ML112030794

Millstone Unit 3 - Draft Operating Exam (Sections a, B, and C) (Folder 2)

ML112030794
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Site:	Millstone
Issue date:	05/27/2011
From:	Minnich D Dominion Nuclear Connecticut
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MILLSTONE POWER SIMULATOR EXAM GUIDE APPROVAL SHEET Exam Title: Loss of Secondary Heat Sink Revision:

o ID Number: 2K11 NRC-01 This document is the property of the Millstone Power Station which controls its distribution.

Further transfer, copying, or modification of this document is strictly prohibited without the written consent of the Millstone Power Station. Submitted by: D. Minnie 03/21/11 /kl-Date Validated by: 5L9/11 Date Approved by: Training Supervisor ff' at STOP THINK ACT REVIEW

SUMMARY

OF Change Description REVlCHG Date of Change THINK ACT REVI.EW SECTION SIMULATOR EXAM GUIDE TABLE OF CONTENTS SECTIONS LISTED IN ORDER 1. Cover Page 2. Table of Contents 3. Exercise/Exam Overview 4. Exam Guide Attachments:

Shift Turnover Validation Scenario Outline Attributes Summary of Page 3 of 80 SECTION EXAM Title: Loss of Secondary Heat Sink 10 Number: 2K11 NRC-01 Revision:

Q The Session will begin with the plant at 100% power and at end of life. The "A" TPCCW pump is out of service for oil replacement.

Shortly after turnover a PEO on rounds will report a large quantity of lube oil around the "8" MDAFW pump. The lube oil system bubbler assembly will appear to have been inadvertently damaged by a maintenance crew moving heavy equipment in the vicinity of the pump. Tech Spec 3.7.1.2 {72 hr action statement}

should be entered and actions taken to remove the MDAFW Pump from service. Assessments will report the expected return of the pump in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. While Tech Specs and other actions for the MDAFW Pump are in progress, the controlling channel of Pressurizer level will slowly fail to a point just below program level, resulting in charging flow increasing.

The crew should use channel checking and other diagnostics skills to determine the failure is an instrument malfunction and not an RCS leak. Pressurizer level on the failed instrument will cause charging flow to rise until manual control of charging flow is established.

The crew should enter AOP 3571, Instrument Failure Response, to address and mitigate the failed instrument up to and including the tripping of associated bistables.

Applicable Tech Specs are identified within the guide. After actions of AOP 3571 are complete, 3MSS-PT20A will fail high resulting in PV20A ('A' SG Atmospheric Relief Valve) opening. The crew should take manual control of the atmospheric relief valve controller and close PV20A once SG Pressure is verified to be less than 1125 psig. The crew should identify the cause as a failed instrument and address the problem using ARP MB5C 5-7, MAINSTEAM RELIEF W NOT CLOSED, and then AOP 3571, Instrument Failure Response.

Event number 4 is a Loss of Main Condenser Vacuum that will begin slowly. The crew initially enters AOP 3559, Loss Of Condenser Vacuum, to commence a rapid load reduction in accordance with AOP 3575, Rapid Downpower.

As load is lowered approximately 15% and with the concurrence of the lead examiner, the condenser vacuum will stabilize and the crew can stop the load reduction.

Once the down power is stopped and the plant stable, a loss of emergency bus 34C will occur. The crew will mitigate the event by carrying out the actions as specified in AOP 3577, Loss of Power to a 4. 16KV Emergency Bus. Actions will include aligning service water, RPCCW and CVCS as required for a loss of bus 34C. Tech Specs will need to be addressed.

Once actions are complete up to bus restoration, an unisolable reactor coolant leak will occur in CTMT. The crew should carry out the actions as specified in AOP 3555, Reactor Coolant Leak, but with normal charging and letdown isolated due to the loss of Bus 34C, there is nothing the crew can do to control the inventory loss, and the leak is severe enough to require a Reactor Trip and Safety Injection.

Upon the Manual Reactor Trip, the Page 4 of 80 Main Turbine fails to trip automatically or manually, and requires a turbine runback [Critical Task]. The crew should carry out the actions of E-O, Reactor Trip Or Safety Injection.

The 'B' SI pump will fail to auto-start

('A' SI pump has no power) ang will have to be manually started [Critical Task). The size of the break will be such that RCS pressure lowers sufficiently to require the RCPs be tripped based on E-O Foldout Page criteria [Critical Task]. At a predetermined point in E-O, the TD AFW pump trips on overspeed.

At step 17 of E-O, the crew will transition to FR-H.1, Response To Loss Of Secondary Heat Sink, and establish feedwater flow to at least one S/G [Critical Task1. Attempts to restore Auxiliary Feedwater will not be successful (the 'A' MD AFW pump is deenergized due to loss of bus 34C, 'B' MD AFW pump in PTL due to no oil). The crew should recognize that feeding SGs from the Main Feed system (MDMFP) is their most likely success path. Once a secondary heat sink is established, the crew will transition back to E-O, step 18 and then transition to E-1. Loss of Reactor or Secondary Coo/ant. The scenario will end when the crew has made the decision to transition to ES-1.2, Post LOCA Coo/down and Depressurization. The SRO candidate (US) should classify this event as an ALERT-Charlie One based on failure of the RCS Barrier. BA 1. The SRO candidate (US) may consider an update to the classification due to Heat Sink being RED if required feed flow cannot be established within 15 minutes. Duration of Exam: 120 minutes Page 5 of 80 SECTION 4 EXAM GUIDE Title: Loss of Secondary Heat Sink ID Number: 2K11 NRC-01 Revision:

Q All Control Room Conduct, Operations and Communications shall be in accordance with 100, Conduct of Operations. "Review the Simulator Operating Limits (design limits of plant) and the Simulator Modeling Limitations and Anomalous Response List prior to performing this exam scenario on the simulator.

The evaluators should be aware if any of these limitations may be exceeded." (NSEM 6.06) Page 6 of 80 SECTION EXAM Title: Loss of Secondary Heat Sink 10 Number: 2K11 NRC-01 Revision:

Q SIMULATOR PROBLEMS DURING EXAMS It is the responsibility of the Instructors in the simulator to insure that training interruptions have a minimum negative impact on the Crew and the training we provide. Use your judgment on whether to stop the training and how the training should be commenced after the problem is corrected.

Be aware that at all times the Operators should treat the simulator as if it were the plant and you too should treat it as much like the plant as possible when they are in the simulator.

As soon as the Instructors are aware of a simulator problem that wlll adversely affect the training in progress (computer fault, etc.) the Instructor should: Place the simulator in FREEZE if possible. Announce to the Crew that there is a simulator problem. Request that the Crew either standby (for minor trouble that can be handled quickly) or leave the simulator control room. (The Crew should leave the simulator for problems which involve major switch alignments). Deal with the problem (reboot, close tripped breaker, call STSB, etc.) After the Instructors believe the simulator is restored to service, the Crew should be told how training will continue.

If it is possible and felt to be acceptable to the Instructors, training can begin where it left off with an update on plant parameters and each Crew member is prepared to restart. If training will not begin where it left off, the crew should be told how and where training will begin again. Once the Crew has been told how and where training will begin, have the crew conduct a brief so that the Instructor can insure that the crew has all the necessary information to continue with the scenario. Once all Crew members and Instructors are satisfied that they have the necessary information to continue the scenario, place the simulator in RUN and announce to the Crew that you have continued the training session. Page 7 of 80

-:CTION 4 Lesson Title: Loss of Secondary Heat Sink 10 Number: 2K11 NRC-01 Revision:

Q INITIAL SETUP INSTRUCTIONS Simulator Setup Checklist VERIFY that the current approved training load is loaded. REMOVE the step counter OVERRIDE and allow the counters to step out during the IC reset. RESET to IC# 18 or Temp IC# N/A, LOAD Schedule file 2K11 NRC-01 and, if needed, LOAD or VERIFY BASIC.EVT file Wait at least one minute, PLACE Simulator to RUN. ENSURE Simulator fidelity items cleared If Necessary, RESET the Plant Calorimetric at the Instructor Station PPC going to Unit 3 top menu, then selecting BOP Menu, then selecting Plant Calorimetric Menu. Verify .calorimetric calculation selected appropriately for the plant conditions. (Normally steam flow for 100% power. CHECK the STEP COUNTERS at correct position for plant conditions. PLACE -.1..._ tiles under the DEMINS IN SERVICE lama cord label on MB6. PLACE the Main Turbine on the LOAD LIMITER and ENSURE Standby Load Set MATCHED if conditions require. PLACE the Westronic (2) recorders in active/run by depressing up or down arrow for each. For the NR4S recorder:

select group 3 or 4 at power setting CLEAR DCS alarms on MB7 and BOP console. Reset SMM alarms if required. Select Status Grid on the RMS console. VERIFY annunciator, "COMPUTER FAILURE" (MB4C, 1-11), is NOT LIT. 10. As needed, RESET Computer Terminals to At Power displays if 100% power IC. 11. Ensure that the protected train and environmental placards are appropriately hung 12. Verify various pot setting correct for plant conditions.

Equipment 005: "C" TPCCW pump (Caution Tag on control switch and place in PTL) Verify the MONITOR Time Display the same as the digital time display on MB4. If not page/call the Unit Tech. Page 8 of 80 S.......TION Lesson Title: Loss of Secondary Heat Sink 10 Number: 2K11 Revision:

Q INITIAL SETUP INSTRUCTIONS Initial MalfunctionsIlOs/IDAs:

PLACE GREEN PLACARDS FOR ALL INTAKE PARAMETERS ON MB6 PLACE THE "A" TRAIN PROTECTED PLACARD ON MB4 , Delay Ramp I Event Severity Final Relative 10 Number Description Time Time I Trigger Or Value Value Order .. MALFUNCTIONS i .SI07A 'A' Safety Injection pump fails to automatically Initial I SI07B 'B' Safety Injection pump fails to automatically Initial I.. Turbine fails to Trip automatically or from MB7 Initial pushbutton TP02A "An TPCCW Pump fails to auto-start Initial I I PZR level transmitter failure (L T 459) 60 sec 1 62.0% -! 'A' Atmospheric Relief Valve pressure channel failure 60 sec 4 high. Loss of Condenser Vacuum 1000 cfm Deenergize Emergency Bus 34C 6 RC02D RCS Hot Leg leak (loop 4) 60 s 10 Page 9 of 80 "STION4 Lesson Title: Loss of Secondary Heat Sink ID Number: 2K11 NRC-01 Revision:

Q INITIAL SETUP INSTRUCTIONS I I Delay Ramp! Event Severity Final RelativeID Description Time Time Trigger Or Value Value Order TD AFW pump trip ," REMOTE FUNCTIONS

., I RXR106 Protection Set 2 OPEN tXR25 PZR HI LEV Rx TRIP LS/459A, C1-751, BS-1 (PZR LVL 3 I B/S LB459A)

I Protection Set 30 sec 3 CLOSE SWR25 I I Locally operates 7 (CLOSED) I CCR08, 09 Locally opens 3 CCP-V186, 167, 187,177 to cross-I [8 OPEN !connect non-safety EDR07 Shifts lAC 6 to the alternate source 9 ! ALT . Shifts lAC 5 to the alternate source (32-1 F) 240 s I I 9 ! RPR44,45 SSPS A213 112 OUT I OVERRIDES I I I I I I Lead Refer to the "Briefing Script for the Operational Exam" and brief the crew. Go over the Plant/simulator differences, which follow. Page 10 of

-r;TION 4 Lesson Title: Loss of Secondary Heat Sink 10 Number: 2K11 NRC-01 Revision:

Q INITIAL SeTUP INSTRUCTIONS Booth IF desired by the NRC Exam Team, commence recording Simulator session Booth Perform the crew turnover (Initial Conditions page at end of LP) with the US. Have the US brief his crew on plant conditions and any major equipment OOS. PLANT/SIMULATOR DIFFERENCES: Rad Monitor Historical Oata--Simulator Rad Monitor historical data not valid prior to the beginning of this exercise. If not using the speed dial option on the phone system. the operator must dial either #3333 or #3334 to reach the person/department they desire. The following PPC programs do not function on the simulator: Samarium Follow Xenon Follow Sequence of Events Flow indications 3SIH-F1917 (charging ECCS flow), 3SIH-F1918 (A SI pump flow) and 3SIH-F1922 (8 SI pump flow) will show flow at low flow rates. Page 11 of 80 S' TION 4 Lesson Title: Loss of Secondary Heat Sink ID Number: 2K11 NRC-01 Revision: .Q Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard Event 1: '8' MD AFW pump oil leak. (Tech Spec entry) T+1 min of Call and report that you have found a large pool of oil around the "B" MDAFW Pump. The lube oil system bubbler assembly appears to have been inadvertently damaged. A couple of mechanics say they hit it by accident while moving equipment around. Tech Spec 3.7.1.2.c (72 hr action US Review Tech Specs. statement) should be entered. When the 'B' MDAFW Pump is placed Crew Actions should be taken to remove the in Pull-To-Lock, the Bypass MDAFW Pump from service, including Annunciator for H MD AFW System" will placing the pump in Pull-To-Lock.

come in. Contact the OMOC to request Maintenance assistance.

The US may contact Security to investigate for potential tampering.

T =10 min BOOTH Call as OMOC and report the expected from call to return of the pump in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. OMOC. Event 2: Controlling channel of PZR level fails just below setpoint.

T= RX10A,62%

This will activate the PZR Level Page 12 of 80 SE )N4 Lesson Title: Loss of Secondary Heat Sink ID Number: 2K11 NRC-01 Revision:

Q Time IDA/Malf Evaluator Cue Trigger 1 Task Instructor Information/Activity__

channel failure to just below the Program set point. It will take several minutes before PZR level, CHS Flow and VCT level to respond. AOP 3571 Actions (rev 009-07) RO CREW The RO should place the Master PZR level controller or 3CHS*FCV121 in manual. RO CREW Expected Action The crew should use MB indications and computer trends to diagnose an instrument failure versus an RCS leak. Do not leave the rod selector switch in AUTO while diagnosing a related instrument failure unless the reason for rod movement is a turbine runback. If a reactor trip occurs, immediately go to E-O, Reactor Trip or Safety Injection.

Determine the Initiating Parameter and Place the affected controller in MANUAL Stabilize the Plant Parameters It is desired that I&C personnel trip the bistables specified in this procedure.

If, during off -hours. I&C personnel are not able to trip the necessary bistables Standard AOP 3571 Step 1. CAUTION AOP 3571 Step 1, NOTE AOP 3571 Step 1 AOP 3571 Step 2 AOP 3571 Step 3, NOTE Page 13 of 80 Sf ION 4 Lesson Title: Loss of Secondary Heat Sink 10 Number: 2K11 NRC-01 Revision:

Q Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard I within the time limitations required by the Technical Specifications, Operations Department personnel may trip the bistables using the guidance provided within this procedure.

The appropriate attachment for this US Perform Corrective Actions Using AOP 3571 failure is "C". The US should announce Appropriate Attachment Step 3 to the crew. Instrument Attachment PZR Level Channel Failure RO Defeat the failed channel AOP 3571 Attachment C Step 1 RO should select some other channel

• Pressurizer Level Select than 1. Control -3RCS-LS459D RO should select some other channel Pressurizer Level Select than

• Record -3RCS-LS459E The US should give specific direction RO Restore PZR level to normal. AOP 3571 to the RO to restore PZR level to Attachment C program for the present power level. Step 2 Letdown should not have isolated. If necessary, using OP 3304A, AOP 3571 "Charging and Letdown," Restore Attachment C letdown. Step 3 RO Place PZR level controller in AOP 3571 Attachment C Page 14 of 80 C S' 'ION Lesson Title: Loss of Secondary Heat Sink 10 Number: 2K11 NRC-01 Revision:

Q Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Reset pressurizer heaters as necessary. When conditions have stabilized, Observe MB annunciators and parameters.

Immediately report any unexpected or unexplained conditions to the SM. Trip the associated Reactor Protection System bistable(s); Place a check mark in the box above the appropriate channel that requires tripping on the last page of this Attachment.

The US should identify the applicable US Refer to Technical Specification 3.3.1, TIS and T/R which are: 3.3.3.5, and 3.3.3.6. [Tech Specs] 3.3.1, Functional Unit 11, Action 6 IF PZR level deviates from program level by + or -6%, then also 3.4.3.1, Action b. The RO should do a lamp check to RO Check the existing bistable status to ensure all bistable lights ensure a reactor trip will not occur when the failed channel is tripped. The following step will distinguish whether the failure is within SSPS or the Standard Step 4 AOP 3571 Attachment C Step 5 AOP 3571 Attachment C Step 6 AOP 3571 Attachment C Step 7 AOP 3571 Attachment C Step 7a AOP 3571 Attachment C Step 7b AOP 3571 Attachment C Step 7c AOP 3571 Attachment C Page 15 of 80 SE('ON Lesson Title: Loss of Secondary Heat Sink ID Number: 2K11 NRC-01 Revision:

Q Time IDA/Malf Instructor Information/Activity Task Assign Expected Action Standard Protection channel. Step 7d NOTE NOTE: This is not the case. The channel has failed. The US should go to step 7.e. If bistable status light(s) ( MB4F) indicate that a single bistable input has tripped and channel indication is normal, PERFORM the following:

AOP 3571 Attachment C Step 7d T=2 mins of request Trigger 2 RXR106 'OPEN' Protection Set 1 Door I&C Request the I&C Department trip the appropriate bistables using Attachment C and Attachment S. AOP 3571 Attachment C Step 7e T=3 mins of request Trigger 3 RXR25 'TRIP' RXR106 'CLOSE' PZR High Level Trip BIS ("PZR LEVEL HI" will alarm on MB4) Protection Set 1 Door RO Verify the appropriate bistable status lights are AOP 3571 Attachment C Step 7f PZR level control may still be in manual. It is satisfactory to move on to Event 3. US If indicator 3RCS*LI 459C is failed, Refer to TRM Table 7.4.1, Fire Related Safe Shutdown Components, "Reactor Coolant System." AOP 3571 Attachment C Step 8 US Request I&C Department perform corrective maintenance on failed instrument.

AOP 3571 Attachment C Step 9 EVENT 3: 'A' Atmospheric Relief Valve pressure channel fails high (3MSS*PT20A)

Page 16 of 80 S' ""ION4 Lesson Title: Loss of Secondary Heat Sink 10 Number: 2K11 NRC-01 Task Time IDAlMalf Instructor Information/Activity

_. .Assign T =Bistables MS11A, 3MSS-PT20A fails high tripped 100% Trigger 4 The first indication the crew will receive of the 3MSS-PT20A failure will be the annunciator "MAIN STEAM RELIEF W NOT CLOSED" MB5C 5-7 33S3.MB5C 5-7 (rev 004-03) Corrective Actions BOP should check SG pressures for proper operation of SG Atmospheric Relief Valve. BOP should identify that the process input (3MSS-PT20A) to 3MSS-PIC20A is pegged high as indicated by the controller red pointer. The BOP should take manual control of MSS-PIC20A (UN SG Atmospheric Relief Valve Controller) and close the "A" atmospheric relief valve. Revision:

Q Expected Standard CHECK the following steam generator MBSC pressures for proper operation of main steam Step 1 pressure relief valve (MBS): 3MSS-PIC20A 3MSS-PIC20B 3MSS-PIC20C 3MSS-PIC20D IF a pressure controller has failed, MBSC PERFORM the following (MBS): Step 2 MBSC PLACE applicable controller in "MAN" and Step 2.1 CLOSE valve: 3MSS-PIC20A 1,

IF relief valve does not close, CLOSE the MBSC applicable isolation valve: Page 17 of 80 S6r T ION 4 Lesson Title: Loss of Secondary Heat Sink 10 Number: 2K11 NRC-01 Revision:

Q Task Time IOA/Malf Instructor Information/Activity

_ __

Expected Action 3MSS*MOV18A, "ATMOSPHERIC RELIEF ISOL" "SG 3" Refer To Technical Specification 3.7.1.6 and The US should refer to Technical DETERMINE Limiting Condition for Specification 3.7.1.6. No action will be Operation.

required.

IF failure is due to an instrument problem, Go To AOP 3571, "Instrument Failure Response." The US should go to AOP 3571 AOP 3571 Actions (Rev Do not leave the rod selector switch in AUTO while diagnosing a related instrument failure unless the reason for rod movement is a turbine runback. If a reactor trip occurs, immediately go to E-O, Reactor Trip or Safety Injection.

Determine the Initiating Parameter and Place the affected controller in MANUAL Stabilize the Plant Parameters It is desired that I&C personnel trip the bistables specified in this procedure.

If, during off -hours, I&C personnel are not able to trip the necessary bistables within the time limitations required by the Technical Standard Step 2.2 MB5C Step 3 MB5C Step 4 AOP 3571 Step 1, CAUTION AOP 3571 Step 1, NOTE AOP 3571 Step 1 AOP 3571 Step 2 AOP 3571 Step 3, NOTE Page 18 of 80 SE ON 4 Lesson Title: Loss of Secondary Heat Sink 10 Number: 2K11 NRC-01 Revision: .Q Task Time IDA/Malf Instructor Information/ActivitL_

A!Ssign_ Expected Action The appropriate attachment for this failure is "I". The US should announce to the crew. Rated thermal power (3650 Mwth) may be exceeded as a result of the transient.

The crew should recognize this and take appropriate action (lower turbine load) as specified in OP 3204, At Power Operations.

Specifications, Operations Department personnel may trip the bistables using the guidance provided within this procedure.

Perform Corrective Actions Using Appropriate Attachment The following are symptoms of an atmospheric relief valve pressure channel failure (3MSS-PT20A, 20B, 20C or 200): Actuation of the following annunciator:

MAIN STEAM RELIEF W NOT CLOSED MB5C 5-7 Abnormal indication on any of the following indicators on MB-5 3MSS-PIC20A 1 3MSS-PIC20B1 3MSS-PIC20C1 3MSS-PIC20D1 Defeat the failed instrument input by placing the affected SG atmospheriC relief valve controller in MANUAL and Close the valve. When conditions have stabilized, Observe MB annunciators and parameters and Standard AOP 3571 Step 3 AOP AOP 3571 Attachment I Step 1 AOP 3571 Attachment Page 19 of 80 SE )N4 Lesson Title: Loss of Secondary Heat Sink ID T=AOP 3571 complete Trigger 5 2K11 NRC-01 Revision:

Q Task IDA/Malf Instructor Expected Action immediately report any unexpected or unexplained conditions to the Shift Manager. There are no Technical Specifications or bistables associated with this instrument.

Request I&C Department perform corrective maintenance on failed instrument.

Event 4: Loss of condenser vacuum and procedurally directed rapid down power FW01, This will insert a loss of condenser (1000 vacuum cfm) Goal is to have crew respond to loss of vacuum by performing a rapid load reduction.

When the Examiners are satisfied with the Crew's performance, the cause will be found and corrected.

The crew should then stop the downpower.

AOP 3575, Rapid Downpower, follows AOP 3559, Loss of Condenser Vacuum. AOP 3559 Actions (rev 009) The Foldout page must be open. Standard I Step 2 AOP 3571 Attachment I Step 3 NOTE AOP 3571 Attachment I Step 3 AOP 3559 Step 1 NOTE Page 20 of 80

-ION 4 Lesson Title: Loss of Secondary Heat Sink 10 Number: 2K11 NRC-01 Revision: .Q Task Time IDA/Malf Instructor Information/Activity

_ Expected Action Standard Check If Turbine Load Should Be AOP 3559 Step 1 Condenser backpressure will be less Verify condenser backpressure

-LESS THAN AOP 3559 than 7.5 inches Hg. OR EQUAL TO 7.5 inches Hg Absolute Step 1.a Verify condenser backpressure

-GREATER AOP 3559 THAN 5 inches Hg Absolute Step 1.b Turbine load will be greater than 389 Verify turbine load -GREATER THAN 389 AOP 3559 MWe, the US should Using AOP Step 1.c 3575, "Rapid Downpower" to lower turbine load at 5%/min. Using AOP 3575, "Rapid Oownpower," Lower AOP 3559 turbine load at 5%/min. Step 1.d Proceed to step 2 and WHEN one of the following occurs: Backpressure LESS THAN EQUAL TO 5 inches Hg Absolute OR Turbine load at 389 Mwe THEN Proceed to step 1.e. Check Circulating Water System AOP 3559 Step 2 Page 21 of 80 Sf 'ON 4 Lesson Title: Loss of Secondary Heat Sink 10 Number: 2K11 Revision:

Q Task Time IDA/Malf Instructor Information/Activit}'

___

_ Expected Action Standard Yes, all 6 circulating water pumps Verify circulating water pumps -ONE PER AOP 3559 should be running. CONDENSER RUNNING Step 2.a All water box outlet isolation valves will Verify water box outlet isolation valves -OPEN AOP 3559 be open Step 2.b Verify all circulating water pumps -AOP 3559 Step 2.c Yes, all traveling screen DPs will be Verify the traveling screen differential AOP 3559 less than 12 inches H 2 0 pressure -LESS THAN 12 inches H 2 0 Step 2.d Check Condenser Air Removal AOP 3559 Step 3 Verify steam jet air ejector auxiliary steam AOP 3559 supply valve (3ASS-AOV22)

-OPEN Step 3.a Using OP 3329, "Condenser Air Removal," AOP 3559 locally Perform the following:

Step 3.b Verify both sets of steam jet air ejectors in AOP 3559 service Step 3.b.1 Verify all first stage jets in service on each air AOP 3559 ejector Step 3.b.2 Verify air ejectors -NOT AOP 3559 Step 3.b.3 3GWS* AOD78A and 3GWS* AOD78B Verify isolation dampers for gaseous waste to AOP 3559 are open (VP1) Unit 1 stack (3GWS* AOD78A and Step 3.c 3GWS*AOD78B)

-OPEN T =when BOOTH Report as PEa that 3GWS-FN1A is At Gas Waste Panel (3GWS-PNL-P6), Verify AOP 3559 called as running. process vent fans (3GWS-FN1A or 3GWS-Step 3.d Page 22 of 80 S&,....... ION 4 Lesson Title: Loss of Secondary Heat Sink 10 Number: 2K11 NRC-01 Task Time IDA/Malf Instructor

__

PEa T=when BOOTH Report as PEa that 3ARC-AOV36A called as and 3ARC-AOV36B are open. PEa Gland Seal Pressure will be about 3.5 psig Surge Tank Level will be about 95,000 gal and stable. These Annunciators will not be lit T = After LOWER 'CONDENSER FW01 VACUUM La Severity alarms. to 200 cfm Revision:

Q Expected Action FN1B) -ONE RUNNING Locally (Turbine Bldg 38' southwest)

Verify steam jet air ejector exhaust valves AOV36A and 3ARC-AOV36B)

-OPEN Check Gland Seal Pressure -BETWEEN 2 and 6 psig Locked valve key is required for some local operations.

Check Condensate Surge Tank Level GREATER THAN 18,000 gal NOT DECREASING IN UNEXPECTED A turbine trip occurs if the exhaust hood temperature exceeds 225°F. Check Exhaust Hood Temperature Annunciators EXH HOOD A, B, and C TEMP HI (175°F) (MB6A 5-4,5-5, and 5-6) NOT LIT Check For Condenser In-Leakage Standard AOP 3559 Step 3.e AOP 3559 Step 4 AOP 3559 Step 5 Note AOP 3559 Step 5 AOP 3559 Step 6 Note AOP 3559 Step 6 AOP 3559 Step 7 Verify condenser vacuum breakers (MB7) AOP 3559 Page 23 of 80 s* TION4 Lesson Title: Loss of Secondary Heat Sink 10 Number: 2K11 NRC-01 Time IDA/Malf T = Rapid BOOTH Downpower started T =2 min REMOVE from being FW01 directed to fill seal BOOTH T=when BOOTH called as EDM Report as the PEO that the loop seal associated with 3ARC-MOV23C has no water and air can be heard rushing into the seal pipe. The US should direct the PEO to fill the loop seal. This will simulate filling the loop seal and allow backpressure to stabilize.

Report as the PEO that the loop seal is filled. This Annunciator will not be lit The US should contact the Engineering Duty Manager for assistamce.

Report that the System Engineer is on his way to the TB. Revision:

Q Task Instructor Information/Activity

___

_ Expected Action (3ARC-MOV20A-B-C)

-CLOSED IE any valve will NOT close, THEN Locally Close valve(s) (Turbine Bldg 60' west). Locally Check vacuum breaker loop seals (Turbine Bldg 60' west) -FILLED Locally Fill loop seals. Locally Check for unusual noises indicative of air in-leakage Check seal water supply pressure annunciator EXT STM NRV SEAL PRES LO (MB6A 3-6B) -NOT LIT Using OP 3353.MB6A. "Main Board 6A Annunciator Response," Perform corrective actions for MB6A 3-6B. Contact Engineering to assist in locally checking condenser penetrations for air leakage Standard Step 7.a AOP 3559 Step 6.a RNO AOP 3559 Step 7.b AOP 3559 Step 7.b RNO AOP 3559 Step 7.c AOP 3559 Step 7.d AOP 3559 Step 7.d RNO AOP 3559 Step 7.e Page 24 of 80 SrlON 4 Lesson Title: Loss of Secondary Heat 10 Number: 2K11 Time IDA/Malf Instructor AOP 3575 Actions (Rev 017-03) Rod Control will be in Auto. The crew may perform down power on load limit or load set. Either is acceptable.

Revision:

Q Task __. Expected Action Standard Review Current Maintenance and Testing AOP Activities.

Step Verify Condenser Backpressure*

STABLE AOP OR DECREASING Step Return to step AOP Step If at any time either of the following AOP annunciators is received, Immediately perform Step step 7: ROD CONTROL BANKS LIMIT LO (MB4C 3-9) ROD CONTROL BANKS LIMIT LO-LO (MB4C 4-9)

Check Rod Control -IN AOP Step Align EHC AOP Step Check load reduction using load set -AOP DESIRED Step Page 25 of S' 'iON 4 Lesson Title: Loss of Secondary Heat Sink 10 Number: 2K11 NRC-01 Revision:

Q Task Time IDAlMalf Instructor

___

_ Expected Action Standard CREW Load reductions should be performed at 5%/min as specified in AOP 3559. RO RO Proceed to Note prior to step 3. Using Attachment E align EHC panel for LOAD SET operation.

CONVEX requested load reductions should performed at 5%/min and completed within minutes of Determine Power Reduction Rate (%/min). Check desired power reduction rate -3% / min OR 5% I MIN If SI actuation occurs during this procedure, Go to E-O, Reactor Trip or safety Injection, and restore from rapid boration lineup. Initiate Rapid Boration Verify RCS makeup system in -AUTO START one boric acid transfer pump. OPEN emergency boration valve (3CHS*MV81 04). Verify direct boric acid flow (3CHS-FI 183A) INDICATED.

AOP Step AOP Step 2.b AOP Step AOP Step AOP Step 3.a AOP Step AOP Step AOP Step 4.a AOP Step 4.b AOP Step 4.c AOP Step 4.d Page 26 of f T'ION4 Lesson Title: Loss of Secondary Heat Sink ID Number: 2K11 NRC-01 Task Time IDA/Malf Instructor Information/Activity

____ Assign RO About 17 minutes if "Rapid Downpower Summary Sheet" is used. Revision:

Q Expected Action OPEN charging line flow control valve. to match boric acid flow (3CHS-FI 183A) Record time boration started Time Check Rod Control-AVAILABLE FOR ROD INSERTION Check use of "Rapid Downpower Summary Sheet" (RE-H-17) in the RE Curve and Data Book -DESIRED Proceed to step 4.k. Using the "Rapid Downpower Summary Sheet" (RE-H-17), Determine approximate boration time Proceed To step 6. Use 18 gal BAI% Power to determine boration time in step 4.1 Using formula, Determine boration time (If gravity borating, use net charging flow (chg + seal inj-seal return total flow) for BA flow rate: Standard AOP 3575 Step 4.e AOP 3575 Step 4.f AOP 3575 Step 4.g AOP 3575 Step 4.h AOP 3575 Step 4.h. RNO AOP 3575 Step 4.i AOP 3575 Step 4.j AOP 3575 Step 4.k AOP 3575 Step 4.1 Total Power Change (a %) (gal BAI% = min Power) Page 27 of 80 S' -ION Lesson Title: Loss of Secondary Heat Sink 10 Number: 2K11 Revision:

Q Task Time IDA/Malf Instructor Information/Activity

_ __

Expected Action Standard BA Flow Boration Time US/BOP US 5% should be selected.

Proceed to step 6. If at any time the power reduction rate or final desired power level must be changed, Return to step 1. Initiate Load Reduction Check Rapid or gravity boration -IN PROGRESS Check turbine OPERATING MANUAL Check load reduction using load set DESIRED Perform the following: Using Attachment F, Rotate LOAD LIMIT SET in CCW direction consistent with desired down power schedule. Proceed to step 6.f. Select LOAD RATE LIMIT %/MIN to the desired value (1%,3%, or 5%) AOP 3575 Step 4.m AOP 3575 Step 6 NOTE AOP 3575 Step 6 AOP 3575 Step 6.a AOP 3575 Step 6.b AOP 3575 Step 6.c AOP 3575 Step 6.c RNO AOP 3575 Step 6.d Page 28 of 80 S' ION4 Lesson Title: Loss of Secondary Heat Sink 10 Number: 2K11 Revision:

Q Time IDA/Malt Instructor Intormation/Activity_

.__Ass19"'--__ _ _ Expected The BOP should adjust Load Set to about 360 MWe. Utilizing DECREASE LOAD Adjust LOAD SET to desired final Energize all PZR Adjust Pzr Spray Valves to 50% (RCS-PK 455B and RCS-PK Adjust boration time and/or flow rate necessary to Rods above the Rod Insertion Limit (RIL) Tavg within +/-5_F of Tref AFD within COLR limits Check rapid OR gravity boration performed for the time determined in steps 4.i. or 4.1. Proceed to step 6.k. and, WHEN Boration has been performed for the desired time, THEN Using Attachment G, stop boration.

Using Attachment G, stop boration Check power reduction

-CONVEX REQUESTED Inform CONVEX of load reduction rate (MWe/min) and final MWe level. Verify Rod Position Above RIL Standard AOP 3575 Step 6.e AOP 3575 Step 6.f AOP 3575 Step 6.g AOP 3575 Step 6.h AOP 3575 Step 6.i AOP 3575 Step 6.! RNO AOP 3575 Step 6.j AOP 3575 Step 6.k AOP 3575 Step 6.k RNO AOP 3575 Page 29 of 80 Sh?

