ML20214T537
| ML20214T537 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 02/18/1987 |
| From: | SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | |
| Shared Package | |
| ML20214T470 | List: |
| References | |
| E.07, E.7, NUDOCS 8706100311 | |
| Download: ML20214T537 (29) | |
Text
-
EFFECTIVE DATE 02-18-87
""' 4 E. 07 O
ICC I
POST TRIP Thot WINDOW Y-SATURATION CURVE VARIABLE SUBC00 LED SECONDARY MARGIN SYSTEM f
SATURATION TEMPERATURE f
=
1 O
Rev. 4 E.07-1 8706100311 870602 PDR ADOCK 05000312 PDR 8
l
.)
i g
INFORMATION PAGE 1.0 Max HPI flow - 525 gpm per pump.
Max LPI flow - 3,000 gpm per pump with suction from the RB sump.
- 3,750 gym max flow through a DH cooler.
1.1 Isolates path from RB of potentially highly radioactive waste.
2.2 ECC SETPOINT not operable if any RCPs running.
3.0 AT between OTSG and RCS Tsat should be maintained at 1007 as RCS pressure varies until primary to secondary heat
- transfer 'is established.
g i
i e
Rev. 4 E.07-2 l~
+
E.07
\\
'ICC
.1 Immediately take manual control and CIDSE RCP seal return valves. (SFV-24009 and SFV-24013) 2.0 INCREASE OTSG LEVELS TO 95% (381" EFIC)
.1 E RCPs are tripped M select ECC setpoint.
.2 2 any RCPs are running M regulate AFW flow manually.
- 3. 0 LOWER OTSG PRESSURE TO INDUCE HEAT TRANSFER O
1 Open TBVs in manual, lowering OTSG pressure to decrease OTSG Tsat 90-110 7 below RCS Tsat, for existing RCS pressure.
.1 E TBVs are unavailable M use ADVs until TBVs are available.
.2 WHEN primary to secondary heat transfer is regained M establish maximum cooldown rate, not to exceed 1007/hr.
4.0 VERIFY CORE FLOOD TANK ISOLATION VALVES ARE OPEN (HV-26513 AND HV-26514)
O Rev. 4 E.07-3
.m
.)
/
INFORMATION PAGE g
5.0 Utilize Incore T/Cs (SPDS Incore function or IDADS) to determine RCS condition. SPDS displays average of five highest incore T/Cs. IDADS displays average of preferred and alternate incore T/Cs per FIGURE 1.
2400-oN 1 200o-EGIoN 2
- I "
teco-REGloN 4 E 12o0-sATURAT1oN
$ aoo-1 oo-g 4
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4ao 800 12oo INCoRE TEMPERATURE
l 1
O Rev. 4 E. 07-4
O O
E.07 O
ICC 5.0 TAKE ACTION BASED ON SPDS ICC DISPLAY OR FIGURE 1
.1 E P-T point is in Region 1 (saturated /subcooled)
THEN go to CP.103.
.2 E P-T point is in Region 2 (superheat)
.IHEN so to Step 1.
.3 E point is in Region 3 (clad > 1400'F)
.THEN go to Step 8.
.4 E P-T point is in region 4 (clad > 1800*F)
.IHEN go to Step 14.
O STATUS ENTRY FROM STEP 5 INCORE T/C TEMPERATURE IS IN REGION 3 CAUTION IF AT ANY TIME THE RCS CONDITIONS ENTER A LESS SEVERE ICC REGION, THE OPERATOR SHOULD NOT REVERT TO THE ACTIONS FOR THE LESS SEVERE ICC REGION.
6.0 ESTABLISH MANUAL AFY CONTROL
.1 Place all AFY flow control valves in HAND.
.2 Regulate AFW flow to maintain 95% (381" EFIC).
