ML19224B257
| ML19224B257 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 10/06/1978 |
| From: | Metropolitan Edison Co |
| To: | Mullinix W NRC/IE |
| References | |
| 2202-1.3, TM-0031, TM-31, NUDOCS 7906140301 | |
| Download: ML19224B257 (26) | |
Text
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TMI DOCUMENTS DOCUMENT NO: /
~Oh COPY MADE ON f
0F DOCUMENT PROVIDED BY METROPOLITAN EDISON COMPANY.
Wilda R. Mullinix, NRC I
7 9 0 614 0 3o t 195 049 e
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2202-1.3
,8 Revision 11 b,
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CONTRO_ LED COP"
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CDTR4i ri!F THRec atiLE 1 STAND' NUCLE AR STATION UNIT #2 EMERGEf!CY PROCECURE 2202-1.3 LOSS OF REACTOR COOLANT / REACTOR COOLANT SYSTEM PRESSURE Table of Effective Pages Pace Date R evision Page Date Revision Pace Date R evision 1.0 06/22/77 1
2.0 05/12/78 8
3.0 12/30/77 3
4.0 12/30/77 3
5.0 06/22/77 1
6.0 03/01/78 5
7.0 09/29/78 10 8.0 05/12/78 8
9.0 06/20/78 9
10.0 05/12/78 8
10.1 05/12/78 8
10.2 05/12/78 8
11.0 06/22/77 1
12.0 06/22/77 1
13.0 04/18/78 7
14.0 10/06/78 11 15.0 04/18/78 7
16.0 12/30/77 3
17.0 06/22/77 1
18.0 04/18/78 7
19.0 12/30/77 3
20.0 12/30/77 3
21.0 12/30/77 3
22.0 12/30/77 3
23.0 06/22/77 1
Unit 1 Staf f Recommends Approval Unit 2 Staff Recommends Approval
, V7 Approval
//N Date Approval
/E Date Cognizant Dept. Head Cognizant Dept. Head Unit 1 PORC Recommends Approval Unit 2 PORC Recommends Approval i d'. l*Q k
Date ~
/ II i d'tALv Date Chairrr,an of PORC V - Chairman of PORC Unit 1 Superintendent Approval Unit 2 Superintendent Approval h
k Date I; i.,,?e I Date ?'O W
V'
(,l ll M9 DatC mowe, Geneot;on Ouanty Auuona Approval
" " " ^ " ~ " " '
/95 050 l
7 e, y
<n 2202-1.3 g/
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Revision 1 06/22/77
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AFR 2 3 1979 THREE MILE ISLAND NUCLEAR STATION
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UNIT #2 EMERGENCY PROCEDl!RE 2202-1.3 LOS5 0F Rii.ACIOR COOLANT / REACTOR C00LMIT SYSTEM PRESSURE A.
Leak or Rupture Within Capability of System Operation.
1.0 SYMPTOMS 1.1 Initial loss of reactor coolant pressure & decrease in pressurizer level becoming stable after short period of time.
1.2 Possible reactor building high radiation and/or temp. alarm.
1.3 Possible reactor building sump high level alarm.
1.4 Maka-up tank level decreasing > 1" in 3 min.
1.5 Possible makeup line high ficw alam.
1.6 RB Fan Drip Pan Level Hi Alarms.
NOTE:
The operator may distinguish between a loss of coolant inside containment, an OTSG tube rupture and a steam line break by the fSlowing symptoms which are unique to the aforementioned accidents.
1.
Loss of coolant inside Rx Bldg. - particulate, iodine & gas monitor alarm cn HP-R-227 " Reactor Building Air Sample".
2.
OTSG tube rupture - gas monitor alarm on VA-R-748.
3.
Steam line break (11 Low condensate storage tank level alarm - and or low hot well level alarm.
(21 FW Latch System Actuation.
2.0 IMMEDIATE ACTION 2.1 Autcmatic Action:
1.0 95 057
j 2202-1.3 Revision 8 9;
d 05/12/78 APR 2 3 1979 2.1.1 MU-V17 will open to compensate for reduced pressurizer level.
2.1.2 Additional pressurizer heaters will come on in response to reduced reactor coolant pressure.
2.2 Manual Action 2.2.1 Verify MU-V17 open and pressurizer heaters on.
2.2.2 "CLOSE" MU-V376 letdown isolation valve, & " START" the backup MU pump, if required.
2.2.3 Reduce load at 10% minute & proceed with normal shutdown.
2.2.4 "LINE-UP" waste transfer pump from a R.C. Bleed Holdup Tank &
pump to the makeup tank to maintain required level.
2.2.5 If for any reason the operator cannot maintain Make-uo Tank and Pressurizer levels above their respective low level alarm setooints, " TRIP" the reactor, " INITIATE" Safety Injection manually (push buttons on canel 3), & then "Close" MU-V12.
