ML20080A662
| ML20080A662 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 06/10/1983 |
| From: | Schuyler J Public Service Enterprise Group |
| To: | |
| Shared Package | |
| ML16340D619 | List: |
| References | |
| EP-OP-11, NUDOCS 8307270201 | |
| Download: ML20080A662 (26) | |
Text
..
ATIn0NENI 1 Updates Tncl' M In
'Ihis Submittal Volune 3A Table of Contents EP T-ll, Revision 3 EP T-38, Revision 4
+
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l 8307270201 830719 PDR ADOCK 05000275 F
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(URPINT my pg IMPLDENTING PROCEIERES TABLE OF CIIITEurS Volume 3A TITLE REV (P-O Reactor Trip With Safety Injectica 3
OP-1 Ioss of Coolant Accident 5
OF2 loss of Secondary Coolant 2
OP-3A Steam Gen Tube Failure 4
OP-3B Minor Steam Gen Tube Failure 1
OP-4A Ioss of Electrical Power O
OP-5 Reactor Trip Without Safety Injectica 5
OP-6 Et:ergency Boration 5
OP-7 Ioss of Condenser Vacuum 2
OP-8 Control Roan Inaccessibility 5
OP-9 Ioss of Reactor Coolant Pucp 3
OP-10 Ioss of Auxiliary Salt Water 2
,OP-11 Loss of Ccrponent Cooling Water 3~
OP12 Malfuncticm of Auto Reactor Control 1
Syste CN12A Failure of a Control Bk to 2
Move in Auto Cl-12B Cont Withdrawal of a Control Rod Bank 3
OP-12C Cont Insertion of a Control Rod Bank 2
OP-12D Control Rod Pos Indication Sys Halfune 3
OP-12E Control Rod Misalignment 2
OP-12F Dropped Control Rod 2
OP-13 Malfunction of Reactor Pres Control Systen 2
OP-14 High Activity in Reactor Coolant 2
OP-16 Nuclear Instrumentation Malfuncticus 3
OP-17 Malfunction of RHR Systen 2
OP-18A Ioss of Charging 0
OP-18B Ioss of Nomal Letdown 0
OP-19 Malfunction of Reactor Makeup Control 2
OP-20 Excessive Reactor Coolant Systen 2
leakage m
y em--
- n. - --- -
.7-.
u TITLE
,l Q
REV (P-21 Imos of A Coolant Loop RTD 2
GH22 Bnergency Shutdown 1
CP-23 Natural Circulatim of Reactor Coolant 2
CP-24 Imes of Contab==nt Integrity 1
GH25 Tank Ruptures 1
(P-26 Excessive Feeduater Flor 1
(P-27 Irradiated Fuel Damage 1
(P-28 Startup of an Inactive Reactor Coolant Loop 1
GK29 Excessive Imad Increase.
1 (P-30 Inadvertent Load Fuel Assly Improper Pos 1
Gb31 Systen Under Frequency 1
@-32 Rod Ejection 1
OP-33 Ioss of Instrument Air 1
CP-34 Generator Trip - Full Iced Rejectice 1
OP-35 Ioss of Vital or Non-Vital Instr AC Sys 1
OP-37 Loss of Protectim System Channel 1
.OP-38 Anticipated, Transient Without Trip (AITT) 4 OP-39 BCP Locked Rotor Accident 1
OP-40 Accidental Depmssurization of MS Systera 1
OP-41 Hydrogen " Explosion" Inside Containment 1
OP-44 Gaseous Voids in the RCS 2
R-1 Per Injury (Rad Related) And/Or Overexp 9
R-2 Re1 of Airborne Radioactive Materials 3
R-3 Rel of Rcdioactive Liquids 3
R-4 High External Radiation 3
R-5 Radioactive Liquid Spill 3
{
R-6 Radiological Fire 5
R-7 Trunapnrtation Accidents M-1 Enployee Injury (Nooradiological) _ -
2 9
M-2 Nonenployee Injury or Illness (Third Party) 8 M-3 Chlorine Release 5
M-4 Earthquake 6
M-5 Tsunami Warning 5
M-6 Nonradiological Fire 7
M-7 Oil Spill ISO and Clean Up Procedure 4
M-8 Contal:rnent Emergency Personnel Hatch 0
G-1 Emergency Classification and Emergency Plan 3
Activation G-2 Establishment of the On-Site Emergency 3
Organization l
G-3 Notification of Off-Site Organizatim s 2
G-4 Personnel Accountability and Assenbly 2
G-5 Evamatie of Nonessential Site Personnel 0
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FGWE Pacific Gas and Electric Company REVISION 3 DATE 6/21/82 DEPARTMENT OF NUCLEAR PLANT OPERApS g
4 g
1 AND 2 PAGE 1 OF 20
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O!ABLO CANYON PCMER PLANT UNIT NO(S)
EMERGENCY OPERATING PROCEDURE IMPO:iTANT m. LOSS OF COMPONENT COOLING WATER TO SAFETY Y-N APPROVED:
DATE rLAna mMuy SCOPE This procedure outlines the steps to be taken following component cooling water system leakage or loss of cooling to various vital components. Prompt corrective action is vital to prevent complete deterioration of the system. The primary action is to isolate the defective component or 5,ection and tenninate the leakage.
