ML051930234

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Final - Section C Operating (SRO) (Folder 3)
ML051930234
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 04/14/2005
From: Berry P
Entergy Nuclear Northeast
To: Suzanne Dennis
Operations Branch I
Conte R
References
Download: ML051930234 (68)


Text

TITLE: LOI-05-01 NRC EXAMINATION SCENARIO 1, TORUS RUPTUREIATWS, EOP-3/4/5 SCENARIO NUMBER: NEW PATH:

Primary At The Contro LO1 05-01 NRC Examination Scenario 1 Page 1 of 20

RECORD OF CHANGES LO1 05-01 NRC Examination Scenario 1 Page 2 of 20

A. TITLE: LOI-05-01 NRC EXAMINATION SCENARIO 1, TORUS RUPTURUATWS, EOP-3/4/5 B. SCENARIO SETUP:

1. Initial Protected IC 1 3 2
2. Special Instructions:
a. Plant operating normally a t 100% CTP
b. " A " RHR in Torus Cooling Mode with " A " RHR and " A " RHR/SW pumps in service.
c. " A " EHC pump in service
3. Preset Conditions:
a. TRIGGER 2, SW04:A, RHR/SW Pump A Trip
b. TRIGGER 4, NM14:C, APRM C Failure as is at 1 0 0 %
c. TRIGGER 7, RHlO:A, RHR Pump Suction Line Break, 5 0 % over 600 seconds
d. Preset, RD22:A and B, E and W SDV Hydraulic Block, 60%
e. Preset, SL03:A and B, SLC pump A and B Relief Valve Lift.
f. TRIGGER 9, SLOl :A and B, SLC pump A and B Breaker Trip
g. TRIGGER 10, TC02:B, B EHC Pump Trip
h. TRIGGER 12, T C 0 2 : A , "ALPHA" EHC PUMP
4. Consumable Forms and Procedures:

4 ST-20BI Control Rod Operability For Partially W i t h d r a w n Control Rods, Pre-Marked u p for performance 4 AOP-9, Loss of Primary Containment 4 AOP-1, Reactor Scram LO1 05-01 NRC Examination Scenario 1 Page 3 of 20

C. SCENARIO

SUMMARY

The scenario will begin with the plant operating normally at 100% 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/SW pump breaker charring. The CRS will declare the RHR/SW Subsystem inoperable. Per Reactor Engineer's guidance, a power reduction to 95% will then be commenced for performance of ST-2OB. 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 immediate direction to enter EOP-4/EOP-5. EOP-4 will be entered on low Torus water level and EOP-5 will be entered on High Sump/Floor Water Level in the Crescent Area. Local 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. Shortly after the manual scram occurs, the leak will be reported isolated. 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 result in a turbine trip and a loss of the bypass valves shortly thereafter. This will force transitioning pressure control to the SRV's and trending the approach to the Boron Injection Initiation Temperature (BIll). I f B I l l is reached, another Terminate and Prevent will result in RPV water level control at an even lower level. Timely action to complete rod insertion may avoid exceeding BIIT. The control rod insertion success path will require resetting the scram signal, draining the SDIV(s) and re-inserting a manual scram. Control rad 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 normally at 100% CW;RHR Loop 'Alpha" in Torus Cooling Mode; HPCI SurveillanceTesting recently completed successfully; Torus Cooling needs to be secured; Then, reduce power to 95% using recirculation flow per Reactor Engineer's guidance and perform ST-2OB.

I Critical TasksKtandards Critical Task #1: Isolate the torus leak prior to torus level dropping to 9.58 feet.

Critical Task #2: Terminate / Prevent RPV 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 timely) Terminate / Prevent RPV injection sources when BIIT 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 EVENT SEQUENCE NO.

1. Secure Torus Cooling Lineup. (Normal evolution)
2. Running RHR/SW Pump Trip. (Technical Specification)
3. Power reduction t o 95%. (Reactivity Manipulation)
4. "C" APRM fails t o respond t o power change (Instrument Failure)
5. "C" APRM Inoperable (Technical Specification)
6. "A" EHC Pump Discharge Leak (Component Failure)
7. Lowering Torus Water Level. (Component Failure)
8. ATWS on SDlV Blockage (Major Transient)
9. SLC Pump Start Failure. (Component Failure)
10. EHC Pump Trip (Component Failure)
11. LeveVPower Control (Major Transient)

D. TERMINATION CUES:

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

INSTRUCTOR ACTIVITY I POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION Simulator in RUN Recorder and Alarm Power ON Simulator Checklist Complete Provide Turnover (Attach. 1) 1 After the shift turnover, All Walkdown the control panels and assume the watch. SAT / UNSAT / NA allow no more than five minutes for panel walkdown I CRS SNO Provide crew brief.

Order RHR Loop "A" Torus Cooling secured Obtain OP-13B Section F. 1:

SAT / UNSAT / NA SAT / UNSAT / NA SNO + At 09-3, Close 10MOV-34A SAT / UNSAT / NA SNO + At 09-3, Ensure 1OMOV-16A opens when loop flow SAT / UNSAT / NA

< 1500 gpm SNO + Continue RHR Loop "A" Shutdown per F.7 SAT / UNSAT / NA SNO + At 09-3, Ensure RHR Loop "A" Keep-Full Pump Running SAT / UNSAT / NA SNO + At 09-3, Ensure closed SAT / UNSAT / NA o 1OMOV-34A o 10MOV-38A o 1OMOV-31A LO1 05-01 NRC Examination Scenario 1 INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION Instructor Note: SNO + At 09-3, Secure RHR Pump "A". SAT / UNSAT / NA Upon securing "A" RHR Pump.

ACTIVATE TRIGGER 2 "A" RHR/SW Pump Trip SNO + Report to CRS that RHR/SW "A" tripped. SAT / UNSAT / NA

~~ ~ ~~ ~

SNO Dispatch NPO(s) to investigate RHR/SW pump trip SAT / UNSAT / NA SNO + A t 09-3, Ensure Closed SAT / UNSAT / NA o 10MOV-39A o 10MOV-26A SNO + At 09-3, Ensure open 10MOV-16A SAT / UNSAT / NA SNO + A t 09-3, Ensure open 10MOV-66A SAT / UNSAT / NA SNO + A t 09-3, Close 10MOV-89A SAT / UNSAT / NA Instructor Role Play: SNO Report "A" RHR/SW status to CRS SAT / UNSAT / NA As NPO report to SNO that "A" RHRlSW pump breaker is charred and tripped CRS Declare 'A' RHR/SW Pump inoperable SAT / UNSAT / NA

+ TS 3.7.1 Condition A. 3 0 days t o restore to operable CRS Order power reduction to 95% for performance of ST-20B SAT / UNSAT / NA LO1 05-01 NRC Examination Scenario 1

~ ~ _ _ _ _ _

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION Instructor Note: SNO Obtain OP-27,Section E.2: SAT / UNSAT / NA Just prior to the first recirc + Review RAP-7.3.16 for rate limitation of 200 MWth/min flow adjustment, verify "C" APRM as is failure value and ACTIVATE TRIGGER 4 "C" APRM Fails to respond SNO + At 09-4, Alternately reduce each recirculation pump MG set SAT / UNSAT / NA speed in 1-3% increments

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SNO/SNOl + At 09-5, Monitor reactor power and core flow between SAT / UNSAT / NA adjustments SNO/SNO 1 Report that "C" APRM is not tracking with the others. SAT / UNSAT / NA CRS Order "C" APRM Bypassed SAT / UNSAT / NA SNO Obtain OP-16, Section E. 16: SAT / UNSAT / NA

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SNO + At 09-5, place APRM Bypass Switch in "C" position SAT / UNSAT / NA SNO + At 09-5 and/or EPIC confirm "C" APRM bypass indications SAT / UNSAT / NA SNO + At 09-5 and/or EPIC confirm "A" and "E" APRM bypass SAT / UNSAT / NA indications are OFF CRS Declare "C" APRM inoperable SAT / UNSAT / NA

+ TS Table 3.3.1.1-1 , No action required LO1 05-01 NRC Examination Scenario 1 INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATIC

~~ ~

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

Instructor Role Play: SNO Relay report to CRS SAT / UNSAT / NA 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.

CRS Order swapping EHC to "B" pump in service SAT / UNSAT / NA SNO Obtain OP-8, Section G. 1: SAT / UNSAT / NA SNO + At 09-7, Start "B" EHC pump SAT / UNSAT / NA SNO + At 09-7, Wait 3 0 seconds and verify red light above "B" SAT / UNSAT / NA EHC pump test pushbutton is on Instructor Note: SNO + A t 09-7, Stop "A" EHC pump while monitoring "B" EHC SAT / UNSAT / NA pump amps and system pressure.

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

As NPO report t o the SNO that the EHC leak has stopped Instructor Note: ANY/ALL Report that Torus Water Level is lowering SAT / UNSAT / NA ACTIVATE TRIGGER 7 EVALUATOR NOTE Torus Rupture The torus water level drop may be observed on EPIC LOG 1 or upon EPIC SPDS Alarm at 13.88 feet.

