ML072970079

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July-August Exam 50-325, 324/2007301 Final Simulator Scenarios (Scenario 3 of 4) (Section 4 of 5)
ML072970079
Person / Time
Site: Brunswick  Duke Energy icon.png
Issue date: 01/31/2007
From:
- No Known Affiliation
To:
Office of Nuclear Reactor Regulation
References
50-324/07-301, 50-325/07-301 50-324/07-301, 50-325/07-301
Download: ML072970079 (27)
v • d • e


Text

SCRAM CARD

  • ENSURE SCRAM VALVES ARE OPEN BY MANUAL "SC*RAM OR ARI TRIP

\ . CONTROL REACTOR PRESSURE BETWEEN 800 AND 1000 PSIG

. --: . .~-~

, \ ' .

  • CONTROL REACTOR VESSEL <;

LEVEL BETWEEN +170

  • <:"J .'

AND +200 INCHES

  • INSERT NUCLEAR INSTRUMENTATION
  • PLACE RECIRC PUMP SPEED CONTROLLERS TO'10%
  • ENSURE HEATER DRAIN PUMPS ARE TRIPPED
  • ENSURE TURBINE OIL SYSTEM OPERATING
  • PLACE SULCV I N SERVICE S/907

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  • 3.0 STEP BASES STEPS LPC-1 and LPC-2 LEVElJPOWER CONTROL LPC-l
  • A REACTOR SCRAM IS REQUIRED AND REACTOR POWER IS ABOVE 2',4 OR CANNOT BE DETERMINED
  • REACTOR WATER LEVEL IS LESS THAN 1G61NCHES
  • REACTOR PRESS IS ABOVE 1060 PSIG
  • ORYWELL PRESS IS ABOVE 1.7 PSIG
  • REACTOR SCRAM REQUIRED BY EOP- 02* pcep, EOP* 03- secp, OR EOp* 04- RRCP LPC-2
  • STEP BASES:

The Level/Power Control procedure (LPC) is entered from the Reactor Scram Procedure (RSP). The LPC is entered from the Primary Containment Control Procedure, Secondary Containment Control Procedure, or Radioactivity Release Control Procedure when Emergency Depressurization is required. In addition, the Reactor Flooding Procedure returns the operator to the LeveVPower Control procedure when reactor water level can be determined, and the reactor is not shutdown on control rods alone.

The conditions which require entry to Level/Power Control procedure are symptomatic of an emergency or conditions which, if not corrected, could degrade into an emergency. The entry conditions relate directly to the key parameters controlled in the RPV Control Guideline. The low reactor water level and high reactor pressure entry conditions are directly related to the sections for controlling these same two parameters. The high drywell pressure entry condition is indicative of a line break occurring in the drywell and thus relates to reactor water level control. A condition which requires a reactor scram coincident with the reactor not shutdown is indicative of a failure to scram, and thus relates directly to reactor power control. The reactor scram required by the Primary Containment Control Procedure, the Secondary Containment Control Procedure, or the Radioactivity Release Control Procedure, entry condition,

  • 1001-37.5 Rev. 8 Page 5 of 90 I
  • STEP LPC-5 IF A REACTOR SCRAM HAS NOT BEEN INITIATED THEN INSERT A MANUAL SCRAM LPC*5 I

STEP BASES:

This step specifically addresses the potential for multiple sensor and sensor relay failures in the automatic RPS logic where an automatic reactor scram should have initiated but did not. A manual scram is inserted to verify an automatic action which should have taken place.

  • 1001-37.5 Rev. 8 Page 8 of 90 I

STEPS LPC-6 through LPC-9 ARE YES ALL CONTROL RODS INSERTED TO OR BEYOND POSITION 00 TERMINATE BORON INJECTION LPC*7 YES GO TO "REACTOR VESSEL CONTROL PROCEDURE" IEOP* 01* RVCPI LPC*8 TABLE 5 SHUTDOWN WITHOUT BORON ONLY ONE CONTROL ROO NOT FULLY INSERTED NO MORE THAN 10 CONTROL RODS WITHDRAWN TO POSITION 02 AND NO CONTROL ROD WITHDRAWN BEYOND POSITION 02 AS DETERMINED BY REACTOR ENGINEERING STEP BASES:

Positive confirmation that the reactor will remain shutdown under all conditions is best obtained by determining that no control rod is withdrawn beyond position 00 (Maximum Subcritical Banked Withdrawal Position). The Maximum Subcritical Banked Withdrawal Position is defined to be the lowest control rod position to which all control rods may be withdrawn in bank and the reactor will, nevertheless, remain shutdown under all conditions. The reactor will also remain shutdown under all conditions with any control rod full-out and all other control rods full-in.

