ML20204F730

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Rev 11 to Procedure 2.3.2.1, Panel Procedures Panel 903 Left
ML20204F730
Person / Time
Site: Pilgrim
Issue date: 06/10/1986
From:
BOSTON EDISON CO.
To:
Shared Package
ML20204F710 List:
References
2.3.2.1, NUDOCS 8608040292
Download: ML20204F730 (13)
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Text

BOSTON BEDISON ~

NUCLEAR OPERATIONS DEPARTMENT PILGRIM NUCLEAR POWER STATION Procedure No. 2.3.2.1 PANEL PROCEDURES PANEL 903 LEFT List of Effective Pages ,

2.3.2.1-1 l

2.3.2.1-2 2.3.2.1-3 2.3.2.1-4 2.3.2.1-5 2.3.2.1-6

) 2.3.2.1-7 2.3.2.1-8 2.3.2.1-9 2.3.2.1-10 2.3.2.1-11 2.3.2.1-12 Attachments "0"' Approv  ! 6M~d  %

Nu lehr Operations Manager Date G~ l C bh

! 2.3.2.i-i an . n 88Re%88!28e88anu PDR a

I

Ann. Actuating Set No ._ Engraving Device Point Operator Action A-1 Auto Blowdown Relays 2E-K1A; Loss of DC power 1. If bus "A" check the power supply from D-16 Power failure K1B; K13A; K13B; bus A or B (125V) through breaker 72-161 to D-4.

K13C; K9 2. If bus "B" check power supply from D-17 (125V) through breaker 72-175 to D-5.

3. Check fuses; see elementary 730E900.
4. Begin an orderly shutdown (T.S. 3.5.E.3)

A-2 Auto Blowdown Recorder 260-20 Safety Valves 1. Check recorder 260-20 on panel 921 to Relief Valve Leaking on Panel 921 203-4A determine which valve is leaking. ,

2'*

203-4B '

2. Check suppression chamber temperature l Safety Relief Valves recorder 9044 and temperature indicator 9019 203-3A on panel 903 for possible changes.

203-3B oo , 3. If the valve is leaking, manually exercise 203-3C and valve, not more than tour times.

203-3D 4. If the leakage causes noticeable water level fluctuation in the suppression chamber, scram the reactor and begin an orderly cooldown. l

5. If valve is stuck open and cannot be closed.

l reactor must be scrammed within 5 minutes I according to E0P-4.

l A-3 Auto Blowdown N/A Valves Bellows Leaking Bellows system is no longer operable.

A-4 RHR Pump A Auto Start Breaker Aux. Pump motor breaker 1. This alarm will come in any time the pump is l Contact closed running. i

2. Verify if one of the following initiation signals is present if pump was not manually started:
a. High drywell pressure, 2.5 psig
b. Low low reactor water level, -49" and reactor pressure, 400 psig If no initiation signal is present, stop the pump and investigate the reason for automatic start. j 2.3.2.1-2 Rev. 11 A3-2

nn. Actuating Set No. Engraving Device Point Operator Action 1- 5 RHR Pump C Auto Start Breaker Aux. Pump motor breaker 1. This alarm will come in any time the pump is Contact closed running.

2. Verify if one of the following initiation signals is present if pump was not manually started:
a. High drywell pressure, 2.5 psig
b. Low low reactor water level, -49" and reactor pressure, 400 psig ,

If no initiation signal is present, stop the l pump and investigate the reason for automatic '

start.

l- 6 RHR Pump A Trip or Breaker Aux. Pump motor breaker 1. Alarm comes in when the pump ts manually Inop Contact or Relay tripped with started, but immediately clears.

  1. 74 control switch in 2. Check for incorrect suction valve lineup.

start position 3. For trip check:

a. Breaker for overload targets.
b. Complete loss of bus voltage.
4. For inop check:
a. Breaker racked down.
b. D.C. knife blade open.
c. Breaker not charged.

1-7 RHR "A" Logic or Relays 10A-KIA or Loss of the auxi- 1. Check the power supply to 4160V bus, A-5.

Auxiliary Power 10A-K2A and 11ary power supply 2. Check the keylock switch 10A-S35A on panel failure auxiliary con- to bus A-5 or loss 932 in the cable spreading room to verify tacts from bus of the D.C. power that it is in the normal position.

A-5 feeder supply to bus A 3. Check the 125V D.C. bus "A" for loss of breaker power, also the 10 amp fuses 10A- FI A and 10A-F2A.