4 Lesson Title: Loss of Secondary Heat Sink 10 Number: 2K11 NRC-01 Revision:

Q Task Time IDA/Malf Instructor Information/Activity

__ Expected Action Check ROD CONTROL BANKS LIMIT LO-LO (MB4C 4-9) annunciator

-LIT Proceed to step 7.g and, IF at any time, the annunciator is received, THEN Perform steps 7.c, 7.d and 7.e Check ROD CONTROL BANKS LIMIT LO (MB4C 3-9) annunciator

-LIT Proceed to step 8 and IF the annunciator is received, THEN Perfrom step 7.h and 7.i C-7 (Turbine Load Reject Arm) may Using Attachment C, "Rapid Downpower come in. If so, the BOP will need to Parameters" MONITOR parameters reset C-7. Degrade Condenser Backpressure Verify Final Desired Turbine Load LESS THAN 72% 972 MWe) Condenser backpressure will already be Using OP 3329, "Condenser Air Removal", degraded due to the loss of vacuum. Degrade condenser backpressure to between 2.0 in. HgA and 4.0 in. HgA T = when BOOTH Report as the PEO that the loop seal Standard Step 7 AOP 3575 Step 7.a AOP 3575 Step 7.a RNO AOP 3575 Step 7.g AOP 3575 Step 7.g RNO AOP 3575 Step 8 AOP 3575 Step 9 AOP 3575 Step 9.a AOP 3575 Step 9.b Page 30 of 80 SE ,)N 4 Lesson Title: Loss of Secondary Heat Sink 10 Number: 2K11 NRC-01 Revision:

Q Task Time IDA/Malf Instructor Information/Activity_

Asti!gll Expected Action Standard called as associated with 3ARC-MOV23C has PEa no water and air can be heard rushing into the seal pipe. The US should direct the PEO to fill loop T= 2 min REMOVE This will simulate filling the loop seal from being FW01 and allow backpressure to stabilize.

directed to fill seal Report as the PEa that the loop is The US should direct the downpower stopped since condenser vacuum stabilized.

Once the downpower stopped and the plant stable, to the next Event 5: Loss of emergency bus 34C. T =load ED04C Emergency Bus 34C will deenergize reduction is due to a bus differential relay trip and stopped and lockout. the plant stable Trigger 6 The US will enter AOP 3577, Loss Of Normal AOP 3577 (rev 001*02) Actions US And Offsite Power To A 4.16 Kv Emergency Page 31 of 80 Lesson Title: Loss of Secondary Heat Sink 10 Number: 2K11 NRC-01 Time IDA/Malf Instructor Information/Activity The US should direct the board operators to open and review their foldout pages. Yes, 34C is deenergized.

YES 'ION 4 Revision:

Q Task Assign Expected Action Standard Bus CREW The Foldout page must be AOP 3577 Step 1 NOTE US Check If Letdown Should Be AOP 3577 Step 1 Check either 4.16 KV emergency bus -AOP 3577 DE-ENERGIZED Step 1.a BOP Check affected bus -BUS AOP 3577 Step 1.b RO Simultaneously Perform the AOP 3577 Step 1.c

• CLOSE the charging flow control valve

• CLOSE letdown orifice isolation valves CLOSE charging header isolation valve AOP 3577 (3CHS*MV81

06) Step 1.d Try To Restore Power To Affected AOP 3577 Emergency Bus Step 2 Check bus differential annunciator for the AOP 3577 affected bus -LIT Step 2.a For bus 34C -BUS 34C BUS OIFF (MB8A 4-12) For bus 340 -BUS 340 BUS OIFF (MB8C 4-2) Page 32 of 80 S "ION 4 Lesson Title: Loss of Secondary Heat Sink 10 Number: 2K11 NRC-01 Revision:

Q Time IDA/Malf Instructor Information/Activity The US should direct the BOP to emergency stop the 'A' EOG. The 'B' CHS pump will be running. T =3 min Locally operates MOV71A from request SWR25 Report as PEO that 3SWP*MOV71A is closed Trigger 7 0% (closed>> Task ___

_ Expected Action Standard Perform the following:

AOP 3577 Step 2.b 1) STOP affected bus EOG by pressing both emergency stop pushbuttons.

2) Proceed to step 3. US Check If A Charging Pump Should Be AOP 3577 Started Step 3 RO Check charging pumps -NONE RUNNING AOP 3577 Step 3.a US Proceed to step 4. AOP 3577 Step 3.a RNO US Check Service Water Alignment AOP 3577 Step 4 BOP Check Affected bus -OEENERGIZEO AOP 3577 Step 4.a PEO Locally Close service water supply valve to AOP 3577 TPCCW from affected train Step 4.b

• For Train A: 3SWP*MOV71A The RO will start the 'B' SW pump. RO START the second SW pump in the non-AOP 3577 affected Train Step 4.c Page 33 of 80 f TiON 4 Lesson Title: Loss of Secondary Heat Sink 10 Number: Time 2K11 NRC-01 IDA/Malf Instructor Information/Activity Task _

E1'2ected Action Revision:

Q Standard RO Verify service water supply valve to TPCCW from the operating SW train (3SWP*MOV71A or 3SWP*MOV71 B) -OPEN AOP 3577 Step 4.d The RO will need to open 3SWP*MOV71 B, or a turbine runback will occur due to high Stator Water temperatures.

RO OPEN valve. AOP 3577 Step 4.d RNO US Cross-Connect RPCCW Containment Headers AOP 3577 Step 5 RO Verify the RPCCW containment supply and return header isolation valves in the operating train -OPEN AOP 3577 Step 5.a

• For Train B: Flow indicated

-3CCP-FI15B, CTMT SPL Y FLOW OR 3CCP*MOV45B 3CCP*MOV48B 3CCP*MOV498 (ESF Status Group 4, 9-25, 10-24, and 11-25) RO OPEN the RPCCW containment header cross-connect valves: AOP 3577 Step 5.b 3CCP*AOV179A 3CCP*AOV1798 Page 34 of 80 S -ION Lesson Title: Loss of Secondary Heat Sink 10 Number: Time 2K11 NRC-01 IDA/Malf Instructor Information/Activity_

Task Assign Expected Action Revision:

Q Standard 3CCP*AOV180A 3CCP* AOV180B RO CLOSE RPCCW containment return header isolation valve in the affected train AOP 3577 Step 5.c For Train A: 3CCP*MOV49A For Train B: 3CCP*MOV49B Check Boric Acid Transfer Pump Alignment AOP 3577 Step 6 Verify the boric acid transfer pump selected for AUTO -ENERGIZED AOP 3577 Step 6.a Select AUTO on energized pump. AOP 3577 Step 6.a RNO Adjust boric acid blend flow pot setting to the appropriate setpoint AOP 3577 Step 6.b US Restore Containment Cooling AOP 3577 Step 7 CREW LOP signal may take up to six minutes before it can be reset with the bus de-energized.

AOP 3577 Step 7.a NOTE RO RESET both trains LOP AOP 3577 Step 7.a BOP Check affected bus -Bus 34C AOP 3577 Step 7.b Page 35 of 80 Sf--!ON 4 Lesson Title: Loss of Secondary Heat Sink 10 Number: 2K11 NRC-01 Time IDA/Malf Instructor Information/Activity__

T+ 3 This will manually open 3 CCP*V186, CCR08 from 167, 187, 177 per OP3330A. CCR09 Trigger 8 "OPEN" NOTE: Once the non-safety headers are cross-connected, the max flow allowed through a CCP HX (8100 gpm) will be challenged.

The crew should discuss methods to reduce the 'B' train CCP flow. Revision:

Q Task Expected Action Standard RO OPEN RPCCW non-safety header supply/return isolation valves Train B (3CCP* AOV197B/194B)

AOP 3577 Step 7.c RO CLOSE RPCCW non-safety header supply/return isolation valves Train A (3CCP* AOV197 Al194A) AOP 3577 Step 7.d RO Verify COS chiller on train with power -AUTO STARTS AOP 3577 Step 7.e RO Using OP 3330A, Reactor Plant Component Cooling Water," Cross-connect Non-safety related RPCCW headers. AOP 3577 Step 7.f RO Verify associated CDS chiller -AOP 3577 Step 7.g START AOP 3577 Step 7.g RNO BOP Check CAR fans -TWO FANS AOP 3577 Step 7.h START fan(s), if AOP 3577 Step 7.h RNO BOP Check CRDM fans -TWO FANS AOP 3577 Page 36 of 80 SE )N4 Lesson Title: Loss of Secondary Heat Sink 10 Number: 2K11 NRC-01 Task Time IDA/Malf Instructor Information/Activity Assign The BOP will need to start the 'B' CRDM fan. RO RO If CTMT pressure exceeds 14.0 psia, US the US should enter the LCO for TS 3.6.1.4, "Containment Pressure" (one hour action statement)

US BOP RO The RO will Use GA-14, to establish head vent letdown to the PRT. This is necessary to balance RCS inventory due to ongoing seal injection.

Revision:

Q Expected Action START fan(s), if available.

Check containment pressure -STABLE OR DECREASING Perform the following: Using OP 3313E, "Containment Vacuum," Maintain normal operating containment pressure. Refer to Technical Specification 3.6.1.4, "Containment Pressure," for additional actions. Align Charging And Letdown Check the affected bus -Bus 340 Perform the following: Using GA-14, Establish head vent letdown to the PRT. Standard Step 7.i AOP 3577 Step 7.i RNO AOP 3577 Step 7.j AOP 3577 Step 7.j RNO AOP 3577 Step 8 AOP 3577 Step 8.a AOP 3577 Step 8.a RNO Page 37 of 80 Sf ON 4 Lesson Title: Loss of Secondary Heat Sink 10 Number: 2K11 NRC-01 Revision:

Q Task Time IDA/Malf Instructor Information/Activity Assign Expected Action US 2. Proceed to step 9. Isolate Auxiliary Steam To Auxiliary Building CLOSE auxiliary steam isolation valves to the Auxiliary Building 3ASS*AOV102A 3ASS* AOV1 02B Verify Service Water Flow To The Operating Control Building Chiller Heat Exchanger Using OP 3314F, "Control Building Heating, Ventilation, Air Conditioning and Chill Water," Perform operation of Control Building AC System to start the other chiller and its associated service water booster pump. For chiller A (HVK(CHl1A)

Check annunciator CONTROL BLDG CHLR CNDSR A SW FLOW LO (VP1 A 3-3) NOT LIT For chiller B (HVK(CHL 1 B) Check annunciator CONTROL BLDG CHLR CNDSR A SW FLOW LO (VP1C NOT LIT Verify Spent Fuel Pool Cooling Alignment Standard AOP 3577 Step 9 AOP 3577 Step 9.a AOP 3577 Step 10 AOP 3577 Step 10 RNO AOP 3577 Step 11 Page 38 of 80 S -ION Lesson Title: Loss of Secondary Heat Sink 10 Number: 2K11 NRC-01 Revision:

Q Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Yes, the 'B' spent fuel cooling pump is Check spent fuel cooling pumps -ONE running. RUNNING Perform the following:

Check RPCCW to the in-service spent fuel pool cooling heat exchanger

-FLOW INDICATED Flow will be indicated. RPCCW safety header flow indication minus RHR HX RPCCW flow I indication Using OP 3305, "Fuel Pool Cooling and Purification," Perform Spent Fuel Pool Cooling System HX shift. Restore Auxiliary Building Ventilation Using GA-20, Place charging and RPCCW area a ventilation in service. Block Automatic loading Of Affected Emergency Bus Place the following control switches for equipment on the affected bus in LOCK

• One service water pump

• RPCCW pumps Standard AOP 3577 Step 11.a AOP 3577 Step 11.a RNO AOP 3577 Step 11.b AOP 3577 Step 11.b AOP 3577 Step 12 AOP 3577 Step 12.a AOP 3577 Step 13 AOP 3577 Step 13.a Page 39 of 80 TION 4 Lesson Title: Loss of Secondary Heat Sink 10 Number: 2K11 NRC-01 Task Time IDA/Malf Instructor Information/Activity Assign us RO An instrument air compressor is RO running. RO BOP Revision:

Q Expected Standard

• Quench spray pump

• Recirc spray pumps

• SI pump

• RHR pump

• Charging pumps

• MD AFW pump

• Control Bldg chiller

• Aux Building filter Maintain Stable Plant AOP 3577 Step 14 Energize available PZR heaters as AOP 3577 Step 14.a Start an instrument air compressor, if AOP 3577 necessary Step 14,b Maintain the following parameters stable at or AOP 3577 trending to desired values, Step 14,c

• PZR pressure

• PZR level

• RCS temperature

• SG levels Page 40 of 80 sr 4 Lesson Title: Loss of Secondary Heat Sink ID Number: 2K11 NRC-01 Revision:

Q Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard If power is not restored to Bus 34C or AOP 3577 computer panels (3VBA-PNL-6A and 6B) are Step 15 not energized by the alternate source within NOTE 30 minutes, Inverter 6 deenergizes making the process computer unavailable. Check If Non-Vital Panels Should Be AOP 3577 Energized By Alternate Source Step 15 BOP Check affected bus -Bus AOP 3577 Step 15.a BOP Check Bus 34C -NOT AOP 3577 Step 15.b T = 4 min EDR07 and Shifts lAC 6 to the alternate source PEO 1. Using OP 3345A, "120 Volt Non-Vital from EDR06 Instrument AC," Perform transferring dispatch (delayed 4 min) 3VBA-PNL-6A and 3VBA-PNL-6B to 'AL T' Shifts lAC 5 to the alternate source power from 3VBA-INV-6 to alternate Trigger 9 (32-1 F) AC source. PEO Using OP 3345A, "120 Volt Non-Vital Instrument AC," Perform transferring 3VBA-PNL-5 and 3VBA-PNL-5C power from 3VBA-INV-5 to alternate AC source Refer To The Following Technical AOP 3577 Specifications For Any Additional Required Step 16 Actions TIS 3,8.1.1, AC Sources -Operating TIS 3,8.1.2, AC Sources -Shutdown Page 41 of 80 s* TION 4 Lesson Title: Loss of Secondary Heat Sink 10 Number: Time 2K11 NRC-01 IDA/Malf Instructor Information/Activity Task Assign Expected Action Revision: .Q Standard TS 3.8.2.1 (action a), DC Sources and 3.8.3.1 (action a), Onsite Power Distribution apply. TIS 3,8.2.1, DC Sources -Operating due to the loss of 34C. 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> action statement for DC Sources. TIS 3,8.2.2, DC Sources -Shutdown Also, 3.8.1.1, AC Sources, has an action (b.1) to conduct the surveillance for Offsite Sources within one hour if an EDG is INOPERABLE.

Although the 'A' EDG is OPERABLE it is in effect not usable, so the surveillance should be conducted.

TIS 3,8.3.1 Onsite Power Distribution Operating T TIS 3,8.3.2 Onsite Power Shutdown T =When called BOOTH Reply as Maintenance that repair is possible in 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, bus differential relay is bad TRM 7.4.1, Fire Related Safe Shutdown Components (A train only) EVENT 6: Small Break LOCA inside CTMT. RC02D T= Tech Malfunction entry will cause a small (180 Specs unisolable RCS leak to occur on the Ibm/sec, 60 addressed loop 4 hot leg. Sec) Trigger 10 The leak is about 600 gpm, well in Page 42 of 80 SE JN4 Lesson Title: Loss of Secondary Heat Sink 10 Number: 2K11 Revision:

Q. Task Time IDA/Malt Instructor Intormation/Activity_

Expected Action Standard excess of the capacity of two The first indication of the RCS leak will be PZR level and pressure lowering, followed by computer point alarms associated with CTMT Unidentified sump and CTMT high pressure alarms. CMS22 will also show an adverse trend, but does not reach the alert setpoint for several minutes. AOP 3555 Actions (Rev 017-02) YES, PZR level will be decreasing.

RO Check PZR Level -

AOP 3555 Step 1 Charging and Letdown were isolated as US Increase Charging Flow AOP 3555 procedurally directed in AOP 3577. Step 2 Charging flow cannot be increased.

RO Check charging AOP 3555 Step 2.a Align valves as AOP 3555 Step 2.a, RNO Throttle Open charging line flow control valve AOP 3555 to increase charging flow to maximum Step 2.b NO letdown orifice isolation valves will Check letdown orifice isolation valves -ONLY AOP 3555 be open. ONE OPEN Step 2.c Page 43 of 80 SE Lesson Title: Loss of Secondary Heat Sink o Number: 2K11 NRC-01 Revision:

Q Task Time IDA/Malf Instructor Expected Action Standard There is nothing the crew can do to control the inventory loss. Based on the rapid lowering of PZR level, the US should direct a Reactor Trip and an initiation of Safety Injection.

PZR level wi" be rapidly lowering.

RO Verify PZR level-STABLE OR AOP 3555 Step 6.a Perform the AOP 3555 Step 6.a, RNO TRIP the reactor. Initiate SI. Go to E-O, Reactor Trip or Safety Injection. US should go to "Master Silence" before ordering reactor trip. E-O (Rev. 026) Crew Foldout page must be open E-O, Step 1, NOTE The only available source of AFW will

• ADVERSE CTMT defined as GREATER be from the TO AFW pump. THAN 180°F or GREATER THAN 10 5 Page 44 of 80 sr ION Lesson Title: Loss of Secondary Heat Sink 10 Number: 2K11 NRC-01 Time IDA/Malf Instructor Information/ActivitY' EVENT 7: Turbine Fails To Trip Turbine stop valves will NOT be closed. [*] Critical Task The BOP should recognize that the turbine failed to trip and manually run back the turbine The operators may close the MSIVs if they do not believe the turbine control valves are closing quickly enough. Revision:

Q Task Assign Expected Action Standard in containment. The reactor can be interpreted as "tripped" when any two of three bulleted substeps of Step 1.* are satisfied.

RO Verify Reactor E-O, Step 1 Check reactor trip and bypass breakers -OPEN Check rod bottom lights -LIT Check neutron flux -DECREASING TRIP the reactor. E-O, Step 1, RNO Verify Turbine E-O, Step 2 Check all turbine stop valves -E-O, Step 2.a Trip the E-O, Step 2.a If the Turbine will Not Trip RNO THEN Runback the turbine to close the control [*] valves. If the turbine cannot be E-O, Step 2.a THEN Page 45 of 80 S ""ION Lesson Title: Loss of Secondary Heat Sink 10 Number: 2K11 NRC-01 Time IDA/Malf Instructor Information/Activity Task Assign BOP BOP us RO us Revision:

Q Expected Standard CLOSE MSIVs & MSIV bypass valves RNO Verify Power to AC Emergency Busses E-O, Step 3 Check busses 34C and 340 -E-O, Step 3.a BOTH ENERGIZED Check If SI Is Actuated E-O, Step 4 Verify SAFETY INJECTION ACTUATION E-O, annunciator

-(MB4D 1-6 or MB2B 5-9) -LIT Step 4.a Check if SI is E-O, Step 4.a, RNO CTMT pressure GREATER THAN 18 psia OR PZR pressure LESS THAN 1890 psia OR PZR level LESS THAN 9% OR RCS subcooling LESS THAN 32°F OR

• SG pressure LESS THAN 660 psig Page 46 of 80 SF;"' -ION 4 Lesson Title: Loss of Secondary Heat Sink D Number: 2K11 NRC-01 Task Time IDA/Malf Instructor RO RO EVENT 8: SIH pumps fails to RO Auto-Start. Critical Task Crew should identify that the liS' SI pump did not automatically start and manually start the pump. BOP Revision:

Q Expected Action 1E 51 is Initiate 51 and Proceed to step Check Reactor trip and bypass breakers OPEN Verify Service Water Pumps -AT LEAST ONE PER TRAIN RUNNING START pump(s) Verify Two RPCCW Pumps -ONE PER TRAIN RUNNING Verify ECCS Pumps Running

• Check 51 pumps -RUNNING

• Check RHR pumps -RUNNING

• Check two charging pumps -RUNNING Verify AFW Pumps Running Check MD pumps -RUNNING Standard E-O, Step 4.c E-O, Step 5 E-O, Step 5, RNO E-O, Step 6 E-O, Step 7 E-O, Step 8 E-O, Step 8.a Page 47 of 80 TION 4 Lesson Title: Loss of Secondary Heat Sink 10 Number: 2K11 NRC-01 Time IDA/Malf Instructor Information/Activity The safety Injection closed the RPCCW CTMT cross-connect valves. As a result, the 'A' and '0' RCPs have no motor lube oil cooling and RCP bearing temperatures will start to increase.

The crew should identify this and trip the 'A' and '0' Reps. Revision:

Q Expected Action Check turbine -driven pump -RUNNING, IF NECESSARY Verify FW Isolation Check SG feed regulating valves CLOSED Check SG feed regulating bypass valves CLOSED Check FW isolation trip valves -CLOSED Check TO FW pump -TRIPPED Check MD FW pumps -STOPPED Check SG blowdown isolation valves CLOSED Check SG blowdown sample isolation valves -CLOSED Check SG chemical feed isolation valves CLOSED Standard E-O, Step 8.b E-O, Step 9 Page 48 of 80 Sf 'ON 4 Lesson Title: Loss of Secondary Heat Sink 10 Number: 2K11 NRC-01 Task Time IOA/Malf Instructor Information/Activity Assign BOP [*] Critical Task -BOP RCS pressure will eventually lower to < 1500 psia. Crew should identify this and trip all RCPs. RO Revision: .Q Expected Action Align component(s) as necessary for minimum safety function.

I Check If Main Steam Lines Should Be Isolated Check Ctmt pressure GREATER THAN 18 psia OR Any SG pressure LESS THAN 660 psig OR Annunciator "MAIN STEAMLINE ISOLATION" (MB2B 5-7) -LIT Proceed to Step 11 Verify MSIVs and MSIV bypass valves CLOSED Check ESF Group 3 lights -LIT. Check if COA Required Check Ctmt pressure is GREATER THAN 23 psia Standard E-O, Step 9 RNO Step Step Step Step Step Step Step Page 49 of 80 "ION 4 Lesson Title: Loss of Secondary Heat Sink ID Number: 2K11 Revision:

Q Task Time IDA/Malt Instructor Information/Activity_ _ _

Expected Action Standard OR Annunciator "CONTAINMENT DE PRES ACTUATION" (MB2B 5-5) -LIT US Proceed to Step E-O, Step11,a, RNO Verify CAR Fans Operating In Emergency E-O, Mode Step 12 BOP Check CAR fan E-O, Step 12.a CAR fans A and B -RUNNING *

• CAR fan C -STOPPED BOP START/STOP CAR fans as E-O, Step 12.a, RNO Verify RPCCW Ctmt supply and return header E-O, isolations

-OPEN Step 12.b Verify Train A and B RPCCW supply and E-O, return to chill water valves -OPEN Step 12.c RO Verify E-O, Step 13 Check ESF Group 2 status columns 2 through E-O, 10 -LIT Step 13.a RO Verify Proper ESF Status Panel E-O, Page 50 of 80 S -ION Lesson Title: Loss of Secondary Heat Sink ID Number: 2K11 NRC-01 Time IDA/Malf Instructor Information/Activity RO RO Revision:

Q _ Expected Standard Step 14 Verify ESF Group 1 lights -OFF

• Verify ESF Group 2 lights -LIT

• Determine If ADVERSE CTMT Conditions E-O, Exist Step 15 Ctmt temperature GREATER THAN 180°F

• OR

• Ctmt radiation GREATER THAN 10 5 R/hr Verify ECCS E-O, Step 16 Check PZR pressure -GREATER THAN E-O, 1900 psia Step 16.a Proceed to step E-O, Step 16.a RNO Check PORV block valves -E-O, Step 16.b Proceed to step E-O, Step 16.c Check charging pumps E-O, Step 16.d FLOW INDICATED START pumps and Align E-O, Step 16.d, RNO Page 51 of 80 8 TION 4 Lesson Title: Loss of Secondary Heat Sink 10 Number: 2K11 NRC-01 Revision:

Q Task Time IDA/Malf Instructor Information/Activity

_ Assign RO US CREW should perform a short brief and come out of "Master Silence" at the completion of Step 16. EVENT 9: Loss of Secondary Heat Sink. T =Step 17 FW19 This will trip the TO AFW pump. Loss of BOP aIlAFW. Expected Action Check RCS pressure -GREATER THAN 1650 psia (1950 psia ADVERSE CTMT) Proceed to Step 17 Check SI pumps -FLOW START pumps and Align Check RCS pressure -LESS THAN 300 (500 psia ADVERSE Proceed to step Check RHR pumps -FLOW INDICATED.

START pumps and Align valves. Verify Adequate Heat Sink Step Step Step E-O, 16.f RNO Step Step Step Step E-O, Step 17 Page 52 of 80 S -ION 4 Lesson Title: Loss of Secondary Heat Sink 10 Number: 21<11 Revision:

Q Task Time IOA/Malf Instructor Information/Activity Assign Expected Action Standard reached Trigger 11 Heat sink will be RED due to loss of all Check NR level in at least one SG -E-O, AFW. GREATER THAN 8% (42% ADVERSE CTMT) Step 17.a Proceed to step E-O, Step 17.a RNa Verify Total AFW Flow -GREATER THAN E-O, 530 gpm Step 17.d The US should transition to START pumps and Align valves as necessary.

E-O, H.1. IF AFW Flow GREATER THAN 530 gpm can Step NOT be established, THEN Initiate monitoring of CSF Status Trees and Go to Response to Loss of Secondary Heat FR-H.1 Actions (Rev. 020-01) Check If Secondary Heat Sink Is yes FRH.1 step Required 1 Verify RCS pressure BOP GREATER THAN ANY NON-FAULTED SG PRESSURE Verify RCS hot leg WR temperature BOP GREATER THAN 350°F Check Charging Pump Status FRH.1 step AT LEAST ONE RUNNING 2 Done in E-O us Try to Establish AFW Flow to at least One FR-H.1 Page 53 of 80 S" "'-ION 4 Lesson Title: Loss of Secondary Heat Sink 10 Number: 2K11 Revision:

Q Time IDA/Malf Instructor Information/Activity

.. Blowdown will be isolated.

DWST level will be > 80,000 gal. DWST suction valves will be open. The 'A MD AFW pump is deenergized due to bus 34C being deenergized, the 'B' MD AFW pump is tagged out. The TO AFW pump tripped. Task Expected Action Standard Step 3 RO Check SG blowdown FR-H.1 Step 3.a RO Verify SG blowdown isolation valves -CLOSED RO Verify SG blowdown sample isolation valves -CLOSED Verify AFW valve alignment

-PROPER FR-H.1 EMERGENCY ALIGNMENT.

Step 3.b BOP Check DWST level -LESS THAN 80,000 FR-H.1 Step 3.c Proceed to step 3.f and, IF DWST level FR-H.1 decreases to LESS THAN 80,000 gal, THEN Step 3.c Perform step 3.d. RNO Verify DWST suction valves {3FWA*AOV61A FR-H.1 and 3FWA*AOV61B}

-OPEN. Step 3.f BOP Check MD pumps -

FR-H.1 Step 3.g BOP/US START FR-H.1 Step IF the pump(s) do NOT start, THEN 3.gRNO Restore power to the pumps (MB or locally).

BOP Check TD AFW pump -

FR-H.1 Step 3.h OPEN steam supply FR-H.1 Page 54 of 80 SE Lesson Title: Loss of Secondary Heat Sink ID Number: 2K11 NRC-01 Revision:

Q Time IDA/Malf Instructor Information/Activity

___

E;:xpected IE the pump does NOT start, THEN OPEN steam supply isolation valves: 3MSS*MOV17 A 3MSS*MOV17B 3MSS*MOV17D Check total flow to SGs -GREATER THAN 530 gpm. The US should dispatch at least one US Perform the applicable action: PEO to carry out local actions in

• IE any AFW flow is indicated, THEN Attachment

'A', specifically the actions Proceed to step 3.k. associated with the TO AFW pump.

• IE no AFW flow indicated, THEN The US should proceed to step 1) Locally restore AFW flow using Attachment A, if required.

2) Proceed to step 4. and, IF AFW flow is established prior to step 10. THEN Return to step 3.i. The Reps should already be stopped. RO STOP All Reps. T = 5 min BOOTH Report as PEa that the TO AFW trip CREW

• DO NOT reinstall the A213 logic cards from being throttle valve has tripped (MSV-5). until an adequate heat sink has been dispatched Attempting to reset. made available.

Reinstallation of a lobic card may cause actuation of the FWI circuit. Standard Step 3.h RNO FR-H.1 Step 3.i FR-H.1 Step 3.i RNO FR-H.1 Step 4 FR-H.1 Step 5 CAUTION Page 55 of 80 SP )N4 Lesson Title: Loss of Secondary Heat Sink ID Number: 2K11 Revision:

Q Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard T= 6 min BOOTH Report as PEO that the MSV*5 CREW

• Removal of the A213 cards defeats the from being latching mechanism is damaged and low steam pressure SI from Loops 1 and dispatched the valve cannot be reset. Request 2. Manual actions may be required to Maintenance initiate safety injection for a low steam pressure condition. Try to Establish Main FW Flow to At Least FR-H.1 One SG. Step 5 Two condensate pumps will be running. Verify at least one condensate pump -FR-H.1 RUNNING. Step 5.a BOP Check FW isolation trip valves -FR-H.1 Step 5.b T= 3 min RPR 44, This will simulate removing the A213 BOPtRO Perform the following:

FR-H.1 from 45 to cards from SSPS. Step 5.b IF SI OR P-14 has actuated, WHEN RNO request 'OUT' SG levels LESS THAN the P-14 Trigger 12 setpoint, THEN RESET SI AND Remove universal logic card A213 from both Trains of the Solid State Protection System (3RPS*RAKLOGA and 3RPS*RAKLOGB). RESET FWI at MB2. RESET FWI at MB5. Adjust SG feed regulating and SG feed regulating bypass valve controllers to zero output. Page 56 of 80 S'

4 Lesson Title: Loss of Secondary Heat Sink 10 Number: 2K11 NRC-01 Revision:

Q Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard RESET and OPEN the FW isolation trip valves. IE no FW isolation trip valve can be opened, THEN Proceed to Step 9. Perform the following to start the MO FW FR-H.1 pump: Step 5.c Place FW pumps P4 trip bypass selector FR-H.1 switch to BYPASS Step 5.c.1 Place the MO FW pump control switch in FR-H.1 STOP. Step 5.c.2 BOP START the MO FW FR-H.1 Step 5.c.3 Verify MO FW pump startup valve FR-H.1 HIC590) -50% OPEN. Step 5.d The US should direct the BOP to use US/BOP Feed the SGs using SG feed regulating FR-H.1 the PPC to assist in NOT overfeeding bypass valves to restore SG narrow range Step 5.e the SGs and causing an uncontrolled level consistent with preventing excessive cooldown.

This should include a ReS cooldown.

specific band of flowrate such that WR levels in SGs are going up but not such that the BOP loses RCS temperature.

CLOSE the FW control isolation FR-H.1 Step 5.f 3FWS-MOV35A 3FWS-MOV35B 3FWS-MOV35C Page 57 of 80 Sf 'ON 4 Lesson Title: Loss of Secondary Heat Sink ID Number: 2K11 Revision:

Q Task Time IDA/Malf Instructor Information/Activity Assign BOP BOP us BOP WR levels should be increasing.

Core BOP Exit TCs decreasing.