Section A Loss of a CCW Pump - pg.1-B CCW Inleakage - pg. 3 C
CCW Outleakage - pg. 5 0
Loss of CCW flow to the Letdown Heat Exchanger -
p9 7 E
Loss of CCW flow to the Reactor Coolant Pumps -
pg. 9 8
F Loss of CCW flow to the Seal Water Heat
\\
Exchanger - pg. 11 Appendix A Clearing a Component Cooling Water Header Due To Header Failure - pg. 13 Appendix Z Notification Instructions - pg. 20 This procedure and changes thereto require PSRC review.
A.
LOSS OF A COMP 0NENT COOLING WATER PUMP SYMPTOMS 1.
Auto start of STBY CCW pump 2.
Possible Annunciator Alarms a.
CCW Pumps (PK01-09) 1)
CCW Pp Auto Start 2)
CCW Pps P rip DC0067 IV
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Muust EP OP-11 DIA8LO CANYON POWER PLANT UNIT NCMS) 1 AND 2 DATE 6/21/82 TITLE:
LOSS OF COMPONENT COOLING WATER 1
b.
CCW VITAL HDR A/B (PK01-06) 1)
CCW Hdr Flo Lo 2)
CCW Hdr Press to c.
CCW Hdr-C Flo Lo l
AUTOMATIC ACTIONS i
1.
Automatic start of STBY pump on low pressure in CCW headers A or B.
j OBJECTIVES 1.
Restore nonnal operation of CCW system.
ACTIONS /EXPECTtD RESPONSE RESPONSE NOT CBTAINED IM9EDIATE ACTIONS 1.
Verify STBY CCW Pump AUTO START 1.
Manual start STBY CCW Pump SUBSEQUENT ACTIONS l
1.
If only one CCW pump can be 1.
Reduce system heat loads (as started, verify CCW heat detennined by the Shift exchanger outlet temperature is Foreman) to maintain CCW 1ess than 95'F.
system temperatures less than 95*F.
2.
If M CCW pumps can be started.
-a.
Trip the reactor.
b.
Trip the reactor coolant pumps.
c.
GO TO~EP OP-5 Reactor Trip
-with no Safety Injection.
O DC0067 2IV y
1 T_PGstE Pacific Gat, and Electric Company NUMBER EP OP-38 REVISION 4 DEPARTMENT OF NUCLEAR PLANT OPERATIONS DATE 6/7/83 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 PAGE 1 OF 3 EMERGENCY PROCEDURE TITLE: ANTICIPATED TRANSIENT WITHOUT TRIP (ATWT)
APPROVED:
PLANT MANAGER ()
DATE SCOPE This procedure describes the steps to be taken in the event of an ATWT. An ATWT is a failure of the reactor protection system to trip the rods when a reactor trip setpoint has been exceeded. This procedure is "Important to Safety" and changes or revisions shall be approved by the PSRC.
SYMPTOMS 1.
Reactor Trip setpoint exceeded without a reactor trip.
2.
Possible REACTOR PROTECTION SIGNAL Annunciator (PK 04-11 or PK 04-12) without a REACTOR TRIP ACTUATED Annunciator (PK 04-14) 3.
DRPI indicates failure of rods to insert.
NIS does not show a rapidly decreasing neutron count level.
ACTION / EXPECTED PESPONSE RESRASE NOT OBTAINED l
IttEDIATE ACTIONS 1.
Manually Trip the Reactor.
1.
IF NOT, GO TO Step 2.
If tne Reactor Trips GO TO EP OP-5.
2.
Manually Trip the Turbine 2.
Trip it locally at the turbine pedestal.
v3.
De-energize the M-G Sets by 3.
IF rods DO NOT insert, Opening Breakers for 130 and 13E.
a.
Manually SI b.