3.0 FOLLOW UP ACTION 3.1 Safety Injection Not Initiated.
3.1.1 Initiate uait shutdown & coolcuan per 2102-3.1 and 2102-3.2 respectively.
3.2 Safety Infection Manually Initiated (HPI and LPI).
3.2.1 Verify that the Makeup Pumps & Decay Heat Removal Pumps start satisfactorily.
3.2.1.1 Close MU-V12 and MU-V18.
3.2.2 Sypass the SAFETY INJECTION by DEPRESSING the Group Reset Pushbuttons & " THROTTLE" MU-Vl6A/B/C/D as necessary to maintain
_t 220" pressurizer level and not exceed 250 GPM/HPI flow leg.
3.2.3 If MU pump flow drops below 95 GPM, trip excess MU pumps.
195 05g 2.0
V 7,
2202-1.3 Revision 3 7 12/30/77 y
APTs 2 3 '.379
- NOTE:
HPI String A flow is the sum of MU 23 FEl&2.
HPI String B flow is the sum of MU23 FE 3&4.
3.2.4 Verify that Safety Injection equipment is in its ESF position as shown in Table A-1.
3.2.5
_ CAUTION:
Continued operation depends upon the capability to maintain pressurizer level and RCS pressure above the 1640 PSIG Safety Injection Actuation setpoint.
l 1.
If pressurizer level can be maintained above the low level alarm point and the RCS pressure above the Safety Injection Actuation point, then proceed to step 3.2.6.
2.
If pressurizer level cannot be maintained above the low level ala.m point and the RCS pressure above the Safety Injection Actuation point, then the plant has suffered a major rupture and operation should continue according to Part B - Leak or Rupture of Significant Size Such that Engineered Safety Features Systems are Automatically Initiated.
3.2.6 With the pressurizer level and RCS pressure being maintained within allowable limits, initiate plant shutdown and cooldown per 2102-3.1 and 2102-3.2, respectively.
NOTE:
The HPI System is being used for makeup control and valves MU-V16A/B/C/D will have to be throttled to maintain pressurizer level.
As RCS pressure decreases, it may be possible to return to the normal makeup flowpath and secure HPI.
If MU pump
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flow drops below 95 GPM as a result of throttling, "Open" MU-V36 & 37 to provide MU pump recirculation path to MU Tank.
Monitor MU Tank level and open MU-V12 as required.
95 053 3.0
I.
2202-1.3
',/
Revision 3
., h' */,
12/30/77 3.2.7 At the time the DH System is to be brought on line for normal APR 2 3 BI3' -
cooling only one DH string should ce used for decay heat removal (i.e. - recirculation from the RC System).
The other DH string should be mai>teined on standby for use in recirculating water from the RB sump to the RC system.
NOTE:
Trip Reactor Coolant Pumps before R.C. Pressure decreases belcw pump NPSH (See figure 1 of 2102-3.1/3.2.
3.2.8 When the Borated Water Storage Tank level decreases to 12' as indicated on panel 8, Shif t the MU/HP1 pum; (s) suction from the BWST to the RB sump if RCS Pressure is greater than 200 psig as folicws:
(assume DH string A(B) is being used for decay heat removal and DH 5,tring B(A) is being maintained on standby):
3.2.8.1 If not already done, " THROTTLE" HPI string (s) flow rate to at least 500 gpm each < 250 gpm per leg) using control valves MU-V16A/B/C/D (or MU-V17 if flow has been returned to the normal makeup flow path). Flcw rate indication and valve control in control room on Panel 8 and 3, respectively.
3.2.8.2 "0 PEN" valve DH-V7B(A) in crossover line from LPI String B(A) to HPI string B(A) (suction of HPI pumps)..
" REPOSITION" HPI flow control valves MU-V16A/B/C/D (or MU-V17 if flow has been returned to the normal makeup flowpath).
HPI flow would increase because of increased HPI pump suction
~2 pressure.
2 3.2.8.3 When the BWST level decreases to 7',
verify automatic transfer to the RB sump is initiated.
Verify OPEN suction valve for string B( A), DH-V6B( A) from the RB sump.
I95 054 4.0 e
6 st
! h/ -
2202-1.3 Revision 1 06/22/77 APR 2 3 99.,
3.2.8.4 When the suction valve from the R2 sump DH-V6 B(.A),
is fu'lly open, then "CLOSE" the ECCS suction valve, CH-V5B(A), frcm the BSWT (valve controls and position indication in control room).
The ECCS B(A) string is new in " piggy-Back" operation providing makeup to the RCS from the RB sump as required.
3.2.9 After R.C.S. pressure decreases to = 200 psig, throttle HPI discharge flow by throttling MU-V16A/B/C/D. Observe that LPI pumps now deliver water to RCS via DH-VaA/B.
3.2.10 When MU-V16A/B/C/D (HPI flow '[alves) are closed, stop the Hi pressure injection pumps & close CH-V7A & 7B from the LPI pump discharge. Injection flow path is now as follows:
Spill coolant to RB sump, RB sump to LPI pumps, LPI pumps to RCS via UH-V4A/B.
3.2.11 Throttle DH-V128A & B as required to maintain 220" pressurizer level and max. LPI pump ficw of 3C00-33C0 gpm. Within about 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, es'ablish a long-term cooling circulation mode as described in 2104-1.3 and listed bolow.
Mode 1 Forced circulation using decay Heat drop line.
