Text

Initial Exam 2008-301 Draft Simulator Scenarios
	ML101970333
Person / Time
Site:	Robinson
Issue date:	06/28/2010
From:	; NRC/RGN-II
To:	; Progress Energy Carolinas
References
	50-261/08-301 50-261/08-301
	Download: ML101970333 (111)
	v • d • e

I Appendix D Scenario Outline Form ES-D-1 Facility:

HB ROBINSON Scenario No.: 1 Op Test No.: 2008 NRC Examiners:

Operators:

Initial Conditions:

68% EOL, 17,000 MWD/MTU, 106 ppm Boron.

SW Booster Pump "A" is Out-Of-Service for Motor Coupling Alignment.

0 LCO 3.7.7 -A has been entered and is in hour 18 of a 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months action statement.

0 Expected return is within -18 hours.

Main Turbine Vibration for #2, 3 and 4 bearings is elevated.

Turnover:

Returning to RTP following a short Maintenance Outage. Awaiting results of post-outage testing. Maintain power at current level. Critical Task:

Manually restart SW pump to provide cooling to only running EDG before damaging the EDG.

Isolate feedwater to the faulted SIGs using Foldout A OR Supplement G prior to transitioning to PATH-1, Entry Point C. Event Malf. Event Type* Event No. No. Description 1 (C) BOP, SRO PR N-42 Upper Detector Fails Low. (TS) SRO 2 (I) BOP, SRO Feed Flow Channel FT-477 Fails High. (TS) SRO 3 (C) BOP, SRO Condensate Pump "A" trips which trips Feedwater Pump "A". 4 (R) RO Plant down power resulting from loss of Condensate Pump. (N) SRO, BOP 5 (C) RO, SRO RCP "C" #2 Seal fails, requiring a Reactor Trip. 6 (M) ALL Steam Break from S/Gs "8" and "C" on the Reactor Trip. 7 (C) BOP EDG "A" fails to start on the Safety Injection.

8 (M) ALL Loss of Off-Site power. (Loss of SUT) 9 (C) BOP SW Pumps fail to start following restoration of power. * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Appendix D NUREG-1 021, Rev. 9, Supp. 1 I Appendix D Scenario Outline Form ES-D-1 HLC-08 NRC SCENARIO 1

SUMMARY

DESCRIPTION The crew will assume the watch with the plant at 68% RTP. The previous shift identified increased vibration on Main Turbine bearing #3 and has taken all necessary actions to inform station management.

Service Water Booster Pump "A" is under clearance for Motor Coupling Alignment.

Shift instructions are to maintain power at current level. On cue from the Chief Examiner, PR N-42 Upper Detector will fail low. The RO should identify that it is an instrument failure, NOT a dropped rod and respond lAW APP-005-A3.

The crew should remove the instrument from service lAW OWP-011, NUCLEAR INSTRUMENTATION, NI-2, NI-42 POWER RANGE. The SRO will enter LCO 3.3.1. Conditions D, E, Sand T for the failed instrument.

After ITS has been addressed for the PR detector, the Chief Examiner can cue the FT-477, S/G "A" Feed Flow instrument failure. The BOP should respond by taking Manual control of S/G "A" FRV and controlling S/G level within normal parameters.

An alternate instrument will be placed in service and the FRV will be returned to automatic control. The crew should respond lAW AOP-025, RTGB INSTRUMENT FAILURE and remove the instrument from service. The SRO should enter LCO 3.3.1, Condition E for the failed instrument.

On cue from the Chief Examiner, Condensate Pump "A" will trip causing Feedwater Pump "A" to trip. This will result in an entry into AOP-010, MAIN FEEDWATER

/ CONDENSATE MALFUNCTION.

The crew should reduce Turbine load to less than 50% RTP lAW Attachment 1 of AOP-010. When the Chief Examiner is satisfied with the power reduction, he can cue the RCP "c" #2 seal leak. The crew should respond using AOP-018, REACTOR COOLANT PUMP ABNORMAL CONDITIONS, calculating a high sealleakoff and determine a plant shutdown lAW GP-006, NORMAL PLANT SHUTDOWN FROM POWER OPERATION TO HOT SHUTDOWN is required.

At that time seal leakage will degrade to the point where the SRO will direct a Reactor Trip. PATH-1 will be entered and on the Reactor Trip a Steam Break will develop in S/Gs "B" and "C". After the Safety Injection has been reset and S/Gs "B" and "C" have been isolated, the Chief Examiner can cue the Loss of Off-Site power. The Start-Up Transformer will be lost and EDG "B" will load to the bus. Auxiliary Feedwater and Component Cooling Water loads will be restored.

The crew should respond lAW PATH-1 and restart safeguards equipment (SI pump, RHR pump HVH units and SW pumps) manually.

The Chief Examiner may terminate the scenario at any time after the S/Gs have been isolated and Service Water cooling to the EDG has been restored.

Appendix D NUREG-1021, Rev. 9, Supp. 1 I Appendix D Scenario Outline Form ES-D-1 HLC-08 NRC SCENARIO 1 SIMULATOR SETUP IC/SETUP

IC-601, SCN: 006_Sim_1.

SW Booster Pump "A" is OFF, breaker OPEN and switch is RED CAPPED.

Main Turbine Bearing #2 is OFFSET by 1.5, #3 by 2.3 and #4 by 1.7.

Status board updated to reflect IC-17. PRE-LOADED EVENTS: The following events should occur on the reactor trip:

Event 6: Steam Break from S/Gs "B" and "c" on the Reactor Trip.

Event 7: EDG "A" fails to start on the Safety Injection.

Event 9: SW Pumps fail to start on restoration following LOOP. EVENTSITRIGGERS INITIATED DURING THE SCENARIO:

Event 1: PR N-42 Upper Detector fails low.

Event 2: Feed Flow channel FT-477 fails high.

Event 3: Condensate Pump "A" trips causing Feedwater Pump "A" to trip.

Event 4: Plant down power resulting from Condensate Pump "A" trip.

Event 5: RCP "c" #2 Seal fails, requiring a Reactor Trip.

Event 8: Loss of Off-Site Power. (Loss of SUT) EXPECTED PROCEDURE FLOWPATH OR COPIES NEEDED: OWP-011, NI-2; AOP-025, Section E; OWP-026, FWF-2; AOP-010; AOP-018; PATH-1; Foldouts A & B; EPP-11; Supplement G. Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: --Scenario # Event # Page 4 of 26 Event

Description:

PR NI-42 Upper Detector fails low. Time II Position II Applicant's Actions or Behavior BOOTH OPERATOR:

When directed by the Chief Examiner, insert Event 1, PR N-42 Upper Detector fails low. EVENT INDICATIONS:

APP-003-86; Overpower f1T APP-003-C6; Overtemp f1T APP-OOS-A3; PR Dropped Rod APP-OOS-C3; PR Channel Dev APP-OOS-DS; OTf1T/OPf1T Turbine Runback Rod Stop APP-OOS-F3; PR Upper Ch Hi Flux Dev I Auto Defeat APP-OOS-D6; f1 Flux Warning I Status N-42 f1 Flux meter (NI-42C) pegged LOW Upper Detector (A) on N-42 Drawer indicates low On NR-4S and NR-47 Recorders, N-42 reads lower than other Power Range Nis 8istables for: OT f1 T Loop 2 TC422C1, OT f1 T Rod Stop TC422C2 OPf1T Loop 2 TC42281, OPf1T Rod Stop TC42282 RO Recognizes that N-42 has failed and there is NO dropped rod. References APPs to determine actions or recommendations.

SRO Reviews, briefs and directs taking N-42 instrument out of service using OWP-011, NI-2. Reviews ITS for applicable LCOs

Table 3.3.1-1, #2 -Condition D; Place channel in Trip within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

Table 3.3.1-1, #5 and 6 -Condition E: Place channel in Trip SRO within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

Table 3.3.1-1, #17c -Condition T; Verify interlock is in required state within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

Table 3.3.1-1, Item #17d -Condition S: Verify interlock is in required state within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: --Scenario # 1 Event # Page 5 of 26 Event

Description:

PR NI-42 Upper Detector fails low. Time II Position Applicant's Actions or Behavior Perform OWP-011, NI-2 actions to remove channel from service.

Removes N-42 from ERFIS scan. 0 (APP-005-D6 will be received)

Places DROPPED ROD MODE switch on N-42 drawer in the BYPASS position.

0 (APP-005-D4 will be received and NIS ROD DROP BYPASS N-42 status light will ILLUMINATE.) (APP-036-L 1 will be received when Hagan Rack door is opened)

Places N-42 OUT OF SERVICE TRIP SWITCH in the TRIPPED position.

BOP 0 (APP-005-A4 received)

ROD STOP BYPASS switch selected to BYPASS PR42.

COMPARATOR CHANNEL DEFEAT switch placed in the PR42 position.

0 (APP-005-C3 clears and COMPARATOR DEFEAT light illuminates above the switch)

Selects PR42 on UPPER and LOWER SECTION Switches.

0 (APP-005-F3 clears, UPPER SECTION DEVIATION light on drawer clears and CHANNEL DEFEAT light on drawer UPPER SECTION ILLUMINATES) 0 (CHANNEL DEFEAT light on drawer LOWER SECTION ILLUMINATES)

Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix 0 Operator Action Form ES-O-2 Op Test No.: Scenario # 1 Event # 2 Page 6 of 26 Event

Description:

Feed Flow channel FT-477 fails high. Time J Position II Applicant's Actions or Behavior BOOTH OPERATOR:

At the discretion of the Chief Examiner, insert Event 2, Feed Flow channel FT-477 fails high. EVENT INDICATIONS:

APP-006-A1; S/G A FW > STM FLOW (Clears on lamp Acknowledge)

APP-006-A2; S/G A STM > FW FLOW APP-006-A3; S/G A lVl DEV APP-006-D1:

S/G A NAR RANGE lO/lO-lO lEVEL FR-478 Green Pen goes high and FCV-478 closes BOP Recognizes FT-477 has failed and performs Immediate Actions for AOP-025, RTGB INSTRUMENT FAILURE. SRO Enters AOP-025, RTGB INSTRUMENT FAILURE, Section E. BOP Immediate Actiol1 Step: Place the affectedFRV(FCV:'478.forS/G "A") in MAN . ...... BOP Immediate Action$tep:

Restore Affected S/G Level To Between 39% And 52%. RO/BOP Make PA announcement for entry into AOP-025. BOP Place the affected S/G Feed Flow Selector Switch to the alternate channel. (CH-476, FR-478 recorder pen will return to normal status) Continuous Action Step: Restore Affected Controller To Automatic:

BOP

CheckS/G level within+/- 1 % of programmed level. (If YES, place in Auto and Go To Step 6) WHEN S/G level is within +/- 1 % ofprogrammed level, TH EN place the affected Controller in AUTO. Appendix 0 NUREG-1 021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 1 Event # --2 Page 7 of 26 Event

Description:

Feed Flow channel FT-477 fails high. Time I Position II Applicant's Actions or Behavior SRO Reviews, briefs and directs taking FT-477 instrument out of service using OWP-026, FWF-2. Remove the affected transmitter from service using OWP-026, FWF-2.

FR-478 selector switch selected to CH-476. BOP

Remove FT-477 input to the CALO program. (APP-036-L 1 will be received when Hagan Rack door is opened)

Trip bistable FC-478B-1. (APP-006-A2 will be received)

SRO Go To Procedure Main Body, Step 2. SRO Implement the EALs. SRO Review ITS for applicable LCO.

3.3.1-1, #14 Condition E -Trip bistable within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . SRO Return to procedure and step in effect. Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 1 Event # _3;;.... ____ Page 8 of _2_6 ____ 11 Event

Description:

Condensate Pump "A" trips which trips Feedwater Pump "A". Tim Position ! Applicant's Actions or Behavior BOOTH OPERATOR:

When directed by the Chief Examiner, insert Event 3, Condensate Pump "A" trips which results in the tripping of MFP"A". EVENT INDICATIONS:

APP-007-A1 j COND PMP A MOTOR OVLDrrRIP (Extinguishes on Lamp acknowledge)

APP-006-A3j S/G A LVL DEV, APP-006-B3j S/G 8 LVL DEV, APP-006-C3j S/G C LVL DEV (later) Condensate Pump "A" and Main Feedwater Pump "A" breaker open. Recognizes loss of Condensate/Feed Pump and performs immediate BOP actions of AOP-010, MAIN FEEDWATER/CONDENSATE MALFUNCTION.

Immediate Action Step: BOP Check FeedwaterRegulating Valves.Operating Properly in Manual OR Auto. (YES) Continuous Action Step: SRO Check Heactor Trip Setpoint Being Approached. (NO) IF a Reactor Trip Setpoint is approached, THEN trip the Reactor and Go To PATH.,.1. (Go To Step 4) RO Make PA Announcement for Procedure Entry into AOP-01 O. SRO Go to appropriate step: Condensate AND Feed Pump Trip, Step 10. RO Check Reactor Power less than 70%. (YES) RO Check Reactor Power greater than 50%. (YES) BOP Reduce Turbine load at 1 %/MIN to 5%/MIN to achieve less than 50% Reactor Power using Attachment

1. Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix 0 Operator Action Form ES-D-2 Op Test No.: Scenario # 1 Event # --4 Page 9 of 26 ----------

Event

Description:

Plant down power resulting from Condensate Pump "A" trip. Time II Position I Applicant's Actions or Behavior Attachment 1 -Turbine Load Reduction

Check Turbine Control Mode in automatic. (YES) BOP

Depress the IMP IN Pushbutton.

Set the desired load in the SETTER.

Set desired load rate.

Depress the GO Pushbutton.

NOTE: OP-301, Section 8.2.8 Quick Boration Checklist (shaded area) is included in the following steps, but may be used following the commencement of the plant down power. The crew should add -100 gallons of Boric Acid for the 18% down power. RO DETERMINE the amOl.lnt of Boric Acid to add to the RCSand OBTAIN an independent check of thevolume required.

RO OBTAIN permission from the CRSS OR the SSOto borate. RO PLACE theRCS MAKEUP MODE selector switch to BORATE. RO SET YIC':113, BOR.ICACIDTOTALIZER to desired quantity. . RO IF desired,THEN PLACE FCV-113A, BORIC ACID FLOW, in MAN AND ADJUST using the UP and DOWN pushbuttons.

RO Momentarily PLACE the.RCS*MAKEUPSYSTEM switch to START. IF any ofthe below conditions occur, THEN momentarily place the RGS MAKEUP SYSTEM sWitch in the STOP position:

RO

Rod Motion is blocked OR is in the wrong direction

T AvGincreases

Boric Acid addition exceeds the desired value Appendix 0 NUREG-1 021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: -----Scenario # 1 Event # 4 Page 10 of 26 Event

Description:

Plant down power resulting from Condensate Pump "A" trip. Time I Position II Applicant's Actions or Behavior WHEN the desired amount of Boric Acid*has been added, THEN verify the following:

FCY-113A, BORIC ACID FLOW, closes. RO

FCY-113B,BLENDEDMU TO CHGSUCT, closes.

IF in Auto, THEN the operating Boric Acid Pump stops.

The RCSMAKEUP SYSTEM isOFF. IF desired, THEN FLUSH the*Boric Acid.flow path as follows:

PLACEthe RCS MAKEUP MODE selector switch in the AL T DILUTEposition.

SET YIC-114, PRIMARY WTR TOTALIZER to 15-20 gallons.

PLACE FCY-114B, BLENDED MU TO YCT to CLOSE.

Momentarily PLACE the RCS.MAKEUP SYSTEM switch to the ST ART

IF any of the below conditions occur, THEN momentarily place RO the RCSMAKEUP SYSTEM switch in the STOP position:

o Unanticipated R6d*Motion 0 Prima.ryWateraddition re.aches the desired value

WHEN the desired amount of Primary Waterhas been added to the. RCS, THEN verify the following:

0 FCY:-114Acloses.

0 FCY-1136 closes. 0 IFin Auto, THEN the operating PW Pump stops. 0 TheRCS MAKEUP SYSTEM is OFF. ... .. .. RETURN the RCS Makeup. System to automatic as follows:

VERIFY FCV.::f14A is in AUTO.

PLACE FCY::114B to the AUTO position.

RO

PLACE the RCSMAKEUP MODE switch in AUTO.

VERIFY FCY-113A is in AUTO;

Momentarily PlACE.the RCS MAKEUP SYSTEM switch in the START position.

RECORO,in AUTO LOG; ?sindicated byPRIMARYWATER RO TOTALlZER,YIC-114ANO BoricAcid TOTALIZER, YIC-113 the total amount of Primary Water ANDBoric.Acid.added during the boration.

RO MONITOR parameters for the expected change in reactivity AND inform the CRSSORthe SSG. ofthe results of the boration.

Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix 0 Operator Action Form ES-D-2 Op Test No.: --Scenario # 1 Event # _4..:....-

____ Page 11 of .....:2:;.;;6

___ -11 Event

Description:

Plant down power resulting from Condensate Pump "A" trip. Time 1 Position II Applicant's Actions or Behavior BOP Check at least 1 Main Feed Pump running. (YES, Go To Step 37) BOP Check SIG Level at or trending to program. (YES) RO Check T AVG at or trending to T REF. (YES) SRO Contact Maintenance to troubleshoot and correct Feedwater problem. SRO Implement the EALs. Check current loading for the following pumps less than maximum. BOP

Main Feedwater Pump -0.715 KAMPS

Condensate Pump -370 AMPS

Heater Drain Pumps -90 AMPS 800TH OPERATOR:

When contacted, wait 3 minutes and report that Main Feedwater Pump "8" is 530 AMPS, Condensate Pump "8" is 320 AMPS and Heater Drain Pumps are 80 AMPS each. RO Determine Iodine Sampling Requirements:

Check Power change> 15% in one hour. (NO, Go To Step 43) Continuous Action* Step: Check ROD BANKS AlB/C/DLO LIMIT extinguished.

RO (YES) IF alarm is illuminated, THEN Borate to clear the alarm using OP-301 while continuing in this procedure.

RO Monitor Axial Flux Difference to ensure compliance with LCO 3.2.3 Appendix 0 NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: ....;..--Scenario # Event #

Page 12 of 26 ....;;..;......-----ll Event

Description:

Plant down power resulting from Condensate Pump "A" trip. Time J Position II Applicant's Actions or Behavior SRO Notify Load Dispatcher of the unit's load capability.

SRO Return to procedure and step in effect. At the discretion of the Chief Examiner, insert Event 5. Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Op Test No.: --Event

Description:

Operator Action Form ES-D-2 Scenario # 1 Event # 5, 6 & 7 Page 13 of 26 Rep "e" #2 Seal fails, requiring a Reactor Trip. Steam Break from S/Gs "B" and "e" on the Reactor Trip. EDG "A" fails to start on Safety Injection.

Time II Position I Applicant's Actions or Behavior BOOTH OPERATOR:

When directed by the Chief Examiner, insert Event 5, RCP "C" #2 Seal failure requiring Reactor Trip. EVENT INDICATIONS:

APP-001-C5; RCP STANDPIPE HI/LO LVL (RCP C STP HI) FR 154A, Pen 3 (Blue), C RCP Seal Leakoff decreasing RO Recognizes decreasing sealleakoff and references APP-001-C5.