Insert Rods c.
Locally open the Reactor Trip Breakers i
(
(
d.
NuuoER EP OP-38 DIA84.0 CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 4 DATE 6/7/83 PAGE 2 OF 3
}~
TITLE:
ANTICIPATED TRANSIENT WITfl00T TRIP (ATWT)
ACTION /EXPEutu RESPONSE RESPONSE NOT OBTAIED SLESEC1]ENT ACTIONS i
1.
Locally 0)en the Reactor 1.
Open Both MG Set Motor and/or Trip Brea cers.
Generator Breakers.
2.
Verify Feedwater isolation 2.
Manually isolate main at I,yg < 554*F.
feedwater at T,yg < 554"F.
3.
Check AFW Status AFWpumpsrunbing a.
Manually start AFW pumps.
a.
b.
AFW Flow indicated or b.
Manually control AFW l
S/G NR Levels at 33%
LCV's.
l-l 4.
When the Reactor Trip Breakers and/or Both MG Set Breakers are 0)en, Re-energize 13) and 13E.
5.
GO TO EP OP-5, Subsequent Steo No. 1.
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DC0214 2IV
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DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 DATE 6/7/83 PAGE 3 OF 3
('
TITLE:
ANTICIPATED TRANSIENT WITHOUT TRIP (ATWT)
APPENDIX Z EMERGENCY PROCEDURE NOTIFICATION INSTRUCTIONS When this emergency procedure has been activated and upon direction from the Shift Foreman proceed as follows:
1.
Designate this event an Alert. Notify plant staff and response organizations required for tnis classification by Emergency Procedure G-2 " Establishment of On-Site Organization" and Emergency Procedure G-3 " Notification of Off-Site Organization" in accordance with Emergency Procedure G-1 " Accident Classification and Emergency Plan Activation."
2.
Designate this eYent a Site Area Emergency if safety injection was initiated before rods were inserted into the core but no core damage is evident (no abnormal increase in RCS coolant activity and no abnorral increase in gross failed fuel indication).
Notify plant staff and response organizations required by EP G-2 and EP G-3 in accordance with EP G-1.
3.
Designate this event a Genera
- Emergency if one of the following conditions exist:
a.
Core damage is evident by:
1)
Reactor coolant activity greater than 300 pCi/cc -
equivalent I-131, cg-2)
Radiation levels indicate greater than 100% gap release l
(Refer to Appendix H of EP OP-1)'.'
l b.
Complete loss of a safe shutdown system simultaneous with rods not inserted in the core.
c.
Loss of CVCS capability to increase boric acid concentration in the RCS simultaneous with rods not inserted into the Core.
Notify plant staff and response organizations required by-EP 34and EP G-3 in accordance with EP G-1.
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DC0214 3IV
4 P OP-11 CIABLO CANYON POWER M. ANT UNIT NO(5) 1 AND 2 DATE 6/21/82
~l PAGE 3 OF 20 h
m LE:
LOS5 0F COMPONENT COOLING WATER B.
COMPONENT COOLING WATER SYSTEM INLEAKAGE SYMPTOMS 1.
Surge tank level indicators reading high 2.
Possible Annunciator Alarms a.
CCW SURGE TANK (PK01-07)
- 1) CCW Surge TK Lvl Hi b.
RCP (PK 05-01, 02, 03; 04)
- 1) RCP Lower Brg Temp Hi
- 2) RCP No. 1 Seal Outlet Temp Hi d.
HIGH RADIATION (PK 11-21)
- 1) Process Monitor Hi-Rad (RE-17A&B)
AUTOMATIC-ACTIONS l
1.
Surge tank vent closes on high radiation level.
2.
Reactor' coolant pump thermal barrier return line isolation valve (FCV-357) closes on high flow.
OBJECTIVES 1.
Prevent loss of primary water inventory into component cooling water system.
I 2.
Isolate component cooling water system to prevent radiation releases.
3.
Prevent damage to reactor coolant pumps.
ACTIONS / EXPECTED RESPONSE RESPWSENOTOBNINED IMMEDIATE ACTIONS 1.
Verify CCW inleakage l
DC0067 31V 1
OLASLO CANYON POWER M. ANT UNIT NO(S) 1 AND 2 DATE 6/21/82 PAGE 4 OF 20 m
Tm.E:
LOSS OF COMPONENT COOLING WATER M
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ACTIONS /O(PECTE RESb RESPmSE E WTAINED.
IM4EDIATE ACTIONS CONTINUED a.
Process monitor 17A&B reads one decade or more greater than monitor set point.
b.