The US should announce transition to US E-O step 18, and hold a transition brief. Expected Standard 3FWS-MOV35D Verify feed flow -

FR-H.1 Step 5.g CLOSE each TD FW pump's discharge FR-H.1 isolation valve Step 5.h 3FWS-MOV23B 3FWS-MOV23C Check SG FR-H.1 Step 6 Verify NR level in at least one SG -GREATER FR-H.1 THAN 8% (42% ADVERSE CTMT) Step 6.a Perform the FR-H.1 Step 6.a Verify a secondary heat sink established:

RNO WR level in at least one SG is increasing AND Core Exit TCs are stable OR decreasing lE. a secondary heat sink established NOT be established, Proceed to CAUTION prior to Step Maintain feed flow to restore NR level to GREATER THAN 8% (42% ADVERSE CTMT). Go to procedure and step in FR-H.1 Step 6.b Page 58 of 80 S' -ION 4 Lesson Title: Loss of Secondary Heat Sink 10 Number: 2K11 NRC-01 Task Time IDAlMalf Instructor Information/Activity Assign Yes, CBI will be lit. RO BOP BOP RO BOP BOP Revision:

Q Expected Action Verify AFW Valve Alignment

-PROPER EMERGENCY ALIGNMENT Verify ECCS Valve Alignment

-PROPER EMERGENCY ALIGNMENT Check If CBI Required Check CONTROL BUILDING ISOLATION annunciator (MB4D 3-6) -LIT Check Train A Control Building filter fan (3HVC*FN1A)

-RUNNING Check recirc damper for the running Control Building filter fan (3HVC*AOD119A or B) -OPEN Verify ESF Group 2 CBI lights -LIT Verify control building purge supply fan and purge exhaust fan -NOT RUNNING Verify control building purge supply fan and Standard E-O, Step 18 E-O, Step 19 E-O, Step 20 E-O, Step 20.a E-O, Step 20.b E-O, Step 20.c E-O, Step 20.d E-O, Step 20.d E-O, Page 59 of 80 S6,",TION 4 Lt;sson Title: Loss of Secondary Heat Sink ID Number: 2K11 Revision:

Q Time lOA/Malf Instructor Information/Activity T =When BOOTH When asked, REPORT that "all SLCRS called as doors indicate closed." SSS T =When BOOTH When called, WAIT 3 -5 min, Then. called as REPORT "Control Building pressure PEO boundary doors are Closed and Dogged or verified closed as directed." Task Expected Action Standard purge exhaust fan* NOT Step 20.e BOP Place kitchen exhaust fan in E-O, Step 20J Verify SLCRS doors -E*O, Step 20.g CLOSE and DOG the following Control E-O, Building pressure boundary doors ..... Step 20.h RO Check RCS E-O, Step 21 Using GA-26, Dump steam as necessary E-O, to control RCS cold leg WR temperature-Step 21.a BETWEEN 550°F AND 560°F Verify RCS cold leg WR temperature-E-O, GREATER THAN 550°F Step 21.b US Proceed to Step E-O, Step 21.c Check Power To seo Diesel E-O, Step 22 E-O, Verify any SBO bus tie breaker -CLOSED Step 22.a TO AN ENERGIZED BUS Page 60 of 80 sr -'ON 4 Lesson Title: Loss of Secondary Heat Sink 10 Number: 2K11 NRC-01 Task Time IDA/Malf Instructor Information/Activity Assign RO RO RO RO CREW RO RO US Revision:

Q Expected Standard

• Bus 34A: 34A 1-2

• Bus 34B: 34B1-2

• Bus 24E: A505 (Unit 2) Check PZR E-O, Step 23 Verify PORVs -E-O, Step 23.a Verify normal PZR spray valves -E-O, Step 23.b Verify PORV block valves -AT LEAST E-O, ONE ENERGIZED VALVE OPEN Step 23.c Verify PZR safety valves -E-O, Step 23.d To prevent seal damage, seal injection flow E-O, should be maintained to all RCPs. Step 24, CAUTION Check If Reps Should Be E-O, Step 24 Verify RCPs -ANY E-O, Step 24.a Verify RCS pressure -LESS THAN 1500 psia E-O, (1800 psi a ADVERSE CTMT) Step 24.b Proceed to Step E-O, Step 24.b, Page 61 of 80 S' 'ION Lesson Title: Loss of Secondary Heat Sink 10 Number: 2K11 NRC-01 Revision:

Q Time IDA/Malf Instructor Information/Activity Critical Task RCS pressure wi" eventually lower to < 1500 psia. Crew should identify this and trip all RCPs. RO RO BOP RO Expected Standard RNO Verify either of the following:

E-O, Step 24.c Charging pumps -AT LEAST RUNNING AND AT LEAST COLD LEG INJECTION OR SI pumps -AT LEAST STOP all E-O, Step 24,d [*] Check If SG Secondary Boundaries Are E-O, Intact Step 25 Check pressure in all E-O, Step 25.a NO SG PRESSURE IN AN UNCONTROLLED NO SG Check If SG Tubes Are E-O, Step 26 Page 62 of 80 SE" IN Lesson Loss of Secondary Heat Sink 10 Number: 2K11 NRC-01 Task Time IDAlMalt Instructor Intormation/Activity__

RO Acknowledge the request to perform the SIG samples. Ensure crew request activity samples with HP coverage BOP RO Revision:

Q Expected Standard Sample all SGs for E-O, Step 26.a RESET SG blowdown sample isolation OPEN SG blowdown sample isolation valve(s) Request Chemistry obtain activity samples using HP coverage Check steam generator levels -NO SG E-O, LEVEL INCREASING IN AN Step 26.b UNCONTROLLED MANNER Verify trend history and alarm status of I E-O, radiation monitors Step 26.c Main steam line -NORMAL Condenser air ejector -NORMAL SG blowdown -NORMAL Check If RCS Is E-O, Step 27 Verify Ctmt radiation 3CMS*RE22 (pre-trip)

-Verify Ctmt radiation using monitoring group histogram (CTMT) Page 63 of 80 sr -ION Lesson Title: Loss of Secondary Heat Sink ID Number: 2K11 NRC-01 Revision:

Q Task Time loAlMalf Instructor Information/ActivitY'

______ ElCpected Action CTMT pressure will not be normal. The crew should conduct a short transition brief and transition to E-1. E-1 (rev 024) Actions The US should remind the operators to review their Foldout Page Books RCP's should have been stopped in E-O. us RO US US US BOP/ RO Verify Ctmt pressure -NORMAL Verify Ctmt recirculation sump level NORMAL Initiate monitoring of CSF Status Trees and Go to E-1, Loss of Reactor or Secondary Coolant. To prevent seal damage, seal injection should be maintained to all Note: Foldout page must be open. Check If RCPs Should Be Stopped Verify RCP's -ANY RUNNING Proceed to step 2 Check If SG Secondary Boundaries Are Intact Check pressures in all SGs. NO SG PRESSURE DECREASING IN AN UNCONTROLLED MANNER Standard E-O, Step 26 RNO E-1, Step 1 CAUTION E-1, Step 1 NOTE E-1, Step 1 E-1 Step 1a E-1 Step 1a RNO E-1, Step 2 E-1, Step 2.a Page 64 of 80 S" Lesson Title: Loss of Secondary Heat Sink 10 Number: 2K11 NRC-01 Task Time IDA/Malf Instructor Information/Activity Assign us us RO RO Revision:

Q Expected Standard NO SG COMPLETELY DEPRESSURIZED Check Intact SG E-1, Step 3 Verify NR level-GREATER THAN 8% (42% E-1, ADVERSE CTMT) Step 3.a Control feed flow to maintain NR level E-1, between 8% and 50% (42% and 50% Step 3.b ADVERSE CTMT) Check Secondary E-1, Step 4 Sample all SGs for activity.

E-1, Step 4.a 1) RESET SG blowdown sample isolation. OPEN SG Blowdown sample isolation valve(s) Request Chemistry obtain activity samples using HP coverage Verify trend history and alarm status of E-1, radiation monitors Step 4.b Main steam line -NORMAL Condenser air ejector -NORMAL SG blowdown -NORMAL Page 65 of 80 Sf "ON 4 Lesson Title: Loss of Secondary Heat Sink 10 Number: Time 2K11 NRC-01 IDA/Malf Instructor Task Assign Expected Action Revision:

Q Standard US Check PZR PORVs and Block Valves E-1, Step 5 RO Verify PORVs -CLOSED E-1, Step 5.a RO Verify block valves -AT LEAST ONE OPEN E-1, Step 5.b US Check If ECCS Flow Should Be Reduced E-1, Step 6 Subcooling should be <32°F and/or PZR level < 16%. RO Verify RCS subcooling based on core exit TCs -GREATER THAN 32°F (115°F ADVERSE CTMT) E-1, Step 6.a BOP Verify secondary heat sink E-1 Step 6.b

• Total feed flow to intact SGs GREATER THAN 530 gpm OR

• Narrow range level in at least one intact SG -GREATER THAN 8% (42% ADVERSE CTMT) RO Verify RCS pressure -STABLE OR INCREASING E-1 Step 6.c RO US Verify PZR level-GREATER THAN 16% (50% ADVERSE CTMT) Proceed to CAUTION prior to step 7. E-1 Step 6.d E-1, Step 6, Page 66 of 80 SE )N 4 Lesson Title: Loss of Secondary Heat Sink o Number: 2K11 Revision:

Q Task Time IDA/Malf Instructor Information/Activity Expected Action Standard RNO To ensure adequate ECCS flow, do not stop E-1, Step 7 any recirculation spray pumps used for core CAUTION injection flow. The recirculation spray pumps are E-1, Step 7 sequenced to automatically start 11 minutes NOTE after a CDA. Check if containment spray should be E-1, step 7 stopped. RO Verify quench spray pumps -E-1, Step 7.a US Proceed to CAUTION prior to step E-1, Step 7,a, RNO After SI reset, manual operator action is E-1, Step 8 required to: CAUTION Open the charging cold leg injection valves when RCS pressure decreases to LESS THAN 1900 psia. Restart the RHR pumps if RCS pressure decreases in an uncontrolled manner to LESS THAN 300 psi a (SOO psia ADVERSE CTMT). Page 67 of 80 S' -ION 4 Lesson Title: Loss of Secondary Heat Sink 10 Number: 2K11 Revision:

Q Time IDAlMalf Instructor Information/Activity RCS pressure should be around 1200 psi a and stable. But depending on the speed of the crew, RCS pressure may still be going down very slowly. If the crew elects NOT to stop RHR pumps based on this trend, this is satisfactory.

Crew should reset SI Task Assign us RO RO RO US BOP RO US Expected Action Restart safeguards equipment if offsite power is lost. Check RHR pumps -ANY RUNNING IN SI MODE Check RCS pressure 1) Verify pressure -GREATER THAN 300 psia (500 psia ADVERSE CTMT) Verify pressure -STABLE OR INCREASING RESET SI, if necessary STOP RHR pumps and Place in Auto Check RCS and SG Pressures

• Check pressure in all SGs INCREASING OR STABLE (consistent with plant cooldown)

• Check RCS pressure -DECREASING OR STABLE Check If Diesel Generators Should Be Stopped Standard E-1, Step B.a E-1, Step B.b E-1, Step B.c E-1, Step B.d E-1, Step 9 E-1, Step 9 E-1 Step 10 Page 6B of BO 86' ON Lesson Title: Loss of Secondary Heat Sink 10 Number: 2K11 NRC-01 Revision:

Q Task Time IDA/Malf Instructor Information/Activity Assign Expected Action No Verify AC emergency busses -BOTH ENERGIZED BY OFFSITE POWER BOP Proceed to step 10.c. RESET LOP at MB2, if required.

Offsite power is available, however it is Check offsite power from RSSA or NSSA NOT available to be closed in on bus AVAILABLE 34C. The US should recognize this and invoke the RNO. Proceed to step 10.g and, WlIEN Offsite power becomes available, THEN Perform step 10.e and 10.f. Perform the following as required (observe EDG loading requirements):

1) START an instrument air compressor

2) Turn ON PZR backup heaters (H1A and H1B) 3) Check one RPCCW pump -RUNNING 4) Using GA-5, Startup spent fuel pool cooling RESET SI, if required Standard E-1 Step 10a E-1 Step 10a, RNO E-1 Step 10c E-1 Step 10d E-1 Step 10d RNO E-1 Step 10.g E-1 Step 10.g.5 E-1 Page 69 of 80 SF 'ION Lesson Title: Loss of Secondary Heat Sink 10 Number: 2K11 NRC-01 Revision:

Q Task Time IDA/Malf Instructor

__

Expected Action Perform the following to energize MCC32-3T Check Bus 34C -ENERGIZED Proceed to step 10.j and, WHEN Power is restored to emergency bus 34C, THEN Perform step 10.i.2). Check emergency diesel generators

-BOTH RUNNING UNLOADED US! Consult with the ADTS and RMT prior to performing any local inspections in the Auxiliary Building or ESF Building. Initiate Evaluation Of Plant Status Verify cold leg recirculation capability 1) Power to recirculation spray pumps Standard Step 10h Step E-1 Step 10.i.1 E-1 Step 10.i.1 RNO Step E-1 Step 11 CAUTION Step E-1 Step 11.a Page 70 of 80 s.r TION Lesson Title: Loss of Secondary Heat Sink 10 Number: 2K11 NRC-01 Revision:

Q Task Time IDA/Malf Instructor __ _ As!;ign RO Auxiliary Building and ESF Building RO radiation will be normal. US RCS pressure will be about XXXX psia. RO US Expected Action AVAILABLE Using Attachment A, Verify power for cold leg recirculation valves -AVAILABLE Check Auxiliary Building and ESF Building radiation (radiation monitoring group histograms) Auxiliary Building (AUX) -NORMAL ESF Building (ESF) -NORMAL SLCRS Area (SLRW) -NORMAL Check for Auxiliary Building of ESF Building flooding Verify SUMP LEVEL HI lights (MB1) -NOT LIT ESF PIPE TNL ECCS PIPE CUB ESF RHR CUB Verify Annunciator SAFEGUARDS AREA FLOODING (MB1C 2-8) -NOT LIT Check If RCS Cool down And Depressurization Is Required Verify RCS pressure -GREATER THAN 300 psia (500 psia ADVERSE CTMT) Go to ES-1.2, post LOCA Cooldown and Standard E-1 Step 11.b E-1 Step 11c E-1 Step 12 E-1 Step 12a E-1 Page 71 of 80 SF Lesson Title: loss of Secondary Heat Sink 10 Number: 2K11 NRC-01 Revision: .Q Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard Depressurization Step 12b The scenario may be terminated once the transition to ES-1.2 is Page 72 of 80 SECTION Lesson Title: Loss of Secondary Heat Sink 10 Number: 2K11 NRC-01 Revision:

Q EVALUATION GUIDE I. Crew FOLLOW-UP QUESTIONS What is the Emergency Classification for this event? ALERT-Charlie One based on failure of the RCS Barrier, BA 1. The SRO candidate (US) may consider an update to the classification due to Heat Sink being RED if required feed flow cannot be established within 15 minutes. What plant condition(s) is(are) of greatest concern for (this event)? What actions did the crew take to directly mitigate (this event)? Which safety function(s}

were challenged or had the greatest potential for challenge?

Describe why. Page 73 of 80 SECTION 4 EXAM GUIDE

SUMMARY

Title: Loss of Secondary Heat Sink ID Number: 2K11 Revision:

Q Critical Tasks Note: Critical Tasks are not required for Progress Review Exams. TASK DESCRIPTION TASK # KIA >/= 3.0 BASIS SELECTION Manually trip the main turbine [before a severe (orange-path) challenge E-O --Q 045-010 A3.01 3.5/3.6 Failure to trip the main turbine under the postulated plant conditions causes develops to either the challenges to CSFs beyond subcriticality or the 045-050 those irreparably introduced integrity CSF]5 or [before transition to ECA-2.1],6 whichever happens first A 1.01 3.8/4.1 A1.023.3/3.7 by the postulated conditions.

Additionally, such an omission constitutes a A3.01 3.3/3.5 demonstrated inability by the crew to "take an action ... that would prevent a challenge to plant safety." Establish feed flow to at least one SG before bleed and feed is required.

FR-H.1-A E05 EA2.2 3.7/4.3 EA2.1 3.4 14.2 Failure to establish the minimum required feedwater flow rate, under the postulated plant conditions, results in "adverse consequence(s}

or a significant degradation in the mitigative capability of the plant" and represents a "demonstrated inability by the crew to take an action or combination of actions that would prevent a challenge to plant safety. Trip all RCPs so that an Orange Path on Core Cooling based on core exit thermocouples (718°F) does not occur when forced circulation in the RCS stops (small break LOCA). E-1 --C 3.6/3.6 009 EA1.09 4.2/4.3 009 EK3.23 Failure to trip the RCPs under the postulated plant conditions leads to core uncovery and to fuel cladding temperatures in excess of 2200°F, which is the limit specified in the ECCS acceptance criteria.

011 EA1.134.1 Failure to manually start at Establish flow from at E-O --J least one intermediate-head least one SI pump 009 EA1.04 3.4 ECCS pump under the before transition out of postulated conditions E-O, during a Small constitutes "mis-operation or Break LOCA where RCS Page 74 of 80

--SIMULATOR TRAINING SHIFT TURNOVER DATE*TIME PREPARED BY SHIFT. Today Now Shift Manager PLANT STATUS: .. Power: Thermal: 3649 MWTH PZRPressure:

psia Electric:

1284 MWe ReS T-AVE: egF RCS Leakage:

Identified:

0.015 gpm ProtectedTrain/Facility:

A TRAIN Orange Unidentified:

0.036 gpm PRA: .§.w!!l Datemme: Toda 0015 Active Tracking Records and Action Statements Equipment/Reason LCD [ Action I Date I Time in LCO 1_ Action Requirement I Time Left I ! I J 00 CompensatorY Actions I Temp Logs Watch Open Date Class Reason Reason Position None :urveillances I Evolutions in Progress I OP 3204 I Steady State Operation Reactivity Briefing (see reactivity thumbrules I spread sheet for additional info) Current Rod Height CBD@219 Xenon Trend Stable Current Boron 1046 ppm Shift The "A" TPCCW pump is out of service for oil Page 76 of 80 I ATTACHMENT VALIDATION Title: Loss of Secondary Heat Sink 10 Number: 2K11 NRC-01 Revision:

Verified By: (Initials)

Initial Conditions:

The initial condition(s) contained in the guide are certified or have been developed from certified ICs. Test Run: The scenario contained in the guide has been test run in part or whole on the simulator.

The simulator response is reasonable and as expected.

If a simulator guide revision does not affect original Test Run, then enter N/A. Simulator Operating Limits: The simulator guide has been evaluated for operating limits and/or anomalous response by reviewing the Simulator Modeling and Anomalous Response List. For Examination Scenario:

The Scenario Attributes Checklist is complete and attached.

This is not required for Progress Review Exams. Actions Complete (Signature)

Page 77 of 80

---

---

Scenario Outline Form ES*D*1 Facility:

Millstone 3 Scenario No.: 2K11 NRC-01 Op-Test No.: 2K11 Examiners:

Operators:

Initial Conditions:

IC-13, 100% Power, Middle of life, Eguilibrium Xe.

The (2lant is at 100% (2ower and at the middle of life. The "A" TPCCW (2um(2 is out service for oil I -. Event Malf. No Event No. Type'"

1 I'B' MD AFW pump oil leak. (Tech Spec entry) 2 RX10A I (RO) . Controlling channel of PZR level falls just below setpoint. (AOP 3571) 3 MS11A I (BOP) 'A' SG pressure channel failure. (3MSS-PT20A) (Annunciator response, AOP 3571} 4 FW01 R (RO) Loss of condenser vacuum and procedurally directed R (SRO) rapid downpower (5%/min).

Vacuum will stabilize . N (BOP) . (AOP 3559, AOP 3575) 5 ED04C C (RO) Loss of emergency bus 34C. (AOP 3577) C (BOP) 6 RC02D M (ALL) Small break LOCA inside CTMT. Requires Reactor Trip and Safety Injection. (AOP 3555) 7 TC03 C (BOP) , Turbine fails to trip automatically or manually, and requires a turbine runback. 8 SI07NB SIH pumps fail tq auto-start. 9 FW19 M (ALL) Loss of Secondary Heat Sink. TD AFW pump trips, 'A' MD AFW pump deenergized due to loss of bus 'B' MD AFW pump in PTL due to no oil. (success will be to establish Main Feed) .________

_____ .* {N}ormal,

{I}nstrument, {C}omponent, {M}ajor Page 78 of 80 Lesson Title: Loss of Secondary Heat Sink 10 Number: 2K11 NRC-01 Revision: .Q Assessor:

Dave Minnich QUALITATIVE ATTRIBUTES The initial conditions are realistic, in that some equipment and/or instrumentation may be out service, but it does not cue the crew into expected The scenario consists mostly of related Each event description consists of: the point in the scenario when it is to be initiated the malfunctions(s) that are entered to initiate the event the symptoms/cues that will be visible to the crew the expected operator actions (by shift position) the event termination point (if applicable)

No more than one non-mechanistic failure (e.g., pipe break) is incorporated into the scenario without a credible preceding incident such as a seismic event. The events are valid with regard to physics and Sequencing/timing of events is reasonable, and allows for the examination team to complete evaluation results commensurate with the scenario If time compression techniques are used, scenario summary clearly so indicates.

Operators sufficient time to carry out expected activities without undue time constraints.

Cues are The simulator modeling is not The scenario has been validated.

Pursuant to 10 CFR 55.46(d), any open simulator deficiencies or deviations from the referenced plant have been evaluated to ensure fidelity is maintained while running the planned Every operator will be evaluated using at least one new or significantly modified scenario.

All scenarios have been altered lAW Section 0.5 of All individual operator competencies can be evaluated.

as verified using form Each operator will be significantly involved in the minimum number of transients and specified on Form Level of difficulty is appropriate to support licensing decisions for each crew Page 79 of 80 Lesson Title: Loss of Secondary Heat Sink ID Number: 2K11 NRC-01 Revision:

Q.. Note: Following criteria list scenario traits that are numerical (QUANTITATIVE) in nature. 01. Total Malfunctions (TM) -5 to 8 required Total 8 (1) PZR level fails just below setpoint, (2) 'A' SG pressure channel failure, (3) Loss condenser vacuum, (4) Loss of emergency bus 34C, (5) Small break LOCA inside CTMT, Turbine fails to Trip, (7) SIH pumps fail to auto-start, (8) TO AFW pump 02. Malfunctions after EOP entry (EM's) -1 to 2 required Total 3 (1) Turbine fails to Trip, (2) SIH pumps fail to auto-start, (3) TO AFW pump trips 03. Abnormal Events (AE) -2 to 4 required Total 5 (1) PZR level fails just below setpoint, (2) 'A' SG pressure channel failure, (3) Loss condenser vacuum, (4) Loss of emergency bus 34C, (5) Small break LOCA inside 04. Major Transients (MT) -1 to 2 required Total 2 (1) Small break LOCA inside CTMT (2) Loss of Secondary Heat Sink 05. EOP's (EU) entered/requiring sUbstantive actions --1 to 2 required Total 2 (1) FR-H.1, (2) E-1 06. EOP Contingencies requiring substantive actions [ECAs/FRs/] (EC) --Total 1 o to 2 required (1) FR-H.1 07. Critical Tasks (CT) -2 to 3 required Total 4 E-O --Q Manually trip the main E-O --J Establish flow from at least one 51 FR-H.1-A Establish feed flow to at least one SG before bleed and feed is E-1 --C Trip alf 08. Approximate Scenario Run Time: 60 to 90 min. Total 120 min 09. EOP run time: Total 45 min 10. Technical Specifications are exercised during the scenario. (Y/N)_Y_ Page 80 of 80 MILLSTONE POWER SIMULATOR EXAM GUIDE APPROVAL SHEET Exam Title: Faulted, Ruptured Steam Generator Revision:

o 10 Number: 2K11 NRC-02 This document is the property of the Millstone Power Station which controls its distribution.

Further transfer, copying, or modification of this document is strictly prohibited without the written consent of the Millstone Power Station. Submitted D. Minnich 03/21/11 Developer Date Validated by: ate Approved by:

h, upervlsor DatE? ralntng STOP THINK ACT REVIEW

SUMMARY

OF Change Description REV/CHG Date of Change s;rop THINK ACT REVIEW SECTION SIMULATOR EXAM TABLE OF SECTIONS LISTED IN ORDER 1 . Cover Page 2. Table of Contents 3. Exercise/Exam Overview 4. Exam Guide Attachments:

Shift Turnover Validation Scenario Outline Attributes Summary of Page 3 of 74 SECTION EXAM Title: Faulted, Ruptured Steam Generator 10 Number: 2K11 NRC-02 Revision:

Q The Session will begin with the plant at 100% power and at middle of life. The "An EOG is out of service for planned maintenance.

Shortly after turnover, a narrow range Th instrument will fail high. Rods will begin stepping in. The RO should verify no runback in progress and take rod control to manual. The crew will utilize AOP 3571, Instrument Failure Response to mitigate the failure, up to and including the tripping of associated bistables.

Applicable Tech Specs are identified within the guide. Once the actions of AOP 3571 for the failed Th instrument are complete, the "C" SG controlling NR level channel will slowly fail to 0%. The BOP will need to take manual control of the 'C' FRV. Once identified, the crew should respond by entering AOP 3571, to address the problem, which will include shifting to an alternate channel and addressing Tech Specs. Once actions in AOP 3571 are complete, the "B" S/G will develop a tube leak as indicated by the N-16 Monitoring System in ALERT. The crew will respond by transitioning to 3576, Steam Generator Tube Leak. The crew should determine that the CVCS system will be able to stabilize PZR level in AUTO, but that initial tube leakage does warrant a plant shutdown and will be in excess of the Operational Leakage Tech Spec 3.4.6.2. After consulting with Plant Management, the crew will commence a rapid load reduction in accordance with AOP 3575, Rapid Downpower, at 3%/min. When the Lead Examiner is satisfied with the reactivity manipulation, a major steam line break will occur in CTMT ('B' SG). The break will be severe enough to require a Reactor Trip and Safety Injection, and a Reactor Trip 'First Out' will be received prior to the crew taking action. Automatic and the MB7 manual reactor trip switch are failed requiring the RO to manually trip the reactor from MB4 [Critical Task]. In addition, MSI Fails to auto actuate and will have to be manually actuated by the BOP [Critical Task]. Also, Several High Pressure Safety Injection components will fail to reposition requiring manual action to assure minimum safety function.

The crew will carry out the actions of E-O, Reactor Trip Or Safety Injection and transition to E-2, Faulted Steam Generator Isolation, to isolate the faulted SG [Critical Task]. After isolation the steam generator will continue to blow down into CTMT. When the "B" SG tubes become hot and dry, a SG Tube Rupture will occur. The crew will ultimately identify wide range levels and/or pressure going up in "B" SG and transition to E-3, Steam Generator Tube Rupture, from E-2. Once in E-3, the crew will determine that ruptured SG pressure is not sufficient to support the cooldown and depressurization method specified in E-3, and will transition to ECA-3.1, SGTR With Loss of Reactor Coolant -Subcoo/ed Recovery Desired. The crew will initiate an ReS cooldown as specified in ECA-3.1. Once the crew has shown that the cooldown rate is controlled

[Critical Task]. the session will end. Page 4 of 74 The SRO candidate (US) should classify this event as an ALERT-Charlie One, Barrier Failure, BA1. Duration of Exam: 75 minutes Page 5 of 74 SECTION 4 EXAM GUIDE Title: Faulted! Ruptured Steam Generator ID Number: 2K11 NRC-02 Revision:

Q All Control Room Conduct, Operations and Communications shall be in accordance with 100, Conduct of Operations. "Review the Simulator Operating Limits (design limits of plant) and the Simulator Modeling Limitations and Anomalous Response List prior to performing this exam scenario on the simulator.

The evaluators should be aware if any of these limitations may be exceeded," (NSEM 6.06) Page 6 of 74 SECTION EXAM Title: Faulted, Ruptured Steam Generator ID Number: 2K11 Revision:

Q SIMULATOR PROBLEMS DURING EXAMS It is the responsibility of the Instructors in the simulator to insure that training interruptions have a minimum negative impact on the Crew and the training we provide. Use your judgment on whether to stop the training and how the training should be commenced after the problem is corrected.

Be aware that at all times the Operators should treat the simulator as if it were the plant and you too should treat it as much like the plant as possible when they are in the simulator.

As soon as the Instructors are aware of a simulator problem that will adversely affect the training in progress (computer fault, etc.) the Instructor should: Place the simulator in FREEZE if possible. Announce to the Crew that there is a simulator problem. Request that the Crew either standby (for minor trouble that can be handled quickly) or leave the simulator control room. (The Crew should leave the simulator for problems which involve major switch alignments). Deal with the problem (reboot, close tripped breaker, call STSB, etc.) After the Instructors believe the simulator is restored to service, the Crew should be told how training will continue.

If it is possible and felt to be acceptable to the Instructors, training can begin where it left off with an update on plant parameters and each Crew member is prepared to restart. If training will not begin where it left off, the crew should be told how and where training will begin again. Once the Crew has been told how and where training will begin, have the crew conduct a brief so that the Instructor can insure that the crew has all the necessary information to continue with the scenario. Once all Crew members and Instructors are satisfied that they have the necessary information to continue the scenario, place the simulator in RUN and announce to the Crew that you have continued the training session. Page 7 of 74

"':TION 4 lesson Title: Faulted, Ruptured Steam Generator 10 Number: 2K11 Revision:

Q INITIAL SETUP INSTRUCTIONS Simulator Setup Checklist VERIFY that the current approved training load is loaded. REMOVE the step counter OVERRIDE and allow the counters to step out during the IC reset. RESET to IC# 18 or Temp IC# N/A, LOAD Schedule file 2K11 NRC-02 and, if needed, LOAD or VERIFY BASIC.EVT file Wait at least one minute, PLACE Simulator to RUN. ENSURE Simulator fidelity items cleared If Necessary, RESET the Plant Calorimetric at the Instructor Station PPC going to Unit 3 top menu, then selecting BOP Menu, then selecting Plant Calorimetric Menu. Verify calorimetric calculation selected appropriately for the plant conditions. (Normally steam flow for 100% power. CHECK the STEP COUNTERS at correct position for plant conditions. PLACE _7_ tiles under the DEMINS IN SERVICE lama cord label on MB6. PLACE the Main Turbine on the LOAD LIMITER and ENSURE Standby Load Set MATCHED if conditions require. PLACE the Westronic (2) recorders in active/run by depressing up or down arrow for each. For the NR4S recorder:

select group 3 or 4 at power setting CLEAR DCS alarms on MB7 and BOP console. Reset SMM alarms if required. Select Status Grid on the RMS console. VERIFY annunciator, "COMPUTER FAILURE" (MB4C, 1-11), is NOT LIT. 10. As needed, RESET Computer Terminals to At Power displays if 100% power IC. 11. Ensure that the protected train and environmental placards are appropriately hung 12. Verify various pot setting correct for plant conditions.

Equipment 005: The "An EDG is out of service. "An EDG (Yellow Tag on Start Switch, Output Breaker and Prelube pump) Verify the MONITOR Time Display the same as the digital time display on MB4. If not page/call the Unit Tech. Page 8 of 74

--TlON4 Lesson Title: Faulted, Ruptured Steam Generator ID Number: 2K11 NRC-02 Revision:

Q INITIAL SETUP INSTRUCTIONS Initial Malfunctions/lOsllDAs:

PLACE GREEN PLACARDS FOR ALL INTAKE PARAMETERS ON MB6 PLACE THE "A" TRAIN PROTECTED PLACARD ON MB4 Delay Ramp Event Severity Final Relative ID Number Description Time Time Trigger Or Value Value Order . MALFUNCTIONS I RP10A Train 'A' Automatic Reactor Trip Fails I Initial *RP10B I Train 'B' Automatic Reactor Trip Fails Initial RP09B ! MB7 Manual Reactor Trip Switch Fails Initial RP08A Train 'A' Main Steamline Isolation Fails Initial I RP08B [ Train 'B' Main Steamline Isolation Fails [ Initial .RP11E HPSI components fail to respond to a 81 signal Initial EG07A I 'A' EDG Trip I Initial MB8A B11 34C Bus Loss of Control Power ON Initial RX05D Loop 4 narrow range Th, 3RCS*TE441A 60 sec 1 RX121 "C" SG NR Controlling Channel fail low 60 sec 4 0% ! I SG03B I'B' SG

_I ___ 90 sec 7 0.3 gpm _ .... _ .... _ .... _ .... _ .... --.... Page 9 of 74

';TION 4 Lesson Title: Faulted, Ruptured Steam Generator 10 Number: 2K11 NRC-02 Revision: .Q INITIAL SETUP INSTRUCTIONS Delay Ramp-! Event Severity I Final I Relative I 10 Number Description Time Time Trigger Or Value Value Order J MS01B Steam line break in CTMT from the 'B' SG. 160 sec 10 1.5E6 , Ibm/hr ! SG01B I 'B' SG Tube Rupture i I 11 1000 I I I I 1 gpm I REMOTE FUNCTIONS

.... '. .... .. .... I RXR 109 I Protection Set #4 2 OPEN . RXR 04 Loop 4 OP Ll T Bistable 3 TRIP RXR33 Loop 4 C-4 Bistable 20 sec 3 TRIP I RXR 08 I Loop 4 OT Ll T Bistable 40 sec 3 TRIP 3 TRIP Loop 4 C-3 Bistable 60 sec 3 TRIP l RXR 37 RXR 113 Loop 4 Low Tavg Bistable 80 sec I 3 TRIP RXR 117 Loop 4 P-12 Bistable 100 sec I 3 I RXR 109 Protection Set #4 . 120 sec CLOSE r RXR 106 Protection Set #1 5 i OPEN I i TRIP RXR96 LS 539A (P-14) I 6 TRIP RXR84 LS 539B (LO-LO Level) 20 sec 6 RXR 106 Protection Set #1 40 sec 6 CLOSE I I MSR 01 Aux Boilers 8 ON .... _--_... _ ... _ .. _ .... _-.... _....._......_.....---... _-.... _---.... _.... _.... _.... _ .. _ ... _ ... _ .. _ ... _ ... _._.. _ Page 10 of 74 Lesson Title: Faulted, Ruptured Steam Generator ID Number: 2K11 NRC-02 INITIAL SETUP INSTRUCTIONS Revision:

Q ID Number FWR33,62 I EDR18 3CNS-V9, V11 Resets MCC 32-3T Description I ! Delay Time Ramp Time Event Severity Trigger Or Value 9 CLOSE I RESET 12 Final Value Relative Order I ! EDR44 RCR 23 -26 I Acknowledges Inverter 6 Alarms I RCP Overcurrent Switch Position 120 sec 12 13 RESET COLD I OVERRUjES

......*.............

'!.', EGLOOOO1 EGLOOOO2 EGLOOO12 'A' EDG Pre-Lube Pump 'red' I'A' EDG Pre-Lube Pump 'green' I'A' EDG Output Breaker 'green' OFF OFF OFF Initial EGLOOO13 I EGLOOO14 'A' EDG Output Breaker 'red' I I'A' EDG Output Breaker 'amber' I OFF OFF I Initial Initial Page 11 of 74 TlON 4 Lesson Title: Faulted, Ruptured Steam Generator 10 Number: 2K11 NRC-02 Revision: .Q INITIAL SETUP INSTRUCTIONS Lead Refer to the "Briefing Script for the Operational Exam" and brief the crew. Go over the Plant/simulator differences, which follow. Booth IF desired by the NRC Exam Team, commence recording Simulator session Booth Perform the crew turnover (Initial Conditions page at end of LP) with the US. Have the US brief his crew on plant conditions and any major equipment OOS. PLANT/SIMULATOR DIFFERENCES: Rad Monitor Historical Oata--Simulator Rad Monitor historical data not valid prior to the beginning of this exercise. If not using the speed dial option on the phone system, the operator must dial either #3333 or #3334 to reach the person/department they desire. The following PPC programs do not function on the simulator: Samarium Follow Xenon Follow Sequence of Events Flow indications 3SIH-F1917 (charging ECCS flow). 3SIH-F1918 (A SI pump flow) and 3SIH-F1922 (8 SI pump flow) will show flow at low flow rates. Page 12 of 74 SF ON4 Lesson Title: Faulted, Ruptured Steam Generator 10 Number: 2K11 NRC-02 Revision:

Q Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Event 1: Loop 4 Tavg fails high T+1 min of RX05D Loop 4 narrow range Th, turnover 3RCS*TE441A Trigger 1 Tave will fail high. Rods will drive in. Delta T for "0" Loop will go up. AOP 3571 (Rev. 009*07) Actions US Transition to AOP 3571, Instrument Failure Response The RO will place Rod Control in CREW Determine the initiating parameter and manual; PZR level control is already place the effective controller in manual. at 100% program. Steam Dumps not armed so no immediate impact CREW Stabilize the plant parameters.