Mode 2 Gravity craining reactor coolant hot leg to the Reactor Building sump via the D.H. drop line.
Mode 3 Hot leg injection using Pressurizer Auxiliary Spray Line.
Mode 4 Reverse flow through the Decay Heat Drop line into "B" Reactor Coolant Loop Hot Leg.
-j 3.2.12 Evaluate radiation levels & initiate action for Site Emergency as outlined in the TMI radiation emergency plan.
195 055 5-
7.
2202-1.3 Revision 5 03/01/78 [p 3.2.13 Reactcr Building Isolation Initiated APR 2 3 13 1.
Refer to Section B, 3.0 & complete all steps.
8.
LEAK OR RUPTURE OF SIGilIFICANT SIZE SUCH THAT ENGI'1EERED SAFETY FEATURES SYSTEMS ARE AUTCT'ATICALLY INITIATED.
1.0 SYMPTCMS 1.1 Rapid continuing decrease of reactor coolant pressure.
(1)
Lo alarm 2055 psig.
(2)
Lo-Lo-alarm 1700 psig.
(3)
Safety Injection actuation at 1640 psig.
1.2 Rapid continting decrease of pressurizer :evel.
(1)
Lo alarm 200".
(2)
Lo-Lo alarm 80" (Interlock heater shutoff).
1.3 Hi radiation alarm in Reactor Building.
1.4 Reactor Bui~iding Ambient Terpert. tare 'arir..
1.5 Hi Reactor Building Sump level.
1.6 Hi Reactor Building pressure (R.C.S or main steam line rupture).
1.7 Rapidly decreasing make up tank level.
1.8 Both core flood tanks levels & pressurec are decreasing.
NOTE:
The operator may distinguish between a loss of coolant inside containment, an OTSG tube rupture and a steam line break by the following symptoms which are uniye to the aforementioned acciderts.
1.
Loss of coolant inside Rx Bldg. - particulate, iodine gas monitor alarm on HP-R-227 " Reactor Building Air Sample."
C 2.
OTSG tube rupture - Gas monitor alarm cn VA-R-748.
3.
Steam break inside Rx Bldg:
6.0 195 056
3 2202-1.5 Revision 10 09/29/78
'4' (1)
Low condensate storage tank level alarm - and or low hot
/,
well level alarm.
APR 2 3 33 (2)
R1 Latch System Actuation.
2.0 IMMEDIATE ACTION 2.1 Automatic Action.
{
2.1.1 Reactor trip 1900 psig.
2.1.2 Turbine Trip.
2.1.3 Safety Injection initiated 01600 psig R.C.S pressure, or 4 psig Reactor Building pressure.
2.1.4 Both Core Flood Tank levels & pressures may decrease depending upon rupture size and R.C.S. pressure. (< 600 psig).
2.1.5 Reactor Building Isolation & Cooling initiated.
(R.B. Press.
> 4 psig).
2.1.6 Reactor Building Spray if the Reactor Building pressure is greater than 30 psig.
2.2 Manual Action.
2.2.1 "CLOSE" MU-V12 and MU-V18.
2.2.2 Small Break LOCA Response 2.2.2.1 Within 2 minutes of the LOCA the CR0 dedicated to recognition of a small break LOCa must ccraplete the following:
a.
Verify that small break LOCA with single failure symptoms exist.
Symptoms: 1.
SFAS initiation and only one MUP start 9d, or 2.
SFAS initiation and loss of "
c or 2-2E j
7.0 e
1 2202-1.3
,q (
Revision 8 05/12/78 APR 2 3 191d b.
DISPATCH designated LOCA Response Primary A.0. to OPEft MUP Discharge Cross-connect.
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c.
PROCEED to MU-V16A & B or MU-V16C & D.
d.
Within 5 minutes of the LOCA the MVP discharge cross connect valve must be opened off its closed seat and one of the MU-V16 valves on the side of the single failure must be opened 2 turns.
2.2.2.2 CR0 at MU-V16A & B or MU-V16C & D must ESTABLISH comrciunications with the Control Room.
2.2.2.3 Once in comunication with the control room the CR0 at MU-V16A
& B or C & D continue to open the valves to establish 125 gpm per leg; while the control rocm CR0 THROTTLES MU-V16C & 0 or A
& B co prevent pump runout.
NOTE:
If the LOCA was E.S. with loss of MUP all MU-V16 valves would initially be open.
The operator at the controls must in this case throttle all 4 MU-V16 valves to 125 gpm/ leg. Also in this case the CR0 dedicated to Small Break LOCA would not need to go to the MU-V16 valves.
He should go to the MUP discharge cross connect valves and assist the A.0.
to speed up the opening of the MUP discharge cross connect.
SMALL BREAK LOCA ACTION TIMES EVENT TIttE From Cccurance Recognition 1 2 minutes CR0 to MU-16's 1 4.5 minutes 8.0 195 05g g
/ C.
