ML072970064

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July-August Exam 50-325, 324/2007301 Final Simulator Scenarios (Scenario 3 of 4) (Section 2 of 5)
ML072970064
Person / Time
Site: Brunswick  Duke Energy icon.png
Issue date: 01/31/2007
From:
- No Known Affiliation
To:
Office of Nuclear Reactor Regulation
References
2007-301, 50-324/07-301, 50-325/07-301 50-324/07-301, 50-325/07-301
Download: ML072970064 (34)
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Text

  • NRC 2007 Simulator Scenario #3 Examiner Directed Triggers Lead Examiner directs the following Triggers:

Event 3:

Trigger 1: 2A Recirc Scoop Tube Lock (Following power manipulation while raising "A" Recirc flow)

Event 4:

Trigger 2: DG#3 Starting Air Pressure Low (Following Recovery from scoop tube lock)

Event 5:

Trigger 3: 2A NSW Pump Trip (Following Diesel General Tech Spec call)

  • Event 6:

Trigger 12: RCIC Mechanical Overspeed Trip (Following response to 2A NSW Pump Trip)

Event 7/8 Trigger 4: FW-V120 spurious open (Following RCIC Overspeed Trip response)

Trigger 5: Fuel Failure Event 13:

Trigger 9: SRV Tailpipe Failure (Following SW Rad Release Response)

Terminating Cue: When Emergency Depressurization has been performed, the scenario may be terminated .

8.22 Alternating Nuclear Service Water Pumps C Continuous Use 8.22.1 Initial Conditions

1. All applicable prerequisites as listed in Section 4.0 are []

met.

2. Service Water System is in operation in accordance with Section 5.2.

o 8.22.2 Procedural Steps NOTE: IF a Radwaste release is in progress AND the swapping of Nuclear Service Water Pumps is NOT a routine swap (i.e., taking longer than 1 or 2 minutes),

THEN the Radwaste release must be stopped.

1. IF the final number of operating Service Water Pumps will NOT be the same as the initial number of operating o

Service Water Pumps, THEN ENSURE a Radwaste radioactive release is NOT in progress.

2. PLACE mode selector switches for all operable Nuclear o Service Water Pumps in MAN.

CAUTION For pump protection, a Nuclear Service Water Pump should NOT be continuously operated with a flow rate of less than 2500 gpm or greater than 8000 gpm. A flow rate of 2500 gpm corresponds to a discharge pressure of 78 psig and a flow rate of 8000 gpm corresponds to a discharge pressure of 48 psig.

3. START Nuclear Service Water Pump B(A). D
4. CONFIRM discharge valve for the Nuclear Service Water Pump just started automatically opens.

o 1 20P -43 Rev. 124 Page 111 of 2161

  • 8.22.2 5.

Procedural Steps CONFIRM cooling water flow to Nuclear Service Water Pump motor just started has been established by observing discharge into the drain hub.

0

6. CONFIRM Nuclear Service Water Pump B(A) discharge 0 pressure is greater than 40 psig.
7. IF it is desired to maintain two Nuclear Service Water Pumps running for an extended period of time, THEN PLACE both Nuclear Service Water Pump mode switches in AUTO:

- NUC SW PUMP A D

- NUC SW PUMP B D

8. WHEN it is desired to stop a Nuclear Service Water Pump, THEN PERFORM the following:
a. ENSURE mode selector switches for all operable .0 Nuclear Service Water Pumps are in MAN.
  • b.

c.

STOP Nuclear Service Water Pump A(B).

CONFIRM discharge valve for Nuclear Service Water Pump just stopped automatically closes.

D D

d. WHEN Nuclear Service Header Pressure has stabilized, THEN PLACE both Nuclear Service Water Pump mode switches in AUTO:

- NUC SW PUMP A 0

- NUC SW PUMP B 0

9. COMPLETE Attachment 24. 0
  • ATIACHMENT 24 Page 1 of 1 Section 8.22, Alternating Nuclear Service Water Pumps Documentation C

Continuous Use Positionl Number Description Indication Checked Verified N/A Nuclear Service Water Pump 2A AUTO Selector Switch N/A Nuclear Service Water Pump 28 AUTO Selector Switch DatefTime Completed _

Performed By (Print) Initials Reviewed By: _

Unit SCQ

Unit 2 APP A-06 2-4 Page 1 of 2 FLUID DRIVE A SCOOP TUBE LOCK AUTO ACTIONS

1. M-G Set A scoop tube positioner locks in position last called for by the speed control system.

CAUSE

1. Fluid drive lube oil low pressure.
2. Fluid drive lube oil high temperature.
3. M-G Set A drive motor bus undervoltage.
4. Recirculation Pump A speed control signal failure.
5. Loss of power to the scoop tube positioner.
6. Manual trip.
7. Circuit malfunction.

