Text

Draft - Section C Operating Exam (Folder 2)
	ML072690105
Person / Time
Site:	Ginna
Issue date:	07/17/2007
From:	; Constellation Energy Group
To:	; 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: ML072690105 (97)
	v • d • e

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.l, 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-200B 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 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.

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-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 Specification 3.8.9, Distribution Systems Modes 1-4. At this point, Plant Management will make a decision to conduct a plant shutdown at 1YdMinute. 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. Once the plant is stabilized 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 T D A W Pump will fail to auto start. The operator will need to open these valves to restore AFW flow.

2-

Scenario Event Description NRC Scenario 1 With A W flow restored the Work Control Center will call and indicate that the A EDG is now ready for service. The operator will start the AEDG and restore power to Bus 14 and 18.

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-B Establish greater than 200 gpm AFW flow before both S/Gs levels decrease to < 3 5 wide range level.

CT ECA-0.0 0 Restore AC Power to at least one Emergency Bus prior to placing pump control switches in Pull-Stop in ECA-0.0.

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

IC # 171 Place Hold Tags on:

Bus 14 Emergency Feeder Breaker Bus 18 Emergency Feeder Breaker A EDG Control Switch A EDG Pushbutton Place Protected Equipment Tags on:

Bus 16 Emergency Feeder Breaker Bus 17 Emergency Feeder Breaker B EDG Control Switch 0 B EDG Pushbutton Malf. GEN04A A EDG Failure Malf. IND-MIS36 PT-945 Failure Malf. RPS-07M TDAFW Pump Failure Malf . RPS-07N TDAFW Pump Failure Event #1 NONE Event #2 Malf. Pzr 0 5 A @ 2% on Trigger #1 Event #3 E-MIS 10 to 1.O (Ramp in over 60 sec.) On Trigger #2 Event #4 Malf. CVClOA to 0% on Trigger #3 Event #5 Malf. EDS04B on Trigger #4 Event #6 NONE Event #7 Malf. ROD02-J4 on Trigger #5 Event #8 Malf. ROD02-JlO on Trigger #6 Event #9 Malf. EDSO6 1 (FAST) on Trigger #7 Event #10 NONE Event #11 Clear Malf. GEN04A 4-

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 AMFW 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.l, Reactor Protection Bistable Defeat After Instrumentation Loop Failure.).

Hold Tags have been placed on:

Bus 14 Emergency Feeder Breaker Bus 18 Emergency Feeder Breaker A EDG Control Switch A EDG Pushbutton Protected Equipment Tags have been placed on:

Bus 16 Emergency Feeder Breaker Bus 17 Emergency Feeder Breaker B EDG Control Switch B EDG Pushbutton Chemistry has requested you to swapover Letdown Orifice valves from AOV-202 to AOV-200B.

Scenario Event Description NRC Scenario 1 A-52.4 Equipment Date Time Reason Required Actions Required Required Action not met Completion

~

Daterrime PT-945 J-I07 I330 Failed Channel ITS 3.3.2 Condition A rRACKlNG Enter Condition referenced on 3NLY Table 3.3.2-1 (IC, 2c, 4c) immediately.

Condition F (From 4c)- Place Condition G - Be in Mode 3 within 6 Channel in Trip within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months hours, and Mode 4 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

Condition J (From IC, 2c) - Condition K - Be in Mode 3 within 6 Place Channel in Trip within 6 hours, and Mode 5 within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

hours.

A Emergency I I07

.- Breaker ITS 3.8.1 Condition B liesel Generator maintenance Perform SR 3.8.1 .1 for the 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 thereafler.

Declare required feature(s) suppolted by the inoperable DG inoperable when its required redundant feature(s) 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 SR3.8.1.2 for operable DG within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Restore DG to operable within 7 days.

Appendix D Operator Action Form ES-0-2 OpTest No.: - 1 Scenario# -1 Event# 1 Page I,of 33 Event

Description:

Swap Letdown Orifice Valves Time I Position I Applicants Actions or Behavior Booth Operator Instructions:

Indications Available:

S-3.2P Swapping CVCS Letdown Orifice Valves.

5.2 Decreasing Letdown Flow from 60 gpm to 40 gpm.

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

Place PCV-135 to MANUAL AND adjust as necessary to RO control Low Pressure Letdown pressure at approximately 300 Dsia.

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

N/A if not desired.

NOTE: The next steD reauires two actions. ensure AOV-202 closed or to opening AOV-200A or AOV-200B.

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

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

Ensure PCV-I 35 controller signal is nulledhalanced and then Place PCV-135 to AUTO, if desired.

Place or ensure TCV-130 is in AUTO, if desired.

ADDendix D ODerator Action Form ES-D-2 OpTest No.: - Scenario# -1 Event# 1 Event

Description:

Swap Letdown Orifice Valves Monitor Charging/Letdown mismatch. IF desired, THEN place Ro charaina in manual. IF not desired. THEN N/A this steo.

Appendix D Operator Action Form ES-D-2 OpTest No.: - Scenario# -1 Event# 2 Page of 33 Event

Description:

PORV Leakage on PCV-430 Booth Operator Instructions: Enter Malf. PZR 05A @ 2% on Trigger #1.

Indications Available:

1 PPCS Alarm (PORV Mid-position)/F-19 I AR-F-19 PRZR PORV Outlet HI Temp 145°F. I I I I IF Pressurizer pressure is decreasing, THEN GO TO AP-PRZR.l. I NOTE: SRO may carry out AP-PRZR.1 and AR-F-19 simultaneously.

AP-PRZR.1 Abnormal Przr Pressure RO Check PRZR Pressure:

~ ~ ~ ~ ~

All 4 narrow range channels -TRENDING TOGETHER RO Check reactor Power - STABLE RO Check PRZR Pressure:

I I I Pressure - LESS THAN 2235 PSlG I 1 Pressure - GREATER THAN 2000 PSIG I I RO I Check PRZR Heater Status: I I I I PRZR proportional heater breaker - CLOSED. I I I I PRZR heater backup group - ON I RO I Verify Normal PRZR Sway Valves - CLOSED NOTE: With PRZR pressure controller 431 K in manual, PORV-431C will not operate in the automatic mode (refer to TR 3.4.3).

Appendix D Operator Action Form ES-D-2 OpTest No.: - 1 Scenario# -1 Event# 2 Page '0 of 33 Event

Description:

PORV Leakage on PCV-430 Time I Position 1 Applicant's Actions or Behavior I Ro I Check PRZR Pressure Controller, 431K, Demand - LESS THAN 50%.

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 complete, or during the process that it is occurring the RO will report this to the SRO.

---r---

Check PRZR PORVs:

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

Manuallv close PORVs.

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

MOV-516 for PCV-430.

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

If PORV leakaae is indicated, then oerform the followina:

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 be closed upon arrival of this action.

The SRO will note this and move on to steD 0.

1 RO Attempt to reseat any leaking PORV Verify affected PORV Block Valve closed.

Cycle the leaking PORV open and closed.

Verify leakage has stopped.

If leakage continues Then:

Appendix D Operator Action Form ES-D-2 I

OpTest No.:

Event

Description:

Time I 1

Posltlon Scenario# 1 Event#

PORV Leakage on PCV-430 I

2 Page Applicant's Actions or Behavior

-1 11 of 33 I I I 0 Reclose leakina PORV Block Valve. I I I 1 0 Refer to ITS section 3.4.1 1 and TR 3.4.3. I I I 10 GotoStep11. I RO I Check PRZR Pressure Control Restored:

I I I Pressure -TRENDING TO 2235 PSlG 0 I I I I Level - BETWEEN 61% AND 84% I I I I Pressure -APPROXIMATELY 1.5 PSlG AND STABLE I 1 0 Temperature -AT CNMT AMBIENT TEMPERATURE ANDSTABLE i RO Establish PRZR Pressure Control In Auto:

0 Verify 431K in AUTO 0 Verify PRZR spray valves in AUTO.

Verifv PRZR heaters restored:

Crew I Evaluate MCV Annunciator Status I I SRO I Notify Higher Supervision I SRO Notify Reactor Engineer for Transient Monitoring Program AR-F-19 PRZR PORV Outlet HI Temp 145°F.

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

I 1 RO I Check PRZR PORV Outlet temperature, TI-438. I RO I Check PRT parameters.

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

12 of 33 Event

Description:

PORV Leakage on PCV-430 Time I Position I Applicants Actions or Behavior -

Check Containment temperature.

I SROIRO Start OR swap Containment Recirc Fans per Shift Supervisor directions.

Refer to ITS LCO 3.4.1 1 and 3.4.13.

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

CONDITION REQUIRED ACTION COMPLETION TIME B.l Close associated hour One PORV Inoperable.

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 B.3 Restore PORV to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OPERABLE status.

I SRO LCO 3.4.13 RCS operational LEAKAGE NOTE: SRO will check and determine insufficient data to quantify leakaaelno entry.

TRM Anticipated Transients Without Scram (ATWS) Mitiaation CONDITION REQUIRED ACTION COMPLETION TIME A. One or more PORV A.l Declare ATWS Immediately automatic flow path mitigating capability inoperable. inoperable.

Appendix D Operator Action Form ES-D-2 OpTest No.: -1 Scenario# - 1 Event# 3 Page 13 of 33 Event

Description:

Post Contingency Low Voltage Alarm Occurs Time I Position I Applicants Actions or Behavior I Booth Operator Instructions: Set E-MIS10 t o 1.O and ramp in over 60 seconds. [Triager #2)

Booth Operator Instructions: 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.

Indications Available:

0-6.9 Operating Limits for Ginna Station Transmission.

I SRo I 6.3 Low Voltage Condition at 13A With Generator Output Breaker(s) Closed IF RG&E ECC informs the Control Room that a Ginna Post SRO Contingency Low Voltage Alarm has occurred THEN DECLARE offsite power inoperable (Refer to ITS 3.8.1).

NOTE: RG&E ECC will be taking action to clear the Post Contingency Low Voltage Alarm. WHEN the alarm has cleared, THEN RG&E ECC will inform the Control Room that the alarm has cleared and the post-contingency voltage is above the minimum required voltage.

LCO 3.8.1 AC Sources - MODES 1,2,3, and 4 CONDITION REQUIRED ACTION COMPLETION TIME C. Offsitepower to one C.l Restore required or more 480V offsitecircuit to safeguards bus(es) OPERABLE 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months inoperable. status AND OR One DG inoperable. C.2 Restore DG to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months OPERABLEstatus.

OpTest No.: - 1 Scenario# - 1 Event# 3 Page of 33 Event

Description:

Post Contingency Low Voltage Alarm Occurs Time I Position I Applicant's Actions or Behavior ~

CONDITION REQUIRED ACTION B. Two Off-SitePower 8.1 Enter LC03.8.1. Immediately Circuits inooerable.

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

Appendix D Operator Action Form ES-D-2

~

OpTest No.: - 1 Scenario# -1 Event# 4 Event

Description:

VCT Level Transmitter (LT-112) Fails Low I Time I Position I Applicants Actions or Behavior I Booth Operator Instructions: Enter malf. CVClOA @ 0%. (Trigger #3)

Indications Available:

I A-2 VCT LEVEL 1494 86 AR-A-2. VCT LEVEL 14% 86.

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

LT-112 FAILED LOW SROIRO 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-I39 indicates approximately 20%.

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

1 RO 1 Perform makeup by one of the following methods:

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

Appendcx D Operator Action Form ES D-2 OpTestNo -1 Scenario R -1 Event# 5 Page 1 601 33 Event Descnption An Electrical Ground Fault Occurs on Safeguards Bus 16 Time I POSltlOn I Applicanfs Actions or Behavior Booth Operator Instructions: Insert malf. EDSMB. (Trigger #4)

Indications Available:

I L-5 SAFEGUARD BUS MAIN BREAKER OVERCURRENT TRIP I L-7 BUS 16 UNDER VOLTAGE SAFEGUARDS AR-L-5, SAFEGUARD BUS MAIN BREAKER OVERCURRENT TRIP.

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

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

I I To prevent the D/G from loading on the affected Safeguards RO bus while troubleshooting is in progress, PULL STOP the affected D/G supply breaker.