Other criteria may be employed to determine that the reactor will remain shutdown, such as compliance with the Technical Specification requirements governing control rod position and the allowable number of inoperable control rods, etc. The Nuclear Engineers are contacted in order to make this determination. Design calculations have determined that the reactor will remain shutdown under all conditions with 10 control rods withdrawn to position 02 and no control rod withdrawn beyond position 02. Table 5 has been added to the flow chart to provide an easy method of listing items which can be used to determine that the reactor will remain shutdown under all conditions without boron.

1001-37.5 Rev. 8 Page 9 of 90 I

STEP LPC-10

  • EXECUTE RCIL, RCfP AND RC/Q CONCURRENTLY LPC-10 STEP BASES:

Concurrent control of the three identified key reactor parameters is required when taking action to control and stabilize anyone, Reactor water level cannot be stabilized and maintained within a specified band if reactor pressure is oscillating. Reactor pressure cannot be stabilized and adequately controlled if reactor power is varying.

The thermodynamic and neutronic interrelationships between reactor power, reactor pressure, and reactor water level require that these three parameters be controlled concurrently.

The symptomatic approach to emergency response, upon which the EPGs are based, precludes being able to establish in advance a priority for executing any of the parallel action paths of the Level/Power Control procedure. Rather, current values and trends of parameters and the status of plant systems and equipment dictate the relative importance of individual Level/Power Control procedure steps and the relative priority with which each should be accomplished.

  • 1001-37.5 Rev. 8 Page 11 of 90 I
  • STEPS RC/Q-01 and RC/Q-02 RClQ*01 AFTER STEAM FLOW IS LESS THAN 3X10' LBlHR PLACE REACTOR MODE SWITCH TO SHUTDOWN RC/Q*02 STEP BASES:

When the reactor mode switch is placed in the SHUTDOWN position, a diverse and redundant reactor scram signal is generated by the RPS logic. Sets of contacts momentarily open which trip the RPS logic in the same manner as sensor or sensor relay contacts. However, placing the mode switch to the SHUTDOWN position can also produce an adverse plant response, i.e., if the mode switch is taken out of the RUN position prior to reactor pressure decreasing to 835 psig, the MSIV closure due to low main steam line pressure is prevented. However, if the mode switch is taken out of the RUN position when the steam flow is above 33%, (on Unit 2) the MSIVs will close.

Therefore, the operator is required to place the mode switch to the SHUTDOWN 6

position after steam flow has decreased to less than 3 x 10 Ib/hr on Unit 2 only. This equipment design does not apply on Unit 1.

  • 1001-37.5 Rev. 8 Page 77 of 90 I

STEP RCtO-03 IF ARI HAS NOT BEEN INITIATED THEN MANUALLY INITIATE ARI I RC/Q*03 STEP BASES:

Initiating ARI is an additional redundant means of inserting a scram. This may be sufficient to terminate the ATWS and shut down the reactor.

  • 1001-37.5 Rev. 8 Page 78 of 90 I

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NOTE Manpower Required: 1 Control Operator Special Equipment: 4 jumpers (15, 16, 17, and 18)

CO: 1. Unit 1 Only: ENSURE the REACTOR MODE SWITCH, C71-S1, is in *SHUTDOWN.*

CO: 2. Unit 2 Only: IF steam flow is less than 3 X 10 6 lb/hr, THEN ENSURE the REACTOR MODE SWITCH, C72-S1, is in "SHUTDOWN".

NOTE Steps 3 and 4 may be performed concurrently.

3. IF an automatic scram signal is present ANO power is available to the RPS bus, THEN INSTALL the following jumpers to bypass the reactor scram:

CO: a. Jumper 15 in Panel H12-P609, Terminal Board DD, from the right side of Fuse C71A(C72A)-F14A to Terminal 4 of Relay C71A(C72A) -K12E.

CO: b. Jumper 16 in Panel H12-P609, Terminal Board BB, from the left side of Fuse C71A(C72A)-F14C to Terminal 4 of Relay C71A(C72A)-K12G.

CO: c. Jumper 17 in Panel H12-P611, Terminal Board DO, from the right side of Fuse C71A(C72A)-F14B to Terminal 4 of Relay C71A(C72A)-K12F.