OBSERVATIONS

1. FLUID DRIVE A LUBE OIL PRESS LO (A-06 1-3) alarm.
2. FLUID DRIVE A OIL TEMP HI (A-06 5-2) alarm.
3. 4KV BUS SYSTEM UNDERVOLTAGE (UA-06 6-10) alarm.

NOTE: Item 1, 2 or 3 will also cause a drive motor breaker trip.

4. SPEED CONTR A SIGNAL FAILURE (A-06 5-1) alarm.
5. Recirculation Pump A speed remains constant and may differ from Pump B.
6. Recirculation Pump A fails to respond to speed demand signal changes.

ACTIONS CAUTION If a recirculation Lunback occurs dULing a scoop tube lock condition, the affected M-G set will not run back.

1. If the M-G set drive motor breaker is tripped, refer to AOP-04.0.
2. Adjust the speed of Recirculation Pump B as necessary using OP-02 to keep pump speeds within 20% and jet pump loop flows within 10%

(maximum indicated difference 7.5 x 10 6 Ib/hr) when below 58 x 10 6 Ib/hr core flow or within 10% pump speed and jet pump loop flows within 5% (maximum indicated difference 3.5 x 10' lb/hr) when greater than or equal to 58 x 10 6 lb/hr core flow.

3. Verify that reactor power and core flow are within the limits of Flow Control Operational figures as specified in the COLR.

12APP-A-06 Rev. 45 Page 22 of 821

e e i e

ATTACHMENT 1 Page 2 of 3 Control Rod Movement Page I of -.!.'_ SRO Initials: v{

Control Correct Rod If Applicable, Control Rod Licensed Overtravel Full Out Second Licensed Rod Selected and OPT-14.1 Position Operator Check* Position Operator Verified**** Completed-** Check**

/0 *1-/3 'f / r JIA If({ To It, 't Jill AlIA L--

11-J{3 f /;.- JIA Iff To It, t AlIA ,JIA ~

tl2 -/1 r /}...;o AlIA tff To IC- Y ,iIA ,//4 ~

,0 -/1 ;r / l-- tJIA t/f To If" r JJhrJ JJh t..-

/ To 10 - II / JIA It, To JIg t/2.-- J! / Alh It, To 4~

1./2-t./3 / AlIA I' To J/ft

/0 -13 / AlIA Ito To J{ <J

/ To

  • WHEN a control rod is withdrawn to the Full Out position, either MAINTAIN the continuous withdrawal signal for at least 3 to 5 seconds OR APPLY a separate notch withdrawal signal, AND PERFORM the following rod coupling integrity check:

- CONFIRM rod full out light is not lost.

- CONFIRM rod position indication on the four-rod display indicates position 48,

- CONFIRM ROD DRIFT (A-OS 3-2) annunciator does NOT alarm,

    • VERIFY the rod reed switch position indicator corresponds to the control rod position indicated by the Full Out reed switch.
      • Applicable for control rods moved from intermediate to fully withdrawn position, Technical Specification SR 3.1.3.2 must be completed for these rods if NOT performed within the previous seven days. This surveillance requirement is NOT required to be performed until seven days after the control rod is withdrawn and thermal power is greater than the LPSP of RWM.
        • Concurrent Verification of rod selection required prior to rod movement.

I OGP-12 I Rev. 49 I Page 32 of 37 1

ATTACHMENT 1 Page 2 of 3 Control Rod Movement Page I of~___ SROlnitials: t1 Control Correct Rod If Applicable, Control Rod Licensed Overtravel Full Out Second Licensed Selected and OPT-14.1 Position Operator Check* Position Operator Rod Verified**** Completed*** Check**

/0 *1-/3 '( / r JIA tf l( To It. 't JIA JJIA L--

4l-J{3 '( /;'- JIA Iff To It. t AlIA AlIA "C-42 -/1 r /L-- J~ tff To It, y Ali, '//4 ~

10-/1 t / t-- tJIA J/f To It. .r- Alh llil) l.e-

/ To 10-11 / JIA I' To Jlt

'11- tl / 1Ii~ 10 To 4g.

~2* 43 / JIA To "'V-

/ 0 ~ 13 / AlIA "/~ To Jlf

/ To

  • WHEN a control rod is withdrawn to the Full Out position, either MAINTAIN the continuous withdrawal signal for at least 3 to 5 seconds OR APPLY a separate notch withdrawal signal, AND PERFORM the following rod coupling integrity check:
  • CONFIRM rod full out light is not lost.