I SRO I Notify the following:

I I Electricians Scheduling Operations Supervision 1 SRO I Refer to ITS LCO 3.8.1 OR 3.8.2.

SRO I Direct Electricians to investiaate cause of overcurrent condition.

AR-L-7, BUS 16 UNDER VOLTAGE SAFEGUARDS NOTE: Operator may diagnose no voltage on Bus 16 and immediately enter AP-ELECT.I4/16.

SRO 1 Refer to ITS LCO 3.8.1 OR 3.8.2.

I

Appendix D Operator Action Form ES-D-2 OpTestNo -1 Scenario # -1 Event g 5 Page 1 7 01 33 Event Description An Electrical Ground Fault Occurs on Safeguards Bus 16 Time I Position I Applicanls Actions or Behavior 7 -

I AP-ELEC.14116, Loss of Safeguards Bus 14/16 I RO I Monitor Tava.

I I I Place Rods in Manual. I I Manually move Control Rods to control Tavg.

I I I Ro I Verify that Emergency D\G associated with affected bus is running. (NOTE: B EDG is running) I I I I Verify Both Trains of Emergency Busses Energized to at least 420 volts.

RO If one train deenergized Then:

I Mode Switch in UNIT I I I Voltaae Control Selector in AUTO. I I I I Check D\G running. I NOTE: Crew will note that the procedure step cannot be carried out because of the overcurrent lockout on Bus 16.

I I RO 1 Verify ccw Pump status I II II At least one CCW PumD runnina. I 1 Annunciator A-22, CCW Pump Discharge - LO Press 60 PSIG-I Extinguished.

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

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

in AUTO.

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

Appendix D Operator Action Form ES-D-2 OpTestNo -1 Scenario# -1 Event # 5 Page 18of 33 Event Descript.on An Electrical Ground Fault Occurs on Safeguards Bus 16 Time I Position I Applicant's Actions or Behavior I I I I I I BOP 1 Verify Bus 16 - Energized to at least 420 volts. I I I I NOTE: Bus 16 will be deeneraized and incapable of being restored. I 1 ROlBOP 1 Ensure the following equipment is running:

I I I ccw PumD A I I I I Charging Pump A I I PRZR Proportional Heaters I Containment Recirc Fans A and D I I I Boric Acid Pump A I I RMW Pump A 1 Reactor Comoartment Coolino Fan A I I I Penetration Cooling Fan A I 1 SFP Cooling I

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

I I I SRO I Provide alternate room cooling for D/G B I SRO 1 Cross Connect D/G A Fuel Oil transfer Dump to D/G B.

RO 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.

RO Check Charging Pump suction aligned to VCT.

VCT Level > 20%

Align Charging Pumps to VCT LCV-112C Open 1 LCV-112B Closed 1

Appendix D Operator Action Form ES-DP OpTest No.: - 1 Scenario# -1 Event# 5 Page 19 of 33 Event

Description:

An Electrical Ground Fault Occurs on Safeguards Bus 16 Time I Position I Applicant's Actions or Behavior

RO Check CVCS Operation Charging Pumps - At least one running.

Charging line flow > 20 gpm.

~

Check Letdown indications:

I I I Przr level > 13% I 1 Letdown Flow approximately 40 gpm.

I Letdown flow stable.

Adjust Charging Pump speed and HCV-142 to restore Przr leveland labyrinth seal DPs.

RO 1 Verify Przr Heaters restored I Przr ProDortional Heaters Breaker closed.

I I 1 Przr Backup Heater Breaker - Reset, in AUTO. I RO I Verify normal Rod Control restored.

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

Extinguished. I Annunciator E-28, Power Range Rod Drop Rod Stop -

Extinguished.

Annunciator F-15, I 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.

I 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 Aclion Form ES-0-2 OpTest No.: - 1 Scenario# -1 Event# 5 Page 20 of 33 Event

Description:

An Electrical Ground Fault Occurs on Safeguards Bus 16 Time I Position I Applicant3 Actions or Behavior -

I I SRO I If normal power is not restored, go to step 17. I SRO I Establish normal Dlant conditions.

RO Verify two charging pumps running.

Verify at least two Containment Recirc Fans running.

Check CCW DumDs - Onlv one running.

I I I Check radiation monitors: I 1 CNMT Sample Pump running.

Plant Vent Sample Pump running.

All area and process monitors operating as required.

I I BOP I Check Status of DC System loads. I I Verify the T D A W pump DC oil pump Off in AUTO.

I- 1 Check status of battery chargers.

I I BOP I Batterv charaers A or A1 eneraized.

JI I I I Battery chargers B or B1 energized. I SRO I Restore EauiDment alianment.

Verify Annunciator L-I, Aux Bldg. Vent System Control Panel -

Extinauished.

I I I Restore Affected Bus equipment as power supply permits. 1 I Evaluate MCB Annunciators status I Verifv control board valve alignment - normal.

SRO I Establish control svstems in AUTO.

Crew I Evaluate MCB Annunciator status.

Appendix D Operator Action Form ES-D-2 OpTest No -1 Scenario # - 1 Event k 5 Page 21 of 33 Event Description An Electrical Ground Fault Occurs on Safeguards Bus 16 Time I Position I Applicanrs Actions or Behavior 1 SROIBOP Verify Emeraencv AC Bus normal feeder breakers closed.

VOTE: Recognize that Bus 16 cannot be energized and that procedure loop s in effect until Bus is restored.

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

AND 3ne DG inooerable.

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 REQUIRED ACTION COMPLETION TIME E. Two trains with inoperable electrical power distribution E.l 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.

Appendix D Operator Action Form ES-D-2 OpTest No.: - 1 Scenario# -1 Event# 6 Page 22 of 33 Event

Description:

Load Decrease at 1°/dMinute Time I Position [ Applicants Actions or Behavior 1 Booth Operator Instructions: Call SRO as plant management a direct load decrease 63 1Yminute. I Indications Available:

I AP-TURB.5, Rapid Load Reduction. I SRO I Initiate a Load Reduction RO I Verify rods in AUTO BOP I Reduce Turbine Load in AUTO.

I 1 RO 1 Initiate boration at =2gal/% load reduction. I I I RO I Place Przr Backuo Heaters to ON. I RO 1 Monitor RCS Tavg I Tava > 545°F I I I T a w e 579OF I RO 1 Adiust boric acid addition rate as necessaw to:

I I I Maintain rods above RIL. I Match Tavg and Tref.

I Compensate for Xenon.

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

I Bop Monitor MFW Regulating Valves - restoring S/G level to 52% in IAUTO. I RO Monitor Przr Level -Trending to program in Auto Control.

RO I Check Instrument Air to Containment

Appendix D Operator Action Form ES-D-2 Op Test No.: -Scenario# - 1 Event# 6 Event

Description:

Load Decrease at lo/dMinute I I I IA Pressure > 60 wig. I 1 IA to CNMT Isolation Valve AOV 5392 open.

I I RO I Check Steam Dump Status I I Annunciator G-15, Steam Dump Armed - Lit I Steam DumD ODeratina DroDerlv in AUTO.

I Check Hotwell Level I I BOP I Hotwell level controller in Auto.

I Controller demand < 60%.

1I I I I Hotwell level at setooint. I I BOOTH OPERATOR'S NOTE: Wait until load has been decreased 30 MW before proceeding to Event 7. I

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

1 Event# 7,8 Event

Description:

Dropped Rods I Booth Operator Instructions: Insert malf. ROD02-J4. (Trigger #5) I Indications Available:

I E-28 POWER RANGE ROD DROP ROD STOP - 5% I5 SEC I 1 SRO 1 Refer to AP-RCC.3 I NOTE: Booth Operator should note discussion among the crew. If there is decision to Trip reactor that is imminent, move to Event 8 and drop second Control Rod immediately.

RO I Verify Only One Rod has Dropped.

I I RO I Place Rods to MANUAL. I

~ ~ ~

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

I 1 RO 1 Check Tavg - STABLE AT PROGRAM I I I BOP I Perform the following: I I I 1 Place EH control in MNAUAL. I Manually adjust turbine load to match Tavg and Tref.

I I I ROIBOP I Verify Annunciator G-15, STEAM DUMP ARMED -

EXTINGUISHED BOP Check Main Generator Load - GREATER THAN 15 MW

Appendix D Operator Action Form ES-DQ OpTestNo -1 Scenario ff -1 Event R 7.8 Page 25 01 33 Event Description Dropped Rods Time 1 Position I Applicant's Actions or Behavior RO I Establish Stable Plant Conditions:

I Tava -TRENDING TO TREF If Tavg greater than Tref. THEN restore Tavg to Tref by one or more of the following:

I I I Boration I I ROIBOP 1 IF Tavg less than Tref, THEN restore Tavg to Tref by one or more of the following: I Reduce turbine load Dilution of RCS RO 1 PRZR pressure -TRENDING TO 2235 PSlG IN AUTO RO PRZR level - TRENDIGN TO PROGRAM IN AUTO CONTROL MFW Regulating Valves - RESTORING S/G LEVEL TO 52%

INAUTO I

NOTE If not done already, Booth Operator should move to Event 8 and drop second Control Rod immediatelv.

Appendix D Operator Action Form ES-D-2 I I OpTestNo.:

Event

Description:

Time I 1

Position Scenario#

Dropped Rods I

1 Event# 7,8 Page Applicants Actions or Behavior 26 of 133 I Booth Operator Instructions: Insert malf. ROD02-J10. (Trigger #6) I Indications Available:

+PI Verify Only One Rod Has Dropped I I IF 2 or more rods dropped, THEN trip the reactor AND go to E-0. REACTOR TRIP OR SAFETY INJECTION. I E-0, REACTOR TRIP OR SAFETY INJECTION.

I I RO I Verify Reactor Trip: I I I Bop I Verify Both Trains of AC Emergency Busses Energized To At Least 420 VOLTS:

I I I Anv SI Annunciator - LIT I I I I IF anv of the followina conditions are met. THEN manuallv I I actuGe SI and CI: I 1

PRZR pressure less than 1750 psig OR Steamline pressure less than 514 psig 1

OR i

I CNMT pressure greater than 4 psig OR I I SI sequencing started OR 1

Appendix D Operator Action Form ES-D-2 OpTest No -1 Scenario# - 1 Event8 7,8 Page 27 of 33 Event Description Dropped Rods Time I Position I Applicants Actions or Behavior 0 Operator determines SI required IF SI is NOT required. THEN go to ES-0.1, REACTOR TRIP RESPONSE, Step 1 ES-0.1, REACTOR TRIP RESPONSE CAUTION: If SI Actuation occurs during this procedure, THEN E-0, Reactor Trip Or Safety Injection, should be performed.

RO Monitor RCS Tavg - STABLE AT OR TRENDING TRO 547°F I I RO I Check PRZR Level Control:

I I I Verify charging pumps -ANY RUNNING I I I I PRZR LEVEL - greater than 13% I Verify letdown - IN SERVICE PRZR level -TRENDING TO 20°h Check PRZR heaters - ENERGIZED PRZR proportional heaters PRZR heater backuD arouD 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 I Check RCS Tava - LESS THAN 554°F I I I I Verify MFW flow control valves - CLOSED I I I I MFW regulating valves I MFW bypass valves Verify total AFW flow - GREATER THAN 200 GPM Close MFW pump discharge valves

Appendix D Operator Action Form ES-0-2 OpTest No.: - 1 Scenario# -1 Event# 7,8 Page 28 of 33 Event

Description:

Dropped Rods Time I Position I Applicant's Actions or Behavior I 1 I MOV-3977,A MFW pump I I I I MOV-3976, B MFW pump I 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 bvoass valve controllers AND adiust to 0% demand.

