessary, dispatch operator to adjust '"'"HIC-0881 and/or ""'<HIC-0882 to maintain less than or equal to 105°F outlet temperature on Component Cooling Heat Exchangers .

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PALISADES NUCLEAR PLANT Proc No EOP 8.1 EMERGENCY OPERATING PROCEDURE Revision 15 Page 6 of 8 TITLE: LOSS OF COOLANT ACCIDENT

  • b. Perform the following:
1. If each running HPSI pump is not maintaining at least 30 gpm flow, first trip the Charging Pumps one at a time and then the HPSI pumps one at a time until each running HPSI pump is maintaining at least 30 gpm flow or until only one HPSI pump is running.
2. Place the keys in SIRWT Recirculation Valve handswitches
    • HS-3027B and **HS-3056B and place in the closed position.
3. Monitor the radiation levels in the Auxiliary Building and the ESS sumps for signs of leakage from the SIS equipment.

CAUTION Do not perform Step 4 if contain-ment pressure exceeds 4 psig.

4. Align the safeguards sump discharge to the containment by closing ;';;';-l-'1V-DRW151 (sump discharge to DWD) and opening
b"CV-1103 and 'l'd>CV-1104 (Containment Sump Drain Valves).
5. If only one service water pump is running, start another service water pump. If only one service water pump can be operated, align the fire water system to the service water system by opening 'l'0 "t1V-FP130 and ;';-;';-f1V-FP131. This action is required to provide sufficient cooling water flow to the Engineered Safeguards Room coolers.

NOTE: If containment isolation signal is present, refer to Attachment 5.

c. If reactor pressure is less than 230 psia and the safety injection system is lined up for cold leg injection, perform the following:

CAUTION If only one Containment Spray Pump is running, do not open more than one.Containment Spray Valve Ci';"CV-3001 or ;'d>CV-3002) and one HPSI pump supply valve ('l'>;'*CV-3071 or ;'c;'*CV-3070) at the same time.

1. If CHP has been reset:

(a) Check closed **CV-3001 and **CV-3002 .

(b) Start **P-54A, **P-54B or **P-54C.

(c) Open **CV-3071 to supply cooled water from the Shutdown Cooling Heat Exchangers to the suction of ;'d*P-66A.

pa0480-0015a-89-93

PALISADES NUCLEAR PLANT Proc No EOP 8.1 EMERGENCY OPERATING PROCEDURE Revision 15 Page 7 of 8 TITLE: LOSS OF COOLANT ACCIDENT (d) Open ;'d*CV-3070 to supply cooled water from the Shutdown Cooling \Heat Exchangers to the suction of ;'d*P-66B and

-ld*P-66C:*

2. If the CHP signal is present:

(a) If two or more Containment Spray Pumps are running.

(b) Open ;';-;'*CV-3071 to supply cooled water from the Shutdown Cooling Heat Exchangers to the suction of **P-66A.

(c) Open **CV-3070 to supply cooled water from the Shutdown Cooling Heat Exchangers to the suction of -/d*P-66B and

h'*P-66C.

4.13 TWO HOURS AFTER LOCA, ISOLATE OR VENT SAFETY INJECTION TANKS:

NOTE: In the event of a large LOCA, the tanks will already be empty and this step will be unnecessary.

a. Isolate Safety Injection Tanks **T-82A, **T-82B, **T-82C and
',;'*T-82D.
  • . ._ - o,t j_
1. Unlock and close breakers **052-2229 (MCC-22), **052-2429 (MCC-24), -/;-;'*052-2129 (l'lCC-21), and -/;-;'*052-2329 (MCC-23).
2. Close ;'*-l*I-10-3041, ;'*-l*M0-3045, ;';;'*M0-3049 and ;'d*l'I0-3052.
b. If unable to isolate one or more Safety Injection Tanks, vent the unisolated SI Tanks as follows:
1. Open Vent Valve ;'d>CV-3067, ;'d*CV-3065, ;'d>CV-3063 or ;'r;'>CV-3051 on the tank to be vented **T-82A, **T-82B, **T-82C or **T-82D.
2. This will allow the nitrogen to flow into the Clean Waste Receiver Tanks **T-64A, **T-64B, **T-64C or **T-64D and blow at least one of their rupture discs and pass into the containment atmosphere.
3. Repeat Steps (1) and (2) for each unisolated tank until all are vented.