4. Refer to procedure 8.5.2.5. (LPCl System Inop) 3-8 RHR & Core Spray Relays 14A-K9A Reactor pressure 1. Verify that the reactor pressure is S 400, Injection 400 # or 14A-K9B 1 400 psig psig.

Permissive energized 2. If power is available to the breakers, and an initiation signal comes in, verify that the core spray system injects.

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2.3.2.1-3 Rev. 11 A3-3 .

Ann. Actuating Set N o . __ _ __ Engraving Device Point Operator Action A-9 High Drywell Pressure Pressure switches 1 2.5 psig 1. Check the drywell pressure indicator 9046 on CSCS Initiation 1001-90A through D on panel 903.

2. Verify CSCS initiation.
3. If two recirc. pumps are running, observe that loop selection logic isolates the selected recirc. pump.
4. Follow E0P-01 RPV Control Level & Pressure &

E0P-05 Primary Containment Control Pressure.

LA-10 Core Spray "A" Logic Relay 127-A5X or Loss of auxillary 1. Check keylock switch 14A-S11A for normal or Auxillary Power switch 14A-S11A power supply to bus position on panel 932.in the cable spreading failure A-5 or loss of D.C. room.

power supply to bus 2. Check power supply to 4160V bus A-5.

A 3. Check the 125V D.C. bus A for loss of power and check the fuses to the relay logic.

4. Refer to procedure 8.5.1.4. (Core Spray Sub-system Inop)

A-11 Core Spray "A" Break DPIS 1459A -1 (i 1.5) psid 1. Probable cause of alarm is inlet pipe failure.

Detection High -

2. If the Core Spray System has received an Pressure initiation signal, inject through the other loop if available and necessary.
3. If possible, shutdown the Core Spray System and verify pump discharge line break by checking the drywell for any temperature changes and the drywell floor sumps for an increase in pumping rate.
4. If no apparent problems are found, have the I&C lab recalibrate the DPIS switch 1459B located adjacent to rack 2207 in the CRD
mezzanine.

h i

2.3.2.1-4 Rev. 11 A3-4

on. Actuating Set so. Engraving Device Point Operat@r Action 12 Core Spray "A" Valve PS 1400-42A 400 psig 1. Indicates leakage back through the testable Leakage High Pressure check valve and M.0. valve 25A.

2. Close M.0. valve.24A and try to reset 25A M.O. valve.
3. Open test valve M.O. 4A to lower pressure to normal.
4. Assure that pressure in core spray piping does not exceed 600 psig.

0 2.3.2.1-5 Rev. 11 A3-5

! Ann. Actuating Set Engraving Device Point Operator Action lNo.

1

{ B-1 Auto Blowdown Timer Relays 2E-K5A & High drywell pres- 1. Observe annunciator panels for simultaneous Initiated 2E-K5B from pres- sure 1 2.5 psig low annunciator of high drywell pressure and low  ;

sure switches low reactor water low water level.

1001-89A through level -49" 2. Be aware that in 120 seconds, if these D and level indi- conditions still exist, and if a RHR and/or cating switch a core spray pump is running the relief 263-72A through D valves will lift.

3. If management decides to delay the opening of the relief valves longer than 120 seconds, push the two initiation timer signal reset pushbuttons on panel 903. With the initiating signals present, this operator action will delay the valve lifting for another 120 seconds.

B-2 Auto Blowdown Pressure switches 1 2.5 psig 1. Verify the high drywell pressure by observing High Drywell Pressure 1001-89A through D P.I. 9046 on panel 903.

Signal Sealed In 2. Check panels 932 and 933 to see if the monitor lights verify the alarm.

3. After the control room instrumentation indicates that the drywell pressure is < 2.5 psig push the two high drywell pressure reset pushbuttons and clear the alarm.

2.3.2.1-6 Rev. 11 A3-6

I Ann. Actuating Set No. Engraving Device Point Operat@r Action i Auto Blowdown P.S. 1001-93A 150 psig 1. Indicates that a core spray and/or a RHR lB-3 Permissive RHR/ Core through D and i 10 psig pump is running with > 150 psig discharge I Spray Pump Running P.S. 1001-104A pressure.

J through D for the RHR pumps. P.S.

. 1464A and B for i

the Core Spray

Pumps L...

l B-4 RHR Pump C Trip or Breaker aux. Pump motor breaker 1. Alarm comes in when the pump is manually J Inop contact or relay tripped with con- started, but immediately clears.

i #74 trol switch in 2. Check for incorrect suction valve lineup i start position 3. For trip check: l

a. Breaker for overload targets
b. Complete loss of bus voltage
4. For Inop check: ~
a. Breaker racked down
b. D.C. knife blade open
c. Breaker not charged

'85 RHR Pum A Overload Relay 151X > rated amperage on 1. If in test mode, shutdown the pump and l pump motor investigate.

i 2. Reduce load on pump by starting additional pumps, if available.

