ML20204A367
| ML20204A367 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 04/21/1986 |
| From: | CONNECTICUT YANKEE ATOMIC POWER CO. |
| To: | |
| Shared Package | |
| ML20204A363 | List: |
| References | |
| EOP-3.1-4, NUDOCS 8605120128 | |
| Download: ML20204A367 (19) | |
Text
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Attachment A A0083e37-l cc. e-et EOP T -4 Fev. 29 E0P1 P
OPERATIONS REVIEW COMMITTEE APPROVAL Connecticut Yankee Emergency Operating Procedure EOP 3.1-4 9'P D w d?V&.:)
LOSS OF COOLANT
{ APPROV BYSTA UPERINTENDENT hN hB N EFFECTIMDATE d
d- $ {- h 1.0 DISCUSSION V
1.1 This procedure censiders a situation where a loss of coolant incident has occurred with Reactor Coolant System leakage in excess of blended makeup capabilities (about 160 gpm) and pressurizer level and/or pressure cannot be maintained.
1.2 A loss of coolant incident with either normal or emergency station power available is considered in this procedure.
1.3 Do not override automatic actions of enaineered safety features unless continued operation of engineered safety features will result in unsafe plant conditions.
1.4 Before opening any valves that have been closed by HCP initiation, verify by available instrumentation that the lines have integrity, would perform its intended function or would not cause a release path.
1.5 This procedure contains instructions to verify and establish shcrt term core cooling to prevent or minimize damage to the fuel cladding and release of excess radioactivity and to maintain long term shutdown cooling of the reactor by recirculation of spilled reactor coolant and injected water from the reactor containment building sump.
1.6 Reactor coolant system VOIDING is possible during the course of this procedure.
A.
VOIDING can be recognized by:
1.
An unexplained increase in pressurizer level while trying to depressurize the RCS by pressurizer spray, power operated relief valve operation, or other means.
2.
An unexplained difficulty in reducing system pressure while operating with " solid" conditions in the FCS.
8605120128 860422 PDR ADOCK 0500 3
P Page 1 of 17
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EOP 3.1-4 Rev. 29 FOP 1 3.
Indication of vore thermocouple, reactor head or loop temperature ret. lings equal to or greater than saturation temperature for a given RCS pressure (Attachment A & B).
4.
Near zero subcooling margin on the ICC display.
B.
VOIDING can be OVERCOME by:
1.
Increasing RCS pressure by means of pressurizer heaters or L
charging rate to a pressure greater than saturation for a given RCS temperature.
i 2.
Decreasing RCS temperature by feeding and steaming steam l
generators, operation of core cooling equipeent, or adjusting RHR cooling flow (if RHP is in service) to a j
temperature below saturation for a given RCS pressure.
3.
Increasing RCS flow rate which decreases the probability of
+
hot spots occurring in stagnant or low flow areas of the RCS.
4 NOTE:
During cooldown by natural circulation care must l
be taken to cool the FCS slowly and uniformly so j
system hot spots are not created. VOIDING can
?
occur in these hot spots when system pressure is i.
reduced.
2.0 SYMPTOMS l
2.1 Decreasing pressurizer level and pressure and/or low alarm.
Pressurizer level may increase or decrease depending on location and I
size of break.
2.2 Increasing reactor-containment pressure, temperature, dew point j
temperature and/or high alarms.
2.3 Increasing containment sump level and/or high level alare.
1 2.4 Increasing indications and/or alarms on containment area radiation monitors R-31 (Manipulator Crane), F-32 (Charging Floor) and R-37 (Outside Equipment Hatch).
2.5 Increasing indications and/or alarms on containnent high radiation monitors, CD-1 and CD-2.
i 2.6 Figher temperatures at the core thermocouples than pressurizer stene phase indicates a bubble has formed in the reactor vessel head.
Verify this with head thermocouple temperature reading.
t i
Page 2 of 17
E0P 3.1-4 Rev. 20 E0P1 3.0 AUTOMATIC ACTIONS 3.1 Reactor and turbine trip from variable low pressure trip calculator if power level is greater than 10%.
(Minimum setpoint is 1700 psig).
3.2 Charging flow increases if charging flow control in auto standby charging pump may start on low header pressure.
If loss of offsite power has occurred the charging pumps will not be running.
