Text

Final - Section C Operating Exam (Folder 3)
	ML072690158
Person / Time
Site:	Ginna
Issue date:	08/24/2007
From:	Reid J; Constellation Energy Group
To:	Caruso J; NRC Region 1
	Sykes, Marvin D.
Shared Package
ML063560007	List: ML071310329; ML072340101; ML072400127; ML072640224; ML072681173; ML072681198; ML072681202; ML072690061; ML072690085; ML072690103; ML072690105; ML072690112; ML072690120; ML072690132; ML072690139; ML072690147; ML072690158; ML072780402;
References
	Download: ML072690158 (105)
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Scenario Event Description NRC Scenario 1 Ginna 2007 NRC Scenario #1 The plant is at approximately 48% power (BOL), with both A and B MFW Pumps operating.

Load was reduced due to 'A MFW pump vibration. Pump repairs have been made, the pump has been tested and restarted, and a Load Ascension is anticipated.

The following equipment is Out-Of-Service:

A EDG (Expected back in 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ), and Containment Pressure channel PT-945 (The channel has been defeated per ER-INST.1, "Reactor Protection Bistable Defeat After Instrumentation Loop Failure.")

Following turnover the SRO directs the RO to swapover Letdown Orifice valves from AOV-202 to AOV-2006 in accordance with S-3.2P, "Swapping CVCS Letdown Orifice Valves."

Shortly afterwards, seat leakage will develop from PORV PCV-430. The operator will respond in accordance with AR-F-19, "Przr PORV outlet Hi Temp 145OF." The operator will address AP-PRZR.1, "Abnormal Pressurizer Pressure," and close Block Valve MOV-516. The SRO will address Technical Specifications 3.4.1 1, "Pzr Power Operated Relief Valves," and 3.4.13, "RCS Operational Leakage," as well as. Technical Requirements Manual section 3.4.3, "ATWS Mitigation."

Shortly after the PORV isolation, the Energy Control Center notifies the Control Room that the Post-Contingency Low Voltage Alarm has been received for the Off-Site Power System. The operator will enter 0-6.9, "Operating Limits for Ginna Station Transmission," and address Technical Specification 3.8.1, "AC Sources Modes 1-4." (LER 2006-02) The operator will expedite restoration of the A EDG.

Shortly after this, VCT Level Transmitter LT-112 will fail low. The operator will respond in accordance with AR-A-2, "VCT Level 14%86," and control the Reactor Makeup System manually.

Following this an Electrical Ground Fault occurs on Safeguards Bus 16, and the bus deenergizes. The operator will respond in accordance with AR-Ld. '"Safeguards Bus Main Breaker Overcurrent Trip," and AR-L-7, "Bus 16 UndeNOltage Safeguards," And ultimately respond in accordance with AP-ELEC.14116, '"Loss of Safeguards Bus 14/16."

Technical Specification 3.8.1, "AC Sources Modes 1-4," will be addressed, as will Technical Specification 3.8.9, "Distribution Systems Modes 1-4." At this point, Plant Management will make a decision to conduct a piant shutdown at l%/Minute. The crew will start a shutdown in accordance with AP-TURB.5, "Rapid Load Reduction."

During the load decrease, a Control Rod will drop into the Reactor core. The operator will respond in accordance with AR-E-28, "Power Range Rod Drop Rod Stop -5%/5sec," and transition to AP-RCC.3, "Dropped Recovery." Shortly afterwards a second Control Rod will drop into the Reactor core. The operator will manually trip the reactor, and enter E-0, "Reactor Trip or Safety Injection.' The operator will transition to ES-0.1, "Reactor Trip Response."

While in ES-0.1 recovering the plant a total loss of Off-Site Power will occur. The operator will need to transition to ECA 0.0, "Loss of All AC Power," and respond to a station blackout. The TDAFW Pump will fail to auto start. The operator will need to open these valves to restore AFW flow.

With AFW flow restored the Work Control Center will call and indicate that the " A EDG is now ready for service. The operator will start the " A EDG and restore power to BUS 14 and 18.

Scenario Event Description NRC Scenario 1 The scenario will end with the "A" EDG powering busses 14 and 18, and the operator has returned to ES-0.1, "Reactor Trip Response."

Critical Tasks:

CT ECA-0.0-6 Establish greater than 200 gpm AFW flow before both SIGs levels decrease to e 35" wide range level.

CT ECA-0.0 Restore AC Power to at least one Emergency Bus prior to placing pump control switches in Pull-Stop in ECA-0.0.

- 3

Scenario Event Description NRC Scenario 1 Simulator Malfunction List At Start:

IC # 171 Place Hold Tags on:

A EDG Control Switch A EDG Pushbutton Place Protected Equipment Tags on:

B EDG Control Switch B EDG Pushbunon Bus 14 Emergency Feeder Breaker Bus 18 Emergency Feeder Breaker Bus 16 Emergency Feeder Breaker Bus 17 Emergency Feeder Breaker Malf.

Malf.

Event #1 Event #2 Event #3 Event #4 Event #5 Event #6 Event #7 Event #8 Event #9 Event #lo Event #11 GEN04A "A" EDG Failure IND-MIS36 PT-945 Failure RPS-07M TDAFW Pump Failure RPS-07N TDAFW Pump Failure NONE Malf. PZr05A (2%) on Trigger #1 E-MIS 10 to 1.O (Ramp in over 60 sec.) on Trigger #2 Malf. CVClOA to 0% on Trigger #3 Malf. EDS04B on Trigger #4 NONE Malf. ROD02-J4 on Trigger #5 Malf. ROD02J10 on Trigger #6 Malf. EDSO6 1 (FAST) on Trigger #7 NONE Clear Malf. GEN04A

- A -

Scenario Event Description NRC Scenario 1 Shift Turnover:

The plant is at approximately 48% power (BOL), with both A and B MFW Pumps operating.

Load was reduced due to 'A MFW pump vibration. Pump repairs have been made, the pump has been tested and restarted, and a Load Ascension is anticipated.

Power history is as follows: Power reduced from 100% Steady-State conditions 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months ago Stable since then while MFW Pump repairs were made.

The following equipment is Out-Of-Service: A EDG (Expected back in 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ), and Containment Pressure channel PT-945 (The channel has been defeated per ER-INST.1, "Reactor Protection Bistable Defeat After Instrumentation Loop Failure.").

Hold Tags have been placed on:

A EDG Control Switch A EDG Pushbutton Protected Equipment Tags have been placed on:

. B EDG Control Switch B EDG Pushbutton Chemistry has requested you to swapover Letdown Orifice valves from AOV-202 to AOV-2008.

Bus 14 Emergency Feeder Breaker Bus 18 Emergency Feeder Breaker Bus 16 Emergency Feeder Breaker Bus 17 Emergency Feeder Breaker

Scenario Event Description NRC Scenario 1 Required Actions A-52.4 Required Required Action not met Completion Equipment T 9 4 5 Enter Condition referenced on Table 3.3.2-1 (IC, 2c. 4c) immediately.

Condition F (From 4c) - Place Channel in Trip within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

Condition J (From IC, 2c) -

Place Channel in Trip within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

A' Emergency Iiesei Generator ONLY I

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Time

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1330 ITS 3.8.1 Condition B Pedorm SR 3.8.1.1 forthe Offsite Circuit within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter.

- Declare required feature(s) suppolled by the inoperable DG inoperable when its required redundant feature($)

is inoperable within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months of the discovery of Condition B concurrent with inoperablility of required redundant features.

- Determine operable DG is not inoperable due to a common cause failure: OR, Perform SR3.8.i.Zfor operable OG within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

- Restore DG to operable within 7 days.

Reason

ailed Channel

/ 107

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Ireaker iaintenance I Daterime I ITS 3.3.2 Condition A I TRACKING I

Condition G -Be in Mode 3 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . and Mode4 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

Condition K - Be in Mode 3 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and Mode 5 within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

-6

Appendix D Operator Action Form ES-D-2 Place PCV-135 to MANUAL AND adjust as necessary to control Low Pressure Letdown pressure at approximately 300 psig.

RO Op Test No.: 1 Scenario# 1 Event#

1 Page I-of 35 Event

Description:

Swap Letdown Orifice Valves Time I

Position I

Applicant's Actions or Behavior Ro Following turnover the SRO directs the RO to swapover Lerdown Orifice valves lrom AOV-202 to AOV-2006 in accordance wth S-3.2P. "Swapping CVCS Letdown Oril ce Valves."

Place TCV-130 to MANUAL if desired and adjust as necessary.

N/A if not desired.

Booth Operator Instructions: NA Indications Available: NA Ro I

I I

S-3.2P "Swapping CVCS Letdown Orifice Valves."

Close 60 gpm orifice valve, THEN immediately open 40 gpm orifice valve (N/A 40 gpm orifice valve not opened).

t 5.2 Decreasing Letdown Flow from 60 gpm to 40 gpm.

I I

Ro NOTE:

Adjust PCV-135 to achieve Letdown pressure of - 250 psig on PI-135.

PCV-135 should be adjusted to control Letdown pressure at - 300 psig to accommodate the pressure decrease when swamina from a 60 aDm orifice to a 40 aDm orifice.

Ro Ensure PCV-135 controller signal is nulled/balanced and then Piace PCV-135 to AUTO, if desired.

Appendix D Operator Action Form ES-D-2 RO Op Test No.: 1 Scenario # 1 Event #

1 Page 8 oi 35 Event

Description:

Swap Letdown Orifice Valves Time I

Position I Applicant's Actions or Behavior Place or ensure TCV-130 is in AUTO, if desired.

Ro Monitor CharginglLetdown mismatch. IF desired, THEN place charging in manual. IF not desired, THEN N/A this step.

At the Discretion of the Lead Examiner Move to Event #2.

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 1 Event #

2 Page of 35 Event

Description:

PORV Leakage on PCV-430 Time I

Position I

Applicant's Actions or Behavior SRo Shortly aftenvards, seat leakage will develop from PORV PCV-430. The operator will respond in accordance with AR-F-19, "Przr PORV outlet Hi Temp 145°F." The operator will address AP-PRZR.1, "Abnormal Pressurizer Pressure," and close Block Valve MOV-516. The SRO will address Technical Specifications 3.4.1 1, "Pzr Power Operated Relief Valves," and 3.4.13, "RCS Operational Leakage," as well as Technical Requirements Manual section 3.4.3, "ATWS Mitigation."

Booth Operator Instructions:

Indications Available:

Operate Trigger #1 (PZR 05A (2%)).

IF Pressurizer pressure is decreasing, THEN GO TO AP-PRZR.1.

PPCS Alarm (PORV Mid-position)/F-19 Both Valve Position Status lights for PORV 430 are lit.

RO Check PRZR Pressure:

All 4 narrow range channels - APPROXIMATELY EQUAL All 4 narrow range channels - TRENDING TOGETHER I

I 1 NOTE SRO may carry out AP-PRZR.1 and AR-F-19 simultaneously.

I RO AP-PRZR.1 "Abnormal Przr Pressure" Check Reactor Power - STABLE RO Check PRZR Heater Status:

PRZR proportional heater breaker - CLOSED.

PRZR heater backuD arouD - ON RO I Check PRZR Pressure:

I

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Pressure - LESS THAN 2235 PSIG Pressure - GREATER THAN 2000 PSIG

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario# 1 Event#

2 Page '0 of 35 Event

Description:

PORV Leakage on PCV-430 Time I

Position I

Applicanrs Actions or Behavior Ro RO I Verify Normal PRZR Spray Valves - CLOSED I

I IF any valve can NOT be closed, THEN manually close the associated block valve.

MOV-516 for PCV-430.

I I

NOTE:

With PRZR pressure controller 431K in manual, PORV-431C will not operate in the automatic mode (refer to TR 3.4.3).

Ro Check PRZR Pressure Controller, 431 K, Demand - LESS I

Ro i THAN 50%.

Annunciator F-19, PRZR PORV OUTLET HI TEMP 145OF Extinguished. (This annunciator will not be extinguished)

If PORV leakage is indicated, then perform the following:

Close PORV Block Valve one at a time and check if Pressure stabilizes.

If leaking PRZR PORV is identified, then open any non-leaking PORV Block Valve and go to step 8.

NOTE: It is expected that MOV 516 will LE closed upon arrival of this action.

The SRO will note this and move on to steD 8.

NOTE: The Reactor Operator will attempt to close the PORV without direction, and upon discovering that the PORV will not close, attempt to close Block valve MOV-516. Once this action is comolete. or durino the orocess that it is occurrino the RO will reoort this to I

I the SRO.

I RO 1 Check PRZR PORVs:

PORVs - CLOSED. (Note: PCV 430 is indication mid-position)

I RO I Manuallv close PORVs.

Append x D Operator Action Form ES-D-2 RO OpTeslNo.: 1 Scenario# 1 Event#

2 Page 11 of 35 Event Descripfion:

P O W Leakage on PCV-430 Time I

Position I Applicanrs Actions or Behavior Attempt to reseat any leaking PORV Verifv leakaae has StODDed.

Verify affected PORV Block Valve closed.

Cycle the leaking PORV open and closed.

RO If leakage continues Then:

Reclose leaking PORV Block Valve.

Refer to ITS section 3.4.1 1 and TR 3.4.3.

Check PRZR Pressure Control Restored:

Pressure -TRENDING TO 2235 PSlG I

I I

GotoSteD11.

I RO Check PRT Indications:

Level - BETWEEN 61% AND 84%

Pressure -APPROXIMATELY 1.5 PSlG AND STABLE Temperature - AT CNMT AMBIENT TEMPERATURE AND STABLE RO Establish PRZR Pressure Control In Auto:

Verify 431K in AUTO Verifv PRZR sDrav valves in AUTO.

I I

1 Verifv PRZR heaters restored:

I Crew Evaluate MCB Annunciator Status SRO I

SRO I Notify Reactor Engineer for Transient Monitoring Program Notify Higher Supervision

Appendix D Operator Action Form ES-D-2 OP Test No.: 1 Scenario # 1 Event ff 2

Page 12 of 35 Event

Description:

PORV Leakage on PCV-430 Time I

Position I

Applicant's Actions or Behavior AR-F-19 PRZR PORV Outlet HI Temp 145°F.

I RO I

RO SRO/RO I I

SRO I

SRO NOTE: SRO may carry out AP-PRZR.1 and AR-F-19 simultaneously.

Check PRZR PORV Outlet temDerature. TI-438.

Check PRT Darameters.

Check Containment temperature Stafl OR swap Containment Recirc Fans per Shift Supetvisor directions.

Refer to ITS LCO 3.4.11 and 3.4.13.

LCO 3.4.1 1 Each PORV and associated block valve shall be OPERABLE.

CONDITION REQUIRED ACTION COMPLETION TIME 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months One PORV Inoperable.

8.1 Close associated block valve.

AND 8.2 Remove power from associated 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months block valve.

AND 8.3 Restore PORVto OPERABLE status.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months LCO 3.4.13 RCS operational LEAKAGE NOTE: SRO will check and determine insunicient data to quantify leakaqelno entry.

TRM 3.4.3

Appendix D Operator Act on Form ES-D-2 Op Test No.: 1 Scenario # 1 Event #

2 Page '3 01 35 Event

Description:

PORV Leakage on PCV-430 Time 1

Position I

Applicant's Actions or Behavior I Anticipated Transients Without Scram (ATWS) Mitigation CONDITION REQUIRED ACTION COMPLETION TIME A. One Or more POW A.1 Declare AlWS lmmediatey automatic flow path mitigating capabiliry inoperable.

inoperable.

At the Discretion of the Lead Examiner Move to Event #3.

Appendix D Operator Action Form ES-D-2 SRO OP Test No.: 1 Scenario +I 1 Event !+

3 Page 4 of 35 Event

Description:

Post Contingency Low Voltage Alarm Occurs Time I

Position I

Applicants Actions or Behavior IF RG&E ECC informs the Control Room that a Ginna Post Contingency Low Voltage Alarm has occurred THEN DECLARE offsite power inoperable (Refer to ITS 3.8.1).

shortly after the PORV isolation, the Energy Control Center notifies the Control Room hat the Post-Contingency Low Voltage Alarm has been received for the Off-Site Power System. The operator will enter 0-6.9, Operating Limits for Ginna Station rransmission, and address Technical Specification 3.8.1, AC Sources Modes 1-4.

LER 2006-02) The operator will expedite restoration of the A EDG.