I I I SIG A. HCV-466 and HCV-480 I I I I S/GB.HCV-476 and HCV-481 I Verify MRPl Indicates -ALL CONTROL AND SHUTDOWN Ro RODS ON BOTTOM I NOTE: Booth Operator may move to event 9 at this time. I

Appendix D Operator Action Form ES-D-2

~ ~ ~~ ~

OpTest No.: - 1 Scenario# - 1 Event# 9 Page 29 of J 3

3 Event

Description:

A Total Loss of Off-Site Power Occurs I Tlme I Position I Applicants Actions or Behavior I 1 Booth Operator Instructions: Insert malf. EDSO6 1 (FAST). (Trigger #7) I I Indications Available: I EVALUATORS NOTE: B EDG now running without Service Water. SI signal occurs because two Containment Pressure fails have failed (PT-945 initial conditions, PT-- on LOP from Instrument Bus e).

I I IF Bus 14 AND Bus 16 are deenergized, THEN go to ECA-0.0, LOSS OF ALL AC POWER. SteD 1.

ECA-0.0, LOSS OF ALL AC POWER.

CAUTION: Due to potentially extreme environmental conditions.

Caution should be used when entering the intermediate NOTE: CFSTs should be monitored for information only. PR procedures should not be implemented.

Local actions may require portable lighting and I

communication devices.

RO I Verifv Reactor Trio:

BOP I Verify Turbine Stop Valves - CLOSED I NOTE: FOLDOUT page should be open and monitored periodically. I BOP I Adjust S/GARVs To Control Tava At ADDrOXimatelv 547°F RO 1 Stoo Both RCPs

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

1 1 Event# 9 Page 30 of 33 Event

Description:

A Total Loss of Off-Site Power Occurs Time I Position I Applicant's Actions or Behavior RO I Check If RCS Is Isolated:

I I I PRZR PORVs - CLOSED I Verify RCS isolation valves closed:

Place letdown orifice valve switches to CLOSE AOV-200A AOV-200B AOV-202 I I I Place letdown isolation valve switches -to CLOSE I I I 1 AOV-371 I I I I AOV-427 I I Place excess letdown isolation valve switch to CLOSE (AOV-310) I

OpTestluo -1 Scenarioa -Event a 1 10 Page 31 of 33 Event Description TDAFW Pump Failure Time I Position I Applicanrs Actions or Behavior -

1 Booth Operator Instructions:

~~ ~

I Indications Available: I I I I Verify TDAFW pump - RUNNING I BOP 1 Verifv aovernor valve, V-3652. latched.

I Manually or locally open at least one TDAFW pump steam BOP supply valve.

MOV-3505A MOV-3504

/ -

I Critical Task (ECA-0.0-8) Establish greater than 200 gpm AFW flow before both S/G's levels decrease to < 35" wide range level.

BOP I Verify TDAFW pump flow - GREATER THAN 200 GPM

Appendix D Operator Action Form ES-D-2 OpTest No.: - 1 Scenario# -1 Event# 11 Page 32 of 33 Event

Description:

A EDG is restored to service.

Time I Position I Applicant% Actions or Behavior Booth Operator Instructions: Clear malf. GEN04A.

Indications Available:

NOTE: Conditions should be evaluated for Site Contingency Reporting (Refer to EPIP-1.O, 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 AEDG is available and the clearance may be lifted.

SROIRO Tw To Restore Power to Anv Train of AC Emeraencv Busses:

Verify emergency DIG aligned for unit operation Mode switch in UNIT Voltage control selector in AUTO RO Manually align switches on rear of MCB.

SROIRO Check emergency D/Gs - BOTH DIG RUNNING.

WHEN non-running DIG available for starting, THEN perform RO the followina:

Depress DIG FIELD RESET pushbutton Depress DIG RESET pushbutton Start DIG IF DIG starts, THEN go to Step 7.c.

RO CHECK DIG voltage and frequency Voltaae - APPROXIMATELY 480v

Appendix D Operator Action Form ESD-2 OpTest No.: - 1 Scenario# -1 Event# 11 Page 33 of 33 Event

Description:

A EDG i s restored to service.

Time I Position I Applicant's Actions or Behavior

~

I Freauencv - APPROXIMATELY 60 Hz RO/BOP Verify adequate D/G cooling One SW Pump running for each running D/G Verify at least one train of AC emergency busses -

ENERGIZED I I Bus 14andBus18 Critical Task (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.

SRO I Return to procedure and step in effect.

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

BOOTH 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 InstrumentationLoop Failure.) and MCB Annunciator J-8 has alarmed spuriously several times over the last hour (lac 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, 3.4.15, 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.1, 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 10°/dhour in accordance with 0-2.1, Normal Shutdown to Hot Shutdown.

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.1, Reactor Protection Bistable Defeat After Instrumentation Loop Failure. The operator will take manual control of the Charging Pumps and control Pzr Level.

Shortly after this, the SG Tube Leak will degrade to approximately 10 gpm. The operator will return to AP-SG.l, Steam Generator Tube Leak, and re-evaluate for the degraded conditions.

The procedure will start the crew on a rapid downpower at 3Ydminute.

After about 10-15% power reduction, an inadvertent Safety Injection signal will occur (The Automatic Reactor Trip is blocked). The operator will perform a manual reactor trip and enter E-0, Reactor Trip or Safety Injection.

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.1, Response to Loss of Secondary Heat Sink.

The operator will attempt to start the SAFW 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 lea t one Steam Generator before Bleed and Feed Criteria is met in FR-H.I. 6- 7 Scenario Event Description NRC Scenario 2 Simulator Set Up IC-172 Place Hold Tags on:

A MDAFW Pump Control Switch Close and Tag MOV 4007 Control Switch Place Protected Equipment Tags on:

0 B MDAFW Pump Control Switch Insert:

FDWIIA - A MDAFW Trip, (PulVStop, Hold Tag, Close MOV-4007, Protective Covers on B MDAFW Pump)

FDW12 (0 RPM) - TDAFW Pump Overspeed RPSOSA - Fail A Rx Trip Bkr (Manual Available)

RPS05B - Fail B Rx Trip Bkr (Manual Available)

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

RPS07L - B MDAFW Pump fails to auto start Ino/ovr IND-FW31 (SAFW Flow) to 0 Ino/ovr IND-FW33 (SAFW Flow) to 0 Events:

1 Trigger 1 - Malf. RMS02B (letoo7)

Trigger 2 - Malf. SGN04B (.4gpm) 2 When requested - LOA SGN24 (0) (Close V-996A) 3 None 4 Trigger 3 - Malf. RODIA-66 (Insert prior to commencing boration and Load Reduction) 5 Trigger 4 - Maw. PZR03C (100% @30secondramp) 6 Increase Malf. SGNO4B (IOgpm) 7 None 8 Trigger 5 - Malf. SlSOl (0) Train A 9 None (RPS05A and B set at TO) 10 (RPSO7L - B MDAFW Pump fails to auto start at TO), once started trip 2 minutes later by inserting FWD11B on Trigger 30.

11 None (FDW12 (0 RPM) - TDAFW Pump Overspeed at TO) 12 Trigger 29 - FWD15A - 60 delay (Initiated when C S A W Pump is manually started).

Trigger 28 - FWDl5B - 60 delay (Initiated when D S A W 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 (I&C is investigating).

Hold Tags have been placed on:

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

B MDAFW Pump Control Switch Scenario Event Description NRC Scenario 2 A-52.4 Equipment Date Reason Required Actions Required Required Action not met Completion FT-475 _I_I07 Failed ITS 3.3.2 Condition A (Steam Flow Channel Enter Condition ONLY Channel, B SG) referenced on Table 3.3.2-1 (4d, 4e) immediately.

Condition F (From 4d, e) Sondition G - Be in Mode

- Place Channel in Trip 3 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and Mode within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . 4 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

A MDAFW _I _I07 Bearing ITS 3.7.5 Condition B _I_IO? >ondition G - Required Pump replacement Restore MDAFW train to iction and associated operable status within 7 :ompletion time for days. Zondition B not met, be in Mode 3 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and Vlode 4 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

Aooendix D ODerator Action Form ES-D-2

~ ~ ~ ~

OpTest No.: - 1 Scenario# 2Event# 1 Page I,of 30 Event

Description:

R-12 Failure Time I Position I Applicants Actions or Behavior Booth Operator Instructions: Operates Trigger #l.

Indications Available:

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

iI I Refer to ITS LCO 3.3.5.

tI I SRO SRO I Notify RP to sample CNMT. I Evaluate the cause of the alarm.

Perform the following: I Initiate an t I Notify RP.

Notifv I&C.

SubmitWO. I REFER TO ITS 3.3.5, 3.4.15, 3.6.3.

LCO 3.3.5 I CONTAINMENT VENTILATION ISOLATION INSTRUMENTATION

Appendix D Operator Action Form ES-D-2 OpTest No.: - 1 Scenario# 2 Event# 1 Page of 30 Event

Description:

R-12 Failure Time I Position I Applicant's Actions or Behavior CONDITION REQUIRED ACTION COMPLETION TIME A. One radiation A.l Restore the affected monitoring channel channel to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months inoperable. OPERABLE status.

I SRO LCO 3.4.15 RCS LEAKAGE DETECTION INSTRUMENTATION CONDITION REQUIRED ACTION COMPLETION TIME B. Gaseous 6.1 Verify palticulate 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)

Appendix D Operator Action Form ES-D-2 OpTest No.: - 1 Scenario# 2 Event# 2 Page of 30 Event

Description:

B Steam Generator Tube Leak I T me 1 Postion I Applicants Actions or Behavior I 1 Booth Operator Instructions: Operates Trigger #2.

I AR-PPCS-1 I AR-PPCS-1, SGTL INDICATED.

RO I Trend PPCS points R1545A5G.

I I Notify RPKhemistry to IMMEDIATELY obtain and analyze an air ejector grab sample per CH-SAMP-SG-LEAKRATE.

RO I Determine the estimated leak rate usina the R15A5G.

I 1 SRO I IF any condition below is met. THEN a0 to AP-SG.1:

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

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

RO I Monitor PRZR Level.

RO I Monitor S/G Tube Leak Rate:

I PPCS Point R15A5G RO/BOP Trend S/G Leak Rate:

While continuing with this procedure, perform Part A of AT-16.1, ATTACHMENT SGTL Determine S/G leak rate:

PPCS point R15A5G

Appendix D Operator Action Form ES-D-2 OpTest No.: - 1 Scenario# 2Event# 2 Page of 30 Event

Description:

B Steam Generator Tube Leak Time I Position I Applicant's Actions or Behavior All-16.1. "ATTACHMENT SGTL."

Primary to secondary leakage in at least one SIG 2 5 gpd Request RP perform a second sample Notify RP to implement procedure CH-SAMP-SG-LEAKRATE.

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

0 Check operability of the following monitors.

R-15 R-15A R-19 R-31 R-32 Dispatch an A 0 to perform T-35H, Nuclear House Heating Steam To Boiler Steam Supply change 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 samole room).

Direct an A 0 to close V-996A, inlet block valve to Fl-2027 (S/G blowdown Hx A outlet flow) 1 BOOTH OPERATOR'S NOTE: LOA SGN 24 to "0" to CLOSE V-996A.

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

IF R-19 increases, THEN leakaae is in S/G B Open V-996A, inlet block valve to Fl-2027 (S/G blowdown Hx A Ro outlet flow).

Appendix D Operator Action Form ES-D-2 OpTest No -Scenario rt -

1 2 Eventb 2 Page of 30 Event Descriptcon B Steam Generator Tube Leak Time I Position I Applicants Actions or Behavior I BOOTH OPERATORS NOTE: LOA SGN024 to 100% to OPEN V-996A. I AP-SG.l, STEAM GENERATOR TUBE LEAK.

SRO Determine If Shutdown Required:

S/G tube leak rate GREATER THAN OR EQUAL TO 75 GPD SIG tube leak rate - STABLE OR RISING Go to Step 6.

SRO I Confirm S/G Leak Rate:

Notify higher supervision While continuing with this procedure, perform Parts A AND B Of AT-16.1, ATTACHMENT SGTL AIT-1 6.1. AITACHMENT SGTL.

I I SRO I Primary to secondary leakage in at least one S/G z 75 gpd I Refer to ITS LCO 3.4.13 Refer to ITS LCO 3.7.14 Refer to EPIP-1.O, Ginna Station Event Evaluation and Classification.

