ML19224B305
| ML19224B305 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 10/06/1978 |
| From: | Metropolitan Edison Co |
| To: | Mullinix W NRC/IE |
| References | |
| 2202-1.3-01, 2202-1.3-1, TM-0407, TM-407, NUDOCS 7906140446 | |
| Download: ML19224B305 (26) | |
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cAN 11 JCLE AR STATION UTIIT E2 EMERGEifCY PROCEDURE 2202-1.3 LOSS OF REACTOR C00LAtlT/ REACTOR C00LAt1T 5'. STEM PRESSURE Table of Effective Pages Page Date Revision Pm Date Revision
- Page, Date R evision i.0 06/22/77 1
2.0 05/12/78 8
3.0 12/30//7 3
4.0 12/30/77 3
5.0 06/22/77 1
6.0 03/01/78 5
'.0 09/29/78 10 6.0 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 Staff Recommends Approval Unit 2 Staff Recommends Approval g
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Date Cagnizant Dept. Head Cognizant Dept hyd Unit 1 PORC Recommends Approval Unit 2 PORC RKommends Approval lEY Date L
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Chairman of P0 RC V ' Chairman of FORC Unit 1 Superintendent Approval Unit 2 Superintendent Approval k
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2202-1.3 4,
Revision 1 06/22/77.
THREE MILE ISLAND NUCLEAR STATION UNIT #2 EMERGENCY PROCEDURE 2202-1.3 LOSS OF REACTOR COOLANT / REACTOR COOLANT SYSTEM PRESSURE A.
Leak or Rupture Within Capability of System Operation.
1.0 SYMPTOMS 1.1 Initial loss of reactor coolant pressure & decrease in pressurizar level becoming stable after short period of time.
1.2 Possible reactor building high radiation and/or temp. alam.
1.3 Fossible reactor building sump high level alam.
1.4 Make-up tank level decreasing > 1" in 3 min.
1.5 Possible makeup line high ficw alarm.
1.6 RB Fan 0-ip 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 following symptoms which are unique to the aforementioned accidents.
1.
Loss of coolant inside Rx Bldg. - particulate, iodine & gas monitor alarm on HP-R-227 " Reactor Building Air Sample".
2.
OTSG tube rupture - gas monitor alam on VA-R-748.
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3.
Steam line break (1 ).
Low cendensate storage tank level alarm - and or low hot well level alarm.
(21 FW Latch System Actuation.
2.0 D' MEDIATE ACTIO_N, 2.1 Automatic Action:
198.337 1.0
2202-1.3 i
Revision 8 05/12/78 2.1.1 MU-V17 wil. open to corrpensate for reduced pre:surizer 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 isolat. ion 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-up Tank and Pressurizer levels above their respective low level alarm setcoints, " TRIP" the reactor, "ITIITIATE" Safety Injection manually (push buttons on canel 3), & then "Close" MU-V12.
3.0 FOLLO'.1 td ACTI0t1 3.1 Safety Injection flot Initiated.
3.1.1 Initiate unit shutdown & cooldown pe:- 2102-3.1 and 2102-3.2 respectively.
3.2 Safety Injcction Manuclly 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 Sycass the SAFETY IflJECTf0tl by DEPRESSIt!G the Group Reset Pushbuttons & " THROTTLE" MU-VICA/B/C/D as necessary to maintain 220" pressurizer level and not exceed 250 GPM/HPI flow leo.
3.2.3 If MU pump flow drops below 95 GPM, trip excess i!U pumps.
2.0 198 338
V, 2202-1.3 3
Revision 3 12/30/77 NOTE:
HPI String A flow is the sum of MU 23 FEl&2.
HPI String B flow is the sum of "U23 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
Contined 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 pi?ssuriz^r level cannot be maintained above the low level alarm point and the RCS pressure above the Safety Injection Actuation point, then the plant has suffered a major rupture and operatien 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 210.-3.2, respectively.