Possible increase in CCW Surge Tank level.
2.
Verify Surge Tank isolation 2.
CLOSE RCV-16 MANUALLY (VB-1).
valve RCV-16 closed if Hi Rad condition is verified.
3.
If RCP thermal barrier return 3.
If proper RCP Seal Injection Tine isolates check adequate flows and Radial Bearing seal injection flow and normal temperatures cannot be Radial Bearing temperatures.
maintained consnence a reactor shutdown a.
If Hi Radial BeaH ng Alam temperature reached THEN
- 1) Trip the Reactor
- 2) Trip the RCPs
- 3) GO TO EP OP-5, Reactor Trip with no Safety Injection.
Establish R' P seal cooling with CAUTION, in order to prevent CA(JTIm:
C potential introduction of steam into.the CCW system and themal shock to the RCP (Max rate of bearing coo down is l'F/ min).
SUBSEQUENT ACTIONS
~
l 1.
Request a sample of the CCW system from the Chemical and Radiation Protection Department.
l d
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EP OP-11 D.lABLO CANYON POWER PUNT UNrf NO(S) '
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DATE 6/21/82 m
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LOSS OF COMPONENT COOLING WATER SUBSEQUENT ACTIONS CONTINUED
, 2.
Investigate to determine and isolate the source of leakage. Possible Sources:
a.
Letdown Hx b.
Th'ermal Barrier Hx c.
Excess Letdown Hx d.
RHR Hx e.
Surge TK m/u valve failure (LCV-69 t 11/or LCV-70) f.
NSSS Samyly Coolers 9
GFPD Sample Ccbler 3.
Notify the Chemical and Radiation Frotection
_ Department prior to reopening-RCV-16.
C.
COMPONENT COOLING WATER OUTLEAKAGE SYMPTOMS' 1.
CCW Surge Tank level indication decreasing
(
2.
Possible Annunciator Alarms a.
CCW VITAL HOR A/B (PK01-06) l
- 1) CCW Hdr Press Lo i
1 b.
CCW SURGE TANK (PK01-07)
- 1) CCW Surge Tk Lvl Lo
- 2) CCW Surge TK Make-up Viv open AUTOMATIC ACTIONS 1.
Automatic start of standby pump on low pressure in headers A or B.
2.
Surge tank makeup valves (LCV-69 and/or 70) open.
DC0067 SIV L
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DIABLO CANYON POWER PLANT UNIT NO(S) 3 E S 6/21/82 DATE 0
20
)
PAGE OF LOSS OF COMPONENT COOLING WATER Tm l
OBJECTIVES 1..
Restore nonnal operation of component cooling water system.
2.' Prevent damage to vital equipment.
L ACTIONS /EXPEuts RESPONSE RESPONSE NOT OBTAINED IMMEDIATE ACTION 1.
Verify Surge Tank Makeup 1.
OPEN CCW-62 and CCW-65 as valves, LCV-69 and/or LCV-70 necessary.
OPEN.
2.
Verify STBY CCW pump' AUTO 2.
Manually START the STBY CCW STARTED on Loss CCW Hdr pump if necessary.
Pressure (Setpoint 46 psig Hdr A, 45 psig Hdr B).
3.
If Lined up to CCW System START 3.
Line up & START Makeup Water Makeup Water Transfer Pump.
Transfer Pump to the CCW System.
SUBSEQUENT ACTION 1.
Verify makeup by observing 1.
If there is NO Surge Tank increasing CCW Surge Tank level level indication on LI-139 on LI-139 and LI-140.
and LI-140.
a.
TRIP -the Reactor b.
TRIP the RCPs l
c.
TRIP the CCW pumps d.
GO TO EP OP-5 Reactor Trip with no Safety Injection.
2.
If the CCW pumps begi,n to cavitate (pump amps erratic),
TRIP the CCW pumps.
". TRIP'the Reactor.
a b.
TRIP the RCPs.
c.
GO TO EP OP-5, Reactor Trip with no Safety Injection.
DC0067 61V
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~U OLABLO CANYON POWER PLANT UNIT NO(S) '
1'AND 2 R
DATE 6/21/82
']
PAGE 7 OF 20 V
TITLE:
LOSS OF COMPONENT COOLING WATER ACTIONS / EXPECTED ESPONSE RESPONSE NOT OBTAINED SUBSEQUENT ACTION CONTINUED 3.
Detennine the Source of the l
Outleakage and isolate. Refer to Appendix 1 of this procedure if a CCW header must be isolated due to a gross leak that is otherwise unsolable.