CO: d. Jumper 18 in Panel H12-P611, Terminal Board BB, from the left side of Fuse C71A(C72A)-F14D to Terminal 4 of Relay C71A(C72A) -K12H.

  • IOEOP-01-LEP-02 Rev. 25 Page 13 of 281

~ Section 3 - Continued

4. INHIBIT ARI by performing the following steps:

co: a. PLACE ARI AUTO/MANUAL INITIATION switch, Cll(C12)-CS-5560, to "INOP".

co: b. PLACE ARI RESET switch (spring return),

Cll(C12)-CS-5562, to "RESET" and MAINTAI~

for a minimum of five (5) seconds, THEN RELEASE.

co: c. VERIFY the red "TRIP" light located above ARI INITIATION, Cll(C12)-CS-5561 is off.

co: 5. ENSURE the DISCH VOL VENT & DRAIN TEST switch is in "ISOLATE".

6. VERIFY the following valves are closed:

co: a. DISCH VOL VENT VLV Cll(C12)-V139 co: b. DISCH VOL VENT VLV Cll(C12)-CV-F010 co: c. DISCH VOL DRAIN VLV Cll(C12)-V140

~ co: d. DISCH VOL DRAIN VLV Cll(C12)-CV-FOll co: 7. RESET RPS.

co: 8. IF RPS CANNOT be reset, THEN RETURN to Step C.G on Page 2.

co: 9. PLACE the DISCH VOL VENT & DRAIN TEST switch to "NORMAL" .

10. VERIFY the following valves are open:

co: a. DISCH VOL VENT VLV Cll(C12)-V139 co: b. DISCH VOL VENT VLV Cll(C12)-CV-F010 co: c. DISCH VOL DRAIN VLV Cl1(C12) -V140 co: d. DISCH VOL DRAIN VLV C11(C12)-CV-F011

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IOEOP-01-LEP-02 Rev. 25 Page 14 of 281

NOTE IF venting control rod over piston area in accordance with Section 6, THEN the AO should be notified so venting can be secured, prior to inserting a manual SCRAM.

co: 12. Manually SCRAM the reactor.

13. IF control rods moved inward, THEN PERFORM the following:

co: a. IF all control rods are inserted to or beyond Position DO, THEN RETURN to Step C.6 on Page 2.

co: b. IF all control rods are NOT inserted to or beyond Position DO, THEN RETURN to Step S on

  • co: 14.

Page 14 .

IF control rods DID NOT move inward, THEN RETURN to Step C.6 on Page 2 .

  • I OEOP-01-LEP-02 Rev. 25 Page 15 of 281

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RCIC OPERA TIONS FOR EOPs MANUAL RCIC INJECTION (OP-16 SECTION 5.3)

1. ENSURE THE F0 L LOW I NG VA LV ES ARE 0 PEN: E 5 1- V 8 (VALVE POS I TlON). E 51- V 8 (ACTUATOR POS I TI ON). AND E51-V9
2. OPEN E5 1- F0 4 6 i3. START V AC U U M PU,bLP AND LEA--VE SWITCH I N START.

i

4. OPEN E5 1- F04 5
5. OPEN E 5 1- F 013
6. ENSURE RC I C TURBI NE STARTS AND COMES UP TO SPEED AS DIRECTED BY RCIC FLOW CONTROL 7: ADJUST

. - .- .. -'" RC I C FLOW CONTROLLER TO OBTAIN DESIRED FLOW RATE.

S. ENSURE E 5 1- F0 19 I S CLOS ED WIT H FLO W ABOVE 80 GPM .

. 9. ENSURE THE F0 L LOW I NG VA LV ES ARE CLOS ED: E 5 1- F02 5.

E51-F026. E 51-FOO 4. AN D E 51-FOO 5 10: START SBGT (OP-10)

11. OPEN THE S GT - V 8 AND S G T - V 9
12. ENSURE BAR 0 MET RIC C N D S R CON DEN SAT E P U M POP ERAT ES RCIC PRESSURE CONTROL (OP-16 SECTION 8.2,)
1. ENSURE THE F0 L LOW I NG VALVES AREO PE N: E 5 1- V 8 (VALVE POSITION). E51-V8 (ACTUATOR POSITION) AND E51-V9.
2. OPEN E5 1- F 04 6
3. START VACUUM PUMP AND LEAVE SWITCH IN START.
4. ENSURE E 5 1- F0 1 3 IS CLOS ED
5. ENSURE E 4 1- F011 ISO PEN
6. THROTTLE OPEN E51-F022 UNTIL DUAL INDICATION IS OBTAINED
7. OPEN E5 1- F 04 5
8. THROTTLE OPEN E51-F022 OR ADJUST RCIC FLOW CONTROL. E51-FIC-R600. TO OBTAIN DESIRED SYSTEM PARAMETERS AND REACTOR PRESSURE.
9. ENSURE E51-F019 IS CLOSED WITH FLOW ABOVE 80 GPM.
10. ENSURE THE FOLLOWI NG VALVES ARE CLOSED: E 51- FO 25.