Rev. 4 E.07-5
. _ _.O O
INFORMATION PAGE I
7.1 RC Pump start interlocks.
< 307. Reactor power RCP motor oil lift > 1,750 psig RCP motor upper bearing oil level i 2 inches RCP motor lower bearing oil level i 2 inches Seal injection flow > 3 gym RCP CCW flow > 307 gym To start fourth RCP Tc > 500 7 Motor 86 lockout (Motor Protection Relay)
Normal - Green Light Dim Abnormal - Green Light Bright i
r I
O i
9.0 HPVs should stay open until RCS is subcooled or until decay heat removal system is operating with RCS < 140 peig.
9.1 H3RPB1 is located on NSEB Mezz., east equipment room.
1 H3RPA1 is located on NSEB Mezz., west equipment room.
9.2 Obtain keys 236, 237, and 238 from the Shift Supervisor key locker to enable HPV valve BIPBs.
.1 i
i 4
l hv. 4 E.07-6
4 l
E.07 o
ICC 1
i i
.1 Da HQ1 override RCP interlocks.
.2 Do HQI trip a running RCP for any reason except motor electrical faults, until. the RCS returns to Region 1.
j
.1 E an RCP is tripped for an electrical fault j
THEN start another RCP in the same loop.
l 1
8.0 LOWER OTSG PRESSURE TO' INDUCE HEAT I
TRANSFER
.1 Open TBVs in manual, lowering OTSG pressure to 400 psig or as low as needed to achieve a 100'F
. decrease in OTSG Tsat (decrease pressure rapidly).
.1 2 TBVs are unavailable, use ADVs until TBVs Q
are available.
.2 Maintain OTSG level at 95% (381" EFIC).
9.0 OPEN ALL HIGH POINT VENT VALVES
.1 Insert fuses and close HPV disconnects.
.1 DSF1-7 in H3RPB1
.2 DSF1-8 in H3RPB1 l
.3 DSF1-7 in H3RPA1
)
.2 Enable HPV BLPBs by inserting keys and turning j
keyswitches.
.3 Open all HPV valves.
10.0 IE INCORE T/Cs INCREASE TO REGION 4 THEN j
.1 Go to Step 14, otherwise continue.
- !O Rev. 4 E.07-7 i
l
o l.-
INFORMATION PAGE g
12.0 Indications of heat transfer:
.1 Incore T/C temp within 10T of Thol
.2 Max expected RCS AT of 50* to 607.
.3 Tc approximately equal to OTSG Tsat.
.4 Lowering OTSG pressure causes corresponding decrease in Tc.
e O
O Rev. 4 E. 07-8
m, E.07 O
ICC t
11.0 WHEN INCORE T/C TEMPERATURE DECREASES TO SATURATION (REGION 1)
THEN
.1 Continue with step 12.
12.0 IE PRIMARY TO SECONDARY HEAT TRANSFER IS EQT ESTABLISHED
.1 Go to CP.104, otherwise continue.
l l
13.0 MAINTAIN RCS PRESSURE' 25-50 PSIG.> OTSG O
PRESSURE
~
.1 Cycle Pzr HPVs (HV-21522 and HV-21528).
4
.1, IE Pzr HPVs cannot control pressure j
THEN cycle the EMOV.
1 l
.2 WHEN SCM is regained
_QB 4
WHEN RCS pressure decreases to 150 psig l
.THEN Go to CP.103 section 12.
1 1
i.
I O
Rev. 4 E.07-9
'N 3
r
.)
IN70RMAT10N PAGE O
15.0 Maintaining 100 psig ensures availability of AFW from steam driven pump, if needed.
\\
Rev. 4 E.07-10
0 E.07 ICC STATUS ENTRY FROM STEP 5 OR 10 l
INCORE T/C TEMPERATURE IS IN REGION 4-CAUTION IF AT ANY TIME THE RCS CONDITIONS ENTER A LESS SEVERE i
ICC REGION, THE OPERATOR SHOULD NOT REVERT TO THE ACTIONS FOR THE LESS SEVERE ICC REGION.
14.0 START.ALL RCPs, ONE RCP AT A TIME l
.1 2 RCPs will not start remotely l
THEN
.1 Verify breaker closing springs charged.
.2 Pull manual close handle near bottom of breaker to close breaker.
O
.2 Allow starting current on RCP to return to normal before starting the next RCP.