4.
If previously shutdown, restart the CCW pumps as sgon as conditions pennit.
5.
Shutdown the turbine building sump pumps as necessary.
6.
Refer to Emergency Procedure R-5 to combat any uncontrolled CCW coolant leakage.
7.
Notify the Chem & Rad Protection Department for assistance.
D.
LOSS OF CCW FLOW TO THE LETDOWN HEAT EXCHANGER SYMPTOMS 1.
Letdown temperature indicator reads higher than normal.
2.
Possible Annunciator Alarms a.
LETDOWN PRESS /FLO TEMP (PK04-21)
- 1) Letdn Hx Outlet Temp Hi
- 2) Letdn Outlet Temp Hi Divert DC0067 7IV
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DUW.O CANYON POWER M. ANT UNIT NO(S) 1 AND 2
{
6/21/82 DATE PAGE 8 OF EO q
i mu:
LOSS OF COMPONENT COOLING WATER I
AUTOMATIC ACTIONS 1.
The letifown divert valve (TCV-149) bypass the letdown flow around the demineralizers to the volume control tank.
j OBJECTIVES 1.
To Isolate Letdown path to Letdown Hx if CCW cannot'be restored.
2.
Maintain letdown and charcing.via alternate path until cooling is restored to letdown heat exchanger.
ACTIONS / EXPECTED RESPONSE RESPONSE NOT OBTAINED IMEDIATE ACTION 1.
Verify proper operation of TCV-130 1.
Adjust TCV-130 manually to (CCW return from LTDN HX).
establish adequate CCW flow.
SUBSEQUENT ACTION 1.
IF CCW f.ow to LTDN HX CANNOT be H stored THEN:
a.
Isolate LTDN - CLOSE CVCS 8149 A, B, and C.
b.
Take manual control of charging flow.
NOTE: Perform steps 1), 2), and 3) SIMULTANEOUSLY.
- 1) Reduce charging flow rate.
L
- 2) CLOSE HCV-142.
I
- 3) Maintain 32 gpm Seal Water injection to the RCPs (8 gpm per pump).
c.
CLOSE CVCS 8107 and 8108.
d.
Establish excess LETDN to the VCT.
DC0067 81V g
DIABL.O CANYON POWER PLANT UNff NO(S) 1 AND 2-EP OP-11
~
9 ATE 6/21/82 i
O PAGE 9 OF 20 D
LOSS OF COMPONENT COOLING WATER TITLE:
~
SUBSEQUENT ACTION CONTINUED 2.
If the reciprocating charging pump is the pump in service, place its controller back in AUTO.
E.
LOSS OF CCW FLOW TO REACTOR COOLING PUMPS SYMPTOMS 1.
Thermal barrier and lube oil cooler cooling water return high temperature indication.
2.
Possible Annunciator Alams a.
b.
RCP No.
(PK05-01,02,03,04)
- 1) RCP Temp P250
- 2) RCP Lower Brg Temp Hi i
AUTOMATIC ACTIONS 1.
None OBJECTIVES 1.
Prevent damage to reactor coolant pumps.
ACTIONS / EXPECTED RESPONSE RESPONSE NOT OBTAINED IM IDIATE ACTIONS 1.
If CCW is lost to the lube oil coolers of ONE RCP.
a.
Rapidly reduce power to 20%
a.
If RCP Hi Brg temperature THEN TRIP the RCP alams sound:
- 1) TRIP the RCP j.
DC0067 9IV l
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DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 NWSER EP OP-11 REVlWON 3 i
DATE 6/21/82 PAGE IQw 20 TITLE.
LOSS OF COMPONENT COOLING WATER ACTIONS / EXPECTED RESPONSE
~
RESPONSE NOT @TAIED IMEDIATE ACTIONS
- 2) If the Reactor Trips ll GO TO EP-0P-5 Reactor l
Trip with no Safety l'
Injection.
b.
Take Manual control of affected loop S/G level, if necessary to stablize loop transient.
c.
Refer to Technical Specification for limitations on power operation with an idle loop.
l 2.
If CCW is lost to MORE THAN ONE I
RCP:
- a. TRIP the Reactor.
- b. TRIP the affected RCPs.
- c. GO TO EP OP-5, Reactor Trip with no Safety Injection.
SUBSEQUENT ACTIONS 1.
If component cooling to the pump lube oil coolers is lost, leave the l
pump shutdown until cooling has been restored.
2.
If cooling is lost to the thermal barrier:
a.
Check seal injection flow
- a. Go to Section B, normal.