The US should recognize the correct US Perform Corrective Actions Using attachment is lA' and announce as Appropriate Attachment such. Instrument Failure RCS NR Temperature Channel Failure After discussing the expected response, the US should direct the RO RO Defeat the failed channel input. to place the cutout switches in loop 3 Loop Temp Cutout -delta T and pull out. Loop Temp Cutout -Tavg Standard AOP 3571 Step 1 AOP 3571 Step 2 AOP 3571 Step 3 Attachment A AOP 3571 Att.A Step 1 Page 13 of 74 SEf lN 4 Lesson Title: Faulted, Ruptured Steam Generator 10 Number: 2K11 NRC-02 Revision:

Q Task Time IDA/Malf Instructor Information/Activity

__ Assign Expected Action Standard Expected response is as follows: OT/OP delta T Record Select TREF/AUCT TAVE DEVIATION TAVE HI should clear when Temp Cutout for TAVG is pulled Check the following annunciators NOT AOP 3571 LIT: Att.A Step 2 TREF/AUCT TAVE DEVIATION MB4C 6-5 TAVE HI MB4C 5-6 No action may be required RO Restore T AVE -T REF error to within 1 AOP 3571 depending on when crew placed Att.A Step 3 of and return rod control to automatic.

rods in manual. Monitor PZR level until stable. If PZR AOP 3571 level controller is in manual, Restore Att.A Step 4 pressurizer level to program level and Place PZR level controller in automatic. If RCS loop 3 cold leg narrow range AOP 3571 temperature channel computer point Att.A Step 5 (RCS-T 431 E) is X-tagged, the plant Note calorimetric program will automatically shift to an NI based output. When conditions have stabilized, AOP 3571 Observe MB annunciators and Att.A Step 5 parameters.

Immediately report any unexpected or unexplained conditions to the Shift Manager. Page 14 of 74 SE JN4 Lesson Title: Faulted, Ruptured Steam Generator 10 Number: 2K11 NRC-02 Revision:

Q Task Time 10A/Malf Instructor Information/Activity _ _ Assign us us Table 3.3.1 -FU 6, 8 Action 6 applies US! Table 3.3.2 -FU 50 Action 20 applies SM These are 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> requirements to trip bistables.

Expect the RO to do a lamp test of MB2 RO and MB4. CREW Failure is not SSPS CREW Channel indication is NOT normal. Step 6.d is N/A. T=2 mins of RXR109 Protection Set 4 Door request 'OPEN' Trigger 2 Expected Action Trip the associated Reactor Protection System bistable(s):

Place a check mark in the box above the appropriate channel that requires tripping on page 6 of this Attachment.

Refer to Technical Specification 3.3.1 and 3.3.2. Check the existing bistable status to ensure a reactor trip will not occur when the failed channel is tripped. If the General Warning lamp is lit on 3RPS*RAKLOGB, Placing train A SSPS "Multiplexer Test" switch in "A+B" will cause the reactor to trip. The following step will distinguish whether the failure is within SSPS or the Protection channel. If bistable light(s) (MB20 or MB4F) indicate that a single bistable input has tripped and channel indication is normal, PERFORM the following

.... Request the I&C Department trip the appropriate bistables using Attachment A and Attachment S. Standard AOP 3571 Att.A Step 6 AOP 3571 Att.A Step 6a AOP 3571 Att.A Step 6b AOP 3571 Att.A Step 6c AOP 3571 Att.A Step 6.d CAUTION AOP 3571 Att.A Step 6d NOTE AOP 3571 Att.A Step 6d AOP 3571 Att.A Step 6e Page 15 of 74 SP lN4 Lesson Title: Faulted, Ruptured Steam Generator 10 Number: 2K11 NRC-02 Revision:

Q Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard T=3 mins of Will trip bistables (with 20 second time RO Verify the appropriate bistable status AOP request delays between each bistable) and light(s) are lit. Att.A Step Trigger 3 close the RXR04 (trip) TRIP -OP DELTA RXR33 TRIP -RXR08 TRIP -OT DELTA RXR37 TRIP -RXR113 TRIP -Low RXR117 TRIP -P-12 RXR109 (close) CLOSE -Protection Set 4 door Once the US has addressed Specs and bistables are tripped, on to EVENT EVENT 2: "C" SG NR Level Controlling Channel fails Low T= BistabJes RX121, "C" SG Narrow Range Level Crew should enter AOP 3571, "Instrument tripped (0%,60 Transmitter Fails low over 60 Failure Response." sec ramp) seconds. Trigger 4 AOP 3571 Actions (rev 009-07) RO Do not leave the rod selector switch in AUTO AOP 3571 Page 16 of 74 Sf ON 4 Lesson Title: Faulted, Ruptured Steam Generator 10 Number: 2K11 NRC-02 Revision:

Q Time IDA/Malf Instructor Information/Activity MB Annunciator "SG C LEVEL DEVIATION" will be the first to alarm. "C" Feed Reg. Valve is the affected Controller.

The BOP should take the "c" Feed Reg. Valve Controller to 'Manual'.

Appropriate Attachment is liN" The BOP should have already placed the 'c' SG feed regulating valve in MANUAL. BOP should restore level to 50% Task Assign Expected Action Standard while diagnosing a related instrument failure unless the reason for rod movement is a turbine runback. Step 1 CAUTION CREW If a reactor trip occurs. immediately go to E-O Reactor Trip or Safety Injection.

AOP 3571 Step 1 NOTE US Determine The Initiating Parameter And Place The Affected Controller In MANUAL AOP 3571 Step 1 CREW Stabilize The Plant Parameters.

Step 2 US It is desired that I&C personnel trip the AOP 3571 bistables

... Step 3 NOTE Perform Corrective Actions Using Appropriate AOP 3571 Attachment Step 3 Instrument Failure Attachment Narrow Range SG Level Channel Failure N If the failed NR level channel is selected as AOP 3571 the input to SG level control, Perform the Attachment following:

N Step 1 BOP Verify the affected SG feed regulating valve is AOP 3571 in MANUAL. Att. N Step 1.a BOP Restore SG level to normal. AOP 3571 Att.N Page 17 of 74 Sf ON4 Lesson Title: Faulted, Ruptured Steam Generator 10 Number: 2K11 NRC-02 Task Time IDA/Malf Instructor Information/Activity

____

The US should direct the BOP to BOP select channel 2 as the controlling channel. BOP CREW US US Crew should log into 3.3.1 t FU 13, action 3.3.2, FU 6.c, action 20 (3.3.2 FU I action 21 is for < minimum which is not the Channels operable requirements 3.3.3.5 and 3.3.3.6 are met. However the US should verify that they don't apply. RO Revision:

Q Expected Action Defeat the failed channel input by selecting the alternate channel on the level selector.

When SG level is restored to normal and feed/steam flow are matched. Place the affected steam generator feed regulating valve controller in AUTO. When conditions have stabilized, observe MB annunciators and parameters.

Immediately report any unexpected or unexplained conditions to the Shift Manager. Trip the associated Reactor Protection System bistable(s):

Place a check mark in the box above the appropriate channel that requires tripping on the last pages of this Attachment.

Refer to Technical Specification 3.3.1. 3.3.2, 3.3.3.5 and 3.3.3.6. Check the existing bistable status to ensure a reactor trip will not occur when the failed channel is tripped. Standard Step 1.b AOP 3571 Att. N Step 1.c AOP 3571 Att.N Step 1.d AOP 3571 Att. N Step 1.e AOP 3571 Att. N Step 2 AOP 3571 Att.N Step 2a AOP 3571 Att. N Step 2.b AOP 3571 Att. N Step 2.c Page 18 of 74 SE IN 4 Lesson Title: Faulted, Ruptured Steam Generator 10 Number: 2K11 NRC-02 Time IDAlMaif Revision:

Q Task Instructor Information/ActivitL_.

AS!i!9I1_

Expected Action This will not be If bistable status light(s} (MB2D or MB4G) indicate that a single bistable input has tripped and channel indication is normal, PERFORM the following:

Annunciator "SG LEVEL HI HI" comes in during the tripping of B/Ss. The task of tripping bistables was already conducted for the T ave failure. At the examiner's discretion, once Tech Specs are addressed, move on to Event 3, without tripping bistables. Request the IC&E Department trip the Protection Set 1 Door appropriate bistables using Attachment Nand Attachment S. HI HI Level for SG 3, then LO LO Level SG 3, then protection set 1 door Verify the appropriate bistable status lights are lit. Not Applicable as L T539 is failed If any two of the NR level channels which serve as inputs to AMSAC are failed (L 551, LT-552, LT-538, or LT-547), Perform Standard AOP 3571 Att. N Step 2.d AOP 3571 Att. N Step 2.e AOP 3571 Att. N Step 2.f AOP 3571 Attachment N step 3 T=2 mins of request Trigger 5 T=3 mins of request Trigger 6 RXR 106 'OPEN' RXR96 'TRIP' RXR84 'TRIP' RXR 106 'CLOSE' Page 19 of 74 Sf 8N4 Lesson Title: Faulted, Ruptured Steam Generator 10 Number: 2K11 NRC-02 Revision:

Q Task Time IDA/Malf Instructor Information/Activit}'

_____ _ Expected Action Standard the following: If either indicator 3FWS*U 529A or AOP 3571 3FWS*U 548A is failed, Refer to TRM Table Attachment 7.4.1, Fire Related Safe Shutdown N step 4 Components, "Auxiliary Feedwater System." Request I&C Department perform AOP 3571 corrective maintenance on failed Attachment instrument.

N step 5 Event 3: 'B' SG Tube Leak (AOP 3576), and subsequent procedurally required rapid down power. SG03B, SIG B TUBE LEAK, -410 gpd T=AOP sev 0.3 3571 gpm, 90 complete or sec ramp) examiner's cue Trigger 7 Indications of the tube leak includes ARC-21 going into ALERT then ALARM, as well as N-16 ALERT and 16 HIGH. Entry conditions are met for AOP 3576. The US should announce and enter Page 20 of 74 Sf ON 4 Lesson Title: Faulted, Ruptured Steam Generator ID Number: 2K11 NRC-02 Revision: .Q Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard AOP 3576. AOP 3576 Actions (Rev 004*02) Foldout Page must be open. 3576 Step 1 NOTE Step 1 is a continuous action step and should be performed at any time additional charging flow is required to maintain pressurizer level. Verify PZR 3576 Step 1 The leak rate is small enough such that RO Check PZR Level -DECREASING 3576 minimal adjustment of the charging flow Step 1.a control valve will be necessary.

Proceed to step 3576 Step 1.a RNO Fully Open charging line flow control 3576 Step 1.b Check letdown orifice isolation valves -ONLY 3576 ONE OPEN Step i.c Check PZR level-3576 Step 1.d Proceed to step 3576 Step 1.d RNO Page 21 of 74 Sf: 'IN 4 Lesson Title: Faulted, Ruptured Steam Generator 10 Number: 2K11 NRC-02 Task Time IDA/Malf Instructor Information/Activity Assign Primary To Secondary Leakage will be verified based on N-16 Monitoring System and abnormal trends on 21. Revision: .Q Expected Action Adjust charging flow control valve to maintain PZR level on level setpoint. , If desired, Place charging line flow controller in AUTO. Notify Chemistry Request Chemistry perform SP 3861, "Primary to Secondary Leak Rate Determination," to: Determine the presence of primary to secondary leakage. Determine the leak rate. Identify the leaking SG. SG tube leakage can be interpreted as "verified" when any two of the bulleted substeps of step 3 are satisfied.

Verify Primary To Secondary Leakage Check trend history and alarm status of condenser air ejector radiation monitor NOT NORMAL Check trend history and alarm status of steam generator blowdown radiation monitor -NOT NORMAL Standard 3576 Step 1.g 3576 Step 1.h 3576 Step 2 3576 Step 2.a 3576 Step 3 NOTE 3576 Step 3 3576 Step 3 Page 22 of 74 S 'ION Lesson Title: Faulted, Ruptured Steam Generator 10 Number: 2K11 NRC-02 Time IDA/Malf Instructor Information/Activity Blowdown will need to be isolated based on ARC-21 in ALARM, as well as N-16 HIGH, Revision:

Q Task Assign Expected Action Standard Check trend history and alarm status of main steam line radiation monitors -NOT NORMAL Check Chemistry grab sample INDICATES PRESENCE OF PRIMARY TO SECONDARY LEAKAGE Check trend history and alarm status of N16 monitors -NOT NORMAL Perform Monitoring Of N16 Monitor 3576 Step 4 Initiate monitoring of N16 monitor 3576 Step 4.a Verify SG Slowdown 3576 Step 5 Check if blowdown should be isolated 3576 Step 5.a Condenser air ejector radiation monitor IN ALERT OR ALARM OR Steam generator blowdown monitor -IN OR Chemistry grab sample indicates primary to secondary leakage -GREATER THAN Page 23 of 74

"'ION4 Lesson Title: Faulted, Ruptured Steam Generator 10 Number: 2K11 Revision:

Q Task Time IDA/Malf Instructor Information/Activity Assi9 fl The BOP will need to close the SG blowdown isolation valves. MSR01 to This will start the Aux Boilers. T = when 'ON'directed Expected Action OR EQUAL TO 75 Annunciator N16 HIGH (MB2B 3-6A) -IN ALARM Check SG blowdown isolation valves CLOSED 3BDG-CTV22A 3BDG-CTV22B 3BDG-CTV22C

• 3BDG-CTV22D CLOSE valves. Proceed to step 6. Limit Effects Of Secondary Contamination Check auxiliary steam -SUPPLED FROM MAIN STEAM Using OP 3331A, "Auxiliary Boiler, Steam and Condensate" Perform the following: Startup of auxiliary boiler A (B) Standard 3576 Step 5.b 3576 Step 5.b RNO 3576 Step 5.c 3576 Step 6 3576 Step 6.a 3576 Step 6.b Page 24 of 74 SE )N4 Lesson Title: Faulted, Ruptured Steam Generator 10 Number: 2K11 Revision:

Q Task Time IDA/Malf Instructor Information/Activit}'

___ AssijJn_ _ _ Expected Action Standard Trigger 8 Shift auxiliary steam from main steam to auxiliary boiler system. Notify Unit 2 of auxiliary steam 3576 Step 6.b RNO Locally Close condensate This will close 3CNS-V9 & 3CNS*T =5 min 3576 recirculation to condensate V11, and then .....from being to Step 6.c surge tank isolation valves dispatched (3CNS-V9 and 3CNS-V11)

Trigger 9 Report as PEO that 3CNS*V9 & Request HP determine if personnel should be 3576 3CNS*V11 are closed evacuated from affected areas Step 6.d T =when BOOTH Report as HP that surveys will be

• Turbine Bldg (north end) called taken to determine if these areas are safe. Secondary sample sink CPE MS Valve Bldg Evacuate personnel from affected 3576 Step 6.e Examiner Inform the US that the SM will Refer Refer to C OP 200.11, "Operation of a Cross 3576 to C OP 200.11. Contaminated System," and Perform any Step 6.f required actions Check If Unit Shutdown Should Be Initiated 3576 Page 25 of 74 Sf ON4 Lesson Title: Faulted, Ruptured Steam Generator ID Number: 2K11 NRC-02 Time IDA/Malf Instructor Information/Activity Inform the US that the SM will evaluate for classification.

A plant shutdown will be required based on ARC-21 in ALARM, as well as N-16 HIGH. Revision:

Q Task Assi9f'l Expected Action Standard Step 7 Check any of the 3576 Step 7.a Condenser air ejector radiation monitor IN ALERT OF ALARM OR Chemistry grab sample indicates primary to secondary leakage in any SG GREATER THAN OR EQUAL TO 75 gpd OR Condenser air ejector radiation monitor correlation to leak rate (gpd) indicates primary to secondary leakage -GREATER THAN OR EQUAL TO 75 gpd OR Annunciator N-16 HIGH (MB2B 3-6A) -IN ALARM Evaluate event using MP-26-EPI-FAP06-003, 3576 Unit 3 Emergency Action Levels (Barrier Step 7.b Failure) Check plant status -MODE 1 OR 3576 Step 7.c Proceed to step 9. 3576 Step 7.d Page 26 of 74 Sl .ON4 Lesson Title: Faulted, Ruptured Steam Generator 10 Number: 2K11 NRC-02 Time IDA/Malf Instructor Information/Activity The US should proceed to the 'Perform Unit Shutdown' step 9. T =brief for Report as chemistry "8" S/G sample plant results indicate the presence of shutdown primary to secondary leakage. occurs Rate of Increase limit NOT met, but leakage> 150 gpd Revision:

Q Task Assign Expected Action Perform Unit Shutdown Verify a leakage rate of increase limit met: Check leakage increased in any SG by GREATER THAN OR EQUAL TO 15 gpd IN A 30 min PERIOD AFTER THE INITIAL SPIKE OR Check condenser air ejector radiation monitor RATE OF CHANGE ALARM -IN ALARM OR Check N 16 S/G Leak Detection Status (PPC) HIGH RATE (75 GPO & 15 GPO RISE IN 30 MIN) -IN ALARM Proceed to step 9.c Check charging pumps -TWO REQUIRED TO MAINTAIN PZR LEVEL Standard 3576 Step 9 3576 Step 9.a 3576 Step 9.a RNO 3576 Step 9.c Page 27 of 74 SF 8N 4 Lesson Title: Faulted, Ruptured Steam Generator 10 Number: 2K11 NRC-02 Task Time IDA/Malf Instructor Information/Activity Assign Ensure The US enters the LCO for 3.4.6.1, OPERATIONAL LEAKAGE for primary to secondary leakage (150 gpd, 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> AOT to hot standby).

T = Calls the BOOTH Direct as OMOC to commence a OMOC rapid load reduction in accordance with AOP 3575, Rapid Downpower, at 3%/min. Revision:

Q Expected Action Proceed to step 9.i Check SG leakage: Condenser air ejector radiation monitor IN ALARM OR Chemistry grab sample indicates any SG leakaage -GREATER THAN OR EQUAL TO 150 gpd OR N16 S/G Leak Detection Status (ppe) HIGH HIGH (>150 GPO) -IN ALARM Initiate power reduction to be in MODE 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. Check plant status -MODE 3 Return to NOTE prior to step 9. Standard Step 3576 Step 9.i 3576 Step 9.j 3576 Step 9.k 3576 Step 9.k RNa Page 28 of 74 S' Lesson Title: Faulted, Ruptured Steam Generator 10 Number: 2K11 NRC-02 Revision:

Q Task Time IDA/Malf Instructor Information/Activity.

__ .

AOP 3575 Actions (Rev 017-03) Rod Control will be in Auto. The crew may perform downpower on load limit or load set. Either is acceptable. Expected Action If at any time either of the following annunciators is received, Immediately perform step 7: };-ROD CONTROL BANKS LIMIT LO (MB4C 3-9) };-ROD CONTROL BANKS LIMIT LO-LO (MB4C 4-9) Check Rod Control -IN AUTO Align EHC Panel Check load reduction using load set DESIRED Proceed to Note prior to step 3. Using Attachment E align EHC panel for LOAD SET operation.

CONVEX requested load reductions should be performed at 5%/min and completed within 15 minutes of notification.

Determine Power Reduction Rate (%/min). Standard AOP 3575 Step 1 NOTE AOP 3575 Step 1 AOP 3575 Step 2 AOP 3575 Step 2.a AOP 3575 Step 2.a RNO AOP 3575 Step 2.b AOP 3575 Step 3 NOTE AOP 3575 Step 3 Page 29 of 74 SF Lesson Title: Faulted, Ruptured Steam Generator 10 Number: 2K11 NRC-02 Revision:

Q Task Time IDA/Malf Instructor Assi9!!_ _ _ _ Expected Action The load reduction should be performed Check desired power reduction rate -3% at 3%/min as directed by min OR 5% I MIN Management.

If SI actuation occurs during this procedure, Go to E-O, Reactor Trip or safety Injection, and restore from rapid boration lineup. Initiate Rapid Boration Verify RCS makeup system in -AUTO START one boric acid transfer pump. OPEN emergency boration valve (3CHS*MV81 04). Verify direct boric acid flow (3CHS-FI 183A) INDICATED.

OPEN charging line flow control valve, to match boric acid flow (3CHS-FI 183A) Record time boration started Time _______ Check Rod Control-AVAILABLE FOR ROD INSERTION Check use of "Rapid Downpower Summary Sheet" (RE-H-17) in the RE Curve and Data Book -DESIRED Standard AOP Step AOP Step AOP Step AOP Step AOP Step AOP Step AOP Step AOP Step AOP Step AOP Step AOP Step Page 30 of SE Lesson Title: Faulted, Ruptured Steam Generator ID Number: 2K11 Revision: .Q Task Time IDA/Malf Instructor

___ E:x.pected Action Standard Proceed to step AOP 3575 Step 4.h. RNO About 19 minutes if "Rapid Downpower Using the "Rapid Downpower Summary AOP 3575 Summary Sheet" is used. Sheet" 17), Determine approximate Step 4.i boration time Proceed To step AOP 3575 Step 4.j Use 18 gal BA/% Power to determine boration AOP 3575 time in step 4.1 Step 4.k Using formula, Determine boration time (If AOP 3575 gravity borating, use net charging flow (chg + Step 4.1 seal inj-seal return total flow) for BA flow rate: Total Power Change (.6 %) X (gal BA/% = min Power) BA Flow Rate Boration Time AOP 3575 Proceed to step 6. Step 4.m If at any time the power reduction rate or final AOP 3575 desired power level must be changed, Return Step 6 to step 1. NOTE US/BOP Initiate Load Reduction AOP 3575 Page 31 of 74 SF? -'ON Lesson Title: Faulted, Ruptured Steam Generator 10 Number: 2K11 NRC-02 Revision:

Q Task Time IDA/Malf Instructor

__

Expected Action Check Rapid or gravity boration -IN PROGRESS Check turbine OPERATING MANUAL Check load reduction using load set DESIRED Perform the following: Using Attachment F, Rotate LOAD LIMIT SET in CCW direction consistent with desired down power schedule. Proceed to step 6.f. 3% should be Select LOAD RATE LIMIT %/MIN to the desired value (1 %,3%, or 5%) The BOP should adjust Load Set to Utilizing DECREASE LOAD pushbutton, about 300 MWe. Adjust LOAD SET to desired final MWe Energize all PZR heaters Adjust Pzr Spray Valves to 50% setpoint (RCS-PK 455B and RCS-PK 455C) Adjust boration time and/or flow rate as necessary to maintain: Rods above the Rod Insertion Limit (RIL) Tavg within +/-5_F of Tref Standard Step 6 AOP 3575 Step 6.a AOP 3575 Step 6.b AOP 3575 Step 6.c AOP 3575 Step 6.c RNO AOP 3575 Step 6.d AOP 3575 Step 6.e AOP 3575 Step 6.f AOP 3575 Step 6.g AOP 3575 Step 6.h Page 32 of 74 Sf 'ON 4 Lesson Title: Faulted, Ruptured Steam Generator 10 Number: 2K11 NRC-02 Revision:

Q Task Time IDAIMalt Instructor Information/Activity Assign Expected Action

• AFD within COLR limits Check rapid OR gravity boration performed for the time determined in steps 4.i. or 4.1. Proceed to step 6.k. and, WHEN Boration has been performed for the desired time, THEN Using Attachment G, stop boration.

Using Attachment G, stop boration Check power reduction

-CONVEX REQUESTED Inform CONVEX of load reduction rate (MWe/min) and final MWe level. Verify Rod Position Above RIL Check ROD CONTROL BANKS LIMIT LO-LO (MB4C 4-9) annunciator

-LIT Proceed to step 7.g and, IF at any time, the annunciator is received, THEN Perform steps 7.c, 7.d and 7.e Check ROD CONTROL BANKS LIMIT LO (MB4C 3-9) annunciator

-LIT Standard AOP 3575 Step 6'; AOP 3575 Step 6.i RNO AOP 3575 Step 6.j AOP 3575 Step 6.k AOP 3575 Step 6.k RNO AOP 3575 Step 7 AOP 3575 Step 7.a AOP 3575 Step 7.a RNO AOP 3575 Step 7.g Page 33 of 74 SE' 'ON 4 Lesson Title: Faulted, Ruptured Steam Generator 10 Number: 2K11 NRC-02 Revision:

Q Task Time IDA/Malf Instructor Information/Activity _ Expected Action Proceed to step 8 and IF the annunciator is received, THEN Perfrom step 7.h and 7.i Using Attachment C, "Rapid Downpower Parameters" MONITOR parameters Degrade Condenser Backpressure Verify Final Desired Turbine Load LESS THAN 72% 972 MWe) Using OP 3329, "Condenser Air Removal", Degrade condenser backpressure to between 2.0 in. HgA and 4.0 in. HgA. T= When the Examiners are satisfied Examiners with the reactivity manipulation, Cue move on to the next event. Event 4: 'B' main steam line break in CTMT. T= MS01B This will intiate the Steamline Examiners Cue 1.5E6,60 break in CTMT from the 'B' SG. sec Trigger 10 Standard AOP 3575 Step 7.g RNO AOP 3575 Step 8 AOP 3575 Step 9 AOP 3575 Step 9.a AOP 3575 Step 9.b Page 34 of 74 SEf ",)N 4 Lesson Title: Faulted, Ruptured Steam Generator ID Number: 2K11 NRC-02 Revision:

Q Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard The break will be severe enough to require a Reactor Trip Safety Injection, and a Reactor Trip 'First Out' will be prior to the crew taking action. Automatic and the MB7 reactor trip switch are failed requiring the RO to manually trip reactor from MB4 [Critical Task] The US should direct a manual trip and safety US should go to Silence" before reactor E-O (Rev. 026) Crew Foldout page must be open E-O, Step 1, NOTE ADVERSE CTMT defined as GREATER THAN 180°F or GREATER THAN 10 5 R/hr in containment. The reactor can be interpreted as "tripped" when any two of three bulleted substeps of Step 1.* are satisfied.

EVENT 5: Automatic and MB7 manual reactor switch RO Verify Reactor E-O, Step 1 Page 35 of 74 SEr 4 Lesson Title: Faulted, Ruptured Steam Generator 10 Number: 2K11 NRC-02 Revision:

Q Time IDA/Malf Instructor Information/Activity A Reactor First Out annunciator is in. the RO should trip the reactor manually from MB4. [*] [Critical Task] The crew should have manually initiated SI. Task Assign E!Jlected Action Standard Check reactor trip and bypass breakers -OPEN Check rod bottom lights -LIT Check neutron flux -DECREASING TRIP the reactor. E-O, Step 1, RNO [*] Verify Turbine Trip E-O, Step 2 Check all turbine stop valves -CLOSED E-O, Step 2.a BOP Verify Power to AC Emergency Busses E-O, Step 3 BOP Check busses 34C and 340 -E-O, Step 3.a BOTH ENERGIZED us Check If Slls Actuated E-O, Step 4 Verify SAFETY INJECTION ACTUATION E-O, annunciator

-(MB4D 1-6 or MB2B 5-9) -LIT Step 4.a us Check if SI is E-O, Step 4.a, RNO CTMT pressure GREATER THAN 18 psia Page 36 of 74 S' -ION Lesson Title: Faulted, Ruptured Steam Generator 10 Number: 2K11 NRC-02 Task Time IDA/Malf Instructor Information/Activity

__ _. Assign BOOTH NOTE: Monitor "8" SG WR level. When it reaches 10% Insert the SGTR malfunction RO RO EVENT 7: HPSI components fails to Auto-Actuate.

RO manually should start the SI pumps. RO Revision:

Q Expected Action OR PZR pressure LESS THAN 1890 psia OR PZR level LESS THAN 9% OR RCS subcooling LESS THAN 32°F OR

• SG pressure LESS THAN 660 psig Check Reactor trip and bypass breakers OPEN Verify Service Water Pumps -AT LEAST ONE PER TRAIN RUNNING START pump(s) Verify Two RPCCW Pumps -ONE PER TRAIN RUNNING Verify ECCS Pumps Running

• Check Sl pumps -RUNNING

• Check RHR pumps -RUNNING Standard E-O, Step 4.c E-O, Step 5 E-O, Step 5, RNO E-O, Step 6 E-O, Step 7 Page 37 of 74 sr -'ON 4 Lesson Title: Faulted, Ruptured Steam Generator 10 Number: 2K11 NRC-02 Task Time IDA/Malt Instructor Information/Activity Assign BOP The BOP should isolate feed to the BOP faulted SG as soon as identified.

Revision:

Q Expected Action Check two charging pumps -RUNNING Verify AFW Pumps Running Check MD pumps -RUNNING Check turbine -driven pump -RUNNING, IF NECESSARY Verify FW Isolation Check SG feed regulating valves CLOSED Check SG feed regulating bypass valves CLOSED Check FW isolation trip valves -CLOSED Check TD FW pump -TRIPPED Check MD FW pumps -STOPPED Check SG blowdown isolation valves CLOSED Check SG blowdown sample isolation valves -CLOSED Check SG chemical feed isolation valves CLOSED Standard E-O, Step 8 E-O, Step 8.a E-O, Step 8.b E-O, Step 9 BOP Align component(s) as necessary for minimum E-O, Step 9 Page 38 of 74 SF ,)N Lesson Title: Faulted, Ruptured Steam Generator 10 Number: 2K11 NRC-02 Revision:

Q Task Time IDA/Malf Instructor Information/Activity__

_ Assign EVENT 6: Main Steam line Isolation fails to automatically actuate. [*] Critical Task -The BOP needs to BOP initiate a manual MSI from main board 5. BOP CTMT pressure will ultimately reach RO the CDA setpoint.

Expected Action safety function.

Check If Main Steam Lines Should Be Isolated Check Ctmt pressure GREATER THAN 18 psia OR Any SG pressure LESS THAN 660 psig OR Annunciator "MAIN STEAMLINE ISOLATION" (MB2B 5-7) -LIT Verify MSIVs and MSIV bypass valves CLOSED Initiate MSI. Check ESF Group 3 lights -LIT. Check if CDA Required Check Ctmt pressure is GREATER THAN 23 psi a Standard RNO Step Step E-O, Step 10.b E-O, Step 10.b, RNO [*] E-O, Step 10.c E-O, Step 11 E-O, Step 11.a Page 39 of 74 SF 8N 4 Lesson Title: Faulted, Ruptured Steam Generator 10 Number: 2K11 NRC-02 Task Time IDA/Malf Instructor Information/Activity.

A.!i!iign BOP RO RO RO RO RO Revision:

Q Expected Standard OR Annunciator "CONTAINMENT DEPRES ACTUATION" (MB2B 5-5) -LIT Proceed to Step E-O, Step11,a, RNO Verify CAR Fans Operating In Emergency E-O, Mode Step 12 Check CAR fan E-O, Step 12.a CAR fans A and B -RUNNING *

• CAR fan C -STOPPED START/STOP CAR fans as E-O, Step 12.a, RNO Verify RPCCW etmt supply and return header E-O, isolations

-OPEN Step 12.b Verify Train A and B RPCCW supply and E-O, return to chill water valves -OPEN Step 12.c Verify E-O, Step 13 Check ESF Group 2 status columns 2 through E-O, 10 -LIT Step 13.a Verify Proper ESF Status Panel E-O, Page 40 of 74 SE Lesson Title: Faulted, Ruptured Steam Generator 10 Number: 2K11 Revision:

Q Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard Step 14 Verify ESF Group 1 lights -OFF

• The RO should position Verify ESF Group 2 lights -LIT

• components as necessary.

CTMT will be Adverse on RO Determine If ADVERSE CTMT Conditions E-O, temperature.

Exist Step 15 Ctmt temperature GREATER THAN 180°F

• OR Ctmt radiation GREATER THAN 10 5 R/hr* RO Verify ECCS E-O, Step 16 Check PZR pressure -GREATER THAN E-O, 1900 psia Step 16.a Proceed to step E-O, Step 16.a RNO Check PORV block valves -E-O, Step 16.b Proceed to step E-O, Step 16.c Check charging pumps -E-O, Step 16.d FLOW INDICATED RO START pumps and Align valves. E-O, Step 16.d, Page 41 of 74 Sf 'ON 4 Lesson Title: Faulted, Ruptured Steam Generator 10 Number: 2K11 NRC-02 Revision:

Q Task Time IDA/Malt Instructor Information/Activity Assign Expected Action Check RCS pressure -GREATER THAN 1650 psia (1950 psia ADVERSE CTMT) Proceed to Step 17 Check SI pumps -FLOW INDICATED START pumps and Align valves. Check RCS pressure -LESS THAN 300 psi a (500 psia ADVERSE CTMT) Proceed to step 17. Check RHR pumps -FLOW INDICATED.