300th Operator Instructions:

Operate Trigger #2 (E-MIS10 (1.0 ramp in over 60 seconds))

Call Control Room with Energy Operations phone. Tell SRO that the Ginna Post Contingency Low Voltage Alarm has occurred due to the system load. You will inform him when it has cleared.

ndications Available:

I SRO 0-6.9 Operating Limits for Ginna Station Transmission.

LCO 3.8.1 AC Sources - MODES 1.2.3. and 4 6.3 Low Voltage Condition at 13A With Generator Output Breaker($ Closed SRO CONDlTiON REQUIRED ACTION COMPLETION TIME C. Offsite powel t o m C.1 Rsstore requked or more 480V offsite circuit Io

,2 hOU,S Safeguards bus(es)

OPERABLE inoperable.

SfalUS.

Appendix D Operator Action Form ES-D-2 SRO AND OR One DG inoperable "' OPERABLE slatus.

I' TR3.8.1 i

I SRO At the Discretion of the Lead Examiner Move to Event #4.

CONDlTiON REQUIRED ACTION COMPLETION TIME

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8.1 Enter LCO 3.8.1.

lmrnedialely Contact Maintenance Department and check on availability of A EDG. Ask that work be expedited.

Appendix D Operator Action Form ES-D-2 RO OpTest No.: 1 Scenario# 1 Event#

4 Page '6 of 35 Event

Description:

VCT Level Transminer (LT-112) Fails Low Time

[

Position I Applicant's Actions or Behavior Perform makeup by one of the following methods:

Shortly after this, VCT Level Transmitter LT-112 will fail low. The operator will respond in accordance with AR-A-2, "VCT Level 14%86," and control the Reactor Makeup System manually.

Booth Operator Instructions:

Indications Available:

Operate Trigger #3 (CVClOA (0%))

A-2 VCT LEVEL 14% 86 I MCB VCT level at "0%"

I I

AR-A-2, "VCT LEVEL 14% 86."

I SRO/RO I

I Ro IF channel failure is indicated, THEN refer to Attachment 1 and Figure 1 to respond to VCT level transmitter failure.

LT-112 FAILED LOW Notify A 0 to monitor LI-139 in valve alley, and report reading.

Auto makeup will start and operate continuously. Upon verification from A 0 that VCT level as indicated on LI-139 Is greater than 30%, secure auto makeup by taking control switch to OFF.

Inform A 0 to notify Control Room for makeup requirement when LI-139 indicates amroximatelv 20%.

NOTE: Booth Operator should verify and report VCT Level from LI-139 using VCT Screen Drawina VCT 1.

. Rearm auto makeup to start the auto makeup, then disarm when LI-139 is greater than 30%.

At the Discretion of the Lead Examiner Move to Event #5.

Appendix D Operator Action Form ES-D-2 RO I

1 To prevent the DIG from loading on the affected Safeguards bus while troubleshooting is in progress, PULL STOP the affected DIG supply breaker.

OpTest No.: 1 Scenario# 1 Event#

5 Page 17 of 35 Event

Description:

An Electrical Ground Fault Occurs on Safeguards Bus 16 Time I

Position I

Applicanrs Actions or Behavior SRO SRO Following this an Electrical Ground Fault occurs on Safeguards Bus 16, and the bus deenergizes. The operator will respond in accordance with AR-L-5, "Safeguards Bus Main Breaker Overcurrent Trip," and AR-L-7, "Bus 16 Undervoltage Safeguards," And ultimately respond in accordance with AP-ELEC.14/16, "Loss of Safeguards Bus 14/16."

Technical Specification 3.8.1, "AC Sources Modes 1-4," will be addressed, as will Technical Soecification 3.8.9. "Distribution Svstems Modes 1-4."

Notify the following:

Electricians

. Scheduling Operations Supervision Refer to ITS LCO 3.8.1 OR 3.8.2.

Booth Operator Instructions:

Indications Available:

Operate Trigger #4 (EDS04B)

L-5 SAFEGUARD BUS MAIN BREAKER OVERCURRENT TRIP L-7 BUS 16 UNDER VOLTAGE SAFEGUARDS Voltage on Bus 16 goes to " 0 I

I AR-LQ, "SAFEGUARD BUS MAIN BREAKER OVERCURRENT TRIP."

NOTE Operator may diagnose no voltage on Bus 16 and immediately enter AP-ELECT.14liB.

NOTE:

DO NOT attempt to reset affected Safeguards bus normal feed breaker until overcurrent condition has been identib and isolated.

I I

SRO Direct Electric ans to investigate cause of overcbrrent I

I AR-L-7, "BUS 16 UNDER VOLTAGE SAFEGUARDS x

Appendix D Operator Action Form ES-D-2 I

I Op Test No.: 1 Scenario # 1 Event #

5 Page 18 01 35 Event

Description:

An Electrical Ground Fault Occurs on Safeguards Bus 16 Time I

Position 1

Applicants Actions or Behavior I

I NOTE Operator may diagnose no voltage on Bus 16 and immediately enter AP-ELECT.14116.

I SRO I Refer to ITS LCO 3.8.1 OR 3.8.2.

Appendix D Operator Action Farm ES-D-2 OP Test No.: 1 Scenario U 1 Event if 5

Page 19 of 35 Event

Description:

An Eleclrlcal Ground Fault Occurs on Safeguards Bus 16 Time I

Postion I Applicants Actions or Behavior RO Monitor Tavg.

Place Rods in Manual.

Manuallv move Control Rods to control Tava.

I 1

Verify that Emergency D\\G associated with alfected bus is Verify Both Trains of Emergency Busses Energized to at least 420 volts.

If one train deenergized Then:

. Mode Switch in UNIT.

RO Ensure DIG is aligned for Unit Operation I

I 1

Voltage Control Selector in AUTO.

Check D\\G running.

NOTE: Crew will note that the procedure step cannot be carried out because of the overcurrent lockout on Bus 16.

RO Verify CCW Pump Status At least one CCW Pump running.

Annunciator A-22, CCW Pump Discharge LO Press 60 PSIG-1 Extinguished.

I I

RO Verify Charging Pump Status - Atr Least one pump running.

Check MFW Regulating Valves - Restoring S/G Level to 52%

AUTO.

1 BOP 1 Verify Bus 14 -Energized to at least 420 volts.

I I

Appendix D Operator Action Form ES-0-2 BOP An Electrical Ground Fault Occurs on Safeguards Bur 16 Page OpTest No.. 1 Scenario# 1 Event#

5 Event Description.

Verify Bus 16 -Energized to at least 420 volts.

Time 1

Position I Applicant's Actions or Behavior I

SRO Direct A 0 to swap Aux Bldg lighting to MCC C.

NOTE: Bus 16 will be deenergized and incapable of being restored.

SRO I

I I ROIBOP I Ensure the followins eauiDment is rumina:

Provide alternate room cooling for DIG B 1 ccw Pump A I Charging PumD A SRO PRZR Proportional Heaters I Containment Recirc Fans A and D Cross Connect DIG A Fuel Oil transfer pump to DIG B.

Boric Acid Pump A in Automatic RMW Pump A in Automatic Reactor ComDartment Coolina Fan A RO Penetration Cooling Fan A (NOTE: Cooling Fan B is running. Will need 10 be slopped and Cooling Fan A slaned.)

SFP Cooiina Check Charging Pump suction aligned to VCT.

RO I Check VCT Makeup System NOTE Crew must recognize that LT 112 is failed low and the system must be maintained in accordance with AR-A-2.

1 LCV-1 IZC Open 1 LCV-1128 Closed

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 1 Event #

5 Page 21 of 35 Event

Description:

An Electrical Ground Fault Occurs on Safeguards Bus 16 Time I

Position I Applicant's Actions or Behavior

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RO Verify normal Rod Control restored.

Annunciator C-5, PPCS Rod Sequence or Rod Deviation -

Extinguished.

Annunciator E-28, Power Range Rod Drop Rod Stop -

Extinguished.

Annunciator F-15, RCS TAVG DEV 4'F - Extinguished.

Place Rods in AUTO if desired.

SRO Establish Stable Plant Conditions Check Tavg Trending to Tref.

Check Przr Pressure -Trending to 2235 psig in AUTO.

Check Przr Level -Trending to program in AUTO control.

BOP Restore normal Electric System Alignment.

Verify all AC Bus Breakers closed.

NOTE The Bus 16 Breakers will not be able to be closed.

Appendix D Operator Action Form ES-D-2 SRO RO Op Test No.: 1 Scenario# 1 Event#

5 Page of 35 Event

Description:

An Electrical Ground Fault Occurs on Safeguards Bus 16 Establish normal plant conditions.

Verify two charging pumps running.

Verify at least two Containment Recirc Fans running.

Check CCW pumps - Only one running.

Time I

Position I

Applicant's Actions or Behavior

--'- I-.-

I I

I SRO 1 If normal Dower is not restored. 00 to steo 17.

- ' 'BOP Cneck Status of DC System oads.

Verily tne TDAFW pLmp DC BOP Check status of oattory chargers Battery chargers A or AI energizeo.

Battery chargers B or B1 energizeo.

SRO Check radiation monitors:

CNMT Sample Pump running.

Plant Vent Sample Pump running.

All area and Drocess monitors oDeratino as rewired.

Restore Equipment alignment.

Verify Annunciator L-1, AUX Bldg. Vent System Control Panel -

Extinguished.

Restore Affected Bus equipment as power supply permits.

Evaluate MCB Annunciators status SRO Crew Establish control systems in AUTO.

Evaluate MCB Annunciator status.

Verify control board valve alignment - normal.

I I

Appendix D Operator Action Form ES-D-2 OP Test No.: 1 Scenario n 1 Event n 5

Page 23 of 35 Event

Description:

An Electrical Ground Fault Occurs on Safeguards Bus 16 Time I

Position I Applicant's Actions or Behavior SRO Verily Emergency AC BJS norma leeder breakers clossd.

hOTE' Recognize tnal 6,s 16 cannol oe energ zcd an0 inat pmcorre.oop s m eHec1.nt 6.s s restorcd

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LCO 3.8.1 AC Sources - MODES 1, 2, 3, and 4 LCO 3.8.1 AC Sources - MODES 1. 2. 3. and 4 CONDITION Offsite power to one or more 480 V safeguards bus(es) inoperable.

AND One DG inoperable.

Enter applicable Conditions and Required Actions of LCO 3.8.9, "Distribution Systems - MODES 1, 2, 3, and 4," when Condition C is entered with no AC power source to one distribution train.

LCO 3.8.9 Distribution Systems - MODES 1, 2, 3, and 4 CONDITION REOUIRED ACTION COMPLETION TIME E. Two trains with inoperable electrical power distribution E.1 LCO 3.0.3.

Immediately subsystems that result in a loss of safety function.

NOTE: This event leaves the plant with the B EDG running unloaded.

I At the discretion of the Lead Examiner move to Event #6

Appendix D Operator Action Form ES-D-2 SRO OP Test No.: 1 Scenario # 1 Event #

6 Page 24 of 35 Event

Description:

Load Decreaseat 1SblMinute Time I

Position I Applicant's Actions or Behavior Initiate a Load Reduction At this point, Plant Management will make a decision to conduct a plant shutdown at I%/Minute. The crew will start a shutdown in accordance with AP-TURB.5, "Rapid Load Reduction."

Booth Operator Instructions:

Call SRO as plant management a direct load decrease @ 1Ydminute.

BOP Indications Available:

Reduce Turbine Load in AUTO.

AP-TURB.5, "Rapid Load Reduction."

I I

RO Monitor RCS Tavg Tavg > 545°F Tava < 579OF I

1 RO 1 Verifv rods in AUTO I

RO Adjust boric acid addition rate as necessary to:

Maintain rods above RIL.

Match Tavg and Tref.

ComDensate for Xenon.

RO I Place Przr Backup Heaters to ON.

I I

RO Monitor Przr Pressure - Trending to 2235 psig in AUTO.

RO Monitor Przr Level -Trending to program in Auto Control.

Monitor MFW Regulating Valves - restoring S/G level to 52% in I

1 AUTO.

Appendix D Operator Action Form ES-D-2 o p Test No.: 1 Scenario n 1 vent n 6

Page 25 of 35 Event

Description:

Load Decrease a1 lD/dMinute Time I

Posltion I Applicant's Actions or Behavior 1 IA to CNMT Isolation Valve AOV 5392 open.

I RO I Check Steam Dump Status I Annunciator G-15. Steam Dum0 Armed - Lit I

I 1 Steam Dump oDeratina properly in AUTO.

I I

BOP 1 Check Hotwell Level Hotwell level controller in Auto.

Controller demand e 60%.

Hotwell level at setpoint.

I After load has been decreased 30 MW, and at the discretion of the Lead Examiner move to Event 7.

Appendix D Operator Action Form ES-D-2 OPTest No.: 1 Scenario# 1 Event#

7 Page 26 of 35 Event

Description:

Dropped Rod Time I

Position I Applicant's Actions or Behavior SRO

~

During the load decrease, a Control Rod will drop into the Reactor core. The operator will respond in accordance with AR-E-28, "Power Range Rod Drop Rod Stop -5%/5sec,"

and transition to AP-RCC.3. '"DroDDed Recovew."

E-28 POWER RANGE ROD DROP ROD STOP - 5% 15 SEC Refer to AP-RCC.3 RO Verify Only One Rod has Dropped.

RO 1 Place Rods to MANUAL.

CAUTION:

Bank Rod Withdrawal should not be performed until the dropped rod is recovered.

RO I

I 1 Check Tavg -STABLE AT PROGRAM I

I I

BOP I Perform the following:

Place EH control in MNAUAL.

Manually adjust turbine load to match Tavg and Tref.

I Verfy AnnJnclalor G-15, STEAM DUMP ARMED -

I Ro'EoP EXTINGUISHED BOP Check Main Generator Load -GREATER THAN 15 MW

Appendix D Operator Action Form ES-D-2 Ro OpTest No.: 1 Scenario# 1 Event#

7 Page 27 of 35 Event

Description:

Dropped Rod Time I

Position I Applicant's Actions or Behavior If Tavg greater than Tref. THEN restore Tavg to Tref by one or more of the following:

RO I Establish Stable Plant Conditions:

Ro/BoP I

I I

Tava - TRENDING TO TREF I

Boration IF Tavg less than Tref, THEN restore Tavg to Tref by one or more of the following:

Reduce turbine load Dilution of RCS RO 1

lnselt control rods PRZR pressure -TRENDING TO 2235 PSlG IN AUTO RO PRZR level -TRENDlGN TO PROGRAM IN AUTO CONTROL MFW Regulating Valves - RESTORING S/G LEVEL TO 52%

INAUTO If not done already, at the discretion of the Lead Examiner move to Event 8.

Op Test No.: 1 Scenario # 1 Event #

8 Page 28 of -

35 Event

Description:

Second Dropped Rod Time I

Position I Applicant's Actions or Behavior Shortly afterwards a second Control Rod will drop into the Reactor core. The operator will manually trip the reactor, and enter E-0, "Reactor Trip or Safety Injection." The operator will transition to ES-0.1, "Reactor Trip Response."

Booth Operator Instructions:

Operate Trigger #6 (ROD02JlO)

Indications Available:

I Second rod droDs into the core.

RO AP-RCC.3. "DROPPED ROD RECOVERY."

Verify Only One Rod Has Dropped.

RO I

IF 2 or more rods dropped, THEN tnp the reactor AND go lo E-0, REACTOR TRIP OR SAFETY INJECTION

-7 Verify Reactor Trip:

E-0, "REACTOR TRIP OR SAFETY INJECTION."

BOP Bop Verify Turbine Stop Valves - CLOSED Verify Both Trains of AC Emergency Busses Energized To At Least 420 VOLTS:

I I ROlBOP I Check if SI is Actuated:

I I

Any SI Annunciator - LIT IF any of the following conditions are met, THEN manually actuate SI and CI:

PRZR pressure less than 1750 psig OR I

I 1

Steamline pressure less than 514 Dsia 1

Appendix D Operator Action Form ES-D-2 RO Op Test No.: 1 Scenario# 1 Evellt#

8 Page of 35 Event

Description:

Second Dropped Rod Time I

Position I

Applicanvs Actions or Behavior Monitor RCS Tavg - STABLE AT OR TRENDING TRO 547°F OR CNMT pressure greater than 4 psig OR SI sequencing started OR Operator determines SI required IF SI is NOT required, THEN go to ES-0.1, REACTOR TRIP RESPONSE. Steo 1.

I I

ES-0.1, REACTOR TRIP RESPONSE F O N :

If SI Actuation occurs during this procedure, THEN E-0, Reactor TriD Or Safetv Iniection. should be Derformed.