E51-F026. E51-F004. AND E51-F005.

11. START S BGT (OP-10)
12. OPEN THE SGT-V8 AND SGT-V9 1 ":l I:"I~I 101: 0 1\ 0 " ... A ,... .,.. ~ * ~ _ ** - - -

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HPCI INJECTION IN EOPs (OP-19 SE eTION 5.3)

1. ENSURE AUXILIARY OIL PUMP IS NOT RUNNING

~_ .2. ENSURE E41-V9-...AND

.... E41-V8 ARE CLOSED

3. QPEN E41-F059 4'~- ~*START VACUUM PUMP AND LEAVE IN START 5 .. OPEN E41-F001
  • 6.

7.

START AUXILIARY OIL PUMP AND LEAVE IN START OPEN E41-F006. IMMEDIATELY AFTER E41-V8 HAS DUAL INDICATION

8. ~NSURE E41-V9 AND E41-V8 ARE OPEN
9. ENSURE HPCI TURBINE COMES UP TO SPEED
10. ADJUST HPCI fLOW CONTROL. E41-fIC-R600 TO OBTAIN DESIRED FLOW RATE
11. ENSURE E41-F012 IS CLOSED WHEN FLOW HAS INCREASED ABOVE 800 GPM
12. ENSURE FOLLOWING E41 DRAIN VALVES ARE CLOSED: F 025. AND F026
13. START SBGT tOP-10) AND OPEN SGT-V8 AND

~r,T-Vq

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HPCI PRESSURE CONTROL'IN EOPs

, (OP-19 SECTION 8.2)

_ _ 1. HPCI AUTO INITIATION IS RESET

_ _ 2. _ AUXILIARY OIL PUMP IS NOT RUNNINI AND E41-V8 AND E41-V9 ARE CLOSED

.;~

_:_'_ I. OPEN E41-F011

__ 4.,0PIN E41-F069

_ _ S. START VACUUM PUMP AND LEAVE IN START

\.

_ _ 8. TI-.oTI\E OPEN E41-F008 TO MAINTAIN DESIRED REACTOR PRE8SURE

_ _ I. E41-V8 AND E41-V9 ARE OPEN

_ _ 10. E41-F012 18 CL08ED ,WHEN FLOW HA8 INCREA8ED ABOVE 800 GPM

_ _ 11. THE FOLLOWINI E41 DRAIN VALVE8 ARE CL08ED: F026. AND F026

_ _ 12. START 8B8T (OP-10) AND OPEN SGT-V8 AND SGT-V9

_ _ 11. BAROMETRIC CNDSR CONDENSATE PUMP IS OPERATING

14. ADJUST HPCI PARAMETERS BY THROTTLINI E41-F008 OR VARYING HPCI FLOW WITH THE FLOW CONTROLLER TO CONTROL REACTOR PRESSURE

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  • "i-'.s cErEc~ec Proceoure ll by t::-:e Rei::' sect:ic'n (20F'-Ol-R\lC?) I O?~

0:: t:be "React:o::- Vessel CODLrol

(~O?-Ol-L?C), OR

?s c;irected by the "Reactor Flooding Procedure" (EOP-OI-RXFP), OR

4. As directed by the "SAMG Primary Containment Flooding Procedure" (OSAMG-Ol) .

C. OPERATOR ACTIONS co: 1. ENSURE at least one CRD pump is operating.

CO: 2. IF the Reactor Building is accessible, THEN PERFORM Section 1 on page 4 of this procedure.

co: 3. IF the Reactor Building is NOT accessible, THEN PERFORM Section 2 on page 8 of this procedure .

I OEOP-01-SEP-09 Rev. 7 Page 3 of 10 I

Sect. 1 or: _

~anpowe~ ~eq~~~eG: Co~tYoi Opera~o:

2 Auxiliary Ope~ato~s Special SQ~i~~en: Nc~e The sysLem oesignation C1l is for Unit 1, and the system designation C12 is for Unit 2.

co: 1. IF two CRD pump operation is desired AND both ~RDsuctiDn filters AND both CRD drive water filters are available, THEN C01\TTINUE in this section at Step 3.