NOTE:
The HPI System is being used for makeup control and valves MU-V16A/B/C/D will have to be throttle j 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 res'.ilt 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.
ggg 3.0
2202-1.3 2 ') Revision 3 7 12/30/77 at the time the DH System is to be brought on line for normal 3.2.7 cooling only one DH string should be used for decay heat removal (i.e. - recirculation from the RC System). The other DH string should be maintained on standby for use in recirculating water from the RB sump to the RC syst o. NOTE: Trip Reactor Ccalant Pumps before R.C. Pressure decreases below 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, Shift the MU/HPI pump (s) suction from the BWST to the RB sump if RCS Pressure is greater than 200 psig as follcws: (assume DH string A(B) is being used for decay heat removal and DH string B(A) is being maintained on standby): 3.2.8.1 If rot 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-Vi ^10w has been returned to the normal makeup flow path). Flow rate indication and valve control in control room on Panel 8 and 3, respectively. 3.2.8.2 "0 PEN" velve DH-V7B(A) in crossover line from LPI String B(A) to HPI string B(A) (suction of HPI pumps).. " REPOSITION" HDI 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 pressure. 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. 4.0 . - _. ~-
~ .- 2 i. 1 2202-1.3 e Revision 1 ~ 06/22/77-3.2.8.4 When the suction valve from the RB sump DH-V6 B(.A), is fully open, then "CLOSE" the ECCS suction valve, DH-VSB(A), from the BSWT (valve controls and position indication in control room). The ECCS B(A) string is now 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 f pumps now deliver water to RCS via D'f-V4A/B. 3.2.10 When MU-V16A/B/C/0 (HPI ficw va.es) are closed, stop the Hi pressure injection pumps & close DH-V7A & 7B frcm 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 DH-V4A/B. 3.2.11 Throttle DH-V128A & B as required to maintain 220" pressurf.er level and max. LPI pump flow of 3000-3300 gpm. Within abcut 24 hcurs, establish a long-term cooling circulation made as described in 2104-1.3 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 0.H. drop line. Mcde 3 Hot leg injection using Pressurizer Auxiliary Spray Line. Mode 4 Reverse flow through the Decay Heat Drop lire into "B" Reactor Coolant Lcop Hot Leg. [ 3.2.12 Evaluate radiation levels & initiate action for Site Emergency as outlined in the TMI radiation emergency plan. 5-198 541 9 ~
o 2202-1.3 ~ I Revision 5 03/01/78 3.2.13 Reactor Building Isolation Initiated 1. Refer to Section B, 3.0 & complete all stens. B. LEAK OR RUPTURE OF SIGNIFICANT SIZE SUCH THAT Ef1GINEERED SAFETY FEATURES SYSTEMS ARE AUTOMATICALLY IflITIATED. 1.0 SYMPTOMS 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 continuing decrease of pressurizer leoel. (1) Lo alarm 200". (2) Lo-Lo alarm 80" (Interlock heater shutoff). 1.3 Hi radiation alarm in Reactor Building. 1.4 Reactor Building Ambient Temperature Alarm. 1.5 Hi Reactor Building Sump level. 1.6 Hi Reactor Building pressure (R.C.S or main steam line rupture). 1.7 Papidly decreasing make-up tank level. 1.8 Both core flood tanks levels & pressures are decreasing. fl0TE: The operator may distinguish between a loss of coe' ant inside containment, an OTSG tube rupture and a steam line ~ break by the following symptoms waic' tre unique to the aforementioned accidents. 1. Loss of coolant inside Rx Bldg. - particulate, iodine gas monitor alarm on HP-R-227 " Reactor Building Air Sampie." 2. OTSG tube rupture - Gas monitor alarm on VA-R-748. 3. Steam break inside Rx B.Jg: 198 342 6.0