3.3 Volume control tank (VCT) level decreases, initiating automatic makeup. Low level alarm sounds. MOV-373 (Pefueling Water Storage Tank to Charging Pump Suction) opens and MOV-257 (VCT Outlet) closes.
3.4 Pressurizer heaters will de-energize and letdown orifice valves will close on low pressurizer level at 11.5%.
3.5 Core Cooling initiates when pressurizer pressure reaches 1700 PSIG causing reactor and turbine trip from any power level.
3.6 Control Room ventilation is stopped and containment high pressure alarm occurs at 4 psig in the contai,nment.
3.7 All containment isolation trip valves close en SIS actuation or high pressure in the reactor containment if pressure reaches 5 psir.
3.8 Recirculation fan dampers cove to iodine removal position placing the charcoal filters in service if containment pressure reaches 5 psig.
4.0 IMMEDIATE OPERATOR ACTION 4.1 Perform immediate actions contained in E0P 3.1-1, Emergency Fhutdown.
5.0 SUBSEOUENT OPERATOR ACTION 5.1 If RCS pressure is less than 1700 psig, check that core cooling has actuated and operating.
Veeffy HPSI pump operation and stop all reactor coelant pumps. Close #1 seal water return valves, CH-MOV-311, 312, 313, and 314. Adjust seal water supply valves to maintain 5" to 10" W.C. delta P on labyrinth seals.
5.1.1 If RCP's are shut down and containment pressure is greater than 5 psig, close CH-TV-334 (seal water return) and CC-TV-1411 (component cooling from FCP coolers).
5.1.2
- If containment pressure is greater than 5 psig, verify that the 8 PASS valves (SS-SOV-150A through D and SS-SOV-151A through D are closed. *g 5.2 The process variables referred to in this procedure are typically monitored by more than one instrument channel.
The redundant channels should be checked for consistency while performing the steps of this procedure.
Page 3 of 17
E0P 3.1-4 Pev. 29 E0Pl 5.3 Check the following for pertinent information.
a.
Loop TC vide range and incore thermocouple, b.
Pressurizer pressure and reactor coolant system pressure, c.
Steam generator steam pressure and main steam header pressure.
d.
Pressurizer level.
e.
Containment pressure and exacte1.
f.
Containment temperature, g.
Refueling water storage tank level, h.
Demineralized water storage tank level.
1.
CD1 and CD2.
NOTE:
Do not use loop isolation valves to mitigate the circumstances of this accident until the system has stabilized.
CAUTION: Monitor the refueling water storage tank level closely.
If the RWST level decreases rapidly, such that reaching the point where 100,000 gallons have been pumped out go to step 5.16.
NOTE:
Switchover to Containment suno suction must be completed before the RVST tank Jevel drops too low in order to prevent damage to the safety injection pumps.
5.4 Verify the following conditions:
a.
Monitor the degree of subcooling in the core by comparing core outlet thermocouple temperature with saturation temperature for pressurizer pressure. Use attached saturation curve, attachment A.
Maintain reactor coolant pressure ecual to or greater than saturation curve +50 F safety hand.
b.
Establish auxiliary feedwater flow and steam dump to produce a core delta T of greater than 10 F as measured by loop wide range TC and core outlet thermocouples.
NOTE:
Other instrumentation which may be used to monitor core condition both during natural circulation or forced circulation are listed in Attachment B.
Page 4 of 17
ECP 3.1-4 Rev. 29 E0P1 c.
If voiding occurs, re-establish pressurizer pressure and level using pressurizer heaters, charging pumps and/or FPSI pumps as needed.
Isolate. breaks if possible.
d.
When on emergency AC power each diesel provides power for one high pressure safety injection pump, one low pressure safety e
injection pump 480V busses 4 and 5 or 6 and 7.
With associated equipment and motor control center, one RHR pump, two service e
water pumps, two containment recirculation fans and MCC5. A component cooling pump is available.
Pressurizer heater group "A" shall be used with the "A" Eeergency Diesel generator and pressurizer heaters group "E" shall be used with the "B" emergency diesel. This selection is necessary as these groups of heaters will trip from the diesel load should a safety injection signal be initiated or reinitiated while on emergency power.
NOTE:
If the plant is on emergency power, the 27Y-4, 27Y-4B, 27Y-7 and 27Y-7B lockout relays will have to be reset before pressurizer heater group "A" and group "E" can be used.