2202-1.3 Revision 9 ('
SMALL BREAK LOCA ACTION TIMES (Cont'd) 06 APR 2 3 8 TIME From Occuran/20/78 EVENT ce A0 to MUP Discharge X-Connects 1 3.5 minutes Communications Established With 1 5.0 minutes
^
CR0 at MU-V16's One of the Single Failure Side 1 5.0 minutes MU-V16's Open 2 turns Discharge X-Connect 0FF Closed Seat 1 5.0 minutes Discharge X-Connect Open 1 10.0 minutes MU-V16's Throttled to 125 gpm/ leg 1 10.0 minutes 2.2.3 Verify Hi pressure injection is operating properly as evidenced by injection flow in all four legs.
(NU-V16A/B/C/0).
Flow indicated on MU23 FEl,2,3,4.
2.2.4
" TRIP" reactor coolant pumps before reaching 1200 psig.
2.2.5 Verify Reactor Building Cooling and Isolation is operating properly.
3.0 FOLLOW UP ACTION 3.1 Verify that all E.S.F. ecuipment is in its ESF pcsition, by observing that all equipment status lights indicate as shown in Table B-1.
3.1.1 Check locked valve status took and verify closed or close the following manual containment isolation valves MU-V330, MU-V364, CF-Vil4A, CFVil4B, CF-V145, CF-V146, DH-V187, and DW-V28.
NOTE:
Should any component not operate properly, attempt to actuate it at its remote switch in the Control Room.
If it still does not operate, & the component has a local control station attempt to operate the component locally.
3.2 Notify Shift Foreman, who notifies all Station personnel over the cross-tied PA system that a site emergency has occured.
3.3 0 to 20 or 30 minutes past LOCA until sump recircualtion is initiated:
Control Room operator continuously monitors the following:
9.0 195 05p e
il 2202-1.3 I
Revision 8 l/
05/12/78 3.3.1 Liquid levels in the:
AFR 2 3 a73 l.
Borated Water Storage Tank, DH-T1, (CH-3-LI 1/2).
2.
Sodium Hydroxide Tank, DH-T2, (CH-7-LI).
3.3.2 Safety Features flow rate in each of the following:
1.
Two Low Pressure (Decay Heat) Injection lines, DH-1-FI 1 and 2.
2.
Four High Pressure (Makeup) Injection lines, MU-23-FI 1, 2, 3, and 4.
3.
Two Reactor Building Spray injection lines, BS-1-FI and 2.
4.
Four of five reactor building emergency cooling river water lines A'i-FI-5620, 5621, 5522, 5623, or 562? -respectively.
3.3.3 Reactor Building environmental indications:
1.
Temperature, recorder on Panel 25.
2.
Pressure, recorder on Panel 3.
3.4
" DEFEAT" any two channels of Reactor Building Isolation and Cooling, then bypass all three Safety Injection Channels.
CAUTION:
If normal power is lost while operating in the injection Mode from the BWST, RB Isolation and Cooling must be manually initiated, when either the BUS 2-1E or 2-2E Undervoltage alarm is received to ensure proper diesel generator load sequencing.
3.5 " THROTTLE" as required to prevent pump runout:
1.
Hi press. inj. flow (MU-16A/B/C/D) 0-250 GPM/ LEG.
CAUTION:
If MU pump flow drops below 95 GPM trip tne excess MU pumps.
h 10.0 e
2202-1.3 Revision 8 05/12/78 2.
Lo Press. Inj. Flow (CH-V123A/B) 3000-3300 GPM/PMP_
- g 2 3 1379 3.
Building spray flow (BS-Vl A/B) 1400-1700 GPM/PMP.
NOTE:
Hi flow alarms should actuate as a warning to throttle flows.
CAUTION:
The actions to be taken for switching suction from the BWST to the R.B. sump depend upon the number of operating ECCS injection strings and the delivered flowrates in these injection strings. Based upon the existing situation, in the ECCS, proceed as outlined below to perform switch over of suction to the RB sump:
Situation G,o to Step 1.
Both LPI strings are operating and 3.6 indicated flow in each is above 750 gpm.
2.
Both LPI strings are operating 3.7 but indicated flow in each is below 750 gpm.
?.
One _?I string is inoperative.
3.8
.;37E:
The main objective when switching suction from the BWST to the RB sump is to maintain ECCS flow through two flow paths.
3.5 Soth LPI Strings are Operating and Indicated Flow in Each is Above 750 GPM.
3.6.1 When the BWST level reaches approximately 12', initiate the i
following steps:
10.1 6
/
2202-1.3 Revision 8 1
05/12/78 3.6.2 If not already done " THROTTLE" LPI strings flow rates back to APR 2 3 1979 3000 GPM each using control valves CH-V128 A &B (flow ra'te indication and valve control in control room).
3.6.2.1 If not already done, THROTTLE BS pump's flows back to 1600 gpm per pump.
This must 'm done prior to taking suction from the RB sump.
3.6.3
" SHUT OFF" HPI pumps (pump control in control room).
3.6.4 Verify the ECCS suction valves CH-V6A & B from RB sump automatically open at BWST level of 7'.
3.6.5 When suction valves from RB sump are full open, "CLOSE the ECCS suction valves (DH-V5A & B) from the BWST.
3.6.6
" REPOSITION" LPI flow control valves (DH-V128 ASB) to obtain 3000 GPM each string if necessary.
