ML051400362

Draft - Section C Operating (RO & SRO) (Folder 2)

ML051400362
Person / Time
Site:	FitzPatrick  (DPR-059)
Issue date:	01/25/2005
From:	Berry P FitzPatrick
To:	Conte R Operations Branch I
Conte R
References
50-333/05-301
Download: ML051400362 (51)

Text

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JAMES A. FITZPATRICK NUCLEAR POWER PLANT NRC INITIAL LICENSE EXAMINATION SCENARIO 1 I

17 MAY 2005 I

TITLE:

SCENAFUO NUMBER:

NEW PATH:

LOI-05-01 NRC EXAMINATION SCENARIO 1, TORUS RUPTURUAWS, EOP3/4/5 SCENARIO NEEDS TO BE RESNAPPED WITH STABLE INITIAL CONDITIONS INVESTIGATE FAILURE OF RB-TORUS VACUUM BREAKER ANNUNCIATOR NEED TO REVALIDATE THE REVISIONS FROM THE OPS VALIDATION I

I CANDIDATES I

CRS SRO wth command

$NO Primary At The Controh SNOl Rimay09-hSOperato r LO1 05-01 NRC Examination Scenario 1 Page 1 of 20

RECORD OF CHANGES SOURCE OF BRIEF DESCRIPTION OF DATE CHANGE CHANGE INITIATOR REVIEWED 1\\18/05 New New Scenario DeVercelly Binkley LO1 05-01 NRC Examination Scenario 1 Page 2 of 20

A. -

TITLE:

LOI-05-01 NRC EXAMINATION SCENARIO 1, TORUS RUPTURE/ATWS, EOP-3/4/5 B.

SCENARIO SETUP:

1. Initial Protected IC 132

2. Special Instructions:

a. Plant operating normally at 100% CTP

b. "A" RHR in Torus Cooling Mode with "A" RHR and "A" RHWSW pumps in service.

c. "A" EHC pump in service

3. Preset Conditions:

a. TRIGGER 2, SW04:A, RHWSW Pump A Trip

b. TRIGGER 4, NM14:C, APRM C Failure as is at 100%

c. TRIGGER 7, RHlO:A, RHR Pump Suction Line Break, 50% over 600 seconds

d. Preset, RD22:A and B, E and W SDV Hydraulic Block, 60%

e. Preset, SL03:A and 8, SLC pump A and B Relief Valve Lift.

f. TRIGGER 9, SLOl :A and B, SLC pump A and 6 Breaker Trip

g. TRIGGER 10, TC02:B, B EHC Pump Trip

h. TRIGGER 12, TC02:A, "ALPHA" EHC PUMP

4. Consumable Forms and Procedures:

+ ST-208, Control Rod Operability For Partially Withdrawn Control Rods, Pre-Marked up for performance

+ AOP-9, Loss of Primary Containment

+ AOP-1, Reactor Scram LO1 05-01 NRC Examination Scenario 1 Page 3 of 20

C.

SCENARIO

SUMMARY

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The scenario will begin with the plant operating normally at 10046 Core Thermal Power. HPCI surveillance testing has just been completed and the Torus Cooling Mode of RHR is to be secured. During the shutdown of the Torus Cooling Mode, the "A" RHR/SW pump will trip. Dispatch of the NPO will produce a local report of "A" RHR/W pump breaker charring. The CRS will Ware the RHR/SW Subsystem inoperable. Per Reactor Engineer's guidance, a power reduction to 95% will then be amnenced for performance of ST-206. During the power reduction, "C" APRM will not respond as expected. The APRM will be declared inoperable and bypassed. A NPO performing rounds will report a sizable EHC leak in the running "A" EHC pump discharge filter. The crew will swap the running EHC pumps isolating the leak. A rupture in the Torus shell will then start a slow reduction in Torus Water Level. AOP-9 may be entered momentarily resulting in immediite diredion to enter EOP4/EOP-5. EOP4 will be entered on low Torus water level and EOP-5 will be entered on High Sump/Floor Water Level in the Crescent Area. Loc=al investigation will reveal that the leak is isolable and isolation actions will commence. Before Torus Water Level reaches 10.75 feet HPCI will be tripped and a manual scram inserted. Shorlly after the manual scram occurs, the leak will be reported W e d. The manual Scram will result in a power reduction to 40-50% due to a blockage in the SDIV(s). EOP-2 will be entered then exited to EOP-3 resulting in a start of either SLC pump. SLC injection will fail resulting in a manual start of the other SLC pump which will also fail. The Level/Power Control contingency will be exercised by first terminating and preventing injection sources followed by re-injection at a reduced RPV water level. A loss of the remaining EHC pump will mutt in a turbine trip and a loss of the bypass valves shortly thereaffer. This will force transitioning pressure control to the SRV's and trending the approach to the Boron Injection Initiation Temperature (BUT). If BIIT is reached, another Terminate and Prevent will result in RPV water level control at an even lower level. Timety action to complete rod insertion may avoid exceeding BIlT. The control rod insertion success path will require resetting the scram signal, draining the SDIV(s) and re-imerting a manual scram. contrd rod insertion while the SDIV's are draining will occur.

Upon insertinq the second manual scram, all control rods will be reported full-in and the scenario will be terminated.

Shift Turnover Operating nonnally at 100% CTP; RHR Loop "Alpha" in Torus Coding Mode; H W Surveillance Testing recently completed successfully; Torus Cooling needs to be secured; Then, reduce power to 95% using recirculation flow per I Reactor Engineer's guidance and perform ST-20B.

I Critical TaskdStandards

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Critical Task #1: Isolate the tom leak prior lo torus k e l dropping to 9.58 feet.

Critical Task #2: Terminate / Prevent RW injection sources per EP-5. Reinject to maintain RPV water level 0-100 inches.

Critical Task #3: Control rod insertion per EP-3 until all rods are in Critical Task #4: (Potential if Critical Task #3 not timety) Terminate / Prevent RPV injection sources when BIlT is exceeded per EP-5. Reinject to maintain RPV water level -19 to the level at which reinjection is cued.

LO1 05-01 NRC Examination Scenario 1 Page 4 of 20

EVENT SEQUENCE

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2.

3.

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5.

6.

7.

8.

9.

10.

11.

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-1.

1 Secure Torus Cooling Lineup. (Normal evolution)

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Running RHWSW Pump Trip. (Technical Specification)

Power reduction to 95%. (Reactivity Manipulation)

C APRM fails to respond to power change (Instrument Failure)

C APRM Inoperable (Technical Specification)

A EHC Pump Discharge Leak (Component Failure)

Lowering Torus Water Level. (Component Failure)

ATWS on SDlV Blockage (Major Transient)

SLC Pump Start Failure. (Component Failure)

EHC Pump Trip (Component Failure)

LeveUPower Control (Major Transient)

0.

TERMINATION CUES:

I. All Rods In LO1 05-01 NRC Examination Scenario 1 Page 5 of 20

INSTRUCTOR ACTIVITY Simulator in RUN Recorder and Alarm Power ON Simulator Checklist Complete Provide Turnover (Attach. 1)

After the shift turnover, allow no more than five minutes for panel walkdown POSITION All CRS SNO

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SNO SNO SNO SNO SNO OPERATOR ACTIONSSTANDARD

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Walkdown the control panels and assume the watch.

Provide crew brief.

Order RHR LOOD "A" Torus Cooling secured Obtain OP-138 Section F.l:

6 At 09-3, Close IOMOV-34A

+ At 09-3, Ensure 1 OMOV-16A opens when loop flow 4 500 QPm

+ Continue RHR Loop "A" Shutdown per F.7 6 At 09-3, Ensure RHR Loop "A" Keep-Full Pump Running

+ At 09-3, Ensure closed o 1OMOV-34A o 1OMOV-38A o

1OMOV-31A LO1 05-01 NRC Examination Scenario 1 COMMENTS/EVALUATION SAT I UNSAT / NA

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SAT I UNSAT I NA SAT I UNSAT I NA SAT / UNSAT I NA SAT I UNSAT I NA

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SAT I UNSAT I NA SAT I UNSAT I NA SAT / UNSAT / NA

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD

+ At 09-3, Secure RHR Pump A.

COMMENTWEVALUATION

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SAT I UNSAT I NA Instructor Note:

Upon securing A RHR

Pump, ACTIVATE TRIGGER 2 A RHWSW Pump Trip SNO SAT / UNSAT I NA SNO

+ Report to CRS that RHWSW A tripped.