IM EDIATE ACTIONS, step 3 (RESPONSENOTOBTAINED) b.
Check radial bearing b.
Go to Section B, temperature normal.
IM EDIATE ACTIONS, step 3 (RESPONSE NOT OBTAINED) c.
Continue to run the pump (s) but increase sucueillance.
I DC0067 10!V l
l DIASLO CANYON POWER PLANT UNIT NO(S) 1 MD 2 NMR bN 6/21/82 DATE
(}
PAGE lb 20 V
LOSS OF' COMPONENT COOLING WATER rirts.
3.
If gross leakage from header C is suspected, go to Section C of this procedure.
F.
LOSS OF CCW FLOW TO THE SEAL WATER HEAT EXCHANGER SYMPTOMS 1.
Slight increase in Seal Injection temperature.
AUTOMATIC ACTIONS 1.
None OBJECTIVES 1.
Restore normal Seal Water Heat Exchanger outlet temperature.
ACTIONS / EXPECTED RESPONSE ~
ESPONSE NOT OBTAINED IMMEDIATE ACTIONS g
1.
None Required 3UBSEQUENT ACTIONS 1.
Continue to operate. Reactor 1.
If RCP radial bearing temperature Coolant Pump temperatures will or No. 1 Seal Leakoff temoerature increase but not enough to damage exceeds the normal operating band equipment.
limits (alar n 170*F and 160*F respective W. Consider the following action:
a.
Take manual control of TCV-130 & increase CCW flow to reduce VCT temperature.
b.
If excess LTDN is in service:
- 1) Divert excess LTDN to the RCDT.
- 2) Verify AUTO makeup to the VCT.
- 3) Makeup manually if necessary.
i DC0067 11IV l
(
EP OP-11 DIAaLO CANYON POWER PUWT UNIT NO(S) 1 AND 2.
NUMBER REMSON 3 DATE 6/21/82 PAGE 12op 20 m
i LOSS OF COMPONENT COOLING WATER
.)
TITLE:
UiONS/MLits FEPWSE RESPCPE E OBTAlte SUBSEQUENT ACTIONS CONTINUED 2.
Attempt to restore component cooling water flow.
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_I NumeE EP OP-11 DIAM.O CANYON POWER PUWT UNIT NO(S).
I AND 2 DATE 6/21/82 1
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PAGE O
l TkE:
LOSS OF COMPONENT COOLING WATER
]*
APPENDIX A CLEARING A COMPONENT COOLING WATER HEADER DUE TO HEADER FAILURE This procedure is intended to provide guidance for clearing a Component Cooling Water header due to a gross leak that is otherwise unisolable. The operators must detemine which header the leak is on and follow the steps below to clear the respective neader.
1.
Clearing Header "A" a.
If the leak is detemined to be between the pump discharge arid the component cooling water heat exchanger 1,1 motor operated outlet valve (FCV-430), check or place in service 1-2 component cooling water heat exchanger, then:
1)
Close all three component cooling water pump discharge valves to header A.
2)
Close component cooling water heat excnanger 1-1 motor g
operated outlet valve FCV-430.
\\
3)
Close the inlet valve to RE-17A (CCW 1-7).
4)- Shut down the Turbine Building sump pumps as necessary.
5)
Refer to Emergency Procedure R-5 and notify the Chemical and Radiation Protection Engineer.
f b.
If the leak is determined to be downstream'of component l
cooling water heat exchanger outlet valve FCV-430, check or place 1-2 heat exchanger. in service, then:
1)
Close FCV-430.
2)
Close CCW heat exchanger 1-1 outlet header A-C crosstie valve CCW 1-23.
3)
Start 1-1 and 1-2 CCW pumps if available. Shutdown 1-3 CCW pump.
4)
Close header A-C suction crosstie valve CCW 1-5.
i 5)
Isolate Makeup water to the "A" half of the surge tank.
NOTE: The following is a list of equipment normally served by header "A".
Take appropriate actions to swap to alternate equipment.
l l
DC0067 131V
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[OP-11 m
otAaLO CANYON POWER PLANT UNIT N0(S) 1 AND 2 -
DATE 6/21/82 PAGE 14 OF 20 Tirts:
LOSS OF COMPONENT COOLING WATER APPENDIX A CONTINUED CLEARING HEADING "A" Equipment nomally served by CCW "A" header.
EQUIPMENT '
ACTION i.
1.