RO IF Standpipe level is High, THEN check for rising level in the Reactor Coolant Drain Tank. BOOTH OPERATOR:

When requested by the crew wait 3 minutes and inform the crew that RCDT level is slowly rising. (1% in the last 3 min.) SRO Enters AOP-018, RCP ABNORMAL CONDITIONS, Section A. Continuous Action Step: RO Check any RCP#1 Sealleakoff flow> 5.7 GPM. (NO, Go To Step 8) IF sealleakoff*

exceeds 5.7 GPM, THEN Go To Step 2. Continuous Action Step: RO Check indicated

1 Seal Leakoff <0.8 GPM. (NO, Go To Step 14) IF Seal Leakoff decreases to < 0.8 GPM, THEN Go To Step 9. RO Check RCP #2 Seal problem suspected. (YES) Check RCP #2 Seal Leakoff rate known. (NO) SRO Dispatch an operator to perform Att. 2, RCP Seal Leak Rate Calculation.

WHEN calculation is complete, THEN Go To Step 16. Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Op Test No.: .-;...-Event

Description:

Operator Action Form ES-D-2 Scenario # 1 Event # 5, 6 & 7 Page 14 of 26 RCP "C" #2 Seal fails, requiring a Reactor Trip. Steam Break from S/Gs "B" and "C" on the Reactor Trip. EDG "A" fails to start on Safety Injection.

Time II Position Applicant's Actions or Behavior BOOTH OPERATOR:

When requested to perform Leak Rate Calculation, wait 5 minutes and inform the crew that RCP #2 Seal leakoff is 1.3 GPM. Continuous Action Step: RO Check calculated RCP #2 Seal.leakoff

< 1.1 GPM. (NO) Place the plant in Mode. 3 within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months using GP-006, WHEN the plant is in Mode 3, THEN stop the affected RCP. BOOTH OPERATOR:

The crew will make the decision to shut down the plant lAW GP-006. As soon as Step 16 (above) is performed, insert the higher RCS leak rate. The crew will identify the increased leakage and return to Continuous Action Step 1. EVENT INDICATIONS:

APP-001-B2; RCP LABYRTH SEAL LO DP APP-001-D2; RCP #1 SEAL LEAKOFF HI FLOW APP-001-E2; RCP #1 SEAL LEAKOFF LO FLOW PZR level decreasing, Charging Pump Speed increasing FR 154A, A and B Pens decreasing, C Pen pegged HIGH. RO Continuous Action Step: Check any RCP #1 Sealleakoffflow>5.7 GPM. (YES) Check RCP #1 seal leakoff flow RO OR RCP Thermal Barrier b.P on affected RCP(s) decreased. (YES) RO Check Plant in MODE 1. (YES) Perform the following:

RO

Trip the reactor.

Trip RCP "C".

Go To Path-1 while continuing with this procedure.

Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Op Test No.: --:....-Event

Description:

Operator Action Form ES-D-2 Scenario # 1 Event #

Page 15 of ,...;2::,;6;....-

__ --11 Rep "e" #2 Seal fails, requiring a Reactor Trip. Steam Break from S/Gs "B" and "e" on the Reactor Trip. EDG "A" fails to start on Safety Injection.

Time II Position i Applicant's Actions or Behavior NOTE: Following the performance and verification of PATH-1 Immediate Actions, the crew will continue with AOP-018. These steps may be handed off to the RO/BOP to perform independently.

The remaining steps of AOP-018 are listed here. PATH-1 actions begin on page 16. PHASE B isolation has occurred, so AL RCPs will be secured. RO WHEN at least 3 minutes have elapsed since tripping the affected RCP, THEN Close Sealleakoff valve for RCP "C". (CVC-303C)

RO Check RCP "B" or "c" running. (NO) RO Check RCP seal injection flow between 8 and 13 GPM. (YES) RO Check FCV-626, THERM BAR FLOW CO NT Valve CLOSED. (YES) Continuous Action Step: RO Check Thermal Barrier intact. (YES) WHEN.this procedure is completed,THENGoTo AOP-014, CCW SYSTEM MALFUNCTION. . RO Check APP-002-D2, CV ISOL PHASE B extinguished. (NO) SRO Implement EALs. SRO Review ITS for applicable LCOs: LCO 3.4.13, Condition A -Reduce leakage to within limits within 4 hrs. Appendix D NUREG-1021 , Rev. 9, Supp. 1 Appendix D Op Test No.: --Event

Description:

Operator Action Form ES-D-2 Scenario # 1 Event # 5, 6 & 7 Page 16 of 26 Rep "e" #2 Seal fails, requiring a Reactor Trip. Steam Break from S/Gs "B" and "e" on the Reactor Trip. EDG "A" fails to start on Safety Injection.

Time J Position II Applicant's Actions or Behavior 800TH OPERATOR:

Steam break for SIGs "8" and "C" are triggered to occur when the reactor trip breakers open. Verify steam break malfunction is inserted.

SRO Directs tripping the Reactor, tripping Rep "e" and enters PATH-1. RO Immediate Action Step: Reactor Tripped .. (YES) BOP Immediate Action Step: Turbine Tripped. (YES) BOP Immediate Action* Step: E-1 AND E-2 energized. (YES) RO Immediate Action Step: SI Initiated. (YES) NOTE: Phase 8 isolation has occurred; the crew will stop ALL RCPs due to a loss of RCP COOling. When Foldout A is addressed the crew may isolate SIGs "8" and "C" using Foldout A. SI will have to be reset prior to manipulating valves. SRO Open Foldout A.

Rep Trip criteria.

IF BOTH conditions are met, THEN stop all RCPs: (NO) 0 SI Pumps -AT LEAST ONE RUNNING AND CAPABLE OF DELIVERING FLOW TO THE CORE 0 RCS Subcooling

-< 35 degrees F [55 degrees F] Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Op Test No.: ...;....-Event

Description:

Operator Action Form ES-D-2 Scenario # 1 Event # 5, 6 & 7 Page 17 of 26 Rep "e" #2 Seal fails, requiring a Reactor Trip. Steam Break from S/Gs "B" and "e" on the Reactor Trip. EDG "A" fails to start on Safety Injection.

Time I Position II Applicant's Actions or Behavior

SI actuation criteria.

IF EITHER condition occurs, THEN Actuate SI and Go To PATH-1, Entry Point A: 0 RCS Subcooling

-< 35 degrees F [55 degrees F] 0 PZR Level-CAN NOT BE MAINTAINED>

10% [32%1

MSR Isolation criteria.

IF ANY Purge OR Shutoff Valve does NOT indicate fully closed, THEN place the associated RTGB Switch to CLOSE.

S/G isolation criteria.

IF both the following conditions are met, THEN perform the following:

Any S/G pressure is decreasing in an uncontrolled manner OR

Any S/G has completely depressurized.

AND

At least ONE S/G is intact. 0 Reset SI. 0 CLOSE the appropriate AFW isolation valves to the faulted S/Gs AND OPEN the associated breaker for the valves closed.

S/G "B"

V2-14B, SDAFW PUMP DISCH, MCC-9, CMPT -1C

V2-16B, AFW HDR DISCH, MCC-10, CMPT -4F

S/G "c"

V2-14C, SDAFW PUMP DISCH, MCC-10, CMPT -4M

V2-16C, AFW HDR DISCH, MCC-9, CMPT -3J 0 WHEN the faulted S/Gs dry out, THEN dump steam from intact S/G to control RCS mgressurization.

RO Verify Phase A Isolation valves are closed. (YES) BOP Verify FW Isolation valves are closed. (YES) BOP Verify both FW pumps are tripped. (YES) Appendix D NUREG-1 021, Rev. g, Supp. 1 Appendix 0 Op Test No.: -.;...-Event

Description:

Operator Action Form ES-D-2 Scenario # 1 Event # 5, 6 & 7 Page 18 of 26 ---------

Rep "e" #2 Seal fails, requiring a Reactor Trip. Steam Break from S/Gs "B" and "e" on the Reactor Trip. EDG "A" fails to start on Safety Injection.

Time i Position i Applicant's Actions or Behavior BOP Verify both MDAFW pumps are running. (YES) NOTE: Crew may elect to reset SI in order to control AFW and S/G levels. BOP If additional Feedwater is required, start the SDAFW pump. RO Verify 2 SI pumps running. (YES) RO Verify Both RHR pumps running. (YES) RO Verify SI valves are properly aligned. (YES) RO At least 1 CCW pump is running. (YES) BOP All SW and SW Booster pumps running. (NO) BOP Attempt to start all SW and SW Booster pumps. (NO, SW Booster Pump "A" is unavailable)

BOP North OR South SW Header Lo Pressure alarm illuminated. (NO) RO Verify CV Fans HVH-1, 2, 3, 4 running. (YES) RO Verify IVSW initiated. (YES) BOP Verify CV Ventilation isolation. (YES) BOP Verify Control Room Vent aligned for Pressurization Mode. (YES) Appendix 0 NUREG-1 021, Rev. 9, Supp. 1 Appendix 0 Op Test No.: ......;...-

Event

Description:

Operator Action Form ES-D-2 Scenario # 1 Event # 5, 6 & 7 Page 19 of 26 Rep "e" #2 Seal fails, requiring a Reactor Trip. Steam Break from S/Gs "B" and "e" on the Reactor Trip. EDG "A" fails to start on Safety Injection.

Time I Position II Applicant's Actions or Behavior BOP Verify both EDGs running. (NO) NOTE: If requested to investigate what is wrong with the EDG, report that the EDG has tripped on OVERSPEED and you were unable to reset the fuel racks. Continuous Action Step: BOP Restart battery chargers within 30 minutes of power loss using OP-601. RO Continuous Action Step: CV Pressure has remained below 10 psig. (NO) RO Verify CV Spray initiated. (YES) RO Verify ALL CV Spray pumps running with valves aligned. (YES) RO Verify approximately 12 GPM Spray additive tank flow. (Flow will be adjusted from -30 GPM to 12 GPM) RO Verify Phase B isolation valves closed. (YES) RO Stop ALL RCPs. (May be stopped previously)

BOP Verify ALL MSIVs and MSIV bypasses closed. (YES, operator will take MSIV switches to CLOSE) BOP Locally open breaker for HVS-1 at MCC-5. Appendix 0 NUREG-1 021, Rev. 9, Supp. 1 Appendix D Op Test No.: ......;.--

Event

Description:

Operator Action Form ES-D-2 Scenario # 1 Event # _5;;.:"..;;,6,.;;;&;..;,7

___ Page 20 of _2_6 ___ ...,1 RCP "C" #2 Seal fails, requiring a Reactor Trip. Steam Break from S/Gs "B" and "C" on the Reactor Trip. EDG "A" fails to start on Safety Injection.

Time i Position II Applicant's Actions or Behavior RCS pressure>

1350 psig. [1250 psig] RO * (YES, RCS pressure is> 1250, skip the following 2 steps) * (NO, RCS pressure is < 1250, Go To the next step) RO SI Flow Verified. (YES) RO RCS Pressure Greater than 125 psig. (YES) BOP At least 300 GPM AFW flow available. (YES) BOP Verify AFW valves properly aligned. BOP Control AFW flow to maintain SIG levels between 8% [18%] and 50%. RO RCP Thermal barrier cooling water HilLo flow alarm illuminated. (YES) RO At least one Charging Pump running. (YES) BOP Place Steam Dump Mode Switch to Steam Pressure.

RO RCS Temp stable at OR trending to 547 degrees F. (NO) RO RCS temperature>

547 degrees F. (NO) BOP Attempt to limit cooldown.

BOP IF RCS cooldown continues and is NOT due to SI flow, THEN close MSIVs and MSIV bypasses.

Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Op Test No.: Event

Description:

Operator Action Form ES-D-2 Scenario # 1 Event # 5, 6 & 7 Page 21 of 26 Rep "e" #2 Seal fails, requiring a Reactor Trip. Steam Break from S/Gs "B" and "e" on the Reactor Trip. EDG "A" fails to start on Safety Injection.

Time II Position ! Applicant's Actions or Behavior RO PZR PORVs closed. (YES) RO PZR Spray and Aux Spray valves closed. (YES) RO At least 1 RCP running. (NO) BOP Any S/G with uncontrolled depressurization. (YES) RO Reset SPDS and initiate monitoring of CSFSTs. SRO Go To EPP-11, FAULTED STEAM GENERATOR ISOLATION.

BOP Maintain At Least One S/G Available For RCS Cooldown.

BOP Any S/G pressure stable or increasing. (YES) BOP Any S/G pressure decreasing in an uncontrolled manner OR any S/G completely depressurized. (YES) BOP Isolate faulted S/Gs using Supplement G, S/G ISOLATION. (Supplement G Steps are listed on page 22 & 24) BOP Maintain A Faulted S/G In The Isolated Condition During Subsequent Recovery Actions Unless Needed For Cooldown.

BOP Check CST level greater than 10%. (YES) BOP Check Available Secondary Radiation Monitors normal. (YES) Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Op Test No.: ...;...-Event

Description:

Operator Action Form ES-D-2 Scenario # 1 Event # 5, 6 & 7 Page 22 of 26 Rep "e" #2 Seal fails, requiring a Reactor Trip. Steam Break from S/Gs "B" and "e" on the Reactor Trip. EDG "A" fails to start on Safety Injection.

Time II Position I Applicant's Actions or Behavior CRITICAL TASK: Isolate feedwater to the faulted S/Gs using Foldout A OR Supplement G prior to transitioning to PATH-1, Entry point C. RO Check any S/G with an uncontrolled level increase. (NO, Go To Path-1, Entry Point C) (PATH-1 Steps continue on Page 25) Pages 22-24 are steps from Supplement G, STEAM GENERATOR ISOLATION to isolate S/Gs "8" "e" as faulted Steam Generators.

Go to the appropriate step from following table: BOP

S/G B to be isolated, Go To Step 18.

S/G C to be isolated, Go To Step 34 . BOP Check S/G "B" faulted. (YES) Check S/G "C" faulted. (YES) BOP Verify V1-3B, MSIV CLOSED. (YES) Verify V1-3C, MSIV CLOSED. (YES) BOP Verify MS-353B, MSIV V1-3B BYP CLOSED. (YES) Verify MS-353C, MSIV V1-3C BYP CLOSED. (YES) BOP Verify FRV B CLOSED. (YES) Verify FRV C CLOSED. (YES) BOP Verify FRV B BYP CLOSED. (YES) Verify FRV C BYP CLOSED. (YES) Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Op Test No.: Event

Description:

Operator Action Form ES-D-2 Scenario # 1 Event # _5;;.1"...;;.6..;;;&;..;.7

___ Page 23 of .....;2;.,;6

___ -i1 Rep "e" #2 Seal fails, requiring a Reactor Trip. Steam Break from S/Gs "B" and "e" on the Reactor Trip. EDG "A" fails to start on Safety Injection.

Time II Position I Applicant's Actions or Behavior SOP Verify V2-6S, FW HDR SECTION Valve CLOSED. (YES) Verify V2-6C, FW HDR SECTION Valve CLOSED. (YES) SOP Verify V2-14S, SDAFW PUMP DISCH Valve CLOSED. (YES) Verify V2-14C, SDAFW PUMP DISCH Valve CLOSED. (YES) SOP Verify V2-16S, AFW HDR DISCH Valve CLOSED. (YES) Verify V2-16C, AFW HDR DISCH Valve CLOSED. (YES) SOP Verify STEAM LINE PORVs CLOSED. (YES) SOP Verify V1-8S, SDAFW STEAM SHUTOFF Valve CLOSED. (YES) Verify V1-8C, SDAFW STEAM SHUTOFF Valve CLOSED. (YES) SOP Verify S/Gs "S" and "C" Slowdown and Slowdown Sample Valve Status Light Indication CLOSED. (YES) Dispatch an operator to the Pipe Jungle to close MS-29 and MS-38, SOP S/G "S" and S/G "C" SYPASS DRN and WARM-UP LINE TO AFW PUMP. SOP Check S/Gs "S" and "C" MSIV Above and Selow Seat Drain Valves CLOSED. (YES) Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Op Test No.: --Event

Description:

Operator Action Form ES-D-2 Scenario # 1 Event # 5, 6 & 7 Page 24 of 26 Rep "e" #2 Seal fails, requiring a Reactor Trip. Steam Break from S/Gs "B" and "e" on the Reactor Trip. EDG "A" fails to start on Safety Injection.

Time i Position II Applicant's Actions or Behavior Dispatch an operator to E-1/E-2 Room to perform the following:

At MCC-9, verify V2-14B and V2-16C closed and open breakers 0 V2-14B, SDAFW PUMP TO S/G B. BOP V2-16C, MDAFW PUMP HDR DISCH TO S/G C. 0

At MCC-6, verify V1-8B and V1-8C closed and open breakers 0 V1-8B, SDAFW PUMP STEAM ISOLATION.

0 V1-8C, SDAFW PUMP STEAM ISOLATION.

Dispatch operator to the Aux. Bldg. to perform the following:

At MCC-1 0, verify V2-16B closed and open breaker V2-16B, BOP MDAFW PUMP HEADER DISCHARGE TO S/G B.

At MCC-10, verify V2-14C closed and open breaker V2-14C, SDAFW PUMP TO S/G C. BOP Check All Faulted and Ruptured S/Gs isolated. (YES) BOP WHEN the faulted S/Gs dry out, THEN dump steam from intact S/G to control RCS repressurization.

BOP Check Any S/G ruptured. (NO) SRO Return to procedure and step in effect. Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix 0 Operator Action Form ES-D-2 Op Test No.: --.;.....-

Scenario # Event # 8 & 9 Page 25 of 26 Event

Description:

Loss of Off-Site Power. SW Pumps fail to start following restoration of power. Time II Position I Applicant's Actions or Behavior 800TH OPERATOR:

After S/Gs "8" and "C" are isolated and at the discretion of the Chief Examiner, insert Events 8 and 9, Loss of Off-Site Power with a failure of SW Pumps to restart. The crew will continue in PATH-1, but will address components that did NOT restart: 0 Service Water Pump "C" or "0" to provide EOG cooling. 0 RHR Pump "8", HVH Units 3 & 4, SI Pump "C". 0 Charging Pump "C" started OR FCV-626 opened to provide RCP Seal cooling. CRITICAL TASK: Manually restart a Service Water Pump to provide cooling to the only running EDG before damaging the EDG. RO Reset SPDS and initiate monitoring of Critical Safety Function Status Trees. SRO Open Foldout B. SRO Request periodic samples of ALL S/Gs. RO At least one RCP running. (NO) BOP Any S/G with uncontrolled depressurization. (YES) BOP Faulted S/G isolated using EPP-11. (YES) Once S/Gs "8" and "C" have been isolated and a SW pump has been started, the scenario may be terminated.

Appendix 0 NUREG-1021, Rev. 9, Supp. 1 HLC-08 NRC SCENARIO 1 TURNOVER SHEET POWER LEVEL: 68%, 17,000 MWO/MTU.

Returning to RTP following a short Maintenance Outage.

Awaiting results of post-outage testing. BORON CONCENTRATION:

106 ppm EQUIPMENT UNDER CLEARANCE:

SW Booster Pump "A" is Out-Of-Service for Motor Coupling Alignment.

o LCO 3.7.7 -A has been entered and is in hour 18 of a 72 TSAS. o Expected return is within -18 hours. EQUIPMENT STATUS:

Main Turbine Vibration for #2, 3 and 4 bearings is elevated.

INSTRUCTIONS FOR THE WATCH:

Maintain power at 68% RTP. Appendix D NUREG-1021, Rev. 9, Supp. 1 I Appendix D Scenario Outline Form ES-D-1 Facility:

HB ROBINSON Scenario No.: 2 Op Test No.: 2008 NRC Examiners:

Operators:

Initial Conditions:

100% MOL, 9000 MWD/MTU, 766 ppm Boron.