(Flow rate could change due to change in suction sources).
3.6.7 Proceed to step 3.9.
3.7 Both LPI Strings Are Operating But Indicated Flow In Each Is Below 750 GPM.
3.7.1 When the BWST level reaches approximately 12', initiate the following steps.
3.7.2 If not already done, " THROTTLE" HPI strings' flow rates back to 500 GPM per pump each using control v lves MU-V16A, B, C, and D (flow rate indication and valve control in control room).
3.7.2.1 If not already done, THROTTLE BS pump's flows back to 1600 GPM per pump.
This must be done prior to taking suction from the RB sump.
iYb 062 10.2 i
iY 2202-1.3 Revision 1 APR 2 3 mg:.
06/22/77 3.7.3 "0 PEN" valves DH-V7A and B in crossover line frcm LPI line to suction of HPI pumps (valve control and position indication in control room).
" Reposition" HPI ficw control valves (MU-V16A,B,C, & D1 to obtain 500 GPM each string. (HPI ficw would increase because of increased HPI pump suction pressure).
3.7.4 VERIFY the ECCS suction valves (DH-V6A & 8) from RS sump automatically open at BWST level of 7'.
3.7.5
'Enen suction valves from RB sump are fully open, "Close" the ECCS suction valves (OH-VSA & B) frem the BWST. The ECCS is now in " piggy-back" operation.
3.7.6 Proceed to step 3.9.
NOTE:
Once the ficw in each LPI string exceeds 750 gpm, the HPI pumps can be " SHUT OFF" and valves DH-V7A &
B can be " CLOSED".
3.8 One LPI String is Inoperative 3.8.1 The BWST 7' automatic transfer to the RB sump is reached in approximately 55-80 minutes frca initiation of ECCS injection, depending upon reason for string failure (j.e. - local LPI failure or diesel failurel. Prior to actuation of the lo-lo level alarm, initiate the folicwing steps.
3.8.2 Using the controls in the control room, attempt to " START UP" the non-operating LPI 5tring.
If successful, proceed to step 3.6.
If not successful, proceed to step 3.8.3 below.
3.8.3 If step 2 was unsuccessful, initiate opening the DH cross-connect isolation valves (DH-Vl93 A & B)_ as folicws:
3.8.3.1 ENSURE SN-V188 is closed then OPEN CH-Vll2 A & B to fill the inoperable string.
11.0
i D.
9lA 2202-1.3 Revision 1 06/22/77 APR 2 3 1379
~
NOTE:
If offsite power is lost DHVl93 A & 3 must be manually opened.
3.8.3.2 Obtain the keys for the CH cro ss-connect isolation valves'
~(.DH-Vl93A and DH-Vl9381 breakers from the shift supervisor.
3.8.3.3 Proceed to 480V MCC 2-32B and MCC 2-428.
3.8.3.4 Remove the locks from the isolation valve breakers for the DH cross-connect line.
NOTE:
Local control stations for DH-Vl93A and are located in the Aux Bldg at Elev. 280'6" near the CH vaults.
3.8.3.5 "0 PEN" the DH cross-connect isolation valve (e.g. DH-V-193A(Bl}.
next to the operating L?I String.
3.8.3.6 "0 PEN" the second isolation valve (DH-Vl93A(B).)..
3.8.3.7 While opening the second decay heat cross-connect isolation vaive, " THROTTLE" either DR-V128A or DH-V1285 in the control room as required to achieve essentially equal flow rates in both D.H. injection lines. (_Approximately 1500 gpm per LP:
stringl.
3.8.3.8 If flow is established at greater than 750 gpm through each LPI string, then proceed to step 3.8.5.
3.8.3.9 If flow cannot be established threugh each LPI stri.ng in excess of 750 gpm using the cross-connect line before ECCS suction must be switched to the R3 sump, then proceed to step 3.9.4.
3.8.4 If opening the DH cross-connect line fails to provide flow in each LFI string in excess of 750 gpa, then place one HPI
~
string in a modified " Piggy-Back" mode with the operating LPI string as follows (assume LPI string "A"(S). is the operating string):
/
,L:
2202-1.3 Revision 7 C 04/18/78 3.8.4.1 If not a? ready done, " THROTTLE" HPI string "A"(B) flow rate APR 2 5 rats back to 500 GPM using control valve MU-V16A and V168.
3.8.4.2
" THROTTLE" LPI string "A"(B) flow rate to 3000 GPM using control valve DH-V128A(B).
3.8.4.3 "0 PEN" valve DH-V7A(B) in crossover line from LPI line to suction of the operating HPI pump.
3.8.4.4
" REPOSITION" HPI flow control valves MU-V16A&B to otbain 250 GPM per leg HPI flow and reposition LPI flow control valve CH-V128A to obtain 2500 GPM LPI flow.
The LPI pump is pumping design flow of 3000 GPM (2500 GPM LPI plus 500 GPM HPI).
3.8.4.5
" SHUT OFF" HPI pump in HPI string "B"(A).
3.8.4.6 Proceed to step 3.8.6.
3.8.5
" SHUT OFF" HPI pumps (pump control in control room).