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6 Dispatch NPO(s) to investigate RHWSW pump trip SAT / UNSAT I NA SNO SAT / UNSAT I NA SNO

+ At 09-3, Ensure Closed o

1OMOV-39A o 1OMOV-26A SAT I UNSAT I NA SNO

+ At 09-3, Ensure open 1 OMOV-16A

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SAT / UNSAT / NA SNO

+ At 09-3, Ensure open lOMOV-66A SAT I UNSAT I NA SNO

+ At 09-3, Close 1OMOV-89A Instructor Role Play:

As NPO report to SNO that A RHWSW pump breaker is charred and tripped SNO Report A RHWSW status to CRS SAT / UNSAT / NA CRS Declare A RHWSW Pump inoperable

+ TS 3.7.1 Condition A. 30 days to restore to operable SAT I UNSAT I NA SAT / UNSAT I NA CRS Order power reduction to 95% for performance of ST-20B LO1 05-01 NRC Examination Scenario 1

INSTRUCTOR ACTIVITY Instructor Note:

Just prior to the first recirc flow adjustment, verify C APRM as is failure value and ACTIVATE TRIGGER 4 C APRM Fails to respond POSITION SNO SNO SNO/SNOl SNOISNO~

CRS SNO SNO SNO SNO CRS LO1 05-01 NRC Examination Scenario 1 OPERATOR ACTIONS/STANDARD Obtain OP-27,Section E.2:

+ Review RAP-7.3.16 for rate limitation of 200 MWthlmin

+ At 09-4, Alternately reduce each recirculation pump MG set speed in 1-3% increments

+ At 09-5, Monitor reactor power and core flow between adjustments Report that c APRM is not tracking with the others.

Order C APRM Bypassed Obtain OP-16, Section E.16:

+ At 09-5, place APRM Bypass Switch in C position

+ At 09-5 andlor EPIC confirm C APRM bypass indications

+ At 09-5 and/or EPIC confirm A and E APRM bypass indications are OFF Declare C APRM Inoperable

+ TS Table 3.3.1 1, No action required

+ TRM Table T3.3.B-1, No action required.

COMMENTS/EVALUATION SAT I UNSAT 1 NA SAT I UNSAT I NA SAT I UNSAT / NA SAT I UNSAT / NA SAT / UNSAT / NA SAT I UNSAT / NA SAT / UNSAT / NA SAT I UNSAT / NA SAT I UNSAT / NA SAT I UNSAT I NA

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INSTRUCTOR ACTIVITY Instructor Note:

ACTIVATE TRIGGER 12 A EHC Pump Breaker Trip Instructor Role Play:

As NPO report to the SNO that the EHC leak has stopped

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POSITION OPERATOR ACTIONSBTANDARD

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Instructor Note:

Instructor Role Play:

As NPO report to the SNO that there is a sizable EHC leak spraying from the A EHC pump discharge filter.

The leak is not onto any equipment.

ACTIVATE TRIGGER 7 Torus Rupture SNO Relay report to CRS CRS SNO SNO Order swapping EHC to *B pump in service

+ At 09-7, Wait 30 seconds and verify red light above 8 EHC pump test pushbutton is on

+ At 09-7, Stop A EHC pump while monitoring 8 EHC pump amps and system pressure.

SNO CRS SNO Obtain OP-8, Section G.l:

Order NPO(s) dispatched to investigate.

Dispatch NPO(s) to investigate SNO

+ At 09-7, Start B EHC pump ANYIALL Report that Torus Water Level is lowering COMMENTS/EVALUATION

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SAT I UNSAT I NA SAT I UNSAT I NA SAT I UNSAT I NA SAT / UNSAT I NA SAT I UNSAT I NA SAT I UNSAT I NA

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SAT 1 UNSAT I NA SAT I UNSAT I NA SAT I UNSAT I NA LO1 05-01 NRC Examination Scenario 1

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INSTRUCTOR ACTIVITY I ANYIALL 1 Recognize and report EOP-4 and 5 entry conditions 1 SAT I UNSAT I NA 7 -

POSITION OPERATOR ACTiONS/STANDARD COMMENTSEVALUATION I

I EVALUATOR NOTE:

I AOP-9 may also be entered without substantive action required.

Announce entry into EOP-4 and 5 SAT I UNSAT I NA Instructor Role Play:

As NPO report a large packing leak in the Torus room coming from 1OMOV-151A. You believe you can isolate the leak.

Instructor Note:

DELAY CLOSURE UNTtL MANUAL SCRAM RFl-RHll to 0%

SNO CRS SNOISNOI SNO Call Radwaste to confirm both RBFDS pumps running.

Relay report to CRS CRS SAT I UNSAT / NA From EOP-5, order operation of all available Reactor Building Area Coolers CRITICAL TASK #1: ISOLATE THE TORUS LEAK Order 1 OMOV-15lA closed Dispatch NPO to close IOMOV-151A CRITICAL TASK #1 STANDARD: Torus Leak isolated prior to torus level dropping to 9.58 feet.

Instructor Role Play:

Report that both RBFDS pumps are running From EOP-5, order operation of all RBFDS pumps CRS I

SAT I UNSAT I NA SAT I UNSAT I NA SAT I UNSAT I NA SAT I UNSAT I NA SAT I UNSAT I NA SAT / UNSAT I' NA LO1 05-01 NRC Examination Scenario 1

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INSTRUCTOR ACTIVITY 1 POSITION r-SNO CRS

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OPERATOR ACTIONS/STANDARD At 09-75, Start 4 more crescent area unit coolers in each crescent EVALUATOR NOTE:

This action may be accomplished by dispatching a NPO to.

From EOP-4 order restoration of Torus level per OP-13B using the "B" Loop of RHR I

COMMENTSlEVALUATlON SNO CRS 4 At 09-3, Open 1 OMOV-166A or B and 1 OMOV-167A or B Order SNO to reestablish drywell to torus d/p EVALUATOR NOTE:

This action is not a priority and may not be performed.

SAT / UNSAT / NA SAT I UNSAT / NA SAT I UNSAT / NA I EVALUATOR NOTE:

This action is not a simulator capability. It is accomplished by candidate communication wfth the simulator console operator.

Determine that torus water level cannot be maintained above 10.75 feet.

SAT I UNSAT I NA SAT I UNSAT I NA I SNo SNO Obtain OP-l3B, Section G.4:

I SAT I UNSAT I NA CRS Instructor NoWRole Play:

Enter EOP-2 and order a Manual Scram SAT / UNSAT / NA RFI-RH47 or 46 to 100%

Report 1 ORHR-260 Open SNO

+ Dispatch NPO to open 1ORHR-274 ("A) or 260 ("B")

SAT I UNSAT / NA Instructor NotelRole Play:

Udng the containment vent and purge mimic, align the system as dlmcted per OP-37 E.2 or E.3 Report complete:

SNO CRS If ordered, obtain OP-37 Section f.2 or E.3 and establish drywell makeup SAT / UNSAT I NA CRS Order the HPCI Turbine Tripped At 09-3, Depress HPCI Turbine Tip Pushbutton SAT I UNSAT / NA SAT I UNSAT I NA

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INSTRUCTOR ACTIVITY Instructor Note:

When manual scram is inserted :

RFJ-RH1I to 0%

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POS tTlON SNOl CRS SNO SNOl CRS CRS SNOl CRS LO1 05-01 NRC Examination Scenario 1 OPERATOR ACTIONSISTANDARD I

COMMENTS/EVALUATlON At 09-5, Commence AOP-1 Immediate Actions:

I SAT / UNSAT I NA Depress Manual Scram pushbuttons Reactor Mode Switch to Shutdown Fully Insert all SRMs and IRMs Verify all rods in (multiple rods out)

Initiate ARI Verify SDlV Vent and Drain valves closed Verify APRMs downscale (Will NOT be downscale)

(At 09-6) Verify at least 1 Circ Water pump running (At 09-4)

Verify at least 1 Recirc Pump is running.

Order SNO/BOP to level control with FeedlCondensate at 177-222.5 inches.

SAT / UNSAT / NA At 09-5 and 09-4, Recognize ATWS conditions, trend level performance and manipulate GEMAC Master/lndividual controllers, RFP discharge valves and RFP trip as necessary to control level.