CRS Order NPO(s) dispatched t o investigate. SAT / UNSAT / NA LO1 05-01 NRC Examination Scenario 1 I INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTWEVALUAT10N SNO Dispatch NPO(s) to investigate SAT / UNSAT / NA ANY/ALL Recognize and report EOP-4 and 5 entry conditions SAT / UNSAT / NA EVALUATOR NOTE:

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

CRS Announce entry into EOP-4 and 5 SAT / UNSAT / NA Instructor Role Play: SNO Relay report to CRS SAT / UNSAT / NA As NPO report a large packing leak in the Torus room coming from IOMOV-151A. You believe you can isolate the leak.

CRITICAL TASK #1: ISOLATE THE TORUS LEAK Instructor Note: CRS Order 1OMOV-15 1A closed SAT / UNSAT / NA DELAY CLOSURE UNTIL MANUAL SCRAM RFI-RH11 t o 0%

Dispatch NPO t o close 1OMOV-15 1A SAT / UNSAT / NA CRITICAL TASK #I STANDARD: Torus Leak isolated prior t o torus level dropping t o 9.58 feet. SAT IUNSAT INA CRS From EOP-5, order operation of all RBFDS pumps SAT / UNSAT / NA Instructor Role Play: SNO/SNOl Call Radwaste t o confirm both RBFDS pumps running. SAT / UNSAT INA Report that both RBFDS pumps are running LO1 05-01 NRC Examination Scenario 1

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INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION CRS From EOP-5, order operation of all available Reactor Building SAT / UNSAT / NA Area Coolers SNO A t 09-75, Start 4 more crescent area unit coolers in each SAT / UNSAT / NA crescent EVALUATOR NOTE:

This action may be accomplished by dispatching a NPO to.

CRS From EOP-4 order restoration of Torus level per OP-13B using SAT / UNSAT / NA the RHR EVALUATOR NOTE Either loop of RHR may be used. The following steps differentiate between the "A" and "B" loops.

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SNO Obtain OP-l3B, Section G.4: SAT / UNSAT / NA Instructor Note/Role Play: SNO + Dispatch NPO t o open 10RHR-274 ("A") or 260 ("B") SAT / UNSAT / NA RFI-RH47 or 46 t o 100%

Report 1ORHR-260 Open SNO + A t 09-3, Open 1OMOV-166A or B and 1OMOV-167A or B SAT / UNSAT / NA CRS Order SNO t o reestablish drywell t o torus d/p SAT / UNSAT / NA EVALUATOR NOTE:

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

Instructor Note/Role Play: SNO If ordered, obtain OP-37 Section E.2 or E.3 and establish SAT / UNSAT / NA Using the containment vent and drywell makeup purge mimic, align the system as EVALUATOR NOTE:

directed per OP-37 E.2 or E.3 Report when complete. This action is not a simulator capability. It is accomplished by candidate communication with the simulator console operator.

CRS Determine that torus water level cannot be maintained above SAT / UNSAT / NA 10.75 feet.

LO1 05-01 NRC Examination Scenario 1 -1 1-

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION CRS Order the HPCl Turbine Tripped SAT / UNSAT / NA SNO A t 09-3, Depress HPCl Turbine Trip Pushbutton SAT / UNSAT / NA CRS Enter EOP-2 and order a Manual Scram SAT / UNSAT / NA Instructor Note: SNOl A t 09-5, Commence AOP-1 Immediate Actions: SAT / UNSAT / NA When manual scram is Depress Manual Scram pushbuttons inserted:

Reactor Mode Switch to Shutdown RFI-RH1 1 to 0%

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.

CRS Order SNO/BOP to level control with FeedKondensate at 177- SAT / UNSAT / NA 222.5 inches.

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

~~

SNOl Report multiple rods out and post scram power level 50 - 60% SAT / UNSAT / NA CRS Exit EOP-2, Enter EOP-3 SAT / UNSAT / NA LO1 05-01 NRC Examination Scenario 1 -1 2-

I INSTRUCTOR ACTIVITY POSITION OPERATOR ACT10NS/STANDARD COMMENTS/EVALUATION CRS Confirm Reactor Mode Switch in SHUTDOWN SAT / UNSAT / NA SNOl Report Reactor Mode Switch in Shutdown SAT / UNSAT / NA CRS Confirm ARI initiated SAT / UNSAT / NA SNOl Report ARI Initiated SAT / UNSAT / NA

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CRS Order Recirculation Flow reduced t o minimum SAT / UNSAT / NA SNOl A t 09-4, reduce both Recirculation Flow Controllers t o SAT / UNSAT / NA minimum CRS Determine reactor power above 2.5% and order both SAT / UNSAT / NA Recirculation Pumps tripped SNOl A t 09-4, place both Recirculation Drive Motor Breaker Control SAT / UNSAT / NA Switches in Pull-To-Lock.

CRS Order override ADS SAT / UNSAT / NA SNOl A t 09-4, select ADS override switches (2) t o override. Verify SAT / UNSAT / NA annunciator and white lamp.

CRS Order SLC Injection SAT / UNSAT / NA LO1 05-01 NRC Examination Scenario 1 -1 3-

I INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUAT10 N Instructor Note: SNOl At 09-3 select SLC Control Switch to "A" or "B" and confirm SAT / UNSAT / NA Upon start of either SLC injection indications pump, delete that pump from EVALUATOR NOTE TRIGGER 9 and delete The first SLC pump will successfully start yet will not inject PRESET SL03 for the due to the discharge relief valve lifting. The second SLC pump opposite pump.

will fail to inject due to breaker trip.

SNO 1 Report to CRS that the first SLC pump has failed to inject. SAT / UNSAT / NA CRS Order SLC injection on the alternate pump. SAT I UNSAT / NA Instructor Note: SNOl A t 09-3 select SLC Control Switch to the other pump "A" or SAT / UNSAT / NA Upon start of either SLC "B" and confirm injection indications pump, ACTIVATE TRIGGER 9

SNOl Report to CRS that the SLC pump breaker has tripped. SAT / UNSAT / NA CRS Order SLC injected with CRD per EP-4 SAT / UNSAT / NA Instructor Role Play: SNO 1 Dispatch NPO to commence EP-4 field actions. SAT / UNSAT / NA Acknowledge order t o commence EP-4. No actions will be performed.

CRS Assign either operator pressure control with EHC a t 900 to SAT / UNSAT / NA 1000 psig SNO/SNO 1 A t 09-5, Monitor RPV pressure and Bypass Valve operation. SAT / UNSAT / NA LO1 05-01 NRC Examination Scenario 1 -1 4-

I I

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INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD

~~

I COMMENTS/EVALUATION

~~~

CRITICAL TASK 172: TERMINATE / PREVENT AND RE-INJECT TO MAINTAIN -19 t o + 110 INCHES CRS Order T/P all injection except SLC, CRD and RClC per EP-5. SAT / UNSAT / NA Terminate high pressure sources first. Identify reinjection source as feedwater with a level band of 80-100" and caution against rapid level changes during reinjection.

SNO Obtain EP-5: SAT / UNSAT / NA SNO + A t 09-3, Depress HPCl Turbine Trip Pushbutton SAT / UNSAT / NA SNO A t 09-5, Select both RFP GEMAC Controllers t o Manual SAT / UNSAT / NA SNO + A t 09-5, Reduce both RFP GEMAC Controllers t o Minimum SAT / UNSAT / NA SNO + A t 09-6, Ensure both RFP Min Flow Valves are Open SAT / UNSAT / NA

~~ ~

SNO + A t 09-6, As necessary, adjust RFP speed, Feedwater SAT / UNSAT / NA Startup Valve position and RFP Discharge Valve position t o maintain level 80-1 00 inches. Exercise caution against rapid level rise.

SNO As time allows: SAT / UNSAT / NA SNO + A t 09-3, Place both 14MOV-11A and B Auto Actuation SAT / UNSAT / NA Bypass switches in Bypass.

SNO + A t 09-3, Verify both white Auto Actuation Bypass lamps SAT / UNSAT / NA are lit.

LO1 05-01 NRC Examination Scenario 1 -1 5-

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONWSTANDARD COMMENTS/EVALUATION SNO + At 09-3, Ensure closed 14MOV-11A and B SAT / UNSAT / NA SNO + At 09-3, Ensure both Core Spray pumps are stopped SAT / UNSAT / NA SNO + At 09-3, Place both 10MOV-27A and B Auto Control SAT / UNSAT / NA Bypass switches in Bypass.

SNO + At 09-3, Verify both white Auto Control Bypass lamps are SAT / UNSAT / NA SNO I+ At 09-3, Ensure closed 1OMOV-27A and B SAT / UNSAT / NA SNO + At 09-3, Ensure RHR pumps not required to be running are SAT / UNSAT / NA stopped EVALUATOR NOTE The CRS may determine that pumps are required for Torus Cooling.

CRITICAL TASK #2 STANDARD: Terminate / Prevent RPV injection sources per EP-5. Reinject to SAT / UNSAT / NA maintain RPV water level -19 to 110 inches.

CRS Assign either operator t o hang MSlV Low Water Level Jumpers SAT / UNSAT / NA per EP-2 Instructor Note: SNO/SNOl Dispatch NPO to hang MSlV Low Water Level Jumpers SAT / UNSAT / NA RP17A-D "IN" or CAE-MSIVLEVEL CRS Order control rods inserted per EP-3 SAT / UNSAT / NA LO1 05-01 NRC Examination Scenario 1 -1 6-

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMM ENTSEVALUATION SNOl Obtain copy of EP-3 and determine success path to be Manual SAT / UNSAT / NA Scrams or driving with RMCS:

Instructor Note: SNOl + Dispatch NPO to place ARI in Div I Pressure SAT / UNSAT / NA RP20 TEST SNOl + Confirm ARI valves are closed SAT / UNSAT / NA Instructor Note/Role Play: SNOl + At 09-1 5 and 09-17, install jumpers to override all SAT / UNSAT / NA automatic scram signals.

Candidate will page himself:

EVALUATOR NOTE Upon calling, Access Remote Functions RP21: A I ,A2,B1 Not a simulator capability. Simulated by candidate phoning the and B 2 IN or instructor console t o complete the action.

CAE-RPSJUMPERS Report jumpers installed SNOl 4 At 09-5, place SDlV Hi Level Trip Bypass Switch in Bypass SAT / UNSAT / NA Instructor Note: After Scram SNOl + At 09-5, Place Scram Reset Switch in 2-3 then 1-4 and SAT / UNSAT / NA Reset, Delete preset confirm all 8 group lights are lit.

malfunctions RD22A and B Instructor Note: SNOl + While the SDIVs are draining pursue RMCS rod insertion SAT / UNSAT / NA When the scram is reset ACTIVATE TRIGGER 10 ANYIALL Recognize and report EHC pump trip SAT / UNSAT / NA CRS Order pressure control shifted to SRVs at 800-1000 psig SAT / UNSAT / NA LO1 05-01 NRC Examination Scenario 1 -1 7-

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INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTWEVALUAT10N

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SNO A t 09-4, Operate SRV's open and closed as necessary to SAT / UNSAT / NA maintain pressure band I CRS SNOl Recognize and trend approach to BIIT.

Insert control rods with RMCS per EP-3:

SAT / UNSAT / NA SAT / UNSAT / NA i

+ Place RWM keylock switch in Bypass SAT / UNSAT / NA

+ A t 09-5, Raise drive D/P by any of the following: SAT / UNSAT / NA o Start second CRD pump o Close Drive PCV o Raise CRD system flow o Dispatch NPO t o close CRD pump min flow valves.

SNOl 4 Select control rods in sequence of Attachment 1/2 SAT / UNSAT / NA SNOl 4 Insert rods with Rod Movement Control or Rod Emergency SAT / UNSAT / NA In Switch.

SNOl When SDIV's are drained, Insert a manual scram SAT / UNSAT / NA CRITICAL TASK #3 STANDARD: Control rod insertion per EP-3 until all rods are in SAT / UNSAT / NA LO1 05-01 NRC Examination Scenario 1 -1 8-

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUAT10 N CRITICAL TASK #4: TERMINATE / PREVENT AND RE-INJECT TO MAINTAIN -19 TO THE LEVEL AT WHICH REINJECTION IS CUED.

CRS If BllT exceeded while power is > 2.5%: SAT / UNSAT / NA 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 -19" to the level a t which injection may recommence. Caution against rapid level changes during reinjection.

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

SNO + A t 09-5, Reduce both RFP GEMAC Controllers to Minimum SAT / UNSAT / NA SNO + A t 09-3, confirm all other terminate and prevent actions are SAT / UNSAT / NA complete CRS When Rx Power <2.5%, or RPV level at TAF (0") or SRV's SAT / UNSAT / NA will remain closed order injection with feedwater a t a level band of current RPV level to -19".

SNO A t 09-6, As necessary, adjust RFP speed, Feedwater Startup SAT / UNSAT / NA Valve position and RFP Discharge Valve position t o maintain I

level 80-100 inches. Exercise caution against rapid level rise.

CRITICAL TASK #4 STANDARD: Terminate / Prevent RPV injection sources when BIm is exceeded SAT / UNSAT / NA per EP-5. Reinject to maintain RPV water level -19 to the level at which reinjection is cued SNOl Verify and report All Rods In SAT / UNSAT / NA I I I TERMINATE THE SCENARIO LO1 05-01 NRC Examination Scenario 1 -1 9-

ATTACHMENT 1 Shift Turnover Operating normally at 100% CTP HPCI S urveiIIance Testing recentIy completed successfuIIy RHR Loop "Alpha" in Torus Cooling Mode; Torus Cooling needs to be secured Then, reduce power to 95% using recirculation flow per Reactor Engineer's guidance and perform ST-20B.

LO1 05-01 NRC Examination Scenario 1 TITLE: LOI-05-01 NRC EXAMINATION SCENARIO 2, SRV Tailpipe Leak In Torus/EOP-2/4/ED SCENARIO NUMBER: NEW PATH:

LO1 05-01 NRC Examination Scenario 2 Page 1 of 17

RECORD OF CHANGES LO1 05-01 NRC Examination Scenario 2 Page 2 of 17

A. TITLE: LOI-05-01 NRC EXAMINATION SCENARIO 2, SRV Tailpipe Leak In Torus/EOP-2/4/ED B. 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 o n t h e Master Controller with t h e "B" RFP in service.
c. "B" CRD Pump in service.
d. "B Circulating Water Pump in service. " A " secured and available.
e. The A-1 Waterbox is o u t of service per OP-4 Section E t o support single C W pump operation.
3. Preset Conditions:
a. PRESET, RFI-MCO1, Close, (Condenser A-1 Inlet Isolation)
b. PRESET, RFI-MC05, Close, (Condenser A- 1 Outlet Isolation)
c. TRIGGER 2, RR19:B, Controlling FWLC Transmitter Downscale Failure Initially t o 53%, then t o 0% over 600 seconds
d. TRIGGER 4, RD12:42-39, Control Rod Scram.
e. TRIGGER 6, ED18:A, Loss of 1 0 5 0 0 Bus
f. TRIGGER 7, AD08:C, "C" ADS SRV Stuck Open.
g. TRIGGER 7, AD05:C, "C" ADS SRV Seat Leakage ( 1 0 0 % over 300 seconds)
h. TRIGGER 7, ADO6:C, "C" A D S SRV inadvertent opening o n 300 second T D
i. TRIGGER 7, Override "C" SRV Red Lamp o f f o n 299 second T D
j. TRIGGER 9, MS16:C, "C" ADS SRV Discharge Line Rupture ( 100% over 600 seconds)
k. TRIGGER 10, RHOl:D, "D" RHR Pump Trip I . TRIGGER 11, TC04:A-D at 0%. All Bypass Valves failed closed.
4. Consumable Forms and Procedures:

+ AOP-1, Reactor Scram

+ AOP-36, Stuck Open Relief Valve(s)

+ AOP-18, LOSSo f 1 0 5 0 0 BUS LO1 05-01 NRC Examination Scenario 2 Page 3 of 17

C. SCENARIO

SUMMARY

Commitment Document:

The scenario will begin with a reactor startup in progress a t -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 place 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 control of RPV water level, swap level columns and return to automatic level control. The CRS will declare the failed transmitter inoperable. An airline rupture will result in a single control rod scram. The CRS will declare 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 (industry 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 Emergency Depressurization (contingency) is or will soon be required. The scenario will terminate upon the opening of 7 ADS valves.