4 .. 14 SIX HOURS AFTER LOCA, PROCEED AS FOLLOWS:

a. With PCS pressure less than 160 psia, align HPSI for hot and cold leg injection for long term cooling: *
1. Close **M0-3080, then open **M0-3082 .
  • 2. Close ;'d>M0-3081, then open -,',;'*M0-3083.

pa0480-0015a-89-93

PALISADES NUCLEAR PLANT Proc No EDP 8.1 EMERGENCY OPERATING PROCEDURE Revision 15 Page 8 of 8 TITLE: LOSS OF COOLANT ACCIDENT NOTE: Verify flow to hot leg Nwnber 1 on ;'d*FI-0316A and/or ;'d*FI-0317A.

';;'*FI-0316A will indicate hot leg injection from HPSI Pwnp ;';;'*P-66A, and
'd*FI-0317A will indicate hot leg injection from HPSI Pump ;'d*P-66B or
';;'*P-66C. Verify flow to cold'legs on ;'d*FI-0308, ;'""FI-0310, ;';;'*FI-0312, and ;'d*FI-0313. Total flow to hot leg Number 1 should approximately equal total flow to cold legs.
3. Procedure ended.
b. With PCS pressure greater than or equal to 160 psia, place the Shutdown Cooling System in operation:
1. Verify at least 50°F subcooling will be maintained at entry pressure for Shutdown Cooling using loop cold leg temperatures and several incore thermocouples.
2. Enter shutdown cooling per SOP 3:

NOTE: When using SOP 3, ignore any reference to Primary Coolant Pumps; any reference to pressurizer spray is to be considered as auxiliary spray.

(a) If necessary, throttle or secure HPSI and/or charging pump flow to maintain pressurizer level.

(b) If voiding is apparent during depressurization (ie, pressurizer level is erratic), stop auxiliary spray to the pressurizer and vent noncondensibles from the reactor vessel head and/or the pressurizer in accordance with Step 4.0 (18) and (19) of ONP 21.

(c) If the **PS-0104 interlock prevents the opening of either

'd*M0-3015 or ;';;'*~10-3016, *refer to Attachment 7.

NOTE: If there is a high radioactivity level in the Primary Coolant System, circulation of this fluid in the Shutdown Cooling System may result in high area radioactivity readings in the Auxiliary Building. The activity level of the PCS should be determined prior to initiating Shutdown Cooling System flow.

3. If shutdown cooling cannot be established:

(a) Maintain Steam Generator heat removal, using the Steam Bypass to Condenser or the Steam Dumps to Atmosphere, while attempting to establish shutdown cooling.

(b) If heat removal by Steam Generators can no longer be maintained, open PORVs and block valves **M0-1042A,

    • M0-1043A, **PRV~l042B and **PRV-1043B. Continue cold leg injection with at least one HPSI pump. Once Shutdown Cooling entry conditions are met, close the PORVs and their block valves ;';;"M0-1042A, ;';;';MV-1043A, ;';;"PRV-1042B and **PRV-1043B and establish shutdown cooling as described in Step 4.14.b.

pa0480-0015a-89-93

Proc No EOP 8.1 Attachment 1 Revision 15 CHECKSHEET FOR MINIMUM SAFEGUARDS Page 1 of 1 Equipment fed from bus C and/or D/G 1-1 (**K-6AG) 2400V

1. 1 HP Safety Injection Pump running **P-66B

.2. 1 LP Safety Injection Pump running **P-67B - - - - -

3. 1 Component Cooling Water Pump running **P-52A - - - - - or **P-52C - - - - -
4. 1 Service Water Pump running **P-7B
5. 1 Auxiliary Feedwater Pump running **P-8A - - - - -