RO 1 Check PRZR Level Control:

Verify charging pumps -ANY RUNNING I.

PRZR LEVEL - greater than 13%

Verifv letdown - IN SERVICE PRZR level -TRENDING TO 20%

Check PRZR heaters - ENERGIZED PRZR proportional heaters PRZR heater backuo arouo I

I NOTE: Booth Operator may move to event 9 at any time from this point, on cue of Lead Examiner, if necessary for time control of scenario.

I I

BOP 1 Check S/G Feed Flow Status:

I Check RCS Tava - LESS THAN 554°F

Appendix D Operator Action Form E.5.D-2 I

i OpTest No.: 1 Scenario# 1 Event#

8 Page 30 of 35 Event

Description:

Second Dropped Rod Time I

Position I Applicant's Anions or Behavior Verify MFW flow control valves - CLOSED MFW regulating valves MFW bypass valves Verify total AFW flow-GREATER THAN 200 GPM Close MFW pump discharge valves MOV-3977, A MFW pump MOV-3976, B MFW pump Stop MFW pumps and place in PULL STOP WHEN both MFP pumps are stopped, THEN depress MANUAL pushbuttons for A and B MFW regulating valve and bypass valve controllers AND adjust to 0% demand.

SIG A. HCV-466 and HCV-480 I

I 1

S/G 6. HCV-476 and HCV-481 I

Verify MRPl Indicates - ALL CONTROL AND SHUTDOWN RODS ON BOlTOM I

Ro I

At the discretion of the Lead Examiner move to event 9.

1

Op Test No.: 1 Scenario n 1 Event #

9 Page 31 of 35 Event

Description:

A Total Loss of Off-Site Power Occurs Time I

Position I Applicants Actions or Behavior While in ES-0.1 recovering the plant a total loss of Off-Site Power will occur. The operator will need to transition to ECA 0.0, Loss of All AC Power, and respond to a station blackout.

RO

~

.~

k-Booth Operator Instructions:

Operate trigger #7 (EDSOB 1 (FAST))

Verify Reactor Trip:

I Indications Available:

BOP Control Roomlights go out No voltage on Emergency Busses 14/16 I

EVALUATORS NOTE:

8 EDG now running without Service Water. SI signal occurs because two Containment Pressure instruments have failedJPT-945 initial conditions, PT-949 on LOP from Instrument Bus B).

I I

I Verify Turbine Stop Valves - CLOSED IF Bus 14 AND Bus 16 are deenergized, THEN go to ECA-0.0, I

! L o s s OF ALL Ac POWER, Step 1.

ECA-0.0, LOSS OF ALL AC POWER.

I Due to potentially extreme environmental conditions.

Caution should be used when entering the intermediate I

buildino for local actions.

I I

NOTE:

e CFSTs should be monitored for information only. PR procedures should not be implemented.

Local actions may require portable lighting and communication devices.

NOTE:

FOLDOUT page should be open and monitored periodically.

I I

Deleted: haw failed 1

Appendix D Operator Action Farm ES-D-2 BOP Op Test No.: 1 Scenario # 1 Event #

9 Page 32 of 35 Event

Description:

A Total Loss of Off-Site Power Occurs Time 1

Position I Applicant's Actions or Behavior Adjust S/G ARVs To Control Tavg At Approximately 547°F RO Stop Both RCPs RO AOV-2006 AOV-202 Place letdown isolation valve switches - to CLOSE AOV-371 AOV-427 Place excess letdown isolation valve switch to CLOSE (AOV-310)

Move to Event #lo Check If RCS Is Isolated:

PRZR PORVs -CLOSED Verify RCS isolation valves closed:

AOV-200A Place letdown orifice valve switches to CLOSE

Appendix D Operator Action Form ES-D-2 BOP OP Test No.: 1 Scenario n 1 Event b!

10 Event Descriplion:

TDAFW Pump Failure Verify TDAFW pump - RUNNING Verify governor valve, V-3652, latched.

Time I

Position I

Applicant's Actions or Behavior The TDAFW Pump will fail to auto start. The operator will need to open these valves to restore AFW flow.

Booth Operator Instructions: NA Indications Available:

I TDAFW Pump is NOT running.

I 1

BOP I Verify Adeauate TDAFW Flow:

I Manually or locally open at least one TDAFW pump steam I

I Bop I supply valve.

I I

MOV-3505A I

MOV-3504A

' Critical Task (ECA-0.0-6)

Establish greater than 200 gpm AFW flow before both WG's levels decrease to c 35" wide range level.

I BOP. \\/er l y TDAFW pJmp flow - GREATER THAN 200 GPM I Move to Event #11

Appendix D Operator Action Form ES-D-2 OP Test NO.: 1 Scenario # 1 Event #

11 Page 34 of 35 Event

Description:

A EDG is reslored lo service.

Time I

Position I Applicants Actions or Behavior SRO/RO With AFW flow restored the Work Control Center will call and indicate that the A EDG is now ready for sewice. The operator will start the A EDG and restore power to Bus 14and 18.

Booth Operator Instructions:

Indications Available:

Clear malf. GEN04A.

Try To Restore Power to Any Train of AC Emergency Busses:

Verify emergency DIG aligned for unit operation Mode switch in UNIT NOTE:

e Conditions should be evaluated for Site Contingency Reporting (Refer to EPIP-1.0, GINNA STATION EVENT EVALUATION AND CLASSIFICATION).

A 0 should frequently monitor the TDAFW pump until AC power is restored.

BOOTH OPERATORS NOTE:

Call SRO as work control center and inform that A EDG is available and the clearance may be lifted.

SROIRO Check emergency D/Gs-BOTH DIG RUNNING.

I I

Voltacre control selector in AUTO Ro RO I Manuallv alian switches on rear of MCB.

WHEN non-running D/G available for starting, THEN perform the following:

Deoress DIG FIELD RESET oushbunon I

1 DeDress D/G RESET oushbutton Start D/G IF D/G stark, THEN go to Step 7.c.

Appendix D Operator Action Form ES-D-2 RO

~

OpTest No -

1 Scenario # 1 Event #

11 I

CHECK DIG voltage and frequency Voltage -APPROXIMATELY 480v Freauencv - APPROXIMATELY 60 Hz I

I Event

Description:

A EDG is restored lo service.

Time I

Position I Applicant's Actions or Behavior Verify adequate DIG cooling Bus 17 andor Bus 18 - ENERGIZED One SW Pump running for each running DIG I

I Verify at least one train of AC emergency busses 1

ENERGIZED I

I 1

Bus14andBus18 Critical Task (ECA-0.0)

Restore AC Power to at least one Emergency Bus prioi to placing pump control switches in Pull-Stop in ECA-0.0.

I I

SRO 1 Return to procedure and step in effect.

SRO goes to ES-0.1, and then transition to E-0 based on SI having actuated.

Boom OPERATOR:

Freeze simulator.

EAL 6.1.3 (Alert) EDG A only AC Source for > 15 minutes.

Or 6.1.4 (SAE)

Loss of both Trains of AC Power for > 15 minutes

Scenario Event Description NRC Scenario 2 Ginna 2007 NRC Scenario #2 The Plant is at 100% power Steady-State (BOL), and been for the last 9 days following Refueling Outage.

The following equipment is Out-Of-Service: A MDAFW Pump (Expected back in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ),

Steam Flow channel FT-475 (The channel has been defeated per ER-INST.1, Reactor Protection Bistable Defeat After Instrumentation Loop Failure.) and MCB Annunciator J-8 has alarmed spuriously several times over the last hour (KC is investigating).

Shortly after turnover, R-12 (Containment Gas Monitor) will fail high. The operator will respond in accordance with AR-A-25, Containment Ventilation Isolation, and/or AR-RMS-12.2, Cnmt Gas Fail Alarm. The operator will address Technical Specifications 3.3.5, Containment Ventilation Isolation Instrumentation, 3.4.1 5, RCS Leakage Detection Instrumentation, and 3.6.3, Containment Isolation Boundaries.

Shortly after this, a Small SG Tube Leak (.4 gpm) develops on B SG. The operator will respond in accordance with AR-PPCS-1, SGTL Indicated, and AP-SG.l, Steam Generator Tube Leak. The operator will address Technical Specification 3.7.14, Secondary Specific Activity, and 3.4.13, RCS Operational Leakage. With the SG Tube Leak at >150 GPD, the Operations Manager will decide to shutdown the plant. The Operator will commence a plant shutdown to Hot Standby at 1 %/minute in accordance with AP-TURB.5, Rapid Downpower.

Following the start of the shutdown, uncontrolled rod motion will occur. The operator will respond in accordance with AP-RCC.1, Continuous Control Rod Withdrawl\\lnsertion, and place rods in manual.

Once AP-RCC.l is complete, the shutdown will recommence. During the shutdown, Pressurizer Level Channel LT-428 will slowly fail high. The operator will respond in accordance with AR-F-4, Pressurizer Level Deviation -5 Normal +5, and AR-F-28, Pressurizer High Level Channel Alert 87%, and then address ER-INST.l, Reactor Protection Bistable Defeat After Instrumentation Loop Failure. The operator will take manual control of the Charging Pumps and control Pzr Level. The operator will address Technical Specifications 3.3.1, Reactor Trip System Instrumentation, 3.3.2, ESFAS Instrumentation, and 3.3.3, PAM Instrumentation.

After about 10-15% power reduction, an inadvertent Safety Injection signal will occur (The Automatic Reactor Trip is blocked, and the manual MCB pushbuttons will not operate). The operator will enter E-0, Reactor Trip or Safety Injection, and de-energize Busses 13 and 15 to de-energize the Rod Drive Motor Generators and cause a reactor trip.

The B MDAFW Pump will fail to automatically start. When started by the operator, the pump will trip within 60 seconds. Upon start up of the TDAFW Pump, the pump will trip on overspeed and be damaged to the point that it can no longer be used. This will eventually cause a Red Path on Heal Sink and the operator will transition to FR-H.l, Response to Loss of Secondary Heat Sink.

The operator will attempt to start the S A W system to provide flow to one SG, however, both Flow Transmitters (FT-4084 and 4085) will have been isolated from Shutdown, and the S A W pumps when started will reach runout conditions and trip on overcurrent within 60 seconds.

(LER 2006-4)

Scenario Event Description NRC Scenario 2 Feed flow will be restored to one Steam Generator using a Condensate and a Main Feedwater Pump. Once feed flow is restored to one Steam Generator the operator will transition back to ES-0.1, Reactor Trip Response.

Critical Tasks:

E-0-A Trip the reactor before both Steam Generator Wide Range Levels decrease to less than 35.

FR-H.1-A Establish Feedwater flow into at least one Steam Generator before Bleed and Feed Criteria is met in FR-H.I.

Scenario Event Description NRC Scenario 2 2

3 Simulator Set Up IC-172 Place Hold Tags on:

Place Protected Equipment Tags on:

B MDAFW Pump Control Switch Insert:

A MDAFW Pump Control Switch Close and Tag MOV 4007 Control Switch Trigger 2 - Malf. SGN04B (.4gpm)

When requested - LOA SGN24 (0) (Close V-996A)

Trigger 3 - Malf. RODl A-66 (Insert prior to commencing boration and Load Reduction)

FDWl 1A - A MDAFW Trip, (Pull/Stop, Hold Tag, Close MOV-4007, Protective Covers on B MDAFW Pump)

FDW12 (0 RPM) -TDAFW Pump Overspeed RPS05A - Fail A Rx Trip Bkr (Manual Unavailable)

RPS05B - Fail B Rx Trip Bkr (Manual Unavailable)

STMOlB (0) - Fail SF FT-475 (Perform Defeat per ER-INST.l)

RPS07L - B MDAFW Pump fails to auto start Ino/ovr IND-RN31 (SAFW Flow) to " 0 Ino/ovr IND-FW33 (SAFW Flow) to " 0 Events:

1 I Triaaer 1 - Malf. RMS02B (le+007) 4 5

6 7

8 9

10 None (Malfunction inserted prior to event #3)

Trigger 4 - Malf. PZR03C (100% @30second ramp)

Trigger 5 - Malf. SlSOl (0) Train A None (RPS05A and B set at TO)

(RPS07L - B MDAFW Pump fails to auto start at TO), once started trip 2 minutes later by inserting FWDll B on Trigger 30.

None (FDW12 (0 RPM) - TDAFW Pump Overspeed at TO)

Trigger 29 - RNDl5A - 60 delay (Initiated when C SAFW Pump is manually started).

Trigger 28 - FWD15B - 60 delay (Initiated when D SAFW Pump is manually started).

Scenario Event Description NRC Scenario 2 Shift Turnover:

The Plant is at 100% power Steady-State (BOL), and been for the last 9 days following Refueling Outage.

The following equipment is Out-Of-Service: A MDAFW Pump (Expected back in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ),

Steam Flow channel FT-475 (The channel has been defeated per ER-INST.1, "Reactor Protection Bistable Defeat After Instrumentation Loop Failure.") and MCB Annunciator J-8 has alarmed spuriously several times over the last hour (lac is investigating).

Hold Tags have been placed on:

0 A MDAFW Pump Control Switch Close and Tag MOV 4007 Control Switch Protected Equipment Tags have been placed on:

B MDAFW Pump Control Switch

I-O I

I b

0 I

I.

Appendix D Operator Action Form ES-D-2 OpTest No.: -

1 Scenario# -

2 Event #

1 Page of 32 Event

Description:

R-12 Failure Time I

Position I Applicant's Actions or Behavior Shortly after turnover, R-12 (Containment Gas Monitor) will fail high. The operator will respond in accordance with AR-A-25, "Containment Ventilation Isolation," and/or AR-RMS-12.2, "Cnmt Gas Fail Alarm." The operator will address Technical Specifications 3.3.5, "Containment Ventilation Isolation Instrumentation," 3.4.1 5, "RCS Leakage Detection Instrumentation," and 3.6.3. "Containment Isolation Boundaries."

I Booth Operator Instructions:

Operates Trigger #1 (RMS02B (le'w7).

~ -1 Indications Available:

I A-25 CONTAINMENT VENTILATION ISOLATION E-16 RMS Process Monitor High Activity I

I I Hiah indication on R-12 channel.

I AR-A-25, "CONTAINMENT VENTILATION ISOLATION."

I I

RO 1 Monitor Area Radiation Monitors - R-2, R-7.

I SRO I Refer to ITS LCO 3.3.5.

SRO I Notify RP to sample CNMT.

AR-RMS-12.2 CNMT GAS FAIL ALARM I

I SRO/RO I Evaluate the cause of the alarm.

I I

I SRO I Perform the following:

I I

Initiate an A-52.4.

I Notify RP.

Notify I&C.

SubmitWO.

SRO I REFER TO ITS 3.3.5, 3.4.15, 3.6.3.

~

_ _ _ _ _ ~

Appendix D Operator Action Form ES-D-2 OpTest No.: -

1 Scenario# -

2 Event #

1 Page 8 of 32 Event

Description:

R-12 Failure Time I

Position I

Applicant's Actions or Behavior LCO 3.3.5 CONTAINMENT VENTILATION ISOLATION INSTRUMENTATION CONDITION REOUIRED ACTION COMPLETION TIME A.

One radiation A.l Restore the affected monitoring channel channel lo 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months inoperable.

OPERABLE status.

LCO 3.4.15 RCS LEAKAGE DETECTION INSTRUMENTATION CONDITION REQUIRED ACTION COMPLETION TIME

8.

Gaseous 8.1 Verify particulate containment containment atmosphere atmosphere 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months radioactivity monitor radioactivity monitor inoperable.

OPERABLE.

LCO 3.6.3 CONTAINMENT ISOLATION BOUNDARIES

( Not affected)

At the Discretion of the Lead Examiner Move to Event #2.

Appendix D Operator Action Form ES-D-2 RO SRo RO OpTest No.: -

1 Scenario# -

2 Event#

2 Page of 32 Event

Description:

B Steam Generator Tube Leak Time I

Position I

Applicants Actions or Behavior Trend PPCS points R1545A5G.

Notify RP/Chemistry to IMMEDIATELY obtain and analyze an air ejector grab sample per CH-SAMP-SG-LEAKRATE.

Determine the estimated leak rate using the R15A5G.

Shortly after this, a Small SG Tube Leak (.4 gpm) develops on 6 SG. The operator will respond in accordance with AR-PPCS-1, SGTL Indicated, and AP-SG.l, Steam Generator Tube Leak. The operator will address Technical Specification 3.7.14, Secondary Specific Activity, and 3.4.1 3, RCS Operational Leakage. With the SG Tube Leak at >I50 GPD, the Operations Manager will decide to shutdown the plant.