15.0 LOYER OTSG PRESSURE TO INDUCE HEAT TRANSFER
.1 E an Aux. Boiler is operating THEN lower OTSG pressures, as quickly as possible, to atmospheric pressure.
.2 2 an Aur. Boiler is HQI operating, THEN lower OTSG pressures, as quickly as possible, to 100 psig.
.3 Maintain OTSG level at 957. (381" EFIC).
O Rev. 4 E.07-11
~.-
O O
INFORMATION PAGE O
16.3.1 H3RPB1 is located on NSEB Mezz., east equipment room.
H3RPA1 is located on NSEB Mezz., west equipment room.
O 18.0 EFIC will not automatically maintain level at ECC SETPOINT when an RCP is in operation.
l l
O Rev. 4 E.07-12
~
l E.07 ICC i
16.0 DEPRESSURIZE THE RCS l
.1 Open HV-21505, EMOV Block Valve.
.2 Open the EMOV and leave open.
.3 Open all High Point vent valves.
4
.1 Insert fuses and close HPV disconnects.
.1 DSF1-7 in H3RPB1
.2 DSF1-8 in H3RPB1 l
.3 DSF1-7 in H3RPA1 i
.2 Enable HPV BLPBs by inserting keys and turning keyswitches.
i
.3 Open all HPV valves.
.4 Depressurize the RCS until LPI restores core cooling.
j 17.0 IE INCORE T/Cs RETURNS TO THE O
SATURATION TEMPERATURE FOR THE EXISTING RCS PRESSURE l
DIEN
.1 Decrease running RCPs to one per loop.
)
l 18.0 MAINTAIN OTSG LEVEL i
.1 Regulate AFW with flow control valves in HAND.
l j
.2 Maintain OTSG level at 95% (381" EII'IC).
I O
Rev. 4 E.07-13 l
O.
}
INFORMATION PAGE g
l 19.2.1 MCC S2D2 is located on grade level of controlled area.
O O
Rev. 4 E.07-14
m i
i 4
1 l
E.07 ICC 19.0 CONTINUE THIS MODE UNTIL EITHER i
.1 Lo-lo I.avel alarm on BWST, Window 29 on H2SFB.
Verify BWST level with LI-25001 on H2SFB
.T122[ go to Step 23.-
i
)
E
.2 LPI flow has increased to > 1,000 gym per loop for at l,
least 20 minutes THEN
.1 Isolate the Core Flood Tanks.
.1 Rack in breakers for CFT outlet isolation valves.
2D228 (HV-26513))
.1 2D229 (HV-26514
.2
.2 Close CFT outlet isolation valves.
.1 HV-26513 l
.2 HV-26514 l
A-
.2
. Secure HPI cooling.
')
U
.1 Stop HPI pumps and Makeup pump
.2 Close HPI injection valves l
.3 Closer HPV valves
.4 Close EMOV i
.3 IE RCS pressure increases to 150 psig l
THEN cycle EMOV as necessary to maintain RCS pressure < 150 psig.
I a
I t
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I hv. 4 i
E.07-15 i
i
^
]
INFORMATION PAGE g
O 20.1.4 SFV-25003 and SFV-25004 are modulating valves.
Pushbuttons must be held in until the valves are fully closed.
20.1.5 LPI flow must be maintained < 3,000 gpm per pump when suction is from RB emergency sump.
O Rev. 4 E.07-16
O D
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ICC I
CAUTION i
J DO NOT ESTABUSH A FLOW PATH IN ANY SYSTEM ISOLATED i
BY SFAS WITHOUT REVIEW OF THE POTENTIAL RELEASE OF
]
RADIOACTIVE GAS OR IJQUID.
a CAUTION I
PRIOR TO TRANSFERRING LPI SUCTION FROM THE BWST TO THE RB i
EMERGENCY SUMP. EVACUATE THE -20 AND -47 FOOT LEVEIE 0F THE i
AUXILIARY BUILDING.
i i
20.0 WHEN BWST LEVEL DECREASES TO THE LO-LO j
LEVEL ALARM
}
.IIHM s
.1 Transfer LPI suction to the RB Sump within four (4) minutes.
i
.1 Verify Lo-Io BWST level with U-25001 on H2SFB.