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.

I Critical Tasks Critical Task #1: Respond to 06U-94B Failure by taking manual control of RPV level per AOP-41.

Maintain RPV water level 196.5 to 206.5 inches.

Critical Task #2: Manual Scram on SRV Opening per AOP-36 before torus water temperature exceeds 110 O F .

Critical Task #3: Complete RPV 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 EVENT SEQUENCE NO.

1. Swap Circulating Water Pumps. (Normal evolution)
2. FWLC Controlling (B) Level Transmitter Fails Downscale. (Instrument Failure)
3. FWLC Controlling (B)Level Transmitter Inoperable (Technical Specification)
4. Single Control Rod Scram on airline rupture (Component Failure)
5. Control Rod declared inoperable (Technical Specification)
6. Loss of 10500 Bus (Component Failure)
7. "C" ADS SRV Leakage followed by Mechanical Opening. (Component Failure)
8. Manual Scram, EOP-2 (Major Transient)
9. "C" ADS SRV Tailpipe Failure in Torus Air Space, EOP-4. (Component Failure)
10. "D"RHR Pump Trip (shortly after starting). (Component Failure)
11. Emergency Depressurization (Major Transient)

D. TERMINATION CUES:

1. 7 ADS Valves Open LO1 05-01 NRC Examination Scenario 2 Page 5 of 17

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION Simulator in RUN Recorder and Alarm Power ON Simulator Checklist Complete Provide Turnover (Attach. 1)

After the shift turnover, All Walkdown the control panels and assume the watch. SAT / UNSAT / NA allow no more than five minutes for panel walkdown CRS Provide crew brief. SAT / UNSAT / NA Order "A" CW pump started and "6" secured SNO Obtain OP-4, Section G.5, Step G.5.3: SAT / UNSAT / NA SNO + At 09-6, Place 36P-1A Control Switch in START SAT / UNSAT / NA SNO + At 09-6, Observe 36MOV-1OOA opening followed by the SAT / UNSAT / NA start of 36P-1A.

SNO + At 09-6, Verify stable pump amperage on 36P-1A. SAT / UNSAT / NA INSTRUCTOR ROLE PLAY SNO + Contact NPO to verify pump discharge pressure 12 psig SAT / UNSAT / NA Report pump discharge pressure a t 12 psig SNO + At 09-16, Verify 4 white lamps lit a t the RPS A and B SAT / UNSAT / NA Power Source Selector Switches.

LO1 05-01 NRC Examination Scenario 2 INSTRUCTOR ACTIVITY I POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION I SNO + A t 09-6, Place 36P-1B Control Switch t o STOP SAT / UNSAT / NA SNO + At 09-6, Verify 36MOV-1OOB Fully Closes. 1 SAT / UNSAT / NA SNO + At 09-6, Verify 36P-1B Amperage is zero SAT / UNSAT / NA INSTRUCTOR NOTE: ANY/ALL Recognize and report High RPV Water Level SAT / UNSAT / NA Trigger 2, "B" FWLC Level Transmitter Failure Attempt to trigger such that SNO responds to initial level transient.

CRITICAL TASK #1: CONTROL RPV WATER LEVEL IN MANUAL Announce entry into AOP-41 and order SNO to complete the SAT / UNSAT / NA actions of AOP-41 EVALUATOR NOTE May provide a direct order to place FWLC in Manual prior to ordering the actions of AOP-41. Reference AP-12.03, 8.9.3.C.

At 09-5, select 06LC-83 or 06-848 t o MANUAL. SAT / UNSAT / NA Stabilize/Control RPV Water Level in the Green Band using manual control potentiometer.

CRITICAL TASK #1 STANDARD: Respond to 06LI-94B Failure by taking manual control of RPV level per AOP- SAT I UNSAT / NA

41. Maintain RPV water level 177 to 222.5 inches (above scram and below turbine trips).

SNO Obtain AOP-41: SAT / UNSAT / NA LO1 05-01 NRC Examination Scenario 2 INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STAN DARD COMMENTS/EVALUATiON SNO + Determine and report that 06LI-94B is failing downscale SAT / UNSAT / NA SNO + Recommend transfer t o 06LI-94A and return t o automatic SAT / UNSAT / NA level control CRS Order transfer t o 06LI-94A and return t o automatic level control SAT / UNSAT / NA per OP-2A CRS Declare 06LT-52B inoperable per T/S 3.3.2.2. Determine that SAT / UNSAT / NA T/S is not applicable until 25% RTP. (Potential LCO)

SNO Obtain OP-2A Section G.30: SAT / UNSAT / NA SNO + At 09-5, Place 06-S1 in A-LEVEL SAT / UNSAT / NA SNO + Place FWLC in Automatic per OP-2A Steps D.3.29 through SAT / UNSAT / NA D.3.30 SNO + At 09-5, verify 06LC-83 is in manual SAT / UNSAT / NA SNO + At 09-5, ensure 06LC-83 setpoint is 197 t o 203 inches SAT / UNSAT / NA SNO + At 09-5, Slowly adjust 06LC-83 manual control SAT / UNSAT / NA potentiometer t o balance 06-84B SNO + At 09-5, Place 06-84B in BAL SAT / UNSAT / NA SNO + At 09-5, control RFPT "B" speed by adjusting 06LC-83 SAT / UNSAT / NA manual control knob LO1 05-01 NRC Examination Scenario 2 -a-

t- INSTRUCTOR ACTIVITY POSITION SNO SNO

+

OPERATOR ACTIONS/STANDARD At 09-5, Adjust 06LC-83 SP ADJUST to balance then place 06LC-83 in BAL.

At 09-5, adjust 06LC-83 setpoint to 197 to 203 inches.

COMMENTS/EVALUATION SAT / UNSAT / NA SAT / UNSAT / NA INSTRUCTOR NOTE ANY/ALL Recognize and report control rod drift and accumulator trouble SAT / UNSAT / NA alarms Trigger 4, Control Rod 42-3 9 scram.

CRS Order actions of AOP-27, Control Rod Drift SAT / UNSAT / NA I ANY /ALL SNO Determine that the drift alarm resulted from a control rod scram Dispatch an NPO to investigate the HCU for control rod 42-39.

~

SAT / UNSAT / NA

~~

SAT / UNSAT / NA INSTRUCTOR ROLE PLAY SNO Relay report t o CRS SAT / UNSAT / NA Report to SNO that the airline on control rod 42-39 has ruptured downstream of the scram solenoids.

CRS Review TS 3.1.3.C declare control rod 42-39 inoperable SAT / UNSAT / NA INSTRUCTOR NOTE ANY /ALL Recognize and report the loss of the 10500 bus. SAT / UNSAT / NA Trigger 6, Loss of 10500 Bus

~ ~~ ~ ~

INSTRUCTOR NOTE CRS Order SNO to perform actions of AOP-18 SAT / UNSAT / NA When requested, report that the 10514 breaker has tripped on ground overcurrent LO1 05-01 NRC Examination Scenario 2 INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION SNO Obtain AOP-18: SAT / UNSAT / NA SNO + At 09-8, Place A and C EDG Load breaker (10502 and SAT / UNSAT / NA 10512) control switches in TRIP then PULL-TO-LOCK SNO + At 09-8, Ensure EDG A and C Tie Breaker (10504) is SAT / UNSAT / NA tripped.

INSTRUCTOR NOTE SNO + Dispatch a NPO to place EDG A and C Local Control SAT / UNSAT / NA RFI-DG23:A and C. Select Switches in MAINT MAINT INSTRUCTOR ROLE PLAY SNO + At 09-8, Place EDG A and C Control Switches in STOP SAT / UNSAT / NA Report t o SNO the A and C EDG Local Control Switches are in Maintenance SNO + Startup SGT Train "B" per OP-20, Section D.2 SAT / UNSAT / NA SNO + At 09-75, Place 01-1 25MOV-12 control switch t o OPEN SAT / UNSAT / NA SNO + At 09-75, Place 0 1 -1 25MOV-14B Control Switch t o OPEN SAT / UNSAT / NA SNO + At 09-75, Depress RB VENT ISOL B pushbutton. SAT / UNSAT / NA SNO + At 09-75, Start all available Drywell Cooling Fans SAT / UNSAT / NA ANY/ALL + Refer t o AOP-18 Attachment 1 for affected loads SAT / UNSAT / NA LO1 05-01 NRC Examination Scenario 2 INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION INSTRUCTOR NOTE ANY/ALL Recognize and report "C" SRV leakage. SAT / UNSAT / NA Trigger 7, "C" SRV leakage followed by mechanical opening CRS Order "B" Loop of RHR in Torus Cooling SAT / UNSAT / NA SNOl Place RHR "B" loop in Torus Cooling per OP-138 or Posted SAT / UNSAT / NA Attachment at the 09-3 panel.

SNOl + A t 09-3, Place RHR "D" control switch in START SAT / UNSAT / NA SNOl + At 09-3, Insert key and select 10MOV-39B to OPEN SAT / UNSAT / NA SNO 1 + At 09-3, Throttle 10MOV-34B t o establish 2 6500 gpm per SAT / UNSAT / NA operating pump.

SNOl + A t 09-3, ensure closure of 1OMOV-16B when loop flow SAT / UNSAT / NA exceeds 1500 gpm.

SNOl + Startup RHR/SW per OP-13C or 09-3 Posted Attachment. SAT / UNSAT / NA SNOl + A t 09-4 or EPIC, Verify RHR/SW A/B keep full alarm status SAT / UNSAT / NA is clear.

SNOl + At 09-3, Start RHR/SW pump B or D SAT / UNSAT / NA SNOl + At 09-3, Throttle 1OMOV-89B t o establish 2500-4000 gpm SAT / UNSAT / NA per loop.

INSTRUCTOR NOTE: ANY/ALL Recognize and report the full opening of "C" SRV and dropping SAT / UNSAT / N A Upon Manual Scram RPV pressure OR RPV Pressure - 900 psig TRIGGER 9 LO1 05-01 NRC Examination Scenario 2 -1 1-