RO RO RO/BOP Booth Operator Instructions:

Operates Trigger #2 (SGN04B (.4 gpm)).

I AR-PPCS-1 SGTL Indicated Monitor PRZR Level.

NOTE: Przr Level will be stable at this leak rate.

Monitor S/G Tube Leak Rate:

PPCS Point R15A5G Trend S/G Leak Rate:

While continuing with this procedure, perform Part A of ATT-16.1, ATTACHMENT SGTL I

I R-15 in alarm (3 minutes delayed)

IF any condition below is met, THEN go to AP-SG.1:

R15A5G (PPCS) greater than 5 gpd AND INCREASING for greater than one (1) minute.

Appendix D Operator Action Form ES-D-2 1

Scenario #

2 Event#

2 Page 2 of 32 Op Test No.:

Event

Description:

B Steam Generator Tube Leak Time I

Position I

Applicants Actions or Behavior I

Determine S/G leak rate:

RO I

I I

P P C S D ~ ~ ~ ~ R I ~ A ~ G I

Monitor R-19 for approximately two (2) minutes.

I I

I NOTE: SGTL rate will exceed the TS Limit of 150 gpd.

I An-16.1, ATTACHMENT SGTL.

~~

I RO Primary to secondary leakage in at least one S/G 2 5 gpd Reauest RP oerforrn a second samole Notifv RP to irndernent Drocedure CH-SAMP-SG-I LEAKRATE.

Refer to ITS LCO 3.7.14 Notify Chemistry to determine desired S/G blowdown flowpath.

Check operability of the following monitors.

I R-15 R-15A R-19 I

R-31 I

R-32 I

Dispatch an A 0 to perform T-35H, Nuclear House Heating Steam To Boiler Steam SUDD~V chanae Over.

IF the leaking S/G has NOT been identified, THEN perform the following to identify the leaking S/G. (Valves located in IB hot side, outside sample room).

Direct an A 0 to close V-996A, inlet block valve to Fl-2027 (S/G blowdown Hx A outlet flow) 4OTE:

LOA SGN 24 to 0 to CLOSE V-996A.

Appendix D Operator Action Form ES-D-2 Ro OpTest No.: -

1 Scenario# -

2 Event#

2 Page of 32 Event

Description:

B Steam Generator Tube Leak Time 1

Position I

Applicants Actions or Behavior Open V-996A, inlet block valve to Fl-2027 (S/G blowdown Hx A outlet flow).

SRO I BOOTH OPERATORS NOTE:

LOA SGN024 to 100% to OPEN V-996A.

I Primary to secondary leakage in at least one S/G 2 75 gpd I

AP-SG.l, STEAM GENERATOR TUBE LEAK.

I BOP SRO I Determine If Shutdown Required:

Place Hotwell level controller in Manual at 50% position.

S/G tube leak rate GREATER THAN OR EQUAL TO 75 I

GPD I

~ I-I I

S/G tube leak rate - STABLE OR RISING I

I I

Go to Step 6.

I SRO 1 Confirm S/G Leak Rate:

Notify higher supervision While continuing with this procedure, perform Parts A AND B of ATT-16.1, ATTACHMENT SGTL An-16.1, AlTACHMENT SGTL.

I I

I Refer to ITS LCO 3.7.14 I

Refer to EPIP-I.O, Ginna Station Event Evaluation and I

Classification.

I I

Refer to 0-9-3, NRC IMMEDIATE NOTIFICATION.

I

Appendix D Operator Action Form ES-D-2 Bop OpTest No.:

1 Scenario# -

2 Event#

2 Page 12-of 32 Event

Description:

6 Steam Generator Tube Leak Time I

Position I Applicants Actions or Behavior RO 1 Start the A and B CNMT Auxiliary Charcoal Filter Fans.

PULL STOP the TDAFW Pump Steam Admission valve from the leaking SIG.

SRO I Consult with WP Chemistrv.

Shift Support Heating Steam Trap Outlet Valves from the trap header to Blowdown Tank.

BOPIA0 I BOPIAO I Request identification of leaking SIG from the Control Room.

I 1

Close trap drain isolation valve upstream of MSlV on the leaking S/G.

BOPIAO I Verify Blowdown Tank discharge valve V-5714 is closed (at SIG Blowdown Tank).

BOPIAO I I

BOPIAO I Isolate Blowdown from the leaking SIG.

SRO I Refer to ITS LCO 3.7.5.

SRO 1 Refer to TRM 3.4.3.

I SRO I Notify RP to survey.

I I Notify RPs to verify that airborne contaminants that may be discharging from steam reliefs OR the Air Ejector are NOT SRo 1 being pulled into the supply air handling units.

I AP-SG.l, STEAM GENERATOR TUBE LEAK.

Appendix D Operator Action Form ES-D-2 OpTest No.: -

1 Scenario# -

2 Event#

2 Page '3 of 32 Event

Description:

B Steam Generator Tube Leak Time I

Position I

Applicant's Actions or Behavior Initiate Plant Shutdown I

Determine S/G leak rate every 15 minutes I

Check S/G leak rate - RISING LESS THAN 30 GPD/HR I

Check R15A5 - OPERABLE Check S/G leak rate - HAS REMAINED LESS THAN 144 GPD SINCE LEAK INITIATION I

Be in Mode 3 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months of exceeding 144 gpd. (Refer to 0-2.1. NORMAL SHUTDOWN TO HOT SHUTDOWN)

Refer to ITS LCO 3.4.13 LCO 3.4.16 LC03.7.14 Check following Tech Specs LCO 3.7.14 I

SECONDARY SPECIFIC ACTIVITY LCO 3.4.1 6 I

RCS SPECIFIC ACTIVITY LCO 3.4.13 RCS OPERATIONAL LEAKAGE RCS operation LEAKAGE shall be limited to 150 gallons per day primary to secondary leakage through any one SG.

Appendix D Operator Action Form ES-D-2 Page 14 of 32 -1 OpTest No.: -

1 Scenario# -

2 Event#

2 Event

Description:

B Steam Generator Tube Leak I

Time I

Position I

Applicant's Actions or Behavior CONDITION REQUIRED ACTION COMPLETION TIME A.

RCS LEAKAGE not A.1 Reduce LEAKAGE hoUrS within limits for reasons other than pressure boundary lo within limits.

I I

1 LEAKAGE I

I

~~

At the Discretion of the Lead Examiner Move to Event #3.

Appendix D Operator Action Form ES-D-2 BOP OpTest No.: -

1 Scenario# 2 Event#

3 Page 5 of 32 Event

Description:

Rapid Downpower Time I Position I

Applicant's Actions or Behavior Reduce turbine load in AUTO at follows:

Place Turbine EH control in OPER PAN. IMP PRESS OUT. If desired.

The Operator will commence a plant shutdown to Hot Standby at l%/minute in accordance with AP-TURB.5, "Rapid Downpower."

Booth Operator Instructions:

Operate Trigger #3 (RODl A-66).

(Note that this will cause the Continuous Rod Withdrawl malfunction to occur as soon as Rods receive a signal to move in Automatic).

RO Indications Available: NA Depress the GO button.

Initiate boration at -2 aal/% load reduction.

Select desired rate on thumbwheel Reduce the setter to the desired load.

AP-TURB.5, RAPID LOAD REDUCTION Ro I

SRO I Initiate Load Reduction Adjust Boric Acid Addition Rate As Necessary To (Refer to OPG-REACTIVITY-CALC):

I RO I

Verify rods in AUTO 1

RO I

Place PRZR backuD heaters switch to ON.

RO I Monitor RCS Tavg I

Tava - GREATER THAN 545°F I

I Tava - LESS THAN 579°F 1

I Maintain rods above the insertion limit.

Match Tava and Tref I

I Cowensate for Xenon

Appendix D Operator Action Form ES-D-2 Ro OpTest No.: -

1 Scenario# -

2 Event#

3 Page 16 of 32 Event

Description:

Rapid Downpower Time I

Position I Applicant's Actions or Behavior RO I Monitor PRZR Pressure -TRENDING TO 2235 PSlG IN AUTO I Monitor MFW Regulating valves - RESTORING S/G LEVEL TO 52% IN AUTO Monitor PRZR Level -TRENDING TO PROGRAM IN AUTO CONTROL BOP RO I Check IA Available To CNMT I

IA Diessure - GREATER THAN 60 PSlG Check Hotwell Level:

Hotwell level controller in AUTO Controller demand LESS THAN 60%

I 7-I lnstr Air to CNMT Is01 Valve AOV-5392 - OPEN I

I I

BOP I Check Steam DumD Status:

I I

7-I Annunciator G-15. STEAM DUMP ARMED - LIT I

I I

I Steam dump operating properly in AUTO I

I I

I Hotwell level at setpoint I

BOP I Check if Condensate Booster Pumps Should be secured.

At the Discretion of the Lead Examiner Move to Event #4.

Appendix D Operator Action Form ES-D-2 RO OpTest No.: -

1 Scenario# -

2 Event#

4 Page 21-of 32 Event

Description:

Uncontrolled Automatic Rod Motion Occurs Time I

Position I

Applicants Actions or Behavior Monitor Tavg:

Check Tavq -TRENDING TO Tref Following the start of the shutdown, uncontrolled rod motion will occur. The operator will respond in accordance with AP-RCC.1, Continuous Control Rod Withdrawl\\lnsertion, and dace rods in manual.

Bop I Booth Operator Instructions: NA (Malfunction inserted at time of Event #3)

I Check RCS Tavg Channel Indications:

Check Turbine 1 Stage Pressure Channel, PI-485 -

APPROXIMATELY EQUAL TO PI-486 Indications Available:

I Control Rods step out in automatic.

RO AP-RCC.l, CONTINUOUS CONTROL ROD WITHDRAWAUINSERTION.

Check NIS PR Indication:

All Power Range Channels approximately equal.

I RO/BOP I Evaluate Rod Control System Operability:

I Check turbine load - STABLE I-I Place Rods to MANUAL I

I I

Verify control rod motion STOPS I

All AI Indicators approximately equal.

I 1

RO I Establish Stable Plant Conditions:

I Tavg Trending to Tref.

I Przr Pressure Trending to 2235 psig in Auto.

Przr Level trending to Program in Auto control.

1 RIL Alarms - Extinquished.

Appendix D Operator Action Form ES-D-2 RO Op Test No.: -

1 Scenario# -

2 Event#

4 Page 18 of 32 Event

Description:

Uncontrolled Automatic Rod Motion Occurs Time 1

Position 1

Applicant's Actions or Behavior 1 NIS PR AI within desired oDeratina band.

Verify Control Rods Operable In Manual:

Crew I

I I

Verify MRPl indicates control rod motion I

Evaluate MCB Annunciator Status I

I 1

Restore control rods to desired position I

RO I Establish Control Svstems In Auto:

I

~~~

I I Control Rods in Auto.

I Przr Pressure in Auto.

I SDrav Valves in Auto.

Przr Heaters restored.

Verify one Charging Pump in Auto.

I

~~

I SRO I Notify Higher Supervision I

At the Discretion of the Lead Examiner Move to Event #5.

Appendix D Operator Action Form ES-D-2 RO RO

~~

~~~

OpTest No.: -

1 Scenario# -

2 Event#

5 Page 19 of -

32 Perform a channel check.

Check charging and letdown.

Event

Description:

Przr Level Instrument Malfunction Time I

Position I

Applicant's Actions or Behavior I

Once AP-RCC.l is complete, the shutdown will recommence. During the shutdown, Pressurizer Level Channel LT-428 will slowly fail high. The operator will respond in accordance with AR-F-4, "Pressurizer Level Deviation -5 Normal +5," and AR-F-28, "Pressurizer High Level Channel Alert 87%," and then address ER-INST.l, "Reactor Protection Bistable Defeat After Instrumentation Loop Failure." The operator will take manual control of the Charging Pumps and control Pzr Level. The operator will address Technical Specifications 3.3.1, "Reactor Trip System Instrumentation," 3.3.2, "ESFAS Instrumentation," and 3.3.3, "PAM Instrumentation."

Booth Operator Instructions:

Indications Available:

Operate Trigger #4 (PZR03C (100)).

I I Charging Flow decreases.

1 F-4, PRESSURIZER LEVEL DEVlAlTON - 5 NORMAL + 5 I F-28, PRESSURIZER HIGH LEVEL CHANNEL ALERT 87%

ARF-4, PRESSURIZER LEVEL DEVlAlTON - 5 NORMAL + 5 RO Perform a channel check.

I RO I Verify Backup Heaters on at + 5%.

RO Check charging pump speed and controls.

I RO I Check Letdown in service.

RO I Control Charging and Letdown as necessary to control level.

I ER-INST.1 for failed channel.

Appendix D Operator Action Form ES-D-2 OpTestNo -

1 Sccnarion -

2 Eventn 5

Page 20 01 32 Event Descript on Przr Level Instrument Malfunction Time I

Postion I

Appxants Actions or Behav or SRO I For failed channel go to ER-INST.l.

I ER-ISNT.1, Reactor Protection Bistable Defeat After Instrumentation Loop Failure.

Identify the failed instrument channel by observation of the bistable status light board, MCB annunciators, and the MCB metering indication.

SRO/RO When identified, refer to the appropriate section for PRZR Level Failure (4.5).

SRo I

I SRO I (4.5) PRZR LEVEL CHANEL FAILURE IF PRZR low level heater cut and has occurred, THEN monitor PRZR pressure AND DEFEAT failed channel in a timely manner to allow restoration of PRZR heaters.

NOTE: Przr Level Instrument has failed high, and low level Heater Cutout has not occurred.

SRO If Letdown Isolation Valve, AOV-427 has closed, Then perform I

SRo I the following:

I I

I NOTE: Letdown Isolation Valve AOV-427 has NOT closed Refer to the appropriate attachment for defeat of the associated I

SRo I control functions.

I I

I Przr Level Ll-428 Blue Channel I

BLUE CHANNEL ATACHMENT PRZR Ll-428 In the PLP PRZR PRESS AND LEVEL rack, check PRZR level I

Ro I defeat switch L\\428A position.

Appendix D Operator Action Form ES-D-2 I

RO OpTest No.: -

1 Scenario# -

2 Event #

5 Page 21 of 32 Event

Description:

Przr Level Instrument Malfunction Time I

Position I Applicants Actions or Behavior I Reset PRZR Heater breakers as necessarv.

If L\\428A is in Normal, THEN place L-428A to DEFEAT-3.

RO OR Restore normal letdown.

If L\\428A is NOT in Normal, THEN notifv the Shift Manaaer.

In the (BLUE) B-1 Protection Channel 3 rack, PLACE the bistable proving switch 428, Channel 3 High Level Trip to Defeat (Up). Proving light will be off if the channel failed high.

If any proving light status is not correct, then submit a Condition Report on the discrepancy and continue with the channel defeat steps.

Place Przr Level Recorder transfer switch to position 427.

Verify the bistable status light above is lit. If the bistable status light is NOT lit, Then the channel may not be in the tripped condition. Further investigation is necessary to ensure ITS reauirements are met.