.. 480V

6. 1 Charging ~ **P-SSC - - - - -
7. 4 HP Safety Injection Valves open
    • M0-3007'

**M0-3009 ----- **M0-3011 ----- **M0-3013 -----

8. 2 LP Safety Injection Valves open **M0-3008 - - - - - **M0-3010 -----)m
9. 2 Boric Acid gravity feed stops open **M0-2169 * - - - - - **H0-2170 _ _ _.....;fA.=.
10. 1 Containment Air Cooler recirculation fan **V-4A 0 11.

Volume Control Tank Outlet Isolation Valve closed **M0-2087 u

OR Equipment fed from bus D and/or D/G 1-2 (**K-6BG) z 2400V 0

12. 1 HP Safety Injection Pump running **P-66A

or **P-66C -----1~-

13. 1 LP Safety Injection Pump running **P-67A

<(

14.

15.

1 Component Cooling Water Pump running 1 Service Water Pump running **P-7A

    • P-52B or **P-7C  !
  • ~

480V ----

16. 2 Charging Pumps **P-SSA and **P-SSB
17. 4 Redundant HP Safety Injection Valves open z ll'.il:3
    • M0-3062

**M0-3064 ----- **M0-3066 ----- **M0-3068

18. 2 LP Safety Injection Valves open **M0-3012

**M0-3014 -----

19. 1 Boric Acid Pumped Feed Stop Valve open **M0-2140
20. 1 Boric Acid Pump running **P-56A
21. 3 Containment Air Cooler Recirculation fans running

'f..-kV-lA **V-3A

'f..~V-2A - - - - - -----

Completed By: I Signature Date Reviewed By: I pa0480-0015b-89-93 Shift Supervisor Date

Proc No EOP 8.1 Attachment 2 Revision 15 Page 1 of 1 I 1.

CHECK SHEET FOR MINIMUM SAFEGUARDS Complete Attachment 1.

WITH CONTAINMENT HIGH PRESSURE

2. 2 Containment Spray Valves open **CV-3001 and **CV-3002
3. 4 Containment Air Cooler High Capacity Service Water Valves open
    • CV-0861 **CV-0864 **CV~0867
4. 2 Iodine Removal Valves (open after 1 minute time delay)
    • CV-0437A -

**CV-0437B

~

and From 2400 V bus lC and/or Diesel Generator 1-1

5. 2 Containment Spray Pumps **P-54B **P-54C

----~

or From 2400 V bus ID and/or Diesel Generator 1-2

6. 1 Containment Spray Pump ~""*P-54A Completed By: I Signature Date Reviewed By: I Shift Supervisor Date pa0480-0015c-89-93
  • Proc No EOP 8.1 Attachment 3 Revision 15 Page 1 of 2 CONTAINMENT ISOLATION CHECKLIST All containment isolation CV's have latching circuits, the handswitches have to be placed to closed position prior to open position.

VALVE NO. DESCRIPTION CLOSED

    • CV-1808 Containment Purge Exhaust Isolation Valve
    • CV-1814 Air Room Supply
    • CV-1806 Containment Purg_e Exhaust Isolation Valve
    • CV-1501 - Containment Htg Steam Return "1..-kCV-1101 Containment Vent Hdr
    • CV-1807 Containment Purge Exhaust Isolation Valve
    • CV-1813 Air Room Supply