CCW pump 1-2 and 1-3 Open "B" header supply and return for CCW pump 1-2 (CCW 1-104 and
(
CCW 1-108). Close "A" header Stuffing Box and Lube Oil Coolers supply and return for 1-2 CCW pump (CCW 1-105 and CCW 1-109).
NOTE: No action required for 1-3 E pump since it was shut down.
2.
Centrifugal Charging Pump 1-1 Lube Start 1-2 or 1-3 charging pump if 011 and Seal Coolers.
needed. Shut down 1-1 charging pump.
3.
RHR Heat Exchanger 1-1 and RHR pump If in service, swap heat 1-1 Seal Water Cooler.
exchanger and pumps.
4.
Safety Injection Pump 1-2 Start 1-1 Safety Injection Pump if needed. Shut down 1-2 Safety l
Lube oil and Seal Water Injection Pump.
Coolers I
6.
Post LOCA Sample Coolers None l
l 4
1 DC0067 141V 0
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l otAst.O CANYON POWER PLANT UNIT NO(5) 1 AND 2 NunaBE EP OP-11 j
g DATE 5/21/82 g
PAGE 15 OF 20 k
i Tm.E.
LOSS OF COMPONENT COOLING WATER
\\
i c.
Shutdown the turbine building sump pumps as necessary. Refer to Emergency Procedure R-5 and notify the Chemical and Radiaticn Protection Engineer.
l 2.
Clearing Header "B" If the leak is determined to be between the pump discharge and a.
the component cooling water heat exchanger 1-2 motor operated I
outlet valve FCV-431, check or place in service 1-1 component.
cooling water heat exchanger, then:
1)
Close all three component cooling water pump discharge valves to header "B".
2)
Close component cooling water heat exchanger 1-2 motor operated outlet valve FCV-431.
3)
Close the inlet valve to RE-17B (CCW 1-9).
-4)
Shut down the Turbine Building sump pumps -as necessary.
5)
Refer to Emergency Procedure R-5 and notify the Chemical and g
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Radiation Protection Engineer.
b.
If the leak is determined to be downstream of component cooling water heat exchanger outlet valve FCV-431, check or place 1-1 CCW heat exchanger in service, then:
1)
Close FCV-431.
2)
Close CCW heat exchanger 1-2 outlet header B-C crosstie,
valve (CCW 1-24).
3)
Start 1-2 and 1-3 CCW pumps if available. Shut down 1-1 CCW pump.
4)
Close header B-C suction crosstie valve (CCW 1-4).
5)
Isolate makeup water to the "B" half of the surge tank.
NOTE: The following is a list of equipment nownally served by header "B".
Take appropriate actions to s' ap to alternate w
equipment.
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j NUMBE P OP-11 DIABLO CANYON POWER Pt. ANT UNIT NO(S) 1 AND 2 DATE 6/21/82 PAGE 16 OF 20
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TITLE. LOSS OF COMPONENT COOLING WATER
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ADPENDIX A CONTINUED CLEARING HEADING "B" Equipment normally served by CCW "B" header.
l EQUIPMENT ACTION l
1.
CCW Pump 1-1 None required since 1-1 CCW pump was shut down.
Stuffing box and Lube Oil Coolers 2.
RHR heat exchanger 1-2 and RHR If in service, swap RHR heat Pump 1-2 Seal Water Coolers exchanger and pump to-1-1, and shutdcwn 1-2 RHR pump.
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3.
Centrifugal Charging Pump 1-2 Start 1-1 or 1-3 Charging Pump if needed. Shut down 1-2 Charging Lube Oil and Seal Coolers pump.
4.
Safety Injection Pump 1-1 Start 1-2 Safety Injection Pump if needed. Shut down 1-1 Safety Lube 011 and Seal Coolers Injection Pump.
l 5.
Containment Fan Coolers Start 1-3 and 1-4 CFCU's.
1-2 and 1-5.
Shutdown-1-1, 1-2 ard 1-5 CFCU's.
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DC0067 161V-1 l
o,iAsto CANYON POWER PLANT UNIT NO(S) '1 AND 2 NUMBE EP OP-11 DATE 6/21/82
-(O PAGE 17 OF 20 k
m LE; LOSS OF COMPONENT COOLING WATER
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c.
Shutdown the turbine building sump pumps as necessary.
d.
Refer to Emergency Procedure R-5 and notify the Chemical and Radiation Protection Engineer.
3.
Clearing Header "C" NOTE: Clearing Header "C" results in a loss of component cooling water to all Reactor Coolant pumps.
a.
Prior to clearing header "C" reduce Unit Load.
b.
Upon clearing header'"C":
1 1.