Remove the PRZR Level channel from the PPCS.

~~~

NOTE: Attachment is complete, SRO will return to body of procedure.

ER-ISNT.1, Reactor Protection Bistable Defeat After Instrumentation Loop Failure.

I When PRZR Level is restored to normal. Then Dlace an nu I operating charging pump controller in AUTO.

I SRO I Check the following Technical Specifications:

I

OpTestho -

1 Scenario (f -

2 Event n 5

Page 22 of 32 Event Description Przr Level Instrument Malfunction Time I

Position I Applicant's Actoons or Benavior SRO C

Required Adon and associated Completion Time of Condition D. E. 0, F is not met.

SRO G.1 Be in MODE 3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months SRO SRO SRO SRO SRO Section 3.3.1. Table 3.3.1-1, Function 8 Section 3.3.3, Table 3.3.3-1, Function 2.

Section 3.4.9.

LCO 3.3.1 - The RTS instrumentation for each Function in Table 3.3.1-1 shall be OPERABLE.

Applicability: According to Table 3.3.1-1. Function 8 - Przr Water Level Hiqh.

0.

As required by Required D.l ActionA.1 and referenced by Table 3.3.1-1.

- NOTE -

The inoperable channei may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing of other channels.

Place channel in trip.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Applicability: Modes 1, 2 and 3.

CONDITION I

REOUIRED ACTION 1 COMPLETION TiME F.

As required by Required 1 Be in MODE 3.

~ 1 hours1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Action E.l and referenced in Table 3.3.3~1 Be in MODE 4 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

Form ES-D-2 Appendix D Operator Action CONDITION REQUIRED ACTION A.

Pressurizer water level A 1 Be in MODE 3 wlth reactor not wthin limit.

trip breakers Open.

AND A 2 BeinMODE4 OpTest No.: -

1 Scenario# 2 Event#

5 Page 23 of 32 Event

Description:

Przr Level Instrument Malfunction Time I

Position I Applicant's Actions or Behavior COMPLETION TIME 6 houn 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SRO SRO SRO LCO 3.4.9 - The Pressurizer shall be OPERABLE.

Applicability: Modes 1, 2 and 3 At the Discretion of the Lead Examiner Move to Events #6-9.

Appendix D Operator Action Form ES-D-2 OpTest No.: -

1 Scenario# -

2 Event#

6,7,8

& 9 Page 24 of 32 Event

Description:

Inadvertent SI, ATWS, B MDAFW Pump Trip, TDAFW Pump Trip Time I

Position I Applicants Actions or Behavior BOP After about 10-15% power reduction, an inadvertent Safety Injection signal will occur (The Automatic Reactor Trip is blocked, and the manual MCB pushbuttons will not operate). The operator will enter E-0, Reactor Trip or Safety Injection, and de-energize Busses 13 and 15 to de-energize the Rod Drive Motor Generators and cause a reactor trip. The B MDAFW Pump will fail to automatically start. When started by the operator, the pump will trip within 60 seconds. Upon start up of the TDAFW Pump, the pump will trip on overspeed and be damaged to the point that it can no longer be used. This will eventually cause a Red Path on Heat Sink and the operator will transition to FR-H.l, Response to Loss of Secondaty Heat Sink.

Verify Turbine Stop Valves - CLOSED.

Booth Operator Instructions:

Indications Available:

Operate Trigger #5 (SISOl (0)).

I I

I One Train of SI actuates.

I Reactor remains at power.

E-0, REACTOR TRIP OR SAFETY INJECTION.

I I

RO I Verify Reactor Trip NOTE: Reactor does not trip on Inadvertent SI and must be tripped manually.

RO 1 Manuallv trip reactor.

NOTE: The manual pushbuttons are not successful in tripping the reactor.

BOP I TriD the reactor as follows:

I

~ r -

1 ODen Bus 13 and Bus 15 normal feeder breakers.

I I

Verify Rod Drive MG Sets tripped.

I I

Close Bus 13 and Bus 15 normal feeder breakers.

I I

Reset Lighting Breakers.

I Critical Task (E-&A) Trip the reactor before both Steam Generator Wide Range Levels decrease to less than 35.

Verify Both Trains of AC Emergency Busses Energized To At I

Bop I Least 420 VOLTS:

Appendix D Operator Action Form ES-D-2

~

~~

~

Page 25 of 32 OpTest No.: -

1 Scenario # 2 Event #

6,7,8

& 9 Event

Description:

Inadvertent SI, ATWS, B MDAFW Pump Trip, TDAFW Pump Trip Time I

Position I

Applicants Actions or Behavior BOP I

I RO/BOP I Check if SI is Actuated:

I Verify Both MDAFW Pumps Running I

SI sequencing - BOTH TRAINS STARTED.

BOP RO 1 Manually actuate SI and CI.

Verify AFW Valve Alignment:

I I

RO I Verify CNMT Spray Not Required:

I BOP Direct Operator to Perform ATT-27.0, ATTACHMENT AUTOMATIC ACTION VERIFICATION while the other board operator works with the CRS to continue on in E-0.

Manually align valves as necessary.

BOP I

1 BOP I Manually start both MDAFW pumps.

I Verify total AFW flow - GREATER THAN 200 GPM NOTE A MDAFW Pump 00s and B MDAFW will fail to Auto Start. It must be started manuallv.

IF less than 2 MDAFW pump are running, THEN manually open TDAFW pump steam supplv valves.

I

~

BOOTH OPERATORS NOTE:

Operate Trigger #30 (FWDllB) and Trip B MDAFW Pump 2 minutes after pump start.

BOP I Monitor Heat Sink:

1 0 Check S/G narrow ranae level - GREATER THAN 7%.

SRO I

FR-H.l, RESPONSE TO LOSS OF SECONDARY HEAT SINK.

IF total AFW is less than 200 gpm, THEN manually start pumps and align valves to establish greater than 200 gpm AFW flow.

IF AFW flow greater than 200 gpm can NOT be established.

HEAT SINK, Step 1.

THEN go to FR-H.l, RESPONSE TO LOSS OF SECONDARY Check If Secondarv Heat Sink Is Required:

RCS pressure - GREATER THAN ANY NON-FAULTED SIG PRESSURE Check RCS cold leg temperature - GREATER THAN 350°F Monitor Secondary Heat Sink:

Verify either S/G level -WIDE RANGE GREATER THAN 50 inches.

Verify PRZR pressure - LESS THAN 2335 PSIG.

Tw to Establish AFW Flow To At Least One Intact SIG:

Verify 2 MDAFW pumps - AVAILABLE NOTE: Both MDAFW Pumps are unavailable.

Verify TDAFW pump available.

NOTE: The TDAFW Pump has undergone an Overspeed Trip and cannot be reset.

StoD Both RCPs Move to Event #lo.

Appendix D Operator Action Form ES-D-2 Op Test No.: -

1 Scenario# 2 Event#

10 Page 27 of 32 Event

Description:

S A W Flow Transmitters are Isolated Resulting in Pump Run Out of S A W Pump. (Pumps Trips < 60 Seconds After Start)

RO I

Time I

Position I

Applicant's Actions or Behavior Align SAFW Pump C to selected S/G as follows:

Ensure SI Reset Ensure the followina valves oDen:

The operator will attempt to start the S A W system to provide flow to one SG, however, both Flow Transmitters (FT-4084 and 4085) will have been isolated from Shutdown, and the S A W pumps when started will reach runout conditions and trip on overcurrent within 60 seconds. (LER 2006-4). Feed flow will be restored to one Steam Generator using a Condensate and a Main Feedwater Pump. Once feed flow is restored to one Steam Generator the operator will transition back to ES-0.1, "Reactor Trip Response."

BOP 1 Booth Operator Instructions:

Operate trigger #29 at the start of SAFW pump C (FWDl5A 60 seconds delayed).

To feed S/G A.

Verify at least 1 SW pump running.

Restore SAFW flow as directed bv DrOCedUre in effect.

1 Indications Available:

I I

1 RO I Reset SI If Actuated I

RO 1 Trv To Establish S A W Flow To At Least One Intact S/G:

I I

I Align SAFW system for operation (Refer to ATT-5.1.

I All-5.1, "ATTACHMENT SAFW."

I I

I MOV-9701A. S A W PUMP C DISCHARGE VLV I

I I

1 MOV-4616, AUX BLDG SW ISOL VLV I

I I

I MOV-9704A, S A W PUMP C ISOL VLV I

I I

1 Open MOV-9629A, SAFW PUMP C SUCTION VLV.

I Determine SAFW flow requirements per ATT-22.0, I

ATTACHMENT RESTORING FEED FLOW

Appendix D Operator Action Form ES-DP

~

OpTest No.. -

1 Scenario# -

2 Event#

10 Page 28 r

I Event

Description:

S A W Flow Transmitters are Isolated Resulting in Pump Run Out of SAFW Pump. (Pumps Trips < 60 Seconds After Start)

I Time I

Position I ApplicanVs Actions or Behavior Am-22.0, ATTACHMENT RESTORING FEED FLOW.

NOTE:

SROIBOP SROIBOP SROIBOP RO Initiate Feed flow as follows:

IF feedwater flow to affected SIG greater than 50 gpm OR affected SG level greater than 50 inches (100 inches adverse CNMT). THEN fill as desired to restore narrow range greater than 7% (25% adverse CNMT) and go to step 2 of this attachment.

IF NOT, THEN establish less than or equal to 100 gpm feed flow to affected SIG. WHEN SIG level greater than 50 inches (100 inches adverse CNMT), THEN fill as desired to restore narrow range greater than 7% (25% adverse CNMT) and go to step 2 of this attachment.

Start selected S A W DumD(s).

Pump will start and trip 60 seconds later. Crew will return to Step 6 and attempt to start D SAFW pump.

RO 1 Trv to Establish S A W Flow To At Least One Intact SIG:

I I

I Perform the following:

Align SAFW system for operation (Refer to ATT-5.1 ATTACHMENT SAFW)

ATT-5.1, ATTACHMENT SAFW.

RO I Align S A W Pump D to selected SIG as follows:

Ensure SI Reset Ensure the following valves open:

MOV-9701B. SAFW PUMP D DISCHARGE VLV

Appendix D Operator Action Form ES-D-2 RO OpTest No.: -

1 Scenario# -

2 Event #

10 Page 29 of 32 Event

Description:

S A W Flow Transmitters are Isolated Resulting in Pump Run Out of SAFW Pump. (Pumps Trips < 60 Seconds After Start)

Time I

Position I

Applicants Actions or Behavior MOV-4615. AUX BLDG SW ISOL VLVS To feed S/G A, perform the following:

Close MOV-9704B, SAFW PUMP D ISOL VLV Ooen either SAFW CROSSOVER VLV:

I I

I MOV-9704B. SAFW PUMP D ISOL VLV I

RO I

I I

MOV-9746, SAFW PMP D EMERG DISCH VLV I

Restore SAFW flow as directed by procedure in effect.

Verify open MOV-9704A, SAFW PUMP C SOL VLV I

I 1

Open MOV-9629B, SAFW PUMP D SUCTION VLV.

I BOP I

Verify at least 1 sw pump running.

I I

I MOV-9703A I

OR I

I I

MOV-9703B I

Determine SAFW flow requirements per ATT-22.0 I

ATTACHMENT RESTORING FEED FLOW AT-22.0. AlTACHMENT RESTORING FEED FLOW.

I SROIBOP SROIBOP SRO/BO?

Initiate Feed flow as follows:

IF feedwater flow to affected S/G greater than 50 gpm OR affected SG level greater than 50 inches (100 inches adverse CNMT). THEN fill as desired to restore narrow range greater than 7% (25% adverse CNMT) and go to step 2 of this attachment.

IF NOT, THEN establish less than or equal to 100 gprn feed flow to affected S/G. WHEN S/G level greater than 50 inches (100 inches adverse CNMT), THEN fill as desired to restore narrow range greater than 7% (25% adverse CNMT) and go to step 2 of this attachment.

Appendix D Operator Action Form ES-D-2 OpTest No.: -

1 Scenario# -

2 Event#

10 Page 30 of 32 Event

Description:

S A W Flow Transmitters are Isolated Resulting in Pump Run Out of SAFW Pump. (Pumps Trips < 60 Seconds After Start)

Time I

Position I Applicant's Actions or Behavior SRo I

I RO I Start selected S A W pump@)

IF greater than 235 gpm total SAFW flow can NOT be established, THEN go to Step 7 BOOTH OPERATOR NOTE:

Operate trigger #28 at the start of SAFW D (FWD15B 60 seconds delayed).

FR-H.1. RESPONSE TO LOSS OF SECONDARY HEAT SINK Try to Establish MFW Flow to at Least One SIG Check anv MFW Durn0 AVAILABLE

~

Check condensate svstem:

Condensate pump - ANY RUNNING MFW pump suction pressure GREATER THAN 200 PSlG Establish MFW flow:

Check MFW pump discharge valves - CLOSED Verify MFW regulating or bypass valves -

OPERABLE Depress MANUAL pushbuttons for A and B MFW regulating valve and bypass valve controllers AND adjust to 0% demand.

Open MFIV's for both SIG's:

SIG A, AOV-3995 SIG B, AOV-3994 DisDatch A 0 to restore MFW DumD SW coolina

~~

~

Verifv SIG blowdown kev switches in NORMAL Ensure Annunciator H-4, MAIN FEED PUMP OIL SYSTEM - EXTINGUISHED

Appendix D Operator Action Form ES-D-2 SRO/BOP OpTest No.: -

1 Scenario# -

2 Event#

10 Page 31 of 32 Event

Description:

S A W Flow Transmitters are Isolated Resulting in Pump Run Out of S A W Pump. (Pumps Trips < 60 Seconds After Start)

Initiate Feed flow as follows:

I Time I

Position I

Applicant's Actions or Behavior SRo/BoP Ensure Annunciator H-11, FEED PUMP SEAL WATER LO Close Condensate Bypass valve, AOV-3959.

DlFF PRESS 15 PSI - EXTINGUISHED IF feedwater flow to affected S/G greater than 50 gpm OR affected SG level greater than 50 inches (100 adverse CNMT),

THEN fill as desired to restore narrow range greater than 7%

(25% adverse CNMT) and go to step 2 of this attachment.

I 1

Ensure one MFW pump recirc valve - OPEN SRO/BOP 1

I Start Selected MFW pump Ooen MFW oumo discharae valve IF NO, THEN establish less than or equal to 100 gpm feed flow to affected S/G. WHEN S/G level greater than 50 inches (100 inches adverse CNMT), THEN fill as desired to restore narrow range greater than 7% (25% adverse CNMT) and go to step 2 of this attachment.

NOTE: There are no useable flow meters to ensure feeding requirements are restricted when using Main Feedwater. The direction must be '"Slowly feed Steam Generators to establish a rising level."

~

I O E n MFW rzulatina or bvDass valves to control MFW Ro flow per requiGmentsof Afi-22.0, ATTACHMENT I

RESTORING FEED FLOW Check RCS Loop Hot Legs - BOTH HOT LEG TEMPERATRUES DECREASING An-22.0, AlTACHMENT RESTORING FEED FLOW Critical Task (FR-H.1-A)

Establish Feedwater flow into at least one Steam Generator before Bleed and Feed Criteria is met in FR-H.l.

Appendix D Operator Action Form ES-D-2 OpTest No.: -

1 Scenario# 2 Event#

10 Page 32 of 32 Event

Description:

SAFW Flow Transmitters are Isolated Resulting in Pump Run Out of SAFW Pump. (Pumps Trips c 60 Seconds After Start)

BOP Time I

Position I

Applicant's Actions or Behavior Verify affected S/G is not faulted or ruptured.

NOTE: The SG with the higher level is the B SG with a Tube Leak. Efforts should be made to feed this generator regain a Heat Sink, and then continue to feed the A SG.

FR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK I

I I

SRO IGotoStep11.

BOP I Check S/G Levels:

Narrow range level in at least one S/G -GREATER THAN I

7% (25% adverse CNMT)

T S R

O

~

Return to DrOCedUre and step in effect.

Booth Instructor: Freeze the Simulator EAL 1.3.1 (SAE)

Red Path on Heat Sink Modes 1-4.

Scenario Event Description NRC Scenario 4

~~

Ginna 2007 NRC Scenario #4 The Plant is at 100% power Steady-State (BOL), and has been for the last 9 days following Refueling Outage.

The following equipment is Out-Of-Service: A MDAFW Pump (Expected back in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ),

Containment Pressure channel PT-945 (The channel has been defeated per ER-INST.l) and MCB Annunciator J-8 has alarmed spuriously several times over the last hour (lac is investigating).

Shortly after taking the watch, a nitrogen leak will develop on the B Accumulator. The operator will respond in accordance with AR-C-12, Accumulator 1B (Loop A) Press 720 Psi 760. The crew will investigate and determine a slow N2 leak has occurred, and seek to add Nitrogen in accordance with S-16.2, Nitrogen Make-up To The SI Accumulators. The operator will address Technical Specification 3.5.1, Accumulators.

After the Accumulator Technical Specification is addressed, the I Stage Pressure Transmitter PT-485 will fail low. The control rods will move inward if in Auto, and the operator will respond in accordance with AP-RCC.l, Continuous Control Rod Withdrawalllnsertion. The operator will address ER-INST.1, Reactor Protection Bistable Defeat After Instrumentation Loop Failure, to defeat the channel.

Shortly after this, the A FRV controller will fail such that the FRV will start to close. The operator will need to recognize the failure, and take manual control of the controller, re-open the FRV, and stabilize the plant. The operator will enter AP-FW.l, Abnormal Main Feedwater Flow. The Condensate Booster Pumps will trip if the A FRV closes. If this occurs the operator will be directed to reduce power to < 80% in accordance with AP-TURB. 5,Rapid Load Reduction.

After completion of AP-FW.1, the main turbine will experience high vibrations. The operator will respond in accordance with AR-1-27, Rotor Eccentricity Or Vibration, which will require that AP-TURB.3, Turbine Vibration, be addressed. This will require a load decrease in accordance with AP-TURB.5, Rapid Load Reduction.

During the load decrease a rod lift coil for a D Bank rod fails (Blown fuse) causing a misaligned rod. The operator will respond in accordance with AP-RCC.2, RCC/RPI Malfunction, and address Technical Specification 3.1.4, Rod Group Alignment Limits.

Following this, an electrical fault will occur on the C Instrument Bus resulting in a loss of the bus, and a Safety Injection actuation. The operator will enter E-0, Reactor Trip or Safety Injection.

On the Safety Injection actuation, both the A and B SI Pumps will fail to auto start and require manual starting.

When MOV-852B opens (RHR to Rx Vessel) on the SI actuation, CV-853B fails causing an inter-system LOCA (to RHR). The RHR common header fails from overpressure resulting in a LOCA outside Containment.

The operator will transition to ECA-I.2, LOCA Outside Containment. Upon completion of ECA-I.2, the operator will transition to E-1, Loss of Reactor or Secondary Coolant.

The scenario will terminate at Step 12e of El, after the crew decides to transition to ES-1.1, SI Termination.

Scenario Event Description NRC Scenario 4 Critical Tasks:

E-0 I Establish flow from at least two SI pumps before transition out of E-0.

E-1 C Trip all RCPs within 5 minutes of reaching the trip criteria.

ECA-1.2 A Isolate the LOCA outside Containment before transitioning out of ECA-1.2.

Scenario Event Description NRC Scenario 4 1

2 3

4 5

Simulator Set Up IND-SIS43 on Trigger #I A-SISOG (On) on Trigger #1 (Annunciator C-12 to On)

TUR16A (0 psig) on Trigger #2 FDW07A (0%) on Trigger #3 TUR05H (9 mils) on Trigger #4 (Bearing 8)

NA IC-l74C Place Hold Tags on:

Place Protected Equipment Tags on:

B MDAFW Pump Control Switch Insert:

FDWl 1A - A MDAFW Trip, (Pull/Stop, Hold Tag, Close MOV-4007, Protective Covers on B MDAFW Pump)

IND-MIS36 PT-945 Failure RPS07A RPS07B A MDAFW Pump Control Switch Close and Tag MOV 4007 Contrc. Switch A SI Pump fails to Auto Start B SI Pump fails to Auto Start 7

8 9

EDS07C on Trigger #5 RPS07NB at T=O RCSl9D (900 gpm) on Trigger #5 6

1 ROD03 on Triooer #30 conditional on T:N41B.LE.85 1