2. IF one CRD pump operation is desired OR IF limited to one pump operation, THEN PERFORM the following steps:
a. IF the standby CRD pump suction filter is available, THEN PLACE the standby filter in service as follows:

AO: (1) VERIFY that the standby eRD Pump Suction Filter AfB)

Drain Valve, CO-V315(V318), is CLOSED .

--..~ .'

AO:

AO:

(2)

(3)

VERIFY that the standby CRD Pump Suction Filter A(B)

Vent Valve, CO-V314(V317), is CLOSED.

VERIFY that the standby CRD Pump Suction Filter A(B)

Inlet Isolation Valve, CO-V305{V307), is OPEN.

NOTE The CO-V314 (V317) vent line is hard piped to the drain system, therefore water flow cannot be verified visually.

Opening the vent valve for approximately 60 seconds should remove most of the air trapped in the filter.

AO: (4) OPEN the standby CRD Pump Suction Filter A(B) Vent Valve, CO-V314(V317), for approximately 60 seconds, and THEN CLOSE the vent valve.

AO: (5) OPEN the standby CRD Pump Suction Filter A(B) Outlet Isolation Valve, CO-V308(V309).

I OEOP-01-SEP-09 Rev. 7 Page 4 of 10 I

Sec~ion _ {Con~in~edl

b. IF tnt? s~c.:!.<iD:,-,- c?~ p~~~\p. s*-.lc:io~ fil"L.e=:'* is NOT' availabl, 7HEN OPEi\: c~:rc ?w:np S~-ctio*~~ Fi ~ ~e~s 3y-pass "valve r CO-'l30*6_

co: c. ENSu"?E C?~D FLO~: CC'1:~TAOL, Cl.l(C12)-FC-P.600, is in the 1l~.A.~1l pos i ':: ie::1 .

d. TH?OTTL2 the :ol.lo\-.'2.ng valves, .as necessary, to *maintain charging water pressure greater than or equal to 8D0 psig bu~ as low as possible:

co: (l) The in-service FLOW CONTROL VLV, Cll(C12)-FOG2A{FOD2B} .

co: (2) DRIVE PRESSURE VLV, Cll{C12)-PCV-F003.

AO: (3) Charging Water Header Throttle Valve, Cll(C12}-F034 (Reactor Building, mastr flow control area., 20ft east) .

co: e. CONTINUE in this section at Step 4.

3. IF two CRD pump operation is desired AND both CRD -suction filters AND both CRD drive water filters are available,THEN PERFORM the following steps:
  • AO:

a .. PLACE the standby CRD pump suction filter in service as follows:

(1) VERIFY that the standby CRD Pump Suction Filter A(B)

Drain Valve, CO-V315(V31Bl, is CLOSED.

AO: (2) VERIFY that the standby CRD Pump Suction Filter A{B)

Vent Valve, CO-V314(V317), is CLOSED.

IOEOP-01-SEP-09 Rev. 7 Page 5 of 10 I

Sec~io~ 1 (Cc~~in~eo~

  • 7".r, *

--~\..; . ( 3) \J:2?I?"':.":' ~c ~

Inle: IS0~2~ic~

~r:e NOT~

s ~>:;. ::JGb~/ C;-.:=: ~'G-:-I;'

V61vE. CO--~30~i~307}, lS S1..:C ~ ~ 07:. ? i 1 i:E:Y OPEN.

].:a.. {B)

TOE CO-V314{V31i} ven~ line is n~rd piped to tne Grain sysTem, therefore wacer f~ow cannoe be verified visually.

Opening the vent valve for approximately 60 seconds should remove most of the air trapped in the filter.

AO: (4) OPEN the standby CRD Punlp Suction Filter A{B) Vent Valve, CO-V314(V317), for approximately 60 seconds and THEN CLOSE the vent valve.

AO: {5) OPEN the standby CRD PurnpSuction Filter A(B} Outlet Isolation Valve, CO-V308(V309).

AO: b. OPEN CRD Pump Suction Filters Bypass Valve, CO-V30:6.

c. PLACE the standby CRD drive water filter in service as follows:

AO: (l) VERIFY that the standby Drive Water Filter -A(B) Drain Valve, Cll{C12)-F023A{F023B), is CLOSED.

AO: (2) VERIFY that the standby Drive Water Filter A(B) Vent Valve, Cll(C12)-F022A(F022B), is CLOSED.