.2 Check RB emergency Sump level indicating light
.3 Open emergency sump outlet valves.
.1 HV-26105
.2 HV-26106 j
.4 Close BWST outlet valves.
.1 SFV-25003
.2 SFV-25004 i
.5 Control LPI flow to < 3,000 gym per train.
i j
21.0 WHEN LPI SUCTION HAS BEEN TRANSFERRED TO l
MN
.1 Stop all RCPs.
)
I i
22.0 CONTINUE LPI COOLING UNTIL STATION MANAGEMENT PROVIDES ADDITIONAL INSTRUCTIONS O
hv. 4 E.07-17
_ _ _, _ _. - -, - _ _ - - ~ - _ _ _ _.,,,. -, _ _. - -.. - _, - - - -. - _, _.,, _ _ _ _ _.
- -., =. ~ _ _ -,,
O O
INFORMATION PAGE g
23.0 Maximum DHS pump flow with suction from the RB emergency g
sump is 3,000 gpm.
W 23.2 A minimum time of four (4) minutes is allowed to open sump valves, upon receipt of BWST ID-LO alarm, depending on ECCS flow rates. As much BWST water should be allowed to flow to the RCS as possible, without endangering suction to the pumps.
O Rev. 4 E.07-18
i O
U l
E.07 ICC STATUS ENTRY FROM STEP 19.1 BWST LO-LO LEVEL ALARM.
LPI FLOW IS < 1,000 GPM PER TRAIN.
I CAUTION 4
DO NOT ESTABLISH A FLOW PATH IN ANY SYSTEM ISOLATED BY SFAS WITHOUT REVIEW OF THE POTENTIAL RELEASE OF
]
RADI0 ACTIVE GAS OR LIQUID.
i CAUTION 1
PRIOR T0 TRANSFERRING LPI SUCTION FROM THE BVST TO THE RB l
EMERGENCY SUMP, EVACUATE THE -20 AND -47 FOOT LEVELS OF THE i
AUXILIARY BLULDING.
1, 2
ALIGN PERABLE HPI/MU AND DHS PUMPS FOR O
i PIGGYBACK OPERATION f.
1 Open appropriate piggyback. valve (s).
HV-26007 (A Train))
.1 HV-26006 (B Train
.2 i
2 Open appropriate emergency sump valve (s).
.1 Verify RB emergen y sump level indicating lights.
.2 HV-26105 (A Train l
.3 HV-26106 (B Train i
3 Stop any HPI/MU pump HQI aligned to an operable DHS pump DE align both pumps to the operable DHS '
I Pump.
t i
4 Close BWST suction valves.
l
.1 SFV-25003 (A Train) i
.2 SFV-25004 (B Train) 1 I
5 IE one decay heat system train is inoperable I
THEN attempt to restore it to operation in j
conjunction with the remainder of this procedure.
O i
hv. 4 l
E.07-19 i
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O O
INFORMATION PAGE O
24.0 COOLDOWN LIMITS:
RCS temp > 2707
- 100 RCS temp < 2707 > 1707 - 507 hr RCS temp < 1707
- 10T O
Rev. 4 E.07-20
rm i
.j O
ICC 24.0 E RCS TEMP CAN BE CONTROLLED J',
BY THE OTSG(s) i un i
.1 Cooldown with the OTSG(s) until the decay heat system is placed in service.
.2 Throttle HPI as necessary to prevent exceeding pressure limits of FIGURE 2.
(RULE 2)
.3 Go to step 27.
25.0 E OTSGs CAN NOT CONTROL RCS TEMP THEN
.1 Continue-HPI cooling. until.the decay heat, system is placed in senice..
.2 Throttle HPI to maintain SCM AND PTS limits from FIGURE 2. (RULE 2) i 9
Rev. 4 E.07-21
.- O
R m
_)
INFORMATION PAGE O
i 26.0 COOLDOWN LIMITS:
RCS temp > 2707
- 1007/hr RCS temp < 2707 > 1707 - 507/hr RCS temp < 1707
- 107/hr S
l l
t l
l 0
Rev. 4 E.07-22 3
O-ICC 26.0 E BOTH DECAY HEAT SYSTEMS ARE-OPERABLE AHQ RCS PRESSURE IS < 250 PSIG 3xu i
.1 Place 1 LPI train in the DHS mode.