NOTE:
When on emergency power and a high pressure safety injection pump fails to start, place the control switch in the trip pull out position and start the charging pump associated with that train.
5.5 Stop, or verify stopped, any containment sump pumps that may be operating and place their control switches in the trip pull out position.
5.6 Monitor containment pressure and if pressure apnroaches 40 psig initiate containment spray by opening MOV-23 and MOV-34.
(Use the diesel fire pump supply by opening MOV-31 if only one I. PSI pump is operating. Containment spray should be initiated only as a last resort to limit containment pressure).
If on offsite power, start all available containment recire. fans.
If on emergency power, check one recire. fan running from each diesel and starr a third fan within 15 minutes of onset of accident.
If only one emergency diesel cperating, start second fan within 10 minutes and third fan within 15 minutes of onset of accident. Use key interlocked alternate power supply for third recire. fan. Do not overload emergency diesel.
5.7 Check all motor-operated Icop drain and containment isolation trip valves indicated on Main Control Board closed. Close or check closed DH-MOV-310.
Page 5 of 17
E0P 3.1-4 Rev. 29 EOP1 5.8 Verify heat is being dissipated via-the steam dump to condensers or steam generator relief valves.
5.9 Regulate feedwater additions to the steam generators as necessary to maintain heat sink and maintain wide range level 70% to 90% level.
5.9.1 Auto auxiliary feed will be initiated if both main feed pumpe are stopped or if steam generator level is less than 45% on two of four S/Gs.
i 5.9.2 If normal station power is lost, take manual control of auxiliary feed and operate feed pumps and atmospheric dump valve to maintain S/G 1evels and heat sink.
5.9.3 If normal station power is available, maintain S/G levels with main feed pumps and use steam dump to condenser as a heat sink.
CAUTION: BE CAREFUL NOT.TO OVER FEED TFE STEAM GENERATORS AND CAUSE A FURTHER RCS PRESSURE REDUCTION.
5.10 Assemble all shift operating personnel in the centrol room and pass out the necessary respirator equipment, high-range dosimeters and survey eeters. Confirm completion of Attachment C.
5.'11 Verify that both pressurizer PORVs are closed. Also verify the closed j
status and availability of power to both pressurizer PORV backup isolation valves. Check pressurizer relief tank pressure. Temp, and 4
Level. Also check panel alarms for pressurizer relief valve open and pressurizer relief valve position indication to ensure PORVs are closed.
CAUTION:
If the pressurizer power operated relief valves open automatically at any time during this transient, verify that the valves reclose when pressure drops below the PORV setpoint pressure.
If either PORV does not reclose, attempt to isolate it by using the appropriate backup isolation MOV.
4 5.12 To open reactor coolant sample trip valve, SS-TV-950, with containment pressure greater than 5-psig and allow operation on P.A.S.S. system.
5.12.1 Turn control switch for SS-TV-950 to the close position.
i 5.12.2 Turn the key-locked SOV-950 HCP override switch to the override position.
5.12.3 Turn control switch for SS-TV-950 to the open position to allow flow to P.A.S.S. system.
l 5.13 When containment pressure is less than 5 psig, recet containment l
isolation before opening SS-TV-950 by:
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Page 6 of 17
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Place Containment Sump Pumps in T.P.O.
2)
Place car fan damper switches in " test" position and verify RMS channel F-12/ll (Vapor Container Gas & Particulate) pump off prior to resetting containment isolation.
3)
Close or check closed the following control switches on M.C.B.
LD-A0V-202, LD-A0V-203, LD-A0V-204, SS-TV-950, SS-TV-955, SS-TV-960, SS-TV-965, DH-A0V-554, WG-A0V-558 CC-TV-611, DH-A0V-1841 and CF-MOV-331.
4)
Reset high containment pressure relay switches, 86 HCP 'A' and 86 HCP
'B'.
5)
Check Block Available Lights lit on Core Cooling Block Switch.
6)
Turn Core Cooling Block Switch to Block position and let it return to neutral position.
7)
Check Core Cooling Block Panalarms lit on both trains.
8)
Reset Core Cooling W.L. Switches.
5.14 SS-TV-950 can now be opened to supply P.A.S.S. sample system.
5.15 Safety Injection can be terminated if:
(a) The reactor coolant pressure is greater than 1800 PSIG and increasing ned, (b) pressurizer level is greater than 50% and, (c) the reactor coolant system is at least 50 F subcooled as indicated on the ICC display.