SW Booster Pump "A" is Out-Of-Service for Motor Coupling Alignment.

0 LCO 3.7.7 -A has been entered and is in hour 18 of a 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months action statement.

0 Expected return is within -18 hours.

Main Turbine Vibration for #2, 3 and 4 bearings is elevated.

Turnover:

Maintain power at normal levels. Critical Task:

Initiate isolation of the applicable S/G using Supplement G before exiting EPP-11.

Verify CVC-381 closed before transitioning to FRP-H.1. Event Malf. No. Event Type* Event No. Description 1 (C) RO, SRO Charging Pump "B" trip. 2 (I) RO, SRO IRPI K8 Fails Low simulating a dropped rod. (TS) SRO 3 (I) BOP, SRO Controlling Steam Flow channel FT -494 for S/G "C" fails LOW. (TS) SRO 4 (C) BOP, SRO FWH 4A Tube Leak. 5 (R) RO Downpower to support removing FWH 4A from service. (N) SRO, BOP 6 (C) RO Rods continue to step requiring Reactor Trip. (M) ALL 7 (C) BOP Failure of the Turbine to trip. 8 (M) ALL FW break on S/G "B" inside CV. Loss of all Feedwater.

9 (C) RO Containment Spray Pump "A" fails to Auto Start. 10 (C) RO Phase B Isolation Valves FCV-626 and CVC-381 fail to close. * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Appendix D NUREG-1021, Rev. 9, Supp. 1 I Appendix D Scenario Outline Form ES-D-1 HLC-08 NRC SCENARIO 2

SUMMARY

DESCRIPTION The crew will assume the watch with the plant at 100% RTP. The previous shift identified increased vibration on Main Turbine bearing #3 and has taken all necessary actions to inform station management.

Service Water Booster Pump "A" is under clearance for Motor Coupling Alignment.

Shift instructions are to maintain the plant at 100% RTP. On cue from the Chief Examiner, Charging Pump "B" will trip. The RO should respond lAW APP-003-F4, starting the standby Charging pump to maintain PZR level on program. On cue from the Chief Examiner, IRPI K8 will fail low simulating a dropped rod. The crew should respond lAW AOP-001 , MALFUNCTION OF REACTOR CONTROL SYSTEM, and verify that no dropped rod exists due to stable Reactor parameters.

The SRO should enter LCO 3.1.7, Condition A for the failed IRPI. On cue from the Chief Examiner, the controlling steam flow channel (FT-494) for S/G "c" will fail low. The BOP will take Manual control of Feedwater Regulating valve FCV-498, lAW AOP-025, RTGB INSTRUMENT FAILURE, to match Feed Flow and Steam Flow in order to control S/G "c" water level. An alternate controlling channel will be selected, FCV-498 will be returned to automatic control and FT-494 will be removed from service lAW OWP-034, STEAM FLOW, SF-5, STEAM FLOW TRANSMITTER FT-494. The SRO should enter LCO 3.3.1 Condition E and 3.3.2 Condition D, for the failed instrument.

As soon as Tech Specs are addressed, the Chief Examiner can cue a tube leak in Feed Water Heater 4A. The crew should respond lAW APP-007-E7, identifying the leak and entering AOP-010, MAIN FEEDWATER/CONDENSATE MALFUNCTION and using requirements from OP-407, HEATER DRAINS AND VENTS, ramp the plant down in power to 517 MWe in order to remove the FWH from service. As soon as the Chief Examiner is satisfied with the power maneuver, he can cue the Rod Control System failure. Control Rods will continually step in the direction moved and the crew will be unable to stop rod motion. The SRO should respond by directing a Reactor trip and enter PATH-1. On the Reactor trip, the turbine will not trip and cannot be tripped from the RTGB, requiring the BOP to Manually runback the turbine. Shortly after the Reactor Trip, a Feedwater Break will develop inside CV, resulting in a Safety Injection.

On the SI, all Auxiliary Feedwater Pumps will fail to start or will trip, resulting in a complete loss of feed. On the SI and CV Spray, Containment Spray Pump "A" will fail to Auto start, Phase B isolation valves CVC-381 and FCV-626 will fail to close. The crew should respond and take actions lAW PATH-1, transitioning to FRP-H.1 , LOSS OF SECONDARY HEAT SINK. The Chief Examiner may terminate the scenario at any time after S/G "B" Feedwater break is isolated and feedwater is restored to at least 1 S/G. Appendix D NUREG-1 021, Rev. 9, Supp. 1 I Appendix 0 Scenario Outline Form ES-D-1 HLC-08 NRC SCENARIO 2 SIMULATOR SETUP IC/SETUP:

SW 800ster Pump "A" is OFF, breaker OPEN and switch is RED CAPPED.

Main Turbine 8earing #2 is OFFSET by 1.5, #3 by 2.3 and #4 by 1.7.

Status board is correctly marked up for IC-13. PRE-LOADED EVENTS: The following events should occur on the reactor trip:

Event 8: FW break on S/G "8" inside CV. Loss of all Feedwater.

Event 9: Containment Spray Pump "A" fails to Auto Start.

Event 10: Phase 8 Isolation Valves FCV-626 and CVC-381 fail to close. EVENTSITRIGGERS INITIATED DURING THE SCENARIO:

Event 1: Charging Pump "8" trip.

Event 2: IRPI K8 Fails Low simulating a dropped rod.

Event 3: Controlling Steam Flow Channel FT-494 for S/G "C" Fails LOW.

Event 4: FWH 4A Tube Leak

Event 5: Downpower to support removing FWH 4A from service.

Event 6: Rods continue to step requiring Reactor Trip.

Event 7: Failure of the Turbine to trip. EXPECTED PROCEDURE FLOWPATH OR COPIES NEEDED:

AOP-001, Section 0; AOP-025, Section F; OWP-034, SF-5; AOP-01 0; OP-407; OP-105, Section 8.4; AOP-001; PATH-1; Supplement G; Foldout A and 8; FRP-H.1; EPP-11. Appendix 0 NUREG-1 021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: ......;....-

Scenario # 2 Event # Page 4 of 28 Event

Description:

Charging Pump "B" trip Time Position I Applicant's Actions or Behavior 800TH OPERATOR:

When directed by the Chief Examiner, insert Event 1, Charging Pump "8" trip. EVENT INDICATIONS:

APP-003-F5; CHG PMP MOTOR OVLDfTRIP APP-001-86; LP LTDN LN HI TEMP (will clear as the running Charging Pump speeds up) APP-003-F4; CHG PMP HI SPEED (after short delay) RO Receives APP-003-FS, notes dual indication for Charging Pump "S", references APP-003-FS actions. RO

Verifies at least 1 Charging Pump is running and supplying adequate RCP seal injection flow. RO

Dispatch an operator to check Charging Pump "S" breaker at 480V Sus E-1. RO

Dispatch operator to check the Charging Pumps. RO

IF adequate RCP seal injection flow cannot be maintained, THEN refer to AOP-018. RO Receives APP-003-F4 and reviews actions. RO

IF RCS leakage is indicated, THEN refer to AOP-016. RO

IF required to maintain level, THEN start standby Charging Pump. (Will clear APP-003-F4)

Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: ......;....-

Scenario # 2 Event #

____ Page 5 of ....;2:;,;;8

___ ...,1 Event

Description:

IRPI K8 Fails Low simulating a dropped rod. Time II Position II Applicant's Actions or Behavior BOOTH OPERATOR:

At the discretion of the Chief Examiner, insert Event 2, IRPI K8 fails low simulating a dropped rod. EVENT INDICATIONS:

APP-005-F2; ROD BOTTOM ROD DROP Shutdown Bank B, Group 2, K8 indicates 0 inches with RBL ON RO Recognizes K8 RBL and performs Immediate Actions of AOP-001. SRO Enters AOP-001, MALFUNCTION OF REACTOR CONTROL SYSTEM. RO Immediate Action Step: Check Unexpected Rod Motion in Progress. (NO, Go To Step 7) RO/BOP Make PA Announcement for entry into AOP-001. Determine if multiple rods have dropped:

Prompt Drop present. (NO) RO

More than 1 RBL illuminated. (NO)

More than 1 IRPI indicates on bottom. (NO) RO Check multiple dropped rods present. (NO, Go To Step 11) RO Check T AVG trending to T REF. (YES) Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix 0 Operator Action Form ES-D-2 Op Test No.: ......;...-

Scenario # 2 Event # ....;2=--____ Page 6 of ...;2::.;;8

___ ..,1 Event

Description:

IRPI K8 Fails Low simulating a dropped rod. Time II Position I Applicant's Actions or Behavior Determine the status of rods.

APP-005-A3 Illuminated (NO)

APP-005-F2 Illuminated (YES) SRO/RO

RBL for affected rod illuminated (YES)

Indication of Prompt Drop (NO)

Quadrant Power Tilt indications present (NO)

APP-005-F3 and F4 extinguished, ERFIS shows no tilt. SRO/RO Check dropped rod present (NO, Go To Step 14) Determine The Status Of IRPI:

IRPI Indication

-Indicator drift with no flux effects. (NO)

IRPllndication

-Erratic movement with no flux effects. (YES)

IRPllndication

-Off-scale high/low with no flux effects. (YES) RO

Dropped Rod Indication with no flux changes

Rod Bottom Light for K8 illuminated. (YES) AND

APP-005-A3, PR DROP ROD extinguished. (YES)

Simultaneous loss of ALL IRPI Indication present. (NO) SRO Checks IRPI malfunction present. (YES, Go To Section D) RO Check IRPI energized. (YES) SRO Check current plant status MODE 1 or MODE 2. (YES) Review ITS for applicable LCOs: SRO

3.1.7, Condition A; Verify Rod position by movable in-core detectors OR Decrease power to .$ 50% within 8 hrs. Appendix 0 NUREG-1 021, Rev. 9, Supp. 1 Appendix 0 Operator Action Form ES-O-2 Op Test No.: ...;....-Scenario # 2 Event # ____ Page 7 of ....;2::.::8::..-

__ ---l 1 Event

Description:

IRPI K8 Fails Low simulating a dropped rod. Time i Position II Applicant's Actions or Behavior BOOTH OPERATOR:

If the crew chooses to perform a power reduction lAW LeO 3.1.7, inform the CRSS to wait for Rx Engineering to perform a flux map. SRO Check Adjustment to IRPI will be performed. (NO, Notify I&C, Go To Step 8) SRO Implement the EALs and return to procedure and step in effect. Appendix 0 NUREG-1021, Rev. 9, Supp. 1 Appendix 0 Operator Action Form ES-O-2 Op Test No.: ......;...-

Scenario # 2 Event # 3 Page 8 of 28 Event

Description:

Steam Flow Channel FT-494 Fails Low. Time Position I Applicant's Actions or Behavior BOOTH OPERATOR:

At the discretion of the Chief Examiner, insert Event 3, Steam Flow channel FT-494 fails low. EVENT INDICATIONS:

APP-006-C1; S/G C FW > STM FLOW APP-006-C2:

S/G C STM > FW FLOW APP-006-C3; S/G C L VL DEV FR-498, Pen #1 (Red) decreasing and FCV-498 CLOSING. BOP Recognizes FT -494 has failed and performs Immediate Actions of AOP-025. SRO Enters AOP-025, and determines Section F is the applicable section. BOP Immediate Action Step: Place the affected FRV (FeV-498 for S/G "C") in MAN. BOP Immediate Action Step: Restore Affected S/G Level To Between 39% And 52%. NOTE: The crew may receive a Power Limit Warning and reduce the Turbine Limiter to maintain power < 100%. RO/BOP Make PA announcement for entry into AOP-025. Place The Affected S/G Steam Flow Selector Switch To The Alternate BOP Channel. (CH-495) (Recorder pen will return to normal status on FR-498) Appendix 0 NUREG-1 021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 2 Event # 3 Page 9 of 28 Event

Description:

Steam Flow Channel FT-494 Fails Low. Time 1 Position I Applicant's Actions or Behavior CONTINUOUS ACTION STEP: Restore Affected Controller To Automatic:

BOP

Check S/G level within +/- 1 % of PROGRAMMED LEVEL (If YES -Place in Auto and Go To Step 6) WHEN S/G level is within +/- 1 % of PROGRAMMED LEVEL, THEN place the affected Controller in AUTO. SRO Reviews, briefs and directs taking FT-494 instrument out of service using OWP-034, SF-5. Perform OWP-034, SF-5 actions to remove channel from service.

Remove FT-494 input to the CALO program by removing ERFIS Point. SRO/BOP

FR-498 Steam Flow Selector Switch selected to CH 495. (APP-036-L 1 will be received for entering Hagan Racks)

Trip bistable FC-494 (APP-006-F4 received)

Trip bistable FC-498B-1 (APP-006-C2 received)

SRO Go To Procedure Main Body, Step 2. SRO Implement the EALs. Review applicable ITS. SRO

Table 3.3.1-1, #14, Condition E -Trip bistables within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

Table 3.3.2-1, #1f, 1 g, 4d, 4e, Condition D -Place Channel in trip within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . SRO Return to procedure and step in effect. Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: ....;...-Scenario # 2 Event # 4 Page 10 of 28 Event

Description:

FWH 4A Tube Leak. Time II Position II Applicant's Actions or Behavior BOOTH OPERATOR:

At the discretion of the Chief Examiner, insert Event 4, FWH 4A Tube Leak. EVENT INDICATIONS:

APP-007-E7; HTR 4A HI/LO LVL APP-007-08; HTR 38 HI/LO LVL (-2 minutes later) APP-007-E8; HTR 48 HI/LO LVL (Later) BOP Respond to alarms and references APP-007-E7.

SRO/BOP Dispatch an operator to check sight glass level and Level Control Valve position.

NOTE: The crew may receive a Power Limit Warning ERFIS alarm due to the feedwater transient.

If so, they will use the Turbine GV limiter to reduce power to < 100%. BOOTH OPERATOR:

When requested, FW Heater 4A is flooded and both Normal and Alternate Drains are open. 4A Shell Side Relief valve is cycling. 4B has a high level and the Normal valve is OPEN and the Alternate drain is cycling. NOTE: The crew may enter AOP-010, MAIN FEEDWATER/CONDENSATE MALFUNCTION due to the transient on the Feedwater system. AOP-010 steps are listed for reference, but are NOT necessary for successful mitigation of the event. SRO Enters AOP-010, MAIN FEEDWATER/CONDENSATE MALFUNCTION.

Immediate .Action* Step: BOP Check Feedwater Regulating Valves Operating properly in AUTO or MANUAL.*(YES)

Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: ......;....-

Scenario # 2 Event # _4..;...-____ Page 11 of ...,;2;;;,;8;......

__ ---11 Event

Description:

FWH 4A Tube Leak. Time I Position ! Applicant's Actions or Behavior Continuous Action Step: RO CheckReactorTripSetpoint being approached. (NO, Go To Step 4) I F Reactor Trip Setpointis being approached, THEN trip the Reactor and Go To Path:-1. RO/BOP Make PA Announcement For Entry into AOP-01 O. SRO Goes to Step 21, Pipe Break/Leak.

Match Steam Flow With Feed Flow:

Reduce Turbine Load to match Feed Flow and Steam Flow BOP using Attachment

1.

Check Feed Flow matched with Steam Flow. (YES)

Stop the power reduction Determine location of the leak:

Visual observation of an external leak. CREW

Feed Water Heater level alarms.

Feed Water Heater Normal and Alternate drain valve positions.

Feed Water Heater #1 & #2 Emergency Dump valve positions.

CREW If tube leakage is occurring, then bypass the affected string of heaters for repair of defective tubes using OP-407, Heater Drains and Vents. SRO Determine that heater must be bypassed and isolated per OP-407 and commence a plant down power to < 517 MWe. Appendix D NUREG-1 021, Rev. 9, SUpp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: ......;...-

Scenario # 2 Event # 5 Page 12 of 28 Event

Description:

Downpower to support removing FWH 4A from service. Time II Position II Applicant's Actions or Behavior NOTE: The crew will use OP-105, MANEUVERING THE PLANT WHEN GREATER THAN 25% POWER, to perform the plant down power. Only the applicable steps have been listed. SRO Notify the Load Dispatcher that unit load will be reduced. SRO Notify RC that increased radiation levels are expected in the CV Pump Bays and Pipe Alley due to normal shutdown crud bursts. RO Monitor the highest operable Power Range Channel and the highest operable Intermediate Range Channel on NR-45. SRO/RO IF Reactor Engineering has not provided technical guidance, THEN determine the reactivity change required.

IF additional letdown flow is desired, THEN: RO

Start additional Charging Pumps as necessary,

Place additional letdown orifice in service . RO IF a significant change in RCS Boron concentration occurs, THEN energize additional PZR heaters as needed. NOTE: OP-301, Section 8.2.8 Quick Boration Checklist (shaded area) is included in the following steps, but may be used following the commencement of the plant down power. RO DETERMINE the amount of Boric Acid to add to the RCS and OBTAIN an independent check of the volume required.

NOTE: -160 gallons of Boric Acid will be added based on rods stepping to 160 steps. (The crew will add Boric Acid in 2-4 batches.)

RO OBTAIN permission from the CRSS OR the SSO to borate. Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix 0 Operator Action Form ES-D-2 Op Test No.: ......;....-

Scenario # 2 Event # _5;;...-____ Page 13 of .....:2:.;;8

___ -11 Event

Description:

Downpower to support removing FWH 4A from service. Time Position Applicant's Actions or Behavior RO PLACE the RCS MAKEUP MODE selector switch to BORATE. RO SET YIC-113, BORIC ACID TOTALIZER to desired quantity.

RO IF desired, THEN PLACE FCV-113A, BORIC ACID FLOW, in MAN AND ADJUST using the UP and DOWN pushbuttons.

RO Momentarily PLACE the RCS MAKEUP SYSTEM switch to START. IF any of the below conditions occur, THEN momentarily place the RCS MAKEUP SYSTEM switch in the STOP position:

RO

Rod Motion is blocked or in the wrong direction

T AVG increases

Boric Acid addition exceeds the desired value WHEN the desired amount of Boric Acid has been added, THEN verify the following:

FCV-113A, BORIC ACID FLOW, closes. RO FCV-113B, BLENDED MU TO CHG SUCT, closes. *

IF in Auto, THEN the operating Boric Acid Pump stops.

The RCS MAKEUP SYSTEM is OFF. IF desired, THEN FLUSH the Boric Acid flow path as follows:

PLACE the RCS MAKEUP MODE selector switch in the AL T DILUTE position.

SET YIC-114, PRIMARY WTR TOTALIZER to 15-20 gallons.

PLACE FCV-114B, BLENDED MU TO VCT to CLOSE.

Momentarily PLACE RCS MAKEUP SYSTEM switch to START. RO

IF any of the below conditions occur, THEN momentarily place the RCS MAKEUP SYSTEM switch in the STOP position:

0 Unanticipated Rod Motion 0 Primary Water addition reaches the desired value

WHEN the desired amount of Primary Water has been added to the RCS, THEN verify the following:

0 FCV-114A closes. 0 FCV-113B closes. 0 IF in Auto, THEN the operating Primary Water Pump Appendix 0 NUREG-1 021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: --:...-Scenario # 2 Event # ____ Page 14 of ,..;2;;,;;8

___ ...,1 Event

Description:

Downpower to support removing FWH 4A from service. Time II Position II Applicant's Actions or Behavior stops. 0 The RCS MAKEUP SYSTEM is OFF. RETURN the RCS Makeup System to automatic as follows:

VERIFY FCV-114A is in AUTO.