Report multiple rods out and post scram power level 50 - 60%

SAT I UNSAT I NA SAT / UNSAT / NA Exit EOP-2, Enter EOP-3 Confirm Reactor Mode Switch in SHUTDOWN Report Reactor Mode Switch in Shutdown SAT I UNSAT / NA SAT / UNSAT / NA SAT I UNSAT I NA Confirm ARI initiated SAT / UNSAT / NA I

INSTRUCTOR ACTIVITY I

Instructor Note:

Upon start of either SLC pump, delete that pump from TRIGGER 9 POSITION SNOl CRS SNOl CRS SNOl CRS SNOl CRS SNOI SNOl CRS LO1 05-01 NRC Examination Scenario 1 OPERATOR ACTIONS/STANDARD Report ARI Initiated

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Order Recirculation Flow reduced to minimum At 094, reduce both Recirculation Flow Controllers to minimum Determine reactor power above 2.5% and order both Recirculation Pumps tripped

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At 09-4, place both Recirculation Drive Motor Breaker Control Switches in Pull-To-Lock.

Order override ADS At 094, select ADS override switches (2) to override. Verify annunciator and white lamp.

Order SLC Injection At 09-3 select SLC Control Switch to "A" or "8" and confirm injection indications EVALUATOR NOTE The first SLC pump will successfully start yet will not inject due to the discharge relief valve lifting. The second SLC pump will fail to inject due to breaker trip.

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Report to CRS that the first SLC pump has failed to inject.

Order SLC injection on the alternate pump.

-1 3-COMMENTS/EVALUATION SAT / UNSAT / NA SAT / UNSAT / NA SAT / UNSAT / NA SAT / UNSAT / NA SAT / UNSAT / NA SAT / UNSAT / NA

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SAT / UNSAT / NA SAT I UNSAT / NA SAT / UNSAT I NA SAT / UNSAT / NA

INSTRUCTOR ACTIVITY I POSITION At 09-3 select SLC Control Switch to the other pump A or 6 and confirm injection indications Instructor Note:

SAT / UNSAT I NA I SNOI Instructor Role Play:

Acknowledge order to commence EP-4. No actions will be performed.

Upon start of either S l C pump, ACTIVATE TRIGGER 9

SNOl I SNOl Assign either operator pressure control with EHC at 900 to 1000 Psig At 09-5, Monitor RPV pressure and Bypass Valve operation.

CRS SAT UNSAT / NA SAT / UNSAT I NA Order T/P all injection except SLC, CRD and RClC per EP-5.

Terminate high pressure sources first. Identtfy reinjection source as feedwater with a level band of 80-100 and caution against rapid level changes during reinjection.

SNOISNO 1 SAT / UNSAT / NA I

CRITICAL TASK #2:

4 At 09-3, Depress HPCl Turbine Trip Pushbutton SNO SNO SAT / UNSAT / NA SNO OPERATOR ACTIONS/STANDARD I COMMENTS/EVALUATION Report to CRS that the SLC pump breaker has tripped.

SAT I UNSAT I NA Order SLC injected with CRD per EP-4 SAT / UNSAT I NA

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Dispatch NPO to commence EP-4 field actions.

SAT / UNSAT I NA I

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Obtain EP-5:

I SAT / UNSAT / NA 4 At 09-5, Select both RFP GEMAC Controllers to Manual 1 SAT I UNSAT / NA LO1 05-01 NRC Examination Scenario 1

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OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION POSITION INSTRUCTOR ACTIVITY SNO

+ At 09-5, Reduce both RFP GEMAC Controllers to Minimum SAT I UNSAT / NA

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6 At 09-6, Ensure both RFP Min Flow Valves are Open SAT / UNSAT / NA SNO SNO SAT / UNSAT / NA

+ At 09-6, As necessary, adjust RFP speed, Feedwater Startup Valve position and RFP Discharge Valve position to maintain level 80-100 inches. Exercise caution against rapid level rise.

SAT / UNSAT / NA SNO

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SAT / UNSAT / NA SNO

+ At 09-3, Place both 14MOV-11A and B Auto Actuation Bypass switches in Bypass.

SNO

+ At 09-3, Verify both white Auto Actuation Bypass lamps are lit.

SAT / UNSAT / NA SNO

+ At 09-3, Ensure closed 14MOV-1 ?A and B SAT I UNSAT / NA SNO

+ At 09-3, Ensure both Core Spray pumps are stopped SAT / UNSAT / NA

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+ At 09-3, Place both 10MOV-27A and B Auto Control Bypass switches in Bypass.

SAT / UNSAT / NA SNO

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SAT / UNSAT / NA SNO

+ At 09-3, Verify both white Auto Control Bypass lamps are lit.

SNO

+ At 09-3, Ensure closed 1OMOV-27A and B SAT / UNSAT / NA LO1 05-01 NRC Examination Scenario 1

-1 5-

I INSTRUCTOR ACTIVITY CRS I

Assign either operator to hang MSlV Low Water Level Jumpers per EP-2

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POSITION CRS Order control rods inserted per EP-3 SNO SAT I UNSAT / NA OPERATOR ACTIONSETANDARD SNOl At 09-3, Ensure RHR pumps not required to be running are stopped EVALUATOR NOTE The CRS may determine that pumps are required for Torus Cooling.

Obtain copy of EP-3 and determine success path to be Manual Scrams or driving with RMCS:

SNOl SNOl Instructor Note:

SNOlSNO1 RP17A-D IN or CAE-MSIVLEVEL Dispatch NPO to place ARI in Div I Pressure SAT / UNSAT / NA 6 Confirm ARI valves are closed SAT / UNSAT I NA Dispatch NPO to hang MSlV Low Water level Jumpers COMMENTSEVALUATION SAT I UNSAT / NA SAT I UNSAT I NA SAT I UNSAT I NA I

Instructor Note:

RPZO TEST SAT I UNSAT I NA I

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LO1 05-01 NRC Examination Scenario 1

INSTRUCTOR ACTIVITY Instructor NoWRole Play:

Candidate will page himself:

Upon calling, Access Remote Functions RP2l :A1,AZ,Bl and B2 IN or CAE-RPSJUMPERS POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION SNOl

+ At 09-15 and 09-17, install jumpers to override all automatic SAT UNSAT NA scram signals.

EVALUATOR NOTE Not a simulator capability. Simulated by candidate phoning the instructor console to complete the action.

Report jumpers installed SNOl

+ At 09-5, Place Scram Reset Switch in 2-3 then 1 4 and confirm all 8 group lights are lit.

+ At 09-5, place SDlV Hi Level Trip Bypass Switch in Bypass SAT / UNSAT / NA SAT / UNSAT / NA Instructor Note: After Scram Reset, Delete preset malfunctions RD22A and B SNOl Recognize and report EHC pump trip I ANY/ALL I Instructor Note:

When the scram is reset ACTIVATE TRIGGER 10 I SAT/UNSAT/NA SNOl

+ While the SDIVs are draining pursue RMCS rod insertion SAT / UNSAT / NA I CRS Order pressure control shifted to SRVs at 800-1000 psig I

I SNo At 094, Operate SRVs open and closed as necessary to maintain pressure band I SAT/UNSAT/NA I CRS Recognize and trend approach to BIIT.

I SAT/UNSAT/NA I SNol Insert control rods with RMCS per EP-3:

I SAT/UNSAT/NA LO1 05-01 NRC Examination Scenario 1

-1 7-

I INSTRUCTOR ACTIVITY POSITION SNOl SNO SNOl SNOl SNOl OPERATOR ACTIONS/STANDARD 6 Place RWM keylock switch in Bypass 6 At 09-5, Raise drive O/P by any of the following:

o Start second CRD pump o Close Drive PCV o Raise CRD system flow o Dispatch NPO to close CRD pump min flow valves.

6 Select control rods in sequence of Attachment 1/2 6 Insert rods with Rod Movement Control or Rod Emergency In Switch.

When SDIVs are drained, Insert a manual scram COMMENTS/EVALUATION SAT / UNSAT / NA SAT / UNSAT / NA SAT / UNSAT / NA If BllT exceeded while power is > 2.5%:

Order T/P all injection except SLC, CRD and RClC per EP-5.

Terminate high pressure sources first. Identify reinjection source as feedwater with a level band of -1 9 to the level at which injection may recommence. Caution against rapid level changes during reinjection.

EVALUATOR NOTE Timely earlier actions to insert control rods may avoid the need to perform this terminate and prevent activity.