(d) The water level in at least one inservice steam generator is in the narrow range span, or in the wide range span at a level sufficient to assure that the tubes are covered.
5.15.1 After the safety injection (core cooling) relays have been reset the low pressure and high pressure safety injection pumps may be stopped. Place one charging pump in standby and keep one running for seal water injection and volume control.
Establish letdown as necessary.
NOTE:
On emergency power neither charging pump will be running.
It will be necessary to start one after stopping the low pressure safety injection puro.
CAUTION:
If the reactor coolant pressure drops below 1700 PSIG or pressurizer water level drops below 20% of epan or the reactor coolant subcooling nargin is less than 50 F subcooled, as indicated on the ICC display, manually reinitiate safety injection, if not auto initiated.
5.15.2 Reestablish operation of the pressurizer heaters for pressure control.
Page 7 of 17
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E0P 3.1-4 I
Rev. 29 FOP 1 5.15.3 Monitor either Taverage indication or core exit thermocouple and reactor coolant subcooling rargin on the ICC display.
If 50 F subcooling is not indicated, increase steam dump to cool the reactor coolant system.
Establish a 50 F to 100 F per hour cooldown rate consistent with makeup capability.
CAUTION:
If 50 F indicated subcooling cannot be maintained then manually reinitiate safety injection and re-diagnose the event.
5.15.4 Perform a controlled cooldown to cold shutdown condition as i
per NOP 2.3-4, Hot Standby to Cold shutdown.
5.16 If the corditions of 5.15 are not met and if 100,000 gallons have been 1
purped from the RWST, it will he necessary to establish a recirculation mode for core cooling to prevent damaging the ECCS pumps.
1 4
CAUTION: Verify that the water level in the containment is at elevation 2.25 feet or more on the wide range indicator before opening the RHP pump suction valves to ensure that the RHR pumps do not become air bound. Monitor this containment level throughout this phase.
NOTE:
If an operator is dispatched to the PAB to
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manually position valves, DO NOT start the RFR pumps until all personnel are out of the PAB.
5.16.1 Open circuits 13A and 13B in the DC panels.
l 5.16.2 Feset the safety iniection W.L. switches.
5.16.3 Initiate service water flow to the RHR heat exchangers hv opening SW-MOV-5 and SW-Mov-6.
NOTE:
Ensure that two service water puros are operating prior to opening SW-MOV-5 and SW-Mov-6.
If only one service water pump is operating, open one i
valve only. Additional containment recire. fans may be started if on emergency power.
See step 5.6.
5.16.4 Line up the RHR system for recirculation by opening j
RH-MOV-2 2.
If necessary, the manual containment sump suction may be opened from the PAB.
5.16.5 Stop both LPSI pumpe.
5.16.6 Start oniv one RHR pump.
i i
t Page 8 of 17
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E0P 3.1-4 Pav. 29 FOP 1 5.17 High Head Recirculation.
5.17.1 Figh Fead Recirculation using charging purps:
5.17.1.1 Open both RHR to charging pump cross connects RH-MOV-33A and RH-MOV-33B.
5.17.1.2 Close RWST to charging pump suction header BA-MOV-373 and check CH-POV-32 closed.
5.17.1.3 Check open CF-F0V-292B and CF-MOV-292C (charging stops to Loop 2).
5.17.1.4 Check running or start one chargine pump.
5.17.1.5 Adjust charging flow as necessary to maintain PCS pressure.
5.17.2 Perform the following valve Ifne-up:
5.17.2.1 Close breakers for RF-MOV-874 and SI-MOV-24, 5.17.2.2 Stop both HPSI pumps and close SI-V-857A and SI-V-857B (HPST recire. isolations).
5.17.2.3 Close SI-MOV-24 (FWST to FPSI suction).
5.17.2.4 Close SI-V-878 (SI recire at tank).
5.17.2.5 Open RH-MOV-874 (RHR discharge to HPST suction).
5.17.3 If RCS Pressure stabilizes above 1500 PSIG, then close RF-MOV-874 and go to step 5.17.4 If RCS pressure is less than 1500 PSIG and CD1 and CD2 are less than 20,000 F/hr, line-up for HPSI recirc in accordance with steps 5.17.3.1 through 5.17.3.5.