PLACE FCV-114B to the AUTO position.

RO

PLACE the RCS MAKEUP MODE switch in AUTO.

VERIFY FCV-113A is in AUTO.

Momentarily PLACE the RCS MAKEUP SYSTEM switch in the START position.

RECORD, in AUTO LOG, as indicated by PRIMARY WATER RO TOTALIZER, YIC-114 AND Boric Acid TOTALIZER, YIC-113 the total amount of Primary Water AND Boric Acid added during the boration.

RO MONITOR parameters for the expected change in reactivity AND inform the CRSS OR the SSO of the results of the boration.

IF EH Turbine Control is in OPER AUTO, THEN reduce turbine load as follows:

Place the EH Turbine Control in the desired position:

IMP IN. BOP

Set the desired load in the SETTER.

Select the desired Load Rate.

Depress the GO pushbutton.

Verify proper programming of the following:

RO

T AVG tracks within 5 degrees F of T REF.

PZR level tracks within 5% of reference level. SRO/RO Maintain the control rods above the minimum allowable rod height borating the RCS lAW OP-301. BOOTH OPERATOR:

As soon as the power reduction is 2: 5% or at the discretion of the Chief Examiner, insert the next event. Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix 0 Operator Action Form ES-D-2 Op Test No.: Scenario # 2 Event # 6 and 7 Page 15 of 28 ----------

Event

Description:

Rods continue to step requiring a Reactor Trip, Failure of the Turbine to Trip. Time Position II Applicant's Actions or Behavior BOOTH OPERATOR:

At the discretion of the Chief Examiner, insert Event 6, Control Rods continue to step requiring a Reactor Trip. EVENT INDICATIONS:

Rod speed indication and directional lights Control Rod step counters RO notices that rods are stepping when not demanded and performs RO Immediate Actions of AOP-001, MALFUNCTION OF REACTOR CONTROL SYSTEM. RO Immediate Action Step: Check unexpected rod motion in progress. (YES) RO Immediate Action Step: Check Reactor Power greater than 15%. (YES) Immediate Action Step: CheckTurbine Load: RO/BOP

Control. rods stepping in AND unexpected load reduction in progress. (NO) . OR

Unexpected load reduction has occurred. (NO) Immediate Action Step: AttempttoSt6p Rod Motion as follows:

IFBODBANKSELECTORSwitch is in AUTO, THEN place the ROD I3ANKSELECTOHSwitch in Manual. RO

IF ROD BANK SELECTOR Switch is in Manual, THEN place theROD BANK SELECTOR Switch in Auto.

IF Rod Motion does NOTstop, THEN trip the Reactor and Go To PATH..:l.

Appendix 0 NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: --Scenario # 2 Event # 6 and 7 Page 16 of 28 Event

Description:

Rods continue to step requiring a Reactor Trip, Failure of the Turbine to Trip. Time II Position II Applicant's Actions or Behavior RO Manually trips the Reactor by depressing the Reactor Trip pushbutton.

Notices that the Turbine failed to trip. Attempts to manually trip the BOP turbine by depressing the Turbine Trip pushbutton and THINK pushbutton simultaneously.

Turbine will not trip from the RTGB. BOP manually runs back the turbine: BOP

Verifies the Turbine is in TURBINE MANUAL.

Depresses the GV DOWN and FAST button simultaneously until ALL GV valves indicate CLOSED. RO Immediate Action Step: Reactor Tripped. (YES) " Immediate Action Step: BOP Turbine Tripped.(NO)

Trip or Runback the Turbine. (YES, RLinback was successful)

,,' . BOP Immediate Action' Step: E-1 AND E-2 energized.

'(YES) RO Immediate Action Step: SI Initiated. (YES) Appendix D NUREG-1021 , Rev. g, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 2 Event # ......;....-

-8,9 and 10 Page 17 of 28 Event

Description:

FW Break on S/G "B" inside CV with a loss of ALL feedwater.

CV Spray Pump "A" fails to start, Phase B valves FCV-626 and CVC-381 fail to CLOSE. Time 1 Position II Applicant's Actions or Behavior BOOTH OPERATOR:

As soon as the Reactor Trips, verify Events 8, 9 and 10 are inserted.

If requested, Manually trip the Turbine locally. NOTE: The crew may take action lAW OMM-022 to start CV Spray Pump "A" and shut Phase B valves CVC-381 and FCV-626 following verification of Immediate Actions. The crew may also stop ALL RCPs due to a Phase B isolation.

CREW Open Foldout A.

RCP Trip criteria.

IF BOTH conditions are met, THEN stop all RCPs: (NO) RO 0 SI Pumps -AT LEAST ONE RUNNING AND CAPABLE OF DELIVERING FLOW TO THE CORE 0 RCS Subcooling -< 35 degrees F [55 degrees F]

SI actuation criteria.

IF EITHER condition occurs, THEN Actuate SI SRO/RO and Go To PATH-1, Entry Point A: 0 RCS Subcooling -< 35 degrees F [55 degrees F] 0 PZR Level-CAN NOT BE MAINTAINED>

10% [32%].

MSR Isolation criteria.

IF ANY Purge OR Shutoff Valve does not BOP indicate fully closed, THEN place the associated RTGB Switch to CLOSE. Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Op Test No.: --.;....-Event

Description:

Operator Action Form ES-D-2 Scenario # 2 Event # _8;.:.,...;,9...;;;a;.;.;nd;;..1;..;;O

__ Page 18 of ...,;2;;,;;8

___ -11 FW Break on S/G "B" inside CV with a loss of ALL feedwater.

CV Spray Pump "A" fails to start, Phase B valves FCV-626 and CVC-381 fail to CLOSE. I Time II Position II Applicant's Actions or Behavior

S/G isolation criteria.

IF both the following conditions are met, THEN perform the following:

Any S/G pressure is decreasing in an uncontrolled manner OR

Any S/G has completely depressurized.

AND

At least ONE S/G is intact. 0 Reset SI. 0 CLOSE the appropriate AFW isolation valves to the faulted S/G AND OPEN the associated breaker for the valves closed.

S/G "B"

V2-14B, SDAFW PUMP DISCH, MCC-9, CMPT -1C

V2-16B, AFW HDR DISCH, MCC-10, CMPT -4F 0 WHEN the faulted S/G drys out, THEN dump steam from intact S/Gs to control RCS repressurization.

RO Verify Phase A Isolation valves are closed. (YES) BOP Verify FW Isolation valves are closed. (YES) BOP Verify both FW pumps are tripped. (YES) BOP Verify both MDAFW pumps are running. (NO) BOP If additional Feedwater is required, start the SDAFW pump. (NO, Pump started but tripped) RO Verify 2 SI pumps running. (YES) RO Verify Both RHR pumps running. (YES) Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Op Test No.: --Event

Description:

Operator Action Form ES-D-2 Scenario # 2 Event # 8,9and10 Page 19 of 28 ......;.;.;.---...,1 FW Break on S/G "B" inside CV with a loss of ALL feedwater.

CV Spray Pump "A" fails to start, Phase B valves FCV-626 and CVC-381 fail to CLOSE. Time II Position II Applicant's Actions or Behavior RO Verify SI valves are properly aligned. (YES) RO At least 1 CCW pump is running. (YES) BOP All SW and SW Booster pumps running. (NO) BOP Attempt to start all SW and SW booster pumps. (NO, SW Booster Pump "A" is unavailable)

BOP North OR South SW Header Lo Pressure alarm illuminated. (NO) RO Verify CV Fans HVH-1, 2, 3, 4 running. (YES) RO Verify IVSW System Initiated. (YES) RO Verify CV Ventilation isolation. (YES) BOP Verify Control Room Vent aligned for Pressurization Mode. (YES) BOP Verify both EDGs running. (YES) CONTINVOUS ACTION*STEP:

BOP Restart battery chargers within 30 minutes of power.loss using OP-601. .. CONTINUOUS ACTION STEP: RO CVPressure has remained b.elow (NO) RO Verify CV Spray initiated. (YES) Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Op Test No.: ......;....-

Event

Description:

Operator Action Form ES-D-2 Scenario # 2 Event # 8,9 and 10 Page 20 of 28 FW Break on S/G "B" inside CV with a loss of ALL feedwater. CV Spray Pump "A" fails to start, Phase B valves FCV-626 and CVC-381 fail to CLOSE. Time II Position I Applicant's Actions or Behavior RO Verify all CV Spray pumps running with valves properly aligned. (NO, CV Spray Pump "A" did not Auto start) NOTE: The crew may have already taken action to start CV Spray Pump "A" per guidance in OMM-022. RO Verify -12 GPM spray additive tank flow. (Will require adjustment)

RO Verify Phase B isolation valves closed. (NO, takes action to close CVC-381 and FCV-626 from the RTGB.) CRITICAL TASK: Verify CVC-381, Phase B CV Isolation Valve is closed prior to transitioning from PATH-1. RO Stop all RCPs. (May be previously stopped) Verify all MSIVs and MSIV bypass valves closed. (YES) BOP (Operator will ensure that switches for the MSIVs are placed in the CLOSE position)

SRO Locally open breaker for HVS-1 at MCC-5. RO RCS pressure>

1350 psig. [1250 psig] (YES) BOP At least 300 GPM AFW flow available. (NO) BOP Level in at least one S/G greater than 8% [18%] (NO) Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Op Test No.: -----Event

Description:

Operator Action Form ES-D-2 Scenario # 2 Event # _8;.:"..;;,,9.,;;;a;.;,;nd;;,..1;.,;;O

__ Page 21 of ,....;2::..;;8

___ -11 FW Break on S/G "B" inside CV with a loss of ALL feedwater.

CV Spray Pump "A" fails to start, Phase B valves FCV-626 and CVC-381 fail to CLOSE. Time II Position II Applicant's Actions or Behavior BOP Align AFW valves. BOP At least 300 GPM AFW flow verified (NO) RO Reset SPDS and Initiate monitoring of Critical Safety Function Status Trees SRO Transition to FRP-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK. BOP Check Total Feed Flow less than 300 GPM due to operator action. (NO) Determine if Secondary Heat Sink is required:

Check RCS pressure greater than any non-faulted S/G RO pressure. (YES)

Check RCS temperature greater than 350 degrees F [310 degrees F] (YES) Continuous Action Step: BOP Check Any TWQ S/G Wide Range Levels less than 10%. [19%1 (NO) IF any TWO S/GWR levels decrease.

to < 10% [19%], THEN Go To Step 5. BOP Check CST level greater than 10%. (YES) RO Verify All S/G Blowdown and Sample Isolation Valves CLOSED. (YES) BOP Check AFW Lines INTACT. (YES) Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix 0 Op Test No.: Event

Description:

Operator Action Form ES-D-2 Scenario # 2 Event # 8,9 and 10 Page 22 of .....;2;.;8

___ ...,1 FW Break on S/G "B" inside CV with a loss of ALL feedwater. CV Spray Pump "A" fails to start, Phase B valves FCV-626 and CVC-381 fail to CLOSE. Time II Position Applicant's Actions or Behavior BOP Try to Establish Motor Driven AFW Flow To At Least One S/G:

Check AFW Pump Breakers TRIPPED. (NO) BOP Verify AFW HDR DISCH valves (V2-16A/B/C)

OPEN. (YES) BOP Check AFW flow to SIGs > 300 GPM. (NO) Attempt to Start SDAFW Pump: BOP

Verify STEAM DRIVEN AFW PUMP STM SHUTOFF VALVES OPEN. (V1-8A, V1-8B, V1-8C) (NO) SRO IF the steam supply valves cannot be opened, THEN Go To Step 11. Locally Investigate AND Attempt To Restore AFW Flow: BOP

Verify AFW Pump suction supply is available. (YES)

Position MDAFW Pump LOCAUREMOTE Switch to LOCAL. Attempt to reclose any tripped breakers:

Depress the MDAFW Pump local STOP pushbutton.

BOP

Depress the MDAFW Pump local START pushbutton.

Check MDAFW Pump started. (YES) BOP Continuous*

Action Step: Check AFW Flow To SIGs greater than 300 GPM. (YES) RO Reset SPDS and Return to Procedure and Step In Effect. (PATH-1, grid location B-11) Appendix 0 NUREG-1021 , Rev. 9, Supp. 1 Appendix D Op Test No.: Event

Description:

Operator Action Form ES-D-2 Scenario # 2 Event # .....;8;;;.:.,..;;.9.;;;a;.;.;nd;;...1;.,;;O

__ Page 23 of ....;2:;;8

___ ...,1 FW Break on S/G "B" inside CV with a loss of ALL feedwater.

CV Spray Pump "A" fails to start, Phase B valves FCV-626 and CVC-381 fail to CLOSE. Time i Position Applicant's Actions or Behavior BOP Control AFW flow to maintain S/G levels between 8% [18%] and 50% RO RCP Thermal Barrier Cooling Water High or Low Flow alarms illuminated. (YES) RO At least One Charging Pump Running. (YES) BOP Place Steam Dump Mode switch to Steam Pressure.

RO RCS Temperature stable at or trending to 547 degrees F. (NO) RO RCS temperature greater than 547 degrees F. (NO) BOP Attempt to limit cooldown.

BOP If RCS cooldown continues and is not due to SI flow, Then close MSIVs and MSIV Bypasses.

RO PZR PORVs closed. (YES) RO PZR Spray and Aux Spray valves closed. (YES) RO At least One RCP running. (NO) BOP Any S/G with uncontrolled depressurization or completely depressurized (YES) RO Reset SPDS and Initiate monitoring of Critical Safety Function Status Trees. Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Op Test No.: Event

Description:

Operator Action Form ES-D-2 Scenario # 2 Event # 8,9 and 10 Page 24 of 28 FW Break on S/G "B" inside CV with a loss of ALL feedwater.

CV Spray Pump "A" fails to start, Phase B valves FCV-626 and CVC-381 fail to CLOSE. Time II Position II Applicant's Actions or Behavior SRO Transition to EPP-11, FAULTED SIG ISOLATION.

BOP Maintain at least One S/G available for RCS Cooldown.

BOP Identify intact S/Gs:

ANY S/G Pressure Stable or Increasing (YES,"A" and "C") Identify faulted S/Gs: BOP

Any S/G Pressure decreasing In An Uncontrolled Manner OR Any S/G Completely Depressurized. (YES, "B") BOP Isolate faulted S/G using Supplement G. (See pg. 26-27 for steps) BOP Maintain a faulted S/G in the isolated condition during subsequent recovery actions unless needed for cooldown.

BOP Check CST Level greater than 10%. (YES) BOP Check available Secondary Radiation Monitors normal. (YES) BOP Check any S/G with an uncontrolled level increase. (NO) SRO Go To PATH-1, Entry Point C. SRO Reset SPDS and initiate monitoring of CSFSTs. SRO Open Foldout B. Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Op Test No.: Event

Description:

Operator Action Form ES-D-2 Scenario # 2 Event # _8;...:. * ...;.9...;,;a;.;.;nd;;.,.1;..;.O

__ Page 25 of

___ -I1 FW Break on S/G "B" inside CV with a loss of ALL feedwater.

CV Spray Pump "A" fails to start. Phase B valves FCV-626 and CVC-381 fail to CLOSE. Time II Position II Applicant's Actions or Behavior

SI Termination criteria; 0 IF ALL conditions below occur. THEN Go To EPP-7. SI TERMINATION:

RCS subcooling greater than 35°F [55 OF]

Heat Sink established as follows: 0 Total feed flow to intact S/Gs > 300 GPM OR SRO 0.2x10 6 PPH. OR 0 Level in at least one intact S/G > greater than 8% [18%]

RCS pressure >1650 PSIG [1750 PSIG] AND STABLE OR INCREASING

PZR level> 10% [32%] SRO Determines that SI termination criteria are met and transitions to EPP-7, SI TERMINATION.

The Chief Examiner may terminate the scenario anytime after flow is established to at least one SIG and the faulted SIG has been isolated lAW Supplement G. Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Op Test No.: Event

Description:

Operator Action Form ES-D-2 Scenario # 2 Event # 8, 9 and 10 Page 26 of .....;2;;;.;8

___ FW 8reak on S/G "8" inside CV with a loss of ALL feedwater.

CV Spray Pump "A" fails to start, Phase 8 valves FCV-626 and CVC-381 fail to CLOSE. Time I Position I Applicant's Actions or Behavior Pages 26-27 are steps from Supplement G, STEAM GENERATOR ISOLATION to isolate SIG "8" as a faulted Steam Generator.

BOP Go to the appropriate step from following table: S/G B to be isolated, Go To Step 18. BOP Check S/G "B" faulted. (YES) BOP Verify V1-3B, MSIV CLOSED. (YES) BOP Verify MS-353B, MSIV V1-3B BYP CLOSED. (YES) BOP Verify FRV B CLOSED. (YES) BOP Verify FRV B BYP CLOSED. (YES) BOP Verify V2-6B, FW HDR SECTION Valve CLOSED. (YES) BOP Verify V2-14B, SDAFW PUMP DISCH Valve CLOSED. (YES) BOP Verify V2-16B, AFW HDR DISCH Valve CLOSED. (YES) BOP Verify STEAM LINE PORV CLOSED. (YES) BOP Verify V1-8B, SDAFW STEAM SHUTOFF Valve CLOSED. (YES) BOP Verify S/G B Blowdown and Blowdown Sample Valve Status Light Indication CLOSED. (YES) Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Op Test No.: --Event

Description:

Operator Action Form ES-D-2 Scenario # 2 Event # 8,9and10 Page 27 of 28 -----II FW Break on S/G "B" inside CV with a loss of ALL feedwater.

CV Spray Pump "A" fails to start, Phase B valves FCV-626 and CVC-381 fail to CLOSE. Time i Position i Applicant's Actions or Behavior Dispatch an operator to the Pipe Jungle to close MS-29, S/G B BOP BYPASS DRN and WARM-UP LINE TO AFW PUMP (located above / right of V1-SB) BOP Check S/G B MSIV Above and Below Seat Drain Valves CLOSED. (YES) Dispatch an operator to E-1/E-2 Room to perform the following:

At MCC-9, verify V2-14B closed and open breaker V2-14B, BOP SDAFW PUMP TO S/G B (CMPT-1C)

At MCC-6, verify V1-SB closed and open breaker V1-SB, SDAFW PUMP STEAM ISOLATION (CMPT-16M)

Dispatch operator to the Aux. Bldg. to perform the following:

BOP

At MCC-10, verify V2-16B closed and open breaker V2-16B, MDAFW PUMP HEADER DISCHARGE TO S/G B (CMPT-4F)

SRO Go To Step 49. BOP Check All Faulted and Ruptured S/Gs ISOLATED. (YES) BOP WHEN the faulted S/Gs dry out, THEN dump steam from intact S/G to control RCS repressurization.

BOP Check Any S/G RUPTURED. (NO) SRO Return to procedure and step in effect. Appendix D NUREG-1 021, Rev. 9, Supp. 1 HLC-08 NRC SCENARIO 2 TURNOVER SHEET POWER LEVEL: 100%, 9000 MWO/MTU BORON CONCENTRATION:

766 ppm EQUIPMENT UNDER CLEARANCE:

SW Booster Pump "A" is out of service and under clearance for Motor Coupling Alignment.

o LCO 3.7.7-A has been entered and is in hour 18 of a 72 Action Statement.

o Expected return is within -18 hours. EQUIPMENT STATUS:

Main Turbine bearing #3 has a slightly elevated vibration and is being monitored by Systems Engineering.