3.8.6 If not already done, THROTTLE BS pump's flows back to 1600 GPM per pump.
This must be done prior to taking suction from the RB sump.
3.8.6.1 When the BWST level decreases to 7' 'sERIFY the ECCS suction valves (DH-V6A & B) frcm RB sump automatically open.
3.8.7 When suction valves from RB sumo are full open (position indic: cion in control room), "CLOSE" the ECCS suction valves (DH-V5A & B) from the BWST.
3.8.8
" REPOSITION" LPI flow control valve (s) (DH-V128A and/or B) as required to obtain proper string flowrates.
(Flow rates could change due to change in suction sources).
~.
3.9 When the Sodium Hydroxide Tank level reaches approximately 3 ft.
"CLOSE" DH-VSA & B.
3.10 Actuate En' iron.nental Barrier System by opening EB-Vil.
065 13.0 e
l'i 2202-1.3
/
b((Mf Revision 11 10/06/78 APR 2 3 1979 -
3.11 Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of ECCS initiation, establish one of the long-term cooling circulation modes described in 2104-1.3 - Decay Heat femoval System, and listed below:
Mode 1 Forced circulation using decay heat drop line.
Mode 2 Gravity draining reactor coolant hot leg to the Reactor Building sump via the D.H. drop line.
Mode 3 Hot leg injection using pressurizer auxiliary spray line.
Mode 4 Reverse flow through the decay heat drop line into "B"
Reactor Coolant Loop Hot leg.
4.0 LONG TERM ACTION 4.1 Verify all previous actions and carry out additional actions as outlined below.
4.2 Evaluate symptoms and determine if possible the cause of the loss of coolant.
4.3 Secure turbine, feed water, and steam systems when time permits.
4.4 Monitor for H buildup and assure actuation of H recombiner per 2
2 2104-6.4, Hydrogen Recombiner Operations.
4.5 Monitor R.B. Sump for pH and add Sodium Hydroxide as required thru the decay heat removal system.
4.6 As conditions permit, evaluate unit conditions, and return all non-essential equipment to its normal line up.
NOTE:
Refer to the following instructions and procedures for additional information as required.
1.
Radiation emergency plan site emr rgency in the emergency plan.
?
-1 2.
2104-5.4 - Control Building HVAC.
14.0 195 ogg e
/l 2202-1.3 Revision 7 04/18/78 s_
APR 2 3 G79 TABLE A-1 ESF EQUIPMENT - ESF POSITION IN THE CONTROL ROOM PANEL 13 The White light for each component should be lit to indicate that the component is in its ESF position, unless otherwise noted.
ACTUATION A ACTUATION P SAFETY INJECTION GP. 1 SAFETY INJECTION GP. 1 Eouipment ESF Position Equipment ESF Position
- DC-9-1A ON
-DC-P-1B ON
, G2-12 (flote 1)
CLOSED G22-12 (Note 1)
CLOSED MU-P-1A (Note 2)
ON MU-P-1B (Note 2)
Oil
, NR-P-1A (Note 3)
ON
- flR-P-lC (Note 3)
ON NS-P-1A (Note 4)
ON
- NS-P-1B (Note 4)
ON TIE-2E2 OPEN
-T2E-lE2 OPEN T3E-4E2 OPEN
- T4E-3E2 OPEN Tile-21E2 OPEN
- T21E-llE2 OPEN DC-V96A CLOSED
- DC-V96B CLOSED SAFETY INJECTION GP. 2 SAFETY IrlJECTICM GP. 2 Eauicment ESF Position Eauicment ESF Position
' N R-V9 A CLOSED
- NR-V9B CLOSED
- CH-V4A OPEN
- DH-V4B OPEN
.DH-V5A OPEN DH-V5B OPEN DH-V8A OPEN
. DH-V8B OPEN DH-V100A -
CLOSED DH-V1008 CLOSED
, DH-V102A OPEtt
-OH-V102B OPEN MU-P-1B (tiote 2)
Ott MU-P-lC Ctl
-j
-NR-V40A, OPEN v-flR-V408 OPEN NS-P-lc ON
,NS-P-lC (Note 4)
ON T12-22E-2 OPEN T22E-12E-2 OPEN C0[b Of,7
- MU-V28 CLOSED LHY-V55 15.0
/ /,
2202-1.3
)2/30)77 R i$ "
TABLE A-1 APR 2 3 ss, '
ACTUATION A ACTUATION B SAFETY INJECT ION GP. 3 SAFETY INJECTION GP. 3 Ecuicment ESF Position Equipment ESF Position vMU-V36 CLOSED MU-V37 CLOSED
> MU-V16A OPEN
'NS-V32 CLOSED
,MU-V16B OPEN
. NS-V67 CLOSED CH-P-1A ON
- CH-P-1 B ON NR-P-1B (Note 3)
ON
- MU-V16C OPEN 131 E-41 E-2 OPEN
-MU-V160 OPEN
<NS-V84B CLOSED
- NR-P-10 (Note 3)
ON
'NR-V42A OPEN T41E-31E-2 OPEN NS-V84A CLOSED J R-V42B OPEN PANEL 8 Status Light Equipment ESF Position Indicator __
NS-V83A OPEN R
' NS-V83B OPEN R
NS-V215 CLOSED G
' NS-V216 CLOSED G
NOTE 1:
Diesel Generator Breaker will or y be closed if Normal Power is lost; otherwise status indication will be Open (white).