+ At 09-5, Reduce both RFP GEMAC Controllers to Minimum LO1 05-01 NRC Examination Scenario 1

-1 8-SAT / UNSAT / NA SAT / UNSAT / NA CRITICAL TASK #3 STANDARD: Control rod insertion per EP-3 until all rods are in CRITICAL TASK #4: TERMINATE I PREVENT AND RE-INJECT TO MAINTAIN 0 -100 INCHES SAT I UNSAT I NA SAT / UNSAT / NA SAT / UNSAT I NA

INSTRUCTOR ACTIVITY I SNo POSITION OPERATOR ACTIONS/STANDARD

+ At 09-3, confirm all other terminate and prevent actions are complete CRS SNO When Rx Power <2.5%, or RPV level at TAF (0) or SRVs will remain closed order injection with feedwater at a level band of current RPV level to -19.

At 09-6, As necessary, adjust RFP speed, Feedwater Startup Valve position and RFP Discharge Valve position to maintain level 80-100 inches. Exercise caution against rapid level rise.

CRITICAL TASK #4 STANDARD: Terminate / Prevent RPV injection sources when B I n is exceeded per EP-5. Reinject to maintain RPV water level -19 to the level at which reinjection is cued SNOi Verify and report All Rods In LO1 05-01 NRC Examination Scenario 1 TERMINATE THE SCENARIO

-1 9-COMMENTS/EVALUATION SAT I UNSAT I NA

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SAT I UNSAT I NA SAT I UNSAT I NA SAT / UNSAT / NA SAT I UNSAT I NA

AlTACHMENT 1 Shift Turnover Operating normally at 100°/~ CTP H PCI Surveil lance Testing recently corn pleted successfu I ly RHR Loop Alpha in Torus Cooling Mode; Torus Cooling needs to be secured Then, reduce power to 95% using recirculation flow per Reactor Engineers guidance and perform ST-206.

LO1 05-01 NRC Examination Scenario 1

I I

JAMES A. FlTDATRlCK NUCLEAR POWER PLANT NRC INITIAL LICENSE EXAMINATION SCENARIO 2 18 MAY 2005 I

I TITLE:

SCENARIO NUMBER:

NEW PATH:

LOI-05-01 NRC EXAMINATION SCENARIO 2, SRV Tailpipe Leak In ToruslEOP-2/4fED SCENARIO NEEDS TO BE RESNAPPED WITH MALFUNCTION REVISIONS RESNAP WITH RFP B 100 VALVE CLOSED AND FCV-137 FULL OPEN NEED TO REVALIDATE THE REVISIONS FROM THE OPS VALIDATION I

CANDIDATES SRO with Command SNO Prbnary At The Controls Operator

$NO1 Primary 096 operator LO1 05-01 NRC Examination Scenario 2 Page 1 of 17

RECORD OF CHANGES SOURCE OF BRIEF DESCRIPTION OF DATE CHANGE CHANGE INITIATOR REVIEWED aZm5 New New Scenario OeVerceVy Binkley LO1 05-01 NRC Examination Scenario 2 Page 2 of 17

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TITLE:

LOI-05-01 NRC EXAMINATION SCENARIO 2, SRV Tailpipe Leak In Tonrs/EOP-2/4/D

8.

SCENARIO SETUP:

1. Initial Protected IC 133 Base IC 006

2. Special Instructions:

a. Plant operating at -5% CTP. Plant startup in progress.

b. FWLC in Automatic on the Master Controller with the B RFP in service.

c. B CRD Pump in service.

d. B Circulating Water Pump in service. A secured and available.

e. The A-I Waterbox is out of service per OP4 Sedion E to support single CW pump operation.

3. Preset Conditions:

a. PRESET, RFI-MCO1, Close, (Condenser A-1 Inlet Isolation)

b. PRESET, RFI-MCO5, Close, (Condenser A-1 Outlet Isolation)

c. TRIGGER 2, RR19:B, Controlling FWLC Transmitter Downscale Failure

d. TRIGGER 4, RD12:42-39, Control Rod Scram.

e. TRIGGER 6, ED18:A, Loss of 10500 Bus

f. TRIGGER 7, AD08:C, C ADS SRV Stuck Open.

g. TRIGGER 7, ADOS:C, C ADS SRV Seat Leakage (100% over 300 seconds)

h. TRIGGER 7, ADOG:C, C ADS SRV inadvertent opening on 300 second TO

i. TRIGGER 7, Override C SRV Red Lamp off on 299 second TD

j. TRIGGER 9, MS16:C, C ADS SRV Discharge Line Rupture (100% over 600 seconds)

k. TRIGGER 10, RHOl:D, D RHR Pump Trip

1.

TRIGGER 12, TC04:A-D at 0%. All Bypass Valves failed closed.

Initially to 53%, then to 0% over 600 seconds

4. Consumable Forms and Procedures:

+ AOP-1, Reactor Scram

+ AOP-36, Stuck Open Relief Valve@)

+ AOP-18, LOSS of 10500 BUS LO1 05-01 NRC Examination Scenario 2 Page 3 of 17

C.

SCENARIO

SUMMARY

r Shift Turnover Reactor Startup In-Progress at -5% CTP; Currently at OP-65, Step D.19; Reactor Mode Switch in "Startup". The uAlpha" Circulating Water Pwnp Has Just Been Repaired; Start Up "Alpha" CW Pump and Secure "Bravo" CW Pump for Inspection. The A-1 Waterbox is out of service per OP-4 Section E to support single CW pump operation. Continue Power Ascent to 25% CTP Using Control Rods; Reactor Engineer is present in Control Room.

Commitment Document:

The scenario will begin with a reactor startup in progress at -5% Core Thermal Power. Turnover information will indicate that repairs to the 'A' Circulating Water Pump have just been completed. The crew will be directed to pbce the 'A' CW pump in service and secure 'B. The "selected" Reactor Water Level Transmitter will fail downscale resulting in a slow rise in Rpv Water Level. The crew will take manual contrd of RPV water level, swap level columns and return to automatic level contrd. The CRS will dedare the failed transmitter inoperable. An airline rupture will result in a single mtrol rod scram. The CRS will Ware the control rod inoperable. A 4160 VAC bus loss will remove / degrade the containment cooling function. Operator actions will protect the A and C EDG's and complete the reactor building isolation. An SRV will develop growing seat leakage that will eventually result In an inadvertent opening (indusby OE) requiring the crew to manually Scram the reactor. The SRV tailpipe will develop a leak into the torus air space resulting in EOP-2 and EOP-4 entry. Upon shifting the "B" loop of RHR to Torus Spray, the only RHR pump in that loop will trip unexpectedly. This will force the crew to conclude that an Emergemy Depressurization (amtingency) is or will soon be required. The scenario will terminate upon the openinq of 7 ADS valves.

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Critical Task #1: Respond to 06U-94B Failure by taking manual control of RW level per AOP41. Maintain RPV water level 196.5 to 206.5 inches.

Critical Task #2: Manual %am on SRV Opening per AOP-36 before torus water temperature exceeds 110 OF.

Critical Task #3: Complete RW depressurization as directed by EOP-2 and 4 to prevent torus pressure from exceeding the Pressure Suppression Pressure (PSP) limit.

LO1 05-01 NRC Examination Scenario 2 Page 4 of 17

EVENT NO.

1.

2.

3.

4.

5.

6.

7.

8.

9.

10.

11.

D.

TERMINATION CUES:

1. 7 ADS Valves Open EVENT SEQUENCE Swap Circulating Water Pumps. (Normal evolution)

FWLC Controlling (B) Level Transmitter Fails Downscale. (Instrument Failure)

FWLC Controlling (B) Level Transmitter Inoperable (Technical Specification)

Single Control Rod Scram on aihine rupture (Component Failure)

Control Rod declared inoperable (Technical Specification)

Loss of 10500 Bus (Component Failure)

C ADS SRV Leakage followed by Mechanical Opening. (Component Failure)

Manual Scram, EOP-2 (Major Transient)

C ADS SRV Tailpipe Failure in Torus A h Space, EOP-4. (Component Failure)

W RHR Pump Trip (shortly after starting). (Component Failure)

Emergency Depressurization (Major Transient)

LO1 0501 NRC Examination Scenario 2 Page5of17

I INSTRUCTOR ACTIVITY I POSITION After the shift turnover, allow no more than five minutes for panel walkdown

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1

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Simulator in RUN Recorder and Alarm Power ON Simulator Checklist Complete All I Provide Turnover (Attach. 1) I L

INSTRUCTOR ROLE PLAY Report pump discharge pressure at 12 psig SNO SNO I CRS I SNo I

I SNO I SNo SNO SNO I SNO Walkdown the control panels and assume the watch.