- CONFIRM rod position indication on the four-rod display indicates position 48.

  • CONFIRM ROD DRIFT (A-OS 3-2) annunciator does NOT alarm.
    • VERIFY the rod reed switch position indicator corresponds to the control rod position indicated by the Full Out reed switch.
      • Applicable for control rods moved from intermediate to fully withdrawn position. Technical Specification SR 3.1.3.2 must be completed for these rods if NOT periormed within the previous seven days. This surveillance requirement is NOT required to be performed until seven days after the control rod is withdrawn and thermal power is greater than the LPSP of RWM.
        • Concurrent Verification of rod selection required prior to rod movement.

IOGP-12 I Rev. 49 I Page 32 of 37 1

Unit 2 APP A-06 2-4 Page 1 of 2 FLUID DRIVE A SCOOP TUBE LOCK AUTO ACTIONS

1. M-G Set A scoop tube positioner locks in position last called for by the speed control system.

CAUSE

1. Fluid drive lube oil low pressure.
2. Fluid drive lube oil high temperature.
3. M-G Set A drive motor bus undervoltage.
4. Recirculation Pump A speed control signal failure.
5. Loss of power to the scoop tube positioner.
6. Manual trip.
7. Circuit malfunction.

OBSERVATIONS

1. FLUID DRIVE A LUBE OIL PRESS LO (A-06 1-3) alarm.
2. FLUID DRIVE A OIL TEMP HI (A-06 5-2) alarm.
3. 4KV BUS SYSTEM UNDERVOLTAGE (UA-06 6-10) alarm.

NOTE: Item 1, 2 or 3 will also cause a drive motor breaker trip.

4. SPEED CONTR A SIGNAL FAILURE (A-06 5-1) alarm.
5. Recirculation Pump A speed remains constant and may differ from Pump B.
6. Recirculation Pump A fails to respond to speed demand signal changes.

ACTIONS CAUTION If a recirculation runback occurs during a scoop tube lock condition, the affected M-G set will not run back.

1. If the M-G set drive motor breaker is tripped, refer to AOP-04.0.
2. Adjust the speed of Recirculation Pump B as necessary using OP-02 to keep pump speeds within 20% and jet pump loop flows within 10%

(maximum indicated difference 7.5 x 10 6 Ib/hr) when below 58 x 10 6 lb/hr core flow or within 10% pump speed and jet pump loop flows within 5% (maximum indicated difference 3.5 x 10e lb/hr) when greater than or equal to 58 x 10 6 Ib/hr core flow.

3. Verify that reactor power and core flow are within the limits of Flow Control Operational figures as specified in the COLR.

12APP-A-06 Rev. 45 Page 22 of 821

Unit 2 APP A-06 2-4 Page 2 of 2 ACTIONS (Continued)

4. Verify power is available to the scoop tube positioner from Emergency 120V AC Distribution Panel 2A-TB, Circuit 2.
5. When the cause of the scoop tube lock has been corrected, refer to OP-02, to recovery from a scoop tube lock.

DEVICE/SET POINTS RX. Recirc. Aux. Relay B32-K5A Energized Temperature Switch B32-S001A-TS-2 210°F RX. Recirc. Aux. Relay B32-K619A 1 milliamp Pressure Switch B32-S001A-PS-l, 2 or 3 30 psig Scoop Tube Positioner B32-S002A Loss of power Device 27X 2912 volts POSSIBLE PLANT EFFECTS

1. Speed mismatch between recirculation pumps.
2. Loss of recirculation M-G Set A.

REFERENCES

1. LL-9364 - 89
  • 2.

3.

4*

FP-5572, sh 2 AOP-04.0, Low Core Flow.

OP-02, Reactor Recirculation System

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8.4 Recovery from Scoop Tube Lockout C Continuous Use 8.4.1 Initial Conditions

1. Annunciator FLUID DRIVE A(B) SCOOP TUBE LOCK, D A-6 2-4 (A-7 1-6), is actuated.
2. Lockout bus power is available. D
3. The cause of the scoop tube lockout has been corrected. D
4. Plant conditions have stabilized. D 8.4.2 Procedural Steps
1. CHECK RECIRC RUNBACK A(B) light is off. D

, . "~ (':

CAUTION

,~

A flow transient will occur if there is a difference in actual Recirculation Pump speed and the speed demand signal from the flow controller OR if a runback signal is present when the scoop tube lockout is reset.