NOTE 2:
MU-P-1B will be running if normal power is available for the Actuation,
.'or the pump that it is seleuted to backup.
If normal power is lost, MU-P-1B will be running, if the pump that it is selected to backup fails to starc or is inoperable.
95 Ofg 16.0
an i
'A 2202-1.3 Revision 1
('
06/22/77 APR 2 3 1375 TABLE A-1 NOTE 3:
The NR pump in each neader selected for ES or standby will start if a pcmp is not operating in that header; otherwise the operating pump will remain in service.
NOTE 4:
Normally NS-P-lA and 18 will start; hcwever, NS-P-lC will start if either NS-P-1A or 3 (depending upon which pump it is selected to backup) fails to start or is inoperable.
-I 17.0 5 Qf9
si 2202-1.3 Revision 7 TABLE B-1 04/18/78 APR 2 3 879 ESF EQUIPMENT - ESF POSITION IN THE CONTROL ROCM PANEL 13 The White light for each component should be lit to indicate that the component is in its ESF position, unless otheraise noted.
ACTUATION A ACTUATION B SAFETY INJECTION GP. 1 SAFETY INJECTION GP. 1 Ecuicment ESF Position Eauipment ESF Position DC-P-1A CN DC-P-1B ON G2-12 (Note 1)
CLOSED G22-12 (Note 1)
CLOSED MU-P-1A (Note 2)
ON MU-P-1B (Note 2)
ON NR-P-1A (fiote 3)
ON flR-P-lC (Note 3)
ON NS-P-1A (Note 4)
ON NS-P-1B (Note 4)
ON TIE-2E2 OPEN T2E-l E2 OPEN T3E-4E2 OPEN T4E-3E2 OPEN Tile-21E2 OPEN T21E-llE2 OPEN i
DC-V96A CLOSED DC-V968 CLOSED SAFETY IftJECTION GP. 2 SAFETY If1JECTION GP. 2 Eauioment ESF Position Equipment ESF Position NR-V9A CLOSED NR-V98 CLOSED DH-V4A OPEN DH-V4B OPEN DH-VSA OPEN DH-V5B OPEN DH-V8A OPEN DH-V8B OPEN DH-V100A CLOSED DH-V1008 CLOSED DH-V102A OPEN DH-V1028 OPEN MU-P-1B (Note 2)
ON MU-P-lC ON NR-V40A OPEN NR-V40B OPEN NS-P-lC ON NS-P-lC (Note 4)
ON T12-22E-2 OPEN T22E-12E-2 OPEN MU-V28 CLOSED HY-V55 CLOSED 195 070 18.0
}.2 2202-1.3 j hff TABLE B-1 ACTUATION A ACTUATION B SAFETY INJECTION GP. 3 SAFETY INJECTION GP. 3 Eauipment ESF Position Eauipment ESF Position MU-V36 CLOSED MU-V37 CLOSED MU-V16A OPEN NS-V32 CLOSED MU-V16B OPEN flS-V67 CLOSED DH-P-1A ON DH-P-1B ON NR-P-1B (Note 3)
ON MU-V16C OPEN T31 -41E-2 OPEN MU-V16D OPEN NS-V84B CLOSED tR-P-lC (Note 3)
ON l
NR-V42A OPEN T41E-31E-2 OPEN NS-V84A CLOSED NR-V42B OPEN R.B. ISOLATION AND COOLING GP. 1 R.B. ISOLATION AND COOLING GP 1 Equioment Position Ecuicment Position AH-V81 CLOSED AH-E-llD ON AH-V101 CLOSED AH-V80 CLOSED AH-V102 CLOSED AH-V103 CLOSED AH-V105 CLOSED AH-V104 CLOSED AH-V107 CLOSED AH-V106 CLOSED CF-V144 CLOSED AH-V108 CLOSED DH-V3 CLOSED CF-Vil5 CLOSED NM-VS2 CLOSED DH-V2 CLOSED NR-V51A CLOSED NM-V104 CLOSED RR-V2A OPEN NR-V51B CLOSED
.?*
RR-V2B RR-VSA OPEN RR-V2C OPEN RR-V5B OPEN RR-V2D OPEN 19.0
s.
'l 2202-1.3 Revision 3
,i TABLE B-1 12/30/77 l,,l g,
ACTUATION A ACTUATION B zy,q. 3,yg.
j R.B.
ISOLATION & COOLING GP. 1 R.B. ISOLATION & COOLING GP.~1 Eauicment Position Ecuipment Position v RR-V5C OPEN
-RR-V6C OPEN
- SV-VSS CLOSED u RR-V6D GPEN
-WDL-V1095 CLOSED
. RR-V6E OPEN DC-Vil4 CLOSED
- SV-V54 CLOSED v
- WDL-V1092 CLOSED v DC-V103 CLOSED
_ DC-V115 CLOSED R.B.