If RCS pressure is less than 1500 PSIC and CD1 or CD2 are greater than 20,000 P/hr or HPSI line-up cannot be accceplished then isolate charging MOV's CH-POV-292B and CH-MOV-292C and line-up the Fill Header by opering all four Fill Header MOV's, Fill Heeder Flow Control Valve and Bypass Valve, then go to step 5.17.4 5.17.3.1 Close two loop SI MOV's.
5.17.3.2 Open one PORV and POPV block valve and leave open.
5.17.3.3 Start one FPSI pump.
Page 9 of 17
EOP 3.1-4 Rev. 29 E0Pl 5.17.3.4 Close CH-V-292B and CH-V-292C, keep one charging pump running to raintain seal injection to the PCP's.
If the HPSI pump shews indication of cavitation, shift the charging pump suction to the VCT.
5.17.3.5 Verify HPSI flow.
5.17.4 Af ter all core cooling values have been verified to have gone to the accident position, lock open the breakers for RH-MOV-33A, RH-MOV-33B, BA-MOV-373, CH-MOV-32, SI-MOV-861A, SI-F0V-861B, SI-MOV-861C, SI-MOV-86]D, CD-F0V-871A, CD-MOV-871F., LD-MOV-200 and CH-MOV-257.
5.17.5 Pefer to Section 6.0 for RCS cooldown. When RCS pressure decreases below 500 PSIG [ Note: Pressure setpoint includes 350 psi harsh environment uncertainty above nominal setpoint of 150 psigl, monitor FPSI Pump or charging purp (whichever applicable) and RHR pump for indications of cavitation, l'pon indication of cavitation, shif t to RHR only recirculation as follows:
5.17.5.1 Stop HPSI pump, if running, and close RH-MOV-874, if open.
5.17.5.2 Verify RHR flow and monitor reactor vessel level and indications of reactor vessel fluid temperature and subcooling to ensure adequate core cooling.
CAUTION:
Indication of inadequete RHR flow suggests RCS pressure is higher than RFP pump shutoff head.
In this case, realign and restart chargine flow or HPSI puep as applicable.
5.17.5.3 Lock open breaker for RH-MOV-874.
5.18 Maintain seal injection flow to the RCPs.
5,19 When RCS pressure is less than 100 psig check the FCP seal water return MOVs closed.
5.20 When RCS pressure is at atmospheric pressure, stop seal water injection flow and shutdown the charging pump.
Restore power and close FF-MOV-33A and RH-MOV-33B.
5.21 Restoration of Core Cooling System 5.21.1 Core Cool.ing System I f neun shall be returned to a normal lineup when pressurfrer is restored to 1800 psig and level is 50'J or af ter a spurious initiation.
5.21.2 See Attachment D to reset core cooling.
Page 10 of 17
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EOP 3.1-4 Rev. 29 E0P1 5.21.3 Stop high pressure and low pressure safety in4ection pumps and place control switches in Auto position.
5.21.4 Stop one charging pump.
5.21.5 Close Core Deluge valves (CD-MOV-871A and B) and return control switches to auto position.
5.21.6 Close safety injection stop valves (SI-F0V-861A, B, C and D) and return control switches to auto position.
NOTE:
T.DCA in a hot standby condition is a significant accident and blocking or disabling of autesatic core cooling action should be avoided.
CAUTTON:
Ifreactorcoolantsystemdropsbelow17h5PSICor pressurizer level drops more than 20% of'ipan following termination of safety injection flow or if the reactor coolant Th is greater thah normal full power Th manually reinitiate safety injection to establish reactor coolant pressure and pressurizer water level. Go to E0P 3.1-45.
5.21.7 Establish lerdown, shift charging pump suction to the VCT.
5.21.8-Stop diesel generators if not needed.
6.0 SMALL BREAK CORE COOLING In case of a small break LOCA characterized by the reactor coolant pressures slowly decressing or stabilizing at seme point above the lowert steam system safety valve set point of 985 PSIC the following additicral manual action should be taken to aid cooldown and depressurization of the reactor coolant system.
6.1 If the main condenser is in service,. dump steam to reduce reactor coolant pressure and temperature.
6.2 If the main condenser is not in service, use atmospheric steam dump and hog jets to reduce reactor coolant pressure and temperature.
6.3 Reduce steam generator pressure and maintain 100 F/hr. cooldown rate with a more than 50 F subcooled condition.
6.4 Maintain RCS temperature and pressure within the Ifmits of the normal cooldown curves in the technical specifications to avoid pressurized thermal shock.