Scenario Event Description NRC Scenario 4 Shift Turnover:

The Plant is at 100% power Steady-State (BOL), and been for the last 9 days following Refueling Outage.

The following equipment is Out-Of-Service: A MDAFW Pump (Expected back in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ),

Containment Pressure channel PT-945 (The channel has been defeated per ER-INST.l) and MCB Annunciator J-8 has alarmed spuriously several times over the last hour (I&C is investigating).

Scenario Event Uescription NRC Scenario 4 A-52.4 Equipment PT-945 4 MDAFW Pump Date I I07 I I07 Time 1330 Reason Failed Cham 3earing

,eplacement Required Actions ITS 3.3.2 Condition A Enter Condition referenced on Table 3.3.2-1 (IC, 2c, 4c) immediately.

Condition F (From 4c) -

Place Channel in Trip within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

Condition J (From IC, 2c) -

Place Channel in Trip within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ITS 3.7.5 Condition B Restore MDAFW train to operable status within 7 days.

Required Completion Datemime TRACK1 NG ONLY I 107 Required Action not met 2ondition G - Be in Mode 3 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and Mode 4 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

2ondition K - Be in Mode 3 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and Mode 5 within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

2ondition G - Required iction and associated

ompletion time for Condition 3 not met, be in Mode 3 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and Mode 4 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

Appendix D Operator Action Form ES-D-2 OpTest No.: -

1 Scenario# 4 Event#

1 Page I-of 41 Event

Description:

N2 Leak on B Accumulator Time I

Position I

Applicants Actions or Behavior SRO Shortly after taking the watch, a nitrogen leak will develop on the B Accumulator. The

>perator will respond in accordance with AR-C-12, Accumulator 1 B (Loop A) Press 720 si 760. The crew will investigate and determine a slow N2 leak has occurred, and seek to add Nitrogen in accordance with S-16.2, Nitrogen Make-up To The SI 4ccumulators. The ODerator will address Technical SDecification 3.5.1, Accumulators.

Refer to ITS LCO 3.5.1.

Booth Operator Instructions:

Operate Trigger #1 (IND-SIS43, A-SISO6 (On))

Indications Available:

I 1 B Accumulator Pressure low C-12, ACCUMULATOR 1B (LOOP A) PRESS 720 PSI 760 AR-C-12, ACCUMULATOR 1B (LOOP A) PRESS 720 PSI 760.

Add N2 (S-16.2) OR water (5-16.13) to accumulator until

-740 Dsia k 15).

RO I

SRO I LCO 3.5.1 I Two ECCS accumulators shall be OPERABLE.

1 SRO I APPLICABILITY:

I I MODES 1 and 2 I

I MODE 3 with pressurizer pressure > 1600 psig.

I SRO CONDITION

8.

One accumulator inoperable for reasons other than Condition A.

REQUIRED ACTION 8.1 Restore accumulator to OPERABLE status.

COMPLETION TIME 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months At the discretion of the Lead Examiner move to Event #2.

Appendix D Operator Action Form ES-D-2 Transmitter PT-485 will fail low. The control rods will move inward if in Auto, and the operator will respond in accordance with AP-RCC.1, "Continuous Control Rod Withdrawalllnsertion." The operator will address ER-INST.l, "Reactor Protection Bistable Defeat After Instrumentation Loop Failure," to defeat the channel.

Booth Operator instructions:

indications Available:

Operate Trigger #2 (TURl6A (0 psig))

Op Test No '

1 Scenario# -

4 Event#

2 I

I F-16, Tavg - Tref Deviation +I-5 Degree F I Control Rods moving inward in AUTO.

G-22, ADFCS System Trouble I

AR-F-16, TAVG-TREF DEVIATION +I-5 DEGREE F I

ROIBOP t

+

AP-RCC.l, COh Check Avg Tavg and Tref indication.

Check for instrument failures on Tavg channels and Turbine first stage pressure (PI-485)

I Go to the appropriate procedure:

I AP-RCC.l (If control rod failures)

I ER-INST.l (If for instrument failures)

I NOTE: Either procedure is acceptable based on crew diagnosis. If crew goes directly to ER-INST.1, proceed to page 10 of 41.

INUOUS CONTROL ROD WITHDRAWAL I INSERTION SRO 1 Evaluate Rod Control System Operability:

I I

BOP I Check turbine Load - STABLE I

RO I Place Rods to MANUAL.

Appendix D Operator Action Form ES-D-2 OpTest No.: -

1 Scenario# 4 Event#

2 Page of 41 Event

Description:

1.' Stage Pressure Transmitter Fails Low Time I

Position I Applicant's Actions or Behavior F

tf-I SRO I

I RO RO I

I Ro RO Verify control rod motion stops.

Monitor Tava:

Tavq - GREATER THAN 545°F.

Tavg - LESS THAN 579°F Check Tava -TRENDING TO Tref Check RCS Tavg Channel Indications:

All 4 channels indicate amroximatelv the same value

~

All 4 channels responding to the power change Check Turbine 1 Stage Pressure Channel, PI-485 -

APPROXIMATELY EQUAL TO PT-486.

IF PI-485 malfunction is indicated, THEN refer to ER-INST.1, REAQCTOR PROTECTION BISTABLE DEFEAT AFTER INSTRUMENTATION LOOP FAILURE.

NOTE SRO will perform remainder of procedure in parallel with ER-INST.l.

Check NIS PR Indication:

All PR total channel indicators - APPROXIMATELY EQUAL All AI indicators -APPROXIMATELY EQUAL Establish Stable Plant conditions:

Tavg -TRENDING TO TREF 0

PRZR pressure -TRENDING TO 2235 PSlG IN AUTO PRZR level -TRENDING TO PROGRAM IN AUTO CONTROL Rod insertion limit alarms - EXTINGUISHED

Appendix D Operator Action Form ES-D-2 OpTesl No.: -

1 Scenario# -

4 Event#

2 Page '0 of 41 Event

Description:

1 Stage Pressure Transmitter Fails Low Time I

Position I Applicant's Actions or Behavior I

I RO I

I Sflo I

I SRO NIS PR AI -WITHIN DESIRED OPEATING BAND I

Verifv Control Rods ODerable In Manual:

I InserVwithdraw control rods to MRPl transition I

Verify MRPl indicates control rod motion I

Restore control rods to desired position I

Establish Control Systems In Auto:

Verify rods in AUTO I

Verify 431 K in AUTO I

Verify PRZR spray valves in AUTO I

Verify PRZR heaters restored:

I PRZR proportional heaters breaker - CLOSED PRZR backup heaters breaker - RESET IN AUTO Verify one charging pump in AUTO.

I Evaluate MCB Annunciator Status (Refer to AR Procedures).

I Refer to ITS section 3.1 for control rod operability requirements.

Notify Higher Supervision.

Return to Procedure or Guidance In Effect.

ER-INST.l, REACTOR PROTECTION BISTABLE DEFEAT AFTER INSTRUMENTATION LOOP FAILURE I

I I

I

Appendix D Operator Action Form ES-D-2 7

OpTest No.: -

1 Scenario# 4 Event#

2 Page of 41 Event

Description:

lo' Stage Pressure Transmitter Fails Low Time I

Position I Applicant's Actions or Behavior Identify the failed instrument channel by observation of the bistable status light board, MCB annunciators, and the MCB metering indication.

WHEN a failed instrument loop and/or channel has been identified, THEN refer to the appropriate section of this procedure listed below:

TURBINE FIRST STAGE PRESSURE CHANNEL FAILURE:

IF turbine first stage pressure channel PT-485 fails, THEN the followina actions should be considered:

The Rod Control Selector switch should be placed in MANUAL (485 inputs the PWER MISMATCH circuit and TREF).

The Steam Dump Mode Selector Switch should be placed in MANUAL if necessarv.

S/G level should be monitored AND controlled MANUALLY IF necessarv.

~

Refer to Attachment FIRST STAGE PRESSURE PI-485, WHITE, to defeat channel AND to restore AUTOMATIC control.

I WHITE CHANNEL ATTACHMENT FIRST STAGE PRESSURE PI-485 In the (WHITE) W1 PROTECTION CHANNEL 2 rack, PLACE the following bistable proving switch to DEFEAT (UP) AND verifv the Drovina liaht status is correct:

485 CHANNEL 2 I

TURBINE PWR TRIP Light OFF If PI-485 2 51.6 PSlG (approximately 8% RTP).

Appendix D Operator Action Form ES-D-2 OpTest No.: -

1 Scenario# -

4 Event#

2 Page 11-of 41 Event

Description:

In Stage Pressure Transmitter Fails Low Time I

Position I

Applicant's Actions or Behavior SRO/AO IF any proving light status is NOT correct, THEN submit a Condition Report on the discrepancy and continue with the channel defeat stem.

IF 2 35% power, THEN verify AMSAC feedwater Flow bistables are reset by observing the following: (FOX 3-RELAY ROOM)

RO/BOP I Verify the AMSAC TRIPPED status light (MCB) is extinguished.

RO/BOP ROlBOP SRO/AO Verify the TL 400 bistable indicating light (FOX 3-RELAY 1 ROOM) is extinquished.

IF 2 40% power, THEN verify the AMSAC AUTO BLOCK status light (MCB) is extinguished.

Delete the computer point from the PPCS by performing the following:

On the "Sub/Delete/Restore" display Select Point ID PO485 Turn "OFF scan processing Select "Change" TU466 TRIP STATUS LIGHT EXTINGUISHED TU467 TRIP STATUS LIGHT EXTINGUISHED TU476 TRIP STATUS LIGHT EXTINGUISHED TU477 TRIP STATUS LIGHT EXTINGUISHED SRO/AO PLACE switch TPS/485 (FOX 3-RELAY ROOM) to the TRIP I Dosition AND verify TU485 TRIP STATUS light is lit.

Appendix D Operator Action Form ES-D-2 SRO OpTest No.: -

1 Scenario# -

4 Event#

2 Page of 41 Event

Description:

1 Stage Pressure Transmitter Fails Low Time I

Position I

Applicant's Actions or Behavior Verify the following systems in AUTO if desired:

SRO I GO TO step 4.15.

RO I

I SRO I FOLLOW UP ACTIONS:

HC431K PRZR spray valves PRZR heaters PRZR level control IF necessary, verify an operable channel is selected for the I

Ro I affected recorder.

SRO Notifications to the following people will be made by the Shift Manaaer:

I I

RO I

Rod control I

I BOP I

Turbine EH control I

1 RO 1

PRZR Pressure control BOP I

Steam Dump (unless 1 stage pressure failed)

I I

BOP I

MFW control I

I BOP I

S/G Atmos Relief Vlv Control I

Operations Supervision During normal working hours, Maintenance personnel shall be I

SRo I notified immediately of the problem.

I At the discretion of the Lead Examiner move on to Event 3.

Appendix D Operator Action Form ES-D-2 OpTest No.: -

1 Scenario# -

4 Event#

3 Page 4 of 41 Event

Description:

A FRV Controller fails causing valve to Close Time I

Position I

Applicants Actions or Behavior BOP Shortly after this, the A FRV controller will fail such that the FRV will start to close. The operator will need to recognize the failure, and take manual control of the controller, re-open the FRV, and stabilize the plant. The operator will enter AP-FW.1, Abnormal Main Feedwater Flow. The Condensate Booster Pumps will trip if the A FRV closes. If this occurs the operator will be directed to reduce power to.= 80% in accordance with AP-TURB. 5,Rapid Load Reduction.

Booth Operator Instructions:

Indications Available:

Operate Trigger #3 (FDW07A (0%))

Perform a channel check of LI-461, Ll-462, and Ll-463.

I Feed flow in A SG decreases.

I G-3, SG A Level Deviation + 7%

Control SG Level manually.

Place FW Flow Loop A Bypass VLV HCV-480 in MANUAL.

I AR-G-3. SG A LEVEL DEVIATION + 7%

I I

I BOP 1 If necessary perform the following:

I I

Place SG A MFW REG VLV HCV-466 in MANUAL.

I SRO I For a valid feed control problem, go to AP-FW.1 I

I I

AP-FW.l, ABNORMAL MAIN FEEDWATER FLOW I

SRO I Check MFW Reauirements:

I I

RO I

Power - GREATER THAN 50%.

I I

I BOP I

Both MFW pumps - RUNNING.

I SRO I GO to Step 3.

BOP I Verifv At Least One MFW PumD - RUNNING

Appendix D Operator Action Form ES-D-2 OpTest No.: -

1 Scenario# -

4 Event#

3 Page 15 of 41 Event

Description:

A FRV Controller fails causing valve to Close Time I

Position I

Applicants Actions or Behavior Check S/G Status MFW flows - GREATER THAN STEAM FLOWS S/G levels stabilizing or returning to program IF MFW regulating valves NOT controlling in AUTO, THEN place affected S/G(s) MFW regulating valve and bypass valve in MANUAL and restore S/G level to 52%.

Verify At Least 2 Condensate Pumps - RUNNING.

Verify Both HDT Pumps - RUNNING.

Check Condensate Booster Pumps - 2 RUNNING NOTE: If FRV goes closed, Condensate Booster Pumps will trip and procedure will require the use of AP-TURB.5 to reduce power to 80%. This may or may not occur. If so. follow script for AP-TURB.5 in parallel with AP-FW.1. If not, Rapid Downpower will occur in next event (High Turbine Vibration).

IF no condensate booster pump is running, THEN perform the following:

Ensure power less than 80°F. (Refer to AP-TURB.5, RAPID LOAD REDUCTION.)

Continue with Step 7.

hOTE. If necessary. Stan (oad reouct.on to 809. in accordance wlih AP-TJRB.5, and c0ntint.e with th s DrocedJre In Daral el.

Check Hotwell Level:

Hotwell Level controller in AUTO.

Controller demand less than 70%.

Hotwell level at setpoint.

Appendix D Operator Action Form ES-D-2 BOP OpTest No.: -

1 Scenario# -

4 Event#

3 Page 16 of 41 Event

Description:

"A' FRV Controller fails causing valve to Close Time I

Position I

Applicant's Actions or Behavior Check MFW Pump Suction Pressure.

Both MFW pump suction pressures GREATER THAN 200 PSlG SRO Annunciator H-17, FEED PUMP NET POSITIVE SUCTION I

HEAD - EXTINGUISHED.

Establish Stable Plant conditions:

BOP I Perform the followinq:

I I

1 Verify condensate bypass valve open.

I I

I Place trim valve controller to manual and close trim valves.

Verify annunciator H-17, FEED PUMP NET POSITIVE I

SUCTION HEAD, extinauished.

I I

I IF NOT, THEN reduce power to restore NPSH.

BOP I Verify Adequate MFW Flow:

A MFW flow - GREATER THAN OR EQUAL TO A STEAM I

FLOW B MFW FLOW - GREATER THAN OR EQUAL TO B STEAM FLOW I

I SRO I Check Status of MFW System:

BOP

[

Both MFW pumps - RUNNING Verify condensate pump recirc valve AOV-4238 -

I Bop I CLOSED(PPCSV4238)

I 1

BOP 1

Check MFW pump suction pressure:

Pressure - GREATER THAN 200 PSlG I

I I

pressure-^^^^^^

PRZR pressure -AT OR TRENDING TO 2235 PSlG IN

~

Ro 1

AUTO RO I

Tavg -AT OR TRENDING TO TREF

Appendix D Operator Action Form ES-D-2 OpTest No.: -

1 Scenario# -

4 Event#

3 Page of 41 Event

Description:

" A FRV Controller fails causing valve to Close Time I

Position I Applicant's Actions or Behavior rT=-

I I

SRO I

I BOP I

I SRO I

I BOP I

I Bop PRZR level -AT OR TRENDING TO PROGRAM IN AUTO CONTROL MFW regulating valves - RESTORING S/G LEVEL TO 52% IN AUTO Rod insertion limit alarms - EXTINGUISHED Check Status of Condensate System:

Check hotwell level controller, HCV-I07 Hotwell Level controller in AUTO Controller demand less than 70%

Hotwell level at setDoint Check condensate bvDass valve CLSOED. IN AUTO Check condensate pump - LESS THAN 3 PUMPS RUNNING Verifv trim valves in AUTO at 375 Dsia 0

Verify Control System in AUTO Verify 431 K in AUTO Verifv PRZR Heaters restored:

Verify PRZR spray valves in AUTO PRZR DroDortional heater breaker - CLOSED PRZR backup heater breaker - RESETAN AUTO Verify one charging pump in AUTO Verify MFW regulating valves in AUTO Verify EH controls in OP PAN, IMP OUT Verify steam dump controller, HC-484, in AUTO at 1005 Psig Verify annunciator G-15, STEAM DUMP ARMED -

EXTINGUISHED

. Verify Rods in AUTO

Appendix D Operator Action Form ES-D-2 SRO OpTest No.: -

1 Scenario# -

4 Event#

3 Page E of 41 Event

Description:

A FRV Controller fails causing valve to Close Time I

Position I Applicants Actions or Behavior Restore AFW System to Auto Standby:

SRO Go to /Step 16.

~~

CREW Evaluate MCB Annunciator Status (Refer to AR procedures)

SRO RO BOP SRO RO I

Boration Derformed for load reduction I Check if PRZR Boron Should Be Mixed Initiate Load Reduction Verify rods in AUTO Reduce turbine load in AUTO at follows:

I 1

RO I

Place PRZR backuD heaters switch to ON SRO 1 Notify Higher Supervision SRO I Return To Procedure Or Guidance In Effect.

I AP-TURB.5, RAPID LOAD REDUCTION NOTE: If FRV goes closed, Condensate Booster Pumps will trip and procedure will require the use of AP-TURB.5 to reduce power to 80%. This may or may notoccur. If so. follow script for AP-TUR6.5 in parallel with AP-FW.1. If not, Rapid Downpower will occur in next event (High Turbine Vibration).

Place Turbine EH control in OPER PAN. IMP PRESS OUT. If desired.

Select desired rate on thumbwheel Reduce the setter to the desired load.

I I

I DeDress the GO button I

1 RO 1

Initiate boration at -2 gall% load reduction.

Appendix D Operator Action Form ES-D-2 Ro Op Test No.: -

1 Scenario# -

4 Event#

3 Page 2 of 41 Event

Description:

"A' FRV Controller fails causing valve to Close Adjust Boric Acid Addition Rate As Necessary To (Refer to OPG-REACTIVITY-CALC):

Maintain rods above the insertion limit.

T me 1

Position I Applicant's Actions or Behavior I

Ro I

I RO 1

Place PRZR backup heaters switch to ON.

I Monitor PRZR Level -TRENDING TO PROGRAM IN AUTO CONTROL RO I Monitor RCS Tava BOP I

I I

Tava - GREATER THAN 545°F I

Check Hotwell Level:

I I

I Tavg - LESS THAN 579°F I

I I

~~

I Match Tava and Tref I

I I

ComDensate for Xenon I

RO I Monitor PRZR Pressure - TRENDING TO 2235 PSlG IN AUTO Monitor MFW Regulating valves - RESTORING S/G LEVEL I

I TO 52% IN AUTO I

I I

RO I Check IA Available To CNMT I

IA pressure - GREATER THAN 60 PSlG lnstr Air to CNMT lsol Valve AOV-5392 - OPEN I

1 BOP I Check Steam Dump Status:

I Annunciator G-15, STEAM DUMP ARMED - LIT Steam dump operating properly in AUTO I

Hotwell level controller in AUTO

Appendix D Operator Action Form ES-D-2 Page 20 of 41 OpTest No.: -

1 Scenario# -

4 Event#

3 Event

Description:

A FRV Controller fails causing valve to Close Time I

Position 1

Applicants Actions or Behavior I

I 1

Controller demand LESS THAN 60%

I I

I Hotwell level at setpoint I

At the discretion of the Lead Examiner move to Events 4 & 5.

I

Appendix D Operator Action Form ES-D-2 OpTest No.: -

1 Scenario # -

4 Event#

4 & 5 Page 21 of 41 Event

Description:

High Vibrations on Main TurbindRapid Downpower Time I

Position I

Applicants Actions or Behavior After completion of AP-RN.1, the main turbine will experience high vibrations. The operator will respond in accordance with AR-1-27, Rotor Eccentricity Or Vibration, which will require that AP-TURB.3, Turbine Vibration, be addressed. This will require a load decrease in accordance with AP-TURB.5, Rapid Load Reduction.

Booth Operator Instructions:

Indications Available:

Operate Trigger #4 (TUR05H (9 mils))

I I

I 1-27, ROTOR ECCENTRICITY OR VIBRATION I

1 AR-1-27, ROTOR ECCENTRICITY OR VIBRATION I