2202-1.5 Revision 10 .= 2 t 09/29/78 (1) Low condensate storage tank level alarm - and or low hot well level alarm. (2) FW 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 @ 1600 psig R.C.S pressure, or 4 psig Reactor Building pressure. 2.1.4 Bcth Care 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. 2.4 psig). 2.1.6 Reactor Building Spray if the Reactor Building ~ressure is p greater than 30 psig. 2.2 Manual Action. 2.2.1 "CLOSE" MU 'll2 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 complete the following: a. Ve ify that small break LOCA with single failure symptoms exist. Symptoms: 1. SFAS initiation and only one MUP star *- or 2. SFAS initiation and loss of 2-lE or 2-2E i98.343 7.0
2202-1.3 Revision 8 05/12/78 i b. DISPATCH designated LOCA Respons Primary A.0. to OPEN o MUP Discharge Cross-connect. c. PROCEED to MU-V16A & B or MU-V16C & D. d. Within 5 minutes of the LOCA the MUP 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 communicati" s with the Control Room. 2.2.2.3 Once in communication with the control room the CR0 at MU-Vla- & B or C & D continue to open the valves to establish 125 gpm per leg; while the control room CR0 THR0'iLES MU-V16C & D or A & B to 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 MVP 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 TIME F,on Occurance Recognition 5,2 minutes CR0 to MU-16's 5.4.5 minutes 198 344 8.0
2202-1.3 Revision 9 SMALL BREAK LOCA ACTION TIMES (Cont'd) =-a 06 EVENT TIME From Occuran/20/78 ce A0 to MVP Dischsrge 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 Di charge X-Connect Open 1 1 0.0 minutes MU-V16's Throttled to 125 gpm/le 4 1 10.0 minutes 2.2.5 Verify Hi pressure in,iection is operating properly as evidenced by injection flow in all four legs. (MU-V16A/B/C/0). Flow indicated on MU23 FEl,2,3,4. 2.2.4 " TRIP" reactor coolant pumps before reaching 1:'00 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. equipment is in its ESF position, 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 I following manual containment isolation valves MU-V330, MU-V364, CF-V114A, CFVil48, CF-V145, CF-V146, CH-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 statico attempt to operate the component locally.
- 3. 2 tbtify Shif t Foreman, who notifies all Station personnel over tnc 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 3
220,?-1.3 .? Re,ision 8 0.5/12/78 3.3.1 Liquid levels in tiie: 1. Borated Water Storage Tank, DH-T1, (DH-3-LI 1/2). 2. Sodium Hydroxide Tank, DH-T2, (DH-7-LI). 3.3.2 Safety Features flov, 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 AH-F1-5620, 5621, 5522, 5623, or 5624 respectively. 3.3.3 Reactor Building environmental indications: 1. Temperature, recorder on Panel 25. 2. Pressure, recorder on Pane' 3. 3.4 " DEFEAT" any two channels of Reactor Euilding 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-lE or 2-2E ~ -Undervoltage alarm is received tn ensure proper diesel generator load sequencing. 3.5 " THROTTLE" as required to prevent pump runout: 1. Fi press. inj. flow (MU-LEA /B/C/D) 0-250 GPM/ LEG. CAUTION: If MU pump flow. Tops below 95 GPM trip the excess MU pumps. 198 346 10.0 s.