CAUTION .

The lockout condition should be cleared and the lockout reset as soon as possible due to loss of runback capabilities on the affected Recirculation Pump. IF a recirculation runback occurs and causes an excessive speed mismatch between pumps, THEN the Recirculation Pump with a scoop tube lock should be tripped.

2. ADJUST the potentiometer on the affected RECIRC PUMP 2A(B) SPEED CONTROL until the speed demand signal has settled out and is nulled with the actual pump speed as required by the following guide-lines.
a. IF the lockout was MANUALLY initiated for a D SHORT duration with STABLE plant conditions then no adjustment is required.
b. IF step 8.4.2.2.a is NOT applicable THEN D REQUEST assistance from I&C in adjusting the controller to a nulled condition.

1_2_o_p_-_o_2 L..-.. R_e_v._1_2_6____ Page 59 of 1531

  • 8.4.2 3.

Procedural Steps OBSERVE the affected pump speed, loop flow and core flow for changes that would indicate a speed change when the scoop tube is unlocked.

o NOTE: IF flow controller operation is unstable when the scoop tube lockout is reset, THEN it may be necessary to manually lock out the affected scoop tube.

4. PLACE SCOOP TUBE A (B) LOCK switch to RESET. o
5. CHECK flow conditions stable. o
6. CHECK annunciator FLUID DRIVE A (B) SCOOP TUBE LOCK, A-6 2-4 (A-7 1-6), is clear.

o

7. WHEN both Recirculation Pumps are reset, THEN ADJUST flow as directed by the Unit seo.

o

  • 1 20 P-02 Rev. 126 Page 60 of 1531

Unit 2 APP UA-21 6-2 Page 1 of 1 DG-3 LO START AIR PRESS AUTO ACTIONS NONE CAUSES

1. Air compressor malfunction.
2. Air leaks on Starting Air System.
3. Circuit malfunctions.

OBSERVATIONS

1. Low starting air pressure indication on diesel generator control panel (less than 235 psig) .
2. LOW STARTING AIR PRESSURE alarm on local diesel generator control panel.

ACTIONS

l. Verify that diesel generator starting air compressors are running.
2. Check for air leaks.

J. Check for proper air compressor operation per OP-39, Diesel Generators.

4. If air leaks exist or a circuit malfunction is suspected, ensure that a WRjJO is prepared.

DEVICEjSETPOINTS DG-PSL-6536-3 (air pressure switch) 235 psig DG-PSL-6537-3 (air pressure switch) 235 psig POSSIBLE PLANT EFFECTS

1. Loss of diesel generator may result in technical specification LCO.

REFERENCES

1. 9527-LL-9358 - 15
2. Technical Specifications 3.8.1, 3.8.2
3. OP-39, Diesel Generators
  • BUS E3 4KV MOTOR OVLD Unit 2 APP UA-17 6-1 Page 1 of 2 AUTO ACTIONS NONE CAUSE
1. Motor overload in one of the following motors:
a. RHR Pumps 1A and/or 2A (Breakers AI8 and AJ1)
b. RHR SW Pump 1A and/or 2A (Breakers AI9 and AI?)
c. Core Spray Pump 2A (Breaker AI6)
d. CRD Pump 2A (Breaker AJ2)
e. Conventional Service Water Pump 2A (Breakers AJ4)
f. Nuclear Service Water Pump 2A (Breaker AJ3)
2. Circuit, electrical, or mechanical malfunction OBSERVATIONS
l. Annunciator CORE SPRAY PUMP 2A OVERLOAD (A-01 6-6)_
2. Annunciator RHR SW PUMP 2A OVERLOAD (A-01 2-9).

3 _ Annunciator RHR PUMP 2A OVERLOAD (A-01 4-8).

4. Unit 1 Annunciator RHR SW PUMP 1A OVERLOAD (A-01 2-9)_
5. Unit 1 Annunciator RHR PUMP 1A OVERLOAD "(A-01 4-8).

ACTIONS

1. Direct Auxiliary Operator to Bus E3 switchgear to confirm which pump has an overload condition.
2. If in other than an emergency condition, shift to alternate equipment, if feasible, per applicable operating procedure.
3. If applicable, refer to appropriate annunciator and operating procedure for further action.

DEVICE/SETPOINTS 51 Reference respective equipment annunciators

  • POSSIBLE PLANT EFFECTS Unit 2 APP UA-17 6-1 Page 2 of 2
1. Loss of essential equipment during an emergency condition.
2. Severe damage to motors of applicable pumps.
3. Loss of safety equipment may result in a Technical Specification LCO.