I AP-TURB.3. TURBINE VIBRATION I

SRO I Verify turbine vibration -ALL BEARINGS LESS THAN 14 MILS I

I Check turbine bearings No. 1 through No. 8 Vibration - LESS I

Bop I THAN 7 MILS SRO I Attempt to stabilize vibration as follows:

I IF aenerator on line. THEN beain reducina load to stabilize 1

vibyations. (Refer to AP-TUR6.5, RAPlDiOAD REDUCTION).

I I

BOP 1 Check Bearina No. 9 Vibration - LESS THAN 10 MILS I

SRO I Evaluate Plant Conditions:

BOP I

Check turbine vibrations - STABLE OR LOWERING Reduce turbine load until turbine vibrations stabilize and go to I Steps.

Appendix D Operator Action Form ES-D-2 Page of 41 OpTestNo -

1 Scenario# -

4 Event R 4 & 5 Event Descript.on High Vibrations on Main TurbinelRapid Downpower Time I

Posltion I Applicant's Actions or Benavior RO RO IF vibrations can NOT be stabilized with the plant at power, THEN take unit off line (refer to AP-TURB.5, RAPID LOAD REDUCTION)

Initiate boration at -2 gal/% load reduction.

Place PRZR backup heaters switch to ON.

NOTE: it is not intended to have Turbine Vibrations degrade or be reduced throuah the remainder of the scenario.

NOTE: AP-TURB.5 may already be in progress from event #3. If so move forward at the discretion of Lead Examiner, if not. Rapid Load Reduction will occur now in accordance with AP-TURB.5.

I AP-TURB.5, RAPID LOAD REDUCTION SRO I Initiate Load Reduction I

1 RO 1

Verifyrods inAUTO I

1 BOP I

Reduce turbine load in AUTO at follows:

I Place Turbine EH control in OPER PAN. IMP PRESS OUT. If desired.

I I

1 Select desired rate on thumbwheel I

I I

Reduce the setter to the desired load.

Depress the GO button.

I 1

RO I Monitor RCS Tavg 1

Tavg - GREATER THAN 545°F 1

Tavg - LESS THAN 579°F Adjust Boric Acid Addition Rate As Necessary To (Refer to I

Ro I OPG-REACTIVITY-CALC):

I I

1 Maintain rods above the insertion limit Match Tavg and Tref Compensate for Xenon

Appendix D Operator Action Form ES-D-2 OpTest No.: -

1 Scenario# -

4 Event#

4 & 5 Page 23 of 41 Event

Description:

High Vibrations on Main TurbindRapid Downpower Time 1

Position I

Applicant's Actions or Behavior I

RO Monitor PRZR Pressure - TRENDING TO 2235 PSlG IN AUTO I

I I Monitor MFW Regulating valves - RESTORING S/G LEVEL SRO I

I ITO52%INAUTO I

Hotwell level at setpoint Check to see if Condensate Booster Pumps should be secured.

Monitor PRZR Level -TRENDING TO PROGRAM IN AUTO I

Ro I CONTROL I

RO I Check IA Available To CNMT I

I 1

IA pressure - GREATER THAN 60 PSlG I

I I

I lnstr Air to CNMT lsol Valve AOV-5392 - OPEN I

BOP I Check Steam DumD Status:

I I

I Annunciator G-15, STEAM DUMP ARMED - LIT I

I I

I Steam dump operating properly in AUTO I

BOP I Check Hotwell Level:

I I

I Hotwell level controller in AUTO I

I I

I Controller demand LESS THAN 60%

I

Appendix D Operator Action Form ES-D-2 OpTest No.: -

1 Scenario# -

4 Event#

6 Page 24 of 41 Event

Description:

Misaligned Rod Time I

Position I

Applicants Actions or Behavior During the load decrease a rod lift coil for a D Bank rod fails (Blown fuse) causing a misaligned rod. The operator will respond in accordance with AP-RCC.2, RCC/RPI Malfunction, and address Technical Specification 3.1.4, Rod Group Alignment Limits.

Booth Operator Instructions:

Operate Trigger #30 (ROD03) Conditional on Power e 85%

I Indications Available:

Control Rod C-7 MRPl shows rod not moving with the rest of the bank.

C-5, PPCS Rod Sequence or Rod Deviation AR-C-5, PPCS ROD SEQUENCE OR ROD DEVIATION SRO I If Rod position deviation, go to AP-RCC.2.

I AP-RCC.2, RCC/RPI MALFUNCTION I

I I

RO I Place Rods to Manual I

RO I Check Dropped Rod Indication:

Annunciator E-28, POWER RANGE ROD DROP ROD I

STOP 5%/5 SECONDS - EXTINGUISHED I

~

Annunciator C-14, ROD BOTTOM ROD STOP -

EXTINGUISHED I

I RO I Check Tavg - STABLE AT PROGRAM

~~

-1 BOP I Perform the following:

I I

I Place EH control in MANUAL.

I Manually adjust turbine load to match Tavg and Tref.

Verify Annunciator G-15, STEAM DUMP ARMED -

EXTINGUISHED

Appendix D Operator Action Form ES-D-2 1

Scenario #

4 Event#

6 Page 25 of 41 Op Test No.:

Event

Description:

Misaligned Rod Time I

Position I

Applicant's Actions or Behavior I

I RO I

I RO I I

SRO I Check Main Generator Load - GREATER THAN 15 MW Establish Stable Plant Conditions:

Tava -TRENDING TO TREF

~

~~

0 PRZR Diessure -TRENDING TO 2235 PSlG IN AUTO PRZR level -TRENDING TO PROGRAM IN AUTO CONTROL MFW Regulating Valves - RESTORING S/G LEVEL TO 52% IN AUTO NOTE: A FRV is still in manual control Check Control Rod Alignment:

Verify all rods in affected group - WITHIN & 12 STEPS OF ASSOICATED GROUP STEP COUNTER Refer to ITS Section 3.1.4.

Check QPTR - LESS THAN 1.02 Refer to ITS Section 3.2.4.

Verify ALL Individual Rod Position Indication Per Bank Operable:

MRPl system - NO MRPl SYSTEM ALARMS MRPl system - NO KNOWN PROBLEMS WITH MRPl SYSTEM THAT COULD RENDER ROD POSITION INDICATION INOPERABLE Evaluate Control Rod Operability:

Verify less than two misaligned rods

Appendix D Operator Action Form ES-D-2 OpTest No.: -

1 Scenario# -

4 Event#

6 Event

Description:

Misaligned Rod Time I

Position I

Appl cant's Actions or Behavior IF two or more rods are misaligned, THEN initiate plant shutdown. (Refer to 0-2.1, NORMAL SHUTDOWN TO HOT SHUTDOWN)

Direct I&C to locally investigate rod failure Rod failure identified Refer to ER-RCC.2, RESTORING A MISALIGNED RCC Perform the following:

Consult Reactor Engineer and ITS section 3.1.4 for operational concerns.

Return to step 2.

LCO 3.1.4 All shutdown and control rods shall be OPERABLE, with all individual indicated rod positions within 12 steps of their group steo counter demand Dosition.

APPLICABILITY:

MODE 1 MODE 2 with ldl 2 1.O.

Appendix D Operator Act on Form ES-D-2 OpTest No.: -

1 Scenario# 4 Event#

6 Page -

27 of 4 I

I I Event

Description:

Misaligned Rod I

Time I

Position I

Applicant's Actions or Behavior I

SRO CONDITION REOUIRED ACTION 8.1.1 Verify SDM is within the limits specified in the COLR.

OR 6.1.2 Initiate boration to restore SDM to within limit.

AND 8.2 Reduce THERMAL POWER to < 75%

RTP.

AND One rod not within 8.3 Verify SDM is within alignment limits.

the limits specified in the COLR.

AND 8.4 Perform SR 3.2.1.1.

AND 8.5 Perform SR 3.2.2.1.

AND 8.6 Re-evaluate safety analyses and confirm results remain valid for duration of COMPLETION TIME 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 1 houi 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 72 hours 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months 5 days operation under these conditions.

I At the discretion of the Lead Examiner move to Events 7 & 8.

Appena x D Operator Action Form ES-D-2 OpTestNo -

1 Scenaro b -

4 Event#

7 & 8 Page 28 01 41 Event Description Loss of Instrument Bus C (causing SI)/ A&B SI Pumps fail to Auto Start Time I

Position I

Applfcants Actions or Behavior Following this, an electrical fault will occur on the C Instrument Bus resulting in a loss of the bus, and a Safety Injection actuation. The operator will enter E-0, Reactor Trip or Safety Injection. On the Safety Injection actuation, both the A and B SI Pumps will fail to auto start and require manual starting.

Booth Operator Instructions:

Operate Trigger #5 (EDS07C, RCS19D (900 gpm))

Indications Available:

1 BOP/RO I

I I Reactor Trip occurs I

Check if SI is Actuated:

I I

I Safetv lniection occurs I

E-0, REACTOR TRIP OR SAFETY INJECTION.

I I

RO I Verify Reactor Trip:

I Neutron flux - LOWERING MRPl indicates -ALL CONTROL AND SHUTDOWN RODS ON BOTTOM At least one train of reactor trip breakers - OPEN I

I BOP I Verify Turbine Stop Valves - CLOSED I

Verify Both Trains of AC Emergency Busses Energized To At I Least 420 VOLTS:

I Bus 14 and Bus 18 Bus 16 and Bus 17 I

I I

SI seauencina - BOTH TRAINS STARTED I

RO I Verify CNMT Spray Not Required:

I Annunciator A-27, CNMT SPRAY - EXTINGUISHED

Appendix 0 Operator Actson Form ES-D-2 RO OpTest No.: -

1 Scenario# -

4 Event#

7 8 8 Page 29 of 41 Event

Description:

Loss of Instrument Bus C (causing SI)/ A&B SI Pumps fail to Auto Start Verify SI and RHR Pumps Running:

All SI pumps - RUNNING Both RHR PumDs - RUNNING I

Time I

Position I

Applicants Actions or Behavior I

RO I

Check If Main Steamlines Should Be Isolated:

Any MSlV - OPEN Check CNMT pressure - LESS THAN 18 PSlG I

Ro RO 1

An-27.0, A Ensure BOTH MSlVs closed and go to Step 4.

CNMT pressure - LESS THAN 28 PSlG RO Verify CNMT spray initiated.

Verify MFW Isolation:

MFW pumps -TRIPPED Direct Operator to Perform ATT-27.0, ATTACHMENT AUTOMATIC ACTION VERIFICATION NOTE: The CRS will assign one board operator to perform Attachment 27.0, while the other board operator works with the CRS to continue on in E-0.

TACHMENT AUTOMATIC ACTION VERIFICATION.

I I NOTE: Both the A and B SI Pumps have failed to Auto Start on SI.

Critical Task:

E-0 I transition out of E-0.

Establish flow from at least two SI pumps before I

I RO I Verify CNMT RECIRC Fans Running:

I I

AII fans - RUNNING Charcoal filter dampers green status lights -

EXTINGUISHED

Appendix D Operator Action Form ES-D2

~

[OpTest No.: -

1 Scenario# -

4 Event#

7&8 Page -

30 of 4

~

~~

RO Verify SI and RHR Pump Flow:

SI flow indicators - CHECK FOR FLOW RHR flow indicator - CHECK FOR FLOW Event

Description:

Loss of Instrument Bus C (causing SI)/ A&B SI Pumps fail to Auto Start Time I

Position I Applicant's Actions or Behavior I

I I

MFW Isolation valves - CLOSED I

I I

I S/G blowdown and sample valves - CLOSED I

RO I Verifv At Least Two SW Pumps - RUNNING RO I Verify CI and CVI I

CI and CVI annunciators - LIT I

Ro CNMT RECIRC fan coolers SW outlet valve status lights -

BRIGHT I

RO I Letdown orifice valves - CLOSED RO I Check CCW Svstem Status:

I I

I Verifv ccw Dump - AT LEAST ONE RUNNING I

I I

I Place switch for excess letdown AOV-310 to CLOSE I

Place switch for CCW from excess letdown, AOV-745 to CLOSE I

Verify SI Pump And RHR Pump Emergency Alignment:

RHR pump discharge to Rx vessel deluge - OPEN Verifv SI DumD C - RUNNING Verify SI pump A - RUNNING I

Verify SI pump B - RUNNING I

Verify SI pump C discharge valves - OPEN I

Appendix D Operator Action Form ES-D-2 Page 31 of 41 Loss of Instrument Bus C (causing SI)/ A&B SI Pumps fail to Auto Start OpTest No.: -

1 Scenario# -

4 Event#

7&8 Event

Description:

I Time I

Position I

Applicants Actions or Behavior I

RO I Verify CREATS Actuation:

I I

I At least one damper in each flowpath -CLOSED I

I I

CREATS fans - BOTH RUNNING I

E-0, REACTOR TRIP OR SAFETY INJECTION.

Verify AFW Valve Alignment:

AFW flow - INDICATED TO BOTH S/G(S)

AFW flow from each MDAFW pump - LESS THAN 230 GPM Monitor Heat Sink:

Check S/G narrow range level - GREATER THAN 7%

(25% adverse CNMT) in any S/G Check S/G narrow range level - BOTH S/G LESS THAN Control feed flow to maintain S/G narrow range level between 7% (25% adverse CNMT)and 50%.

50%.

Check if TDAFW Pump Can Be Stopped:

Both MDAFW pumps - RUNNING PULL STOP TDAFW Dumr, steam SUDD~V valves MOV-3504A MOV-3505A Check CCW Flow to RCP Thermal Barriers:

Annunciator A-7, RCP 1A CCW RETURN HI TEMP OR LO Annunciator A-15, RCP 1B CCW RETURN HI TEMP OR LOW FLOW EXTINGUISHED FLOW - EXTINGUISHED

Appendix D Operator Action Form ES-D-2 OpTest No.: -

1 Scenario# 4 Event#

7&8 Page 32 of 41 Event

Description:

Loss of Instrument Bus C (causing SI)/ A&B SI Pumps fail to Auto Start Time I

Position I Applicant's Actions or Behavior Monitor RCS Tavg - STABLE AT OR TRENDING TO 547°F I

IF temperature less than 547°F and lowering, THEN perform the followina:

I Stop dumpina steam.

I Ensure reheater steam supply valves are closed.

I IF cooldown continues, THEN control total feed flow between 200 gpm to 230 gpm until narrow range level greater than 7% [25% adverse CNMT] in at least one S/G.

WHEN S/G level greater than 7% [25% adverse CNMT] in one S/G, THEN limit feed flow to that required to maintain level in at least one S/G.

IF cooldown continues, THEN close both MSIVs.

I Check PRZR PORVs and SDrav Valves:

I

~

PORVS - CLOSED Auxiliaw spray valve (AOV-296) -CLOSED I

Check PRZR pressure - LESS THAN 2260 PSlG I

Normal PRZR spray valves - CLOSED I

PCV-431A I

PCV-431B Monitor RCP Trip Criteria:

I RCP status - ANY RCP RUNNING I

SI pumps -AT LEAST TWO RUNNING RCS pressure minus maximum S/G pressure - LESS THAN 210 psi [240 psi adverse CNMT]

Stop both RCPs.

I

Appendix D Operator Action Form ES-D9 OpTest No.: -

1 Scenario# -

4 Event#

7&8 Page 33 of 41 Event

Description:

Loss of Instrument Bus C (causing SI)/ A&B SI Pumps fail to Auto Start I

Time I

Position I

Applicant's Actions or Behavior 1

Critical Task E-1 C Trip all RCPS within 5 minutes of reaching the trip criteria.

E-0 Foldout Page Trip Criteria:

If both:

SI pumps - at least two running.

RCS Pressure minus maximum SIG Pressure - < 210 Psi.

ROIBOP Check if SIG Secondary Side is Intact:

Pressure in both S/Gs - STABLE OR RISING Pressure in both S/Gs - GREATER THAN 110 PSlG I RO/BOP I Check if S/G Tubes are Intact:

I Air ejector radiation monitors (R-15 or R-15A) - NORMAL I

I S/G blowdown radiation monitor (R-19) - NORMAL I

1 0 Steamline radiation monitors (R-31 and R-32) - NORMAL 1 ROIBOP 1 Check If RCS is Intact:

I I

CNMT area radiation monitors - NORMAL I

1 R-2 I

I R-7 I

I R-29 R-30 CNMT pressure - LESS THAN 0.5 PSlG CNMT sumD B level - LESS THAN 8 INCHES I

1 Level-STABLE I

Annunciator C-19, CONTAINMENT SUMP A HIGH LEVEL - EXTINGUISHED

Appendix D Operator Action Form ES-D-2 SRO OpTest No.: -

1 Scenario# -

4 Event#

7&8 Page 34 of 4 I

Check If SI Should Be Terminated:

RCS pressure:

Pressure - GREATER THAN 1625 PSlG I

Event

Description:

Loss of Instrument Bus C (causing SI)/ A&B SI Pumps fail to Auto Start I

SRO I

Time I

Position I

Appl cant's Actions or Behavior 1

Initiate Monitoring of Critical Safety Function Status Trees.

NOTE: The RCS is not intact due to an intersystem LOCA, however, this step will not diagnose the LOCA. SRO should continue in E-0.

I I

I Pressure - STABLE OR RISING I

SRO I DO NOT stop SI pumps, GO to Step 19.

I I

BOP I Monitor SlG Levels:

I I

Narrow range level - GRETER THAN 7%

I Control feed flow to maintain narrow range level between I

17%and50%

I SROlRO I Check Secondarv Radiation Levels - NORMAL I

I I

Steamline radiation monitor (R-31 and R-32)

I I

Dispatch A 0 to locally check steamline radiation I

I I

I Request RP sample SlGs for activity I

RO I Reset SI I

I RO I Reset CI:

I I

Depress CI reset Dushbutton I

Verify annunciator A-26, CNMT ISOLATION -

I EXTINGUISHED BOP I Verify Adequate SW Flow:

Appendix D Operator Action Form ES-D 2 1

Scenario R -

4 Evcntn 7 & 8 Page 35 01 41 OpTest No -

Event Descr plion Loss of Instrument Bus C (causing SI)/ A&B SI Pumps fail to Auto Start Time I Positlon I

Applicant's Act ons or Benavior RO At least three SW pumps - RUNNING Dispatch A 0 to establish normal shutdown alignment (Refer to ATT-17.0, ATTACHMENT SD-1)

Reset both trains of XY relays for IA to CNMT AOV-5392 Verifv IA to CNMT AOV-5392 - OPEN Pressure - GREATER THAN 60 PSlG Pressure - STABLE OR RISING I BOPlRO I Establish IA to CNMT:

RO Verify non-safeguards busses energized from offsite power Bus 13 normal feed - CLOSED Check Auxiliary Building Radiation - NORMAL OR Verifv SW isolation valves to turbine buildina - OPEN Bus 15 normal feed - CLOSED I

I MOV-4613 and MOV-4670 I

I I

MOV-4664 I

I I

RO I

Verify adequate air compressor(s) - RUNNING I

RO I. Check IA supply:

I I

I Plant vent uarticulate (R-13)

I I

Plant vent aas (R-14)

I I

I I 0 CCW monitor (R-17 I

I I

I Letdown line monitor (R-9)

I Charging pump room (R-4)

I NOTE: Aux Building radiation will not be normal due to an intersystem LOCA.

I I

SRO I Evaluate cause of abnormal conditions.

I

Appendix D Operator Action Form ES-D-2 OpTest No.: -

1 Scenario# -

4 Event#

7 8 8 Page 36 of 41 Event

Description:

Loss ot Instrument Bus C (causing SI)/ A&B SI Pumps fail to Auto Start Time I

Position I

Applicant's Actions or Behavior IF the cause is a loss of RCS inventory outside CNMT, THEN go to ECA-1.2, LOCA OUTSIDE CONTAINMENT, Step 1.

Move to Event #9

Appendix D Operator Action Form ES-D-2

~

~~

~

OpTest No.: -

1 Scenario# 4 Event#

9 Page 37 of 41 Event

Description:

Check Valve CV-853B fails causing intersystem LOCA Time I

Position I

Applicants Actions or Behavior When MOV-852B opens (RHR to Rx Vessel) on the SI actuation, CV-853B fails causing an inter-system LOCA (to RHR). The RHR common header fails from overpressure resulting in a LOCA outside Containment. The operator will transition to ECA-1.2, LOCA Outside Containment. Upon completion of ECA-1.2, the operator will transition to E-1, Loss of Reactor or Secondary Coolant. The scenario will terminate at Step 12e of E-I, after the crew decides to transition to ES-1.1, SI Termination.

I Booth Omrator Instructions:

NA I

I

~

~~

Indications Available: Event in progress, continue with EOP implementation ECA-1.2, LOCA OUTSIDE CONTAINMENT I

I RO I Verifv orooer RHR Normal Coolina Valve Alianment:

I I

I 1

MOV-700 and MOV-701, RHR suction valves from A hot I

1 leg -CLOSED 1

I MOV-721, RHR discharge valves to B cold leg - CLOSED I

1 RO I Check CVCS Valve Alignment:

I 1

Verify the following valves - CLOSED AOV-310. Excess letdown isolation valve T

~

-1 AOV-296. Auxiliarv sorav valve Verify the following CI valves - CLOSED AOV-371, letdown isolation valve AOV-392A, Charging line isolation valve to loop B hot leg MOV-313, seal return isolation valve I

I RO I Check Safeauards Valves For Backflow:

I I

I 1

Ensure SI reset I

Close RHR pump discharge to Rx vessel deluge MOV-852A (turn on DC power keyswitch)

Check for RCS oressure rise

Appendix D Operator Action Form ES-D.2 RO OpTest No.: -

1 Scenario# 4 Event#

9 Page 38 of 41 Event

Description:

Check Valve CV-8538 fails causing intersystem LOCA Time I

Position I

Applicantk Actions or Behavior 0

Place MOV-852A DC power keyswtich to OFF.

I I

SRO I Perform the following:

I RO RO

_ _ ~

~