2202-1.3 I Revision 8 '? 05/12/78 ~ 2. Lo Press. Inj. Flow (DH-V128A/B) 3000-3300 GPM/PMP. 3. Building ~ spray flow (BS-Vl A/B) 1400-1700 GPM/PMP. NOTE: Hi flow alarms should actuate as a .rning 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 Gp 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 eacn is below 750 gpm. 3. 0.ne '_?I string is inoperative. 3.0 .iGTE: The main objective when switchinq suction from the BWST to the P.B sump is to maintain ECCS flow through two flow paths. 3.6 Both LFI Strings are Operating and Indicated Flow in Each is Above 750 GPM. 3.6.1 Wnen the BWST level reaches approximately 12', initiate the following steps: 198 347 10.1 O i
2202-1.3 -I Revision 8 05/12/78 3.6.2 If not already done " THROTTLE" LPI strings flow rates back to 3000 GPM eacn. ng control valves DH-V128 A &B ' flow rate indication and valve control in control room). 3.6.2.1 If not already do,ne, THROTTLE BS pump's flows back to 1600 gpm per pump. This must be 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 DH-V6A & B f,om 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-VSA & B) from the BWST. 3.6.6 " REPOSITION" LPI flow control valves (DH-V128 A&B) 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 tFa following steps. 3.7.2 If not already done, " THROTTLE" HPI strings' flow rates back to1500 GPM per pump each using control valves NU-V16A, B, C, and D (flow rate indication and valve control in control rcom). 3.7.2.1 If not already done, THROTTLE B3 pump's flows cack to 1600 GPM per pump. This must be done prior to taking suction from the RB sump. 198 M8 10.2
~ 1 =. ~ 2202-1.3 Revision 1 06/22/77' 3.7.3 "0 PEN" valves DH-V7A and B in crossover line from LPI line to suction of HPI pumps (valve control and position indication in control room). " Reposition" HPI flow control valves (MU-V16A,B,C, & D) 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 & B) from RB sump automatically open at BWST level of 7'. 3.7.5 When suction valves from RB sump are fully open, "Close" the ECCS suction valves (DH-VSA & B) from the BWST. The ECCS is now in " piggy-back" operation. 3.7.6 Proceed to step 3.9. N0_TE: Once the ficx 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 from initiation of ECCS i.1jection, dependi_ng upon reason for string failure [i.e. - local LPI -failure or diesel failurel. Prior to actuation of the lo-lo level alarm, initiate the following steps. =- 3.8.2 Using the controls in the control room, attempt to " START UP" -the non-operating LPI String. 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 crcss-connect isolation valves (DH-V193 A & Bl as folicws: 3.8.3.1 ENSURE SM-V188 is closed then GPEN DH-Vll2 A & B o fill the inoperable string. ' l. 3kh 11.0 I