Page 11 of 17
E0P 3.1-4 Rev. 29 FOP 1 7.0 CONTINGENCY ACTIONS 7.1 In the event of a loss of coolant accident, coincident with a loss of off site power and one diesel generator fails to start the ections to establish a two path recirculation flow for long term cooling are no different than described in Section 5.16.
An attempt to start a failed diesel and close it onto its respective bus should be made as soon as possible in order to satisfy single failure criterion.
All motor operated valves in the safety injection system have hand wheels and may be operated manually if necessary and if radiological conditions permit.
8.0 INADEOUATE CORE COOLING INSTRUCTIONS 8.1 PURPOSE To specify precautions and operator actions aimed at restoring a condition of core cooling when inadequate core cooling exists. If the high range readings from core exit thermocouples are not available, a condition of inadeounte core cooling exists uhen:
the hot leg RTD's are pegged high or five or more incore thermocouples are off-scale above 750*F and safety injection flow is not being delivered to the reactor coolant system and auxiliarv feed water is not being delivered to the intact steam generator.
8.2 ACTIONS a.
Throughout this instruction, continue efforts to provide safety injection and/or charginF flow to the RCS and/or feedwater flow to the steam generators. Attempt to operate equipment manually locally, if possible.
b.
Continue monitoring of core exit thermocouples to determine effectiveness of subsequent actions.
c.
Depressurize the RCS by:
1.
Dumping steam to the condenser, or, 2.
If the condenser is not available dump steam through the atmospheric vent valve.
CAUTION: Depressurization through use of the steam generators should only be attempted if there is an effective water level and auxiliary or main feedwater is available.
Page 12 of 17
E0P 3.1-4 Rev. 29 E0P1 8.3 Open the pressurizer POPV's only if:
(a) SIS or charging is available to deliver to the RCS.
(b) RCS depressurization cannot be accomplished by steam generator.
(c)
Feed water is not available to maintain the steam generator secondary water leve? at an effective level.
8.4 Tf no means for RCS depressurization are available, or if the depressurization did not result in decreasing core exit the rnocouple temperatures, then start a reactor coolant pump, if applicable.
CAUTION: Maintain a positive labyrinth seal delta P with seal in.iection to prevent highly contaminated coolant from entering the seal water return header.
9.0 FOOTNOTES 9.1 1 - Amendment 72 go Facility Operating License, issued February 19, 1986.
Page 13 of 17
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i E0P 3.1-4 Fev. 29 E0P1 ATTACFMENT B Instrumentation available to aid the operator in monitoring pressure / temperature relationships are:
Pressure 1.
Pressurizer pressure - 3 independent channels that read out on the Main Control Panel.
2.
Reactor Coolant Loop #4 - 2 independent channels that read out on the Main Control Panel.
3.
Drain Header Pressure - I channel that reads out on the Main Centrol Panel. Drain Header Motor operated shutoff valve must be in open position.
4 Test Cage - I channel that reads out in the Primary Auxiliary Building.
Temperature 1.
Loop T cold - 4 channels that read out on Main Control Panel.
2.
Loop T avg - 4 channels that read out on Main Control Panel.
3.
Loop Delta T - 4 channels that read out on Main Control Penel.
4 Peactor Vessel Head Thermocouple - I channel that reads out on Main Control Panel.
5.
Pressurizer Surge Line Thereoccuple - I channel that reads out on Main Control Panel.
6.
Pressurizer Liquid Space Thermocouple - I channel that reads out on Main Control Panel.
7.
Pressurizer Steam Space Thermocouple - I channel that reads out on Main Control Panel.
8.
Peactor Core Outlet Thermocouple - 40 channels that read out through an IBM 1800 process computer. Range up to 750 F.
i Additional indications of void information available to the operator are reactor coolant pump vibration alarms and erratic or unstable ammeter readings.
1 Page 15 of 17
E0P 3.1-4 Rev. 29 E0P1 ATTACHMENT C PAB INCIDENT CHECKLIST CAUTION: Do not perform these instructions unless there has been a radiation survey conducted in the areas to be entered or the. operator is accompanied by a Health Physics technician and permission has been granted by the shift supervisor.