REFERENCES

1. LL-9358 - 8
2. LL-9047 - 49
3. lAPP A-Ol
4. 2APP A-Ol

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Unit 2 APP UA-01 1-10 Page 1 of 2 NUCLEAR HDR SERV WTR PRESS-LOW AUTO ACTIONS

1. If the nuclear service water header pressure decreases to 40 psig, the standby nuclear service water pump selected to AUTO will start.
2. If a standby conventional service water pump is selected to the nuclear header and AUTO and the nuclear header pressure decreases to 40 psig, then that conventional service water pump will start.

CAUSE

1. Nuclear or conventional service water pump tripped.
2. Nuclear or conventional service water pump strainer clogged.
3. Improper valve alignment.
4. System piping failure.
5. Circuit malfunction.

OBSERVATIONS

  • 1.

2.

3.

NUCLEAR HDR SW PUMP A(B) TRIP [UA-01 2-10(4-10)} alarm.

Service water nuclear header pressure, as indicated on SW-PI-143-1 on RTGB Panel XU2, indicating less than or equal to 42 psig.

NUC SW PUMP STRAINER A(B) DIFF-HIGH [UA-01 3-1 0(5-1 O)} alarm.

ACTIONS

1. If the standby service water pump did not automatically start, start the pump.
2. If the service water pump strainer is not automatically backwashing, start the strainer backwashing.
3. Check the valve lineup.
4. If a circuit or equipment malfunction is suspected, ensure that a WRIJO is prepared.
5. If the nuclear service water header pressure cannot be maintained above 40 psig, refer to OAOP-18, Nuclear Service Water System Failure.

DEVICE/SETPOINTS Pressure Switch SW-PSL-142 42 psig

Unit 2

  • POSSIBLE PLANT EFFECTS APP UA-01 1-10 Page 2 of 2
1. Reduced cooling capability of systems using nuclear service water.

REFERENCES

1. LL-9352 - 22
2. OAOP-18, Nuclear Service Water System Failures
3. APP UA-01 2-10 (4-10), NUCLEAR HDR SW PUMP A (B) TRIP
4. APP UA-01 3-10 (5-10), NUC SW PUMP STRAINER A (B) DIFF-HIGH

c c*

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Unit 2 APP UA-01 2-10 Page 1 of 2 NUCLEAR HDR SW PUMP A TRIP AUTO ACTIONS

1. If the nuclear service water header pressure decreases to 40 psig, the standby nuclear service water pump selected to AUTO will start.
2. If a standby conventional service water pump is selected to the nuclear header and AUTO and the nuclear service water header decreases to 40 psig, that conventional service water pump will start.

CAUSE

1. Overcurrent (12 amps with 12 second time delay, 20 amps instantaneous).
2. Circuit malfunction.

OBSERVATIONS

1. Nuclear Service Water Pump A status light, as indicated on RTGB Panel XU2, turns green.
2. Nuclear service water header pressure, as indicated on SW-PI-143-1 on RTGB Panel XU2, decreasing.
3. If the nuclear service water header pressure decreases to 42 psig, NUCLEAR HDR SERV WTR PRESS-LOW (UA-01 1-10) alarm.

ACTIONS

1. If the standby nuclear or conventional service water pump did not automatically start, start the pump.
2. If the vital service water header loses pressure due to the pump trip and cannot be restored, transfer the vital header supply to the conventional header.
3. Check the phase current transformers.
4. Check the lock-out relay.
5. Verify Nuclear Service Water Pump 2A discharge SW-V19 closes.
6. If a circuit or equipment malfunction is suspected, ensure that a WR/JO is prepared.

DEVICEISETPOINTS Overcurrent Relays SO/51 12 amps with 12 second time delay 20 amps instantaneous Lock-out Relay 86 Relay 74 Energized

!2APP-UA-01 Rev. 57 Page 37 of 1021

Unit 2 APP UA-01 2-10 Page 2 of 2 POSSIBLE PLANT EFFECTS

1. Reduced cooling capability of systems using nuclear service water.
2. If Nuclear Service Water Pump A is inoperable, a technical specification LCO may result.

REFERENCES

1. LL-9352 - 22
2. Technical Specification 3.7.2
3. APP UA-01 1-10, NUCLEAR HDR SERV WTR PRESS-LOW

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  • 2.0 2.1 AUTOMATIC ACTIONS NSW pump selected to AUTO starts AND discharge valve opens.