START pumps and Align valves. CREW should perform a short brief come out of "Master Silence" at completion of Step Standard Step Step Step E-O, 16.f RNO Step Step Step Step Check NR level in at least one SG E-O, GREATER THAN 8% (42% ADVERSE Step 17.a Page 42 of 74 Sf 'ON 4 Lesson Title: Faulted, Ruptured Steam Generator 10 Number: 2K11 NRC-02 Task Time IDA/Malf Instructor Information/Activity Assign US BOP BOP RO RO RO RO RO Revision:

Q _ _ EXf:)ected Action Proceed to Step Verify Total AFW Flow -GREATER THAN 530 gpm Verify AFW Valve Alignment

-PROPER EMERGENCY ALIGNMENT Verify ECCS Valve Alignment

-PROPER EMERGENCY ALIGNMENT Check if CBI is required Check CONTROL BUILDING ISOLATION annunciator (MB4D 3-6) -LIT Check if CBI is required Ctmt pressure GREATER THAN 18 psia OR Control Building radiation monitor in alarm OR SI manually actuated Standard Step Step Step Step Step Step Step Page 43 of 74 Sf ON4 Lesson Title: Faulted, Ruptured Steam Generator 10 Number: 2K11 Revision:

Q. Time IDA/Malf Instructor Information/Activity_ _ _ _

Expected IF CBI required, THEN Initiate CBI. IE CBI is NOT required, THEN Proceed to Step 20.g. Check Train A Control Building filter fan (3HVC*FN1A)

-RUNNING Check recirc damper for the running Control Building filter fan (3HVC*AOD119A or B) -OPEN Verify ESF Group 2 CBI lights -LIT Align HVAC components as necessary for minimum safety function. Verify control building purge supply fan and purge exhaust fan -NOT RUNNING Place kitchen exhaust fan in OFF T =When BOOTH When asked, REPORT that "all SlCRS US Verify SLCRS doors -CLOSED called as doors indicate closed." Standard E-O, Step 20.b E-O, Step 20.c E-O, Step 20.d E-O, Step 20.d, RNO E-O, Step 20.e E-O, Step 20J E-O, Step 20.g Page 44 of 74 SE )N 4 Lesson Title: Faulted, Ruptured Steam Generator 10 Number: 2K11 NRC-02 Task Time IDA/Malf Instructor

___

SSS T=When BOOTH When called, WAIT 3 -5 min, Then PEO called as REPORT "Control Building pressure PEO boundary doors are Closed and Dogged or verified closed as directed." Event 8: Hot, dry '8' SG results in a SGTR. Faulted, ruptured SG. T = "B" SG SG01B, At 10% WR level, the 'B' SG will be RO WR level sev=1000 hot and dry. Malfunction insertion reaches 10% gpm will rupture the 'B' SG. Trigger 11 BOP Revision:

Q Expected Standard Perform the E-O, Step 20.h CLOSE and DOG the following Control Building pressure boundary doors. CB west 47'6" (C-47-1A) CB east 64' 6" (C-64-1B)

Verify the following Control Building pressure boundary doors -CLOSED CB west 47'6" (C-47-1) CB north 64'6" chiller room door CB north 64'6" chiller room door CB east 49'6" (C-49-1) Check RCS E-O, Step 21 Using GA-26, Dump steam as necessary to E-O, Page 45 of 74 SION4 Lesson Title: Faulted, Ruptured Steam Generator 10 Number: 2K11 NRC-02 Task Time IDA/Malf Instructor Information/Activity_

Assign RCS cold leg WR temperature will be BOP less than 550°F BOP BOP BOP Yes, breaker 34A1-2 will be closed. Revision:

Q. Expected Action control RCS cold leg WR temperature BETWEEN 550°F AND 560°F Verify ReS cold leg WR temperature GREATER THAN 550°F Proceed to step 21.d. , Maintain total feed flow BETWEEN 530 and 600 gpm until NR level is GREATER THAN 8% (42% ADVERSE CTMT) in at least one SG CLOSE SG atmospheric relief and relief bypass valves Check the following valves -CLOSED

• MSIVs

• MSIV bypass valves Check Power To SBO Diesel Auxiliaries Verify any SBO bus tie breaker -CLOSED TO AN ENERGIZED BUS

• Bus 34A: 34A 1-2

• Bus 34B: 34B1-2

• Bus 24E: A505 (Unit 2) Standard Step 21.a E-O, Step 21.b E-O, Step 21.b RNO E-O, Step 21.d E-O, Step 21.e E-O, Step 21.f E-O, Step 22 E-O, Step 22.a Page 46 of 74 S' 'ION Lesson Title: Faulted, Ruptured Steam Generator 10 Number: 2K11 NRC-02 Time IDA/Malf Instructor Information/Activity Revision:

Q Task Assign Expected Action Standard RO Check PZR Valves E-O, Step 23 Verify PORVs -CLOSED E-O, Step 23.a RO Verify normal PZR spray valves -CLOSED E-O, Step 23.b RO Verify PORV block valves -AT LEAST E-O, ONE ENERGIZED VALVE OPEN Step 23.c RO Verify PZR safety valves -CLOSED E-O, Step 23.d CREW To prevent seal damage, seal injection flow E-O, should be maintained to all RCPs. Step 24, CAUTION RO Check If RCPs Should Be Stopped E-O, Step 24 Verify RCPs -ANY RUNNING E-O, Step 24.a RO Verify RCS pressure -LESS THAN 1500 psia E-O, (1800 psi a ADVERSE CTMT) Step 24.b US Proceed to Step 25 E-O, Step 24.b, RNO RO Verify either of the following:

E-O, Charging pumps AT LEAST ONE* Step 24.c RUNNING AND AT LEAST ONE Page 47 of 74 Sf ON4 Lesson Title: Faulted, Ruptured Steam Generator ID Number: 2K11 NRC-02 Task Time IDA/Malf Instructor Information/Activity Assign RCS pressure will eventually lower to < 1500 psia. Crew should identify this and trip all RCPs. RO BOP RO The 'B' SG will be depressurized.

US The US should announce and make the transition to E-2. Revision:

Q Expected Action COLD LEG INJECTION VALVE OPEN OR SI pumps -AT LEAST STOP all RCPs Check If SG Secondary Boundaries Are Intact Check pressure in all SGs NO SG PRESSURE DECREASING IN AN UNCONTROLLED MANNER NO SG Initiate monitoring of CSF Status Trees and Go to E-2, Faulted Steam Generator Isolation.

Standard Step Step Step Step Page 48 of 74 SE JN4 Lesson Title: Faulted, Ruptured Steam Generator ID Number: 2K11 NRC-02 Revision:

Q Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard E-2, Faulted Steam Generator US At least one SG must be maintained available E-2 Isolation, Rev. 011 for RCS cooldown.

CAUTION Any faulted SG or secondary break should remain isolated during subsequent recovery actions unless needed for RCS cooldown or sampling is required. If RWST level decreases to LESS THAN 520,000 gal, Go to ES-1.3, Transfer to Cold Leg Recirculation, to align the ECCS system. Check Main Steam Isolation And Bypass E-2, Step 1 Valves -CLOSED US US Check at least one SG boundary intact. E-2, step 2 ROt Check pressures in all SGs -AT LEAST ONE E-2, step BOP STABLE OR INCREASING 2.a US Identify Faulted SGS E-2, Step 3 The 'B' SG will be depressurized.

ROt Check pressure in all SGs E-2, Step BOP 3.a ANY SG PRESS DECREASING IN AN UNCONTROLLED MANNER OR ANY SG COMPLETELY DEPRESSURIZED , If the TD AFW pump is the only available E-2, Step 4 source of feed flow, a steam supply to the TD CAUTION AFW pump must be maintained from at least one steam generator Page 49 of 74 SE' 'IN Lesson Title: Faulted, Ruptured Steam Generator 10 Number: 2K11 NRC-02 Revision:

Q Task Time IDA/Malf Instructor Information/Activity_

Assign Expected Action Standard [*] [Critical Task] Isolate the ROJ Isolate each faulted SG. E-2, step 4 faulted S/G before transition out BOP Isolate main feed line [*]of E*2 ROJ TRIP TO FW pumps BOP Place MD FW pump in PULL-TO-LOCK Isolate AFW flow path CLOSE steam supply isolation valve to TDAFW pump Verify SG atmospheric relief and bypass valves -CLOSED Verify SG blowdown isolation valve CLOSED Verify SG blowdown sample isolation valve -CLOSED Verify SG chemical feed isolation valve CLOSED Using table, Verify main steam line drains upstream of MSIVs and TO AFW pump -CLOSED Page 50 of 74 i SE IN 4 Lesson Title: Faulted, Ruptured Steam Generator 10 Number: 2K11 NRC-02 Task Time IDA/Malf Instructor Information/Activity _ _ _

SGA 3DTM* AOV29A 3DTM*AOV61A 30TM*AOV63A 3DTM* AOV64A US BOP PEO Revision: .Q Expected Standard SG SG C SGD 3DTM*AOV29B 3DTM*AOV29C 30TM*AOV29D 3DTM*AOV61 B 3DTM*AOV61C 30TM*AOV61D 3DTM* AOV63B 3DTM* AOV63D 3DTM* AOV64B 3DTM*AOV64D Main steam safety valve flow indication E-2, step 5 (derived from differential temperature CAUTION switches) may erroneously indicate flow if the common drain header is warmed by previous steam releases.

Flow indication should be verified by local observation and other plant response indications.

Check SG Code Safety Valves Closed E-2, step 5 Flow switches (MB5) -NOT LIT Locally observation of safety valves (MSVB Roof) -NO STEAM OBSERVED Check AFW Suction Source E-2, step 6 Check OWST level-LESS THAN 80,000 gal E-2, step 6.a Proceed to step 7 and, IF DWST level E-2, step decreases to LESS THAN 80,000 6.a RNO Page 51 of 74 SE" lN 4 Lesson Title: Faulted, Ruptured Steam Generator ID Number: 2K11 NRC-02 Time IDA/Malf Instructor Information/Activity NO: '8' SG is ruptured The rupture will not show on the rad monitor, since it occurred post trip. BOOTH Verify 'B' SG WR level is rising. It takes approximately 4 -5 minutes after the SGTR for wide range level to start rising. The crew may also identify that '8' SG pressure is slowly increasing.

The US should announce and make Revision:

Q Task Assign Expected Action Standard THEN Perform step 6.b Check If SG Tubes Are Intact E-2, step 7 Align all SGs for activity samples: E-2, step 7.a RESET SG blowdown sample isolation OPEN SG blowdown sample Request Chemistry provide samples using HP Check steam generator levels -NO SG E-2, step LEVEL INCREASING IN AN 7.b UNCONTROLLED MANNER Verify trend history and alarm status of E-2, step radiation monitors:

7.c Main steam line -NORMAL Condenser air ejector -NORMAL SG blowdown -NORMAL Go to E-3, Steam Generator Tube Rupture. E-2, step Page 52 of 74 Sf ON4 Lesson Title: Faulted, Ruptured Steam Generator 10 Number: 2K11 NRC-02 Revision:

Q Task Time IDA/Malf Instructor Information/Activity_

Assign Expected Action the transition to E-3. Check If ECCS Flow Should Be Reduced Go to E-1, Loss Of Reactor Or Secondary Coolant Verify RCS subcooling based on core exit TCs -GREATER THAN 32 Q F (115°F ADVERSE CTMT) Verify secondary heat sink Total feed flow to intact SGs -GREATER THAN 530 gpm OR Narrow range level in at least one intact SG -GREATER THAN 8% (42% ADVERSE CTMT) Verify RCS pressure -STABLE OR INCREASING Verify PZR level-GREATER THAN 16% (50% ADVERSE CTMT) Go to ES-1.1, SI Termination E-3, SGTR (rev 022) Actions CREW To prevent seal damage, seal injection flow Standard 7.b RNO E-2, step 8 E-2, step 8 RNO E-2, step 8.a E-2, step 8.b E-2, step 8.c E-2, step 8.d E-2, step 8.e E-3 Step 1 Page 53 of 74 SEr',)N 4 Lesson Title: Faulted, Ruptured Steam Generator ID Number: 2K11 NRC-02 Revision:

Q Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard should be maintained to all CAUTION Foldout page must be open E-3, Step 1,

• The RCP trip criteria is only applicable NOTE until a controlled cooldown is initiated in step 6, RO Check If RCPs Should Be E-3, Step 1 Check RCP's -ANY E-3, Step 1.a Verify RCS pressure -LESS THAN 1500 psia E-3, (1800 psia ADVERSE CTMT) Step 1.b E-3, Verify either of the following:

Step 1.c Charging pumps -AT LEAST ONE RUNNING AND AT LEAST ONE COLD LEG INJECTION VALVE OPEN OR SI pumps -AT LEAST ONE RUNNING us Proceed to step E-3, Step 1.b, RNO RO STOP all E-3, Step 1.d Page 54 of 74 SE' ,)N 4 Lesson Title: Faulted, Ruptured Steam Generator ID Number: 2K11 NRC-02 Task Time IDA/Malf Instructor Information/Activity Assign CREW CREW BOP Revision:

Q Expected Action Identify Ruptured SGs Unexpected increase in any SG level OR High radiation from any SG steam line as indicated by the trend history or alarm status OR High radiation from any SG sample If the TD AFW pump is the only available source for feed flow, a steam supply to the TO AFW pump must be maintained from at least one SG. At least one SG must be maintained available for RCS Cooldown.

Isolate Flow From Each Ruptured SG Verify each ruptured SG atmospheric relief valve controller

-IN AUTO AT 1125 psig Check each ruptured SG atmospheric relief valve -CLOSED Standard E-3, Step Step E-3, Step E-3, 3.a E-3, Step 3.b Page 55 of 74 Sf ,)N 4 Lesson Title: Faulted, Ruptured Steam Generator ID Number: 2K11 NRC-02 Revision:

Q Task Time IOA/Malf Instructor Information/Activit)' _ _ _

BOP BOP RO RO RO BOP SGA 3DTM* AOV29A 3DTM*AOV61A 30TM*AOV63A 3DTM* AOV64A SG B 3DTM* AOV29B 3DTM* AOV61 B 3DTM"'AOV63B 3DTM*AOV64B BOP Expected Action Check each ruptured SG atmospheric relief bypass valve -CLOSED. CLOSE each ruptured SG steam supply isolation valve to TD AFW pump.

• 3MSS*MOV17 A

• 3MSS*MOV17B

• 3MSS"'MOV17D Verify each ruptured SG blowdown isolation valve -CLOSED CLOSE each ruptured SG blowdown sample isolation valve Verify each ruptured SG chemical feed isolation valve -CLOSED Using table, CLOSE the main steam line drains upstreams of MSIVs and TO AFW . -.. --SBC SBO 3DTM*AOV29C 3DTM'" AOV29D 3DTM"'AOV61 C 3DTM* AOV61 D 3DTM* AOV63D 3DTM* AOV64 0 CLOSE each ruptured SG MSIV and MSIV bypass valve Standard E-3, Step 3.c E-3, Step 3.d E-3, Step 3.e E-3, Step 3.f E-3, Step 3.g E-3, Step 3.h E-3, Step 3.i Page 56 of 74 Sf: :)N 4 Lesson Title: Faulted, Ruptured Steam Generator 10 Number: 2K11 NRC-02 Revision: .Q Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard This caution applies. Feed flow CREW If any ruptured SG is faulted, feed flow to that E-3, should remain isolated to the "B" SG should remain isolated during subsequent Step 4, SG. The other SGs are available for recovery actions unless the SG is needed for CAUTION cooldown.

RCS cooldown.

Check Ruptured SG E-3, step 4 Level will not be > 67% WR or > 8% RO Verify one of the following is satisfied: NR. However, feed flow to the 'B' SG Step Ruptured SG WR level -GREATER THAN should remain isolated.

67% (95% ADVERSE CTMT) OR Ruptured SG NR level-GREATER THAN 8% (42% ADVERSE CTMT) BOP Stop feed flow to ruptured E-3, Step 4.b Major steam flow paths from the ruptured E-3, SG(s} must be isolated prior to RCS Step 5, cooldown.

Major flowpaths include the main CAUTION steam line, TO AFW pump steam supply, and SG atmospheric relief and bypass lines. 'B' SG pressure will NOT be greater BOP Check Ruptured SGs Pressure -GREATER E-3, Step 5 than 530 psig. THAN 530 psig The US should announce and make the US Go to ECA -3.1, SGTR With Loss of Reactor E-3, Step 5 transition to ECA*3.1. Coolant -Subcooled Recovery Desired. RNO ECA-3.1 (rev 019*02) Actions Page 57 of 74 SE Lesson Title: Faulted, Ruptured Steam Generator ID Number: 2K11 NRC-02 Time IDA/Malf Instructor Information/Activity_

Revision:

Q Task Assign Expected Action Standard After SI reset, manual operator action is ECA-3.1 required to: Step 1, Caution Open the charging pump cold leg injection valves when RCS pressure decreases to less than 1900 psia. Restart safeguards equipment If offsite power is lost. CREW Foldout page must be ECA-3.1 Step 1, Note RESET ESF Actuation Signals, If ECA-3.1 Step 1 RO RESET ECA-3.1 Step 1a RESET the ECA-3.1 Step 1b

• CDA

• LOP

• CIA

• CIS Establish Instrument Air to ECA-3.1 Step 2 Check instrument air compressors

-AT ECA-3.1 Page 58 of 74 S -ION 4 Lesson Title: Faulted, Ruptured Steam Generator 10 Number: 2K11 Revision:

Q Task Time IDA/Malf Instructor Information/Activity Assign T =4 minutes EDR18 (Will reenergize 32.3T) after being EDR44 Then report as PEO that 32 3T is dispatched energized lAW GA*1, with the TRIGGER 12 exception of arming the lift pumps. Expected Action LEAST ONE START one instrument air OPEN instrument air Ctmt isolation Check Electrical Alignment Verify AC emergency busses -ENERGIZED BY OFFSITE POWER Proceed to step 3.g. Perform the following to energize MCC 32-3T: Check emergency bus 34C Using GA-1, Energize MCC 32-3T Verify busses 34A and 34B -BOTH ENERGIZED BY OFFSITE POWER Proceed to step 3.1. Check RCPs -ANY RUNNING Standard Step 2.a ECA-3.1 Step 2.a, RNO ECA-3.1 Step 2.b ECA-3.1 Step 3 ECA-3.1 Step 3.a ECA-3.1 Step 3.b ECA-3.1 Step 3.g ECA-3.1 Step 3.h ECA-3.1 Step 3.i ECA-3.1 Page 59 of 74 SE ,)N 4 Lesson Title: Faulted, Ruptured Steam Generator ID Number: 2K11 NRC-02 Time IDA/Malf Instructor InformationfActivity T =4 minutes RCR 23*26 (Selects COLD for RCPs) after being Then report as PEO that the eight dispatched RCP overcurrent trip switches are in the TRIGGER 13 COLD position.

T =When BOOTH REPORT as ADTS to use 22% as the Called level that covers PZR Heaters. Yes, quench spray pumps will be running. Revision:

Q Task Assign Expected Action Locally, Place the eight RCP overcurrent trip switches (43PP and 43PB) in the COLD position using CO Key Locker key #7. Deenergize PZR Heaters Turn OFF all Pzr heaters Consult ADTS for a recommended minimum indicated PZR water level to ensure heaters are covered Check If Containment Spray Should Be Stopped Verify quench spray pumps -RUNNING Verify Ctmt pressure -LESS THAN 17.5 psia Proceed to CAUTION prior to step 5 and WHEN Ctmt pressure is LESS THAN 17.5 psia, THEN Return to step 4.c. Using GA-8, Stop Ctmt spray Standard Step Step Step 4 ECA-3.1 Step 4.a ECA-3.1 Step 4.b ECA-3.1 Step 5 ECA-3.1 Step 5.a ECA-3.1 Step 5.b ECA-3.1 Step 5.b, RNO ECA-3.1 Examiner Inform the US that an extra RO will Page 60 of 74 sr ION Lesson Title: Faulted, Ruptured Steam Generator 10 Number: 2K11 NRC-02 Revision:

Q Task Time IDA/Malf Instructor

__ .. Assign Expected Action perform GA-S. If any ruptured SG is faulted, feed flow to that SG should remain isolated during subsequent recovery actions unless the SG is needed for RCS cooldown.

Since the 'B' SG is faulted, feed flow Check Ruptured SG Level should remain isolated, per the CAUTION. Verify one of the following is satisfied: Ruptured SG WR level -GREATER THAN 67% (95% ADVERSE CTMT) OR Ruptured SG NR level -GREATER THAN 8% (42% ADVERSE CTMT) Perform the following: Maintain feed flow to the ruptured SGs. Proceed to CAUTION prior to step 6 and, WHEN WR level is GRATER THAN 67% (95% ADVERSE CTMT) Standard Step 5.c ECA-3.1 Step 6 CAUTION ECA-3.1 Step 6 ECA-3.1 Step 6.a ECA-3.1 Step 6.a RNO Page 61 of 74 SE Lesson Title: Faulted, Ruptured Steam Generator 10 Number: 2K11 NRC-02 Revision:

Q Task Time IDA/Malf Instructor Information/Activity Assign Expected Action OR NR level is GREATER THAN 8% (42% ADVERSE CTMT) THEN Stop feed flow to ruptured SG. Stop feed flow to ruptured SGs After SI reset, manual operator action is required to restart the RHR pumps if RCS pressure decreases in an uncontrolled manner to LESS THAN 300 psia (500 psia ADVERSE CTMT). Check If RHR Pumps Should Be Stopped Check RHR Pumps -ANY RUNNING IN SI MODE RCS pressure mayor may not be Check RCS pressure stable, depending on the timing of the RCS pressure -GREATER THAN 300 crew. psia (500 psia ADVERSE CTMT) RCS pressure -STABLE OR INCREASING Proceed to step 8. and, IF conditions for stopping RHR pumps are met, THEN Perform step 7.c. Standard ECA-3.1 Step 6.b ECA-3.1 Step 7 CAUTION ECA-3.1 Step 7 ECA-3.1 Step 7.a ECA-3.1 Step 7.b ECA-3.1 Step 7.b, RNO Page 62 of 74 S -'ON 4 Lesson Title: Faulted, Ruptured Steam Generator 10 Number: 2K11 NRC-02 Time IDA/Malf Instructor Information/Activity _ _ Radiation in the Auxiliary Building and ESF Building will be normal.

Inform the US that the Tech Support Center will carry out ECA-3.1 steps B.b, c and d. Revision: .Q Task Assign Expected Action STOP RHR pumps and Place in AUTO Initiate Evaluation of Plant Status Check Auxiliary Building and ESF Building radiation (radiation monitoring group histogram) Auxiliary Building (AUX) -NORMAL ESF Building (ESF) -NORMAL Request ADTS obtain samples using any means possible ..... Evaluate plant equipment for continued usage capabilities

.... Start additional plant equipment as needed for plant recovery.....

Check If SG Secondary Boundaries Are Intact Check pressures in all SGs NO SG PRESSURE DECREASING IN AN UNCONTROLLED MANNER NO SG COMPLETELY DEPRESSURIZED Standard ECA-3.1 Step 7.c ECA-3.1 Step B ECA-3.1 Step B.a ECA-3.1 Step B.b ECA-3.1 Step B.c ECA-3.1 Step B.d ECA-3.1 Step 9 ECA-3.1 Step 9.a Page 63 of 74 Sf ON4 Lesson Title: Faulted, Ruptured Steam Generator 10 Number: 2K11 NRC-02 Revision:

Q Task Time IDA/Malf Instructor Information/Activity Assign _ __ _ _ Expected Action The 'B' SG should already be Verify each faulted SG NOT required for cooldown is isolated ..... Check Intact SG Levels Verify NR level-GREATER THAN 8% (42% ADVERSE CTMT) Control feed flow to maintain NR level BETWEEN 25% and 50% (42% and 50% ADVERSE CTMT) Shutdown margin must be monitored during RCS cool down using GA---15, Establishing RCS Boron Concentration For Shutdown Margin. Ensure Low Steam line Pressure SI is blocked when pressurizer pressure is LESS THAN 2000 psia. Initiate ReS Cooldown To Cold Shutdown.

Maintain cooldown in RCS cold legs ---AT A MAXIMUM RATE NOT TO EXCEED 80 0F/hr Use RHR System if in service The BOP should use GA-26 to Using GA-26, Dump steam from intact SGs commence the cooldown, using the atmospheric relief bypass valves. Standard ECA-3.1 Step 9.a RNO ECA-3.1 Step 10 ECA-3.1 Step 10.a ECA-3.1 Step 10.b ECA-3.1 Step 11 NOTE ECA-3.1 Step 11 ECA-3.1 Step 11.b ECA-3.1 Step 11.c Page 64 of 74 SP Lesson Title: Faulted, Ruptured Steam Generator ID Number: 2K11 NRC-02 Revision:

Q Task Time IDA/Malf Instructor Information/Activity Assign Depending on the timing of the crew, RWST level mayor may not < 920,000 gal. WR sump level should be in the acceptable leakage region. Expected Action Check If Saturated Recovery Should Be Performed Check RWST level -LESS THAN 920,000 gal Proceed to step 11.d Using Attachment A, Check Ctmt WR sump level -IN UNACCEPTABLE LEAKAGE REGION Proceed to step 12.d Go to ECA -3.2, SGTR With Loss of Reactor Coolant -Saturated Recovery Desired Check ruptured SG NR level -GREATER THAN OR EQUAL TO 87% (68% ADVERSE CTMT) Proceed to step 13 Check ADTS determines

-RECOVERY TO BE COMPLETED USING ECA -3.2, SGTR WITH LOSS OF REACTOR COOLANT SATURATED RECOVERY DESIRED Standard ECA-3.1 Step 12 ECA-3.1 Step 12.a ECA-3.1 Step 12.a RNO ECA-3.1 Step 12.b ECA-3.1 Step 12.b RNO ECA-3.1 Step 12.c ECA-3.1 Step 12.d ECA-3.1 Step 12.d RNO ECA-3.1 Step 12.e Page 65 of 74 srON 4 Lesson Title: Faulted, Ruptured Steam Generator ID Number: 2K11 NRC-02 Revision: .Q Task Time IDA/Malf Instructor Information/Activity.

__ Assign Expected Action Standard Proceed to step 13 ECA-3.1 Step 12.e RNO Go to ECA -3.2, SGTR With Loss of Reactor Coolant -Saturated Recovery Desired Step The scenario may be terminated once the RCS cooldown is shown to be controlled and the US makes the decision to transition ECA-3.2, or remain in ECA-3.1. Page 66 of 74 SECTION Lesson Title: Faulted, Ruptured Steam Generator 10 Number: 2K11 NRC-02 Revision:

Q EVALUATION GUIDE Crew FOLLOW-UP QUESTIONS What is the Emergency Classification for this ALERT* Charlie One, Barrier Failure, What plant condition(s) is(are) of greatest concern for (this event)? What actions did the crew take to directly mitigate (this event)? Which safety function(s}

were challenged or had the greatest potential for challenge?

Describe why. Page 67 of 74 SECTION 4 EXAM GUIDE

SUMMARY

TitlE!: Faulted, Ruptured Steam Generator ID Number: 2K11 Revision: .Q Critical Tasks Note: Critical Tasks are not required for Progress Review Exams. TASK DESCRIPTION TASK # KIA >/= 3.0 BASIS SELECTION Manually trip the reactor from the control room with either Main Board trip switch or by opening 32B and 32N supply breakers before completing step 1 of E-O. E-O --A 029-EA1.08 4.5/4.5 029-EA1.12 4.1/4.0 Failure to manually trip the reactor causes a challenge to the subcriticality CSF beyond that irreparably introduced by the postulated conditions.

Also, it constitutes an "incorrect performance that requires the crew taking compensating action which complicates the event mitigation strategy and demonstrates the inability by the crew to recognize a failure of the automatic actuation of the RPS." Isolate the faulted S/G E-2 --A 040 M1.04 Failure to isolate a faulted before transition out of 4.3/4.3 SG that can be isolated E-2 causes challenges to CSFs beyond those irreparably introduced by the postulated conditions.

Manually actuate Main E-O-P E12-EA1.1 3.8/3.8 Failure to close the MSIVs Steamline isolation or close MSIVs before a severe 039-K4.053.7/3.7 under the postulated plant conditions causes challenges (orange path) challenge to CSFs beyond those develops to either the irreparably introduced by the subcriticality or the integrity postulated conditions.

Such an CSF or before transition to omission constitutes a ECA-2.1! whichever "demonstrated inability by the happens first. crew to recognize a failure of the auto actuation of an ESF system or component and to take an action that would prevent a challenge to plant safety." Cool down the RCS to ECA-3.1 011 EA1 .11 4.2 4.2 Depending upon the plant cold shutdown B 011 EA1 .15 4.2 4.2 conditions, failure to perform conditions at the allowed by procedure (80°F/HR).

but such that a severe (orange path) challenge to the Integrity CSF is not 038 EA1.16 4.4 4.3 038 EA1.27 3.93.9 038 EA1.32 4.64.7 the critical task either causes accelerated depletion of RWST inventory leading to loss of SI and eventual core uncovery or causes increased secondary leakage leading to SG overfill and more radioactive release. Thus, Page 68 of 74 encountered.

038 EA 1.35 3.5 3.6 Note: Used to designate critical tasks. Should also be incorporated into column 3 or 4 of Instructor Guide. failure to perform the critical task leads to a "significant reduction in safety margin beyond that irreparably introduced by the scenario." It also represents a "demonstrated inability by the crew to take an action or combination of actions that would prevent a challenge to plant safety." Page 69 of 74 SIMULATOR TRAINING SHIFT TURNOVER DATE-TIME SHIFT Today Now PLANT STATUS: *RxPower:*.

100% Thermal: 3649 MWTH PZRPressurel 2250 psia Electric:

1284 MWe ReST-AVE:

BrJdegF ReS Leakage: Identified:

0.015 gpm Protected TrainlFacility:

A TRAIN Orange Unidentified:

0.036 gpm PRA: Date/Time:

Toda 0015 Active Tracking Records and Action Statements Equipment/Reason LCO Action Date Time in LCO Action Requirement Time Left 3.8.1.1 b.1, b.2, b.3, b.4, b.S yesterday 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> SR4.8.1.1.1.a due in 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> 13 days 7.4.1 a.1, a.3 yesterday 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> 13 days 00 Compensatory Actions I Temp Logs Watch Open Date Class Reason Reason Position None 'urveillances I Evolutions in Progress Qp 3204 Steady State Operation Reactivity Briefing (see reactivity thumbrules I spread sheet for additional info) Current Rod Height CaD@219 Xenon Trend Stable Current Boron 1046 ppm Shift Orders The "A" EDG is out of service for planned maintenance.

Page 70 of 74 ATTACHMENT VALIDATION Title: Faulted, Ruptured Steam Generator ID Number: 2K11 NRC-02 Revision:

o Initial Conditions:

The initial condition(s) contained in the guide are certified or have been developed from certified ICs. Verified By: (Initials)

Test Run: The scenario contained in the guide has been test run in part or whole on the simulator.

The simulator response is reasonable and as expected.

If a simulator guide revision does not affect original Test Run, then enter N/A. Simulator Operating Limits: The simulator guide has been evaluated for operating limits and/or anomalous response by reviewing the Simulator Modeling and Anomalous Response List. For Examination Scenario:

The Scenario Attributes Checklist is complete and attached.

This is not required for Progress Review Exams. Actions Complete (SignatureD Page 71 of 74 Appendix 0 Scenario Outline Form ES-D-1 Facility:

Millstone 3 Scenario No.: 2K11 NRC-02 Op-Test No.: 2K11 Examiners:

Operators:

Initial Conditions:

IC-18, 100% Power, Middle of life, Eguilibrium Xe. Turnover:

The Qlant is at 100% Qower and at middle of life. The "A" EDG is out of service for Qlanned maintenance.

Event Malf. Event Event No. No Type* Description 1 RX05D I (RO) Loop 4 Tavg fails high (loop 4 narrow range Thot). (AOP 3571) 2 RX12G I (BOP) 'C' steam generator level channel (controlling) fails low. (AOP 3571) 3 SG03B R(RO) 'B' SG Tube Leak (AOP 3576), and subsequent R (SRO) procedurally required rapid downpower.

(3%/min).

N (BOP) (AOP 3576, AOP 3Ql5) 4 MSO'IB M (ALL) 'B' main steam line break in CTMT. Requires Reactor Trip and Safety Injection.

5 RP10AlB C (RO) Automatic and MB7 manual reactor trip switch fail. RP09B Successful manual rea,ctor trie MB4. 6 RP08A1B C (BOP) Main Steamline Isolation fails to automatically actuate. 7 RP11E C (RO) Several HPSI components fail to respond to a Safety -----s I SG018 M (ALL) Injection signal. Hot, dry 'B' SG results in a SGTR. Faulted, ruptured SG. * (N}ormal,

{I Page 72 of 74 Lesson Title: Faulted, Ruptured Steam Generator ID Number: 2K11 NRC-02 Revision:

Q Assessor:

Dave Minnich QUALITATIVE ATTRIBUTES The initial conditions are realistic, in that some equipment and/or instrumentation may be out service, but it does not cue the crew into expected The scenario consists mostly of related Each event description consists of: the point in the scenario when it is to be initiated the malfunctions(s) that are entered to initiate the event the symptoms/cues that will be visible to the crew the expected operator actions (by shift position) the event termination point (if applicable)

No more than one non-mechanistic failure (e.g., pipe break) is incorporated into the scenario without a credible preceding incident such as a seismic event. The events are valid with regard to physics and Sequencing/timing of events is reasonable, and allows for the examination team to complete evaluation results commensurate with the scenario If time compression techniques are used, scenario summary clearly so indicates.

Operators sufficient time to carry out expected activities without undue time constraints.

Cues are The simulator modeling is not The scenario has been validated.

Pursuant to 10 CFR 55.46(d), any open simulator deficiencies or deviations from the referenced plant have been evaluated to ensure fidelity is maintained while running the planned Every operator will be evaluated using at least one new or significantly modified scenario.

All scenarios have been altered lAW Section 0.5 of All individual operator competencies can be evaluated, as verified using form Each operator will be significantly involved in the minimum number of transients and specified on Form Level of difficulty is appropriate to support licensing decisions for each crew Page 73 of 74 Lesson Title: Faulted. Ruptured Steam Generator ID Number: 2K11 NRC-02 Revision: Note: Following criteria list scenario traits that are numerical (QUANTITATIVE) in nature. 01. Total Malfunctions (TM) -5 to 8 required (1) Loop 4 Tavg failure. (2) 'c' steam generator level channel failure. (3) '8' SG Tube Leak. (4) '8' main steam line break. (5) Automatic reactor trip failure. (6) ESF (MSI) Auto Actuation Failure, (7) ESF (HPSI components)

Auto Actuation Failure, (8) Faulted, ruptured SG. 02. Malfunctions after Eap entry (EM's) -1 to 2 required (1) ESF (MSI) Auto Actuation Failure. (2) ESF (HPSI components)

Auto Actuation Failure. (3) Faulted, ruptured SG. 03. Abnormal Events (AE) -2 to 4 required (1) Loop 4 Tavg failure (AOP 3571), (2) "c' steam generator level channel failure (AOP 3571). (3) 'S' SG Tube Leak (AOP 3576) 04. Major Transients (MT) -1 to 2 required (1) '8' main steam line break, (2) Faulted, ruptured SG 05. EOP's (EU) entered/requiring substantive actions --1 to 2 required (1) E-2. (2) E-3, (3) ECA-3.1 06. Eap Contingencies requiring substantive actions [ECAs/FRs/] (EC) o to 2 required (1) ECA-3.1 07. Critical Tasks (CT) -2 to 3 required E-O --A Manually trip the reactor E-2-A Isolate the faulted S/G before transition out of E-2 E-O --P Manually actuate Main Steamline isolation or close MSIVs ECA 3.1 -B Cool down the RCS 08. Approximate Scenario Run Time: 60 to 90 min. 09. Eap run time: 10. Technical Specifications are exercised during the scenario.

Total 8 Total 3 Total 3 Total-=2_

Total--=::,.3_

Total ----:..1_ Total _____4_ Total 75 min Total 35 min (Y/N)_Y_ Page 74 of 74 MILLSTONE POWER SIMULATOR EXAM GUIDE APPROVAL Exam Title: Large Break LOCA Revision:

o 10 Number: 2K11 NRC-04 This document is the property of the Millstone Power Station which controls its distribution.