1.0 Don protective clothing fron PAB emergency kit as necessary.
2.0 If core cooling has initiated, perform the following:
2.1 Verify proper operation of safety injection purps.
2.2 Check solenoid valves for containment isolation in the unlatched position.
2.3 Line up blended makeup to RWST by opening BA-V-391.
3.0 If on emergency power open all load circuit breakers on MCC-8 except those for boric acid and primary water pumps.
4.0 Report the completion of this checklist to control room.
5.0 Go to the control room unless control assigns other duties.
Page 16 of 17
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- E0P 3.1-4 Rev. 29 FOP 1 ATTACHMENT D PRCCEDURE FOR RESETTING COPE COOLING AND CONTAINPFNT ISOLATION When containment pressure is less than 5 psig:
1)
Place Containment Sump Pumps in T.P.O.
2)
Place car fan damper switches in " test" position and verify RMS channe!
R-12/Il (Vapor Container Gas & Particulate) pump is off prior to resetting containment isolation.
3)
Close or check closed the following control switchee on M.C.B. LD-A0v-202, LD-A0V-203, LD-AOV-204, SS-TV-950, SS-TV-955, SS-TV-960, SS-TV-965, DH-A0V-554, WG-A0V-558, CC-TV-611, DH-A0V-1841 and CH-MOV-331.
4)
Peset high containment pressure relay switches, 86 HCP 'A' and 86 HCP,'B'.
5)
Check Block Available Lights lit on Core Cooling Block Switch.
6)
Turn Core Cooling Block Switch to Block position and let it return to neutral position.
7)
Check Core Cooling Block Panalarms lit on both trains.
8)
Reset Core Cooling W.L. Switches.
9)
SS-TV-950 can now be opened to supply P.A.S.S. sample system.
To restore containment isolation valves to normal:
- 10) Open one of the 12 valves in step 3 and push the CIAS/HCP rest button hehind the control board.
- 11) Reset the solenoids for the following valves and verify that the valves open: Open these valves only if proper conditions exist.
DH-TV-1844 RM-TV-1848 WD-TV-1846 WG-TV-1845 DH-TV-1843 LM-TV-1812 DH-TV-1842A SG-TV-1312-1 LM-TV-1811B SG-TV-1312-2 CC-TV-1831 SG-TV-1312-3 DH-TV-1847 SG-TV-1312-4 DH-TV-1842B MS-TV-1212 LM-TV-1811A MS-TV-1713
- 12) Place the following FCB switches in the normal position: Open these valves only if proper conditions exist.
SS-TV-955 SS-TV-965 SS-TV-960 SS-TV-950 CC-FCV-611 CH-MOV-331 LD-A0V-202 LD-A0V-203 LD-A0V-204 DH-TV-1841 DF-A0V-554 WG-AOV-558 CARFAN DAMPERS CONTAINMENT SUMP PUMPS RESTART CONTATTMENT PMS MONITOR PUMP Page 17 of 17
oa e Attachment B ALIGN SUMP TO RHR START ONE RHR PUMP ALIGN RHR TO CHARGING / LOOP 2 START ONE CHARGING PUMP ATTEMPT TO MAINTAIN RCS PRESSURE AllGN RHR TO HPSI CD 1/2 < 20,000 R/HR P > 1500 PSIG HPSI ALIGNMENT SUCCESSFUL NO NO YES YES CONTINUE CHARGING CLOSE TWO INJ. MOVs CLOSE HPSI TO LOOP 2 OPEN ONE PORV CROSS CONNECT START ONE HPSI PUMP ALIGN FILL HEADER CLOSE LOOP 2 CONNECTION
)
COOLDOWN AND
~
DEPRESSURIZE OST40CA RECIRCM ATION P < 500 PSIG NO -
YES MONITOR PUMPS FOR CAVITATION AND CONTINUE TO COOL DOWN AND DEPRESSURIZE SHUT OFF ALL NO PUMPS CAVITATE 7 YES MON TOR RCS EVEL AND TEMPERATURE
Attachment C POTENTI AL RECIRCUL ATION ALIGNMENTS DUTSIDE CONTAINMENT INSIDE CONTAINMENT CORE
- DELUGE FILL HEADER
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d id d : M : d : 6 :
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LOOP 1 2
3 4
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p REGCN h
h m v-24 LOOP.1 l
W k
HPSI 2
i 3
MOV-874 4
O RHE!> ELT E (C M NiiERS gg
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