0 2.2 CSW pump(s) selected to AUTO on the NSW Header starts 0 AND discharge valve to NSW Header opens 2.3 IF diesel generators are operating, THEN cooling water valves 0 may shift to the opposite unit NSW Header.

2.4 IF RHR SW pumps are operating on the NSW Header, THEN 0 the pumps may trip on low suction pressure.

3.0 OPERATOR ACTIONS 3.1 Immediate Actions None 3.2 Supplementary Actions

  • 3.2.1 1.

IF NSW Header pressure remains low after additional pumps are started, THEN PERFORM the following to reduce flow:

REDUCE service water flow to RBCCW heat exchangers.

0 NOTE: A minimum flow rate of 4500 gpm is required for containment cooling during accident conditions.

2. REDUCE RHR SW flow. o
  • IOAOP-18.0 Rev. 20 Page 3 of 11 I

Unit 2

  • APP A-03 5-3 Page 1 of 2 RCIC TURBINE TRIPPED AUTO ACTIONS
1. RCIC turbine trips as follows:
a. If open, the Turbine Trip And Throttle Valve, E51-VS, trips closed.
b. If open, the RCIC Injection Valve, E51-F013, closes.
c. If open, the Minimum Flow Bypass To Suppression Pool Valve, E51-F019, closes.

CAUSE

1. Mechanical overspeed trip (5625 rpm).
2. High turbine exhaust pressure (50 psig).
3. Low RCIC pump suction pressure (15 inches Hg vacuum).
4. RCIC Isolation Trip Signal A.
5. RCIC Isolation Trip Signal B.
6. Turbine trip push button.
7. Circuit malfunction.

OBSERVATIONS NOTE: Once the turbine trips, exhaust pressure and suction pressure will

  • 1.

2.

3.

return to zero or a positive value .

Turbine speed (E51-C002-2).

Turbine exhaust pressure greater than 50 psig (E51-PI-R603).

RCIC pump suction pressure less than 15 inches Hg vacuum (E51-PI-R604) .

4. Isolation Signal A indicating light.
5. Isolation Signal B indicating light.
6. Turbine Trip And Throttle Valve, E51-VS, closed.
7. RCIC Injection Valve, E51-F013, closed.

S. Minimum Flow Bypass To Suppression Pool Valve, E51-F019, closed.

9. RCIC TURB EXH PRESS HI (A-03 2-3) alarm.
10. RCIC PUMP SUCTION LO PRESS (A-03 4-3) alarm.
11. RCIC ISOL TRIP SIG A INITIATED (A-03 5-2) alarm.
12. RCIC ISOL TRIP SIG B INITIATED (A-03 6-2) alarm.

ACTIONS

1. If the RCTC turbine tripped on mechanical overspeed and the RCIC System is required, reset the mechanical overspeed per OP-16 and operate RCIC in accordance with OP-16 or the Emergency Operating Procedures (EOPs) .

Unit 2 APP A-03 5-3 Page 2 of 2 ACTIONS

2. If the turbine tripped on high turbine exhaust pressure, refer to APP A-03 2-3.
3. If the turbine tripped on low RCIC pump suction pressure, refer to APP A-03 4-3.
4. If the turbine tripped on Isolation Signal A, refer to APP A-03 5-2.
5. If the turbine tripped on Isolation Signal B,refer to APP A-03 6-2.
6. If a circuit malfunction is suspected, ensure that a WR/JO is prepared.

DEVICE/SETPOINTS RCIC Auxiliary Relay E5I-K20 (actuated from Energized Turbine Trip And Throttle Valve, E5I-V8)

Turbine Speed 5625 rpm Turbine Exhaust Pressure Switch E5I-PSH-N009A 48-52 psig*

Turbine Exhaust Pressure Switch E5I-PSH-N009B 48-52 psig*

RCIC Pump Suction Pressure Switch E5I-PSL-N006 15 inches Hg vacuum

  • Pressure in turbine exhaust line POSSIBLE PLANT EFFECTS
1. If the RCIC System is inoperable, a Technical Specification LCO may result .
  • REFERENCES 1.

2.

3.

4.

LL-9364 - 48 Technical Specification OP-I6, RCIC System APP A-03 2-3, RCIC TURB 3.5.3 EXH PRESS HI

5. APP A-03 4-3, RCIC PUMP SUCTION LO PRESS
6. APP A-03 5-2, RCIC ISOL TRIP SIG A INITIATED
7. APP A-03 6-2, RCIC ISOL TRIP SIG B INITIATED

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8.3 Mechanical Overspeed Reset R Reference Use 8.3.1 Initial Conditions

1. The RCIC turbine has tripped due to the mechanical overspeed trip device.

o 8.3.2 Procedural Steps NOTE: Resetting of the mechanical overspeed trip device is accomplished locally at TURBINE TRIP & THROTTLE VLV, E51-VB.