~~ - ~~

INSTRUCTOR ACTIVITY I POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION CRS Announce entry into AOP-36 and direct SNO to perform SAT / UNSAT / NA actions.

Obtain AOP-36: SAT / UNSAT / NA

+ At 09-5, Attempt t o close the "C" SRV by cycling the SAT / UNSAT / NA control switch between AUTO and OPEN. Several cycles may be performed.

INSTRUCTOR NOTE: + Dispatch a NPO to the relay room t o remove the control SAT / UNSAT / NA RFI-ADO2:C "OUT" power fuses for the "C" SRV

+ At 09-3, verify either Torus Temperature Recorder (16-1TR- SAT / UNSAT / NA 131A/B) is operating

+ At 09-3 or EPIC monitor Torus Water Temperature at least SAT / UNSAT / NA every 5 minutes.

INSTRUCTOR ROLE PLAY + At 09-4, observe "C" SRV solenoid lamps extinguished and SAT / UNSAT / NA Report to S N O that "C" SRV fuses tailpipe temperatures still elevated.

are removed.

CRITICAL TASK #2: MANUAL SCRAM ON TORUS TEMPERATURE ANY/ALL Recognize AOP-36 required Manual Scram based upon the SAT / UNSAT / NA 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.

CRS Order SNOl to insert a Manual Scram and perform AOP-1 SAT / UNSAT / NA Immediate Actions.

Order SNO to maintain RPV Water Level a t 177 t o 222.5 inches using Feed and Condensate.

~ ~~~~ ~

SNOl At 09-5, Depress both Manual Scram Pushbuttons SAT / UNSAT / NA LO1 05-01 NRC Examination Scenario 2 -1 2-

INSTRUCTOR ACTIVITY 1 POSITION 1 OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION CRITICAL TASK #2 STANDARD: Scram on SRV Opening per AOP-36 before torus water temperature exceeds SAT / UNSAT I NA 110 OF.

SNOI A t 09-5, Place the Reactor Mode Switch in SHUTDOWN and SAT / UNSAT / NA report to CRS.

SNOI A t 09-5, Select and insert all IRM's and SRM's SAT / UNSAT / NA SNOI A t 09-5, Verify APRM Downscale lights on and report to CRS SAT / UNSAT / NA SNOl A t 09-5, Verify all rods fully inserted and report to CRS SAT / UNSAT / NA SNOI A t 09-5, Verify SDlV Vent and Drain Valves closed. SAT / UNSAT / NA SNO CRS r ~~ ~~ ~~ ~~ ~

A t 09-5 and 09-6, Trend level performance and manipulate GEMAC Master/lndividual controller, RFP "A" discharge valve and RFP trip as necessary t o control RPV Water Level.

Order SNOl to trend RPV Pressure SAT / UNSAT / NA SAT / UNSAT / NA SNOI Make periodic RPV pressure reports SAT / UNSAT / NA ANY/ALL I Recognize and report upward trend in Drywell Pressure and EOP-2 and 4 Entry Condition.

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

LO1 05-01 NRC Examination Scenario 2 -1 3-

1 INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION CRS Order SNO to turn over RPV Level Control to SNOl SAT / UNSAT / NA SNO Turnover RPV Level Control t o SNOl SAT / UNSAT / NA

~~

CRS Order SNO t o Terminate and Prevent Core Spray and RHR per SAT / UNSAT / NA EP-5 SNO Obtain EP-5: SAT / UNSAT / NA SNO + At 09-3, Place 10MOV-27A and B AUTO CONTROL SAT / UNSAT / NA BYPASS Switch in BYPASS SNO + At 09-3, Verify 10MOV-27A and B AUTO CONTROL SAT / UNSAT / NA BYPASS white lamp is lit SNO + A t 09-3, Close 1OMOV-27A and B. SAT / UNSAT / NA SNO + A t 09-3, Place 14MOV-11A and B AUTO ACTUATION SAT / UNSAT / NA BYPASS Switch in BYPASS SNO + At 09-3, Verify 14MOV-11A and B AUTO ACTUATION SAT / UNSAT / NA BYPASS white lamp is lit.

EVALUATOR NOTE 14MOV-11A lamp will be de-energized due t o the bus loss SNO + At 09-3, Close 14MOV-11A and B SAT / UNSAT / NA EVALUATOR NOTE 14MOV-11A will be de-energized due t o the bus loss SNO + Stop Core Spray Pumps A and B SAT / UNSAT / NA LO1 05-01 NRC Examination Scenario 2 INSTRUCTOR ACTIVITY POSITION I OPERATOR ACTIONS/STANDARD COMMENTS/EVALUAT10N CRS Before Torus Pressure reaches 15 psig, order SNO to place the SAT / UNSAT / NA "B" RHR Loop in Torus Spray.

~ ~

SNO Startup "B" RHR in Torus Spray per OP-13B or 09-3 posted SAT / UNSAT / NA attachment:

SNO + At 09-3, Place 1OA-S17B in MANUAL SAT / UNSAT / NA SNO + At 09-3, Verify 10A-DS67B white lamp is lit SAT / UNSAT / NA SNO + At 09-3, Place 10MOV-39B control switch in OPEN SAT / UNSAT / NA INSTRUCTOR NOTE SNO + At 09-3, Throttle open 1OMOV-388 and throttle closed SAT / UNSAT I NA Upon initial stroking of 10MOV-34B t o maximize Torus Spray Flow 1OMOV-38B, Trigger 10, "D" RHR pump trip I

~~ ~~

SNO Report that I'D,' RHR pump has tripped SAT / UNSAT / NA ANY/ALL Determine that all RHR Containment Cooling functions have SAT / UNSAT / NA been lost.

CRS Determine that Torus Pressure cannot be maintained below the SAT / UNSAT / NA Pressure Suppression Pressure Limit.

INSTRUCTOR NOTE: CRS Order SNO1 t o Open all Bypass Valves in anticipation of SAT / UNSAT / NA Emergency Depressurization Trigger 11. All bypass valves fail closed.

SNO 1 A t 09-5, Select Bypass Opening Jack t o open all 4 Bypass SAT / UNSAT / NA Valves. Report that Bypass Valves will not open.

LO1 05-01 NRC Examination Scenario 2 -1 5-

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIO NS/STANDARD COMMENTS/EVALUATION 1 SNOl A t 09-5 and 09-6, Adjust FWLC t o maintain RPV Water Level 177 to 222.5 inches.

~

SAT

~~

UNSAT / NA CRITICAL TASK #3: DEPRESSURIZE THE RPV CRS Before Torus Pressure exceeds the Pressure Suppression SAT / UNSAT / NA Pressure limit, order the SNO t o open 7 ADS Valves SNO A t 09-4, Select all 7 ADS valve control switches t o OPEN. SAT / UNSAT / NA CRITICAL TASK #3 STANDARD: Complete RPV depressurization as directed by EOP-2 and 4 to prevent torus SAT / UNSAT / NA pressure from exceeding the Pressure Suppression Pressure (PSP) limit.

TERMINATE THE SCENARIO LO1 05-01 NRC Examination Scenario 2 -1 6-

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TITLE: LOI-05-01 NRC EXAMINATION SCENARIO 3, Seismic Event, AOP-31, MSL Break in TB SCENARIO NUMBER: NEW PATH:

CRS Primarv 09-5 ODerator LO1 05-01 NRC Examination Scenario 3 Page 1 of 15

RECORD OF CHANGES LO1 05-01 NRC Examination Scenario 3 Page 2 of 15

A. TITLE: LOI-05-01 NRC EXAMINATION SCENARIO 3, Seismic Event, AOP-31, MSL Break in TB B. SCENARIO SETUP:

1. Initial Protected IC 134
2. Special Instructions:
a. Plant operating normally at 7 5 % CTP
3. Preset Conditions:
a. Preset, RP13, PClS Group 1 Isolation Failure.
b. Preset, RD13:30-15, Control Rod Fail To Scram
c. Preset, AD07:J, G, C and B. Several ADS SRVs Fail To Open
d. Trigger 2, RFI-EPO9, Seismic Event Alarm
e. Trigger 2, ANN-09-6-4-11 , RFP A High Vibration, CRYWOLF
f. Trigger 2, RFP A DDR-10 Vibration Point with Step rise followed b y s l o w rise.
g. Trigger 3, RFI-HP15, HPCl AOP Breaker Trip.
h. Trigger 5, M C O l , Loss of Main Condenser Vacuum,(35% over 1 8 0 seconds)
i. Trigger 7, MS05, Main Steam Line Break in t h e Turbine Building ( 2 5 % over 300 seconds)
4. Consumable Forms and Procedures:

4 AOP-1 , Reactor Scram 4 A O P - I 4, Earthquake 4 AOP-31 , Loss of Condenser Vacuum 4 AOP-40, Main Steam Line Break LO1 05-01 NRC Examination Scenario 3 Page 3 of 15

C. SCENARIO

SUMMARY

I Commitment Document:

The scenario will begin with the reactor at -75% 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 declare 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 Line 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.

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

I 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 O F .

LO1 05-01 NRC Examination Scenario 3 Page 4 of 15

EVENT EVENT SEQUENCE NO.

1. Raise Power using Recirculation Flow (Reactivity)
2. Seismic Event resulting in RFPT slight vibration and CRYWOLF alarm (Component)
3. HPCl Aux Oil Pump Breaker Trip (Component) 4 HPCl Inoperable (Technical Specification)
5. Loss of Condenser Vacuum (Component)
6. I AOP Required Power Reduction with Rods and Recirculation (Reactivity Manipulation)
7. Main Steam Line Break in the Turbine Building with Failure To Automatically Isolate (Major)
8. One Control Rod Fails t o Scram (Component)
9. RClC Level Control and SRV's Pressure Control IO. Several SRV's Fail t o Open (Instrument/Component)

D. TERMINATION CUES:

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

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION Simulator in RUN Recorder and Alarm Power ON Simulator Checklist Complete

~~ ~~

Provide Turnover (Attach. 1)

~~

After the shift turnover, All Walkdown the control panels and assume the watch. SAT / UNSAT / NA allow no more than five minutes for panel walkdown