Further transfer, copying, or modification of this document is strictly prohibited without the written consent of the Millstone Power Station . Submitted O. Minnich .1/2,1/11 Developer Date' Validated by: Approved by: Training Supervisor STOI> THINK ACT REVIEW

SUMMARY

OF Change Description Date of Change SlOP TI1INK ACT REVIEW SECTION SIMULATOR EXAM TABLE OF SECTIONS LISTED IN ORDER 1 . Cover Page 2. Table of Contents 3. Exercise/Exam Overview 4. Exam Guide Attachments:

Shift Turnover Validation Scenario Outline Attributes Summary of Page 3 of 59 SECTION EXAM Title: Large Break LOCA ID Number: 2K11 NRC-04 Revision:

Q 1. The crew will take the shift with reactor power stable, low in the power range (reactor power 7%), following a reactor startup by the previous shift. This is the initial plant startup from a refueling outage. OP 3203, Plant Startup, is in progress and complete up through step 4.3.7, Main Turbine shell warming. The crew is to raise reactor power from 7% to 15 to 19% in accordance with step 4.3.9. The US should facilitate a brief of the evolution prior to taking the shift. The MP3 simulator briefing room may be used for this purpose. During the power ascension, and when power rises above 11%, the Crew will find that the P-10 'PERMISSIVE STATUS 'annunciator has failed to energize.

The US should refer to Technical Specifications and recognize that 3.0.3 applies, and results in a termination of the startup. The US should contact Plant Management for maintenance assistance and guidance.

While the organization is developing a shutdown plan, the IC, (lead) Service Water pump will trip, and the "A' (follow) Service Water pump will start. The crew should respond by addressing the Annunciator Response Procedure for the service water pump trip. Actions will include reestablishing service water supply flow to the TPCCW system, which isolated on low service water pressure, as well as addressing Technical Requirements.

When actions are complete for the tripped service water pump, Power Range Nuclear Instrument (NI) Channel 42 Lower Detector will fail high and the appropriate annunciators will alarm. Rod control is in manual so no rod motion will occur, but the auctioneered high PRNI channel inputs to the control circuitry for the FRV Bypass valves. The FRV Bypass valve controllers should be placed in manual and the crew should respond using AOP 3571, Instrument Failure Response.

Tech Specs will need to be addressed.

After Tech Specs are addressed, shaft vibration on the 'B' RCP will increase.

The crew should address the RCP vibration alarm using the Main Board 4 Annunciator Response Procedure for Rep B VIBRA TlON HI-HI. The procedure requirements will have the operator transition to AOP 3554, Rep Trip or Removing a Rep from Service At Power, to stop the affected RCP. After the RCP is tripped, a loss of off-site power will occur resulting in a reactor trip. The "AU EDG will fail to start automatically and must be manually started by the BOP from MB8. Additionally, the EDG output breakers fail to auto-close and the BOP must manually close the "A' and "B' EDG output breakers [Critical Task]. At the time of the reactor trip, a small break LOCA on loop 2 occurs (Simulating a total failure of the #2 RCP #1 seal). The crew will carry out the immediate actions of E-O, Reactor Trip and Safety Injection, determine that automatic safety injection (SI) actuation has failed, and manually initiate SI [Critical Task]. In addition, Feedwater Isolation fails to automatically actuate, requiring the BOP to manually position feedwater components.

Page 4 of 59 The crew will execute the actions as specified in E-O, and then transition to E-1, Loss of Reactor or Secondary Coo/ant. While in E-1, the crew will stop the RHR pumps when procedurally directed.

After the crew trips the RHR pumps, the LOCA will rapidly increase in severity forcing the restart of the RHR pumps. As the break size increases an "Orange" Path will be generated based on CTMT pressure.

The crew should respond by transitioning to FR-Z.1, Response to High CTMT Pressure.

CDA Train "A" & "B" will fail to automatically or manually actuate. This will require the crew to manually manipulate individual components

[Critical Task]. Once FR-Z.1 is complete, the crew transitions back to E-1, the session can be terminated. The SRO candidate (US) should classify this event as an ALERT-Charlie One based on failure of the RCS Barrier, BA 1. Duration of Exam: 90 minutes (without a crew startup brief) Page 5 of 59 SECTION 4 EXAM GUIDE Title: Large Break LOCA 10 Number: 2K11 NRC-04 Revision:

Q All Control Room Conduct, Operations and Communications shall be in accordance with 100, Conduct of Operations. "Review the Simulator Operating limits (design limits of plant) and the Simulator Modeling limitations and Anomalous Response list prior to performing this exam scenario on the simulator.

The evaluators should be aware if any of these limitations may be exceeded." (NSEM 6.06) Page 6 of 59 SECTION EXAM Title: Large Break LOCA ID Number: 2K11 Revision:

Q SIMULATOR PROBLEMS DURING EXAMS It is the responsibility of the Instructors in the simulator to insure that training interruptions have a minimum negative impact on the Crew and the training we provide. Use your judgment on whether to stop the training and how the training should be commenced after the problem is corrected.

Be aware that at all times the Operators should treat the simulator as if it were the plant and you too should treat it as much like the plant as possible when they are in the simulator.

As soon as the Instructors are aware of a simulator problem that will adversely affect the training in progress (computer fault, etc.) the Instructor should: Place the simulator in FREEZE if possible. Announce to the Crew that there is a simulator problem. Request that the Crew either standby (for minor trouble that can be handled quickly) or leave the simulator control room. (The Crew should leave the simulator for problems which involve major switch alignments). Deal with the problem (reboot, close tripped breaker, call STSB, etc.) After the Instructors believe the simulator is restored to service, the Crew should be told how training will continue.

If it is possible and felt to be acceptable to the Instructors, training can begin where it left off with an update on plant parameters and each Crew member is prepared to restart. If training will not begin where it left off, the crew should be told how and where training will begin again. Once the Crew has been told how and where training will begin, have the crew conduct a brief so that the Instructor can insure that the crew has all the necessary information to continue with the scenario. Once all Crew members and Instructors are satisfied that they have the necessary information to continue the scenario, place the simulator in RUN and announce to the Crew that you have continued the training session. Page 7 of 59 SEr-'ON 4 Lesson Title: Large Break LOCA 10 Number: 2K11 Revision:

Q INITIAL SeTUP INSTRUCTIONS START the Sun Workstation.

a. IF the Sun Workstation is running THEN go to SIM ACTIVE. PLACE Recorder Power to ON. VERIFY that the current approved training load is loaded. REMOVE the step counter OVERRIDE and allow the counters to step out during the IC reset. RESET to IC 312 (modified ICOS), Load Schedule NRC-04.sch, if needed, Load BASIC.EVT file (boolean triggers) ADJUST the various pot settings to the valued specified by the chart in the simulator booth or Notepad for the selected IC. Pay particular attention to the Pzr spray valves and their setpoints. PLACE Simulator to RUN. If Necessary, RESET the Plant Calorimetric at the Instructor Station PPC by Pressing "SHIFT LEFT" and "F6" simultaneously. ENSURE Simulator fidelity items cleared. a. CHECK the STEP COUNTERS at correct position for plant conditions.

b. PLACE _4_ tiles under the DEMINS IN SERVICE lamacord label on MB6. c. PLACE the Main Turbine on the LOAD LIMITER and ENSURE Standby Load Set MATCHED if conditions require. d. PLACE the Westronic (5) and Gammametrics (2) recorders in active/run by depressing up or down arrow for each. e. For the RIL recorder:

select printer to "ON" when command? appears select "Autojog".

f. CLEAR DCS alarms on MB? and BOP console. g. VERIFY annunciator, "COMPUTER FAILURE" (MB4C, 1-11), is NOT LIT. As needed, RESET Computer Terminals to At Power displays if 100% power IC. RESET Rad Monitor Screen to Status Grid. Page 8 of 59

1'"ION 4 Lesson Title

Large Break LOCA 10 Number: 2K11 NRC-04 Revision:

Q INITIAL SETUP INSTRUCTIONS IF placing equipment OOS, THEN perform the necessary switch manipulations and hang appropriate tags, as required, listed under "Equipment OOS." 13. Ensure that the protected train and environmental placards are appropriately hung. Equipment OOS: NONE Insert applicable Crew Training Tape/CD into the DVONCR. Verify the MONITOR Time Display the same as the digital time display on MB4. If not page/call the Unit Tech. Initial MalfunctionsIiOs/IDAs:

PLACE GREEN PLACARDS FOR ALL INTAKE PARAMETERS ON PLACE THE "A" TRAIN PROTECTED PLACARD ON Page 9 of 59 S' -ION 4 Lesson Title: Large Break LOCA ID Number: 2K11 NRC-04 Revision: .Q INITIAL SETUP INSTRUCTIONS ID Number RP06A RP06B RP07A RP07B NI11 EG13A RP11M RP11L SW01C NI09B RC25B RC25B ED01 Final Relative Delay I Ramp / Event I Severity I Description Time . Time . Trigger Or Value Value Order MALFUNCTIONS

, I'A' Train CDA fails to Auto-Actuate i ! I !I Initial I 'B' Train COA fails to Auto-Actuate Initial ! I 'A' Train Safety Injection fails to Auto-Actuate Initial I 'B' Train Safety Injection fails to Auto-Actuate Initial I P-10 Permissive failure ,Initial I I'A' EDG fails to automatically start I I i I Initial ' A' and 'B' EDG output breakers fail to Auto-Close i Initial Feedwater Isolation fails to automatically actuate i Initial 'C' Service Water Pump trip. I 1 PRNI 42 lower detector fails High 3 'B' RCP shaft 6 9.2 'B' RCP shaft vibration 130 sec I 7 15 mils I Loss of Offsite Power I I I 10 Page 10 of 59 sr 'ION 4 Lesson Title: Large Break LOCA 10 Number: 2K11 NRC-04 Revision:

Q INITIAL SETUP INSTRUCTIONS I 'B' RCP #1 seal leakoff flow 130 150 gpm RC02B I "B" Hot Leg break (Inside CTMT on reactor trip) 13tj 200 Ibm/sec I "B" Hot Leg break (Inside CTMT on reactor trip) 11 7E4 Ibm/sec REMoTE FUNCTIONS I'A' Train SWP Lead/Follow

! 'A'Lead I \2 RXR107 IPS Door I I[4 OPEN RXR35 I OTDT 421C 5 TRIP RXR06 I OTOT 4210 5 TRIP Isec I I RXR107 I PS Door 40 sec I CLOSE OVERRIDES RPOI0004 PB1 COA Actuate Train 'A' NACTUATE RPOI0006 PB3 COA Actuate Train 'B' NACTUATE Lead Refer to the "Briefing Script for the Operational Exam" and brief the crew. Go over the Plant/simulator differences, which follow. Booth Commence recording Simulator session Page 11 of 59 SE"--ION 4 Title: Large Break LOCA 10 Number: 2K11 NRC-04 Revision:

Q INITIAL SETUP INSTRUCTIONS Booth Perform the crew turnover (Initial Conditions page at end of LP) with the SM . Have the SM brief his on plant conditions and any major equipment PLANT/SIMULA TOR DIFFERENCES: Rad Monitor Historical Oata--Simulator Rad Monitor historical data not valid prior to the beginning of this exercise. If not using the speed dial option on the phone system, the operator must dial either #3333 or #3334 to reach the person/department they desire. The following PPC programs do not function on the simulator: Samarium Follow Xenon Follow Sequence of Events Flow indications 3SIH-F1917 (charging ECCS flow), 3SIH-F1918 (A SI pump flow) and 3SIH-F1922 (8 SI pump flow) will show flow at low flow rates. Page 12 of 59 Sf 'ON 4 Lesson Title: Large Break 10 Number: 2K11 NRC-04 Revision: Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard EVENT 1: Power increase to place the Turbine online using OP OP 3203, Plant Startup, is in and complete up through step Main Turbine shell warming. The is to raise reactor power from 7% to to 19% in accordance with step The US should facilitate a brief of evolution prior to taking the OP 3303, Plant Startup (rev 019*11) With the SG bypass level control valves in OP 3203 "AUTO", reactor power should be increased Step 4.3.9 slowly to avoid feed control instabilities.

CAUTION As Main Generator Output increases to OP 3203 approximately 15% (194 MWe), "Power Step 4.3.9 System Stabilizer" PPC Point: EXS-PSSACT, NOTE will change from inactive to active. The reactivity plan specifies control US / RO INCREASE reactor power to between 15% OP 3203 rods be used to raise reactor power. and 19% by one of the following methods Step 4.3.9 while continuing with this procedure: WITHDRAW control rods at a rate not greater than 2 steps/minute DILUTE RCS boron concentration at a rate not greater than 10 to 15 pcm/minute.

Page 13 of 59 Sf ON4 Lesson Title: Large Break 10 Number: 2K11 NRC-04 Revision: Time IDA/Malt Task Instructor Event 2: P-10 Permissive failure results in a termination of the startup and Tech Spec 3.0.3 entry. "REACTOR AT POWER P-10" will NOT be lit. T = US calls OMOC tor guidance.

The US should notify the OMOC and RE that P-10 is not in its required state. The US should halt the startup. BOOTH As OMOC, direct the US to halt the startup and to check Tech Specs for applicability.

The US should enter TIS 3.3.1, Reactor Trip System Instrumentation.

Functional Unit 17.b (RT System Interlock P-10), __

Action If reactor power is allowed to decrease below 9.2% subsequent to blocking the Intermediate and Power Range Reactor Trips, the trips will be reinstated.

WHEN reactor power increases above approximately 11 %, PERFORM the following (MB4): CHECK the following blue "PERMISSIVE STATUS" lights: MB4D 4-3, "REACTOR AT POWER P-10" lit MB4D 5-3, "RX OR TURB NOT AT POWER P-7" not lit Standard OP 3203 Step 4.3.10 CAUTION OP 3203 Step 4.3.10 Page 14 of 59 Sf ON4 Lesson Title: Large Break LOCA ID Number: 2K11 NRC-04 Revision:

Q.. Task Time IDA/Malf Instructor Information/Activity Assign Action Standard Action 8 specifies:

With Jess than the minimum channels OPERABLE, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> determine by observation of the associated permissive annunciator window(s) that the interlock is in its required state for the existing plant condition, or apply Specification 3.0.3.

If the Tavg -Tref Deviation alarm comes in, report that another RO will perform SP 3601 G.3, Tavg Monitoring T = When BOOTH Report as RE to maintain reactor power requested stable using control rods. A reactivity plan is forthcoming.

EVENT 3: 'C' Service Water Pump trip. T= SW01C This will trip the rc' Service Water The crew should respond using ARP 3353. examiner's pump. MB1C 5-3, "SERV WTR PP AUTO TRIP / cue OVERCURRENT" . Trigger 1 ARP 3353.MB1 C 5-3 Actions (rev 005-15) T+4 minutes IF PEa dispatched to breaker cube from being report that the 50GS is flagged and the dispatched.

86E is picked up. The 86E will be reset WHEN the control switch for the pump is taken to the stop position Automatic Function:

Follow Automatic Function:

Follow service water Page 15 of 59 SE" ON Lesson Title: Large Break LOCA 10 Number: 2K11 NRC-04 Time IDA/Malt T+4 minutes BOOTH from request. SWR01 to Trigger 2 'A'Lead Instructor Information/Activity__

water pump starts on low header pressure (26 psig). 3SWP*MOV 71A18 close on low header pressure (25 psig). The 'A' SWP started automatically on low header pressure.

The US should direct the RO to open 3SWP*MOV71A and 3SWP*MOV718.

If PEO is dispatched to swap LEAD/FOLLOW SW Pumps, then perform the following:

after SWR01 is 'A' lead, report A' SW pump is lead, 'C' SW pump is follow" TRM 3.7.4, action 'a' should be entered (14 day action statement).

and TRM 7.4.1, for 'C' SWP, and 3HVR*ACU1A (14 day action statement)

Task }\1;sign RO RO RO RO US/PE o US/SM US/SM Revision:

Q.. Expected Action pump starts on low header pressure.

If annunciator M81C 4-3, "SERVICE WTR PUMP DIS PRES La" is lit, Go To that annunciator's response procedure.

START follow service water pump on the affected train. IF follow service water pump fails to start, Go To AOP 3560, "Loss of Service Water." OPEN "3SWP*MOV71A, SERVICE WATER TRAIN A, A HDR TPCCW SPL Y," and 3SWP*MOV718, "SERVICE WATER TRAIN 8, 8 HDR TPCCW SPL Y." Refer To OP 3328, "Hypochlorite," and SHIFT hypochlorite injection.

Refer To the following and DETERMINE Limiting Condition for Operation.

T/S 3.7.4, "Service Water System," Technical Requirements 3.7.4, "Service Water Pump" TRM 7.4.1 for3HVR*ACU1A118 . REVIEW OP 3326 "Service Water System," for swapping service water pumps. Standard M81C 5-3 Step 1 M81C 5-3 Step 2 M81C 5-3 Step 3 M81C 5-3 Step 4 M81C 5-3 Step 5 M81C 5-3 Step 6 M81C 5-3 Step 7 Page 16 of 59 Sf 'IN 4 Lesson Title: Large Break LOCA 10 Number: 2K11 NRC-04 Revision:

Q.. Task Time IDA/Malf Instructor Information/Activity

____A.!i!iign Expected Action Standard N109B,5 T= Tech MAMP Spec (100%)addressed Trigger 3 Once Tech Specs are addressed, move on to Event 4. Event 4: Power Range Nuclear Instrument (NI) Channel 42 Lower Detector fails high. PRNI 42 lower detector will fail High The US should recognize the entry conditions for AOP 3571 are met and announce entry. AOP 3571 Actions (rev 009-07) All Feed Reg Bypass Valves will go full BOP Determine the Initiating Parameter and open. Place the affected controller in MANUAL The BOP should place all SG level Control Bypass Valve controllers in manual and stabilize steam generator level. Stabilize the Plant Parameters The appropriate attachment for this Perform Corrective Actions Using failure is "0". The US should announce Appropriate Attachment to the crew. 3571 Entry Conditions AOP 3571 Step 1 AOP 3571 Step 2 AOP 3571 Step 3 Instrument Failure Attachment Page 17 of 59 Sf 'ON 4 Lesson Title: Large Break LOCA 10 Number: 2K11 Revision:

Q.. Task Time IDA/Malf Instructor Information/Activity

___ Assign Expected Action Standard Power Range Nuclear Instrument Channel 0 Failure Power Range Nuclear Instrument Channel Failure Failure of two or more channels of PR AOP 3571 instrumentation may prevent P-10 from Attachment resetting when power is reduced below 10%. o Step 1 If P-10 fails to reset, the following automatic CAUTION reactor trip signals are lost: SR HIGH FLUX TRIP (10 5 CPS) IR HIGH FLUX TRIP (25%) PR HIGH FLUX LOW STPT TRIP (25%) The reactor operator must remain alert to any power increases which would necessitate a manual reactor trip. The Gamma Metrics Nuclear Instrumentation System shall be used during the reactor shutdown in lieu of the source range channels.

RO Defeat the failed channel AOP 3571 Attachment o Step 1 At the detector current comparator drawer, AOP 3571 Turn the following switches to the failed Attachment Page 18 of 59 S -ION Lesson Title: Large Break 10 Number: 2K11 NRC-04 Revision: Task Time IDA/Malf Instructor Information/Activity _ _ Expected Action channel: Rod Stop Bypass Upper Section Lower Section Power Mismatch Bypass. At the comparator and rate drawer, Turn the following switch to the failed channel: Comparator Channel Defeat. Defeating the failed channel will remove it from the rod control circuit and may create an artificial primary to secondary power rate of change signal to rod control. Placing rod control in automatic, prior to the signal dissipating, may result in rod motion. There should be no error, since rod RO Restore T AVE

• T REF error to within 1°F and control was in manual Place rod control in automatic.

If the plant calorimetric source is Nl's, the failure of one NI channel will disable the calorimetric program. When conditions have stabilized, observe MB board annunciators and parameters and immediately report any unexpected or unexplained conditions to the Shift Manager. Trip the associated Reactor Protection Standard o Step 1a AOP 3571 Attachment D Step 1b AOP 3571 Attachment o Step 2 NOTE AOP 3571 Attachment o Step 2 AOP 3571 Attachment o Step 3 NOTE AOP 3571 Attachment D Step 3 AOP Page 19 of 59 s* TION Lesson Title: Large Break 10 Number: 2K11 NRC*04 Revision: Task Time IDA/Malf Instructor

_Assign [Tech Specs] LCO 3.3.1 (FU2) 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> action statement to trip bistables.

This is not the case. The channel has failed. The US should proceed to step 4.e. T = after RXR107 Protection Set Door 2 Open Expected Action System bistable(s):

Place a check mark in the box above the appropriate channel that requires tripping on page 6 or 7 of this Attachment.

Refer to Technical Specification

3.3.1. Check

the existing bistable status to ensure a reactor trip will not occur when the failed channel is tripped. If the General Warning lamp is lit on 3RPS*RAKLOGB.

Placing train A SSPS "Multiplexer Test" switch in "A+B" will cause the reactor to trip. The following step will distinguish whether the failure is within SSPS or the Protection channel. If bistable status Iight(s) ( MB4F or MB4G) indicate that a single bistable input has tripped and channel indication is normal. PERFORM the following:

Request the I&C Department trip the Standard Attachment o Step 4 AOP 3571 Attachment o Step 4a AOP D Step AOP o Step 4c AOP 3571 Attachment o Step 4.d CAUTION AOP 3571 Attachment D Step 4.d NOTE AOP 3571 Attachment o Step 4.d AOP 3571 Page 20 of 59 Sf :IN 4 Lesson Title: Large Break LOCA ID Number: 2K11 NRC-04 Time IDA/Malf Instructor Information/Activity brief for tripping of bistables.

Trigger 4 T =after RXR35 OTDT 421 C Bistable door open RXR06 OTDT 4210 Bistable Trigger 5 RXR107 Protection Set Door 2 Closed Revision:

Q.. Assign Expected Action appropriate bistables using Attachment D and Attachment Attachment S. D Step 4e Verify the appropriate bistable status lights AOP 3571 are In. Attachment I D Step 4f Within one hour, Determine by AOP 3571 observation of the associated permissive Attachment annunciator window (s) that the following D Step 5 interlocks are in their required state for the existing plant condition (Tech, Spec. 3.3.1, Action 8): Rx or turbine not at power P-7 (MB4D 5-3) Three loop permissive P-8 (MB4D 3) NIS power range P-9 permissive (MB4D 6-1)

• Reactor at power P-10 (MB4D 4-3). Page 21 of 59 SF Lesson Title: Large Break LOCA 10 Number: Time 2K11 NRC-04 IDAlMalf Instructor Information/Activity Task Assign Expected Action Revision:

Q.. Standard

• The following step for removing the failed PR channel from Program 3R5 restores OPERABILITY to the AFD Monitor Alarm and must be completed within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or SURVEILLANCE REQUIREMENT 4.2.1.1.1.b must be performed.

AOP 3571 Attachment o Step 6 NOTE

• The following step for removing the failed PR channel from Program 3R5 does NOT restore OPERABILITY to the QPTR Alarm Monitor; therefore, TABLE 3.3-1, ACTION 2.c and SURVEILLANCE REQUIREMENTS 4.2.4.1.b and 4.2.4.2 are in effect. US! CREW Perform the following to remove the affected power range input to the AFD and QPTR monitor alarm (Program 3RS): AOP 3571 Attachment o Step 6 Using PPC display "TILT_CHANNEL," 'Press the button that corresponds to the channel to be removed. AOP 3571 Attachment o Step 6a Press "Apply" button to remove channel input. AOP 3571 Attachment o Step 6b Refer to the following Technical Specifications and Perform any required actions: AOP 3571 Attachment o Step 7

• Surveillance Requirement 4.2.1.1.1.b Page 22 of 59 Sf 'ON 4 Lesson Title: Large Break ID Number: 2K11 NRC-04 Revision: Time IDA/Malf Instructor Information/Activity The US should enter T/S 3.3.1, Action 2 EVENT 5: 'B' RCP high shaft vibration requiring an immediate shutdown of the affected RCP T =Bistables RC25B, 9.2 This will cause shaft vibrations for 'B' tripped and mils RCP to increase to just above the T.S. alarm setpoint for HI vibes.(Alarm Addressed setpoint is 15 mils) Trigger 6 NOTE: The malfunctions for the Rep vibrations are additive to the existing vibrations.

Therefore, if current vibrations are 7.0 mils and RC258 is inserted at 8 mils the result will be an indication of 15.0 mils on the RCP. MB4B 4-3, RCP B VIBRATION HI Corrective Actions (rev 004-011). Crew Expected Action

• TABLE 3.3-1, ACTION 2.c

• Surveillance Requirement 4.2.4.1.b

• Surveillance Requirement 4.2.4.2 Request I&C Department perform corrective maintenance on failed instrument.

The crew should respond using ARP OP 3353. MB4B 4-3, "RCP B VIBRATION HIli CHECK reactor coolant pump vibration monitor panel to confirm alarm (MB3R). Standard AOP 3571 Attachment D Step 8 Entry Conditions MB4B 4-3 Step 1 Page 23 of 59 SE ,)N Lesson Title: Large Break LOCA ID Number: 2K11 NRC-04 Revision:

Q. Task Time IDA/Malf Instructor

___

Expected Action Standard Indicated vibration level is higher than IF indicated vibration level is less than alarm MB4B 4-3 the alarm setpoint for shaft. setpoint.

RESET the alarm. Step 2 RCP B VIBRATION HI-HI is not in. IF "RCP B VIBRATION HI-HI" (MB4B 3-3) is MB4B 4-3 lit, Go To MB4B 3-3, "RCP B VIBRATION HI-Step 3 HI." The RCP vibrations should be reported IF RCP B shaft vibration is greater than 15 MB4B 4-3 as STABLE. If necessary cue the crew mils AND increasing greater than 1 mil/hour, Step 4 that the vibrations are NOT increasing PERFORM the following:

as follows: T =If BOOTH Report as Engineering that 'B' Rep required shaft vibrations are stable. Reactor power is NOT greater than US IF reactor power is greater than P-8 (50%), MB4B 4-3 8. PERFORM the following

.... Step 4.1 Refer To AOP 3554, "RCP Trip or Stopping MB4B 4-3 an RCP at Power," and REMOVE RCP B Step 4.2 from service. RCP B frame vibration is LESS THAN 3 RO IF RCP B frame vibration is greater than 3 MB4B 4-3 mils mils AND increasing

..... Step 5 RO/BOP MONITOR RCP B parameters.

MB4B 4-3 Step 6 T =When BOOTH When Contacted, as OMOC, direct US REQUEST Technical Support determine MB4B 4-3 contacted the crew to halt any uppower in necessary action. Step 7 progress and continue to monitor 'B' RCP. The OMOC will make notifications.

US Refer To Technical Specifications, and MB4B 4-3 Page 24 of 59 S[ ON Lesson Title: Large Break LOCA 10 Number: Time 2K11 NRC-04 IDA/Malf Instructor Information/Activity Task Assign Expected Action Revision:

Q.. Standard DETERMINE Limiting Condition for Operation.

Step 8 T=ARP complete Trigger 7 RC25Bto 15 mils This will cause shaft vibrations for 'B' RCP to increase to above the alarm setpoint for HI-HI vibes.(Alarm setpoint is 20 mils) Crew The crew should respond using ARP OP 3353. MB4B 3-3, "RCP B VIBRATION HI-HI" Entry Conditions MB4B 3-3, RCP B VIBRATION Corrective Actions (rev 004-11). An overranged probe may read zero while the other channel reads high. MB4B 3-3 Step 1 CAUTION RO CHECK reactor coolant pump vibration monitor panel to confirm alarm (MB3R). MB4B 3-3 Step 1 Indicated vibration level is higher than the alarm setpoint for shaft. IF indicated vibration level is less than alarm setpoint, RESET the alarm. MB4B 3-3 Step 2 Reactor power is NOT greater than 8. IF reactor power is greater than P-8 (50%), PERFORM the following

.... MB4B 3-3 Step 3 Refer To AOP 3554, "RCP Trip or Stopping an RCP at Power," and REMOVE RCP B from service. MB4B 3-3 Step 4 US The US should recognize the entry conditions for AOP 3554 are met, announce entry and direct the steps to take the 'B' RCP out of 3554 Entry Conditions Page 25 of 59 Sf ON 4 Lesson Title: Larqe Break 10 Number: 2K11 NRC-04 Revision: Task Time IDA/Malt Instructor AOP 3554 ACTIONS (rev 008-01) Yes, all RCPs are running. RO US Yes, the P-8 annunciator is LIT. RO N/A CREW There will be negligible shrink at the current power level. BOP RO Expected Action service. Check RCP Status -ALL PUMPS RUNNING Check Reactor Power Verify THREE LOOP PERMISSIVE P-8 annunciator (MB40 3-3) -LIT. If stopping the RCP due to No.1 seal failure, steps 3 through 5 should be completed as quickly as possible in order to isolate the affected pump No. 1 seal within the recommended 5 minutes. While removing the RCP from service, it is desirable to maintain feedwater flow to the affected steam generator, to ensure that the reactor does not trip on low-low steam generator level from the shrink that will occur. Approximately 0.5 MPPH excess flow is sufficient.

Feedwater flow to the affected steam generator should be stopped once shrink has stopped. Feed Affected Loop SG NR Level to Between 65% and 70% ESTABLISH approximately 0.5 MPPH excess feed flow to raise affected SG level. Defeat Affected Loops Temperature Input Standard AOP 3554 Step 1 AOP 3554 Step 2 AOP 3554 Step 2.a AOP 3554 Step 3 NOTE AOP 3554 Step 3 NOTE AOP 3554 Step 3 AOP 3554 Step 3.a AOP 3554 Page 26 of 59 SF ON Lesson Title: Large Break 10 Number: 2K11 NRC-04 Revision: Task Time IDA/Malf Instructor Information/Activity Assign Loop 2 Loop 2 Loop 1, 3,4 us RO us BOP RO RO RO Expected Action Place loop temperature cutout switch for d T to the affected loop and pull out. Place loop temperature cutout switch for Tavg to the affected loop and pull out. Place OT/OP d T recorder select switch to an unaffected loop. Remove Affected Rep From Service Check RCP status -ALL PUMPS RUNNING. Check the following conditions: Affected SG NR level-GREATER THAN 65%. THREE LOOP PERMISSIVE P-8 annunciator (MB40 3-3) -LIT STOP affected RCP. Verify affected S/G level-STABLE Stop feeding the affected S/G Check RCP 1 and 2 -BOTH RUNNING. Standard Step 4 AOP 3554 Step 4.a AOP 3554 Step 4.b AOP 3554 Step 4.c AOP 3554 Step 5 AOP 3554 Step 5.a AOP 3554 Step 5.b AOP 3554 Step 5.c AOP 3554 Step 5.d AOP 3554 Step 5.e AOP 3554 Step 5.1 Page 27 of 59 SEr-'ON 4 Lesson Title: Large Break LOCA 10 Number: 2K11 NRC-04 Time IDAlMalf Instructor Information/Activity_

RO should take the loop 2 Spray to manual and close Once step 6 of AOP 3554 is reached move on to the next event. The evolution of tripping Bistables has already been conducted for the PRNI channel failure. NO, not a seal failure. EVENT 6: Loss of Offsite Power T = BIS ED01 This will initiate a loss of offsite cannot power causing a reactor trip_ tripped Trigger 10 'A' Emergency Diesel Generator (EDG) fails to automatically start and must be manually started from MB8. BOP must manually close the 'A' and 'B' EDG output breakers.

EVENT 7: Small break LOCA inside CTMT RC02C, NOTE: CV13B Revision: Task Assign Expected Action Standard RO Place affected PZR Spray Controller in AOP 3554 manual and CLOSE spray valve. Step 5.f RNO Check if RCP Seal Leakoff should be AOP 3554 isolated Step 6 Verify Rep -STOPPED AS A RESUL T OF AOP 3554 SEAL FAILURE REQUIRING IMMEDIA TE Step 6.a SHUTDOWN Page 28 of 59 Sf 'ON 4 Lesson Title: Large Break LOCA 10 Number: 2K11 NRC-04 Time IDAIMalf Instructor Information/Activity The failure of the '8' RCP seal T = Reactor package and small break LOCA will Trip initiate upon the reactor trip. US should go to "Master Silence" before ordering reactor trip. E-O (Rev. 026) STEPS Rod bottom lights are out due to loss of power. The crew still meets two of three Revision: Assign Expected Standard RO Crew Foldout page must be open E-O, Step 1, NOTE ADVERSE CTMT defined as GREATER THAN 180°F or GREATER THAN 10 5 R/hr in containment The reactor can be interpreted as "tripped" when any two of three bulleted substeps of Step 1.* are satisfied.

RO Verify Reactor E-O, Step 1 Check reactor trip and bypass breakers -OPEN Check rod bottom lights -LIT Check neutron flux -DECREASING Verify Turbine Trip E-O, Step 2 Page 29 of 59 SFr-ION 4 Lesson Title: Large Break LOCA 10 Number: 2K11 Revision:

Q.. Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard Check all turbine stop valves -E-O, Step 2.a Verify Power to AC Emergency Busses E-O, Step 3 Neither bus is energized.

BOP Check busses 34C and 340 -E-O, Step 3.a BOTH ENERGIZED

[Critical Task] [*] Try to energize the affected buss(es) from E-O, associated EDG. Step 3.8, The BOP must manually start the 'A' RNO [*] EDG from MB8. BOP must manually close the 'A' and 'B' EDG output breakers. LE power can NOT be restored to at least one AC emergency bus, THEN Go to ECA-O.O, Loss of All AC Power, Step 3. (Observe NOTE prior to step 1). Check If Slls Actuated E-O, Step 4 Verify SAFETY INJECTION ACTUATION E-O, annunciator

-(MB4D 1-6 or MB2B 5-9) -LIT Step 4.a EVENT 8: Safety Injection fails

[Critical Task] [*] US Check if SI is E-O, Step 4.a, Crew should identify that 51 did RNa [*]not actuate and it is required.

51 Page 30 of 59 SF 'ON Lesson Title: Large Break LOCA 10 Number: 2K11 NRC-04 Task Time IDA/Malf Instructor Information/Activity

__ ..

should be manually actuated.