INSTRUCTIONS FOR THE WATCH:

Maintain power at 100% RTP. Appendix 0 NUREG-1 021, Rev. 9, Supp. 1 I Appendix D Scenario Outline Form ES-D-1 Facility:

HB ROBINSON Scenario No.: 3 Op Test No.: 2008 NRC Examiners:

Operators:

Initial Conditions:

7% BOl, 150 MWD/MTU, 1645 ppm Boron.

SW Booster Pump "A" is Out-Of-Service for Motor Coupling Alignment.

0 lCO 3.7.7 -A has been entered and is in hour 18 of a 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months action statement.

0 Expected return is within -18 hours.

Main Turbine Vibration for #2, 3 and 4 bearings is elevated.

Turnover:

Continue with GP-005 to synchronize the Generator to the grid. Critical Task:

Manually trip the Reactor prior to transitioning out of AOP-001.

Recognize that a SGTR has occurred and isolate the applicable S/G before transitioning to EPP-17. Event Malt. No. Event Type* Event No. Description 1 (N) BOP, SRO Place the Generator Voltage Regulator in service. 2 (R) RO Inadvertent Turbine Trip with Power < P-7. (C) SRO 3 (C) BOP, SRO Service Water Pump "A" breaker trips on overload.

4 (C) RO low pressure on SI Accumulator "B". (TS) SRO 5 (M) All Multiple dropped rods requiring a Reactor Trip. 6 (M) All S/G Tube Rupture on S/G "C". (TS) SRO 7 (C) BOP S/G "c" Safety fails 15% open. 8 (C) RO Safety Injection Pump "C" fails to start. 9 (C) BOP S/G Blowdown Sample valves fail to close. I * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Appendix D NUREG-1 021, Rev. 9, Supp. 1 I Appendix D Scenario Outline Form ES-D-1 HLC-08 NRC SCENARIO 3

SUMMARY

DESCRIPTION The crew will assume the watch with the plant at 7% Reactor Power, with the Turbine rolling at 1800 RPM, but not synchronized to the grid. A Dedicated Operator (Surrogate) required by procedure, will be stationed for S/G level control. The previous shift identified increased vibration on Main Turbine bearing #3 during rollup and has taken all necessary actions to inform station management.

Power was stabilized for shift turnover and to obtain vibration data on the Turbine. Service Water Booster Pump "A" is under clearance for Motor Coupling Alignment.

Shift instructions are to continue with GP-005, POWER OPERATION, to synchronize the Generator to the grid. The crew will use GP-005 to place the Generator Voltage Regulator in service in preparation to synchronize the Generator to the grid. On cue from the Chief Examiner, the Turbine will inadvertently trip. The crew should respond lAW AOP-007, TURBINE TRIP BELOW P-7, by stabilizing Reactor Power at -3%. During stabilization, the BOP will verify proper operation of the Condenser Steam Dumps. Following plant stabilization the Dedicated Operator will no longer be required and exit the simulator.

On cue from the Chief Examiner, Service Water Pump "A" breaker will trip on overload.

RTGB Annunciator APP-008-F4 will direct the operators to start a standby Service Water Pump. All of the actions will be directed from annunciators received during the Service Water pressure transient.

When Tech Specs are addressed, the Chief Examiner can cue a Low Pressure on SI Accumulator "B". The RO will reference APP-002-D4 and take action to repressurize the Accumulator lAW OP-202. The SRO will enter LCO 3.5.1, Condition C for the Low Pressure condition.

On cue from the Chief Examiner, all Control Bank C, Group 2 rods will drop. The SRO should respond by directing a Reactor trip and enter PATH-1. On the Reactor trip, S/G "C" will develop a 500 gpm tube rupture which will require a Safety Injection.

On the Safety Injection, S/G "C" Safety Valve will fail 15% open and will not close, SI Pump "C" will fail to start, requiring the RO to start it manually, and S/G "C" Blowdown Sample valves will not close as expected.

The Chief Examiner may terminate the scenario at any time after all possible S/G isolation actions have been taken and the crew has transitioned to EPP-17. Appendix D NUREG-1 021, Rev. 9, Supp. 1 I Appendix D Scenario Outline Form ES-D-1 HLC-08 NRC SCENARIO 3 SIMULATOR SETUP IC/SETUP:

IC-603, SCN 006_Sim_3.

SW Booster Pump "A" is OFF, breaker OPEN and switch is RED CAPPED.

Main Turbine Bearing #2 is OFFSET by 1.5, #3 by 2.3 and #4 by 1.7.

Status board is correctly marked up for IC-3.

Provide candidates with a marked up (up to Step 8.4) copy of GP-005 to synchronize the Generator to the Grid. PRE-LOADED EVENTS: The following events should occur on the reactor trip:

Event 8: SI Pump "c" fails to start.

Event 9: S/G Blowdown Sample valves fail to close. EVENTSITRIGGERS INITIATED DURING THE SCENARIO:

Event 2: Inadvertent Turbine Trip with Power < P-7.

Event 3: SW Pump "A" Breaker trips on overload.

Event 4: Low pressure on SI Accumulator "B".

Event 5: Multiple dropped rods requiring a Reactor Trip.

Event 6: S/G Tube Rupture on S/G "C".

Event 7: S/G "c" Safety Valve fails 15% open. EXPECTED PROCEDURE FLOW PATH OR COPIES NEEDED: GP-005, Section 8.4; AOP-007; OP-202, Section 8.2.3; AOP-001; PATH-1; Foldout A; Supplement G; EPP-11; PATH-2; Foldout C. Appendix D NUREG-1021 , Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: ......;....-

Scenario # 3 Event # --.;... ____ Page 4 of .....;2;;.;6

___ ..,1 Event

Description:

Place the Generator VR in service and synchronize the Generator to the grid. Time I Position I Applicant's Actions or Behavior NOTE: The crew will brief Generator synchronization prior to entering the simulator.

They will start with Step 8.4 of GP-OOS. SRO Inform the Load Dispatcher that the unit will be placed on the grid. BOP WHEN the turbine is at 1800 rpm, THEN close the Exciter Field Breaker. Place the Voltage Regulator in service:

Slowly raise Generator volts to 22KV using the Manual Field Current Adjuster.

I F Generator voltage exceeds 22KV and the Exciter breaker BOP has not tripped, THEN reduce voltage as soon as possible.

Place the VOLTAGE REGULATOR in the TEST position.

Adjust Regulator Balance to zero using the VOLTAGE ADJUSTER.

Place the VOLTAGE REGULATOR in AUTO. BOP Place the MAIN GENERATOR synchroscope key switch in the GEN NORTH position.

BOP Adjust the % DIFF VOLTS to zero using the VOLTAGE ADJUSTER.

Adjust Turbine speed so that the synchroscope is rotating SLOWL Y in BOP the FAST direction. (Using Reference Setter, sets turbine speed to -1802 RPM and depresses GO) BOP Verify T AVG is at the high end of the 547°F to 551°F band and Reactor Power is .:s. 8%. Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: -:..._ Scenario # 3 Event # _____ Page 5 of

__ ----41 Event

Description:

Place the Generator VR in service and synchronize the Generator to the grid. Time I Position I Applicant's Actions or Behavior NOTE: The sequence of actions necessary to synchronize the unit to the grid is TIME CRITICAL.

The RO, BOP and FW Operator shall verbally rehearse the actions of the following steps and coordinate their actions while synchronizing to the grid and loading the unit. NOTE: Prior to the Generator output breaker being closed, insert Event 2, Inadvertent trip with Power < P-7. Synchronize the Main Generator to the grid:

WHEN the synchroscope is rotating SLOWLY in the FAST direction and reaches the 5 minutes to 12 o'clock position, THEN close the NORTH OCB BKR 52/9.

IF GLU and GLL remain closed, THEN within 30 seconds adjust Turbine load until GLU and GLL are off their closed seats. (Not to exceed 70 MWe) BOP

IF the Turbine cannot pick up at least 20 MWe, THEN reopen the OCB and inform the SSO and DO NOT CONTINUE.

IF the unit is at 70 MWe and none of the GV closed lights are extinguished, THEN within the next 30 seconds: 0 Place Turbine Control in TURB MANUAL and use GV Down to shed load to minimum. 0 Verify Reactor Power is < 10%. 0 Open the North OCB BKR 52/9. Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: ....;...-Scenario # 3 Event # 2 Page 6 of 26 Event

Description:

Inadvertent Turbine Trip with power <

Time Position I Applicant's Actions or Behavior BOOTH OPERATOR:

When directed by the Chief Examiner, insert Event 2, Inadvertent trip of the Turbine. (Ensure Reactor Power is below P-7) EVENT INDICATIONS:

APP-008-B1; EH FLUID PMP AlB AUTO START APP-008-B2; EH FLUID SYSTEM HIILO PRESS APP-008-C2; EH FLUID HI/LO-LO LEVEL APP-009-E2; GOV CAB MONITOR TROUBLE Turbine speed is decreasing and all Turbine valves indicate closed. SRO Enters AOP-007, TURBINE TRIP BELOW P-7. Check Turbine trip as follows:

Both Turbine Stop Valves closed (YES) BOP OR

All Governor Valves Closed (YES) RO/BOP Make PA announcement for AOP-007 entry. Check Reactor Power less than 3%. (NO) RO

Manually insert control rods or borate to reduce reactor power less than 3%. NOTE: The crew will declare MODE 2 after going below 5% Reactor Power. Check Turbine Oil system status:

Turbine Bearing Oil Pressure>

6 psig. (YES) BOP

Turning Gear and Seal Oil Backup pumps running. (NO) IF the Lube Oil system is intact, THEN start the Turning Gear and Seal Oil Backup pumps. (Will start Pumps using Manual switch) Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 3 Event # 2 Page 7 of 26 Event

Description:

Inadvertent Turbine Trip with power < P-7. Time i Position II Applicant's Actions or Behavior Continuous Action Step: Verify Bearing Oil Lin Pump running: BOP Check Turbine Speed < 600 RPM. (NO) WHEN Turbine Speed is <.600 RPM,THENverify Bearing Oil Lift Pump is running. Check North OCB BKR 52/9, South OCB BKR 52/8 and Exciter Field BOP Breaker tripped. (NO, Exciter Field Breaker is still CLOSED) IF the Exciter Field Breaker has NOT tripped, THEN momentarily place the control switch in TRI P. Check T AVG 547 of to 551°F. (NO) IF Steam Dumps are available THEN:

Adjust PC-464B to maintain 547-551 of. RO/BOP

Verify Steam Dump Control switch is ON.

Verify Steam Dump Mode switch in Steam Press. (YES) Continue with Step 8. BOP Check 1 Main Condensate Pump AND 1 Feed Pump running. (YES) BOP Maintain S/G levels 35 to 44% using FRV Bypass Valves. Check PZR pressure between 2220 and 2250 PSIG. (YES) RO IF pressure is < 2220, THEN Control Heaters and Spray valves to restore pressure to between 2220-2250.

RO Control Charging and Letdown to maintain PZR level -22%. Determine if the Reactor should be shutdown:

SRO Check Reactor Power stable. (YES) Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: --.;...-Scenario # 3 Event # 3 Page 8 of 26 Event

Description:

SW Pump "An trip. Time II Position II Applicant's Actions or Behavior BOOTH OPERATOR:

When directed by the Chief Examiner, insert Event 3, Service Water Pump "A" trips on breaker overload.

EVENT INDICATIONS:

APP-OOS-F4; SW PMP AlB/C/D OVLD APP-OOS-F7; SOUTH SW HDR LO PRESS APP-OOS-FS; NORTH SW HDR LO PRESS APP-002-AS/BS/CS/DS; HVH-1/213/4 WTR OUTLET LO FLOW RO/BOP Recognizes that SW Pump "A" has tripped and references applicable APP-008-F4.

APP-008-F4 actions: If an operating SW Pump has tripped, perform the following:

0 Start a standby pump. (Will start SW Pump "B" or "D") BOP Dispatch an operator to check breaker and current limiter fuses 0 for SW Pump A -480V Bus E-1 , CMPT 20B. 0 Throttle CCW Heat Exchanger return valves to maintain header pressure at 40 -50 psig. Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 3 Event # 4 Page 9 of 26 Event

Description:

Low pressure on SI Accumulator "B". Time I Position I Applicant's Actions or Behavior BOOTH OPERATOR:

When directed by the Chief Examiner, insert Event 4, Low pressure on SI Accumulator "B", EVENT INDICATIONS:

APP-002-D4; SI ACCUM B HI/LO PRESS Decreasing Accumulator B pressure RO Recognizes that SI Accumulator "8" pressure is decreasing slowly and references APP-002-D4.

Reviews, briefs and directs Accumulator repressurization using OP-SRO 202, SAFETY INJECTION AND CONTAINMENT VESSEL SPRAY SYSTEM, Section 8.2.3. RO Verify HIC-936, ACC VENT HDR FLOW CLOSED. (YES) RO Verify SI-855, ACC NITROGEN ISOLATION OPEN. (YES) RO OPEN SI-8538, VENT. RO WHEN the desired pressure is obtained, (Normal operating pressure is 630 PSIG) THEN close SI-8538. (APP-002-D4 will clear) Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Op Test No.: --Event

Description:

Operator Action Form ES-D-2 Scenario # 3 Event # 5,6 Page 10 of 26 Multiple dropped rods requiring a Reactor Trip. S/G Tube Rupture on S/G "en. Time Position I Applicant's Actions or Behavior BOOTH OPERATOR:

When directed by the Chief Examiner, insert Event 5, Multiple dropped rods. When the reactor has been tripped, verify that Event 6, SIG "C" Tube Rupture has been entered. EVENT INDICATIONS:

APP-005-F2; ROD BOTTOM ROD DROP RBLs for Control Bank C, Group 2 are LIT Decreasing SUR Decreasing power. RO Recognizes multiple dropped rods and performs Immediate actions of AOP-001, MALFUNCTION OF REACTOR CONTROL SYSTEM. RO Check unexpected rod motion in progress. (NO) RO/BOP Make PA Announcement for entry into AOP-001. Determine if multiple rods have dropped:

Prompt drop present. (YES) RO

More than 1 RBL illuminated. (YES)

More than 1 IRPI indicates on bottom. (YES) RO Check multiple dropped rods present. (YES) RO Check Reactor in MODE 1 or 2. (YES) SRO Directs tripping the reactor and enters PATH-1. IMMEDIATE ACTION STEP: RO Reactor Tripped. (YES) Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Op Test No.: --Event

Description:

Operator Action Form ES-D-2 Scenario # 3 Event # 5, 6 Page 11 of 26 Multiple dropped rods requiring a Reactor Trip. S/G Tube Rupture on S/G "C". Time I Position I Applicant's Actions or Behavior IMMEDIATE ACTION STEP: BOP Turbine Tripped

.. (YES) IMMEDIATE ACTION STEP: BOP E-l AND E-2 energized. (YES) IMMEDIATE ACTION.STEP:

RO SI Initiated. (NO) SI Initiation required. (NO)

CRITICAL TASK: Manually trip the Reactor prior to transitioning out of AOP-001. RO Verify two Charging Pumps running. SRO Transition to EPP-4, REACTOR TRIP RESPONSE.

Continuous Action Step: Determine if procepureexit is warranted:

SRO

Check.atlack onRNPsite in progress. (NO)

Check a total loss of SW OR. Loss of Lake Robinson Dam integrity in progress. (NO, Go to Step 2) Continuous Action Step: RO CheckSI signal initiated. (NO, Go to Step 4) IfSI initiation occurs during this procedure, THEN Go to PATH-1, Entry Point A Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Op Test No.: ...;....-Event

Description:

Operator Action Form ES-D-2 Scenario # 3 Event # 5,6 Page 12 of 26 Multiple dropped rods requiring a Reactor Trip. S/G Tube Rupture on S/G "e". Time I Position I Applicant's Actions or Behavior SRO Reset SPDS and initiate monitoring of CSFSTs. CREW Open Foldout A.

RCP Trip criteria.

IF BOTH conditions are met, THEN stop all RCPs: (NO) RO 0 SI Pumps -AT LEAST ONE RUNNING AND CAPABLE OF DELIVERING FLOW TO THE CORE 0 RCS Subcooling

-< 35 degrees F [55 degrees F]

SI actuation criteria.

IF EITHER condition occurs, THEN Actuate SI and Go To PATH-1, Entry Point A: (YES) SRO/RO RCS Subcooling

-< 35 degrees F [55 degrees F] 0 0 PZR Level-CAN NOT BE MAINTAINED>

10% [32%].

MSR Isolation criteria.

IF ANY Purge OR Shutoff Valve does BOP not indicate fully closed, THEN place the associated RTGB Switch to CLOSE. SRO Direct a manual SI and Transition to PATH-1, Entry Point A. Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Op Test No.: --.;...-Event

Description:

Operator Action Form ES-D-2 Scenario # 3 Event # _7;..l"..;;.81..,;'

&;.;..9;.....

__ Page 13 of .....;2;;;.;;6

___ S/G "C" Safety Valve fails open. Safety Injection Pump "C" fails to start. S/G Blowdown Sample valves fail to close. Time II Position Applicant's Actions or Behavior BOOTH OPERATOR:

When the crew actuates Safety Injection, verify Events 7, 8 and 9 are inserted.

CREW Open Foldout A. (nothing additional to address) RO Verify Phase A Isolation valves are closed. (NO, crew will direct local isolation of the open S/G Blowdown Sample valves) BOP Verify FW Isolation valves are closed. (YES) BOP Verify both FW pumps are tripped. (YES) BOP Verify both MDAFW pumps are running. (YES) BOP If additional Feedwater is required, start the SDAFW pump. RO Verify 2 SI pumps running. (NO, "C" will be manually started) RO Verify Both RHR pumps running. (YES) RO Verify SI valves are properly aligned. (YES) RO At least 1 CCW pump is running. (YES) BOP All SW and SW Booster pumps running. (NO) BOP Attempt to start all SW and SW booster pumps. (NO, SW Booster Pump "A" is unavailable and SW Pump "A" is tripped) Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix 0 Op Test No.: --.;...-Event

Description:

Operator Action Form ES-O-2 Scenario # 3 Event # _7;..,l.'..;;.8:..;;'

__ Page 14 of .....;2;;.;;6

___ ...,1 S/G "C" Safety Valve fails open. Safety Injection Pump "C" fails to start. S/G Blowdown Sample valves fail to close. Time i Position i Applicant's Actions or Behavior BOP North OR South SW Header Lo Pressure alarm illuminated. (NO) RO Verify CV Fans HVH-1, 2, 3, 4 running. (YES) RO Verify IVSW System Initiated. (YES) RO Verify CV Ventilation isolation. (YES) BOP Verify Control Room Vent aligned for Pressurization Mode. (YES) BOP Verify both EOGs running. (YES) CONTINUOUS ACTION STEP: BOP Restart battery chargers within.30 minutes of power loss using OP-601. CONTINUOUS ACTION STEP: RO CV Pressure.hasremained below.10 psig. (YES) RO Automatic Steam Line Isolation initiated. (NO) RO Automatic Steam Line Isolation required. (NO) SRO Locally open breaker for HVS-1 at MCC-5. RO RCS pressure>

1350 psig. [1250 psig] (YES) BOP At least 300 GPM AFW flow available. (YES) Appendix 0 NUREG-1021 , Rev. 9, Supp. 1 Appendix D Op Test No.: Event

Description:

Operator Action Form ES-D-2 Scenario # 3 Event # _7;"':"..;;.8:..;'

__ Page 15 of -:2:.;:6 ___ -11 S/G "C" Safety Valve fails open. Safety Injection Pump "C" fails to start. S/G Blowdown Sample valves fail to close. Time II Position I Applicant's Actions or Behavior BOP Verify AFW valves properly aligned. BOP Control AFW flow to maintain S/G level between 8% [18%] and 50%. RO RCP Thermal barrier cooling water Hi/Lo flow alarms illuminated. (NO) BOP Place Steam Dump Mode Switch to Steam Pressure.