~~~~

CRS Provide crew brief. SAT / UNSAT / NA Order raising Reactor Power to 9 2 % using Recirculation Flow.

____ ~

SNO Obtain OP-27, Section E ; SAT / UNSAT / NA SNO + At 09-4, Alternately raise recirculation pump speeds in SAT / UNSAT / NA 1-3% increments while monitoring:

0 Core Flow maintained less that 77 Mlbm/hr 0 J e t Pump Loop Mismatch 1 .5% (3.85 Mlbm/hr)

INSTRUCTOR NOTE ANY /ALL Recognize and report RPP High Vibration Alarm and EPIC SAT / UNSAT / NA Seismic Event alarm Trigger 2, Seismic Event/RFP Vibration CRS Direct SNO to enter and perform AOP-14 SAT / UNSAT / NA Direct SNO to respond to annunciator 09-6-4-1 1

~ ~ ~~

SNO At 09-6, Monitor and trend RFP A Vibration on 31TR-100A SAT / UNSAT / NA SNO Obtain AOP-14: SAT / UNSAT / NA LO1 05-01 NRC Examination Scenario 3 INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION INSTRUCTOR ROLE PLAY SNO + Dispatch NPO's throughout plant to inspect for damage SAT / UNSAT / NA No observable damage and unusual indications INSTRUCTOR ROLE PLAY SNO + At 27CAD, confirm that 27SOV-129A or B is open. SAT / UNSAT / NA Report 27SOV-129A is Open EVALUATOR NOTE This activity is simulated by candidate phoning the instructor console from the back panel area.