Provide crew brief.

Order "A" CW pump started and "B" secured Obtain OP-4, Section G.5, Step G.5.3:

+ At 09-6, Place 36P-1A Control Switch in START

+ At 09-6, Observe 36MOV-1OOA opening followed by the start of 36P-1 A.

+ At 09-6, Verify stable pump amperage on 36P-1A.

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+ Contact NPO to verify pump discharge pressure - 12 psig

+ At 09-16, Verify 4 white lamps lit at the RPS A and 6 Power Source Selector Switches.

+ At 09-6, Place 36P-16 Control Switch to STOP

+ At 09-6, Verify 36MOV-100B Fully Closes.

LO1 05-01 NRC Examination Scenario 2 COMMENTSEVALUATION SAT I UNSAT I NA SAT I UNSAT I NA SAT I UNSAT I NA SAT I UNSAT I NA SAT I UNSAT I NA SAT I UNSAT I NA SAT I UNSAT I NA

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~-

SAT I UNSAT I NA SAT I UNSAT I NA SAT I UNSAT / NA

INSTRUCTOR ACTIVITY w

POSITION INSTRUCTOR NOTE:

Trigger 2, "8" FWLC Level Transmitter Failure Attempt to trigger such that SNO responds to initial level transient.

OPERATOR ACTIONS/STANDARD I

COMMENTS/EVALUATION I

SNO

+ At 09-6, Verify 36P-I B Amperage is zero ANY/ALL Recognize and report High RPV Water Level SAT / UNSAT / NA SNO SAT / UNSAT / NA Obtain AOP-41:

CRITICAL TASK #1: CONTROL RPV WATER LEVEL IN MANUAL SNO CRS

+ Determine and report that 06LI-94B is failing downscale Announce entry into AOP-41 and order SNO to complete the actions of AOP-41 EVALUATOR NOTE May provide a direct order to place FWLC in Manual prior to orderina the actions of AOP-41. Reference AP-12.03, 8.9.3.C.

SN O/SNO 1 At 09-5, select 06LC-83 or 06-848 to MANUAL. StabiJize/Control RPV Water Level in the Green Band using manual control potentiometer.