RO RCS Temp stable at OR trending to 547 degrees F. (NO) RO RCS temperature>

547 degrees F. (NO) RO Attempt to limit cooldown.

RO If RCS cooldown continues and is not due to SI flow, then close MSIVs and MSIV bypasses.

RO PZR PORVs closed. (YES) RO PZR Spray and Aux Spray valves closed. (YES) RO At least 1 RCP running. (YES) RO At least 1 SI Pump Running. (YES) RO RCS Subcooling less than 35 degrees F [55]. (NO) BOP Any S/G with uncontrolled depressurization. (YES) Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Op Test No.: Event

Description:

Operator Action Form ES-D-2 Scenario # 3 Event # _7;..."..;;.8.:..;, &;.;..9;;....-__

Page 16 of

__ ---i1 S/G "C" Safety Valve fails open. Safety Injection Pump "C" fails to start. S/G Blowdown Sample valves fail to close. Time I Position I Applicant's Actions or Behavior RO Reset SPDS and initiate monitoring of CSFSTs. SRO Transition to EPP-11, FAULTED SIG ISOLATION.

BOP Maintain At Least One S/G Available For RCS Cooldown.

BOP Any S/G pressure stable or increasing. (YES) BOP Any S/G pressure decreasing in an uncontrolled manner OR any S/G completely depressurized. (YES) BOP Isolate faulted S/G using Supplement G, S/G ISOLATION. (Supplement G Steps are listed on pages 22-25) BOP Maintain A Faulted S/G In The Isolated Condition During Subsequent Recovery Actions Unless Needed For Cooldown.

BOP Check CST level greater than 10%. (YES) BOP Check Available Secondary Radiation Monitors normal. (NO) SRO Transition to PATH-2, Entry Point J. RO Reset SPDS and initiate monitoring of CSFSTs. CREW Open Foldout C. RO WHEN below 10-10 amps, THEN energize Source Range detectors and monitor recorder.

BOP Request periodic activity samples of all S/Gs Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Op Test No.: Event

Description:

Operator Action Form ES-D-2 Scenario # 3 Event # 7,8,&9 Page 17 of 26 S/G "C" Safety Valve fails open. Safety Injection Pump "C" fails to start. S/G Blowdown Sample valves fail to close. Time I Position II Applicant's Actions or Behavior BOP Place Steam Dump Mode Switch to Steam Pressure.

BOP Open QCV -10426, Bypass Condensate Polishers.

BOP Close C-48A and 48B to isolate Hotwell Return to CST. RO At Least 1 RCP running. (YES) RO At Least 1 SI pump running. (YES) RO RCS Subcooling less than 35 degrees F. [55] (NO) BOP Ruptured S/G identified. (YES) RO Maintain at least 1 S/G available for RCS Cooldown.

BOP Verify ruptured steam line PORV setpoint at 1035 psig using status board. RO Verify RCS temperature

< 547 degrees F prior to MSIV closure. RO Close ruptured S/G MSIV and MSIV Bypass. RO Ruptured S/G MSIV and MSIV bypass closed. (YES) Continuous Action Step: RO WHEN ruptured S/G pressure decreases below 1035 psig, THEN verifyruptured Steam Line PORV closed. Appendix D NUREG-1021, Rev. 9, SUpp. 1 Appendix 0 Op Test No.: --Event

Description:

Operator Action Form ES-D-2 Scenario # 3 Event # _7...:,._8:...;'

&_9;.,...-

__ Page 18 of .....:2:..;6

___ -11 S/G "C n Safety Valve fails open. Safety Injection Pump "C n fails to start. S/G Blowdown Sample valves fail to close. Time Position II Applicant's Actions or Behavior RO IF MDAFW pump is not available, THEN maintain at least 1 S/G supply to SDAFW pump. CREW Close ruptured S/G steam shutoff to SDAFW pump. BOP Verify S/G Blowdown Isolation and Sample Valves Closed. BOP Locally close warmup steam supply from ruptured S/G to SDAFW pump. BOP Locally close above and below seat drains from ruptured S/G. BOP Isolate Feed Flow to any ruptured S/G that is faulted unless needed for RCS cooldown.

CRITICAL TASK: Recognize that a Steam Generator Tube Rupture has occurred and isolate the affected S/G before transitioning to EPP-17. Continuous Action Step: BOP WHEN ruptured S/G level is greater than 8% [18%], THEN isolate Feed Flow. Continuous Action Step: BOP Open* breakers for V1..,8, V2-14 and V2-16 valve closed* to isolate rupturedS/G.

BOP Control Feed Flow to maintain intact S/G level between 8% [18%] and 50%. Appendix 0 NUREG-1021 , Rev. 9, Supp. 1 Appendix 0 Op Test No.: -.;...-Event

Description:

Operator Action Form ES-O-2 Scenario # 3 Event # _7;..:" ...;;,8:.,;;,

Page 19 of ...;2=..:6:....-

__ ---l 1 S/G "C" Safety Valve fails open. Safety Injection Pump "C" fails to start. S/G Blowdown Sample valves fail to close. Time Position I Applicant's Actions or Behavior BOP Any other S/G with uncontrolled level increase. (NO) RO PZR PORVs closed. (YES) RO Open at least one PORV block unless closed to isolate an open PORV. RO IF PORV opens on high pressure, THEN verify reclosure at or below 2335 PSIG, close PORV blocks as necessary.

RO Reset SI. CREW IF offsite power is lost, THEN restart emergency safeguards equipment.

RO Reset CV Spray. RO Reset Phase A and Phase B. RO Establish Instrument Air to CV. IF compressor NOT running, THEN start compressor.

BOP All AC Busses energized by offsite power. (YES) RO IF RCS pressure decreases below 275 PSIG, THEN restart RHR Pumps. BOP Ruptured S/G isolated. (YES, completed during Supplement G) Appendix 0 NUREG-1 021, Rev. 9, Supp. 1 Appendix D Op Test No.: -.;...-Event

Description:

Operator Action Form ES-D-2 Scenario # 3 Event # _7;...l,'..;;.8:..;'

__ Page 20 of

__ ----11 S/G "C" Safety Valve fails open. Safety Injection Pump "C" fails to start. S/G Blowdown Sample valves fail to close. Time II Position Applicant's Actions or Behavior BOP Ruptured S/G pressure>

220 PSIG. (YES) BOP At least one intact S/G available for RCS cooldown. (YES) SRO Determine required core exit temperature from Table 3. RO WHEN PZR press decreases to < 2000 PSIG, THEN block PZR pressure/hi steam line SI signals. RO IF RCPs are NOT running, THEN do NOT monitor CSF-4. BOP Condenser available for Steam Dump. (YES) RO Verify TAVG < 543 degrees F AND block TAVG SI signal prior to maximum steam dump. BOP Dump steam from intact S/G to condenser at maximum rate. RO Align Charging Pump suction to RWST. RO Establish Charging flow to maintain PZR level. RO Core Exit Temperature less than required temperature. (YES) BOP Reduce Steam flow to stabilize RCS temperature.

CREW Allow RCS temperature to stabilize from cooldown prior to continuing.

BOP Ruptured S/G pressure stable or increasing. (NO) Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Op Test No.: --=---Event

Description:

Operator Action Form ES-D-2 Scenario # 3 Event # _7.;..:.,...;.8.:..;,

__ Page 21 of _2_6 ___ ---i1 S/G "COO Safety Valve fails open. Safety Injection Pump "COO fails to start. S/G Blowdown Sample valves fail to close. Time I Position I Applicant's Actions or Behavior BOP Ruptured S/G pressure decreases to < 250 PSIG above pressure of intact S/G used for cooldown. (YES) SRO Transition to EPP-17, SGTR WITH LOSS OF RCS: SUBCOOLED RECOVERY.

At the discretion of the Chief Examiner, when the crew has transitioned to EPP-17 and SIG "C" has been isolated as a faulted and ruptured SIG, the scenario may be terminated.

Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Op Test No.: --Event

Description:

Operator Action Form ES-D-2 Scenario # 3 Event # 7,8, & 9 Page 22 of 26 S/G "c" Safety Valve fails open. Safety Injection Pump "c" fails to start. S/G Blowdown Sample valves fail to close. Time Position i Applicant's Actions or Behavior Pages 22-25 are steps from Supplement G, STEAM GENERATOR ISOLATION to isolate SIG "C" as a faulted SIG and to isolate SIG "C" as a ruptured S/G. BOP Go to the appropriate step from following table:

S/G C to be isolated, GO To Step 34 . BOP Check S/G "C" faulted. (YES) BOP Verify V1-3C, MSIV CLOSED. (YES) BOP Verify MS-353C, MSIV V1-3C BYP CLOSED. (YES) BOP Verify FRV C CLOSED. (YES) BOP Verify FRV C BYP CLOSED .(YES) BOP Verify V2-6C, FW HDR SECTION Valve CLOSED. (YES) BOP Verify V2-14C, SDAFW PUMP DISCH Valve CLOSED. (YES) BOP Verify V2-16C, AFW HDR DISCH Valve CLOSED. (YES) BOP Verify STEAM LINE PORV CLOSED. (YES) BOP Verify V1-8C, SDAFW STEAM SHUTOFF Valve CLOSED. (YES) BOP Verify S/G "C" Blowdown and Blowdown Sample Valve Status Light Indication CLOSED. (NO) Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Op Test No.: -.;...-Event

Description:

Operator Action Form ES-D-2 Scenario # 3 Event # 7, 8, & 9 Page 23 of 26 S/G "C n Safety Valve fails open. Safety Injection Pump "C n fails to start. S/G Blowdown Sample valves fail to close. Time II Position I Applicant's Actions or Behavior Deenergize R-19C. IF S/G "c" Blowdown and Sample valves fail to close, THEN close:

SGB-38C, SGBD HX "C". BOP

SGB-56C, SGBD HX "c" BYPASS/HX FLOW CONTROL ISOLATION.

SGB-60C, SGBD LINE "c" TO WLU SYSTEM.

SGB-38, S/G "c" SAMPLE FLOW ISOLATION.

BOP Dispatch an operator to the Pipe Jungle to close MS-38, S/G "c" BYPASS DRN and WARM-UP LINE TO AFW PUMP. BOP Check S/G C MSIV Above and Below Seat Drain Valves CLOSED. (YES) Dispatch an operator to E-1/E-2 Room to perform the following:

At MCC-9, verify V2-16C closed and open breaker V2-16C, BOP MDAFW PUMP TO S/G C.

At MCC-6, verify V1-8C closed and open breaker V1-8C, SDAFW PUMP STEAM ISOLATION.

Dispatch operator to the Aux. Bldg. to perform the following:

BOP

At MCC-10, verify V2-14C closed and open breaker V2-14C, SDAFW PUMP HEADER DISCHARGE TO S/G C. BOP Check All Faulted and Ruptured S/Gs ISOLATED. (NO, Go To Step 1) BOP Go to the appropriate step from following table:

S/G C to be isolated, Go To Step 34. Appendix D NUREG-1021, Rev. g, Supp. 1 Appendix D Op Test No.: --.;...-Event

Description:

Operator Action Form ES-D-2 Scenario # 3 Event # _7;,..:.,..;;,8,:,.;&;.;.,;9;;...-.

__ Page 24 of .....;2:..;;6

___ -l 1 S/G "C" Safety Valve fails open. Safety Injection Pump "C" fails to start. S/G Blowdown Sample valves fail to close. Time II Position I Applicant's Actions or Behavior Check S/G "C" faulted. (NO) BOP Verify ruptured Steam Line PORV setpoint at 1035 PSIG using Status Board. BOP Verify V1-8C, SDAFW STEAM SHUTOFF Valve CLOSED. (YES) BOP Verify S/G C Blowdown and Blowdown Sample Valve Status Light Indication CLOSED. (NO) Deenergize R-19C. IF S/G "C" Blowdown and Sample valves fail to close, THEN close:

SGB-38C, SGBD HX "C". BOP

SGB-56C, SGBD HX "C" BYPASS/HX FLOW CONTROL ISOLATION.

SGB-60C, SGBD LINE "C" TO WLU SYSTEM.

SGB-38, S/G "C" SAMPLE FLOW ISOLATION.

BOP Dispatch an operator to the Pipe Jungle to close MS-38, S/G "C" BYPASS DRN and WARM-UP LINE TO AFW PUMP. BOP Check S/G C MSIV Above and Below Seat Drain Valves CLOSED. (YES) Dispatch an operator to E-1/E-2 Room to perform the following:

At MCC-9, verify V2-16C closed and open breaker V2-16C, BOP MDAFW PUMP TO S/G C.

At MCC-6, verify V1-8C closed and open breaker V1-8C, SDAFW PUMP STEAM ISOLATION.

Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Op Test No.: .-;...-Event

Description:

Operator Action Form ES-D-2 Scenario # 3 Event # _7;..:.,....;;.8.:....;, &;;...9:.....-

__ Page 25 of ....;2;;.,;;6

___ -11 S/G "C" Safety Valve fails open. Safety Injection Pump "C" fails to start. S/G Blowdown Sample valves fail to close. Time II Position I Applicant's Actions or Behavior Dispatch operator to the Aux. Bldg. to perform the following:

BOP

At MCC-1 0, verify V2-14C closed and open breaker V2-14C, SDAFW PUMP HEADER DISCHARGE TO S/G C. BOP Check All Faulted and Ruptured S/Gs ISOLATED. (YES) BOP WHEN the faulted S/Gs dry out, THEN dump steam from intact S/G to control RCS repressurization.

BOP Check Any S/G RUPTURED. (YES) Perform the following to minimize Secondary system contamination:

Use Auxiliary boilers for auxiliary steam.

Bypass the condensate polishers.

Verify hotwell return to CST isolated:

0 Locally verify C-48A and C-48B CLOSED. SRO/BOP Dispatch an operator to close GS-36, MANUAL GLAND STEAM DUMP. SRO Return to procedure and step in effect. Appendix D NUREG-1 021, Rev. 9, Supp. 1 HLC-08 NRC SCENARIO 3 TURNOVER SHEET POWER LEVEL: 7% BOL, 150 MWD/MTU. BORON CONCENTRATION:

1645 ppm EQUIPMENT UNDER CLEARANCE:

SW Booster Pump "A" is out of service and under clearance for Motor Coupling Alignment.

o LCO 3.7.7 -A has been entered and is in hour 18 of a 72 Action Statement.

o Expected return is within -18 hours. EQUIPMENT STATUS:

Main Turbine bearing #3 has a slightly elevated vibration and is being monitored by Systems Engineering.

INSTRUCTIONS FOR THE WATCH:

Continue with GP-005 and synchronize the Generator to the Grid. Appendix 0 NUREG-1 021, Rev. 9, Supp. 1 I Appendix D Scenario Outline Form ES-D-1 Facility:

HB ROBINSON Scenario No.: 4 Op Test No.: 2008 NRC Examiners:

Operators:

Initial Conditions:

50% BOL, 150 MWD/MTU, 1285 ppm Boron.

SW Booster Pump "A" is Out-Of-Service for Motor Coupling Alignment.

0 LCO 3.7.7 -A has been entered and is in hour 18 of a 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months action statement.

0 Expected return is within -18 hours.

Main Turbine Vibration for #2, 3 and 4 bearings is elevated.

Turnover:

Returning to RTP following a Maintenance Outage. Increase power to 75%. Critical Task:

Manually initiate SI to provide injection flow from at least 1 SI Pump before Reactor Vessel level reaches 41 % by Full Range RVLlS indication.

Ensure that ALL Phase A valves are closed upon receipt of a valid actuation signal prior to completion of Grid Location B-9 (SI Flow Verified).

Event Malf. Event Type* Event No. No. Description 1 (R) RO Increase power to 75% RTP. (N) SRO, BOP 2 (I) BOP, SRO Loop 1 T HOT Fails Low. (TS) SRO 3 (C) BOP, SRO SW flooding from the South SW Header. (TS) SRO 4 (C) RO, SRO PZR PORV PCV-456 fails 70% open. (TS) SRO 5 (M) ALL High vibration on #3 Turbine bearing which leads to a manual Reactor trip. 6 (M) ALL Failure of the Reactor to trip. (ATWS) SDAFW Pump trips. 7 (M) ALL Small Break LOCA. (TS) SRO 8 (C) RO Phase A fails to automatically actuate and several valves fail to automatically close. 9 (C) RO Safety Injection fails to automatically actuate. 10 (C) BOP Control Room HVAC Train A and Train B fail to automatically actuate. (HVE-19A fails to start and HVE-16 fails to stop) * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Appendix D NUREG-1021, Rev. 9, Supp. 1 I Appendix D Scenario Outline Form ES-D-1 HLC-08 NRC SCENARIO 4

SUMMARY

DESCRIPTION The crew will assume the watch with the plant at 50% RTP. The previous shift identified increased vibration on Main Turbine bearing #3 and has taken all necessary actions to inform station management.

Service Water Booster Pump "A" is under clearance for Motor Coupling Alignment.

Shift instructions are to increase power to 75% and hold for Reactor Engineering instructions.

On cue from the Chief Examiner, Loop 1 T HOT will fail low. The crew will respond lAW APP-003-A4, and remove the instrument from service using OWP-028, T/DeltaT1.

The SRO will enter LCO 3.3.1-1 , Condition E for the failed instrument.

On cue from the Chief Examiner, flooding will occur from the discharge of SW Pump "A" at the Service Water intake. The BOP will take immediate actions to split the North and South SW header. The crew should respond lAW AOP-022, LOSS OF SERVICE WATER and isolate the South SW Header, isolating the source of the flooding.

The SRO will enter LCO 3.8.1, Condition B for the inoperable EDG. On cue from the Chief Examiner, PZR PORV PCV-456 will fail 70% open. The crew should attempt to close PCV-456, which will not respond, requiring closing the block valve (RC-535).

The RO should control PZR Heaters and Spray valves to maintain RCS pressure above 2205 psig. The crew should respond using AOP-019, MALFUNCTION OF RCS PRESSURE CONTROL. The SRO should enter LCO 3.4.11, Condition B for the inoperable PORV, and may enter LCO 3.4.1, Condition A if pressure falls below 2205 psig. The PORV will remain unavailable throughout the scenario.

On cue from the Chief Examiner, Turbine bearing #3 vibration will increase to the alarm point and AOP-006, TURBINE ECCENTRICITY I VIBRATION, will be entered. High bearing vibrations will be reflected on adjacent bearings # 2 and #4. Vibrations will increase to 14 mils and actions in AOP-006 will require the SRO to direct a manual Reactor trip and enter PATH-1. When the crew attempts to trip the reactor, both Reactor Trip pushbuttons will fail and the SRO will enter FRP-S.1, RESPONSE TO NUCLEAR POWER GENERATION/ATWS.

The SDAFW Pump will trip and remain unavailable for the remainder of the scenario.

The AO will be successful in tripping the Reactor locally when directed.

When the crew has transitioned to EPP-4, REACTOR TRIP RESPONSE and on cue from the Chief Examiner, a Small Break LOCA will be inserted.