5 2202-1.3 Revisior. 1 06/22/77 NOTE: If offsite power is lost DHVl93 A & B must be manually opened. 3.8.3.2 Obtain t h keys for the CH cross-connect isolation valves' (DH-Vl93A and DH-Vl93B1 breakers frcm 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 DH vaults. 3.8.3.5 "0 PEN" the DH cross-connect isolation valve (.e.g. DH-V-193A(B)). next to the operating LPI 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 valve, "TbR0TTLE" either DH-V128A or DH-V1288 in the control room as required to achieve essentially equal ficw rates in octh D.H. i.'jection lines. (Approximately 1500 gpm per LP1 string). 3.8.3.8 If ficw 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 through each LPI string in ex55ss of 750 gpm using the cross-connect line befcre ECCS suction must be switched to the RB sump, than proceed to step 3.9.4. 3.8.4 If opening the DR cross-connect line fails to provide flow 'n each LPI string in excess of 750 gpm, then place one HPI string in a modified " Piggy-Back" mode with the operating LPI string as follows (assume LPI string "A"(_B) is the o$eratiag '198 3 0 string): 12.0
2202-1.3 } Revision 7 04/18/78 3.8.4.1 If nec already done, " THROTTLE" HPI string "A"(B) ficw rate back to 500 GPM using control valve MU-V16A and V16B. 3.8.4.2 " THROTTLE" LPI string "A"(B) flow rate to 3000 M using control valve DH-V128A(B). 3.8.4.3 "0 PEN" valve OH-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 DH-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 cmtrol room). 3.8.6 If not already done, THROTTLE BS pump ilows back to 1600 GPM + pump. This must be done prior to taking suction from the RB sump. 3.8.6.1 When the BWST level decreases to 7' VERIFY the ECCS suction valves (DH-V6A & B) froa RB sump automatically open. 3.8.7 W'len suction valves from RB sump are full open (position in{ cation in control room), "CLOSE" the ECCS suction valves (DH-VSA & B) from the BWST. 3.8.8 " REPOSITION" LPI flow control valve (s) (DH-,28A and/or B) as required to obtain proper string flowrates. (Flow rates could change due to change in suction sources). 3.9 WPen the Sodium Hydroxide Tank level reaches approximately 3 ft. "CLOSE" DH-V8A & B. 3.10 Actuate Environmental Barrier System by opening EB-Vil. 198 351 13.0
2 2 L. ?- 1. 3 Revision 11 9 10/06/78 ] 3.11 Within 24 hours of ECCS initiation, establish one of the long-term cooling circulation modes described in 2104-1.3 - Decay Heat Removal System, and listed below: Mode 1 Forced circulation usin] decay heat drop line. Mode 2 Gravity draining reactor coolant hot leg to the Reactor Building sump via the D.rt. 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 systens 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 instruct.ons and procedures for additional information as required. 1. Radiation emergency plan site emergency in the emergency plan. 2. 2104-5.4 - Control Building H'/AC. 14.0 }90 b
2202-1.3 - _i, Revision 7 i 04/18/78 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 8 SAFETY INJECTION GP. 1 SAFETY IfidECTION GP. 1 Equipment ESF Position Equipment ESF Position - DC-P-1A ON DC-P-1B ON . G2-12 (Note 1) CLOSED --027.-12 (Note 1) CLOSED - MU-P-1A (Note 2) ON MU-P-1B (Note 2) ON . NR-P-1A (Note 3) ON - NR-P-1C (Note 3) ON NS-P-lA (Note 4) ON - NS-P-1B (Note 4) ON TIE-2E2 OPEN 'T2E-lE2 OPEN _ T3E-4E2 OPEN T4E-3E2 OPEN - TllE-21E2 OPEN - T21E-llE2 OPEN DC-V96A CLCSED - DC-V96B CLOSED SAFETY INJECTION GP. 2 SAFETY INJECTION GP. 2 Equ i p:.ien t ESF Position Equipment ESF Position - NR-V9A CLOSED - NR-V9B CLOSED - DH-V4A OPEN - DH-V4B OPEN .;_OPEN - DH-V5B OPEN DH-VSA DH-V8A OPEN . DH-VJd OPEN DH-V100A < CLOSED . DH-V1008 CLOSED , DH-V102A OPEN -DH-V1028 OPEN MU-P-lB (Note 2) ON - MU-P-lc ON t -fiP.-V40A OPEN - tiR-V40B OPEN g NS-P-lC ON NS-P-lC (Note 4) ON T12-22E-2 OPEN T22E-12E-2 OPEN - MU-V28 CLOSED diY-V55 CLOSED 15.0 i