I I I Refer to 0-9-3, NRC IMMEDIATE NOTIFICATION. I BOP I Place Hotwell level controller in Manual at 50% position.

RO I Start the A and B CNMT Auxiliarv Charcoal Filter Fans.

SRO I Consult with RIP Chemistry.

OpTest No -1 Scenanod -2 Event P 2 Page 11- of 30 Event Descript on B Steam Generator Tube Leak Time I Position I Applicants Actions or Behavior Shift Support Heating Steam Trap Outlet Valves from the trap header to Blowdown Tank.

I BOPIAO I Request identification of leaking S/G from the Control Room.

I BOPIAO I Close trap drain isolation valve upstream of MSlV on the leakina SIG. I 1 BOPIAO 1 Verify Blowdown Tank discharge valve V-5714 is closed (at S/G Blowdown Tank). I I BOPIAO I Isolate Blowdown from the leakina SIG.

SRO I Refer to ITS LCO 3.7.5.

I I SRO I Refer to TRM 3.4.3. I PULL STOP the TDAFW Pump Steam Admission valve from Bop the leaking SIG.

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

AP-SG.1, STEAM GENERATOR TUBE LEAK.

SRO I Initiate Plant Shutdown Determine Slg leak rate every 15 minutes Check S/G leak rate - RISING LESS THAN 30 GPD/HR

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

Description:

B Steam Generator Tube Leak 8 Check R15A5 -OPERABLE

~

Check S/G leak rate - HAS REMAINED LESS THAN 144 GPD SINCE LEAK INITIATION 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) 8 Referto ITS LC03.4.13 LC03.4.16 LCO 3.7.14 Check following Tech Specs LCO 3.7.14 SECONDARY SPECIFIC ACTIVITY LCO 3.4.16 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.

CONDITION REQUIRED ACTION COMPLETION TIME A. RCS LEAKAGE not within limits for A.1 Reduce LEAKAGE hoUrS reasons other than to within limits.

pressure boundary LEAKAGE.

Appendix D Operator Action Form ES-D-2 OpTest No.: - Scenario# -2 Event# 3 Event

Description:

Plant Shutdown to Hot Standby Required By Tech Specs Booth Operator Instructions: Operate Trigger #3 (Note that this will cause the Continuous Rod Withdrawl malfunction to occur as soon as Rods receive a signal to move in Automatic).

Indications Available:

0-2.1, Normal Shutdown to Hot Shutdown.

EVALUATE whether the following surveillances will be SRO performed during this procedure.

NOTIFY RG&E Energy Control Center of impending load SRO reduction.

CHECK that Scheduling has notified CPS Generation Dispatch SRO of impending lowering of load including rate of load reduction and eXDeCted Dower level at which Dlant will stabilize, PLACE PRZR BACKUP HEATERS control switch to the ON RO position.

ADJUST ONE Pressurizer SPRAY VALVE controller setpoint to RO 50%.

I IF load reduction is necessary due to unusual plant condition, SRO THEN:

NOTIFY the following personnel of the unusual plant conditions requiring load reductions:

Plant Manaaer Manaaer. Ooerations I Assistant Ooerations Manaaer I Outaae Director I NOTIFY Shift Manager to commence investigation of

Appendix D Operator Action Form ES-D-2 OpTest No.: - 1 Scenario# -2 Event# 3 Page '5 of 30 Event

Description:

Plant Shutdown to Hot Standby Required By Tech Specs Time I Position I Applicant's Actions or Behavior unusual Dlant condition.

ENSURE Shift Manager (on duty) has conducted a shift briefing, with onsite Operations and Scheduling Supervision included. on Power reduction.

PLACE the Metal Impact Monitoring System (MIMS) ALARM ENABLEANHIBIT switch on the Master Control Module in the ALARM INHIBIT Dosition.

~ ~

(Note: Not Simulated)

Start of Load Reduction ENSURE the ROD CONTROL BANK SELECTOR switch is in the desired A (Automatic) OR M (Manual) position AND MARK position NOT used N/A.

~ ~~ ~~

REFER to S-3.1, Boron Concentration Control, AND INITIATE Boric Acid additions to the Reactor Coolant System, as necessary.

START the load reduction at the EH Control Panel as follows:

IF the IMP PRESS OUT pushbutton back light is illuminated. THEN PERFORM the followina:

~ ~ ~~

DEPRESS the IMP PRESS in Dushbutton VERIFY the IMP PRESS IN pushbutton back light is illuminated.

IF the EH Control Panel is in OPER PAN. Control, THEN PERFORM the following:

LOWER the SElTER setpoint using the V pushbutton.

DEPRESS the GO pushbutton.

Appendix D Operator Action Form ES-D-2 OpTest No.: - 1 Scenario# 2 Event# 4 Page 5 of 30 Event

Description:

Uncontrolled Automatic Rod Motion Occurs Time I Position I Applicants Actions or Behavior I Booth Operator Instructions:

I Indications Available: I I AP-RCC.l, CONTINUOUS CONTROL ROD WITHDRAWAUINSERTION. I I ROlBOP I Evaluate Rod Control System Operability:

I Check turbine load - STABLE I I I Place Rods to MANUAL I I I I Verify control rod motion STOPS I RO I Monitor Tava:

I I I Check Tavg -TRENDING TO Tref I I Check RCS Tavg Channel indications:

I I Check Turbine 1 Stage Pressure Channel, PI-485 -

APPROXIMATELY EQUAL TO PI-486 RO I Check NIS PR Indication:

I All Power Range Channels approximately equal.

I All AI indicators approximately equal.

I I RO I Establish Stable Plant Conditions: I Tavg Trending to Tref.

I I 1 Przr Pressure Trendina to 2235 osia in Auto. I I I I Przr Level trending to Program in Auto control. I RIL Alarms - Extinguished.

1 NIS PR AI within desired operatina band.

RO I Verify Control Rods Operable In Manual:

I InserVwithdraw control rods to MRPl transition

Appendix D Operator Action Form ES-D-2 OpTest No.: - Scenario# 2 Event# 4 Event

Description:

Uncontrolled Automatic Rod Motion Occurs Verify MRPl indicates control rod motion I Restore control rods to desired Dosition RO I Establish Control Systems In Auto:

I Control Rods in Auto.

I I I Przr Pressure in Auto. I I Spray Valves in Auto.

1 Przr Heaters restored.

I I I Verify one Charging Pump in Auto. I Crew I Evaluate MCB Annunciator Status I

SRO I Notify Higher Supervision I

Appendix D Operator Action Form ES-D-2 OpTestNo -1 Sccnarion- - 2 Event II 5 Page (8 of 30 Event Descnption Pnr Level Instrument Malfunction Tame I Position I Applicants Actions or Behavior I Booth Ooerator Instructions: Operate Triaaer #4.

I Indications Available: I NOTE: The downpower should recommence with Control Rods in MANUAL.

I F-4, PRESSURIZER LEVEL DEVlAlTON - 5 NORMAL + 5 I I I F-28, PRESSURIZER HIGH LEVEL CHANNEL ALERT 87% I I AR.F-4. PRESSURIZER LEVEL DEVlAlTON - 5 NORMAL + 5 I Perform a channel check. I Verify Backup Heaters on at + 5%.

Check charging pump speed and controls.

Check Letdown in service.

Control Charging and Letdown as necessary to control level. 1 ER-INST.l for failed channel.

I AR-F-28, PRESSURIZER HIGH LEVEL CHANNEL ALERT 87%. I RO I Perform a channel check.

RO I Check charging and letdown.

I I 1 SRO I For failed channel go to ER-INST.1. I

Appendix D Operator Action Form ES-D-2 OpTest No.: - 1 Scenario# 2Event# 5 Page 19 of 30 Event

Description:

Przr Level Instrument Malfunction Time I Position I Applicants Actions or Behavior I ER-ISNT.l, Reactor Protection Bistable Defeat After Instrumentation Loop Failure. I Identify the failed instrument channel by observation of the SROIRO bistable status light board, MCB annunciators, and the MCB metering indication.

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.

Appendix D Operator Action Form ES-D-2 OpTest No.: - 1 Scenario # 2 Event # 6,7 Page 20 of 30 Event

Description:

Rapid Downpower due to increased Steam Generator Tube Leak Time I Position I Applicants Actions or Behavior I Booth Operator Instructions: Once RO has effectively controlled charging and letdown. increase SGNO4B to 10 aDm. I I Indications Available: I AP-SG.1. STEAM GENERATOR TUBE LEAK.

RO Monitor PRZR Level I I ROlBOP I Monitor S/G Tube Leak Rate: I I I I Estimate S/G tube leak rate:

0 I PPCS Point R15A5G Check total RCS to secondary leak rate - LESS THAN 1 GALLON PER MINUTE (1440 GPD)

I I SRO I Initiate Load Reduction I 1 I I

~~

I BOP Reduce-turbine load in Auto as follows:

Place Turbine EH Control in OPER Pan. IMP PRESS IN. if desired.

Select rate of 3%/min on thumbwheel.

Reduce the setter to zero. -

Deoress the GO button.

I I RO I Initiate boration at -2 aal/%. I I I I Place PRZR backuD heaters switch to ON. I BOP Transfer 4160V Auxiliary load from #11Transformer.

RO Monitor RCS Tavg.

RO Adjust Boric Acid Addition Rate As Necessary to:

Appendix D Operator Action Form ES-DP OpTest No.: - 1 Scenario # 2 Event # 6,7 Page 21 of 30 Event

Description:

Rapid Downpower due to increased Steam Generator Tube Leak Time I Position I Applicant's Actions or Behavior I I I Maintain control rods above insertion limits I I I 1 Match Tavq and Tref I I I I Compensate for Xenon I NOTE: Ensure load decreases at least 30 MW before the initiation of Event 8.

Appendix D Operator Action Form ES-DP OpTest No.: - 1 Scenario# 2 Event# 8.9, i o , & 11 Page 22 of 30 Event

Description:

Inadvertent Safety Injection Occurs Causing an ATWS Automatic Reactor Trip is Blocked Manual Trip Received; B MDAFW Pump Fails to Auto Start and then Trips Shortly After Manual Start; TDAFW Pump Trips on Overspeed I Time I Position I Applicanrs Actions or Behavior I Booth Operator Instructions:

Indications Available:

Operate trigger #5.

I E-0, REACTOR TRIP OR SAFETY INJECTION.

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

RO I Manuallv triD reactor.

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

I Bop I Verify Both Trains of AC Emergency Busses Energized To At Least 420 VOLTS: I I I ROlBOP 1 Check il SI is Actuated: I I I I SI sequencing - BOTH TRAINS STARTED. I RO I Manuallv actuate SI and CI.

I RO 1 Verify CNMT Spray Not Required:

I I SRo I Direct Operator to Perform AT-27.0, ATACHMENT AUTOMATIC ACTION VERIFICATION BOP I Verifv Both MDAFW PurnDs Runnina

Appendix D Operator Action Form ES-D-2 OpTest No.: - 1 Scenario # 2 Event # 8,9,10, & 11 Page 23 of 30 Event Descriution: Inadvertent Safety Injection Occurs Causing an ATWS; Automatic Reactor Trip is Blocked - Manual Trip Received, B MDAFW Pump Fails to Auto Start and then Trips Shortly After Manual Stalt; TDANV Pump Trips on Overspeed Time I Position I Applicants Actions or Behavior Manually start both MDAFW Dumps.

NOTE: A MDAFW Pump 00s and B MDAFW will fail to Auto Start. It must be started manually.

IF less than 2 MDAFW DumD are running, THEN manuallv open TDAFW pump steam Supply valves.

Verify AFW Valve Alignment:

Manually align valves as necessary.

I BOOTH OPERATOR! UOTE: TriD B MDAFW PumD 2 minutes after DumD start. (Trigger #30)

BOP Monitor Heat Sink:

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

BOP Verifv total AFW flow - GREATER THAN 200 GPM 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 oreater than 200 opm can NOT be established.

THEN go to FR-H.I, RESPONISETO LOSS OF SECONDARY HEAT SINK, Step 1.