~~~

~

Close RHR pump discharge to Rx vessel deluge MOV-8528 (turn on DC power keyswitch).

Check for RCS pressure rise.

0 NOTE: This step will isolate the intersystem LOCA, and RCS pressure should be increasing.

SRO SRO I GO to SteD 7.

Go to Step 2.

I I

SRO I Check If Break Is Isolated.

I RO/BOP I

I RO I

~ ~ ~ D r e s s u r e - ~ l ~ l ~ ~

I Check If S/G Secondary side is Intact:

GO to E-1, LOSS OF REACTOR OR SECONDARY COOLANT, 1

0 I Step 1.

I Critical Task:

NOTE:

(ECA-1.2 A) Isolate the LOCA outside Containment before transitioning out of ECA-1.2.

If the crew does not isolate the LOCA, and transitions to ECA-1.1, instead of E-1. there is a failure of the Critical Task.

E-1, LOSS OF REACTOR OR SECONDARY COOLANT.

I 1

RO I Monitor RCP Trip Criteria:

I 1

RCP status - ANY RCP RUNNING

Appendix D Operator Action Form ES-D-2 RO OpTest No.: -

1 Scenario# 4 Event#

9 Page 39 of 41 Event

Description:

Check Valve CV-853B fails causing intersystem LOCA Time I

Position I

Applicant's Actions or Behavior Monitor PRZR PORV Status:

Pressure in both S/Gs - GREATER THAN 110 PSlG RO RO/BOP 1 Monitor Intact S/G Levels:

Reset CI:

Depress CI reset pushbutton Verify annunciator A-26, CNMT ISOLATION -

EXTINGUISHED Narrow range level - GRETER THAN 7% [25% adverse 1

CNMT]

Control feed flow to maintain narrow range level between 17% 125% adverse CNMTI and 50%.

I I

I 1

PORVs-CLOSED I

I I

Block valves - AT LEAST ONE OPEN RO 1 Reset SI I

I BOP I Verify Adequate SW Flow:

I I

I Check at least two SW pumps - RUNNING Dispatch A 0 to establish normal shutdown alignment (Refer to ATT-17.0, ATTACHMENT SD-1)

I RO I Establish IA to CNMT:

Verify non-safeguards busses energized from offsite powei I

I 1

Bus 13 normal feed - CLOSED I

I I

OR I

I I

Bus 15 normal feed - CLOSED

Appendix D Operator Action Form ES-13-2 RO Page 40 of 41 OpTest No.: -

1 Scenario# -

4 Event#

9 Event

Description:

Check Valve CV-853B fails causing intersystem LOCA Time I

Position I

Applicant's Actions or Behavior Check Normal Power Available To charging Pumps:

I I

I Verify turbine building SW isolation valves - OPEN RO MOV-4613 and MOV-4670 MOV-4614 and MOV-4664 Verifv adeauate air ComDressors - RUNNING Check If Charging Flow Has Been Established:

I I

I CHECK IA SUDDIV:

I I

I Pressure - GREATER THAN 60 PSlG I

I I

Pressure - STABLE OR RISING I

I I

Reset both trains of XY relays for IA to CNMT AOV-5392 I

Verify IA to CNMT AOV-5392 - OPEN I

I I

Bus 16 normal feed breaker - CLOSED Charging pump suction aligned to RWST:

LCV-112B OPEN LCV-112C - CLOSED Start charging pumps and adjust charging flow as necessary to restore PRZR level.

I I

SRO I Check if SI should be Terminated:

I 1

RO I

RCS Pressure > 1625 psig.

I RCS Pressure Stable or Rising.

RCS Subcooling based on Core Exit thermocouples > 0°F using Figure 1.O, Figure Minimum Subcooling.

I I

I BOP I

Secondary Heatsink:

o Total feed flow to intact SG > 200 gpm.

OR

Appendix D Operator Action Form ES-D-2 Op Test No.: -

1 Scenario# 4 Event#

9 Page 41 of 41 Event

Description:

Check Valve CV-8536 fails causing intersystem LOCA Time I

Position I

Applicant's Actions or Behavior o

NR Level in at least one SG > 7%.

I 1

RO I

Przr Level > 10%

I SRO I Go to ES-1.1, SI Termination.

Booth Instructor: Freeze the Simulator.

EAL (ALERT) 3.1.2 Primary System Leakage > 46 gpm.

(SAE) 4.1.3 if intersystem LOCA is not isolated from MCB.

ML072690158

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