B-6 RHR Pump C Overload Relay 151X > rated amperage on 1. If in test mode, shutdown thu pump and pump motor investigate.

2. Reduce load on pump by starting additional pumps, if available.

2.3.2.1-7 Rev. 11 A3-7

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! Ann. Actuating Set

! NO . ___...Engraying Deelce Point Operator Action i B-7 RHR Discharge or P.S. 1001-74A, Pressure switches 1. Indicates leakage back through testable check

, Shutdown Cooling P.S. 1001-748, 1001-74A and B valve and M.O.28 and/or M.O.29A Loop or B actuate at<400 psig. Loop.

! Suction High P.S.1001-82 Pressure switch 2. Determine which loop is leaking by feeling ,

Pressure 1001-82 actuates at the pipes, then close the appropriate

<125 psig. valve either M.O.29A(B) or M.O.28A(B),

and attempt to reseal the normally closed f

valve.

3. Check temperature of pipes at installed ,

temperature surveillance points in the l A and/or B RHR valve rooms. '

l 4. Open M.O.34A(B) and crack open M0-36A(B) to lower pressure to normal.

5. Assure that pressure in RHR pumps does not exceed 600 psig.

] 6. Log times that alarm comes in. If alarm j frequency is greater than once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />,

issue an F&M Report and assess the I in-leakage *. If leakage is greater than 1

) gpm, initiate a controlled shutdown.

j *(Leakage assessment is performed per

]

TP-86-85).

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) 8-8 RHR H'x A or B Temp. recorder 125*F 1. Check recorder 2340-9 on panel 921.

i Outlet High Water 2340-9, temp. 2. This alarm is the RBCCW temperature leaving i Temp. element 1045A or B the HX; therefore check the RBCCW temp. to l the RHR HX and the RHR flow through the HX.

l Adjust as necessary.

~

~B ' Core Spriy~ Pump A Breaker aux. Pump motor breaker 1. This alarm will come in any time the pump is Auto Start contact closed running.

l 2. Verify if one of the following initiation i signals is present if pump was not manually l started:

! a. High drywell pressure, < 2.5 psig

.! b. Low low reactor water level, -49" and j reactor pressure, 400 psig j If no initiation signal is present, stop the pump and investigate the reason for automatic

, start.

~ ~ ~ ~ ~ ~ - - -

2.3.2.1-8 Rev. 11 j A3-8 i

--.~. - -

ann. Actuating Set l No. Engraving Device Point Operator Action i

B-10 Suppression Charber LS 5037 -6" 1. Stop transfer of torus tater to radwaste if l Low Water Level in progress.

! 2. If using automatic makeup, verify open A.O.

8001 valve is open and that the condensate transfer system is in service.

3. If not using automatic makeup, open A.O. 8000 valve locally and restore the level to normal.
4. Investigate the reason for low level.

!B-11 Co Spray Pump A Relay 151X > rated amperage 1. If in test mode, stop the pump and investigate l Overload on pump motor the cause of the alarm.

l 2. If an initiation signal is present, remove j the pump from service after the reactor water i level has been restored to normal.

l.__.____ _ __._.____

B-12 Core Spray Pump A Breaker aux. con- Pump motor breaker 1. Alarm comes in when the pump is manually 1

Trip or Inop tact or relay #74 tripped with con- started, but immediately clears.

trol switch in 2. Check for incorrect suction valve lineup.

start position 3. For trip check:

. a. Breaker for overload targets

b. Complete loss of bus voltage.
4. For Inop check:
a. Breaker racked down.
b. D.C. knife blade open.

j c. Breaker not charged.

i I

i '

j 2.3.2.1-9 Rev. 11 i

j A3-9

) -

i 1 -- ._ __. .-,

Actuating Set No. Engraving Device Point Operator Action C-1 RHR "A" Valve Overloads on the High current 1. If testing valves, immediately de-energize Overload following valves: the associated breaker.

1001-7A, 7C, 16A, 2. Visually check valves for fire hazard where 18A, 34A, 36A, 37A, possible.

43A and 43C 3. Investigate cause. l l

C. 2 RHR "A" Injection Overloads on the High current 1. If testing valves, immediately de-energize Valves Overload following valves: the associated breaker.

1001-28A, 1001-29A 2. Visually check valves for fire hazard where possible.