SNO

+ Recommend transfer to 06LI-94A and return to automatic level con t ro I I

SAT / UNSAT / NA SAT / UNSAT / NA

~

SAT / UNSAT / NA SAT / UNSAT / NA

~~~

SAT / UNSAT / NA SAT / UNSAT / NA LO1 05-01 NRC Examination Scenario 2

INSTRUCTOR ACTIVITY POSITION

=+

INSTRUCTOR NOTE Trigger 4, Control Rod 42-39 scram.

I CRS ANY/ALL I SNo SNO I SNo I SNO I SNo SNO SNO SNO CRS LO1 05-01 NRC Examination Scenario 2 OPERATOR ACTIONWSTANDARD

~~

Order transfer to 06LI-94A and return to automatic level control per OP-2A Declare 06LT-526 inoperable per T/S 3.3.2.2. Determine that TIS is not applicable until 25% RTP. (Potential LCO)

Obtain OF-2A Section G.30:

+ At 09-5, Place 06-SI in A-LEVEL

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+ Place FWLC in Automatic per OP-2A Steps 0.3.28 through D.3.29

~

+ At 08-5, Verify 06LC-83 is in manual

+ At 09-5, ensure 06LC-83 setpoint is 196.5 to 203 inches

+ At 09-5, Slowly adjust 06LC-83 manual control potentiometer to balance 06-84B

+ At 09-5, Place 06-846 in BAL

~~

+ At 09-5, Adjust 06LC-83 setpoint to balance then place 06LC-83 in BAL.

Recognize and report control rod drift and accumulator trouble alarms Order actions of AOP-27, Control Rod Drift COMMENTSEVALUATION SAT / UNSAT / NA SAT / UNSAT / NA

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SAT / UNSAT / NA SAT / UNSAT / NA SAT / UNSAT / NA SAT / UNSAT / NA SAT / UNSAT I NA SAT / UNSAT / NA SAT / UNSAT / NA SAT I UNSAT / NA SAT / UNSAT / NA SAT / UNSAT / NA

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OPERATOR ACTIONWSTANDARD Determine that the drift alarm resulted from a control rod scram Dispatch an NPO to investigate the HCU for control rod 42-39.

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INSTRUCTOR ROLE PLAY Report to SNO that the airline on control rod 4239 has ruptured downstream of the scram solenoids.

COMMENTSEVALUATION SAT / UNSAT / NA SAT I UNSAT I NA SNO INSTRUCTOR ACTIVITY CRS POSITION ANYIALL SNO INSTRUCTOR NOTE Trigger 6, Loss of 10500 Bus INSTRUCTOR NOTE When requested, report that the 10514 breaker has tripped on ground overcurrent Relay report to CRS Review TS 3.1.3.C declare control rod 42-39 inoperable Recognize and report the loss of the 10500 bus.

Order SNO to perform actions of AOP-18 Obtain AOP-18:

4 At 09-8, Place A and C EDG Load breaker (10502 and 10512) control switches in TRIP then PULL-TO-LOCK At 09-8, Ensure EDG A and C Tie Breaker (10504) is tripped.

ANYIALL SAT I UNSAT I NA SAT I UNSAT I NA SAT I UNSAT I NA SAT / UNSAT I NA SAT I UNSAT I NA SAT I UNSAT I NA SAT I UNSAT I NA CRS INSTRUCTOR NOTE RFI-DG23:A and C. Select MAINT SNO SNO Dispatch a NPO to place EDG A and C Local Control Switches in MAINT INSTRUCTOR ROLE PLAY Report to SNO the A and C EDG Local Control Switches SAT I UNSAT I NA LO1 05-01 NRC Examination Scenario 2

+ At 09-8, Place EDG A and C Control Switches in STOP SAT I UNSAT I NA

L INSTRUCTOR ACTIVITY POSITION are in Maintenance SNO SNO SNO SNO SNO ANYIALL INSTRUCTOR NOTE ANYIALL Trigger 7, C SRV leakage followed by mechanical OPERATOR ACTlONSlSTANDARD

+ Startup SGT Train B per OP-20, Section 0.2 4 At 09-75, Place 01-125MOV-12 control switch to OPEN 4 At 09-75, Place 01-125MOV-148 Control Switch to OPEN

+ At 09-75, Depress RB VENT ISOL B pushbutton.

6 At 09-75, Start all available Drywell Cooling Fans 4 Refer to AOP-18 Attachment 1 for affected loads Recognize and report C SRV leakage.

openinq CRS SNOl SNOl LO1 05-01 NRC Examination Scenario 2 Order 8 Loop of RHR in Toms Cooling Place RHR B loop in Toms Cooling per OP-13B or Posted Attachment at the 09-3 panel.

+ At 09-3, Place RHR D control switch in START

-1 0-COMMENTSEVALUATION 1

SAT I UNSAT I NA SAT I UNSAT I NA SAT I UNSAT I NA SAT I UNSAT / NA SAT I UNSAT I NA SAT I UNSAT I NA SAT / UNSAT I NA I SAT I UNSAT I NA SAT I UNSAT I NA

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION SAT / UNSAT / NA SNOl SNOl 4 At 09-3, Insert key and select 1OMOV-39B to OPEN 4 At 09-3, Throttle 1 OMOV-34B to establish 3 6500 gpm per operating pump.

4 At 09-3, ensure closure of IOMOV-16B when loop flow exceeds 1500 gpm.

SAT / UNSAT / NA SNOl SNOl 4 Startup RHWSW per OP-13C or 09-3 Posted Attachment.

I SAT / UNSAT / NA SNOl 4 At 09-4 or EPIC, Verify RHWSW AJB keep full alarm status is clear.

SAT / UNSAT / NA SNOl SNOl 4 At 09-3, Start RHFUSW pump B or D 4 At 09-3, Throttle 1OMOV-89B to establish 2500-4000 gpm per loop.

Recognize and report the full opening of C SRV and dropping RPV pressure SAT / UNSAT / NA ANYlALL SAT / UNSAT / NA INSTRUCTOR NOTE:

Upon Manual Scram RPV Pressure = 900 psig TRIGGER 9 OR CRS Announce entry into AOP-36 and direct SNO to perform actions.

SAT / UNSAT / NA SAT / UNSAT / NA SAT / UNSAT / NA Obtain AOP-36:

4 At 09-5, Attempt to close the C SRV by cycling the control switch between AUTO and OPEN. Several cycles may be performed.

INSTRUCTOR NOTE:

RFI-AW2:C OUT 4 Dispatch a NPO to the relay room to remove the control power fuses for the C SRV SAT / UNSAT / NA I

SAT / UNSAT / NA 4 At 09-3, verify either Torus Temperature Recorder (16-1TR-131AJB) is operating 4 At 09-3 or EPIC monitor Torus Water Temperature at least every 5 minutes.

SAT / UNSAT / NA s INSTRUCTOR ROLE PLAY 4 At 09-4, observe C SRV solenoid lamps extinguished and SAT / UNSAT / NA I

LO1 05-01 NRC Examination Scenario 2

-1 1-

INSTRUCTOR ACTlVlTY Report to SNO that "C" SRV fuses are removed.

ANYIALL CRS POSITION OPERATOR ACTIONS/STANOARD COMMENTSEVALUATION tailpipe temperatures still elevated.

Recognize AOP-36 required Manual Scram based upon the I inability to maintain Torus Bulk Temperature 110 degrees.

EVALUATOR NOTE The crew may choose to manually scram earlier due to the dropping trend in RPV pressure.

Order SNOl to insert a Manual Scram and perform AOP-1 Immediate Actions.

Order SNO to maintain RPV Water level at 177 to 222.5 inches using Feed and Condensate.

I SAT/UNSAT'NA SAT / UNSAT I NA CRITICAL TASK #2 STANDARD: Scram on SRV Opening per AOP-36 before torus water temperature exceeds 110 OF.

At 09-5, Depress both Manu4 Scram Pushbuttons 1

SAT I UNSAT / NA SAT I UNSAT I NA SNOl SNOl At 09-5, Select and insert all IRM's and SRM's SAT I UNSAT I NA At 09-5, Verify APRM Downscale lights on and report to CRS SAT I UNSAT I NA SNOl

~~

At 09-5, Place the Reactor Mode Switch in SHUTDOWN and report to CRS.

SAT I UNSAT I NA SNOl At 09-5, Verify all rods fully inserted and report to CRS SAT I UNSAT I NA SNOl

~

SDlV Vent and Drain Valves closed.

SAT I UNSAT I NA LO1 05-01 NRC Examination Scenario 2

INSTRUCTOR ACTIVITY POSITION SNO CRS SNOl ANYIALL CRS CRS CRS SNO CRS SNO SNO SNO OPERATOR ACTIONS/STANDARD At 09-5 and 09-6, Trend level performance and manipulate GEMAC Master/lndividual controller, RFP "A" discharge valve and RFP trip as necessary to control RPV Water Level.

Order SNOl to trend RPV Pressure Make periodic RPV pressure reports

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Recognize and repoiupward trend in Drywell Pressure and EOP-2 and 4 Entry Condition.

Announce entry into EOP-2 and 4 on High Drywell Pressure Monitor conditions of all 5 EOP-4 legs and all 3 EOP-2 legs concurrently.

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Order SNO to turn over RPV Level Control to SNOl Turnover RPV Level Control to SNOl Order SNO to Terminate and Prevent Core Spray and RHR per EP-5

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Obtain EP-5:

+ At 09-3, Place 1OMOV-27A and B AUTO CONTROL BYPASS Switch in BYPASS

+ At 09-3, Verify 1OMOV-27A and B AUTO CONTROL BYPASS white lamp is lit LO1 05-01 NRC Examination Scenario 2

-1 3-COMMENTSEVALUATION SAT / UNSAT / NA SAT / UNSAT / NA

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SAT I UNSAT / NA

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SAT / UNSAT / NA SAT I UNSAT / NA SAT / UNSAT / NA SAT / UNSAT / NA

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SAT / UNSAT / NA SAT / UNSAT / NA

---l SAT / UNSAT / NA SAT / UNSAT / NA 1

INSTRUCTOR ACTIVITY I SNo POSITION OPERATOR ACTIONSISTANDARD COMMENTSIEVALUATION SNO 6 At 09-3, Close IOMOV-27A and B.

SAT I UNSAT I NA

+ At 09-3, Place 14MOV-11A and B AUTO ACTUATION I SAT I UNSAT I NA I

BYPASS Switch in BYPASS Before Torus Pressure reaches 15 psig, order SNO to place the B RHR Loop in Torus Spray.