The LOCA will require a Safety Injection initiation and Phase A isolation, which will fail to automatically actuate. Manual operator actuation will be successful, but three Phase A valves will fail to close and require the RO to manually close these valves from the RTGB. The Control Room HVAC System Train A and Train B will fail to automatically actuate, requiring the BOP to manually align HVAC for Emergency Pressurization Mode. The scenario can be terminated, at the Chief Examiner's discretion, after it is determined that SI termination criteria will not be met. Appendix D NUREG-1021 , Rev. 9, Supp. 1 I Appendix 0 Scenario Outline Form ES-D-1 HLC-08 NRC SCENARIO 4 SIMULATOR SETUP IC/SETUP

IC-604, SCN: 006_Sim_4.

Status board updated to reflect IC-4. PRE-LOADED EVENTS: The following events should occur on the reactor trip:

Event 6: Failure of the Reactor to trip. (A TWS) SDAFW Pump trips.

Event 8: Phase A valves CVC-204B, CCW-739 and SI-855 fail to close on SI actuation.

Event 9: Safety Injection fails to automatically actuate.

Event 10: Control Room HVAC Train A and Train B fail to automatically actuate. EVENTSITRIGGERS INITIATED DURING THE SCENARIO:

Event 1: Increase power to 75%.

Event 2: Loop 1 T HOT fails low.

Event 3: SW flooding from the South SW Header.

Event 4: PZR PORV PCV-456 fails 70% open.

Event 5: High vibration on #3 Turbine bearing which leads to a manual Reactor trip.

Event 7: Small Break LOCA. EXPECTED PROCEDURE FLOWPATH OR COPIES NEEDED: OP-105, Section 8.4.2; OWP-028, T/Deita T 1; AOP-022, Section F; AOP-019; AOP-006; PATH-1, FRP-S.1; EPP-4; FRP-P.1; Supplement D. Appendix 0 NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 4 Event # Page 4 of 31 ----------

Event

Description:

Increase power to 75%. Time Position I Applicant's Actions or Behavior BOOTH OPERATOR:

Event 1 is normal power ascension to 75% lAW OP-105. The crew will brief the event in the classroom prior to entering the simulator and begin the ascension as soon as they take the shift. SRO Begins power ascension using OP-1 05 Section 8.4.2. SRO IF Reactor Engineering has not provided technical guidance, THEN determine the reactivity change required.

SRO Notify the Load Dispatcher that unit load will be increased.

RO T AVG is within 5 of of T REF. RO Monitor the highest operable PR and IR channels on NR-45. Steam Dump controls are set as follows: BOP

Potentiometer set at 7.28 (1020 psig).

In Automatic and T AVG Control. BOP FRVs in AUTO and S/Gs are being maintained at programmed level. BOP IF the EH Turbine Control is in OPER AUTO, THEN verify the Turbine Control is in IMP IN. (Preferred)

RO Check the ERFIS PDCIII Delta Flux monitoring program enabled. BOP Check the Turbine Lube Oil Cooler is maintaining the oil temperature leaving the bearings within the limits of OP-506. BOP The Bulk Auxiliary electrical loads should be on the Unit Auxiliary Transformer lAW OP-603. Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: ......;....-

Scenario # 4 Event # Page 5 of 31 ----------

Event

Description:

Increase power to 75%. Time II Position I Applicant's Actions or Behavior SRO For each power change greater than or equal to 10%, update the power change log in the Reactor Startups/Shutdowns/Trips Book. BOP While increasing power, Generator MVAR loading should be lAW the Robinson Plant Voltage Support and Coordination Procedure.

BOP Verify the Valve Position Limit is adjusted to maximum. IF EH Turbine Control is in OPER AUTO, THEN increase turbine load as follows: BOP

Adjust the SETTER indication using the REF UP pushbutton to the desired load.

Depress the GO and/or HOLD pushbuttons and the REF UP as necessary to continue the load increase.

NOTE: OP-301, Section 8.2.7 Quick Dilution Checklist (shaded area) is included in the following steps, but may be used prior to the commencement of the plant up power. When power is between 55-60%, the crew will start the second MFP. DETERMINE the amount of water to add to the RCS. (The calculate

-2000 gallons of water needed for the dilution to 75%power,basedon Rods at ...;175 steps. Water will be added.in 4-6 dilutions)

.. OBTAIN an independent cneckof .the volume of water. required.

OBTAIN permissionJrom the CRSS OR the SSOto dilute. PLACE the RCS MAKEUP MODE selector switch in DILUTE. Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: -----Scenario # 4 Event # ......;....

____ Page 6 of ....,;3;.,;.1

___ -11 Event

Description:

Increase power to 75%. Time Position I Applicant's Actions or Behavior SETYIC-114, PRIMARY WTR TOTAUZERto the desired quantity.

IFdesired,THENPLACEFCV-114A, PRIMARY WTR FLOW DILUTE MODE, in MAN:ANDadjust Primary Water Flow rate using the UP/DOWN push buttons. . .... Momentarily PLACE the RCS MAKEUP SYSTEM switch to START. VERIFY proper operation VCT/HLDP TK DIV valve. IF any of thebelowconditions occur, THEN momentarily place the RCS MAKEUPSYSTEM switch in.the STOP position:

UnantiCipated Rod>Motion.

Primary Water addition . exceeds the desired value. WHEN desired amount of PYV has been added, THENverify:

FCV-t14A, PW TO BLENDER; doses.

FCY-114B, BLENDED MUTO YCT, closes.

IF inAuto, THEN the operating Primary Water Pump stops.

TheHCSMAKEUPSYSTEM is OFF. ... ... ... . .

VERIFY FCV-114A,PRIMARY WTR FLOW DILUTE MODE is in AUTO.

PLACEtheHCSMAKEUP MODE switch in AUTO.

Momentarily Pl.ACE RCS MAKEUP SYSTEM switch to START. ... . RECORD,inAUTO LOG,* as .indicated*

by PRIMARY WATER TOTALlZER,.YIC-114 total amount of PW added during the dilution . .. MONITOR pqrameters for the.expected*change in reactivity AND informtheCRSS OR theSSO the results pfthedilutiort

.. Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: ...;....-Scenario # 4 Event # _2 _____ Page 7 of _3;:;.1:"'-

__ Event

Description:

Loop 1 T HOT Fails Low. Time II Position i Applicant's Actions or Behavior BOOTH OPERATOR:

When directed by the Chief Examiner, insert Event 2, Loop 1 T HOT failure. EVENT INDICATIONS:

APP-003-A4; RC LOOPS I1T DEV APP-003-A6; RCS HIILO TAVG APP-003-B4; RC LOOPS TAVG DEV TR-412 Pen 1, I1T (RED) pegged low. TR-41211T Power fails low. RO Recognizes that instrument has failed and references APP-003-A4.

Recommends removing the instrument from service. SRO Reviews, briefs and directs taking Loop 1 T HOT instrument out of service using OWP-028, T/LlT1. Perform OWP-028, T/LlT1 actions to remove channel from service. (APP-036-L 1; will be received when Hagan Rack door is opened.) BOP The following alarms will be received when the bistables are tripped:

APP-003-B6; OVERPOWER Ll T

APP-005-D5; OTLlT/OPLlT TURBINE RUNBACK ROD STOP

APP-003-C6; OVERTEMP Ll T Review ITS for applicable LCOs:

Table 3.3.1-1, #5, 6 -Condition E; Place channel in Trip within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . SRO

Table 3.3.2-1, # 1.f -Condition D; Place channel in Trip within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

Table 3.3.2-1, # 4.d & 6.b -Condition H; Verify interlock is in required state for existing unit condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # --4 Event # 3 Page 8 of 31 Event

Description:

SW flooding from the South SW Header. Time II Position II Applicant's Actions or Behavior BOOTH OPERATOR:

When directed by the Chief Examiner, insert Event 3, SW Flooding in the Intake Bay from the South SW Header. EVENT INDICATIONS:

APP-008-F7; SOUTH SW HDR LO PRESS APP-008-F8; NORTH SW HDR LO PRESS APP-008-E7; S SW HDR STRAINER PIT HI LEVEL APP-008-E8; N SW HDR STRAINER PIT HI LEVEL APP-002-A8; HVH-1 WTR OUTLET LO FLOW APP-002-B8; HVH-2 WTR OUTLET LO FLOW APP-002-C8; HVH-3 WTR OUTLET LO FLOW APP-002-D8; HVH-4 WTR OUTLET LO FLOW APP-008-D7; SSW HDR STRAINER PIT HI-HI LVL (Delayed)

APP-008-D8; N SW HDR STRAINER PIT HI-HI LVL (Delayed)

SW Booster Pump "B" trips due to low suction pressure.

BOP Recognizes a Loss of Service Water has occurred and performs Immediate Actions of AOP-022, LOSS OF SERVICE WATER. NOTE: The crew will place the Turbine ramp on hold while this malfunction is addressed.

SRO Enters AOP-022, LOSS OF SERVICE WATER. Immediate Action Step: BOP AND APP-008-E8Extinguished. (NO)

Closes valves.V6-12B and V6-12C . SRO Transitions to Section F. RO/BOP Makes PA announcement for entry into AOP-022. Crew Evaluate Control Room Indications and perform local inspections to determine source of leakage. Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 4 Event # --3 Page 9 of 31 Event

Description:

SW flooding from the South SW Header. Time I Position i Applicant's Actions or Behavior BOOTH OPERATOR:

Report that water is gushing up through the deck plates above the South Service Water header. If the crew has closed both cross-connect valves and V6-12A, then report water has stopped, but was from the South header. BOP Check SW source of flooding. (YES) BOP Check SW leak on the South Header. (YES) Verify the following:

SW Pump "C" Running. (YES)

SW Pump "D" Running. (NO, will start pump) BOP 0 Will receive APP-008-E4, ES & E6 alarms

SW Pump "A" Stopped. (NO, will stop pump)

SW Pump "B" Stopped. (YES) Evaluate SW Header Pressure:

SRO/BOP

Check South SW pressure Decreasing. (YES)

Check North SW pressure Stable or Increasing. (YES) NOTE: With Service Water Pumps "A" AND "B" isolated, EDG "A" is inoperable.

ITS 3.S.1 requires SR 3.S.1.1 to be performed within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . With low flow to all CV HVH units, LCO 3.6.6 applies for both CV Cooling Trains inoperable.

The crew may start SWBP "B" using APP-002-ASIBSICSIDS guidance.

BOP Close V6-12A (APP-008-E4/ES/E6/F8 will clear) Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: --.;...-Scenario # 4 Event # ____ Page 10 of ...,;3;;..;,1

___ -11 Event

Description:

SW flooding from the South SW Header. Time II Position I Applicant's Actions or Behavior BOP Verify SW-S51 and SW-S57 closed. BOOTH OPERATOR:

When requested, report that SW-851 and SW-857 are closed. (Not modeled on simulator)

SRO/BOP Check Flooding status stopped. (YES) BOOTH OPERATOR:

Report water is no longer gushing up above the South SW header. BOP Check North SW header pressure>

40 psig. (YES) SRO Remove Control Power fuses from breakers for SW Pumps "A" & "B". BOOTH OPERATOR:

Rack out the breakers for Service Water Pumps "A" and "B" on 480V Bus E-1. When requested, report that leak is from the connection of SW Pump "A" and the 30 inch header. Determine if a SW Booster Pump should be started: SRO/BOP

Check SW Booster pumps all stopped. (YES)

Start one SW Booster Pump. (APP-002-AS/BS/CS/DS clear). BOP Check any CW Pump running. (YES) Determine if adequate seal water is available to CW:

APP-00S-E4, CW PMP A SEAL WTR LOST extinguished.

BOP

APP-00S-E5, CW PMP B SEAL WTR LOST extinguished.

APP-00S-E6, CW PMP C SEAL WTR LOST extinguished. (YES, ALL extinguished)

Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: -:...-Scenario # 4 Event # 3 Page 11 of 31 Event

Description:

SW flooding from the South SW Header. Time II Position II Applicant's Actions or Behavior Determine maximum allowable CCW temperature as follows: RO

Check RCS temperature 350 degrees F. (NO)

Maintain CCW Heat Exchanger outlet temperature indicated on TI-607 less than or equal to 105 degrees F. Perform the following:

Inspect the area of the leak. SRO

Report findings to the SSO.

Identify and isolate the source of the SW leak. SRO Contact Maintenance to install temporary pumps to dewater Service Water pits. Contact Engineering to perform the following:

SRO

Evaluate operability of equipment affected by flooding.

Provide corrective actions for flooding.

Refer to ITS for any applicable LCOs.

LCO 3.6.6, Condition D -Restore one containment cooling train to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . (Will only be in this LCO until a SW Booster Pump is started) SRO

LCO 3.7.7, Condition A -Restore SWS train to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . (This LCO has already been entered due to the SWBP being out of service)

LCO 3.8.1, Condition B -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 . (Cascaded LCO from SW NOT available to EDG "A") SRO Implement the EALs. SRO Return to procedure and step in effect. Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: --:...._ Scenario # 4 Event # _4..:..-____ Page 12 of _3 ... 1 ___ -i1 Event

Description:

PZR PORV PCV-4S6 fails 70% open. Time Position II Applicant's Actions or Behavior BOOTH OPERATOR:

When directed by the Chief Examiner, insert Event 4, PZR PORV PCV-456 fails 70% OPEN. EVENT INDICATIONS:

APP-003-C3;PRT HI PRESS APP-003-D6;PZR PORVISAFETY VLV OPEN APP-003-E6;PZR PORV LN HI TEMP APP-003-F6;PZR SAFETY VLV LINE HI TEMP APP-003-D8;PZR CONTROL HIILO PRESS RO Recognizes PORV is OPEN and takes Immediate Actions of AOP-019, MALFUNCTION OF RCS PRESSURE CONTROL. SRO Enters AOP-019, MALFUNCTION OF RCS PRESSURE CONTROL. Immediate Action Step:** Determine.if*PZR PORVs should be CLOSED:* RO

Check PZR Pressure less than 2335PSIG. (YES)

Verify both PZR PORVs CLOSED. (NO) IF anyPZR PORVcan NOT be CLOSED,THEN close its PORV BLOCK valve. . Immediate Acti()nStep:

RO ControlHeaters and Spray valves torestore.HCS Pressure to desired corttrolband; RO Check PZR Pressure under operator control. (YES) RO Check PC-444J, PZR PRESSURE operating in AUTO. (YES) RO Check RCS pressure < required for current plant conditions. (YES) Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: ....;...-Scenario # 4 Event # 4 Page 13 of 31 Event

Description:

PZR PORV PCV-456 fails 70% open. Time II Position Applicant's Actions or Behavior Continuous.

Action<Step:

.. RO Check PZR pressure less than 2205 PSIG. IF pressure decreases to <:: 2205 PSIG, THEN restore pressure within 2. hours Or be in MODE 2 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . RO Check BOTH PZR Spray valves CLOSED. (YES) RO Check CVC-311, AUX PZR SPRAY valve CLOSED. (YES) RO Check APP-003-F8, PZR LO LVL HTR OFF & L TDN SECURE extinguished. (YES) Determine Heater Capacity:

SRO/RO

Contact Maintenance and Engineering to check PZR Heater capacity.

Check PZR Heater capacity REDUCED. (NO) BOOTH OPERATOR:

When requested, inform the crew that heater capacity has NOT changed since the last Refueling Outage test. RO Check PZR Pressure stable or trending to required value. (YES) SRO Implement The EALs. SRO Contact I&C To Make Repairs To The PZR Pressure Control System. Review ITS For Applicable LCOs: SRO

LCO 3.4.11, Condition B, Close Block valve within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND

Remove power within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Op Test No.: Event

Description:

Operator Action Form ES-D-2 Scenario # 4 Event # 5&6 Page 14 of 31 High vibration on #3 Turbine bearing which leads to a manual Reactor trip. Failure of the Reactor to trip. (ATWS) SDAFW Pump Trips. Time Position II Applicant's Actions or Behavior BOOTH OPERATOR:

When directed by the Chief Examiner, insert Event 5, Turbine bearing #3 vibrations will increase above the alarm setpoint and require manual Reactor and Turbine trips. EVENT INDICATIONS:

APP-OOS-AS; TURBINE SUPERVISORY INSTRUMENT (Will reflash as each bearing vibration increases greater than 7 mils) Turbine Generator Supervisory Recorder and Vibration module bearings in alarm. BOP Recognizes alarm, monitors vibration recorder and references APP-OOB-AB. BOP

Verify lube oil cooler discharge temperature between 115-125 degrees F. (YES) BOP

If turbine bearing temperature is > 225 degrees F, trip the turbine. (NO) SRO Enters AOP-006, TURBINE ECCENTRICITY

/ VIBRATION.

BOP Check Turbine Speed 600 RPM. (NO, Go To Step 4) Continuous Action . Step: BOP Check Bearing Vibration Levels on theTURBINE GENERATOR SUPERVISORY RECORDER less than 14.0 MILS. (YES) NOTE: At this time, vibration level is less than 14 mils but Step 4 RNO will be implemented as vibration increases.

Attempt to decrease or stabilize vibration by at least one of the following methods: BOP Vary load (MW and/or VARS) or turbine speed. *

Vary Hydrogen Side or Air Side Seal Oil temperatures.

Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Op Test No.: .....;...-

Event

Description:

Operator Action Form ES-D-2 Scenario # 4 Event # _5;;;...;;.;.&..;;.6

___ Page 15 of _3_1 ___ --11 High vibration on #3 Turbine bearing which leads to a manual Reactor trip. Failure of the Reactor to trip. (ATWS) SDAFW Pump Trips. Time II Position i Applicant's Actions or Behavior

Vary Turbine Lube Oil cooler discharge temperature.

Increase Exciter Air discharge temperature.

BOOTH OPERATOR:

As a Security Officer patrolling the Protected Area, provide input to the crew that increased vibration is noted on the Turbine Deck and adjacent to the Control Room. NOTE: At this time, vibration level on #3 bearing will have increased to greater than 14 mils and Step 4 RNO actions will be implemented.

Continuous Action Step: Check Bearil'1g.Vibration LevelsoritheTURBINEGENt=RATOR SUPERVISORY RECORDER less than 14;0 MILS. (NO) SRO IF vibration is*felt in theControlRoom,THEN perform one of the following:

IF the REACTORTRIP FROM TURBBLOCK P-7 permissive light is extinguished, THEN trip the Heactbr AND GoTo PATH-1. (YES) SRO Directs the RO to manually trip the Reactor and perform the immediate actions of PATH-1. Immediate J\,ction*

Step: Check REACTOR TRI Pasfollows:

Reactor trip main and bypass breakers OPEN. (NO) RO

Rod Position indication ZERO. (NO)

Rod Bottom Lights I LLUMINATEO> (NO)

Neutron Flux DECREASING. (NO) Appendix D NUREG-1021 , Rev. 9, Supp. 1 Appendix D Op Test No.: --=--Event

Description:

Operator Action Form ES-D-2 Scenario # 4 Event # 5 & 6 Page 16 of 31 ---------

High vibration on #3 Turbine bearing which leads to a manual Reactor trip. Failure of the Reactor to trip. (ATWS) SDAFW Pump Trips. Time I Position II Applicant's Actions or Behavior Immediate Action Step: Perform the following:

Depress both Reactor Trip*pushbuttons.

If Reactor Trip breakerswillnot.open,.

then perform the follQWing:

RO/SRO f nsert.control.

rods. *

Dispatch an operator to theMG Set Room to trip Reactor Trip Breakers "A" and "B" AND MGSet Generator Circuit Breakers "A" and "B".