I FR-H.1. RI SPONSE TO LOSS OF SECONDARY HEAT SINK.

ROIBOP Check If Secondary Heat Sink Is Required:

RCS pressure - GREATER THAN ANY NON-FAULTED SIG PRESSURE I Check RCS cold leg temperature - GREATER THAN 350°F

Appendix D Operator Action Form ES-D-2

~ ~ ~ ~ ~

OpTestNo -Scenario# -

1 2 Event# 8.9. l o . & 11 Page 24 of Event Description Inadvertent Safety Injection Occurs Causing an AMIS; Automatic Reactor Trip is Blocked Manual Trip Received; B MDAFW Pump Fails to Auto Start and then Trips Shortly After Manual Start; TDAFW Pump Trips on Overspeed Time I Position I Applicant's Actions or Behavior I BOP I Monitor Secondary Heat Sink:

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

I I 1 Verifv PRZR Dressure - LESS THAN 2335 PSIG. I BOP Try to Establish AFW Flow To At Least One Intact SIG:

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

I I BOP I Verify TDAFW pump available. I I NOTE: The TDAFW Pump has undergone an Overspeed Trip and cannot be reset.

I 1 RO I Stop Both RCPs. I

Appendix D Operator Action Form ES-D-2 OpTest No.: - 1 Scenario# 2Event# 12 Page 25 of 3 0 Event Descnption: S A W Flow Transminers are Isolated Resulting in Pump Run Out of SAFW Pump. (Pumps Trips c 60 Seconds After Start)

Time 1 Position I Applicants Actions or Behavior l

RO I Reset SI If Actuated I

RO Try To Establish SAFW Flow To At Least One Intact S/G:

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

RO 1 Alian SAFW PumD C to selected S/G as follows:

I I I Ensure SI Reset I I I I 0 Ensure the followinQvalves open: I I I I MOV-9701A, SAFW PUMP C DISCHARGE VLV I I I I MOV-4616, AUX BLDG SW ISOL VLV I I I I MOV-9704A, SAFW PUMP C S O L VLV I BOP I Open MOV-9629A, SAFW PUMP C SUCTION VLV.

Verify at least 1 SW pump running.

i To feed S/G A.

Restore S A W flow as directed bv DrOCedUre in effect.

I Determine S A W flow requirements per ATT-22.0, ATTACHMENT RESTORING FEED FLOW ATT-22.0, ATTACHMENT RESTORING FEED FLOW.

SRO/BOP Initiate Feed flow as follows:

Appendix D Operator Action Form ES-D-2 OpTest No.: - 1 Scenario# -2 Event# 12 Page 26 of 30 Event

Description:

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

Time I Position I Applicants Actions or Behavior IF feedwater flow to affected SIG greater than 50 gpm OR affected SG level greater than 50 inches (100 inches adverse SROIBOP 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 SROIBOP (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.

RO Start selected SAFW pump(s).

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

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

Perform the following:

Align S A W system for operation (Refer to AT-5.1 ATTACHMENT S A W )

I ATT-5.1, ATTACHMENT SAFW.

RO I Align S A W PumD D to selected S/G as follows:

I I I Ensure SI Reset I I I Ensure the following valves open:

MOV-97018, SAFW PUMP D DISCHARGE VLV MOV-4615, AUX BLDG SW ISOL VLVS MOV-9704B, S A W PUMP D ISOL VLV MOV-9746, SAFW PMP D EMERG DISCH VLV 0 Open MOV-9629B, SAFW PUMP D SUCTION VLV.

Appendix D Operator Action Form ES-DP OpTest No.: - 1 Scenario# 2Event# 12 Page 27 of 30 Event

Description:

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

Time I Position I Applicants Actions or Behavior I I BOP Verify at least 1 SW pump running.

To feed SIG A, perform the following:

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

T

~

MOV-9703A OR I I I MOV-97030 Verify open MOV-9704A, SAFW PUMP C ISOL VLV RO 1 Restore SAFW flow as directed by procedure in effect.

Determine SAFW flow requirements per ATT-22.0 ATTACHMENT RESTORING FEED FLOW An-22.0, ATTACHMENT RESTORING FEED FLOW.

SROIBOP 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 SROIBOP 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 S/G. WHEN SIG level greater than 50 inches SROIBOP (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.

RO Start selected SAFW pump(s)

Appendix D Operator Action Form ES-DP Scenario# - 2 Event# 12 Event

Description:

IF greater than 235 gpm total SAFW flow can NOT be SRo established, THEN go to Step 7 I FR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK BOP I TWto Establish MFW Flow to at Least One S/G I I I Check any MFW Dump AVAILABLE I I I Check condensate system:

I I I Condensate pump - CNY RUNNING

! I I MFW pump suction pressure GREATER THAN 200 PSlG I 1 BOP I Establish MFW flow:

I I I Check MFW pump discharge valves - CLOSED I 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.

I I I Open MFIV's for both S/G's:

SIG A, AOV-3995 S/G B, AOV-3994 Dispatch A 0 to restore MFW pump SW cooling 1 Verifv S/G blowdown kev switches in NORMAL Ensure Annunciator H-4, MAIN FEED PUMP OIL SYSTEM - EXTINGUISHED Close Condensate Bypass valve, AOV-3959.

Ensure Annunciator H-11, FEED PUMP SEAL WATER LO DlFF PRESS 15 PSI - EXTINGUISHED Ensure one MFW pump recirc valve - OPEN

Appendix D Operator Action Form ES-D-2 Scenario# 2Event# 12 Event

Description:

S A W Flow Transmitters are Isolated Resulting in Pump Run Out of S A W I I Start Selected MFW DumD I I Open MFW DumD discharae valve Open MFW regulating or bypass valves to control MFW flow per requirements of ATT-22.0, ATTACHMENT RESTORING FEED FLOW An-22.0, AlTACHMENT RESTORING FEED FLOW SROIBOP 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 adverse CNMT),

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

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

IF NO, THEN establish less than or eaual to 100 aDm feed flow to affected SIG. WHEN SIG level greater than 56inches (100 SROIBOP 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.

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

I Ro I Check RCS Loop Hot Legs - BOTH HOT LEG TEMPERATRUES DECREASING BOP Verify affected SIG 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.

Appendix D Operator Action Form ES-D-2 OpTest No.: - 1 Scenario# 2vent# 12 Page 30 of 30 Event

Description:

SANY 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 t I I FR-H.l, RESPONSE TO LOSS OF SECONDARY HEAT SINK SRO I Go to Step 11.

J BOP Check S/G Levels:

Narrow range level in at least one SIG - GREATER THAN 7% (25% adverse CNMT)

I I SRO I Return to procedure and step in effect. I EAL 1.3.1 (SAE) Red Path on Heat Sink Modes 1-4.

Scenario Event Description NRC Scenario 3 Ginna 2007 NRC Scenario #3 The Plant is critical at IO8 amps in the process of starting up after a short duration shutdown (MOL). The Electrical Distribution System is in a 50/50 Alignment. The startup procedure (0-1.2) is complete through step 6.3.4, and now it is intended to proceed to the POAH.

The following equipment is Out-Of-Service: Pressurizer Pressure channel PT-449 (The channel has been defeated per ER-INST.l) and MCB Annunciator E-16, RMS Process Monitor High Activity, has failed and is Locked In (I&C is investigating).

The Reactor Operator completes the startup to the POAH in accordance with 0-1.2, Plant Startup From Hot Shutdown to Full Load. Upon arrival at the POAH the compensating voltage to IR N-35 is lost. The operator will stabilize and respond in accordance with AR-E-9, IR N-35 Loss of Compensating Voltage, and ER-NIS.2, IR Malfunction. The operator will address Technical Specification 3.3.1, Reactor Trip System Instrumentation, and respond to the Technical Specification Action. This will require that the crew stabilize power at IO amps while I&C investigates and completes repairs.

Upon insertion of the Control Rods to lower power to IO-,one Control Rod Individual Rod Position Indicator (MRPI) will fail. The operator will respond in accordance with AP-RCC.2, RCC/RPI Malfunction, and address Technical Specifications 3.1.4, Rod Group Alignment Limits, and 3.1.7, Rod Position Indication. I&C will repair both the IR and MRPI failures.

Shortly afterwards, the Letdown Pressure Controller fails causing Control Valve PCV-135 to close. The operator will respond in accordance with AR-A-11, Letdown Line Hi Press 400 PSI, and take manual control of PCV-135.

Shortly afterwards, a leak will develop on the discharge expansion joint of the C Service Water Pump. The operator will respond in accordance with AP-SW.2, Loss of Service Water, and AP-SW.l, Service Water Leak, and because of water spray onto the C Service Water Pump, the pump will trip. The operator will address Technical Specification 3.7.8, Service Water System.

Upon restoration of the Service Water System, a Large Break LOCA will occur. The plant will trip and SI will actuate. Both trains of CI will fail to actuate requiring the operator to manually isolate the Containment. The operator will enter E-0, Reactor Trip or Safety Injection, RCPS will be stopped and transition will be made to E-I, Loss of Reactor or Secondary Coolant.

After S K I is reset a loss of Circuit 767 will occur such that the B EDG will start and re-power Bus 16, however the feeder breaker from Bus 17 will fail to reclose (SW Pumps Band D are de-energized) (LER 2005-003).

The operator should transition to ES-1.3, Transfer to Cold Leg Recirculation, and align the RHR System for Cold Leg Recirculation, using Attachment 2.1, Attachment Min SW, for guidance on minimum Service Water.

Critical Tasks:

CT E-0-0 Initiate CNMT isolation such that at least one valve is closed in each flowpath which is passing fluid out of containment.

Scenario Event Description NRC Scenario 3 CT ES-1.3-A Transfer to cold leg recirculation on at least one train of RHR pump(s) prior to cavitating SI pumps taking suction from the RWST.

Scenario Event Description NRC Scenario 3 Simulator Set Up IC-173 Ensure Electrical Distribution is in 50/50 Lineup.

Insert:

PZR02D (0) - Fail PZR Pressure PT-465 (Perform Defeat per ER-INST.l)

Fail Annunciator E-I6 On RPSO6 - Fail Containment Isolation (Both Auto and Manual)

Events:

1 None 2 Trigger 1 - Malf. NISO5A (lea8) 3 Trigger 2 (ROD11-G3 (230) Fail MRPl at TO) 4 Trigger 3 - Malf. CVCO7A set at 0(Manual Available) 5 Trigger 4 - Malf. CLGOlC (SW Pump C Trip) and Malf. CLGOBE (SW Leak

@ 200 gpm). A-EDS33 (L-8 on).

6 Trigger 5 - Malf. RCS03D (LBLOCA) 7 None (RPSO6 - Fail Containment Isolation (Both Auto and Manual) at TO) 8 I Trigger 6 - Malf. EDSOIB 9 I None (Malf. GENOGD - Bus 17 Feeder Breaker Failure at TO)

Scenario Event Description NRC Scenario 3 Shift Turnover:

The Plant is critical at 10" amps in the process of starting up after a short duration shutdown (MOL). The Electrical Distribution System is in a 50/50Alignment. The startup procedure (0-1.2) is complete through step 6.3.4, and now it is intended to proceed to the POAH.

The following equipment is Out-Of-Service: Pressurizer Pressure channel PT-449 (The channel has been defeated per ER-INST.1) and MCB Annunciator E-16, "RMS Process Monitor High Activity," has failed and is "Locked In" (I&C is investigating).

After turnover you have been directed to continue with the startup and proceed to the POAH.

Scenario Event Description NRC Scenario 3 A-52.4 Equipment Date Time Reason Required Actions Required Required Action not met Completion Daterrime PT-449 _I- I07 Failed ITS 3.3.1 Condition A TRACKING (Przr Pressure) Channel One or more functions with ONLY one channel inoperable, entei the Condition referenced by Table 3.3.1 -1 immediately.