SNO SAT uNSAT I NA

+ At 09-3, Verify 14MOV-11A and B AUTO ACTUATION BYPASS white lamp is lit.

EVALUATOR NOTE 14MOV-1lA lamp will be de-energized due to the bus loss

~~

SNO SAT I UNSAT I NA

+ At 09-3, Place IOMOV-39B control switch in OPEN SAT I UNSAT I NA

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SNO 6 At 09-3, Close 14MOV-11A and B EVALUATOR NOTE 14MOV-11A will be de-energized due to the bus loss I SNo

+ Stop Core Spray Pumps A and B SAT I UNSAT / NA SAT I UNSAT I NA I CRS 1 SNo Startup B RHR in Torus Spray per OP-138 or 09-3 posted attachment:

SAT / UNSAT I NA I SNo

+ At 09-3, Place 1OA-Sl7B in MANUAL SAT I UNSAT I NA SNO

+ At 09-3, Verify 10A-DS67B white lamp is lit SAT I UNSAT I NA LO1 05-01 NRC Examination Scenario 2

INSTRUCTOR ACTIVITY I POSITION COMMENTSEVALUATION OPERATOR ACTIONS/STANDARD

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+ At 09-3, Throttle open 1 OMOV-388 and throttle closed 1 OMOV-34B to maximize Torus Spray Flow SAT I UNSAT I NA SNO INSTRUCTOR NOTE Upon initial stroking of 1 OMOV-38B, Trigger 10, D RHR pump trip SAT I UNSAT 1 NA

, SNO Report that 0 RHR pump has tripped

~

SAT I UNSAT I NA ANYIALL Determine that all RHR Containment Cooling functions have been IO&.

Determine that Torus Pressure cannot be maintained below the Pressure Suppression Pressure Limit.

SAT I UNSAT / NA

~

Order SNOl to Open all Bypass Valves in anticipation of Emergency Depressurization SAT I UNSAT I NA Trigger 1 1, All bypass valves fail closed.

SAT I UNSAT / NA SNOl At 09-5, Select Bypass Opening Jack to open all 4 Bypass Valves.

Report that Bypass Valves will not open.

At 09-5 and 09-6, Adjust FWLC to maintain RPV Water Level 177 to 222.5 inches.

SNOl CRITICAL TASK #3: DEPRESSURIZE THE RPV SAT I UNSAT I NA CRS Before Torus Pressure exceeds the Pressure Suppression Pressure limit, order the SNO to open 7 ADS Valves

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At 09-4, Select all 7 ADS valve control switches to OPEN.

SAT I UNSAT / NA SNO LO1 05-01 NRC Examination Scenario 2

-1 5-

a a

z t-m z

3 I-3 v) 0 2

c, c

0 m

c (0

Y E

3

ATTACHMENT 1 Shift Turnover Reactor Startup In-Progress at ~ 5 %

CTP; Currently at OP-65, Step D.19; Reactor Mode Switch in "Startup".

The "Alpha" Circulating Water Pump Has Just Been Repaired; Start Up "Alpha" CW Pump and Secure "Bravo" CW Pump for Inspection.

The A-1 Waterbox is out of service per OP-4 Section E to support single CW pump operation.

Continue Power Ascent to 25% CTP Using Control Rods; Reactor Engineer is present in Control Room.

LO1 05-01 NRC Examination Scenario 2

-1 7-

JAMES A. FITZPATRICK NUCLEAR POWER PLANT NRC INITIAL LICENSE EXAMINATION SCENARIO 3 18 MAY ZOO5 I

TITLE:

SCENARIO NUMBER:

NEW PATH:

LOI-05-01 NRC EXAMINATION SCENARIO 3, Seismic Event, AOP-31, MSL Break in TB RESNAP WITH CORRECT EVENT NUMBERS AND MALFUNCTION EDITS SCENARIO NEEDS TO BE RESNAPPED WITH MALFUNCTION REVISIONS RESNAP WITH MSLCS ALARMS epic-989 AND 990 OUT OF SCAN NEED TO REVALIDATE THE REVISIONS FROM THE OPS VALIDATION I

I CANDIDATES I

SNO Primary At The Controls Operato c SNOI Primary 096 Operator LO1 05-01 NRC Examination Scenario 3 Page 1 of 14

RECORD OF CHANGES DATE 03/Olx)5 SOURCE OF BRIEF DESCRIPTION OF CHANGE CHANGE INITIATOR REVIEWED New Newsoenario DeVercelly Binkley LO1 05-01 NRC Examination Scenario 3 Page 2 of 14

A.

TITLE:

LOI-05-01 NRC EXAMINATION SCENARIO 3, SeiSf~~ic Event, AOP-31, MSL Break in TB

6.

SCENARIO SETUP:

1. Initial Protected IC 134

2. Special Instructions:

a. Plant operating normally at 75% CTP

3. Preset Conditions:

a. Preset, RP13, PClS Group 1 Isolation Failure.

b. Preset, RD13:3O-15, Control Rod Fail To Scram

c. Preset, AD07:J, G, C and B. Several ADS SRVs Fail To Open

d. Trigger 2, RFI-EPOQ, Seismic Event Alarm

e. Trigger 2, ANN-09-641 1, RFP "A" High Vibration, CRYWOLF

f. Trigger 2, RFP 'A DDR-10 Vibration Point with Step rise followed by slow rise.

g. Trigger 3, RFI-HP15, HPCl AOP Breaker Trip.

h. Trigger 5, MCOl, loss of Main Condenser Vacuum,(35% over 180 seconds)

i. Trigger 7, MS05, Main Steam Line Break in the Turbine Building (25% over 300 seconds)

4. Consumable Forms and Procedures:

4 AOP-1, Reactor Scram 4 AOP-14, Earthquake 4 AOP-31, Loss of Condenser Vacuum

+ AOP40, Main Steam Line Break LO1 05-01 NRC Examination Scenario 3 Page 3 of 14

C.

SCENARIO

SUMMARY

Commitment Document:

The scenario will begin with the reactor at ~ 7 5 %

Core Thermal Power. The crew will raise power using recirculation flow. A seismic event will result in several failures starting with a 'crywolf RFP alarm on high vibration. Vibration will be slightly elevated and monitored by the crew. The following event will be a HPCI power supply loss that will disable HPCI. The CRS will deciare HPCI inoperable. The crew will then notice a slow loss of condenser vacuum and perform the AOP actions including a power reduction using recirculation flow. The major event will be a Main Steam tine Break in the Turbine Building that will fail to automatically isolate. A manual scram will be inserted followed by manually isolating the steam lines. During the scram, one control rod will fail to scram but will be inserted using RMCS. RCIC will be operated for Level Control and the SRVs will be operated in Pressure Control. Several SRVs will fail to open forcing alternative SRV selection. The scenario will terminate upon stabilization of Pressure and Level Control.

Shift Turnover Reactor Power is at 75% to support recent repairs to "Alpha" Circulating Water Pump. "A" CW pump has been returned to service. Return power to 92% using recirculation flow. Hold at 92% for Reactor Engineefs ramp guidance.

Critical Tasks Critical Task #1: Power Reduction on Degrading Condenser Vacuum per AOP-31 to prevent turbine trip(s) on low condenser vacuum.

Critical Task #2: Manual Scram and Close MSIVs per AOP-40 prior to steam tunnel temperature exceeding 200 OF.

LO1 05-01 NRC Examination Scenario 3 Page 4 of 14

EVENT 1 NO.

8.

9.

EVENT SEQUENCE One Control Rod Fails to Scram (Component)

RClC Level Control and SRVs Pressure Control

1.

I Raise Power using Recirculation Flow (Reactivity)

2.

I Seismic Event resulting in RFPT slight vibration and CRYWOLF alarm (Component)

3.

I HPCl Aux Oil Pump Breaker Trip (Component) 4 I HPCl Inoperable (Technical Specification)

5.

I Loss of Condenser Vacuum (Component)

6.

I AOP Required Power Reduction with Rods and Recirculation (Reactivity Manipulation)

Main Steam Line Break in the Turbine Building with Failure To Automatically Isolate (Major)

10.

1 Several SRVs Fail to Open (InstrumentlComponent)

D.

TERMINATION CUES:

1. Stable RPV Level and Pressure Control LO1 05-01 NRC Examination Scenario 3 Page 5 of 14

INSTRUCTOR ACTIVITY Simulator in RUN Recorder and Alarm Power ON Simulator Checklist Complete Provide Turnover (Attach. 1)

After the shift turnover, allow no more than five minutes for panel walkdown POSITION All CRS I

OPERATOR ACTIONSSTANDARD COMMENTWEVALUATION Walkdown the control panels and assume the watch.

Provide crew brief.

SAT I UNSAT / NA SAT I UNSAT / NA SNO Recognize and report RPP High Vibration Alarm and EPIC Seismic Event alarm Order raising Reactor Power to 92% using Recirculation Flow.

Obtain OP-27, Section E ;

SAT I UNSAT I NA I

SNO

+

At 09-4, Alternately raise recirculation pump speeds in 1-3% increments while monitoring:

0 Core Flow maintained less that 77 Mlbm/hr 0

Jet Pump Loop Mismatch 5 5% (3.85 Mibmhr) 7 SAT / UNSAT I NA INSTRUCTOR NOTE Trigger 2, Seismic EvenVRFP Vibration I

I I

I ANYIALL LO1 05-01 NRC Examination Scenario 3 CRS Direct SNO to enter and perform AOP-14 SAT I UNSAT / NA I

SAT I UNSAT I NA SNO Direct SNO to respond to annunciator 09-64-1 1 At 09-6, Monitor and trend RFP A Vibration on 31TR-IOOA SAT / UNSAT / NA I

SNO Obtain AOP-14:

I SAT / UNSAT / NA

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INSTRUCTORACTIVITY I POSITION

+

Dispatch NPOs throughout plant to inspect for damage and unusual indications At 27CA0, confirm that 27SOV-129A or B is open.

+

INSTRUCTOR ROLE PLAY I SNO SAT / UNSAT / NA SAT / UNSAT / NA No observable damage INSTRUCTOR ROLE PLAY OPERATOR ACTIOWSTANDARD I COMMENTSEVALUATION SNO This activity is simulated by candidate phoning the Instructor console from the back panel area.