." " 1 CAUTION IF the RCIC turbine trips on an overspeed condition, THEN TURBINE TRIP &

THROTTLE VLV, ES1-VB, should NOT be reset until turbine speed is less than 4000 '

rpm.

1. IF open, THEN CLOSE TURBINE TRIP & THROTTLE 0 VL V motor actuator.
2. PUSH OR PULL, depending on body position, the 0 emergency connection rod against spring pressure in the direction of TURBINE TRIP & THROTTLE VLV, E51-VB, (approximately 1 inch).
3. OBSERVE the tappet assembly, which resembles a 0 plunger, drop into place.
4. IF the tappet assembly does NOT drop in place, THEN 0 L1GHTLY depress the assembly.
5. RELEASE the emergency connection rod AND ENSURE 0 the head lever is resting against the flat on the tappet nut. (There should be approximately 1/16 inch of engagement. )
6. IF the mechanical overspeed trip device did NOT reset, 0 THEN CONTACT the Control Room for further instructions.

1 20 P -16 Rev. 98 Page 34 of 791

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  • 5.0 5.1 STARTUP Standby DatelTime Started _

C Continuous Use 5.1.1 Initial Conditions Initials

1. All applicable prerequisites as listed in Section 4.0 are met.
2. Suppression pool level is between -27 and -31 inches.
3. Condensate Storage Tank level is greater than 10 feet.
4. RCIC discharge piping is filled and vented in accordance with Section 8.1.

5.1.2 Procedural Steps

1. DEPRESS INITIATION SIGNAURESET, E51-S18,
  • push button.
2. ENSURE RCtC INITIA TlON SIGNAL sealed-in I indicating light is off. Ind.ver.
3. DEPRESS ISOLA TlON SIGIRESET AUTO SYSTEM A, E51-S25, push button.
4. DEPRESS ISOLA TlON SIGIRESET MA NUAUA UTO SYSTEM B, E51-S16, push button.
5. ENSURE isolation signal does NOT exist by checking the following annunciators are clear:
a. RCIC ISOL TRIP SIG A INITIATED (A-3, 5-2) _1-IndVer.
b. RCIC ISOL TRIP SIG B /NITIA TED (A-3, 6-2) _1-Ind.Ver.
6. ENSURE BAROMETRIC CNDSR VACUUM PUMP I-control switch in AUTO and pump is NOT running.

IndVer.

  • 5.1.2 7.

Procedural Steps ENSURE BAROMETRIC CNDSR CONDENSATE PUMP control switch in AUTO and pump is NOT running.

/

IndVer.

8. ENSURE TURBINE SPEED TEST SELECTOR switch /

in NORMAL. IndVer.

9. ENSURE TURBINE TEST POWER control switch /

in OFF. IndVer.

10. ENSURE RCIC FLOW CONTROL, E51-FIC-R600, is as follows:
a. In automatic (A) position. I IndVer.
b. Setpoint set at 400 gpm. I IndVer.
c. Yellow ALM light off. I Ind.Ver.
d. Red FAIL light off. I Ind.Ver.
11. ENSURE the following valves are in the position indicated:
a. SUPPL Y DRAIN POT INBD DRAIN VL V, I E51-F025, is open. Ind.Ver.
b. SUPPL Y DRAIN POT OTBD DRAIN VL V, I E51-F026, is open. IndVer.
c. COND PUMP DISCH INBD DRAIN VL V, _1-E51-F004, is closed. IndVer.
d. COND PUMP DISCH OTBD DRAIN VL V, I E51-F005, is open. Ind.Ver.

5.1.2 Procedural Steps CAUTION During normal operation MAIN STEAM DRAIN VL V, MVD-F021, will be closed with reactor pressure greater than 150 psig, as directed by EC 47894. During a plant ,.:

shutdown the valve may be opened to aid in reactor cooldown in accordance with OGP-05.

e. MAIN STEAM DRAIN VL V, MVD-F021 , is closed.
12. ENSURE TURBINE GOVERNOR VALVE, E51-V9, is I open. Ind.Ver.
13. ENSURE TURBINE TRIP & THROTTLE VLV I-(Actuator Position), E51-VB, is open.

Ind.Ver.