RO RO Revision:

Q. _ _ __ _ EXJ:)ected Standard CTMT pressure GREATER THAN 18 PZR pressure LESS THAN 1890 PZR level LESS THAN RCS subcooling LESS THAN

• SG pressure LESS THAN 660 IF SI is Initiate SI and Proceed to step Check Reactor trip and bypass breakers -OPEN Step 4.c Verify Service Water Pumps -AT LEAST E-O, Step 5 ONE PER TRAIN RUNNING START Step Verify Two RPCCW Pumps -ONE PER E-O, Step 6 TRAIN RUNNING Page 31 of 59 SF ION Lesson Title: Large Break LOCA 10 Number: 2K11 Revision:

Q... Task Time IDA/Malf Instructor Information/Activity___

Expected Action Standard RO Verify ECCS Pumps E-O, Step 7 Check SI pumps -RUNNING Check RHR pumps -RUNNING

• Check two charging pumps -RUNNING BOP Verify AFW Pumps Running E-O, Step 8 Check MD pumps -RUNNING E-O, Step 8.a Check turbine -driven pump -RUNNING, IF E-O, NECESSARY Step 8.b EVENT 9: Feedwater isolation fails to BOP Verify FW Isolation E-O, Step 9 Actuate. BOP should identify that FWI did not

• Check SG feed regulating valves actuate and it is required.

FWI CLOSED components should be manually actuated. Check SG feed regulating bypass valves CLOSED Check FW isolation trip valves -CLOSED Check TO FW pump -TRIPPED Check MD FW pumps -STOPPED Check SG blowdown isolation valves Page 32 of 59 Sf ON4 Lesson Title: Large Break LOCA o Number: 2K11 NRC-04 Time IDA/Malf Instructor Information/Activity CTMT pressure will ultimately reach Revision:

Q.. Task Assign Expected Action Standard CLOSED Check SG blowdown sample isolation valves -CLOSED Check SG chemical feed isolation valves CLOSED Align component(s) as necessary for E-O, Step 9 minimum safety function.

RNO Check If Main Steam Lines Should Be E-O, Isolated Step 10 Check Ctmt pressure GREATER THAN 18 E-O, psia Step 10.a OR Any SG pressure LESS THAN 660 psig OR Annunciator "MAIN STEAMLINE (MB2B 5-7) -Verify MSIVs and MSIV bypass valves -CLOSED Step 10.b Check ESF Group 3 lights -UT. E-O, Step 10.c RO Check if CDA Required E-O, Step 11 Check Ctmt pressure is GREATER THAN 23 E-O, Page 33 of 59 S' 'ION Lesson Title: Large Break LOCA ID Number: 2K11 NRC-04 Revision:

Q.. Task Time IDA/Malf Instructor Information/Activit}'

Assign Expected Action Standard the CDA setpoint. Step 11.a OR Annunciator "CONTAINMENT DEPRES ACTUATION" (MB2B 5-5) -LIT US Proceed to Step E-O, Step11,a, RNa Verify CAR Fans Operating In Emergency E-O, Mode Step 12 BOP Check CAR fan E-O, Step 12.a

• CAR fans A and B -RUNNING

• CAR fan C -STOPPED BOP START/STOP CAR fans as E-O, Step 12.a, RNa Verify RPCCW Ctmt supply and return,header E-O, isolations

-OPEN Step 12.b Verify Train A and B RPCCW supply and E-O, return to chill water valves -OPEN Step 12.c RO Verify E-O, Step 13 Check ESF Group 2 status columns 2 through E-O, 10 -LIT Step 13.a Page 34 of 59 Sf 'ON 4 Lesson Title: Large Break LOCA 10 Number: Time 2K11 NRC-04 IDAIMalf Instructor Information/Activity Task Assign Expected Action Revision:

Q.. Standard RO Verify Proper ESF Status Panel Indication E-O, Step 14

• Verify ESF Group 1 lights -OFF

• Verify ESF Group 2 lights -LIT CTMT will not yet be adverse RO Determine If ADVERSE CTMT Conditions Exist E-O, Step 15

• Ctmt temperature GREATER THAN 180°F OR

• Ctmt radiation GREATER THAN 10 5 RO Verify ECCS Flow E-O, Step 16 Check PZR pressure -GREATER THAN 1900 psia E-O, Step 16.a Proceed to step 16,d. E-O, Step 16.a RNO Check PORV block valves -OPEN E-O, Step 16.b Proceed to step 17. E-O, Step 16.c Check charging pumps FLOW INDICATED E-O, Step 16.d Page 35 of 59 S' -ION Lesson Title: Large Break LOCA 10 Number: 2K11 Revision:

Q.. Task Time IDA/Malf Instructor Information/Activity

_Assign E:x:pected Action Standard RO START pumps and Align E-O, Step 1p.d, RNO Check RCS pressure -GREATER THAN E-O, 1650 psia (1950 psi a ADVERSE CTMT) Step 16.e US Proceed to Step E-O, Step 16.e, RNO Check SI pumps -FLOW E-O, Step 16.f START pumps and Align E-O, Step 16.f RNO Check RCS pressure -LESS THAN 300 psia E-O, (500 psia ADVERSE CTMT) Step 16.g Proceed to step E-O, Step 16.g RNO CREW should perform a short brief come out of "Master Silence" at completion of Step BOP Verify Adequate Heat E-O, Step 17 Check NR level in at least one SG -E-O, GREATER THAN 8% (42% ADVERSE Step 17.a CTMT) Proceed to step 17.d. E-O, Page 36 of 59

4 Lesson Title: Large Break 10 Number: 2K11 NRC-04 Revision: Task Time IDAIMalt Instructor Information/Activity Assign Expected Action Verify Total AFW Flow -GREATER THAN 530 gpm BOP Verify AFW Valve Alignment

-PROPER EMERGENCY ALIGNMENT RO Verify ECCS Valve Alignment

-PROPER EMERGENCY ALIGNMENT Check if CBI is required Yes. RO Check CONTROL BUILDING ISOLATION annunciator (MB4D 3-6) -LIT Check Train A Control Building filter fan (3HVC*FN1A) RUNNING Check recirc damper for the running Control Building filter fan (3HVC*AOD119A or B) -OPEN RO Verify ESF Group 2 CBI lights -LIT RO Align HVAC components as necessary for minimum safety function.

BOP Verify control building purge supply fan and purge exhaust fan -NOT RUNNING Standard Step 17.a RNa E-O, Step H.d E-O, Step 18 E-O, Step 19 E-O, Step 20 E-O, Step 20.a E-O, Step 20.b E-O, Step 20.c E-O, Step 20.d E-O, Step 20.d, RNa E-O, Step 20.e Page 37 of 59 SEf'l)N 4 Lesson Title: Large Break LOCA ID Number: 2K11 NRC-04 Time Instructor Information/Activity BOOTH INST When asked, REPORT that "all SLCRS doors indicate closed." T = 4 min BOOTH REPORT "Control Building pressure from being boundary doors are Closed and dispatched Dogged or verified closed as directed." BOP US PEO RO Revision: .Q.. Expected Standard Place kitchen exhaust fan in E-O, Step 20J Verify SLCRS doors -E-O, Step 20.g Perform the E-O, Step 20.h CLOSE and DOG the following Control Building pressure boundary doors. CB west 47'6" (C-47-1A) CB east 64' 6" (C-64-1B)

Verify the following Control Building pressure boundary doors -CLOSED CB west 47'6" (C-47-1) CB north 64'6" chiller room door CB north 64'6" chiller room door CB east 49'6" (C-49-1) Check RCS E-O, Step 21 Verify RCS cold leg WR temperature GREATER THAN 550°F Page 38 of 59 S "ION Lesson Title: Large Break LOCA ID Number: 2K11 NRC-04 Revision:

!L Task Time IOA/Malf Instructor Information/Activity

_ Assign BOP BOP BOP Expected Action Proceed to step 21.c. Maintain total feed flow BETWEEN 530 and 600 gpm until NR level is GREATER THAN 8% (42%1 ADVERSE CTMT) in at least one SG CLOSE SG atmospheric relief and relief bypass valves Check the following valves -CLOSED

• MSIVs

• MSIV bypass valves Check RCS cold leg WR GREATER THAN 550°F Proceed to step 22. and, WHEN RCS temperature GREATER THAN 550°F, THEN Perform step 21.g. Check Power To sao Diesel Auxiliaries Verify any SBO bus tie breaker -CLOSED TO AN ENERGIZED BUS

• Bus 34A: 34A 1-2

• Bus 34B: 34B1-2

• Bus 24E: A505 (Unit 2) Standard E-O, Step 21.c E-O, Step 21.d E-O, Step 21.e E-O, Step 21.f E-O, Step 21.f RNO E-O, Step 22 E-O, Step 22.a Page 39 of 59 Sf 'ON 4 Lesson Title: Large Break 10 Number: 2K11 NRC-04 Revision: Task Time IDA/Malf Instructor

_

__

Action T =step 22.a Examiner "The extra licensed operator will RNO carry out GA-27." reached RO RO RO RO CREW RO RO us IE busses 34A AND 34B are NOT energized, THEN Using GA-27, Establish power to SBO diesel auxiliaries.

Check PZR Valves Verify PORVs -CLOSED Verify normal PZR spray valves -CLOSED Verify PORV block valves -AT LEAST ONE ENERGIZED VALVE OPEN Verify PZR safety valves -CLOSED To prevent seal damage, seal injection flow should be maintained to all RCPs. Check If RCPs Should Be Stopped Verify RCPs -ANY RUNNING Verify RCS pressure -LESS THAN 1500 psia (1800 psia ADVERSE CTMT) Proceed to Step 25 Standard E-O, Step 22.a RNO E-O, Step 23 E-O, Step 23.a E-O, Step 23.b E-O, Step 23.c E-O, Step 23.d E-O, Step 24, CAUTION E-O, Step 24 E-O, Step 24.a E-O, Step 24.b E-O, Step 24.b, RNO Page 40 of 59 SE' '()N Lesson Title: Large Break LOCA 10 Number: 2K11 Task Time IDA/Malf Instructor Information/Activity Assign RO RO BOP RO Revision:

Q.. Expected Action Verify either of the following: Charging pumps -AT LEAST ONE RUNNING AND AT LEAST ONE COLD LEG INJECTION VALVE OPEN OR SI pumps -AT LEAST STOP all RCPs Check If SG Secondary Boundaries Are Intact Check pressure in all SGs NO SG PRESSURE DECREASING IN AN UNCONTROLLED MANNER NO SG COMPLETEL Check If SG Tubes Are Intact Sample all SGs for activity Standard Step 24.c Step [*] E-O, Step 25 Step 25.a Step E-O, Step 26.a Page 41 of 59 Sf 'ON 4 Lesson Title: Large Break LOCA ID Number: 2K11 NRC-04 Time IDA/Malf Instructor Information/Activity_ Acknowledge the request to perform the SIG samples. Ensure crew request activity samples with HP coverage NOTE: The BOP/Crew may observe level going up in the 'B' SG more rapidly than the other SGs. This is due to tripping of the 'B' RCP due to high vibrations, NOT a rupture in the 'B' SG. Task _ . Assign BOP RO Revision:

Q.. Expected Standard RESET SG blowdown sample isolation OPEN SG blowdown sample isolation valve(s) Request Chemistry obtain activity samples using HP coverage Check steam generator levels -NO SG E-O, LEVEL INCREASING IN AN Step 26.b UNCONTROLLED MANNER Verify trend history and alarm status of E-O, radiation monitors Step 26.c Main steam line -NORMAL Condenser air ejector -NORMAL SG blowdown -NORMAL Check If RCS Is Intact E-O, Step 27 Verify Ctmt radiation 3CMS*RE22 (pre-trip)

-Verify Ctmt radiation using monitoring group histogram (CTMT) Page 42 of 59 sr 'ON Lesson Title: Large Break 10 Number: 2K11 NRC-04 Revision: Time IDA/Malf Instructor Information/Activity CTMT pressure will not be normal. The crew should conduct a short transition brief and transition to E-1. E-1 (rev 024) Actions Note The US should remind the operators to review their Foldout Page Books RCP's should have been stopped in E-O. US RO US US RO US US Expected Action Verify Ctmt pressure -NORMAL Verify Ctmt recirculation sump level NORMAL Initiate monitoring of CSF Status TreeSj and Go to E-1, Loss of Reactor or Secondary Coolant. To prevent seal damage, seal injection should be maintained to all Note: Foldout page must be open. Check If RCPs Should Be Stopped Verify RCP's -ANY RUNNING Proceed to step 2 Check If SG Secondary Boundaries Are Intact Check pressures in all SGs. NO SG PRESSURE DECREASING IN AN UNCONTROLLED MANNER Standard E-O, Step 26 RNO E-1, Step 1 CAUTION E-1. Step 1 NOTE E-1. Step 1 E-1 Step 1a E-1 Step 1a RNO E-1, Step 2 E-1, Step 2.a Page 43 of 59 SEf",)N 4 Lesson Title: Large Break ID Number: 2K11 NRC-04 Revision: Task Time IDA/Malf Instructor Information/Activity_

Assi91l us SOP SOP us RO RO Expected Action NO SG COMPLETELY DEPRESSURIZED Check Intact SG Levels Verify NR level-GREATER THAN 8% (42% ADVERSE CTMT) Control feed flow to maintain NR level between 8% and 50% (42% and 50% ADVERSE CTMT) Check Secondary Radiation Sample all SGs for

1) RESET SG blowdown sample

2) OPEN SG Slowdown sample valve(s) 3) Request Chemistry obtain activity samples using HP coverage Verify trend history and alarm status of radiation monitors Main steam line -NORMAL Condenser air ejector -NORMAL SG blowdown -NORMAL Standard E-1, Step 3 E-1, Step 3.a E-1, Step 3.b E-1, Step 4 E-1, Step 4.a E-1, Step 4.b Page 44 of 59 Sf 'IN 4 Lesson Title: Large Break LOCA ID Number: 2K11 NRC-04 Time IDA/Malt Instructor Information/Activity Subcooling should be <32°F and/or PZR level < 16%. Revision: Task Assign Expected Action Standard CRE W If any PZR PORV opens because of high PZR pressure, step 5.a should be repeated after pressure decreases to LESS THAN 2350 psia. E-1, Step 5 CAUTION US Check PZR PORVs and Block Valves E-1, Step 5 RO Verify PORVs -CLOSED E-1, Step 5.a RO Verify block valves -AT LEAST ONE OPEN E-1, Step 5.b US Check It ECCS Flow Should Be Reduced E-1, Step 6 RO Verify RCS subcooling based on core exit TCs -GREATER THAN 32°F (115°F ADVERSE CTMT) E-1, Step 6.a BOP Verify secondary heat sink E-1 Step 6.b

• Total feed flow to intact SGs -GREATER THAN 530 gpm OR

• Narrow range level in at least one intact SG -GREATER THAN 8% (42% ADVERSE CTMT) RO Verify RCS pressure -STABLE OR INCREASING E-1 Step 6.c Page 45 of 59 Sf -'ON 4 Lesson Title: Large Break LOCA 10 Number: Time 2K11 NRC-04 IDA/Malf Instructor Information/Activity Task Assign Expected Action Revision: .Q.. Standard RO Verify PZR level -GREATER THAN 16% (50% ADVERSE CTMT) E-1 Step 6.d US Proceed to CAUTION prior to step 7. E-1, Step 6, RNO US To ensure adequate ECCS flow, do not stop any recirculation spray pumps used for core injection flow. E-1, Step 7 CAUTION US The recirculation spray pumps are sequenced to automatically start 11 minutes after a CDA. E-1, Step 7 NOTE RO Check if containment spray should be stopped. E-1, step 7 RO Verify quench spray pumps -RUNNING E-1, Step 7.a US Proceed to CAUTION prior to step 8. E-1, Step 7,a, RNO After SI reset, manual operator action ,is required to: E-1, Step 8 CAUTION

• Open the charging cold leg injection valves when RCS pressure decreases to LESS THAN 1900 psia.

• Restart the RHR pumps if RCS Page 46 of 59 SF ,)N Lesson Title: Large Break LOCA 10 Number: 2K11 NRC-04 Time IDA/Malt Instructor Information/Activity RCS pressure should be around 1050 psi a and stable. But depending on the speed of the crew, RCS pressure may still be going down very slowly. If the crew elects NOT to stop RHR pumps based on this trend; this is satisfactory.

Crew should reset SI NOTE: This step will stop the RHR Pumps. If stopped, the pumps will need to be restarted when the LOCA becomes larger. Revision: Task Assign Expected Action Standard pressure decreases in an uncontrolled manner to LESS THAN 300 psia (500 psia ADVERSE CTMT).

• Restart safeguards equipment if offsite power is lost. US Check It RHR Pumps Should Be Stopped E-1, Step 8 US Check RHR pumps -ANY RUNNING IN SI MODE E-1, Step 8.a RO Check RCS pressure 1) Verify pressure -GREATER THAN 300 psia (500 psia ADVERSE CTMT) E-1, Step B.b 2) Verify pressure -STABLE OR INCREASING RO RESET SI, if E-1, Step 8.c RO STOP RHR pumps and Place in E-1, Step B.d US Check RCS and SG E-1, Step 9 BOP

• Check pressure in all SGs Page 47 of 59 SEC'..... 'f)N 4 Lesson Title: Large Break LOCA 10 Number: Time 2K11 NRC-04 IDA/Malf Instructor Information/Activity Task Assi91'l Expected Action Revision:

Q.. Standard INCREASING OR STABLE (consistent with plant cool down ) RO

• Check RCS pressure -DECREASING OR STABLE E-1, Step 9 T= step 10 Trigger 11 RC02B sev= 100% This will increase the severity of the SBlOCA to a point where ADVERSE CTMT will occur and if stopped, the RHR pumps will need to be restarted.

US Check If Diesel Generators Should Be Stopped E-1 Step 10 The crew will need to recognize 3 items: 1* The rise in CTMT pressure will generate an orange path (no CTMT spray pumps are running) on CTMT, and require transition to Z.1 2* CDA has failed to actuate. 3-If stopped, RHR pumps will need to be restarted.

Note A red path on Integrity may come in first. If so the crew will perform P.1 first as it has a higher priority.

US Go to FR-Z.1 and restart the RHR pumps E-1, step 8 caution and OP3272 FR-P.1 (rev 015) Steps CRE W

• If DWST level decreases to LESS THAN 80,000 gal, Shift AFW pump suction to FR-P.1 Step 1 Page 48 of 59 Sf" 'ON 4 Lesson Title: Large Break LOCA ID Number: 2K11 NRC-04 Revision:

Q.. Task Time IDA/Malf Instructor Information/Activity_

_ Assign Expected Action Standard the CST using CAUTION If RWST level decreases to LESS THAN 520,000 gal, Go to ES-1.3, Transfer to Cold Leg Recirculation, to align the ECCS system. RCS pressure will be less than 300 RO Check RCS Pressure -GREATER THAN FR-P.1, psia. 300 psia (500 psia ADVERSE CTMT) Step 1 RHR pumps may be started by the crew at this point. US Perform the applicable FR-P.1, Step 1, RNO IE RHR pump flow is LESS THAN OR EQUAL TO 1000 gpm THEN Proceed to step 2. RHR Pump flow should be > 1,000

• IE RHR pump flow is GREATER THAN gpm. The appropriate transition will 1000 gpm THEN Go to procedure and be to FR-Z.1 step in effect.

Response to CTMT Pressure, Rev. If RWST level decreases to LESS THAN FR-Z.1, 520,000 gal, Go to ES-1.3, Transfer to Cold Step 1 Leg Recirculation, to align the ECCS CAUTION system. Page 49 of 59 SE Lesson Title: Large Break ID Number: 2K11 NRC-04 Revision: Time IDA/Malf Instructor Information/Activity Yes. CTMT pressure will be greater than 23 psia. "CONTAINMENT DEPRESS ACTUATION" will NOT be lit. The RO is expected to attempt to manually initiate CDA using the main board push buttons The RPCCW pumps will have to be manually stopped. RCPs have already been stopped. The BOP will have to manually stop the CAR and CRDM fans. Task Assign Expected Action Standard US/RO Check if CDA Required FR-Z.1, Step 1 RO Check CTMT pressure GREATER THAN 23 psia FR-Z.1, Step 1.a Verify Annunciator "CTMT DEPRES ACTUATION" (MB2B 5-5)-LlT FR-Z.1, Step 1.b RO Initiate CDA. FR-Z.1, Step 1.b RNa RO Check RPCCW pumps -STOPPED FR-Z.1, Step i.c RO STOP pumps. FR-Z.1, Step 1.c RNa RO STOP all RCPs FR-Z.1, Step 1.d BOP Check CAR fans -STOPPED FR-Z.1, Step 1.e Check CRDM fans -STOPPED FR-Z.1, Step 1.f If ECA-1.1, Loss of Emergency Coolant Recirculation, is in progress, Ctmt spray should be operated as directed in ECA-1.1 FR-Z.1, Step 2 CAUTION US Verify Quench Spray System Operation FR-Z.1, Step 2 Page 50 of 59 Sf Lesson Title: Large Break LOCA ID Number: 2K11 NRC-04 Revision:

Q.. Task Time IDA/Malf Instructor Information/Activity_

Assign Expected Action Standard Check annunciator RWST EMPTY QSS PP FR-Z.1, OFF (69,331 gal)(MB2A 5-2) -NOT LIT Step 2.a NO. RO Verify quench spray pumps -FR-Z.1, Step 2.b Critical Task [*] -RO START pumps. FR-Z.1, Step 2.b, The RO must manually start the RNO [*]QSS pumps. Verify running quench spray pump discharge FR-Z.1, valves -OPEN Step 2.c

• 3QSS*MOV34A

• 3QSS*MOV34B Critical Task [*] -RO OPEN valves. FR-Z.1, Step 2.c, The RO must manually open the RNO [*]quench spray pump US Check Ctmt FR-Z.1, Step 3 CTMT pressure will be less than 60 Check etmt pressure -LESS THAN 60 FR-Z.1, psia. Step 3.a psia FR-Z.1, The US should transition back to Go to procedure and step in effect and, 1, step after evaluating step applicability based Step 3.b on plant conditions, Perform the remainder of this procedure as time allows Page 51 of 59 SEr ',)N 4 Lesson Title: Large Break LOCA 10 Number: 2K11 NRC-04 Revision:

Q.. Task Time IDA/Malt Instructor Intormation/Activity__

Expected Action Standard The scenario may be terminated upon completion of FR-Z.1. Page 52 of 59 SECTION Lesson Title: Large Break LOCA 10 Number: 2K11 NRC-04 Revision:

Q. EVALUATION GUIDE Crew FOLLOW-UP QUESTIONS What is the Emergency Classification for this event? ALERT -Charlie One based on failure ofthe RCS barrier. (BA1) What plant condition(s) is(are) of greatest concern for (this event)? What actions did the crew take to directly mitigate (this event)? Which safety function(s) were challenged or had the greatest potential for challenge?

Describe why. Page 53 of 59 SECTION 4 EXAM GUIDE

SUMMARY

Title: Large Break LOCA 10 Number: 2K11 NRC-04 Revision:

-II. Critical Tasks Note: Critical Tasks are not required for Progress Review Exams. TASK DESCRIPTION Energize at least one ac emergency bus before transition out of E-O, unless the transition is to ECA-O.O, in which case the critical task must be performed before placing safeguards equipment handswitches in the pull-to-Iock position.

Manually actuate at least one train of actuated safeguards before completion of step 4 of E-O. Establish at least one Quench Spray train flow before completion of FR-Z.1 step 4. TASK # KIA >/= 3.0 055 EA1.02 4.3 4.4 055 EA1.06 4.1 4.5 055 EA2.02 3.9 4.7 055 EA2.06 3.7 4.1 E-O --C BASIS SELECTION Failure to energize an ac emergency bus constitutes "mis-operation or incorrect crew performance which leads to degraded emergency power capacity." Failure to perform the critical task also results in needless degradation of a barrier to fission product release, specifically of the RCS barrier at the point of the RCP seals. Failure to manually actuate SI represents a "demonstrated in-ability by the crew to take an action or combination of actions that would prevent a challenge to plant safety. II Failure to establish at least one Quench Spray train flow under the postulated conditions constitutes a "demonstrated inability by the crew to recognize a failure/incorrect auto actuation of an ESF system or component." Note: Used to designate critical tasks. Should also be incorporated into column 3 or 4 of Instructor Guide. Page 54 of 59 SIMULATOR TRAINING SHIFT TURNOVER DATE"TIME PREPARED Today PLANT Mode: 1 . Rx Power: Megawatts:

Thermal: 256 MWTH PZRPressure:

2250 Electric:

0 MWe ........., RCS T-:AVE: RCSLeakage:

Identified:

0.015 gpm PtotectedTrain/Facility:

A TRAIN Unidentified:

0.036 gpm PM: Date/Time:

Toda Active Tracking Records and Action Statements Equipment/Reason LCO Action Date Time in LCO Action Requirement Time Left 00 Compensatory Actions I Temp Logs Watch Open Date Class Reason Reason Position None **urveillances

/ Evolutions in Progress OP 3204 Steady State Operation Reactivity Briefing (see reactivity thumbrules I spread sheet for additional info) Current Rod Height Xenon Trend Current Boron 1868 Shift Orders Reactor power is stable low in the power range (reactor power 7%), following a reactor startup by the previous shift. This is the initial plant startup from a short non-refueling outage. OP 3203, Plant Startup is in progress and complete up through step 4.3.8. The crew is to raise reactor power from 7% to 15 to 19% in accordance with step 4.3.9. The reactivity plan is to raise reactor power using rods at no more than 2 steps per minute. Feed Control is on the FRV Bypass Valves in automatic, with the "A" TO MFP in service, with it's recirc valve open to minimize feed control instabilities.

Page 55 of 59 Appendix D Scenario Form ES-D-1 Facility:

Millstone 3 Scenario No.: 2K11 NRC-04 {s!;larel Op-Test No.: 2K11 -

Operators:

Initial Conditions:

IC-08 (modified}, 7% 120wer, Beginning of Ufe, No The crew will take the shift with reactor l20wer stable and just having entered MODE (reactor l20wer 7%}, following a reactor startul2 by' the I2revious shift. This is the I2lant startul2 from a refueling outage. OP 3203, Plant Startu(l is in Event \ Malf. \ No. No 1 R (RO) R (SRO) N1 BOP) NI11 I SW01C C (RO) NI09B I (BOP) 5 RC25B C (RO) C (BOP) ED01 EG13A C (BOP) RP11M CV13B M (ALL) RC02B 8 RP07AJB C(RQt 9 RP11L C (BOP) 10 RC02C C (RO) RP06AJB

• N)ormal, R)eactivity, Event Description Power increase to place the Main Turbine online OP 3203, Plant Startup. (Section P-10 Permissive failure results in a termination of startup and Tech SQec 3.0.3 "C' Service Water Pum(:l tri(:l. {Annunciator Power Range Nuclear Instrument (NI) Channel Lower Detector fails high requiring FRV Bypass controllers to be (:llaced in 'B' RCP high shaft vibration requiring an shutdown of the affected RCP. (Annunciator AOP Loss of offsite power. 'A' Emergency Diesel (EDG) fails to automatically start and must be started from MB8. BOP must manually close the and 'B' EDG out ut Small break LOCA inside CTMT (catastrophic loss 'B' RCP seal package).

Safety Injection Safety Injection fails to automatically actuate. . Feedwater Isolation fails to automatically actuate. Large break LOCA inside CTMT. CDA fails to auto-actuate. (I )nstrument, {C)omponent, (M)ajor Page 57 of 59 Lesson Title: Large Break LOCA ID Number: 2K11 NRC-04 Revision: .Q.. Assessor:

Dave Minnich QUALITATIVE ATTRIBUTES The initial conditions are realistic, in that some equipment and/or instrumentation may be out service, but it does not cue the crew into expected The scenario consists mostly of related Each event description consists of: the paint in the scenario when it is to be initiated the malfunctions(s}

that are entered to initiate the event the symptoms/cues that will be visible to the crew the expected operator actions (by shift position) the event termination point (if applicable)

No more than one non-mechanistic failure (e.g., pipe break) is incorporated into the scenario without a credible preceding incident such as a seismic event. The events are valid with regard to physics and Sequencing/timing of events is reasonable, and allows for the examination team to complete evaluation results commensurate with the scenario If time compression techniques are used, scenario summary clearly so indicates.

Operators sufficient time to carry out expected activities without undue time constraints.

Cues are The simulator modeling is not The scenario has been validated.

Pursuant to 10 CFR 55.46(d), any open simulator deficiencies or deviations from the referenced plant have been evaluated to ensure fidelity is maintained while running the planned Every operator will be evaluated using at least one new or significantly modified scenario.

All scenarios have been altered lAW Section 0.5 of All individual operator competencies can be evaluated, as verified using form Each operator will be significantly involved in the minimum number of transients and specified on Form Level of difficulty is appropriate to support licensing decisions for each crew Page 58 of 59 Lesson Title: Large Break LOCA 10 Number: 2K11 NRC-04 Revision:

Q. Note: Following criteria list scenario traits that are numerical (QUANTITATIVE) in nature. 01. Total Malfunctions (TM) -5 to 8 required Total 8 (1) 'C' Service Water Pump trip. (2) PRNI Channel Failure. (3) RCP High Vibrations, (4) Loss Offsite Power I EOG fails to automatically start, (5) Small break LOCA. (6) Safely Injection Actuation Failure, (7) Feedwater Isolation fails to auto-actuate, (8) Large Break LOCA I fails to

02. Malfunctions after EOP entry (EM's) -1 to 2 required Total 4 (1) EOG fails to automatically start, (2) Safety Injection Auto Actuation Failure, (3)

Isolation fails to auto-actuate, (4) Large Break LOCA I COA fails to

03. Abnormal Events (AE) -2 to 4 required Total 3 (1) 'C' Service Water Pump trip (ARP). (2) PRNI Channel Failure (AOP 3571). (3) RCP Vibrations I RCP Trip (AOP 04. Major Transients (MT) -1 to 2 required Total 1 (1) Small break LOCA 05. EOP's (EU) entered/requiring substantive actions --1 to 2 required Total 2 (1) E*1. (2) FR-Z.1 06. EOP Contingencies requiring substantive actions [ECAs/FRs/] (EC) --Total 1 o to 2 required (1) FR-Z.1 07. Critical Tasks (CT) 2 to 3 required Total-=3_

E-O -C Energize at least one ae emergency bus E-O 0 Manually actuate at least one train of SI E-G -E Establish at least one Quench Spray train flow 08. Approximate Scenario Run Time: 60 to 90 min. Total 150 min 09. EOP run time: Total 60 min 10. Technical Specifications are exercised during the scenario.

{Y/N)_Y_ Page 59 of 59 JOB PERFORMANCE MEASURE APPROVAL SHEET JPM Title: Determine QPTR, Analyze Results and Make Recommendations.

JPM Number: NRC RO A.1.1 (JPM-051)

Revision:

Initiated:

,> 03/10/11 Developer Date Reviewed: ( sf 1 /11 Technical Reviewer Approved:

5 Supervisor, Nuclear Traini 1 1

SUMMARY

OF " DATE DESCRIPTION REV/CHANGE 1 /0 Updated JPM to revision 004-08 to SP 31012. Modified JPM format to be consistent with the NRC 2K11 JPM set. Removed JPM steps associated with specific steps in AOP 3552, in that it added no value to this JPM. This did not remove any critical steps and shortened the overall time to conduc::t the JPM. DLM _______ ________.-.I

---

JPM Facility:

_M'--P-'-3

____

JPM Number: NRC RO A.1.1 Revision:

Task Title: Determine QPTR, Analyze Results and Make Recommendations.

System: Conduct of Operations Time Critical Task: ) YES (X) NO Validated Time (minutes):

__....;.1..;;;..5

__ Task Number(s):

341-01-788 Applicable To: SRO RO X PEO KJA Number: GEN.2.1.19 KJA Rating: 3.9/3.8 Method of Testing: Simulated Actual Performance:

Performance:

Location:

Classroom:

Simulator:

X In-Plant:

T ask Standards:

Perform a QPTR Reguired Materials:

SP 31012, Quadrant Power Tilt Ratio, Rev. 004-08 (procedures.

equipment.

etc.) Handout 1; Completed Attachment 2 showing the MP3 simulator 100% NI Currents.

General

References:

MP3 Tech Specs AOP 3552, Malfunction of the Rod Drive System, Rev. 010-01 X

• • • READ TO THE EXAMINEE I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this JPM will be satisfied.

You may use any approved reference material normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.

JPM WORKSHEET JPM Number: NRC RO Revision:

1 Simulator Requirements:

1. Reset to IC 305 .... OR Reset to IC-18. Go to run, and insert malfunction R00357 (0 steps) to drop rod 04. Allow primary plant parameters to stabilize. Go to freeze. Approximate simulator setup time is .§ minutes. Initial The plant was at 100% power when Control Rod D4 dropped. The crew is carrying out the actions of AOP 3552, Malfunction of the Rod Drive System, Attachment B; Dropped Rod. The crew is at step 2.b of Attachment B (Determine QPTR). The PPC is out of service. You are the extra licensed operator on shift. Initiating The US has directed you to determine QPTR using SP 31012, Quadrant Power Tilt Ratio. * * *

• NOTES TO TASK PERFORMANCE EVALUATOR

• * *

• Critical steps for this JPM are indicated by checking "Y". For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly. When the student states what his/her simulated action/observation would be, read the appropriate "Cue". If necessary, question student for details of simulated actions/observations (Le. "What are you looking at?" or "What are you observing?"). Under NO circumstances must the student be allowed to manipulate any devices during the performance of this JPM.(in:e.lal only). l___4 _-----I 1 PERFORMA,,.CE INFORMATION JPM Number: NRC RO A.1.1 Revision:

Task Title: Determine QPTR, Analyze Results and Make Recommendations.

START TIME: ____ PERFORMANCE STANDARD STEP Obtain proper Surveillance Procedure.

Candidate obtains and refers to SP Critical:

Grade #1 31012, Quadrant Power Tilt Ratio, Y [ ] S [ ] SP 31012 N[X] U [ ] Section 4.2: QPTR By Measurement.