Dispatch an operator to 480V Busses 2B and 3 to trip Rod Drive MG SetBrs.akers "A".and "B", NOTE: SRO will notify the Inside and Outside Auxiliary Operators while Control Room operators take appropriate actions. 3 minutes after being contacted, OPEN the RTBs and MG set breakers.

Immediate Action Step: Check Turbine Trip as follows: BOP

Both Turbine Stop valves closed. (NO) OR

All Governor (NO) Perform the following:

BOP

Manually trip the Turbine by simultaneously depressing the THINK and TURBINE TRIP Pushbuttons BOP Verify All AFW Pumps running. (NO, SDAFW Pump will NOT start and APP-007-F5, SD AFW PMP LO DISCH PRESS TRIP will illuminate)

Appendix D NUREG-1021 , Rev. 9, Supp. 1 Appendix D Op Test No.: --:...-Event

Description:

Operator Action Form ES-D-2 Scenario # 4 Event # 5&6 Page 17 of 31 High vibration on #3 Turbine bearing which leads to a manual Reactor trip. Failure of the Reactor to trip. (ATWS) SDAFW Pump Trips. Time II Position II Applicant's Actions or Behavior Verify Charging flowpath established as follows: RO

CVC-310B, LOOP 2 COLD LEG CHG OPEN.

HIC-121, Charging Flow Controller demand at 0%. RO Verify Two Charging Pumps running at full speed. RO Verify Boric Acid Pump aligned for blend running. RO Verify MOV-3S0, BA TO CHARGING PMP SUCT open. RO Check flow on FI-110, BORIC ACID BYPASS FLOW indicated.

RO Verify Charging Flow to RCS on FI-122A BOP Verify CONTAINMENT VENTILATION ISOLATION initiated.

NOTE: It is expected that if the CV Ventilation Signal has not been initiated, the operator will take R-11 or R-12 high voltage pushbutton to OFF and return to ON to initiate the signal. This can be verified by the 2 Amber lights ILLUMINATED below the Radiation Monitoring System panel labeled "CV Ventilation Isolation Signal Relay V-1 and V-2." Check SI initiated. (NO) RO IF an SI Signal occurs, THEN verify auto start of all SI equipment using Supplement L while continuing with this procedure.

Check if the following trips have occurred:

RO/BOP

Reactor Trip. (YES)

Turbine Trip. (YES) Appendix D NUREG-1021 , Rev. 9, Supp. 1 Appendix D Op Test No.: ......;...-

Event

Description:

Operator Action Form ES-D-2 Scenario # 4 Event # _5;;..&;;;.;....;.6

___ Page 18 of _3.;,..1 ___ ---lI High vibration on #3 Turbine bearing which leads to a manual Reactor trip. Failure of the Reactor to trip. (ATWS) SDAFW Pump Trips. Time i Position i Applicant's Actions or Behavior Continuous Action Step: Check if Reactor is subcritical:

RO

Check Power. Range indicatiohless than 5%. (YES)

Check Intermediate Range indication negative SUR. (YES, Go To Step. 24) RO Check IRPI has less than two rods stuck out. (YES) Stop the RCS Boration:

Verify MOV-35G closed.

Verify control switch for Boric Acid pump aligned for blend in AUTO. RO

Check emergency boration performed using MOV-35G flowpath.

Notify Engineering to evaluate:

RCP Bearing temperatures

No.1 seal leakoff temperatures and flowrates . Check emergency boration performed using RWST flowpath and it is RO desired to align Charging Pump suction to the VCT. (NO, Go To Step 25.i) RO Control Charging Pump speed to control PZR Level. RO Reset SPDS and Initiate monitoring of Critical Safety Function Status Trees. SRO Return to procedure and step in effect. Appendix D NUREG-1G21, Rev. 9, Supp. 1 Appendix D Op Test No.: --:....-Event

Description:

Operator Action Form ES-D-2 Scenario # 4 Event # .....;5;;...;&;;;..;;..6

___ Page 19 of _3;;.,;1 ___ -i1 High vibration on #3 Turbine bearing which leads to a manual Reactor trip. Failure of the Reactor to trip. (ATWS) SDAFW Pump Trips. Time i Position I Applicant's Actions or Behavior SRO Directs entry at the beginning of PATH-1. IMMEDIATE ACTION STEP: RO Reactor Tripped. (YES) BOP IMMEDIATE ACTION STEP: Turbine Tripped. (YES) IMMEDIATE ACTION STEP: BOP E-1 AND*E-2 energized. (YES) IMMEDIATE ACTION STEP: RO 0 Sllnitiated

.. (NO) 0 Sllnitiation Required. (NO) RO Verify two Charging Pumps running. (YES) SRO Transition to EPP-4, REACTOR TRIP RESPONSE.

Continuous Action Step: Determine if procedure exit is warranted:

SRO

Check attack on .RNPsite in progress. (NO)

Check a total loss of SW .OR Loss of Lake Robinson Dam integrity inprogress.

(NO, Go to Step 2) Continuous Action Step: RO Check SI signal initiated. (NO, Go to Step 4) IF SI initiation occurs during this procedure, THEN Go to PATH-1, Entry Point.A. (Page 21 ) Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Op Test No.: .-;...-Event

Description:

Operator Action Form ES-D-2 Scenario # 4 Event # ...,;5;;..&;;.;..;;;.6

___ Page 20 of ...,;3;;..;.1

___ -l 1 High vibration on #3 Turbine bearing which leads to a manual Reactor trip. Failure of the Reactor to trip. (ATWS) SDAFW Pump Trips. Time Position I Applicant's Actions or Behavior SRO Reset SPDS and initiate monitoring of CSFSTs. CREW Open Foldout A.

RCP Trip criteria.

IF BOTH conditions are met, THEN stop all RCPs: (NO) ° SI Pumps -AT LEAST ONE RUNNING AND CAPABLE OF DELIVERING FLOW TO THE CORE ° RCS Subcooling

-< 35 degrees F [55 degrees F]

SI actuation criteria.

IF EITHER condition occurs, THEN Actuate SI and Go To PATH-1, Entry Point A: ° RCS Subcooling

-< 35 degrees F [55 degrees F] ° PZR Level-CAN NOT BE MAINTAINED>

10% [32%]

MSR Isolation criteria.

IF ANY Purge OR Shutoff Valve does not indicate fully closed, THEN place the associated RTGB Switch to CLOSE. RO Check RCS temperature stable or trending to 547 F. (YES) SRO Transitions to Step 12, based on SW Header pressure between 40-50 PSIG. Continuous Action Step: Determine Feedwater status:

Check RCSaverage temperature less than 554 OF. (YES) BOP Verify FW REG VALVEs CLOSED. (YES) *

Establish FW bypass flow to rriaintainlevel in intact S/Gs between 39% and 50%. (Will stopMDAFW pumps and throttle open* ALL S/GBypass valves to control SIG level) RO Check All Control Rods fully inserted. (YES) Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix 0 Operator Action Form ES-D-2 Op Test No.: Scenario # --4 Event # 7,8,9&10 Page 21 of 31 Event

Description:

Small Break LOCA, Phase A fails to actuate, SI fails to actuate, CR HVAC fails to actuate. Time I Position Applicant's Actions or Behavior BOOTH OPERATOR:

When directed by the Chief Examiner, insert Event 7, Small Break LOCA. EVENT INDICATIONS:

Reactor Trip Breakers open PZR Level and Pressure decreasing RR-1 Recorder Point #11 for R-12 in alarm (later) Phase "A" valves will not close automatically Control Room HVAC Exhaust Dampers are not closed. HVE-19A did not start; HVE-16 did not stop. NOTE: The following actions may be performed using OMM-022 guidance:

Safety Injection fails to actuate on the LOCA, the crew will manually initiate SI which will start all SI and RHR pumps, but SI-870A and 870B valves will NOT open. These valves must be opened manually and at least one valve must be opened to provide an injection path. Phase A fails to actuate, the crew will manually actuate Phase A, but valves CCW-739, CVC-204B and SI-855 will NOT close on manual actuation of the pushbutton.

They will require manual closure from the RTGB control switches.

CR HVAC will fail to shift to PRESSURIZATION MODE. The crew will manually start HVE-19A and HVE-16 will have to be manually stopped. CR-D1 A-SA and D1 B-SB will close -5 seconds after HVE-16 is stopped. CREW Open Foldout A.

RCP Trip criteria.

IF BOTH conditions are met, THEN stop all RCPs: (YES) 0 SI Pumps -AT LEAST ONE RUNNING AND CAPABLE OF DELIVERING FLOW TO THE CORE 0 RCS Subcooling

-< 35 degrees F [55 degrees F] RO Verify Phase A Isolation valves are closed. (NO, must be manually actuated using the pushbutton)

Appendix 0 NUREG-1 021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 4 Event # 7,8,9&10 Page 22 of .....;3;;..;.1

___ ..,1 Event

Description:

Small Break LOCA, Phase A fails to actuate, SI fails to actuate, CR HVAC fails to actuate. Time I Position Applicant's Actions or Behavior NOTE: Valves CCW-739, CVC-204B, SI-855 will NOT close on manual actuation of the pushbutton.

They will require manual closure from the RTGB control switches.

BOP Verify FW Isolation valves are closed. (YES) BOP Verify both FW pumps are tripped. (YES) BOP Verify both MDAFW pumps are running. (YES) NOTE: Crew may elect to reset SI in order to control AFW and S/G levels. BOOTH OPERATOR:

If the crew requests for the vacuum breakers to be opened to assist in turbine coast down, report that the Turbine Engineer requests that they allow the turbine to coast down normally as long as lube oil pressure remains above 5 psig. BOP If additional Feedwater is required, start the SDAFW pump. (Tripped and will NOT restart) RO Verify 2 SI pumps running. (YES) RO Verify Both RHR pumps running. (YES) RO Verify SI valves are properly aligned. (NO, SI-870A and 870B were manually aligned) RO At least 1 CCW pump is running. (YES) BOP All SW and SW Booster pumps running. (NO) Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: .-;...-Scenario # 4 Event # 7,8,9&10 Page 23 of _3.:,..1:.....-

__ ---l 1 Event

Description:

Small Break LOCA, Phase A fails to actuate, SI fails to actuate, CR HVAC fails to actuate. Time i Position ! Applicant's Actions or Behavior BOP Attempt to start all SW and SW Booster pumps. (NO, SW Booster Pump "A" and SW Pumps "A" & "B" are unavailable)

BOP North OR South SW Header Lo Pressure alarm illuminated. (NO) RO Verify CV Fans HVH-1, 2, 3, 4 running. (YES) RO Verify IVSW initiated. (YES) BOP Verify CV Ventilation isolation. (YES) BOP Verify Control Room Vent aligned for Pressurization Mode. (NO) NOTE: HVE-19A will be manually started and HVE-16 will have to be manually stopped. CR-01 A-SA and 01 8-S8 will close -5 seconds after HVE-16 is stopped. NOTE: CSFSTs will indicate an ORANGE PATH on RCS INTEGRITY at some point while the crew is performing actions in PATH-1. At the discretion of the Chief Examiner and when the crew transitions to FRP-P.1, the scenario can be terminated.

If needed, actions for FRP-P.1 begin on page 29. BOP Verify both EDGs running. (YES) ContinuoOs .Action BOP Restart battery chargers within 30 minutes of power loss using OP-601. RO Continuous Action. Step: CV Pressure has remained below 10 psig. (YES) Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 4 Event # 7,8,9&10 Page 24 of 31 -----il Event

Description:

Small Break LOCA, Phase A fails to actuate, SI fails to actuate, CR HVAC fails to actuate. Time ! Position I Applicant's Actions or Behavior BOP Automatic Steam Line Isolation Initiated. (NO) BOP Automatic Steam Line Isolation Required. (NO) BOP Locally open breaker for HVS-1 at MCC-5. RO RCS pressure>

1350 psig. [1250 psig] (NO) RO SI Flow Verified. (YES) RO RCS Pressure Greater than 125 psig. (YES) BOP At least 300 GPM AFW flow available. (YES) BOP Verify AFW valves properly aligned. BOP Control AFW flow to maintain S/G levels between 8% [18%] and 50%. NOTE: The crew may reset SI and secure a MDAFW Pump to control S/G level. RO RCP Thermal barrier cooling water HilLo flow alarms illuminated. (NO) BOP Place Steam Dump Mode Switch to Steam Pressure.

RO RCS Temp stable at OR trending to 547 degrees F. (NO) RO RCS temperature>

547 degrees F. (NO) BOP Attempt to limit cooldown.

Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 4 Event # 7,8,9&10 Page 25 of _3;;:.,.1:...-

__ --11 Event

Description:

Small Break LOCA, Phase A fails to actuate, SI fails to actuate, CR HVAC fails to actuate. Time II Position II Applicant's Actions or Behavior BOP If RCS cooldown continues and is not due to SI flow, then close MSIVs and MSIV bypasses.

RO PZR PORVs closed. (NO) RO RCS pressure>

2335 PSIG. (NO) RO Close PZR PORVs. RO PZR PORVs closed. (NO) RO Close PORV blocks. RO PORV blocks closed. (YES) RO PZR Spray and Aux Spray valves closed. (YES) RO At least 1 RCP running. (NO) BOP Any S/G with uncontrolled depressurization. (NO) BOP Any S/G Completely Depressurized (NO) BOP R-19s, R-31 sand R-15 Rad levels normal (YES) BOP R-2, R-32A, R-32B Rad levels normal (YES) RO CV Pressure Normal (NO) Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 4 Event # 7,8,9&10 Page 26 of 31 ----....,1 Event

Description:

Small Break LOCA, Phase A fails to actuate, SI fails to actuate, CR HVAC fails to actuate. Time II Position I Applicant's Actions or Behavior RO Reset SPDS and initiate monitoring of CSFSTs. (Entry Point C) CREW Open Foldout B. BOP Request periodic activity samples of all S/Gs. RO At least 1 RCP running. (NO) BOP Any S/G with uncontrolled depressurization in progress. (NO) BOP Control AFW flow to maintain S/G levels between 8% [18%] and 50%. BOP Any S/G with uncontrolled level increase. (NO) BOP R-19s, R-31 sand R-15 Rad levels normal. (YES) RO PZR PORVs closed. (NO) RO RCS pressure>

2335 PSIG. (NO) RO Close PZR PORVs. RO PZR PORVs closed. (NO) RO Close PORV blocks. RO Open at least one PORV block unless closed to isolate an open PZR PORV. Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: ......;...-

Scenario # 4 Event # 7,8,9&10 Page 27 of .....:3::....:,1

___ -l 1 Event

Description:

Small Break LOCA, Phase A fails to actuate, SI fails to actuate, CR HVAC fails to actuate. Time Position II Applicant's Actions or Behavior CONTINUOUS ACTION STEP RO If PZR PORV opens on high pressure, then verify reclosure at or below2335 psig. Close PORV blocks as necessary.

RO Reset SI. CREW CONTINUOlJSACTIONSTEP:

Ifoffsite poweris lost,then restart emergency safeguard equipment.

RO Reset CV Spray. RO Reset Phase A and Phase B. RO Establish Instrument Air to CV. IF compressor not running, THEN start compressor.

BOP Offsite power available to Charging Pumps. (YES) RO At least 1 Charging Pump running. (YES) RO Establish charging flow as necessary.

RO CV Spray Pumps running. (NO) RO RCS Subcooling greater than 35 [55] degrees F. (NO) RO When below 10-10 amps, then energize Source Range detectors and monitor recorder.

Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix 0 Operator Action Form ES-D-2 Op Test No.: ......;....-

Scenario # 4 Event # 7,8,9&10 Page 28 of ....,;3;..;,1

___ -l 1 Event

Description:

Small Break LOCA, Phase A fails to actuate, SI fails to actuate, CR HVAC fails to actuate. Time II Position I Applicant's Actions or Behavior RO RCS pressure greater than 275 psig [400 psig] (YES) RO RCS pressure stable or increasing (NO) BOP Any S/G with uncontrolled depressurization in progress (NO) RCS pressure increasing RO (YES) Return to PATH-1, Entry Point C. (page 25) (NO) Continue below. BOP E-1 and E-2 energized by offsite power (YES) BOP Starting air receivers re-pressurized to unloaded EDGs (YES) BOP Stop the unloaded EDGs RO Supplement 0 components capable of recirc (YES) BOP Aux Building radiation normal (YES) RO RCS pressure greater than 275 psig [400 psig] (YES) BOP Obtain RCS boron, activity, and Hydrogen samples CREW Transition to EPP-8, POST LOCA C/D AND DEPRESSURIZATION.

Appendix 0 NUREG-1 021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: --Scenario # 4 Event # 7,8,9&10 Page 29 of 31 ..;;..----11 Event

Description:

Small Break LOCA, Phase A fails to actuate, SI fails to actuate, CR HVAC fails to actuate. Time II Position i Applicant's Actions or Behavior FRP-P.1, RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK actions begin here. Continuous Action Step: BOP Check CST level less than 10%. (NO) IF CST level decreases to .Iess than 10%, THEN perform Step 2. Determine If RCS Cooldown Is Due To A Large Break LOCA: BOP

RCS pressure is less than 275 PSIG [400 PSIG] (NO) AND

RHR flow on FI-605 greater than 1200 GPM. (NO) BOP Check RCS Cold leg temperature decreasing. (NO, skip the next 5 Steps) (YES, continue below) Attempt to Stop RCS cooldown:

Verify STEAM LINE PORVs CLOSED. RO/BOP

Verify Condenser Dumps CLOSED.

Check RHR system aligned for core cooling. (NO) BOP Check any S/G intact. (YES) BOP Check level in at least one S/G > 8% [18%]. WHEN level in at least one S/G is> 8% [18%], THEN perform Step 8. BOP Control Feed flow to intact S/G to stop RCS cooldown.

Identify and Isolate faulted S/G:

Any S/G pressure decreasing in an uncontrolled manner. (NO) BOP OR

Any S/G completely depressurized. (NO) Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 4 Event # 7,8,9&10 Page 30 of 31 "';;";'---'-'1 Event

Description:

Small Break LOCA, Phase A fails to actuate, SI fails to actuate, CR HVAC fails to actuate. Time Position I Applicant's Actions or Behavior Check PORV block valves available.

RO

Power available. (YES, Power is available to one block valve)

At least one open. (YES) Continuous*

Action* Step:

Check L TOP in service. (NO) RO

CheckRCSpressure

<2335PSIG. (YES)

VerifyPORVs CLOSED. (NO, PCV-455C is closed to isolate PCV-456) 0 Verify associated PORV block valve is closed. RO Check SI Pumps running. (YES) Determine if SI can be terminated.

RO

Check RCS subcooling

> 85 degrees F [105 degrees F]. (NO) RO Check ALL RCPs stopped. (YES) Appendix D NUREG-1021, Rev. 9, Supp. 1 HLC-08 NRC SCENARIO 4 TURNOVER SHEET POWER LEVEL: 50%, 150 MWO/MTU.

Returning to RTP following a short Maintenance Outage. BORON CONCENTRATION:

1285 ppm EQUIPMENT UNDER CLEARANCE:

SW Booster Pump "A" is Out-Of-Service for Motor Coupling Alignment.

o LCO 3.7.7-A has been entered and is in hour 18 of a 72 TSAS. o Expected return is within -18 hours. EQUIPMENT STATUS:

Main Turbine Vibration for #2, 3 and 4 bearings is elevated.

INSTRUCTIONS FOR THE WATCH:

Increase power to 75% RTP. Appendix D NUREG-1 021, Rev. 9, Supp. 1

ML101970333

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