14. ENSURE TURBINE TRIP & THROTTLE VL V (Valve I Position), E51-VB, is open. IndVer.
15. ENSURE MIN FLOW BYPASS TO TORUS VL V, I E51-F019, is closed. IndVer.
16. ENSURE BYPASS TO CST VL V, E51-F022, is I closed. Ind.Ver.
17. ENSURE TURBINE EXH VAC BKR VLV, E51-F066, I is open. IndVer.
18. ENSURE TURBINE EXH VAC BKR VLV, E51-F062, _l-is open. IndVer.
19. ENSURE CST SUCTION VLV, E51-F010, is open. I Ind.Ver.
20. ENSURE TORUS SUCTION VLV, E51-F031, is /

closed. Ind.Ver.

21. ENSURE TORUS SUCTION VLV, E51-F029, is /

closed. IndVer.

120P-16 Rev. 98 Page 12 of 791

  • 5.1.2 22.

23.

Procedural Steps ENSURE PUMP DISCHARGE VL V, E51-F012, is open.

ENSURE TURBINE STEAM SUPPL Y VL V, I

IndVer.

I E51-F045, is closed. Ind.Ver.

24. ENSURE RCIC INJECTION VLV, E51-F013, is I closed. IndVer.
25. ENSURE COOLING WA TER SUPPL Y VL V, I E51-F046, is closed. Ind.Ver.
26. IF the RCIC steam line has already been warmed and pressurized, THEN PERFORM the following steps:
a. ENSURE STEAM SUPPL Y OUTBOARD ISOL _1-VLV, E51-F008, is open. IndVer.
b. ENSURE STEAM SUPPL Y INBOARD ISOL I VLV, E51-F007, is open. IndVer.
c. ENSURE SUPPL YDRAIN POT DRAIN BYP I VLV, E51-F054, is closed. Ind.Ver.
27. IF the RCIC steam line has NOT been warmed and pressurized, THEN PERFORM the following steps:
a. ENSURE STEAM SUPPL Y OUTBOARD ISOL VLV, E51-F008, is closed.
b. ENSURE STEAM SUPPL Y INBOARD ISOL VLV, E51-F007, is closed.
c. IF the RCIC steam supply line was depressurized in accordance with Section 8.4, THEN PERFORM the following:

OPEN SUPPL Y DRAIN POT INBD I DRAIN VLV, E51-F025. IndVer.

OPEN SUPPL Y DRAIN POT OTBD I DRAIN VLV, E51-F026. IndVer.

d. OPEN STEAM SUPPL Y OUTBOARD ISOL _1-VLV, E51-FOO8.

IndVer.

120P-16 Rev. 98 Page 13 of 791

5.1.2 Procedural Steps NOTE: Turbine steam inlet pressure should be monitored on E51-PI-R602 on Panel P601.

I.

CAUT10N Anytime the RCIC steam line has been isolated with the reactor pressurized, it should be slowly warmed and pressurized to prevent a water hammer when the system initiates.

WHEN throttling STEAM SUPPL Y INBOARD ISOL VLV, E51-F007, THEN no more than three jogs should be used without waiting at least 5 minutes before the next jog or series of jogs. Each jog should last at least 1 second and 15 seconds should elapse be~eenjogs. - ,

e. SLOWLY THROTTLE OPEN STEAM SUPPL Y INBOARD ISOL VLV, E51-F007.

NOTE: The supply drain pot effluent and supply drain pot bypass effluent are routed to the main condenser.

f. WHEN RelC steam line pressure equals reactor pressure, THEN FULLY OPEN STEAM SUPPL Y INBOARD ISOL VL V, E51-F007.
g. ENSURE STEAM SUPPL Y INBOARD ISOL 1 VL V, E51-F007, is open. IndVer.
h. WHEN RCIC TURBINE STM LINE DRN POT _1_

LEVEL HI (A-3 3-5) alarm clears, THEN Ind.Ver.

ENSURE SUPPL Y DRAIN POT DRAIN BYP VLV, E51-F054, is closed.

i. IF opened in accordance with Section 8.4, 1 THEN CLOSE HPCIIRCIC COND DRN LINE Ind.Ver.

BACK PRESS ORIFICE BYPASS VALVE, MVD-V5002.

1_2_0_P_-_16 ....L- R_ev_._9_8____ Page 14 of 791

  • 5.1.2 28.

29.

Procedural Steps ENSURE RCIC PUMP DISCH PRESS LOW (A-2 1-6) alarm is clear.

MAKE an entry in the Control Operator log, RCIC is in

/

Ind.Ver.

standby.

DatelTime Completed _

Performed By (Print) Initials Reviewed By: _

Unit SCO

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