AO: (3) VERIFY that the standby Drive Water Filter A(B) Inlet Isolation Valve, Cll(C12)-F020A(F020B), is OPEN.

NOTE The Cll(C12)-F022A(F022B) vent line is hard piped to the drain system, therefore water flow cannot be verified visually. Opening the vent valve for approximately 60 seconds should remove most of the air trapped in the filter.

AO: (4) OPEN the standby Drive Water Filter A(B) Vent Valve, Cll(C12)-F022A(F022B), for approximately 60 seconds, and THEN CLOSE the vent valve.

AO: (5) OPEN the standby Drive Water Filter A(B) Outlet Isolation Valve, Cll(C12)-F021A(F021B).

co: d. START the second CRD pump.

IOEOP-01-SEP-09 Rev. 7 Page 6 of 10 I

(Continued)

Sec~ion ~

co: E.

THROT?LE ~~t =ollowin~ valves! as ~EceSSGr~;, ~o main~cii~

cha.rging ~~~-ate::- pressure a~ec.'[er Ll:c.;; 0:- Qw.al to 950 ps:g b~:=. as lo~/; as possib2.e:

co: (1) The in-service FLOW CONTROL VLV, Cll (C12) -F002AfF002B) .

co: .(2) DRIVE PRESSURE VLV, Cll(C12)-PCV-FD03.

AO: (3) Charging Water Header Throttle Valve, Cll(C12) -F034

{Reacr:::or Buil-ding, master flow control area, 20 ft

.east) _

AD: 4. MAKE UP from the MUD tank to the CST as necessary to maintain CST l~vel above 11 feet. (OP-31.2) co: 5. -WHEN CRD flow maximization is no longer required to maintain reactor vessel level, THEN PERFORM Section 3 on page 9 of this procedure .

I OEOP-01-SEP-09 Rev. 7 Page 7 of 10 I

  • 3.0 OPERATOR ACTIONS 3.1 Immediate A c t i o n s J ! ':'.~\,\:;;J" r_~r._. "~i-~t-" _.}~_.f:..,

3.1.1 IF a safety/relief valve is stuck open, THEN PER~tiiji;~~;::'

"'\~

th e f0 II oWlng:,t:~'i$'. ~; .

1. CYCLE the control switch of the affected safety/relief D valve to OPEN and CLOSE OR OPEN and AUTO several times.
2. ENSURE the affected safety/relief valve control switch is D left in CLOSE OR AUTO.

3.2 Supplementary Actions 3.2.1 IF suppression pool temperature increases to 110°F, THEN PERFORM the following:

1. INSERT a manual reactor SCRAM. o
2. REFER to 1(2)EOP-01-RSP. o
  • NOTE:

3.2.2 IF a safety/relief valve is stuck open, THEN PERFORM the following:

Pulling safety/relief valve fuses will de-energize the red and green indicating lights on Panel P601.

1. PULL the fuses in the order listed in Attachment 1 for the affected safety/relief valve.

o

2. MONITOR tailpipe temperatures using sonic readings on Panel XU-73 to determine the safety/relief valve position.

o

  • IOAOP-30.0 Rev. 13 Page 3 of 91
  • ATIACHMENT 1 Page 1 of 2 SRV Fuse Location/Number NOTE: The SRV fuses should be pulled in the listed order to ensure the power sensing relay is NOT required to shift.

Pane1H12-P628 SRV Fuse Location E.P. Number B21-F013A CC-F25 B21C-F7A CC-F34 B21C-F8A CC-F5 B21C-F3A CC-F14 B21C-F4A B21-F013B CC-F45 B21C-F7B CC-F46 B21C-F8B CC-F43 B21C-F3B

  • IOAOP-30.0 Rev. 13 Page 7 of 91
  • ATIACHMENT 1 Page 2 of2 SRV Fuse Location/Number Panel H12-P628 SRV Fuse Location E.P. Number B21-F013F CC-F51 (UNIT 1) B21C-F7F (UNIT 1)

CC-F49 (UNIT 2) B21 C-F7F (UNIT 2)

CC-F52 (UNIT 1) B21 C-F8F (UNIT 1)

CC-F50 (UNIT 2) B21 C-F8F (UNIT 2)

CC-F47 B21C-F3F CC-F48 B21C-F4F B21-F013G CC-F31 B21C-F7G CC-F40 B21C-F8G CC-F11 B21C-F3G CC-F20 B21C-F4G

  • IOAOP-30.0 Rev. 13 Page 8 of 91
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