ISOLATION & COOLING GP. 2 R.B. ISOLATION & COOLING GP. 2 Equipment Position Ecuipment Position AH-E-4A ON AH-E-4B ON AH-E-llA ON AH-E-llc ON
- RR-V25C CLOSED
-RR-V25C CLOSED BS-VlA CPEN VlB OPEN v
- CA-V10 CLOSED
- CA-V1 CLOSED
'CA-V4A CLOSE0
-CA-V3 CLOSED CA-V9 CLOSED
-CA-V4B CLOSED v RR-P-1B ON CA-V8 CLOSED
'WDG-Vl99 CLOSED
-CA-V6 CLOSED
WDL-V22 CLOSED
'RR-P-lD ON WDL-Vil26 CLOSED
--WDG-V2 CLOSED AH-D4092A & B RECIRC
- WDL-V1125 CLOSED AH-040920 & E RECIRC
-WDL-V271 CLOSED
/ ED-4098 AH-D4092A & B RECIRC AH-04092D & E RECIRC ED-4098 RECIRC 195 0;72 20.0
., 9, 2202-1.3 Revision 3
/
TABLE B-1 12/30/77 ACTUATION A ACTUATION B
..y, g
,j g.t R.B. ISOLATION & COOL _ING_GP. 3 R.B. ISOLATION & C00 LING GP. 3 Equioment Position tquicment Position',
'IC-V2 CLOSED
'IC-V3 CLOSED IC-V5 CLOSED
- IC-V4 CLOSED
- MU-V2A CLOSED
- MU-V376 CLOSED
- MU-V2B CLOSED MU-V18 CLOSED
- MU-V377 CLOSED MU-V25 CLOSED
- NS-V72 CLOSED
- NS-V100 CLOSED D NS-V81 CLOSED NR-P-2B ON
. NR-P-2A ON RR-P-lC ON
/ MR-V144A OPEN
' RR-V250 CLOSED RR-V2SE CLOSED RR-P-1A ON
- RR-V25A CLOSED
-AH-C-8A ON
- RR-V2SB CLOSED
- AH-E-ll E ON
- IC-P-1A 0FF vAH-P-1B ON
AH-C-8A ON
'AH-V2A CLOSED t-AH-E-11B ON
"'AH-V2B CLOSED
' AH-E-llc ON
- AH-V3A CLOSED
" AH-P-1A ON AH-V3B CLOSED v
'AH-VlA CLOSED AH-V6 CLOSED c AH-VlB CLOSED v'AH-V61 CLOSED
-AH-V4A CLOSED
-AH-V61 CLOSED L'AH-V4B CLOSED
'AH-V63 CLOSED AH-V5 CLOSED
- AH-V71 CLOSED
-'AH-V60 CLOSED IC-P-1B 0FF
-I
- AH-V102 CLCSED
-AH-V72 CLOSED
- BS-P-1A ON
- BS-P-18 ON
- If RB Pressure >30 psig.
195 073 21.0 e
.O h'
2202-1.3
.e.
Revision 3
,/
12/30/77
/. g' -
NOTE l'.
Diesel Generator Breaker will only be closed if Normal Pcwer is lost; otherwise status indication will be Open (white).
NOTE 2:
MU-P-1B will be running if normal power is available for the Actuation, for the pump that it is selected to backup.
If normal power is lost, MU-P-1B will be running, if the pump that it is selected to backup fails to scart or is inoperable.
NOTE 3:
The NR pump in each neader selected for ES or standby will start if a pump is not operating in that header; otherwise the operating pump will remain in service.
NOTE 4:
Normally NS-P-1A and 1B will start; however, NS-P-lC will start if either NS-P-1A or B (depending upon which pump it is selected to backup) fails to start or is inoperable.
PANEL 8 Eouioment ES Position Indicatier.
- DH-V7A(I)
Close G
DH-V7B(I)
Close G
' NS-V83A Open R
-NS-V83B Open R
-NS-V215 Close G
NS-V216 Close G
-CF-VlA Open R
3F-VlB Ooen R
(I) This valve may have to be opened for " piggy-back" operation.
Once, opened, the Position / Indication becomes Open/R.
~.
f93 g74 22.0
d(
t.f;;.
( $c'Y 2202-1.3 Revision 1 06/22/77 AFR 2 3 g.
PANEL 15 Eauioment ES Position Indication UI 4 H-V6A Close G
U1
'DH-V6B Close G
MU-V378(2)
Open R
U )-
- MS-V4A Open R
0)
- MS-V48 Open R
U)-
- MS-7A Open R
- MS-V7B (3 )-
Ocen R
O)
This valve must be opened for sump-switchover. Once opened, the Position / Indication becomes CPEN/R.
(2}
This valve should be closed at the operator's first chance. Cnce closed, the Positicn/ Indication beccmes CLOSE/'d.
(3)
These valves should be closed when the steam system is secured.
Once closed, the Position / Indication beccmes CLOSE/G.
PANEL 25 Ecuioment ES Position Indication
'AH-E12A Off G
'AH-E123 Off G
~ AH-E19A Off G
"AH-E19B Off G
23.0 195 075 e