INSTRUCTOR ROLE PLAY SNO/SNO 1 + Contact NMP Unit 2 or National Center For Earthquake SAT / UNSAT / NA Report 0.1 Og ( >OBE) Engineering Research to determine the magnitude of the earthquake.

~~~

INSTRUCTOR NOTE ANY/ALL Recognize and report annunciator 09-3-3-38 and the loss of SAT / UNSAT / NA lamp indication for the HPCl Aux Oil Pump.

Trigger 3, HPCl AOP Breaker Trip CRS Order SNO t o respond per the ARP SAT / UNSAT / NA SNO Obtain ARP-09-3-3-38: SAT / UNSAT / NA

~~

INSTRUCTOR NOTE SNO + Dispatch NPO to investigate pump and breaker SAT / UNSAT / NA Report that the pump is fine but the breaker is tripped with an acrid odor from the breaker cubicle.

CRS Deciare HPCl Inoperable. Per T/S 3.5.1 Condition C, must SAT / UNSAT / NA immediately verify RClC Operable and restore HPCl within 1 4 days INSTRUCTOR NOTE ANY/ALL Recognize and report the slow loss of condenser vacuum SAT / UNSAT / NA Trigger 5, Loss of Condenser Vacuum LO1 05-01 NRC Examination Scenario 3 I INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATlON CRS Direct SNO to perform the actions of AOP-31 SAT / UNSAT / NA CRS Set a manual scram benchmark for SNOl. SAT / UNSAT / NA (Typically - 2 3 inches)

SNO Obtain AOP-3 1: SAT / UNSAT I NA SNO + A t 09-6, Trip the Recombiner and verify The Hydrogen SAT / UNSAT / NA Addition System trips INSTRUCTOR ROLE PLAY + Dispatch an NPO t o verify valve positions a t the Off Gas SAT / UNSAT / NA All valve in correct positions System Recombiner Panel (01-1 070GR) per AOP-14, Step C.5.4 INSTRUCTOR NOTE SNO + Dispatch NPO t o place spare SJAE's in service SAT / UNSAT / NA RFI-MC13-20 t o ON for all off service SJAE's SNO + At 09-6, Observe Off Gas Flow on 38FR-101 and SAT / UNSAT / NA determine that the source of condenser vacuum loss is air inleakage INSTRUCTOR ROLE PLAY SNO + Dispatch NPO(s) t o inspect for source of air inleakage. SAT / UNSAT / NA Report a tear in the "A" RFPT Exhaust Boot SNO + At 09-7 monitor Turbine Steam Seal Pressure and SPE SAT / UNSAT / NA Vacuum CRITICAL TASK #I  : POWER REDUCTION ON DEGRADING CONDENSER VACUUM INSTRUCTOR NOTE I CRS I Trend Condenser Vacuum and direct SNO t o perform a power I SAT UNSAT NA reduction with recirculation flow t o combat trend. Limit the Adjust severity of MCO1 t o SNO t o maintain 2 5 0 % Core Flow. Rapid rates may apply.

force power reduction

~~

LO1 05-01 NRC Examination Scenario 3 I INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD CO MMENTS/EVALUAT10N SNO Obtain OP-27, Section E: SAT / UNSAT / NA (Normal Rates a t 5 200 Mwth/min)

~____

INSTRUCTOR NOTE SNO + At 09-4, Alternately lower recirculation pump speeds in SAT / UNSAT / NA After several adjustments, 1-3% increments while monitoring:

adjust MCOl severity to o Jet Pump Loop Mismatch L. 5 % (7.7 Mlbm/hr) force rapid rates.

o Core Flow > 50%

~~

SNO Obtain OP-27, Section G.l (Rapid Rates): SAT / UNSAT / NA SNO + A t 09-4, Simultaneously lower recirculation pump SAT / UNSAT / NA speeds while monitoring:

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

o RPV Water Level < 222.5 inches I INSTRUCTOR NOTE CRS Trend condenser vacuum and direct SNOl to insert Control Rod Cram Groups to combat trend SAT / UNSAT / NA Adjust severity of MCOl to force power reduction SNOl Obtain RAP-7.3.16, Attachment 1 (Posted at 09-5): SAT / UNSAT / NA SNOl + At 09-5, Select control rods in the first cram group SAT / UNSAT / NA INSTRUCTOR NOTE SNOl + At 09-5, Fully insert the selected control rods until all SAT / UNSAT / NA Adjust MCOl severity t o a control rods in cram group 1 are inserted.

slowly improving trend in condenser vacuum CRITICAL TASK #1 STANDARD: Power Reduction on Degrading Condenser Vacuum per AOP-31 to prevent SAT / UNSAT / NA turbine trip(s) on low condenser vacuum.

LO1 05-01 NRC Examination Scenario 3 INSTRUCTOR ACTIVITY I POSITION I OPERATOR ACTIONS/STANDARD I COMMENTS/EVALUATION INSTRUCTOR NOTE ANY/ALL I Recognize and report elevating temperatures in the Main Steam I SAT / UNSAT / NA Tunnel.

Trigger 7, MSL Break in TB CRI' CRS Direct SNO to perform the actions of AOP-40 SAT / UNSAT / NA SNO Obtain AOP-40 and inform CRS that MSlV closure is required. SAT / UNSAT / NA CRS Direct SNOl to perform a manual scram and AOP-1 immediate SAT / UNSAT / NA actions

~

CRS Direct SNO t o maintain RPV Water Level a t 177-222.5 inches SAT / UNSAT / NA using Feed and Condensate SNOl + At 09-5, Depress Manual Scram Pushbuttons SAT / UNSAT / NA I SNol SNOl

+

+

A t 09-5, Place Reactor Mode Switch in SHUTDOWN and report t o CRS At 09-5, select and fully insert all SRM's and IRM's I SAT UNSAT NA' SAT / UNSAT / NA SNOl + At 09-5, Observe APRM downscale indications and report SAT / UNSAT / NA to CRS SNOl + A t 09-5, Trip the Main Turbine SAT I UNSAT / NA SNOl + A t 09-5, Verify all rods Full In. Report t o CRS that Control SAT / UNSAT / NA Rod 30-15 is not full in. Currently at position 48 I

LO1 05-01 NRC Examination Scenario 3 INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION SNOl + At 09-5, Ensure SDlV Vent and Drain Valves are closed SAT / UNSAT / NA SNOl + At 09-8 Ensure 4KV Bus transfers t o Reserve Station SAT / UNSAT / NA Service SNOl + At 09-6, Ensure at least 1 Circulating Water Pump is SAT / UNSAT / NA running.

SNO Trend level performance and manipulate GEMAC SAT / UNSAT / NA Master/lndividual controllers, RFP discharge valves and RFP trip as necessary t o control level. Announce EOP-2 entry condition

~ ~~

CRS Enter EOP-2 SAT / UNSAT / NA

~

Obtain AOP-40: SAT / UNSAT / NA SNO + A t 09-4, Close all 8 MSIV's SAT / UNSAT / NA SAT / UNSAT / NA SNO + A t 09-75, Isolate Control Room and Relay Room Ventilation SAT / UNSAT / NA per OP-55B (Section G . l )

SNO + At 09-75, Place Control Room Vent Control Switch in ISOL SAT / UNSAT / NA SNO + At 09-75, Verify Supply and Exhaust Dampers Close SAT / UNSAT / NA SNO + A t 09-75, Verify Recirculation Dampers Open SAT / UNSAT / NA LO1 05-01 NRC Examination Scenario 3 -1 1-

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION

~~ ~

SNO + At 09-75, Verify Start of 70FN-6A or B SAT / UNSAT / NA

~~

SNO + Dispatch NPO t o Stop 70FN-1 and Close 7ODMPR-105 SAT / UNSAT / NA SNO + At 09-75, Place Relay Room Ventilation Control Switches SAT / UNSAT / NA in ISOL SNO + At 09-75, Verify closure of Relay Room Supply and SAT / UNSAT / NA Exhaust Dampers and the Vent Damper.

SNO + Dispatch NPO t o place TSC Filtered Ventilation in service SAT / UNSAT / NA per OP-59B CRS Direct SNOl t o insert Control Rod 30-1 5 per AOP-1 SAT / UNSAT / NA CRS Direct SNO t o Pressure Control at 800 t o 1000 psig using the SAT / UNSAT / NA SRV's

~~

SNO A t 09-4, Operate SRV's in sequence (Posted at 09-4) to SAT / UNSAT / NA maintain RPV Pressure.

SNO Recognize and report the Failure of SRV's t o operate and SAT / UNSAT / NA continue in sequence t o maintain RPV pressure in band

~~

SNO 1 Obtain AOP-1, Section C.3: SAT IUNSAT INA

~

SNOl + At 09-5, Place RWM keylock switch in BYPASS SAT / UNSAT / NA SNOl + At 09-5, Place SDlV High Level Trip Keylock Switch in SAT / UNSAT / NA BYPASS LO1 05-01 NRC Examination Scenario 3 -1 2-

~~

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION

~

SNOl + At 09-5, Place Scram Reset Switch in Group 2&3 then 1&4 SAT / UNSAT / NA SNOl + Select Control Rod 30-15 SAT I UNSAT / NA SNOl + Fully insert Control Rod 30-15 using RMCS SAT / UNSAT / NA CRS Direct SNO t o maintain RPV Level 177-222.5 inches using SAT / UNSAT / NA RClC

~ ~~ ~~

SNO Obtain OP-19 Section D or 09-4 Posted Attachment SAT / UNSAT / NA 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 SNO 4 Start the RClC Vacuum Pump SAT / UNSAT / NA

~

SNO 4 Open 13MOV-132 SAT / UNSAT / NA SNO + Open 13MOV-131 SAT / UNSAT / NA SNO 6 Open 13 MOV-21 SAT / UNSAT / NA SNO + Ensure Closed 13MOV-27, 13AOV-34 and 13AOV-35 SAT / UNSAT / NA LO1 05-01 NRC Examination Scenario 3 -1 3-

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==%i&gy Nuclear Northeast James A. FitzPatrick Nuclear Power Plant OPERATIONS TRAINING PROGRAMS JOB PERFORMANCE MEASURE SRO NEW TASK TITLE: LOI-05-01 NRC EXAM E-PLAN IMPLEMENTATION FOR SCENARIO 2 APPL. TO JPM NUMBER REV: 0 DATE: 4/26/05 NRC K/A SYSTEM NUMBER: 2.4.41 4.1 JAF TASK NUMBER: JAF QUAL STANDARD NUMBER:

ESTIMATED COMPLETION TIME: 15 Minutes S U BMITTED : OPERATION REVIEW:

CANDIDATE NAME:

JPM Completion: ( 1 Simulated ( X ) Per Location: ( ) Plant DATE PERFORMED: -. Minutes PERFORMANCE EVALUATION: ( ) Satisfactory ( ) Unsatisfactory EVALUATOR:

SIGNATURE/PRINT Page 1 of 8

JOB PERFORMANCE MEASURE RECORD AND CHECKLIST SRO NEW TASK TITLE: LOI-05-01 NRC EXAM E-PLAN IMPLEMENTATION FOR SCENARIO 2 APPL. TO JPM NUMBER Current Update: 4126IO 5 By: RWD Date Int.

Outstanding Items:

Technical Review Additional Information Questions and Answers Validation Procedural Change Required X None Comments:

Page 2 of 8

JOB PERFORMANCE MEASURE REQUIRED TASK INFORMATION SRO NEW TASK TITLE: LOI-05-01 NRC EXAM E-PLAN IMPLEMENTATION FOR SCENARIO 2 APPL. TO JPM NUMBER

1. SAFETY CONSIDERATIONS A. None
11. REFERENCES A. JAF Emergency Plan Implementing Procedures IAP-2, Rev. 25 B. Emergency Plan Implementation Checklist, IAP-1, Rev. 32 111. TOOLS AND EQUIPMENT A. None IV. SET UP REQUIREMENTS A. This JPM is completed as followup after the scenario progress has been frozen.

V. EVALUATOR NOTES A. If performing JPM in the plant, inform the candidate that the conditions of each step need only be properly identified and not actually performed.

B. The candidate should, a t a minimum, identify the change in equipment status light indication when equipment operation is simulated.

VI. TASK CONDITIONS A. Scenario Terminated

  • - CRITICAL STEP Page 3 of 8

VII. INITIATING CUE Based on the events that have just occurred determine if the current circumstances warrant classification in accordance with the JAF Emergency Plan If classification is warranted, determine the appropriate classification level per IAP-2 and implement the Emergency Plan per IAP-1.