-1.-kCV-1805 Containm~nt Purge Exhaust Isolation Valve

    • CV-1502 Conta1nment Htg. Steam Return "1.."*CV-1102 Containment Vent Hdr

'fr:.cv-1064 Clean Waste Receiver Tanks Vent

    • CV-1103 Containment Sump Drain (SIS or CHR)
  • ":.cv-0911 Component Cooling water Return
    • CV-1002 Primary System Drain Tank Outlet
    • CV-1036 Clean Waste Receiver Tanks Recirc Outlet
    • CV-1044 Clean Waste Receiver Tanks Outlet
    • CV-1104 Containment Sump Drain (SIS or CHR)
    • CV-0940 Component Cooling Water Return
    • CV-1007 Primary Syst~m Drain Tank Outlet
    • CV-1038 Clean Waste Receiver Tanks Recirc Outlet
    • CV-1045 Clean Waste Receiver Tanks Outlet
  • ":*cV-1065 Clean Waste Receiver Tanks Vent Steam Generator -1..~*E-SOB Bottom Blowdown Completed By: I I Signature Time Date pa0480-0015d-89-93

Proc No EOP 8.1 Attachment 3 Revision 15 Page 2 of 2 CONTAINMENT ISOLATION CHECKLIST

  • VALVE NO
    • CV-1503 Containment Htg Steam Inlet
    • CV-0738 - Steam Genterator **E-50B Top Blowdown
    • CV-0910 Component Cooling Water Inlet (SIS)

-!.-kCV-0939 Shield Cooling Surge Tank Fill

    • CV-1004 Clean Waste Receiver Tanks Inlet

-.!.-kCV-1037 Clean Waste Receiver Tanks Recirculation Inlet

"!.'"*CV-1358

-:.-::cv-1001

    • CV-1910 Nitrogen Supply Primary System Drain Tank Recirculation Inlet Primary System Sampling

'l."*CV-1911 Primary System Sampling

-k-kCV-2009 Letdown Stop

'1.-A-CV-2083 Controlled Bleedof f

-k-.':CV-0155 Demineralized Water Supply

-l:-kCV-0501 Main Steam Isolation Valve (on CHP)

  • Completed By:

Pages 1 and 2 Reviewed By:

Signature Shift Supervisor I

I Date Date I

I Ti.

Time pa0480-0015d-89-93

Proc No EOP 8.1 Attachment 4 Revision 15 Page 1 of 1 ACCIDENT IDENTIFICATJON LARGE BREAKS PRESSURIZER -PRESSURE DECR~ASING*RAPIDLY I '---

I I

I OBSERVE STEAM GENERATOR PRESSURES__.

ABNORMALLY LOW IN ONE

' STEAM GENERATOR PRESSURES OR BOTH STEAM GENERATORS - ">C:

. i\~*

I INITIALLY NORMAL OR RISING i

STEAM LINE LOCA OR RUPTURE S.G. TUBE RUPTURE 1

J OBSERVE OBSERVE CONTAINMENT PRESSURE CONTAINMENT PRESSURE RADIATION AND SUMP LEVEL I INCREASING I I

NORMAL - -;:--*-I INCREASING i

I- NORMAL I

J VERIFY HIGH  !

1 RADIATION AIR EJECTOR DISCHARGE

\

STEAM BREAK 'I STEAM BREAK OUTSIDE I

~

INSIDE LOCA CONTAINMENT CONTAINMENT ...II,

  • ..L

~. ~

J, ,;,

' lEOP I SEE EOP 7 i p I SEE EOP 8.1 I I SEE 8 *2 I pa0480-0015e-89-93

iJlraE .ll. 1 MIN...

l. © C.B. BI PBESS n CD r------- *11111;-Dl"~;t-?~

CLEAmll?

llE&CTDR TR IPPEDT I .,

(lTTlCH. I) , - - - COJ:DillMEllT ISOL.

' S. I TES I ID YES I ID IES (AftACB. 3) (j') I PCS 50- s-cl -

I

  • s. l l I IES IO I 0.

.I TRIP RElCTDI i

I 1

MlMUlLLY STlRT I

RlllET C.B.

ISOLA.TIOll IES 10 l I 1

  • al) RAISE Pm H1ESS m

F

@1 I

IDDS INSERTED?

YES I ID EQUIP.

l SIGNAL l

(5) MAllllALLY ISOU.TE IIF PCS <1250 PSIA PZH B'l'llS PZH SPRAY MAX CBC.