Trip the Reactor, then; 2.
Trip the Reactor Coolant pumps and refer to EP OP-5 Reactor Trip with no Safety Injection.
3.
To clear header "C", perform the following steps:
a.
Close header "C" supply FCV-355.
g
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b.
Start 1-1 and 1-3 CCW pumps.
c.
Shut down 1-2 CCW pump.
d.
Close header A-C suction crosstie valve (CCW 1-5).
l e.
Close header B-C. suction crosstie valve (CCk 1-4).
f.
Close CCW-2, CCW pump 1-2 suction valve.
g.
Open DC control power locally to CCW pumo 1-2 to prevent an inadvertent AUTO start with CCW-2 closed.
NOTE: The following is a list of equipment nonnally served by header "C" Unit 1.
Take appropriate actions to swap to alternate cooling water or equipment as necessary.
l
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DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND.2 REVISION 3 CTE 6/21/82 PAGE 18 OF 20 TiTts; LOSS DF COMPONENT COOLING WATER 1
APPENDIX A CONTINUED CLEARING HEADING "C" EQUIPMENT ACTION 1.
Reciprocating Charging Pump 1-3 Start 1-2 or 1-3 Charging pump if Fluid Drive, Seal Plate, & Lube Oil needed. Shut down 1-3 Charging Coolers pump.
2.
Letdown Heat Exchanger Isolate normal letdown. Reduce charging flow. Maintain Seal Injection.
3.
Seal Water Heat Exchanger Monitor seal injection temperature 4.
Excess Letdown Heat Exchanger Unless it is in service, then-isolate excess LTDN.
5.
Spent Fuel Pit Heat Exchanger Monitor spent fuel pool temperature 6.
Steam Generator Blowdown Sample NONE Coolers 7.
Pressurizer Steam, Liquid and Hot NONE l
Leg Sample Heat Exchangers i
8.
a.
Waste Concentrator If needed, swap supply and return b.
Boric Acid Evaporator valves over to Unit Two CCW c.
Auxiliary Steam Drain Header "C".
Receiver vent condenser l
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DATE 6/21/82
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PAGE 19 OF 20 j
k.
Tnts; LOSS OF COMPONENT COOLING WATER APPENDIX A CONTINUED CLEARING HEADING "C*
EQUIPMENT ACTION 9.
a.
Reactor Vessel Support Coolers NONE b.
Gross Failed Fuel Detector Heat Exchanger c.
Central Sample Panel Coolers
- 10. Waste Gas Compressor 0,1 and 1-1 Shut down 1-1 WGC and swap CCW Seal Water Coolers.
supply and return valves to Unit Two CCW Header "C" for 0-1 WGC.
k 4.
Shutdown the Turbine Building sump pumps as necessary.
5.
Refer to Emergency Procedure R-5 and notify the Chemical and Raciation Protection Engineer.
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DIABLO CANYON POWER PLANT UNff NCKS) 1 AND 2 DATE 6/21/82 PAGE 20 OF 20
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ints:
LOSS OF COMPONENT COOLING WATER APPENDIX Z NOTIFICATION INSTRUCTIONS 1.
When this procedure has been activated and upon direction from the Shift Foremen, proceed as follows:
a.
Notify the Plant Superintendent, Supervisor of Operations and Plant Manager or their designated alternates, as a minimum.
b.
If any loss.of component cooling water results in a reactor trip, designate this a Significant Event. As a minimum within one hour notify the NRC Bethesoa Operations Center using the Red Phone in the Contror Room. Gather sufficient information from all courses l
prior to calling so that the phone call is meaningful. Refer to Operating Procedure 0-4 " Operating Order (One Hour Reporting j
Requirements to NRC)" for a suggested format for reporting.
l l
l c.
If one vital loop of component cooling water is lost, designate
(
this a Notification of Unusual Event. Notify plant staff and response organizations required for this classification by implementing Emergency Procedures G-2 " Establishment of the On-Site Emergency Organization" and G-3 " Notification of Off-Site Organizations" in accordance with Emergency Procedure G-1
" Accident Classificaticn and Emergency Plan Activation."-
d.
If both vital loops of component cooling water are lost, in modes 5 or 6, designate this an Alert. Notify plant staff and response organizations required by IF F2 and EP G-3 in accordance with EP G-1.
e.
If both vital loops of component cooling water are lost, in modes 1, 2, 3 or 4, designate this a Site Area Emergency. Notify plant staff and response organizations required by Ep G-2 and EP G-3 in accordance with EP G-1.
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