Condition D (F5) -As 2ondition G (F5) - Required required by Required Action W o n D.l and associated A.l and referenced by Table :ompletion time not met, be in 3.3.1-1, place the channel in dode 3 in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

trip in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

Condition K (F7a) -As 2ondition L (F7a) - Required required by Required Action W o n and associated A.l and referenced by Table :ompletion time of Condition K 3.3.1-1, place the channel in lot met, reduce thermal power trip in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . o c 8.5% RTP in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ITS 3.3.3 Condition A (Fl, f6) :ondition F (Fl, F6) As required One or more functions with )y reference in Table 3.3.3-1, be one channel inoperable, n Mode 3 in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and Mode restore required channel to Iin 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

operable status within 30 days.

Appendix D Operator Action Form ES-D-2 OpTest No.: - 1 Scenario# 3 Event# 1 Page - of 7 37 Event

Description:

Raise Reactor Power to POAH Time I Position I Applicanrs Actions or Behavior -

I Booth Operator Instructions: I Indications Available:

I --I I 0-1.2, Plant Startup From Hot Shutdown to Full Load. I RO I RAISE Reactor Power to amroximatelv 1.O x 10 as follows:

WITHDRAW the controlling bank of rods to establish I Ro I WHEN Reactor Power is approaching 1.0 x 10. AMPS, THEN PERFORM the followina:

I I I INSERT rods to level off at 1.0 x I I I I RECORD Actual Critical Rod Position I I I I RECORD Bank -, I RECORD Estimated Critical Rod Position 1

I RECORD Bank RECORD Boron 1

RECORD WITHDRAW controlling bank of Rods and raise Reactor Power RO to the point of adding heat without exceeding the capacity of one A W Puma BOP VERIFY one of the following is operating to control RCS Tavg SGARVs Condenser Steam Dumps

Appendix D Operator Action Form ES-D-2 Op Test No.: - 1 Scenario# 3 Everit# 1 Event

Description:

Raise Reactor Power to POAH I Time I Position I Applicant's Actions or Behavior ENSURE FW Pump Ventilation is in automatic PER T-4G, Main Bop Feedwater Pump Motor Ventilation System.

Appendix D Operator Action Form ES-D-2 OpTest No.: - 1 Scenario# -3 Event # 2 Page of 37 Event

Description:

N35 IR Failure Time I Position I Applicants Actions or Behavior Booth Operator Instructions: When Reactor Power at the POAH, Operate Trigger #I.

I Indications Available: I I I I E-9, IR N-35 LOSS OF COMPENSATION VOLTAGE I AR-E-9, IR N-35 LOSS OF COMPENSATION VOLTAGE.

I Refer to ER-NIS.2 II- SRO ER-NIS.2, IR MALFUNCTION. I Defeat the reactor trip and rod stop function for the affected Ro channel by placing the level trip switch in the BYPASS position.

SRO I Notify I&C to repair the faulty channel.

I Refer to ITS Section 3.3.1, Table 3.3.1-1, Function #3 and SRO Function #16a for NIS intermediate range channel operability requirements.

SRO I The SRO will address the followina Tech SDecs:

SRO I LCO 3.3.1 I I I REACTOR TRIP SYSTEM (RTS) INSTRUMENTATION I SRO I Table 3.3.1-1 I I I 3. Intermediate Range Neutron Flux E, G I

16. Reactor Trip System Interlocks

a. Intermediate Range Neutron Flux, P-6 s, v

Appendix D Operator Action Form ES-D-2 OpTest No.: - 1 Scenario# -3 Event# 2 Page to of 37 Event

Description:

N35 IR Failure Time I Position I Applicant's Actions or Behavior t A.

CONDiTiON Oneor more Functionswith one A.I REQUIREDACTION Enter the Condition referenced in Table COMPLETIONTIME Immediately channel inoperable. 3.3.1-1 for the I channel@)

CONDITION REQUIREDACTION COMPLETIONTIME E. As required by E.l Reduce THERMAL hours Required Action A.l POWER lo < 5E-11 and referenced by amps.

Table 3.3.1-1.

OR E.2 IncreaseTHERMAL POWER TO L 8% 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months RTP.

G. Required Action and Gl, Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition D, E. or F is not met.

S. As required by Required Action A.l s.l Verify interlock is in required state for and referenced by existing plant Table 3.3.1-1. conditions.

OR s.2 Declare associated FITS Function 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months channel@)

inoperable.

V. Required Action and v,l Be in 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition R , S, T. or U not met.

I I Recognize that THERMAL POWER must be reduced to < 5E-11 a m m or increased to 2 8% RTP within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

SRO I Contacts Operations Manager for guidance.

Appendix D Operator Action Form ES-D-2 OpTest No.: -Scenario# 3Event# 2 Event

Description:

N35 IR Failure Booth Operator: When asked, cue SRO as Operations Management:

SRO should reduce power and stabilize at 10' amps, do not approach or exceed a negative one-third Startup Rate, and await further instructions.

The intention is to have I&C investigate the failure and if possible repair the voltage supply on N35. If this cannot be accomplished, the reactor will be shutdown.

I I Ro I Drive rods in to stabilize reactor power at loa amps while not approaching or exceedina a neaative one-third StartuD Rate.

I I Note: Once RO has started driving rods inward to stabilize power at 10.' amps, move on to event 3.

Appendix D Operator Action Form ES-D-2 OpTest No.: - 1 Scenario# 3 Event# 3 Page 2 of 37 Event

Description:

MRPl Failure Time I Position 1 Applicants Actions or Behavior I Booth Operator Instructions: Operate Trigger #2.

Indications Available:

C-5, PPCS ROD SEQUENCE OR ROD DEVIATION/PPCS LTOP HI-LOW TEMPERATURE MRPl I AR-Cd, PPCS ROD SEQUENCE OR ROD DEVIATION/PPCS LTOP HI-LOW TEMPERATURE.

SRO 1 IF rod Dosition deviation. THEN I I SRO I

GOTOAP-RCC.2 I I RO I Check PPCS for ODerabilitv I 1 RO 1 Check PPCS for Fail Over I I SRO I Refer to ITS 3.1.4 and ITS 3.1.6 AP-RCC.2, RCC/RPI MALFUNCTION.

I I RO 1 Place Rods to Manual RO Check Dropped Rod Indication:

Annunciator E-28, POWER RANGE ROD DROP ROD STOP 5%/5 SECONDS - EXTINGUISHED 1 Annunciator C-14, ROD BOTTOM ROD STOP -

EXTINGUISHED RO I Check Tavg - STABLE AT PROGRAM I Ro I Verify Annunciator G-15, STEAM DUMP ARMED -

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

Appendix D Operator Action Form ES-D-2 OpTest No.: - 1 Scenario# 3 Event# 3 Page of 37 Event

Description:

MRPl Failura Time I Position I ApplicanYs Actions or Behavior NOTE: Turbine is NOT latched.

I I SRO 1 Establish Stable Plant Conditions: I I 1 RO 1 Tavg - TRENDING TO TREF I I I I PRZR pressure - TRENDING TO 2235 PSlG IN AUTO I I PRZR level -TRENDING TO PROGRAM IN AUTO CONTROL I 1 1 MFW Regulating Valves - RESTORING S/G LEVEL TO 52%INAUTO RO Check Control Rod Alignment:

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

I I RO I Check QPTR - LESS THAN 1.02 I RO I 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 SRO I Perform the following:

I Refer to ITS section 3.1.7 for reauired action.

I I I Consult Reactor enaineer and Dlant staff to evaluate MRPI. I RO I Verify Aftected Group Step counters Operable:

Appendix D Operator Action Form ES-D-2 OpTest No.: - 1 Scenario# 3 Event# 3 Page of 37 Event

Description:

MRPl Failure Time I Position I Applicant's Actions or Behavior Affected bank group step counter movement -

CONSISTENT WITH MRPl TRANSITIONS (Evaluate affected bank using PT-1, ROD CONTROL SYSTEM) 0 Group step counters for affected bank - WITHIN 1 STEP OF EACH OTHER I

Check Reactor Conditions: I Rod insertion limit alarms - EXTINGUISHED I NIS PR AI -WITHIN DESIRED OPERATING BAND I BOOTH INSTRUCTOR'S NOTE:

Report to Control Room as I&C.

After some investigation, report that blown fuse is suspect.

Allow delay for repair and for SRO to check Technical Specifications.

Remove Malf RODll-G3. Report (As l a c ) that MRPl failure has been repaired.

If asked, express awareness of the N35 malfunction.

Report that power supply failure is suspect and that a Technician is obtaining another Power SUDPIY.

1 The SRO will address the following Tech Spec:

I SRO I LCO 3.1.4 I ROD I GROUP ALIGNMENT LIMITS CONDITION I REQUIRED ACTION 1 COMPLETION TIME B.I.1 Verity SDM is within

8. One rod not within the limits specified 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months alignment limits. in the COLR.

SRO I LCO 3.1.7 I ROD POSITION INDICATION

Appendix D Operator Action Form ES-D-2 OpTest No.: - Scenario# - 3 Event# 3 Event

Description:

MRPl Failure CONDITION REQUIRED ACTION COMPLETIONTIME 8 OneMRPlpw group A.l Verify the position onceper 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months inoperable for of the rods with one or more inoperable position groups. indicators by using movable incore detectors.

OR A.2 Reduce THERMAL 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months POWER TO< 50%

RTP.

SRO I Evaluate Plant Conditions:

I Rod/MRPI malfunction - REPAIRED Verify control rod operability - OPERABILIT RESTORED (Refer to PT-1, ROD CONTROL SYSTEM)

RO 1 Establish Control Systems In Auto I 0 Verify 431K in AUTO Verify PRZR spray valves in AUTO Verify PRZR heaters restored:

0 PRZR DroDortional heaters breaker - CLOSED I PRZR backuD heaters breaker - RESET. IN AUTO Verify one charging pump in AUTO Verify MFW regulating valves in AUTO BOP Place MFW regulating valves in AUTO, if desired.

NOTE: MFW System is not operating at this point in the Staltup.

BOP I Restore EH controls Place in OP PAN. IMP OUT Place load rate thumbwheel to lO%/hr March setter and reference

Appendix D Operator Action Form ES-D-2 OpTest No.: - 1 Scenario# - 3 Event # 3 Page '6 of 37 Event

Description:

MRPl Failure Time I Position I Applicant's Actions or Behavior Verify annunciator G-15, STEAM DUMP ARMED -

EXTINGUISHED RO Verifv rods in AUTO

~ ~~ ~

RO Place rods in Auto, if desired.

Note: Rod will not be in auto at low power.

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

I I SRO 1 Notifv Higher SuDervision SRO I Return to Procedure or Guidance in Effect BOOTH INSTRUCTOR'S NOTE: Remove Malf NISOSA. Report (As lac) that IR Compensating Voltage Power Supply has been reDaired.

[ e o o T H x S T R E T O R S NOTE: Operation Manager direct SRO to conlinue with the startuD and Droceed to the POAH.

Appendix D Operator Action Form ES-D-2 OpTest No.: - 1 Scenario# -3 Event# 4 Page of 37 Event

Description:

Letdown Pressure Controller Fails Low Time I Position I Applicants Actions or Behavior Booth Operator Instructions:

Indications Available:

When Reactor Operator begins to withdrawl control rods, Operate Trigger #3. I I A-3, LO PRESS LTDN RELIEF VLV HI TEMP 130°F.

I I I A-1 1, LETDOWN LINE HI PRESS 400 PSI. I AR-A-3, LO PRESS LTDN RELIEF VLV HI TEMP 130°F.

Check PI-135; IF greater than 500 PSI, reduce letdown RO I Check ODeration of PCV-135.

RO I Verifv AOV-371 is oDen.

RO Monitor PRT for the following:

Pressure (PI-440)

Level (Ll-442)

I I I TemDerature (TI-439)

AR-A-11, LETDOWN LINE HI PRESS 400 PSI.

RO I Adjust PCV-135 controller to lower setting.

I I RO I Transfer PCV-135 controller to manual if necessary. I I Ro I Verify letdown flow (FI-134) is consistent with letdown orifice in service.

Appendix D Operator Action Form ES-DP Event

Description:

Service Water LeakPump Trip 1 Booth Operator Instructions: Operate Trigger #4. I Indications Available:

I L-8, 480 Volt Ground.