TASK STANDARD The candidate will evaluate the events and resulting plant conditions from the scenario, declare the E-plan emergency level using IAP-2, Attachment 2.1 and implement the emergency plan per the IAP-1 checklist.

I STEP I STANDARD I EVALUATION / COMMENT

1. Obtain/Approach IAP-2, Attachment Candidate obtains the procedure or approaches the SAT / UNSAT 2.1 posted attachment.
2. Recognize the applicable conditions Candidate recognizes that the scenario events SAT / UNSAT included Reactor Coolant leak to the primary containment.
3. Confirm the conditions Candidate reviews IAP-2 Technical Bases for SAT / UNSAT expected declarations.
  • 4. Classify the event Candidate selects ALERT 3.1.1 SAT / UNSAT Primary containment pressure cannot be maintained < 2.7 psig due to coolant leakage. *CRITICAL STEP*

5 Implement the E-plan Candidate obtains IAP-1 Attachment 1 SAT / UNSAT I EVALUATOR NOTE If necessary, remind the candidate of the initiating cue "implement the Emergency Plan per IAP-1" Page 4 of 8

STEP STANDARD I EVALUATION / COMMENT A. Implement EAP-1 .if OFFSITE Request a control room communications aid to report to SAT / UNSAT NOTIFICATIONS, in order to notify the control room and commence obtaining Part 1 offsite agencies. Notification data.

EVALUATOR NOTE Act as communications aid and acknowledge order to commence data collection.

B. If a General Emergency has been Candidate determines that this step is not necessary as SAT / UNSAT declared in accordance with IAP-2, a General Emergency has not been declared.

CLASSIFICATION OF EMERGENCY CONDITIONS, then recommend protective actions in accordance with procedure EAP-4, DOSE ASSESSMENT CALCULATIONS, , Initial Protective Actions.

Page 5 of 8

STEP STANDARD EVALUATION / COMMENT 8 C. Per EAP-1.1, notify security (ext. Candidate contacts security (7001 in simulator) to SAT / UNSAT 3456) to activate pagers, and if activate pagers and CAN. Candidate provides the necessary CAN. following information:

Pagers should be activated at the NUE, and once again at the ALERT This is a (1) actual emergency or (2) drill.

or higher classification if escalation Alert and time declared.

from the NUE occurs.

Provide the following information: Activate pagers: YES

1. This is: (1) an actual emergency, OR (2) a drill, OR ( 3 ) a pagerlon-call test Pager code 1 or 2 2
2. Emergency Classification and time Activate CAN: YES declared.

3.Activate Pagers YES NO Activate facilities Group 2.

a. IF YES, provide 3 digit Pager Code
4. Activate CAN YES NO
5. Facilities activated:
a. "Group 1 'I for (CWrSClOSC /JAF) or
b. "Group 2 for (CFUTSC/OSC/JAF/EOF/JNC) or
c. Selected:

CR/TSC/OSC/JAF/EOF/JNC IF Security is unable to activate pagers and/or CAN, THEN the Shift Manager should utilize EAP-17, Attachment 4 to make the activation. CAN will call 315-349-6261 (located near RECS line) for verification of CAN activation. This is the only CR number authorized for CAN activation verification from the CR.

Page 6 of 8

I STEP I STANDARD EVALUATION / COMMENT 9 PAGER CODES See item 8 above SAT / UNSAT 1=Actual Event 2=Drill or Exercise 3=Pager/on-call test only 1 =NUE 2=Alert 3 =SAE 4 =GE 9 =None 1 = Report to CR/OSC/TSC 2 = Report to CR/OSC/TSC/EOF/JNC 3 = On duty only report to CR/OSC/TSC/EOF/JNC 7 = Personnel assigned a pager call CAN 800-205-5175 8 = All personnel report to EOF for further instructions 9 = No response required 1 10 D. Activate emergency response See item 8 above SAT / UNSAT facilities in accordance with the Facility Activation Requirements matrix in Section 4.1 EVALUATOR: Terminate the task at this point.

Page 7 of 8

INlT ATING CUE Based on the events that have just occurred determine if the current circumstances warrant classification in accordance with the JAF Emergency Plan If classification is warranted, determine the appropriate classification level per IAP-2 and implement the Emergency Plan per IAP-I.

I Page 8 of 8

m

-== Entw-gy Nuclear Northeast James A. FibPatrick Nuclear Power Plant OPERATIONS TRAINING PROGRAMS JOB PERFORMANCE MEASURE SRO NEW TASK TITLE: LOI-05-01 NRC EXAM E-PLAN IMPLEMENTATION FOR SCENARIO 1 APPL. TO JPM NUMBER REV: 0 DATE: 4/26/05 NRC K/A SYSTEM NUMBER: 2.4.41 4.1 JAF TASK NUMBER: JAF QUAL STANDARD NUMBER:

ESTIMATED COMPLETION TIME: 15 Minutes SUBMITTED: OPERATION REVIEW:

APPROVED:

- - _ _ 1 _ 1 _ - _ - - - - - - _ _ _ _ _ _ _ _ _ _ _ 1 _ 1 _ _ _ _ _ _ 1 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

CANDIDATE NAME: S.S. NUMBER:

JPM Completion: ( ) Simulated ( X ) Performed Location: ( ) Plant ( X ) Simulator DATE PERFORMED: TIME TO COMPLETE: Minutes PERFORMANCE EVALUATION: ( ) Satisfactory ( ) Unsatisfactory

- - - - _ - - - - - - - - - - - - - _ - _ _ _ _ _ 1 _ _ _ _ _ 1 _ 1 1 _ _ _ 1 _ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE)

EVALUATOR:

SIGNATURE/PRINT Page 1 of 8

JOB PERFORMANCE MEASURE RECORD AND CHECKLIST SRO NEW TASK TITLE: LOI-05-01 NRC EXAM E-PLAN IMPLEMENTATION FOR SCENARIO 1 APPL. TO JPM NUMBER Current Update: 4/26/05 By: RWD Date Int.

Outstanding Items:

Technical Review Additional Information Questions and Answers Validation Procedural Change Required X None Comments:

Page 2 of 8

JOB PERFORMANCE MEASURE REQUIRED TASK INFORMATION SRO NEW TASK TITLE: LOI-05-01 NRC EXAM E-PLAN IMPLEMENTATION FOR SCENARIO 1 APPL. TO JPM NUMBER

1. SAFETY CONSIDERATIONS A. None II. REFERENCES A. JAF Emergency Plan Implementing Procedures IAP-2, Rev. 25 B. Emergency Plan Implementation Checklist, IAP-1, Rev. 32 111. TOOLS AND EQUIPMENT A. None IV. SET UP REQUIREMENTS A. This JPM is completed as followup after the scenario progress has been frozen.

V. EVALUATOR NOTES A. If performing JPM in the plant, inform the candidate that the conditions of each step need only be properly identified and not actually performed.

B. The candidate should, a t a minimum, identify the change in equipment status light indication when equipment operation is simulated.

VI. TASK CONDITIONS A. Scenario Terminated

  • - CRITICAL STEP Page 3 of 8

VII. INITIATING CUE Based on the events that have just occurred determine if the current circumstances warrant classification in accordance with the JAF Emergency Plan If classification is warranted, determine the appropriate classification level per IAP-2 and implement the Emergency Plan per IAP-1.

TASK STANDARD The candidate will evaluate the events and resulting plant conditions from the scenario, declare the E-plan emergency level using IAP-2, Attachment 2.1 and implement the emergency plan per the IAP-1 checklist.

I STEP STANDARD EVALUATION / COMMENT

1. Obtain/Approach IAP-2, Attachment Candidate obtains the procedure or approaches the SAT / UNSAT 2.1 posted attachment.
2. Recognize the applicable conditions Candidate recognizes that the scenario events SAT / UNSAT included a failure to scram.
3. Confirm the conditions Candidate reviews IAP-2 Technical Bases for SAT / UNSAT expected declarations.
  • 4. Classify the event Candidate selects SAE-2.2.2 SAT / UNSAT
  • CRITICAL STEP*

Page 4 of 8

STEP STANDARD EVALUATION / COMMENT

~~ ~~

Candidate obtains IAP-1 Attachment 1 SAT / UNSAT Implement the E-plan EVALUATOR NOTE If necessary, remind the candidate of the initiating cue implement the Emergency Plan per IAP-1 A. Implement EAP-1. l , OFFSITE Request a control room communications aid to report to SAT / UNSAT NOTIFICATIONS, in order to notify the control room and commence obtaining Part 1 offsite agencies. Notification data.

EVALUATOR NOTE Act as communications aid and acknowledge order to commence data collection.

~ ~~ ~~

B. If a General Emergency has been Candidate determines that this step is not necessary as SAT / UNSAT declared in accordance with IAP-2, a General Emergency has not been declared.

CLASSIFICATION OF EMERGENCY CONDITIONS, then recommend protective actions in accordance with procedure EAP-4, DOSE ASSESSMENT CALCULATIONS, , Initial Protective Actions.

Page 5 of 8

STEP STANDARD EVALUATION / COMMENT

~~

8 C. Per EAP-1.I, notify security (ext. Candidate contacts security (7001 in simulator) to SAT / UNSAT 3456) to activate pagers, and if activate pagers and CAN. Candidate provides the necessary CAN. following information:

Pagers should be activated at the NUE, and once again at the ALERT This is a (1) actual emergency or (2) drill.

or higher classification if escalation Site Area Emergency and time declared.

from the NUE occurs.

Provide the following information: Activate pagers: YES

1. This is: (1) an actual emergency, OR (2) a drill, OR ( 3 ) a pagedon-call test Pager code 1 or 2 2
2. Emergency Classification and time Activate CAN: YES declared.

3.Activate Pagers YES NO Activate facilities Group 2.

a. IF YES, provide 3 digit Pager Code
4. Activate CAN YES NO
5. Facilities activated:
a. "Group 1 for (CR/TSC/OSC /JAF I'

or

b. "Group 2 for (CR/TSC/OSC/JAF/EOF/JNC) or
c. Selected:

CR/TSC/OSC/JAF/EOF/JNC IF Security is unable to activate pagers and/or CAN, THEN the Shift Manager should utilize EAP-17, Attachment 4 to make the activation. CAN will call 315-349-6261 (located near RECS line) for verification of CAN activation. This is the only CR number authorized for CAN activation verification from the CR.

Page 6 of 8

STEP STANDARD EVALUATION / COMMENT 9 PAGER CODES See item 8 above 1=Actual Event 2=Drill or Exercise 3=Pager/on-call test only 1 =NUE 2=Alert 3 =SAE 4 =GE 9 =None 1 = Report to CR/OSC/TSC 2 = Report to CR/OSC/TSC/EOF/JNC 3 = On duty only report to CR/OSC/TSC/EOF/JNC 7 = Personnel assigned a pager call CAN 800-205-5175 8 = All personnel report to EOF for further instructions 9 = No response required 10 D. Activate emergency response facilities in accordance with the Facility Activation Requirements matrix in Section 4.1 Page 7 of 8

INITIATING CUE Based on the events that have just occurred determine if the current circumstances warrant classification in accordance with the JAF Emergency Plan If classification is warranted, determine the appropriate classification level per IAP-2 and implement the Emergency Plan per IAP-1.

Page 8 of 8