.1 Stop the HPI/MU pump that is piggybacked with the DHS pump to be placed in the DHS mode.
.2 Close CFr isolation valves, if open.
.3 Stop the DHS pump which is being placed in the DHS mode.
.4 Close the emergency sump valve for the non-running DHS pump.
.1 HV-26105 (A Train)
.2 HV-26106 (B Train)
.5 Open both drop line isolation valves.
.1 HV-20001
.2 HV-20002 -
n
.6 Open the DHR suction valve for the non-running DHS L>
Pump..
.1 HV-20006 (A Train)
)
.2 HV-20006 (B Train)
.7 Restart the secured DHS pump.
- j
.8 Throttle to maintain DHS flow < 3,000 gym.
.i l
27.0 2 BOTH DECAY HEAT. SYSTEMS ARE OPERABLE AND RCS PRESSURE IS < 150 PSIG 4
THEN
.1 Establish LPI/DHS cooling.
.1 Stop all RCPs.
.2 Stop all HPI/MU pumps.
.3 Close all HPI injection valves.
.4 Close all high point vents.
.5 Cycle the EMOV as necessary to maintain RCS pressure < 150 psig.
O Rev. 4 E.07-23 i
1
-, - ~ _ _ _ _ _. _
O N
s' INFORMATION PAGE O
O Rev. 4 E.07-24 l
l
O 3
4 5 a7 0
mc j
l 28.0 CONTINUE CURRENT MODE OF COOLING UNTIL STATION MANAGEMENT PROVIDES ADDITIONAL l
INSTRUCTIONS l
l l
O 4
)
O Rev. 4 E.07-25 I
O O
FIGURE 1 CORE EXIT THERMOCOUPLE TEMPERATURE FOR INADEQUATE CORE COOLING REGION 1 SUBCDOLED REGIDNS 0
REGION 2 SDME GAS GENERAT!W AND FUO. PIN DAMAGE POSSIBLE. TCLAD (1400 F
C.
REGION 3 GAS GacATIm AND FUE1. PIN DAMAGE LIKELY. TCLAD <!800 F
REGION 4 SIGNIFICANT GAS GENERATIDN AND CLAD DAMAGE PROBABLE.
2400 I
I I
g 2200 S
REGION 1 l
j f
2000 REGION 2
@1800 h
. REGION 3 1600-g J
REGION 4_.
3 1400 R
I
/
cn 1200
/I
/
/
1000 g
CunvE y / l' jf
/
SATURATION f
i y I/
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U 600-i INCORE TC's 70 MONITOR
)f j(
PREFERRED ALTERNATE 400
/
/
- 1) T9254 T9256 200-
/[
/[
- 2) T9258 T9260
- 3) n263 3252
- 4) T9272 79266
- 5) T9286 T9270 l
l l
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0 200 400 800 800 1000 1200 1400 INCORE TEMPERATURE -
F h
Rev. 4 E.07-28
FIGURE 2 O
REicrOR cOOtiNr sysrEu INTERIn FRicruRE tIvIr NO FORCED FLOY AND THERMAL SHOCK OPERATING REGION l
I NOTE:
Maintaining the reactor SA TION 3000-coolant subcooled takes precedence
,cuave t
over the Interim Brittle Fracture ysM \\
Curve (BacY 74-1122501 page 8)
NO FORCED-FJDW' \\\\
2800 OPERATING QAND INCORE TC's TO MONITOR W/HPI ral 2600- PREFERRED ALTERNATE
- 1) T9254 79258 II
\\
\\
2400- 2) T9258 T9260 g 2h NDT m k
kJ y
- 3) Tsens T9252 M
- 4) Ts272 79268 l
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n.2200-
- 5) T9286 T9270 u
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RES,TRICTED
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i INDICATED RC TEMPERATURE F
Rev. 4 E.07-27
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