+

Contact NMP Unit 2 or National Center For Earthquake I

I earthauake.

Engineering Research to determine the magnitude of the Report 27SOV-129A is Open I 1 EVALUATOR NOTE I

1 SAT / UNSAT / NA INSTRUCTOR ROLE PLAY Report 0.lOg (>OBE)

INSTRUCTOR NOTE Trigger 3, HPCl AOP Breaker Trip SNO Obtain ARP-09-3-3-38:

SNO/SNOl SAT / UNSAT / NA INSTRUCTOR NOTE Report that the pump is fine but the breaker is tripped with an acrid order from the breaker cu bicle.

INSTRUCTOR NOTE Trigger 5, Loss of Condenser Vacuum ANY/ALL SAT / UNSAT / NA SNO

+

Dispatch NPO to investigate pump and breaker CRS Declare HPCl Inoperable. Per T/S 3.5.1 Condition C, must immediately verify RClC Operable and restore HPCl within 14 days Recognize and report the slow loss of condenser vacuum SAT / UNSAT I NA ANY/ALL SAT / UNSAT / NA Recognize and report annunciator 09-3-3-38 and the loss of lamp indication for the HPCl Aux Oil Pump.

Order SNOto respond per the ARP

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SAT / UNSAT / NA SAT I UNSAT I NA LO1 05-01 NRC Examination Scenario 3

INSTRUCTOR ACTIVITY 1 POSITION OPERATOR ACTIONS/STANDARD Direct SNO to perform the actions of AOP-31 Set a manual scram benchmark for SNOl.

(Typically -23 inches)

Obtain AOP-31:

+

At 09-6, Trip the Recombiner and verify The Hydrogen Addition System trips

+ Dispatch an NPO to verify valve positions at the Off Gas System Recombiner Panel (01 -1 070GR)

+ Dispatch NPO to place spare SJAE's in service

+ At 09-6, Observe Off Gas Flow on 38FR-101 and determine that the source of condenser vacuum loss is air inleakage CRS COMMENTSEVALUATION SAT / UNSAT / NA SAT / UNSAT / NA SAT / UNSAT / NA SAT / UNSAT I NA SAT / UNSAT / NA SAT / UNSAT I NA SAT / UNSAT / NA CRS SNO SNO INSTRUCTOR ROLE PLAY All valve in correct positions per AOP-14, Step C.5.4 INSTRUCTOR NOTE RFI-MC13-20 to ON for all off service SJAE's SNO I SNo INSTRUCTOR ROLE PLAY Report a tear in the 'A" RFPT Exhaust b o t SNO SNO

+ At 09-7 monitor Turbine Steam Seal Pressure and SPE Vacuum SAT / UNSAT / NA

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6 Dispatch NPO(s) to inspect for source of air inleakage.

SAT / UNSAT / NA CRITICAL TASK #I:

POWER REDUCTION ON DEGRADING CONDENSER VACUUM INSTRUCTOR NOTE I CRS I Trend Condenser Vacuum and direct SNO to perform a power I SAT / UNSAT / NA Adjust severity of MCOI to force power reduction LO1 05-01 NRC Examination Scenario 3 reduction with recirculation flow to combat trend. Limit the SNO to maintain 2 50% Core Flow. Rapid rates may apply.

INSTRUCTOR ACTlVlTV

~~

SAT I UNSAT 1 NA INSTRUCTOR NOTE After several adjustments, adjust MCOl seventy to force rapid rates.

I SAT / UNSAT I NA INSTRUCTOR NOTE Adjust severity of MCOl to force power reduction

~

1 Obtain OP-27, Section G.l (Rapid Rates):

INSTRUCTOR NOTE Adjust MCOl severity to a slowly improving trend in condenser vacuum SNOl SNOl SNOl POSITION Obtain RAP-7.3.16, Attachment 1 (Posted at 09-5):

SAT / UNSAT / NA

+ At 09-5, Select control rods in the first cram group

+ At 09-5, Fully insert the selected control rods until all contrd rods in cram group 1 are inserted.

SAT / UNSAT I NA SAT / UNSAT / NA SNO SNO OPERATOR ACTIONS/STANDARD Obtain OP-27, Section E:

(Normal Rates at < 200 Mwth/min)

+

At 09-4, Alternately lower recirculation pump speeds in 1-3% increments while monitoring:

o Jet Pump Loop Mismatch 5 5% (7.7 Mlbm/hr) o Core Flow > 50%

SNO

+

At 09-4, Simultaneously lower recirculation pump speeds while monitoring:

o Jet Pump Loop Mismatch 5 5% (7.7 Mlbmlhr) o CoreFlOw>50%

o RFW Water Level < 222.5 inches CRS

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Trend condenser vacuum and direct SNOl to insert Control Rod Cram Groups to combat trend COMMENTSEVALUATION SAT / UNSAT / NA SAT / UNSAT / NA SAT / UNSAT / NA I

I I

CRITICAL TASK #I STANDARD: Power Reduction on Degrading Condenser Vacuum per AOP-31 to prevent turbine trip(s) on low condenser vacuum.

SAT / UNSAT / NA LO1 05-01 NRC Examination Scenario 3

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD INSTRUCTOR NOTE Trigger 7, MSL Break in TB ANY/ALl Recognize and report elevating temperatures in the Main Steam Tunnel.

The HSIVs will NOT automatkalty isolate on area I temperature COMMENT WEVALUATION SAT UNSAT / NA CRS Direct SNO to perform the actions of AOP-40 Obtain AOP40 and inform CRS that MSlV closure is required.

EVALUATOR NOTE SNO SAT / UNSAT / NA SAT / UNSAT / NA SAT / UNSAT / NA CRS CRS sNo1 SAT / UNSAT / NA

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Direct SNOl to perform a manual scram and AOP-1 immediate actions Direct SNO to maintain R W Water Level at 177-222.5 inches using Feed and Condensate

+ At 09-5, Depress Manual Scram Pushbuttons SAT / UNSAT / NA SNOl SNOl SAT / UNSAT / NA

+ At 09-5, Place Reactor Mode Switch in SHUTDOWN and report to CRS

+ At 09-5, select and fully insert all SRMs and IRMs SAT / UNSAT 1 NA SNOl SNOl 6 At 09-5, Observe APRM downscale indications and report to CRS

+ At 09-5, Trip the Main Turbine SAT / UNSAT / NA SAT / UNSAT / NA SNOl SNOl I SAT/UNSAT/NA

+ At 09-5, Verify all rods Full In. Report to CRS that Control Rod 30-15 is not full in. Currently at position 48 6 At 09-5, Ensure SDlV Vent and Drain Valves are closed SAT / UNSAT / NA LO1 05-01 NRC Examination Scenario 3

-1 0-

I VN / lVSNn / I V S VN / lVSNn / I V S VN / IVSNn / lVS VN / lVSNn / lVS VN / l V S N l l / I V S VN / lVSNfl/ I V S VN / I w N n / 1VS VN / lVSN(I/ l V S VN / lVSNn/ 1VS VN / lVSNfl/ l V S VN 1 lVSNn I l V S NOllVlllVA3/SlN3 W WO3 I

I LONS I LONS I NOlllSOd I AlIA113V tlOl3nkllSNI

I INSTRUCTOR ACTIVITY I POSITION I OPERATOR ACTIONS/STANDARD

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CRS CRS

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SNO Direct SNOl to insert Control Rod 30-1 5 per AOP-1 Direct SNO to Pressure Control at 800 to loo0 psig using the SRVs 6 Dispatch NPO to Stop 70FN-1 and Close 70DMPR-105 SNOl I SNo Obtain AOP-1, Section C.3:

+ At 09-75, Place Relay Room Ventilation Control Switches in I

ISOL SNOl SNO

+ At 09-5, Place Scram Reset Switch in Group 2&3 then 1&4

+ At 09-75, Verify closure of Relay Room Supply and Exhaust Dampers and the Vent Damper.

SNO

+ Dispatch NPO to place TSC Filtered Ventilation in service per OP-59B I SNo At 094, Operate SRVs in sequence (Posted at 094) to maintain RPV Pressure.

SNO Recognize and report the Failure of SRVs to operate and continue in sequence to maintain RPV pressure in band SNOl

+ At 09-5, Place RWM keylock switch in BYPASS I SNo'

+ At 09-5, Place SDlV High Level Trip Keylock Switch in 1

BYPASS COMMENTSEVALUATION SAT / UNSAT / NA SAT / UNSAT / NA SAT / UNSAT / NA SAT / UNSAT / NA SAT / UNSAT / NA SAT / UNSAT / NA SAT / UNSAT / NA SAT / UNSAT I NA SAT / UNSAT / NA SAT / UNSAT / NA SAT / UNSAT / NA SAT / UNSAT / NA LO1 05-01 NRC Examination Scenario 3

-1 2-

1 INSTRUCTOR ACTIVITY COMMENTS/EVALUATION POSITION OPERATOR ACTIONS/STANDARD SNOl

+ Select Control Rod 30-15 SAT / UNSAT / NA

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6 Fully insert Control Rod 30-15 using RMCS SAT / UNSAT / NA SNOl Direct SNO to maintain RPV Level 177-222.5 inches using RClC SAT / UNSAT / NA CRS SNO Obtain OP-19 section D or 09-4 Posted Attachment EVALUATOR NOTE The following actions assume the candidate starts RClC directly in Level Control. Depending upon RPV Water Level and trend, other options may apply resulting in minor deviations SAT / UNSAT I NA SNO

+ Start the RClC Vacuum Pump SAT / UNSAT / NA SAT / UNSAT I NA SNO

+ Open 13MOV-I32

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SAT / UNSAT / NA SNO

+ Open 13MOV-131 SNO

+ Open 13 MOV-21 SAT 1 UNSAT I NA SNO

+ Ensure Closed 13MOV-27, 13AOV-34 and 13AOV-35 SAT / UNSAT / NA

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+ Start RHR in Torus Cooling per W-13B or Posted Attachment at 09-3 SAT / UNSAT / NA SNO TERMINATE THE SCENARIO LO1 05-01 NRC Examination Scenario 3

-1 3-

A7TACHMENT 1 Shift Turnover Reactor Power is at 75% to support recent repairs to "Alpha" Circulating Water Pump.

"A" CW pump has been returned to service.

Return power to 92% using recirculation flow. Hold at 92% for Reactor Engineer's ramp guidance.

LO1 05-01 NRC Examination Scenario 3