~ 2202-1.3 "s P,evision 3 TABLE A-1 12/30/77 ACTUATI0tM ACTUATIO:1 B _ SAFETY INJECTION GP. 3 W ilY INJECTION GP. 3_ Equipment ESF Position Equipment ESF Position vMU-Va6 CLOSED MU-V37 CLOSED 9 MU-V16A OPEN 'ilS-V32 CLOSED ,MU-V16B OPEN , flS-V67 CLOSED DH-P-1A-ON -DH-P-1B ON NR-P-18 (flote 3) ON - MU-V16C OPEN T31E-41E-2 OPEN -MU-V16D OPEN -NS-V84B CLOSED - fir-P-1 D (Note 3) Ofl -NR-V42A OPIN T41E-31E-2 OPE:1 -NS-V84A CLOSED -NR-V428 OPEN PANEL 3 Status Light Equipment E5F Position Indicator NS-V83A OPEN R ' NS-V8SB GPEN R - NS-V215 CLOSED G ' NS-V216 CLOSED G Diesel Generator Breaker will only be closed if Normel Power is lost; NOTE 1: otiierwise status indication wil. 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 's lost, MU-P-1B will be running, if the pump that it is selected to backup fails to start or is inoperable. 198 354 16.0 3
J:. l 2202-1.3 Revision.1 06/22/77 TABLE A-1 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; haviever, 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. -o 17.0
'5, 2202-1.3 Revision 7 ~ TABLE B-1 04/18/78 ESF EQUIPMENT - ESF POSITION Iti THE CONTRGL 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 ACTUATI0t; B SAFElf INJECTION GP. 1 SAFETY INJECTION GP. 1 Equipment ESF Position Equipment ESF Position DC-P-1A ON DC-P-1B ON G2-12 (flote 1) CLOSED G22-12 (Note 1) CLOSED MU-P-1A (Note 2) ON t'.U-P-1B (Note 2) ON NR-P-1A (Note 3) ON ilR-P-lC (?:ote 3) ON NS-P-1A (Note 4) ON NS-P-1B (Note 4) ON TIE-2E2 OPEN T2E-lE2 OPEti T3E-4E2 OPEN T4E-3E2 OPEN TllE-21E2 OPEN T21E-llE2 OPEN DC-V96A CLOSED DC-V96B CLOSED _ SAFETY INJdCTION GP. 2 SAFETY INJECTION GP. 2 _Ep3 p ent ESF Position Equipment ESF Position i tiR-V9A CLOSED itR-V9B CLOSED CH-V4A OPEN DH-V4B OPEN 0-LA OPEN DH-VSB OPEN ' DH-V8A OPEti DH-V8B OPEN DH-V100A C'.05ED DH-V1008 CLOSED DH-V102A OPEfl DH-V102B OPEN MU-P-1B (fote 2) ON tiU-P-lC Od f;R-V40A OPEN NR-V40B OPEN N3-P-lC Ofi i:S-P-lC (Nott 4) ON T12-22E-2 OPEN T22E-12E-2 OPEN HV-V55 j c 8 356 CLOSED tiU-V28 CLOSED i 18.0
a d ',. 2202-1.3 j, )" TABLE B-1 ACTUATION A ACTUATION B SAFETY INJECTION GP. 3 SAFETY IflJECTION GP. 3 Ecu_ipment ESF Position Equipment ESF Position MU-V36 CLOSED MU-V37 CLOSED MU-V16A OPEN NS-V32 CLOSED MU-V16B OPEN NS-V67 CLOSED DH-P-1A ON DH-P-1B ON NR-P-1B (Note 3) ON MU-Vl6C OPEN T31 E-41 E-2 OPEN MU-V16D OPEN NS-V84B CLOSED NR-P-lC (flote 3) ON l NR-V42A OPEN T41 E-31 E-2 OPEN NS-V84A CLOSED flR-V42B OPEN R.B. ISOLATION Arid COOLING GP. 1 R.B. ISOLATION AND COOLING GP 1 Equipment Position Eauipment 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 , CLOSED AH-V108 CLOSED CF-V144 CH-V3 CLOSED CF-V115 CLOSED f;M-VS2 CLOSED DH-V2 CLOSED NR-V5lA CLOSED flM-V104 CLOSED RR-V2A OPEN NR-V51B CLOSED RR-V2B PR-VSA OPEN RR-V2C OPEN RR-VSB OPEN RR-V2D GPEtt 198 357 19.0