C Service Water Pump Trips AP-SW.2, Loss of Service Water.

I I BOP 1 Verifv 480V AC Emeraencv Busses 17 and 18 - ENERGIZED 1 L BOP I Verify At Least One SW Pump Running in Each Loop:

I A or B pump in loop A I c or D D u m in 1000B I 1 BOP I Manually start SW pumps as necessary (257 kw each). I I I SRO I If at least two pumps can be started c10 to step 8. I BOP I Select Operable Service Water Pumps for Auto Start.

I I SRO I Evaluate MCB Annunciator Status I SRO I Return to Procedure or Guidance in effect.

Appendix D Operator Action Form ES-D-2 OpTest No.: - Scenario# 3 Event# 5 Event

Description:

Service Water LeaWPump Trip 1 Booth Operator Note: ~P Contact Control Room as A 0 and report:

A Service Water Leak in the Screenhouse.

At the discharge of the C Service Water Pump, near the expansion joint.

Estimate about 200 gpm leak.

I ReDOrt that the leak can be isolated.

AP-SW.l, Service Water Leak.

I I BOP I Verify 480V AC Emergency Busses 17 and 18 - ENERGIZED BOP Verify At Least One SW# Pump Running in Each Loop:

A or B pump in loop A I I 1 C or D pump in loop 6 1 ROlBOP I Check SW Svstem Status:

I I I Check SW lo00 header oressures:

I I I Pressure in both loops -APPROXIMATELY EQUAL I I 1 PPCS sw JOW pressure alarm status - NOT LOW I Pressure in both loops - STABLE OR RISING I I 1 Check SW loop header pressures -GREATER THAN 55 PSlG i 1 1:

RO Check For SW Leakage In CNMT:

I Check Sumo A indication SumpAlev;RRISING Sump A pump start frequency - RISING (Refer to RCS Daily Leakage Log)

Appendix D Operator Action Form ESD-2 OpTest No - 1 Scenario R -3 Event d 5 Page 20 ot 37 Event Descnption Service Water LeaWump Trip Time I Position I Applicants Actions 01 Behav or SRO IF the SW leak is NOT in the CNMT, THEN go to Step 6.

Dispatch A 0 to Screenhouse to Perform the following:

0 Verifv idle SW DumD check valve CLOSED.

I Idle DUmD shaft StODDed Idle pump discharge pressure -ZERO (unisolated and check local pressure indicator)

Investigate for SW leak in Screenhouse - NO EXCESSIVE LEAKAGE INDICATED I Perform the following:

Identify leak location.

Notify Control Room of leak location.

BOOTH INSTRUCTORS NOTE: Report SW leak form C SW Pump Expansion Joint, and that he is in the process of isolating the leak.

Refer to ATT-2.2. ATTACHMENT SW ISOLATION for a list of the major non-safeguards loads supplied by each service water header.

The SRO will address the followina Technical SDecifications:

LCO 3.7.8 SERVICEWATER (sw) SYSTEM I

Booth Instructors Note: Remove Malfunction CLG08E.

Report to the Control Room, as the AO, that the SW Leak is isolated.

Append Y D Operator Action Form ES-0-2 I 1 II OpTest No.: - 1 Scenario# 3Event# 6&7 Page 21 of Event

Description:

A Large Break LOCA Occurs; CI Trains A B Fail to Actuate I

Time I Posit.on I Applicants Actions or Behavior I I Booth Operator Instructions: Operate Trimer #5.

1 Indications Available: I E-0, REACTOR TRIP OR SFETY INJECTION.

I I RO I Verifv Reactor Trio: I I At least one train of reactor trio breakers - OPEN I I I Neutron flux - LOWERING I MRPl indicates -ALL CONTROL AND SHUTDOWN RODS ON BOTTOM I

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

Bus 14 and Bus 18 I I 1 Bus 16 and Bus 17 I BOPlRO Check if SI is Actuated:

Any SI Annunciator - LIT SI seauencina - BOTH TRAINS STARTED RO I Verify CNMT Spray Not Required:

1 Annunciator A-27. CNMT SPRAY - EXTINGUISHED

~

I I I CNMT Dressure -LESS THAN 28 PSlG I RO I Verify CNMT spray initiated.

I Ro I Direct Operator to Perform ATT-27.0, ATTACHMENT AUTOMATIC ACTION VERIFICATION

Appendix D Operator Action Form ES-DQ OpTest No.: - Scenario # 3 Event # 6&7

- An-27.0. ATTACHMENT AUTOMATIC ACTION VERIFICATION.

RO Verify SI and RHR Pumps Running:

All SI pumps - RUNNING Both RHR PumDs - RUNNING Verify CNMT RECIRC Fans Running:

All fans - RUNNING Charcoal filter dampers green status lights -

EXTINGUISHED RO I Check If Main Steamlines Should Be Isolated:

I I 1 Any MSlV - OPEN I I I I Check CNMT pressure - LESS THAN 18 PSlG I I I RO I Verifv MFW Isolation:

~~~

I I I I MFW DumDs - TRIPPED I I I I MFW Isolation valves - CLOSED I I I I S/G blowdown and samole valves - CLOSED I I 1 RO 1 Verifv At Least Two SW Pumos - RUNNING I RO Verify CI and CVI (NOTE: CI did Not actuate)

CI and CVI annunciators - LIT I I RO I Depress manual CI pushbutton. I

Appendix D Operator Action Form ES-DQ OpTest No.: - 1 Scenario# 3 Event# 687 Page 23 of -37 Event

Description:

A Large Break LOCA Occurs; CI Trains A B Fail to Actuate Time I position I Applicant% Actions or Behavior I

RO 1 I

Verify CI and CVI valve status lights - BRIGHT I I RO I Manually close affected CI and CVI valve(s).

Critical Task (E-0-0) Initiate CNMT isolation such that at least one valve is closed in each flowpath which is passing fluid out of containment.

CNMT RECIRC fan coolers SW outlet valve status lights -

RO BRIGHT RO I Dispatch A 0 to locally fail open valves.

I I RO I Letdown orifice valves - CLOSED RO I Place affected valve switch to CLOSE.

I I RO I Check CCW System Status:

Verify CCW pump -AT LEAST ONE RUNNING Place switch for excess letdown AOV-310 to CLOSE Place switch for CCW from excess letdown, AOV-745 to CLOSE RO I Verifv SI and RHR PumD Flow:

I I I SI flow indicators -CHECK FOR FLOW I I I RHR flow indicator - CHECK FOR FLOW I I RO 1 Verifv SI Pump And RHR PumD Emeraencv Alignment:

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

Appendix D Operator Action Form ES-D-2 OpTest No.: - 1 Scenario# 3 Event# 6&7 Page 24 of 37 Event

Description:

A Large Break LOCA Occurs; CI Trains A/B Fail to Actuate Time I Position I Applicants Actions or Behavior I I I Verifv SI DUmD B - RUNNING I Verify SI pump C discharge valves - OPEN I I RO I Verifv CREATS Actuation:

I I I At least one damDer in each flowDath -CLOSED I I I CREATS fans - BOTH RUNNING E-0, REACTOR TRIP OR SAFETY INJECTION.

BOP Verify AFW Valve Alignment:

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

AFW flow from each MDAFW pump - LESS THAN 230 BOP I 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 50%.

Control feed flow to maintain S/G narrow range level between 7% (25% adverse CNMT)and 50%.

BOP 1 Check if TDAFW PumD Can Be StODDed:

I I I Both MDAFW DumDs - RUNNING I I I PULL STOP TDAFW Dum0 steam SUPPIV valves I I I MOV-3504A I I I MOV-3505A BOP I Check CCW Flow to RCP Thermal Barriers:

I Annunciator A-7, RCP 1A CCW RETURN HI TEMP OR LO FLOW - EXTINGUISHED

Appendix D Operator Action Form ES-D-2 OpTest No.: - 1 Scenario # 3 Event!I 6& 7 Page 25 of 37 Event

Description:

A Large Break LOCA Occurs; CI Trains A B Fail to Actuate Time I Position I Applicant's Actions or Behavior 1 Annunciator A-15, RCP 1B CCW RETURN HI TEMP OR LOW FLOW EXTINGUISHED BOP I Monitor RCS Tavg - STABLE AT OR TRENDING TO 547°F I Bop I IF temperature less than 547°F and lowering, THEN perform the followina: I Stop dumping steam.

1 IF cooldown continues, THEN control total feed flow between 200 aDm to 230 a ~ m until narrow ranae level greater than 7./,[25% adverse CNMT] in at least one S/G. 1 WHEN S/G level greater than 7% [25% adverse CNMT] in one SIG, THEN limit feed flow to that required to maintain level in at least one S/G.

I I I IF cooldown continues. THEN close both MSIVs. I I I BOP I Check PRZR PORVs and SDrav Valves: I I PORVS - CESED Auxiliary spray valve (AOV-296) - CLOSED I Check PRZR Dressure - LESS THAN 2260 PSlG I 1 1 Normal PRZR surav valves - CLOSED I I I I PCV-431A I I I I PCV-431B I I RO/BOP I Monitor RCP TriD Criteria:

I I I RCP status -ANY RCP RUNNING I I I 1 SI pumps -AT LEAST TWO RUNNING I RCS pressure minus maximum S/G pressure - LESS THAN 210 psi [240 psi adverse CNMT]

StOD both RCPs.

Appendix D Operator Action Form ES-D-2 OpTest No.: - 1 Scenario# 3 Event# 6&7 Page 26 of 37 Event

Description:

A Large Break LOCA Occurs: CI Trains N B Fail to Actuate Time I Position I Applicants Actions or Behavior I I RO/BOP I Check if S/G Secondan/ Side is Intact: I I I I Pressure in both S/Gs - STABLE OR RISING I I I I Pressure in both S/Gs - GREATER THAN 110 PSlG I I RO/BOP I Check if S/G Tubes are Intact:

I I 1 Air eiector radiation monitors (R-15 or R-15A) - NORMAL I I I 1 S/G blowdown radiation monitor (R-19) - NORMAL I I I I Steamline radiation monitors (R-31 and R-32) - NORMAL I I ROlBOP I Check If RCS is Intact:

I I 1 CNMT area radiation monitors - NORMAL I I I R-2 I I R-7 CNMT pressure - LESS THAN 0.5 PSlG CNMT sumD B level - LESS THAN 8 INCHES I I 1 CNMT sumD A level I I I I Level-STABLE I Annunciator C-19, CONTAINMENT SUMP A HIG LEVEL - EXTINGUISHED I 0 I GOto E-I, LOSS OF REACTOR OR SECONDARY COOLANT, Step1.

E-1. LOSS OF REACTOR OR SECONDARY COOLANT.

RO Monitor RCP Trip Criteria:

RCP status - ANY RCP RUNNING

Appendix D Operator Action Form ES-D-2 OpTest No.: - Scenario# 3Event# 6&7 I RO/BOP I Check If S/G Secondary side is Intact:

I Pressure in both S/Gs - STABLE OR RISING I I I Pressure in both S/Gs - GREATER THAN 110 PSlG I RO/BOP Monitor Intact SIG Levels:

Narrow range level - GRETER THAN 7% [25% adverse CNMT]

Control feed flow to maintain narrow range level between 17% f 25% adverse CNMT) and 50%.

Booth Operator Note: Operate Trigger #6 and go to Event 8.

(This Trigger Must be Operated Prior to Reset of SI)

Appendix D Operator Action Form ES-D-2 I OpTest No.: 1 Scenario # 3Event # 0&9 Page 28 of II Event

Description:

Time 1 Position Loss of Circuit 767; Bus 17 Feeder Breaker Fails to Re-Close (Loss of Bus 17)

I Applicants Actions or Behavior I

I Booth Operator Instructions: Operate Trigger #6.

Indications Available:

I E-1, LOSS OF REACTOR OR SECONDARY COOLANT.

Recognize loss of Circuit 767 and continue on in same procedure path.

(NOTE: Bus 17 did not reenergize, and the A SW Pump is the only operating Pumd Monitor If Secondary Radiation Levels Are Normal Steamline radiation monitor (R-31 and R-32)

Request RP sample S/Gs for activity Monitor PRZR PORV Status:

Power to PORV block valve - AVAILABLE PORVS- CLOSED Block valves - AT LEAST ONE OPEN Reset SI Reset CI:

DeDress CI reset Dushbutton Verify annunciator A-26, CNMT ISOLATION -

EXTINGUISHED Verify Adequate SW Flow:

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

Appendix D Operator Action Form ES-D-2 I I OpTest No.: - 1 Scenario # 3 Event # 8&9 Page 29 of 37 Event

Description:

Loss of Circuit 767; Bus 17 Feeder Breaker Fails to Re-Close (Loss of Bus 17)

Time I Position I Applicant's Actions or Behavior Establish IA to CNMT:

Verify non-safeguards busses energized from offsite power Bus 13 normal feed - CLOSED OR I Bus 15 normal feed - CLOSED I 0 Verify turbine building SW isolation valves - OPEN I MOV-4613 and MOV-4670 MOV-4614 and MOV-4664 Verify adequate air compressors - RUNNING CHECK IA suodv:

Pressure - GREATER THAN 60 PSlG I Pressure - STABLE OR RISING I Reset both trains of XY relays for IA to CNMT AOV-5392 I Verify IA to CNMT AOV-5392 - OPEN I Check Normal Power Available To charaina Pumos:

Bus 14 normal feed breaker - CLOSED I Bus 16 normal feed breaker - CLOSED I Check If Charaina Flow Has Been Established:

Charging Pumps - ANY RUNNING I Charging pump suction aligned to RWST:

LCV-I 128 OPEN I LCV-112C - CLOSED I Start charging pumps and adjust charging flow as necessary to restore PRZR level.

Check If Emergency DIGS Should Be Stopped:

Appendix D Operator Action Form ES-D-2 OpTest No.: - 1 Scenario# - 3 Event# 8&9 Page 30 of 37 Event

Description:

Loss of Circuit 767; BUS 17 Feeder Breaker Fails t o Re-Close (Lossof Bus 17)

Time I Position I Applicant's Actions or Behavior Verify AC emergency busses energized by offsite power:

BOP Perform the following:

Close non-safeguards bus tie breakers as necessary:

Bus 13 to Bus 14 tie I -0 Bus 15 to Bus 16 tie I I I Place the followina DumDs in PULL STOP:

I I 1 EHDUmDs Turning gear oil pump HP seal oil backup pump I I I Ensure condenser steam dump mode control in MANUAL I I I Restore power to MCCs:

A from Bus 13 F from Bus 15 I I I Start HP seal oil backuo DurnD.

I I 1 Ensure D/G load within limits.

I WHEN bus 15 restored, THEN reset control room lighting breaker.

Refer to Att-8.4, ATTACHMENT SI/UV for other equipment lost with loss of offsite power.

Try to restore offsite power (Refer to ER-ELEC.l.

RESTORATION OF OFFSITE POWER).

CNMT spray pumps running - EQUAL TO NUMBER Ro REQUIRED Start or stop CNMT spray pumps as necessary to meet table Ro requirements.

Appendix D Operator Action Form ES-DP OpTest No.: - 1 Scenario# 3 Event# 8&9 Page 31 of Event

Description:

Loss of Circuit 767; Bus 17 Feeder Breaker Fails to Re-Close (Loss of Bus 17)

Time I Position I Applicant's Actions or Behavior RO I Verify CNMT pressure - STABLE OR LOWERING RO I Monitor If CNMT SDrav Should Be .%ODD&:

I I I CNMT sDrav DUmDS - ANU RUNNING Determine number of CNMT spray pumps required from table:

I I RO I Check If SI Should Be Terminated:

I RCS pressure:

Pressure - GREATER THAN 1625 psig [1825 psig adverse CNMT]

I DO NOT StOD SI DUmDS. GO to SteD 13.

-c SRO Verify CNMT Sump Recirculation Capability:

Check RHR and Support systems:

At least one recirculation flowpath, including required power supplies, from Sump B and back to RCS available per ATT-14.5, ATTACHMENT, RHR SYSTEM At least one SW DumD available.

I I I At least one ccw Dump available.

I I I At least one CCW Hx available.

I I I Check SW DUmDS -AT LEAST 2 PUMPS AVAILABLE I I SRO I Attempt to restore at least 2 SW pumps to operable.

IF only 1 SW pump available, THEN refer to A T - 2 . 1 ,

SRo AlTACHMENT MIN SW for additional guidance.

Appendix D Operator Action Form ES-D-2 I Op Test No.: - 1 Scenario# - 3 Event# 8&9 Page 32 of I Event Descriotion: LOSS of Circuit 767; BUS 17 Feeder Breaker Fails to Re-Close (Loss of Bus I Time I Position 17)

I Applicanrs Actions or Behavior I Dispatch A 0 to check AUX BLDG sub-basement for RHR system leakage (AUX BLDG sub-basement key may be required)

RO Monitor If RHR Pumps Should Be Stopped:

Check RCS Pressure - GREATER THAN 250 psig [465 psig adverse CNMT]

RO Check If Emergency D/Gs Should Be Stopped:

Verify AC emergency busses energized by offsite power:

BOP Perform the following:

Close non-safeguardsbus tie breakers as necessary:

Bus 13 to Bus 14 tie I I I Bus15toBus16tie I I I I Place the followina pumm in PULL STOP: I Turning gear oil pump HP seal oil backup pump I I 1 Ensure condenser steam dump mode control in MANUAL. I I 1 Restore power to MCCs:

Afrom Bus 13 Bfrom Bus 15 I I I Efrom Bus 15 I I I I FfromBus15 I Start HP seal oil backup pump.

Appendix D Operator Action Form ES-D-2 OpTest No.: - 1 Scenario # 3 Event # 8& 9 Page 33 of 37 Event

Description:

Loss of Circuit 767; B u s 17 Feeder Breaker Fails to Re-Close (Lossof BUS 17)

Time I Position I Applicants Actions or Behavior I Ensure D/G load within limits.

I WHEN bus 15 restored, THEN reset control room lighting breaker.

1 I Refer to ATT-8.4 ATTACHMENT SI/UV for other equipment lost with loss of offsite power.

1 Try to restore offsite power (Refer to ER-ELEC.l, RESTORATION OF OFFSITE POWER).

I 1 RO 1 Check If RCS Cooldown And DeDressurization is Reauired:

~-

I 1

~ ~~ ~ ~ ~

RCS pressure - GRETER THAN 250 psig [465 psig adverse CNMT]

SRO IF RHR pump flow greater than 475 gpm, THEN go to Step 20.

I I SRO I Establish Adeauate SW Flow: ~

I I I I Verifv at least two sw Dumm - RUNN~NG - 1 I I I Verify AUX BLDG sw isolation valves - OPEN I I I I MOV-4615 and MOV-4734 I I I I MOV-4616 and MOV-4735 I I I 1 Determine required SW flow to CCW HXs per table: I I I I Direct A 0 to adjust SW flow to required value I 1F on normal SW discharge:

V-4619, CCW HX A V-4620, CCW HX B OR IF on alternate SW discharge:

V-4619C, CCW HX A V-46206, CCW HX B

Appendix D Operator Action Form ES-D-2 OpTest No.: - 1 Scenario# 3 Event# 8&9 Page 34 of 37 Event

Description:

Loss of Circuit 767; Bus 17 Feeder Breaker Fails to Re-Close (Loss of Bus 17)

Time I Position I Applicanfs Actions or Behavior .

IF the required SW flow can NOT be obtained, THEN perform SRO the following:

Isolate SW to screehouse and air conditioning headers.

MOV-4609lMOV-4780- AT LEAST ONE CLOSED MOV-4663/MOV-4733- AT LEAST ONE CLOSED Direct A 0 to locallv adiust SW flow to reauired value.

Direct A 0 to locally close SW return from SFP Hx 8 (V8689)

Verify SW portions of AT-17.0, ATTACHMENT SD-1 are complete.

RO Establish CCW flow to RHR Hxs:

Check both CCW pumps - RUNNING Manually open CCW valves to RHR Hxs MOV-738A MOV-738B RO Check If Transfer to Cold Leg Recirculation Is Required:

RWST level - LESS THAN 28%

SRO GO to ES-I .3, TRANSFERT TO COLD LEG RECIRCULATION, Step 1 I

~~ ~

Verify RWST level - GREATER THAN 15%

Verify CNMT Sump B Level - AT LEAST 113 INCHES RO I Reset SI

OpTestNo -

1 Scenano n 3 Event U 8 89 Page 35 of 37 Event Descript on Loss of Circuit 767; Bus 17 Feeder Breaker Fails lo ReClose (Loss of Bus 17)

Time I Position I Appllcant's Actions of Behavior I

I RO 1 Check If Unnecessaw Pumps Can Be Stopped.

1- I 1 Three SI Dumps - RUNNING I Stop SI pump C and place both switches in PULL STOP Stop both RHR pumps and place in PULL STOP Both CNMT spray pumps - RUNNING Pull stop one CNMT spray pump Check CNMT pressure - LESS THAN 28 PSIG.

1 GO to Step 5.

I SRO SRO I

I Establish Adequate SW Flow: 1 I I I Verify at least two sw pumps - RUNNING 0 I Start additional SW pumps as power supply permits (257 kw each). IF only 1 SW pump operable, THEN perform the following:

I Ensure SW aligned to one CCW Hx per AT-2.1, ATTACHMENT MIN SW.

I I 1 Go to SteD 6. I I Establish CCW flow to RHR Hxs:

II I RO I

I Check both CCW oumos - RUNNING.

ODen ccw valves to RHR HXS I I I I MOV-738A I I I 1 MOV-7380 I RO Verify RHR System Alignment:

Verify the following valves - CLOSED RHR suction valves from loop A hot leg I I I MOV-700 I

Appendix D Operator Action Form ES-DQ Event

Description:

Loss of Circuit 767; Bus 17 Feeder Breaker Fails to Re-Close (Loss of Bus I I MOV-701 I 1 RHR discharge valves to loop B cold leg MOV-720 MOV-721 Verify RHR pump suction crosstie valves - OPEN MOV-704A 1 MOV-7048 I I Verifv the followina valves - OPEN RHR pump discharge to Rx vessel deluge valves MOV-852A I I MOV-8528 I 1 RHR suction from sump B (inside CNMT)

=i--

MOV-851A MOV-8516 Verify RCDT pump suction valves from sump B - CLOSED MOV-1813A MOV-18138 Initiate RHR Sump Recirculation:

Close RWST outlet valve to RHR pump suction, MOV-856 (turn on DC power key switch) 1 Open both RHR suction valves from sump B (outside CNMT)

I I MOV-850A-OPEN I 1 MOV-850B-OPEN Check MOV-738A AND MOV-7386 - BOTH OPEN Start one RHR pump - ONE RHR PUMP RUNNING

Appendix D Operator Action Form ES-DQ I I OpTest No.: __1 Scenario # 3Event # 8&9 Page 37 of 37 Event

Description:

Loss of Circuit 767; Bus 17 Feeder Breaker Fails to ReClose (LOSS of Bus 17)

Time I Position I Applicant's Actions or Behavior Critical Task (ES-1.3-A) Transfer to cold leg recirculation on at least one train of RHR pump(s) prior to cavitating SI pumps taking suction from the RWST.

~

RO J

I Check RWST Level - LESS THAN 15%

I \ RO \ Stop All Pumps Supplied From RWST: I I Stop operating CNMT spray pump and place in PULL STOP I I 1 Check CNMT pressure - LESS THAN 28 PSlG I I I I Reset CNMT spray if necessary I I I I Close CNMT spray pump discharge valves I I I 1 MOV-860A I I I I MOV-8608 I MOV-860C MOV-860D Stop all charging pumps Stop all SI Dumps and place in PULL STOP Booth Instructor: Freeze the Simulator.

EAL 3.1.3 (SAE)

RVLIS cannot be maintained >77% with no RCPs running.

Or 4.1.3 (SAE) CUCVI valves not closed when required following a confirmed LOCA.

ML072690105

Text

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Navigation menu

Search