~ . f

'l'llRll OFF

!TRIP CLUTCH p/SJ I C.B. HI PRESS7 I OH C.P.>5PSIG llillu:mJllS c J I YES l llD I CORTAIRMESr 3 BPSI Pp cm.

0 CD I SAFETY I IJECTI OM I SDLlTE llREU .,

.------i_I( CAUSE CORRECTED)! I ' SPRAY POIPS 1 .1

0. I lCTUlTEDT YES I ID I

!REACTOR SHUTDDllRtl NIM.OP ES.T ATT.lCH. 2 .

CLOSE vom PORIWl'IOI co~ EXISTS!

-L I I 1-

' YES MO TES I 110 SPRAY llEAllER IES 110 I

IM&MUlLLY IM ITllTEI I

- I VALVE; A PZR .. 20~ ' l N

CD I TRIP &LL PCP ' I I

YES I MO 1-- MANUALLY START I © EXITTO T. CD I '

CDllTllMMEllT lna .. 1100 rsnl EQUIP.

I APPLIC.

PROC.

A ISDUTIDM *SIGMlLT I YES I MD l

I YES I MD 1-I *nv c sqs 0 t l I EXIT THIS i-..--..i PROCEDURE

., GD TD ONP-21 I

I YES I MO r-

... C I

MUUlLLY .

llllTIUE 1:

  • c BEAD 1250 PSI !

' J f PCS ... so 0 sua- I INFORMATION COPY 1 I CY I BREU ISDUBLE?

COOLED?

.G SAMPLE PCS

  • I ID I YES I no 1--

D I YES C.B. AIR

'~-------""RESET l

E ACTIVATE : s I TE EMERGENCY PLU I RESTART I N I I SIS PCP'S

  • T EDP_ I 8.1 ©,@,f;!C.*_SUISEQUENl ACTIOI .

. .. PROCEDURE .STEP. .MUMBERS.

30. 6!!_ Pree 110 EDP 8.1.

r.mt. rnm_ 2 HOURS 6 llOURS Attachment 6 ReTis1011 15 Page lot l

'"p-z""1:-:P-::R-::E-=s-=s-

..-::2-::1-::i5 COMM EH CE

(!) PCS 50* S-C PCS COOLING e 0 ISOLATE OR VDiT 1--------.:!;@~l~PZ:.:::R_:PRESS..::::;::...:<::1::6:.o.rr---i-:S~D===CL:"G'-10'-PE:.:R';A~B..::L.=..iE YES NO SI TANKS n:s no . YES HO 15°F/HR n:s llO SECURE SECURE ESTABLISH

  • (!!)RAISE PZR ~* BORIC ACID EST. SD BORIC ACID HOT A!ID COLD r.m' CHARGING CLG. PER PZR BTllS 011 CHARGING IIIJECl"IOll SOP 3. THIS HO P'LR SPRAY OTr ' LPSI PROCEDURE MAX CHG. COMPLETE VERIFJ' l"LOll TO Miii :t.mXlllll .

HOT AlllJ COLD LECS OPEN 3 BPSI Pp Oii. RAS? BOTH PZR THIS PROCEDU!ll!:

PORV 1 S no no COMPLETI!: RUN ~ I vom rcRMA1'IO! HPS I Pp EXISTS?

VERIFY:

LPSl-Pps TRIP C.8. SUMP VLVS OPEN; SIRWT VLYS I CLOSE; .

JIOTE:-RAS. CAN. OCCUR AT 30 GPM FLOW ALMOST ANYTIME /HPSI Pp; DEPEHDIHG OH THE MINIFLOW CY'S BREAK SIZE AHO THE. CLOSE; HUMBER OF PUMPS CC HX OUT RUHHIHG  :::.1os 0 H5 30278 '

HS 3056B TO CLOSE; ROUTE ESS ROOM SUMPS Q SAMPLE PCS

  • T.C.B
  • C.B. AIR . (ATTACH 5)

INFORMATION COPY

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