~ '*s. 2202-1.3 Revision 3 TABLE B-1 12/30/77 ACTUATION A ACTUATION B R.B. ISOLATION & C00LIf;G GP. 1 R.B. ISOLATION & COOLING GP. 1 Equipment Position Equipment Position v RR-V5C OPEN -RR-V6C OPEN sSV-V55 CLOSED c RR-V6D OPEN - WDL-V1095 CLOSED . RR-V6E OPEN DC-Vll4 CLOSED - SV-V54 CLOSED v - WDL-V1092 CLOSED v DC-V103 CLOSED DC-V115 CLOSED R.B. ISOLATION & COOLING GP. 2 R.B. ISOLATION & C00LII;G GP. 2 Equipment Position Equipment Position AH-E-4A ON AH-E-4B ON AH-E-llA ON AH-E-llc ON < RR-V25C CLOSED -RR-V25C CLOSED v B5-VlA OPEN -BS-VlB OPEN - CA-V10 CLOSED - CA-V1 CLOSED -CA-V4A CLOSED -CA-V3 CLOSED - CA-V9 CLOSED -CA-V4a CLOSED v RR-P-1B ON CA-V8 CLOSED <WDG-Vl99 CLOSED -CA-V6 CLOSED " WDL-V22 CLOSED 'RR-P-lD ON WDL-Vll26 CLOSED - WDG-V2 CLOSED s AH-D4092A & B RECIRC - WDL-Vil25 CLOSED AH-040920 & E RECIRC -WDL-V271 CLOSED /ED-4098 AH-D4092A & B RECIRC AH-D4092D & E RECIRC ED-4098 RECIRC 198 358 20.0 E
2202-;,3 TABLE B-1 Revision 3 12/30/77 ACTUATION A ACTUATION B ~ R.B. ISOLATION & C00 lit!C GP. 3 R.B. ISOLATION & COOLING GP. 3 Equipment Position Equipment Position 'IC-V2 CLOSED 'IC-V3 CLOSED 'IC-V5 CLOSED - IC-V4 CLOSED MU-V2A CLOSED - MU-V376 CLOSED u - MU-V2B CLOSED MU 'il8 CLOSED - MU-V377 CLOSED - MU-V25 CLOSED - NS-V72 CLOSED - NS-V100 CLOSED '/ NS-V81 CLOSED - NF. P-2B ON . NR-P-2A ON
- RR-P-lc ON
- NR-V144A OPEN - RR-V25D CLOSED - RR-P-1A ON - RR-V25E CLOSED v RR-V25A CLOSED -AH-C-8A ON - RR-V2SB CLOSED -AH-E-llE ON IC-r.lA 0FF t.- AH-P-1 B ON "AH-C-uA ON -AH-V2A CLOSED t-AH-E-ll B ON "AH-V2B CLOSED ' AH-E lc O!' - AH-V3A CLOSED " AH-P-1A ON v AH-V3B CLOSED - AH-ViA CLOSED - AH-V6 CLOSED c A'i-VlB CLOSED v AH-V61 CLOSED ~ - AH-VU CLOSED vAH-V61 CLOSED i 'AH-V4B CLOSED -AH-V63 CLOSED AH-V5 CLOSED " AH-V71 CLOSED 'AH-V60 CLOSED IC-P-1B 0FF -AH-V102 CLOSED - AH-V72 CLOSED
- BS-P-1A ON
- BS-P-1B ON
- If RB Pressure >30 psig.
21.0 i
_~ o 2202-1.3 ' ~ ~.f, 'Q ~,. Revision 3 1. -, ' ~, - 12/30/77 NOTE 1: Diesel Generator Breaker will only 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 f e 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 start 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-1 A 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. PAdEL 8 Equipment ES Position Indication - DH-V7A(I) Close G ' DH-V7B(I) Close G - NS-V83A Open R - liS-V83B Open R -NS-V215 Cicse G NS-V216 Close G =- -CF-VlA Open R "CF-VlB Open R (I) This valve may have to be opened for " piggy-back" operation. Once, opened, the Position / Indication becomes Open/R. 22.0 198 360
~ ~~~'.,t.-!.s ~ 2202-1.3 J Revision 1 06/22/77 t PA!1EL 15 Eouipment ES Position Indication UI - 1H-V6A Close G UI Close G 'DH-V6B MU-V378(.2) Open R Ul - MS-V4A Open R 0) - MS-V48 Open R U)- - MS-7A Open R 01 - MS-V78 Ooen R U) This valve must be opened for sump-switchover. Once oper.ed, the Position / Indication becomes OPE?t/R. (I This valve should be cicsed at the operator's first chance. Once closed, the Position / Indication becomes CLOSE/W. (3) These valve.s 7Fould be closed when the steam syste'.; is secured. Once closed, the Position / Indication becomer CLOSE/G. PANEL 25 Eauioment ES Position Indica tien 'AH-E12A Off G 'AH-E12B Off G 'AH-E19A Off G ~- 'AH-E19B Off G 23.0 198 361 }}}