3. Investigate cause. .

C- 3 RHR Containment Overloads on the High current 1. If testing valves, immediately de-energize Spray "A" Injection following valves: the associated breaker.

Valves Overload 1001-23A, 1001-26A 2. Visually check valves for fire hazard where possible.

3. Investigate cause.

C- 4 RHR Loop B High P.S. 1001-83B & D Alarms at 1:0 psig 1. Indicates a high drywell pressure of > 1.0 Drywell Pressure Inc. Clear at 0.84 psig.

Spray Permissive psig dec. 2. It is a permissive signal, coincidental with l an initiation signal, to allow you to open the following spray valves: 1001-23B, i 1001-26B and 1001-378.

! 3. Attempt to reduce the drywell pressure rise I prior to its reaching 2.5 psig by cooling.

l venting, or spraying the suppression chamber.

4. Refer to the E0Ps.

Z-5 RHR In Test Status Relays 10A-K104A 1. Verify that a test jack is being used and a -

l and 10A-K1048 surveillance test is being performed.

! and switches 2. Indicates bypass is not reset. ,

) 10A-S45A & S45B 1

! 2.3.2.1-10 Rev. 11 l

A3-10

! Ann. Actuating Set

, No. Engraving Device Point Operator Action _

C.- 6 Containment Spray Switches 10A-S18A 1. Indicate that the keylock switch on panel 903

, Selector in/ manual and 10A-S18B is in the manual override position.

l override 2. With this keylock switch in the manual j override position and an accident condition 1 present with < 2/3 core coverage, you have a l permissive to spray the drywell and/or '

. suppression chamber. It also gives you a i permissive to go into suppression pool l cooling mode of operation.

l _ _ _ _

C-7 RHR Shutdown Cooling P.S. 261-23A Alarms at 100 psi 1. If increasing the reactor pressure and not in Mode High Reactor Inc. - clears at shutdown cooling mode, just acknowledge the Pressure Channel A 74 psi dec. annunciator.

2. If in shutdown cooling mode of operation, observe the following automatic actions:
a. If M.0. valves 1001-47, 50, 29 and/or 63 were open they will automatically close.

j b. If the RHR pumps were running in the j snutdown cooling mode, they will trip as the suction valve close.

L 8 RHR Shutdown Cooling P.S. 261-23B Alarms at 100 ps) 1. If increasing the reactor pressure and not in l Mode High Reactor Inc. - clears at shutdown cooling mode, just acknowledge the Pressure Channel B 80 pst dec. annunciator.
2. If in shutdown cooling mode of operation, I observe the following automatic actions:
a. If M.0. valves 1001-47, 50, 29 and/or 1001-60 were open they will automatically j close.

i b. If the RHR pumps were running in the l shutdown cooling mode, they will trip as the suction valve close.

I 1

2.3.2.1-11 Rev. 11 A3-ll i

! Ann. Actuating Set No. _,____ Engraving Device Point Operator Action J C .9 Reactor lo Lo Level L.I.S. 263-72A -49" 1. Observe the HPCI and RCIC Systems starting and CSCS Initiation through D injection.

Signal 2. Observe the start of the emergency diesel generators.

3. Observe tha starting of the RHR and Core Spray pumps in the reactor pressure is 1 400 i psig.

! 4. Follow the intent of E0P 1.

!C-10 Core Spray "A" Valves Overloads on High current 1. If testing valves, immediately de-energize j Overload 1400-3A and/or the associated breaker.

i 1400-4A 2. Visually check valves for fire hazard where possible.

3. Investigate cause.

C-11 Core Spray "A" Switches 14A-S11A High current 1. If testing valves, immediately de-energize the Injection Valves 1400-24A and/or associated breaker.

Overload 1400-25A 2. Visually check valves for fire fire hazard where possible.

3. Investigate cause.

L 12 Core Spray System Switches 14A-S11A 1. Initiated by operator action using the i A in Test Status S12A, S13A, S14A keylock switch on panels 93? and 933 in thu

! or SISA cable spreading room.

j Relay 14A-K24A 2. Also indicates test jack 14A-J1A and 14A-J1B are being used.

3. After the completion of a surveillance test, l verify that this alarm clears as this could inhibit the Core Spray response to an

)

initiating signal.

J. .

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j l

i 2.3.2.1-12 Rev. 11 l

1

! A3-12

l f

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(

t l

5 1

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! i I ATTACHMENT 4 l

l Temporary PNPS Procedure TP 86-85 4 ,

k RHR Intersystem Leakage Assessment j f i

j And Controlled Leakoff

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