Step 2.1 Comments:

When the Candidate requests or takes action to obtain SP 31012, provide the Candidate a copy of SP 31012, Quadrant Power Tilt Ratio. Cue: '. STEP VERIFY "General Prerequisites" Candidate verifies "Test Authorized By" Critical:

Grade #2 completed.

block is signed on SP 31012, Attachment Y [ J s [ ] SP 31012 N[X] U [ ] 1 Cover Sheet. Step 2.1 Reviews SP 31012, Section 3 Critical:

Grade PRECAUTIONS Y [ ] S [ ] N [XJ U [ ] Candidate initials for 'Prerequisites Critical:

Grade Completed' and 'Precautions Noted' on Y [ ] S [ ] N[Xj U [ ] Attachment 1 Cover Sheet.. Comments:

The Candidate may ask whether NI channel recalibration is in progress.

Provide the following cue: Cue: NI channel recalibration is NOT in progress. I STEP QPTR By Measurement Candidate locates NMP-NM41 F through Critical:

Grade #3 NMP-NM44F at the NI Cabinets and Y [ ] S [ ] N[X] U [ ] RECORD average percent reactor power records the 4 values for reactor power in SP 31012 from NI cabinet meters NMP--NM41 F percent.Step through NMP--NM44F or from the Process Computer Calorimetric on Attachment Comments:

Cue: STEP Candidate averages 4 values for reactor Critical:

Grade #4 power and records on Attachment 1 . Y [ ] S [ ] N[X] U [ ] Comments:

The JPM Key (correctly completed Attachment

1) shows average percent reactor power (about 95.2%). Cue: STEP DETERMINE QPTR as follows: Candidate reviews the NOTE. Critical: #5 Y [ ] S [ SP 31012 N[X] U [ Attachment 2, "100% Nt Currents," is Step NOTE maintained in the "Reactor Curve and Data Book."

When the Candidate requests or takes action to obtain the Reactor Engineering Curve and Data Book, provide the Candidate with the filled out Attachment 2 showing the simulator 100% NI Currents. (Handout 1) Cue: .......__........ --......._ ......_-.......---_ ......6

---

STEP RECORD available upper and lower Locates and records the upper and lower Critical:

Grade #6 detector readings on Attachment

1. detector digital meter readings for PRNI Y[X] S [ ] N [ ] U [ ] channels 41 through 44 on Attachment 1 . SP Step Comments:

The JPM Key (correctly completed Attachment

1) shows the upper and lower detector readings that the Candidate should record. Cue: . STEP On Attachment 1, RECORD 100% Nl upper Candidate identifies and records the Critical:

Grade #7 and lower currents obtained from correct 100% N I upper and lower currents Y[X] S [ ] N [ ] U [ ] Attachment

2. on Attachment 1, for PRNI channels 41 SP 31012 through 44. Step 4.2.2.b Comments:

These 100% NI currents will be obtained from Handout 1. Cue: STEP RECORD data source and date of Locates Remarks" section on Attachment Critical:

Grade #8 Attachment 2 entry in "Remarks" section 1 and records data source (RE Curve Y [ ] S [ ] SP 31012 N[X] U [ ] on Attachment 1 Book) and date (date on Handout 1) of Step 4.2.2.c Attachment 2 entry. Comments:

Cue: . .' . STEP Candidate divides each detectors reading Critical:

Grade CALCULATE the detector ratio for each #9 by that detectors 100% current to Y[X] S [ ] detector by dividing each detectors N [ ] U [ J determine the detector ratio for the upper reading by that detectors 100% current SP 31012 and iower detectors of PRNI channels 41 Step 4.2.2.d and RECORD on Attachment

1. through 44. Comments:

Cue: Candidate records the detector ratios on Critical:

Grade Attachment 1, for the upper and lower Y [ ] S [ ] N[X] U [ ] detectors.

--.... _ ... -.... _ .... --.... _ ..__... _..__.--_._...7 Comments:

The JPM Key (correctly completed Attachlflent

1) shows the detector ratios that the Candidate should record. Cue: STEP CALCULATE the average upper and lower Critical:

Grade Candidate calculates the average upper #10 ratio and RECORD on Attachment

1. Y[X] S [ ] and lower detector ratios. N [ ] U [

SP Step Comments:

Cue: Critical:

Grade Candidate records the average upper and Y [ ] S [ ] lower detector ratios on Attachment 1 . N[X] U [ J Comments:

The JPM Key (correctly completed Attachment

1) shows the average upper and lower detector ratios that the Candidate should record. Cue: STEP Using the following equation.

CALCULATE Candidate determines the power tilt Critical:

Grade #11 power tilt for each detector and RECORD (QPTR) for the upper and lower detectors Y[X] S [ J N [ ] U [ ] in "QPTR" section of Attachment 1: associated with PRNI channel 41 through SP Step 4.2.4.f 44 by dividing each detectors Upper QPTR = (Upper Detector Ratio) + ratio by the average (Average Upper Lower QPTR = (Lower Detector Ratio) (Average Lower Comments:

, Cue: .... _ ... -.... _ .... -_ .... _

Candidate records upper and lower Critical:

Grade QPTR values in the "QPTR" section of Y [ ] S [ ] Attachment

1. N[X) U [ J Comments:

The JPM Key (correctly completed Attachment

1) shows the QPTR values that the Candidate should record in the 'QPTR' section. Cue: STEP RECORD maximum upper and lower Determines maximum upper and lower Critical:

Grade #12 QPTR and associated channel on detector QPTR and associated channel. Y[X] S [ J SP 31012 N [ ] U [ ] Attachment 1 . , Step 4.2.4.f I i Candidate records maximum upper and Critical:

Grade lower detector QPTR and associated Y [ ] S [ ] channel on Attachment

1. N[X] U [ ] Comments:

The JPM Key (correctly completed Attachment

1) shows the maximum upper and lower QPTR values and their associated channel. Cue: STEP VERIFY the following acceptance Candidate recognizes from calculated Critical:

Grade #13 criteria are met: average reactor power (JPM step 4) that Y [ ] S [ ] reactor power is greater than 50%. N[X] U [ ] SP Step 4.2.3.a WHEN above 50% of Rated Power (RTP), VERIFY maximum does not exceed Comments:

Cue: Candidate recognizes that QPTR IS Critical:

Grade greater than 1.02. Y[X] S [ ] N [ ] U [ ] Comments:

The JPM Key (correctly completed Attachment

1) shows QPTR DOES exceed 1.02 on channel 43 upper and lower detectors.

Cue: 9 STEP Candidate informs the US that QPTR is Critical:

Grade IF QPTR is greater than 1.02 and power #14 greater than 1.02 and that Technical Y[X] S [ ] is above 50% RTP, NOTIFY Shift N [ ] U [ ] Specification 3/4.2.4, "Quadrant Power SP 31012 Manager that Technical Step 4.2.3.b Tilt Ratio," action statement 3/4.2.4, "Quadrant Power Tilt action statement Comments:

Cue: TERMINATION CUE: Acknowledge the Candidate's report and reply that the US is referring to TIS 3/4.204. The evaluation for this JPM is concluded.

STOP TIME: ___

--1 VERIFICATION OF JPM JPM Number: NRC RO A.1.1 Date To achieve a satisfactory grade, ALL critical steps must be completed correctly.

If task is Time Critical, it.M!!§I be completed within the specified time to achieve a satisfactory grade. Time Critical Task? Yes No X Validated Time (minutes):

15 Actual Time to Complete (minutes):

Overall Result of JPM: SAT UNSAT Areas for Improvement I Comments: .

---

STUDENT JPM Number: Initial Conditions:

Initiating Cues: NRC RO A.1.1 Revision:

1 The plant was at 100% power when Control Rod 04 dropped. The crew is carrying out the actions of AOP 3552, Malfunction of the Rod Drive System, Attachment B; Dropped Rod. The crew is at step 2.b of Attachment B (Determine QPTR). The PPC is out of service. You are the extra licensed operator on shift. The US has directed you to determine QPTR using SP 31012, Quadrant Power Tilt Ratio.

JPM Title: JPM Number: Initiated:

Reviewed:

Approved:

JOB PERFORMANCE MEASURE APPROVAL SHEET Perform a Shutdown Margin for MODE 3 with One Stuck

..NRC ROA.1.2 (JPM 07BA) Revision:

2 03/08/11 Developer Date Technical R , Dfue I

SUMMARY

OF DATE DESCRIPTION REV/CHANGE 03/08/11 Modified initial conditions to present cycle (14) conditions. -Modified JPM format to be consistent with the NRC

• JPM set. Added critical steps (JPM-078A had no critical I DLM . r

---

JPM Facility:

Millstone Unit 3 Examinee:

JPM Number: NRC RO A.1.2 Revision:

2 Task Title: Perform a Shutdown Margin for MODE 3 with One Stuck Control Rod. System: 001 (Control Rod Drive System) Time Critical Task: ) YES (X) NO Validated Time (minutes):

30 Task Number(s):

341-01-187 Applicable To: SRO __ RO PEO KIA Number: 001-A4.11 2.1.25 KIA Rating: 3.5/4.1 3.9/4.2 Method of Testing: Simulated Performance:

Actual Performance:

X Location:

Classroom:

X Simulator:

In-Plant:

Task Standards:

Correctly determines SHUTDOWN MARGIN Required Materials:

OP 3209B Shutdown Margin (rev 010-06), Form 3209B-002 (rev {procedures, equipment, etc.} 02), and Cycle 14 Middle of Life RE Curve Book General

References:

Unit 3 Technical Specifications, Technical Requirements

• • • READ TO THE EXAMINEE I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When complete the task successfully, the objective for this JPM will be satisfied.

You may use any reference material normally available in the Control Room, including logs. Make all written reports, reports, alarm acknowledgements, and log entries-as if the evolution was actually being JPM WORKSHEET 2 JPM Number: NRC RO Revision:

Initial Thirty minutes ago, the plant tripped from 100%

equilibrium power after 2 months of operation.

Control M-4 failed to insert on the trip. All other plant and systems responded as designed.

The plant is in MODE 3, and stable at normal temperature and Other plant conditions are: RCS boron is 1150ppm (sample taken at 0700 today) Core Burnup is 10,500 MWD/MTU Initiating The US has directed you to calculate SHUTDOWN for current plant conditions per OP 3209B, Shutdown An STA review of your results is NOT Simulator NONE _.._-._--------_._-..* * *." NOTES TO TASK PERFORMANCE EVALUATOR

• ."."." Critical steps for this JPM are indicated by checking "Y". For the student to achieve satisfactory grade, ALL critical steps must be completed When the student states what his/her simulated action/observation would be, read appropriate If necessary, question student for details of simulated actions/observations (Le. "What you looking at?" or "What are you Under NO circumstances must the student be allowed to manipulate any devices during performance of this JPM (in-plant PERFORMANCE INFORMATION JPM Number: NRC RO A.1.2 Revision:

2 Task Title: Perform a Shutdown Margin for MODE 3 with One Stuck Control Rod. START TllME: _______ PERFORMANCE STANDARD STEP Obtains copy of OP 32098 "Shutdown Obtains proper

1. 1 Comments:

When candidate identifies that form 32098-002 is required, provide a copy of the form. Cue: STEP VERIFY "General Prerequisites" Candidate verifies Test Authorized #2 completed.

block is signed on FORM OP step Reviews OP 32098 Section Candidate initials for 'Prerequisites Completed' and 'Precautions Noted' on FORM 32098-002 cover sheet. Comments:

Cue: STEP Refer to OP 32098-002 and RECORD time Records time and date on OP #3 and date. 002. OP 3209B, step 4.2.2 Comments:

Cue: Y [ N[X] Y [ N[X] Y [ Y [ N[XJ Y [ N[X] Grade S [ J U [ ] Grade S [ ] U [ ] Grade S ( ] U [ ] Grade S [ U [ i i Grade . S [ J U [ ]

STEP With DRPI deenergized, verification of roLl Candidate reviews the NOTE. #4 position is based upon the rod position OP to deenergizing the Digital Rod Position step 4.2.3 NOTE Indication System. Comments:

Cue: STEP IF determining SHUTDOWN MARGIN for Candidate circles "3" for the current #5 current plant conditions, Refer To OP MODE on OP 32098-002.

OP 3209B, 32098-002 and PERFORM the following in step 4.2.3.a the Current Conditions section: CIRCLE the current MODE, and applicable, the RCS loops' (Refer To Definition Comments:

Cue: STEP 08TAIN the present core burnup value Enters "10,500" MWD/MTU on OP #6 from the Plant Process Computer and 32098-002.

OP 3209B, DOCUMENT.

step 4.2.3.b Comments:

The value for present core burnup was given in initial plant conditions.

Cue: STEP PERFORM the following to determine Candidate circles "557°F" for the #7 temperature condition:

temperature condition on OP 32098-002.

OP 3209B, step 4.2.3.c iF in MODE 3, AND maintaining load Tavg, CIRCLE Comments:

Cue: Critical: Y [ ] N[X] Y [ N[X] Y [ N[X] Y [ N[X] , Grade S [ ] U [ ] Grade S [ ] U [ ] Grade S [ ] U [ ] i Grade I S [ ] U [ ]

STEP IF performing SHUTDOWN MARGIN Candidate calls or requests the US call Critical:

Grade #8 determination at increased surveillance the Chemistry Department to obtain an Y [ ] S [ ] OP 3209B, N[X] U [ ] frequency due to an inoperable control rod initial RCS boron sample and every 8 step 4.2.3.d OR an inoperable SMM, PERFORM the hours REQUEST Chemistry Department an initial sample of the RCS for concentration AND every 8 Comments:

Cue: The call has been made to Chemistry.

Chemistry reports that an RCS boron sample has just been taken and the results are 1150 ppm. STEP DOCUMENT the most current 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Candidate enters "1150" PPM for the Critical:

Grade #9 RCS boron concentration sample result. current boron concentration on OP Y [ J s ( ]

N[X] U [ J Comments:

Cue: STEP Go To step 4.2.3.f. Candidate proceeds to step 4.2.3.f Critical:

Grade #10 Y [ ] S [ J N[X] U [ L_ Comments:

Cue: STEP DOCUMENT the "Date and Time" the Candidate enters "today & 0700" for the Critical:

Grade #11 boron sample was obtained.

boron sample date and time on OP Y [ ] S [ ] OP 3209B, N[X] U ( ] step 4.2.3.f Comments:

Cue: STEP CIRCLE the status of the Shutdown Banks Candidate circles "Inserted" for the Critical:

Grade #12 (shutdown banks may be withdrawn in Shutdown Banks status on OP 3209B-Y [ J S [ J OP 3209B, N[X] U [ J MODE 3 only). 002. step 4.2.3.g 7 Comments:

Cue: STEP #13 OP 3209B, step 4.2.3.h Comments:

Cue: DOCUMENT the number of stuck rods Candidate enters "one" for the number of indicated by the DRPI System. stuck rods on OP 32098-002.

The number of stuck rods was given in initial plant conditions.

Critical: Y ( ] N[X] Grade S ( ] U [ ] STEP #14 OP 3209B, step 4.2.3.i Comments:

DOCUMENT "N/A" in the "Anticipated Conditions" section. Enters "N/A" in the "Anticipated Conditions" section of OP 32098-002.

Critical: Y [ ] N[X] Grade S [ ] U [ ] Cue: STEP #15 OP 3209B, step 4.2.3.j Comments:

Go To step 4.2.5. Candidate proceeds to step 4.2.5. Critical: y [ 1 N[X] Grade s [ 1 U [ ] Cue: Evaluator Note: Provide a copy of the Cycle 14 Middle of Life RE Curve Book to the Candidate.

STEP IF a control rod is known to be #16 DETERMINE the "Stuck Rod Equivalent" as OP Refer To "Boron Worth vs Boron 4.2.S.a.1)

Concentration And Temperature" graph in the RE Curve and Data Book and PERFORM the following:

SELECT the DBW curve based on the condition circled in step 4.2.3.c. or 4.2.4.c. and INDICATE on OP 3209B* 002 the DBW curve selected: IE 55rF circled, USE the 55rF curve Comments:

Cue: Comments:

Cue: STEP DETERMINE "Differential Boron Worth" #17 for the RCS boron OP recorded in step 4.2.3.d. or 4.2.4.d. using step the selected curve and DOCUMENT as a 4.2.S.a.2) negative value on OP 3209B-002.

The Candidate identifies the correct Critical:

Grade graph (RE-F-03) in the RE Curve and Y[X] S [ ] N [ ] U [ ]

Data Book. Candidate Writes "557°F" on OP 3209B-Critical:

Grade Y [ ] S [ ] NIX] U[J Enters If. 6.9" (-6.8 to -7.0) on OP 3209B-Critical:

Grade 002. Number is approximate.

Allow for Y[XJ S [ ] minor curve interpolation error. N [ ] U [ ]

It is acceptable for the applicant to use the corresponding TABLE (RE-F-03, page 2 of 2) associated with the correct Differential Boron Worth curve. However the acceptable range of values (-6.8 to -7.0)shall remain the same. 9

---

Cue: STEP Refer To "Miscellaneous Core Data" in the Candidate refers to table RE-G-03 and Critical:

Grade #18 RE Curve and Data Book and DETERMINE writes "-1283 pcm" on OP 3209B-002.

Y[X] S [ J OP 3209B, N [ ] U [ ] the "Worst Case Stuck Rod Worth" and step 4.2.S.b DOCUMENT as a negative value on Comments:

Cue: STEP CALCULATE the "Boron Equivalent RW" Candidate divides -1283 by DBW of-6.9 Critical:

Grade #19 (DIVIDE the "Worst Case Stuck Rod pcm/ppm to determine a Boron Y[X] S [ ] OP 3209B, N [ ] U [ ] Worth" by the "Differential Boron Worth") Equivalent RW of 186 ppm (183 to 189 step 4.2.S.c and RECORD on OP 3209B-002 as a ppm). Records value and positive sign positive value. on OPS Form 3209B-002.

Comments:

Number is approximate.

Allow for a slight variation in DBW due to minor curve interpolation error. Cue: STEP CALCULATE the "Stuck Rod Boron Enters ONE and 186 ppm for Stuck Rod Critical:

Grade #20 Equivalent" (MULTIPLY "Boron Equivalent Boron Equivalent on OPS Form 3209B-Y [ ] S [ ] OP 3209B, N[X]Rod Worth" by the number of known stuck 002. U [ J step 4.2.S.d rods) and DOCUMENT on OP 3209B-002.

Comments:

Cue: STEP IE either SMM channel is OPERABLE Candidate recognizes that step 4.2.6 Critical:

Grade #21 based on TIS LCO 3.3.S.b.1 or 3.3.S.b.2, does not apply. Proceeds to step 4.2.7. Y [ ] S [ ] OP 3209B, N[X] U [ ] PERFORM the following to determine the step 4.2.6 additional boron requirement

..... Comments:

Cue:-_.... _-.... _-.... _-.... --.... ---.... _-...._._.... _-.... _-.... _-.... _--.... _ ....._ i STEP Refer To "Shutdown Margin" curves in the The Candidate identifies the correct Critical: #22 RE Curve and Data Book and DETERMINE graph (RE-B-02) in the RE Curve and Y[X] S [ OP 3209B, the required xenon free boron Data Book (Shutdown Margin -MODE N [ J u [ step 4.2.7.a concentration as 3). SELECT the "Shutdown Margin" based on MODE AND RCS operating condition for which calculation is being Comments:

Cue: , STEP Refer To OP 3209B-002 and INDICATE Candidate selects and indicates MODE 3 Critical:

Grade #23 the SHUTDOWN MARGIN curve -ARI [557°F] on OP 32098-002. Y [ J s [ ] OP N[X] U [ ] selected:

step 4.2.7.b Comments:

Cue: STEP IF MODE 3 curve selected, LOCATE the Candidate locates the intersection of Critical: #24 intersection of core burnup and the curve 10,500 MWD/MTU with the ARI [55rF] Y[X] S [ OP 3209B, representing the temperature and curve and determines a required xenon N [ ] U [ step 4.2.7.c shutdown bank condition recorded in free boron concentration of 1125 ppm 4.2.3 or 4.2.4 and DETERMINE (1100 ppm t01150 ppm). required xenon free boron Number is approximate.

Allow for minor curve interpolation error. Comments:

It is acceptable for the applicant to use the corresponding TABLE (RE-B-02, page 2 of 2) associated with the correct Shutdown Margin curve. However the acceptable range of values (1100 ppm t01150 ppm) shall remain the same. Cue: STEP IF a MODE 4 or 5 curve selected .... Candidate recognizes that step 4.2.7.d Critical:

Grade #25 does not apply. Proceeds to step 4.2.7.e. Y [ ] S [ ] OP N[X] U [ J step 4.2.7.d 11 I Comments:

Cue: STEP #26 OP 3209B, step 4.2.7.e STEP #27 OP 3209B, step 4.2.8 STEP #28 OP 3209B, step 4.2.9 Refer To OP 3209B-002 and RECORD the "Required Xenon Free Boron Concentration. " ADD the following values and DOCUMENT as "Total Required Xe Free Cs" on OP 3209B-002.

• Required Xe Free C s

• Stuck Rod Boron Equivalent

• SMM Additional Boron SUBTRACT "Total Required Xe Free Cs" from actual RCS Boron Concentration and RECORD value and sign (+/-) on OP 002. Candidate writes "1125 ppm" on OP 3209B*002 for required xenon free boron concentration.

Candidate adds the values, 1125 ppm + 186 ppm + 0 ppm, to determine a value of total required Xe free Cs, of 1311 ppm. Records 1311 ppm (1283 ppm to 1339 ppm) on OPS Form 3209B-002.

Candidate subtracts 1311 ppm from 1150 ppm to yield -161 ppm. Candidate records "-161 ppm" (-133 ppm to -189 on OP 3209B-002.

Critical: Y [ Critical:

Y[X] N [ ] Critical:

Y[X] N [ 1 Grade S [ ] U [ ] i i Grade i S [ U [ I Grade S [ ] U [ ]

STEP J£ RCS boron concentration is less than th\.. #29 total required Xe free boron concentration for current plant condition, PERFORM one OP 3209B, of the following:

step 4.2.10 I F time after shutdown is less than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> AND in MODE 3, Refer To Section 4.3 and PERFORM xenon correction. Refer To AOP 3566, "Immediate Boration," and PERFORM immediate boration and ESTABLISH actual boron concentration greater than total required boron concentration.

Comments:

Cue: Candidate recognizes that RCS boron concentration IS less than the total required Xe free boron concentration.

Candidate reports to the US that Shutdown Margin is not adequate for current plant conditions and either a xenon correction or immediate boration is required.

Comments:

Once the Candidate makes the report, provide the following cue: Cue: Perform a Xenon Correction.

Candidate proceeds to section 4.3. Comments:

Cue: _ ....._ ....._ .... __.__.__... -.... -Critical:

Y[X] N [ '] Y [ N[X] Y [ N[X] brade S [ ] U [ ] Grade S [ ] U [ ] Grade S [ ] U [ ]

--STEP Xenon may not be credited when Candidate recognizes that current Critical:

Grade #30 calculating SHUTDOWN MARGIN for conditions are MODE 3 and xenon may Y [ ] S [ ] OP N[X] U [ ] MODEs 4 or be credited.

step Comments:

Cue: STEP Performing a xenon correction for the next Candidate reviews the NOTE. Critical:

Grade #31 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period versus hourly corrections is Y [ J s ( ] OP N[X] U [ ] usually the preferred method. step The Candidate may ask whether a xenon correction for the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or hourly corrections is desired. Provide the following cue: Cue: The US directs you to perform a xenon correction for the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Assume it is one hour gost trig. STEP To determine the xenon reactivity, Candidate reviews the step. Critical:

Grade #32 PERFORM the following: Y [ J S [ J N[X] U [ OP Refer To one of the following:

step 4.3.1.a RE Curve and Data Book, Reactivity After Trip 30% to RE Curve and Data Book, Reactivity After Trip 70% to Special Program R7/R9 The Candidate may ask whether to use the PPC or the RE Curve and Data Book. Provide the following cue: Cue: The US directs you to use the RE Curve and Data Book 14 STEP Refer To OP 3209B-002 and INDICATL The Candidate identifies the correct Critical:

Grade #33 the xenon reactivity source selected:

graph (70% to 100% graph) in the RE Y[X] S [ ] N [ ] U [ ] Curve and Data Book. OP 3209B,

• 30% to 60% graph step 4.3.1.b

• 70% to 100% graph

• Program R7/R9 Comments:

, Cue: Candidate Writes "70% to 100%" on OP Critical:

Grade 3209B-002. Y [ ] S [ ] N[X] U [ J Comments:

Cue: , STEP IF performing xenon correction for the Candidate refers to "Xenon Reactivity Critical:

Grade #34 next 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period, PERFORM the After Trip 70% to 100%" (RE-C-02) and Y[X] S ( ] N ( ] U ( ]

locates the intersection of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> with OP 3209B, the 100% power curve. Enters "*2238 step 4.3.1.c OBTAIN the xenon reactivity expected pcm" on OP 3209B-002.

Number at the end of the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period and approximate. (Accept -2188 to RECORD as a negative value on OP It is acceptable for the applicant to use the corresponding TABLE (RE-C-02, page 2 of 5) associated with the "Xenon Reactivity After Trip 100%"curve.

However the acceptable range of values (-2188 to -2288 pcm ).shall remain the same. Cue: STEP CHECK box indicating calculation Candidate checks the box for 'Next 24 Critical:

Grade #35 provided for the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. hours' on OP 3209B-002. Y ( ] S [ ] N[X] U [ ] Comments:

Cue: i

--STEP IF performing hourly xenon corrections, Candidate recognizes that step 4.3.1.d Critical:

Grade #36 PERFORM the following

..... does not apply. Proceeds to step 4.3.2. Y [ ] S [ ] OP 3209B, N[X] U [ ] step 4.3.1.d STEP Refer To "Boron Worth vs Boron The Candidate identifies the correct Critical:

Grade #37 Concentration And Temperature" curve in graph (RE-F-03) in the RE Curve and Y[X) S [ ] the RE Curve and Data Book and Data Book, and uses the correct curve N [ J U [ ] OP 3209B, PERFORM the following:

(55rF).step 4.3.2.a IF maintaining no load Tavg, using 55rF curve, DETERMINE boron worth for the boron recorded in step 4.2.3 or 4.2.4 ENTER as a negative value on Cue: STEP Enters "*6.9" (-6.8 to -7.0) on OP Critical: #38 3209B-002.

Number is approximate.

Y[X] S [ N [ ] U [ Allow for minor curve interpolation STEP CALCULATE boron equivalent Xe (D!VIDE Candidate divides -2238 pcm by DBW of Critical:

Grade #39 xenon reactivity by differential boron worth) -6.9 pcm/ppm to determine a Boron Y[Xl] S [ ] and RECORD as a positive value on OP Equivalent Xe of 324 ppm (313 to 336 N [ J U [ ] OP 3209B, 3209B-002.

ppm). Records value and positive sign step 4.3.3 on OPS Form 3209B-002.

Number is approximate.

Allow for minor curve interpolation error. _ .... _.... _.__... _ .. -_... _..._-.... _.... -... -.... _.... _ .. _._._.... _.... __.... 16 I STEP #40 OP 32098, step 4.3.4 STEP #41 OP 32098, step 4.3.5 STEP #42 OP 32098, step 4.3.6 Refer To OP 3209B-002 and RECORD tht:: total required xenon free boron concentration determined in step 4.2.8. DETERMINE the required boron concentration as follows: SUBTRACT boron equivalent xenon from total required xenon free boron concentration.

ADD 60 ppm. Refer To OP 3209B-002 and RECORD resulting value as the total required Xe corrected CB. SUBTRACT total required xenon corrected boron concentration from actual boron concentration and RECORD value and sign (+/-) on OP 3209B-002.

Candidate refers step 4.2.8 of OP 002 and enters "1311 ppm". <<(1283 ppm to 1339 ppm) Candidate subtracts 324 ppm from 1311 ppm and adds 60 ppm to yield 1047 ppm (1007 ppm to 1086 ppm) as the value for total required Xe corrected Cs. Candidate records "1047 ppm" as total required Xe corrected C s on OP 002. Candidate subtracts 1047 ppm from 1150 ppm to yield +103 ppm (64 to 143 ppm). Critical:

Grade Y [ ] S [ ] N[X] U [ ] i i Critical:

Grade' Y[X] S [ J N [ ] U [ ] Critical:

Grade Y [ J S [ ] N[X] U [ ] , Critical:

Grade Y[X] S [ ] N [ ] U [ ]

--Candidate records "+103 ppm" on OP Critical:

I..;!rade 3209B-002. Y [ ] S [ ] N[X] U[J Comments:

Cue: STEP IF RCS boron concentration is less than Candidate recognizes that RCS boron Critical:

Grade #43 total required xenon corrected boron concentration is GREATER than total Y[X] S [ ] concentration, PERFORM the following

.... required xenon corrected boron N [ 1 U [ ] OP 32098, concentration and step 4.3.7 does not step 4.3.7 apply. Proceeds to step 4.3.8. Comments:

Cue: STEP Refer To the "Xenon Correction Log" of OP Candidate enters the date, time, required Critical:

Grade #44 3209B-002 and RECORD the following:

C B , RCS Cs and initials the Xenon Y [ ] S [ ] N[X] U [ ] Correction Log on line 1. OP 32098, Date step 4.3.8 Time for which xenon reactivity Total required xenon boron RCS boron concentration Initials of person Comments:

Cue: Candidate reports to the US that Critical:

Grade Shutdown Margin IS adequate for current Y [ ] S [ ] plant conditions with a xenon correction.

N[X] U [ J --....... ....... .......-.-....... ......._.-....... --......._---......._-......._-....... ......._-....... ----

---...;omments:

I Once the Candidate makes the report, pro". _d the following cue: Cue: I Termination Cue: The evaluation for this JPM is complete STOP TIME: ___

---2 VERIFICATION OF JPM JPM Number: NRC RO A.1.2 Date To achieve a satisfactory grade, ALL critical steps must be completed correctly.

If task is Time Critical, it MY§! be completed within the specified time to achieve a satisfactory grade. Time Critical Task? Yes No X Validated Time (minutes):

30 Actual Time to Complete (minutes):

Overall Result of JPM: SAT UNSAT Areas for Improvement I Comments:

2 STUDENT JPM Number: Initial Conditions:

Initiating Cues: NRC RO A.1.2 Revision:

Thirty minutes ago, the plant tripped from 100% steady-state equilibrium power after 2 months of operation.

Control rod M-4 failed to insert on the trip. All other plant components and systems responded as designed.

The plant is presently in MODE 3, and stable at normal temperature and pressure.

Other plant conditions are:

• ReS boron is 1150ppm (sample taken at 0700 today)

• Core Burnup is 10,500 MWD/MTU The US has directed you to calculate SHUTDOWN MARGIN for current plant conditions per OP 3209B, Shutdown Margin. An ST A review of your results is NOT required

---

,JPM Title: JPM Number: Initiated:

Reviewed:

Approved:

JOB PERFORMANCE MEASURE APPROVAL Perform a Manual RCS Leakage Calculation NRC RO A.2 Revision:

o Davel1ff 03/04/11 Developer Date s/b(ll T echnical Dat Supervisor.

Nuclear Trainin

SUMMARY

OF DATE DESCRIPTION -,._,.

---

JPM Facility:

MP3 Examinee:

JPM Number: NRC ROA.2 Revision:

1 Task Title: Perform a Manual RCS Leakage Calculation.

System: Equipment Control Time Critical Task: ) YES (X) NO Validated Time (minutes):

___3_0__ Task Number(s):

002-04-040 Applicable To: SRO X RO X PEO KIA Number: 2.2.12 KIA Rating: __3_.7_1_4_._1

__ Method of Testing: Simulated Actual Performance:

Performance:

Location:

Classroom:

x Simulator:

In-Plant:

Correctly perform a manual RCS water inventory balance to meet the T ask Standards:

requirements of TIS 4.4.6.2.1.d, "Reactor Coolant System, Operational Leakage." Required Materials:

SP 3601F.6 (procedures, equipment, etc.) Surveillance Form SP 3601 F.6 -001 Calculator SP 3601 F.6, Reactor Coolant System Water Inventory Measurement General

References:

(revision Surveillance Form SP 3601 F.6 -001, RCS Inventory

Balance, 003-01 X

• • • READ TO THE EXAMINEE I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this JPM will be satisfied.

You may use any approved reference material normally available in the Control Room, including logs. Make all written reports, oraL reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.

JPM WORKSHEET JPM Number: NRC RO Revision:

o Initial The plant is at 100% power and you are the Extra Licensed Operator on night shift. The PPC Program for RCS Leakage is malfunctioning and the RCS Leakage calculation is due. Computer Services has been notified.

Initiating The US has directed you perform a manual RCS water inventory balance using SP 360'1 F.6, Reactor Coolant System Water Inventory Measurement.

The on-shift ROs have gathered the initial and final data to be used in the manual calculation.

Simulator None * * *

• NOTES TO TASK PERFORMANCE EVALUATOR * * *

• Critical steps for this JPM are indicated by checking "y". For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly. When the student states what his/her simulated action/observation would be, read the appropriate "Cue". If necessary, question student for details of simulated actions/observations (Le. "What are you looking at?" or "What are you observing?"). Under NO circumstances must the student be allowed to manipulate any devices during performance of this JPM (in-plant only).

PERFORMANCE INFORMATION JPM Number: NRC RO Revision:

o Task Title: Perform a Manual RCS Leakage Calculation.

START TIME: ____

STANDARD Evaluator Provide copy of SP 3601F.6 and a copy of Surveillance Form SP 3601 F.6 -001 (with Data Table filled in) NOTE: to the candidate.

STEP VERIFY "General Prerequisites" Verifies "Test Authorized By" block is Critical:

Grade #1 completed.

signed on FORM SP 3601 F.6 -001. Y [ ] S [ ] N[X] U [ ] MB2B 2-9 Step 1 Reviews SP 3601 F.6, Section 3 Critical:

Grade PRECAUTIONS Y [ 1 S [ ] N[X] U [ ] Comments:

Cue: STEP Candidate locates section 4.3 of SP Critical:

Grade Locate correct procedure step. #2 Y [ ] S [ ] N[X] U [ ] Comments:

If the Candidate questions whether section 4.2 (Establish Initial Conditions for Manual Calculation) was performed, provide the following cue: Cue: The proper initial conditions for the manual calculation were established during the data gathering period. -.... -.... ---.... __ .... _ .... -_ .... _---.... .....-... _-.... _ .... _-_ .... _-.... -.... _ ....... _ .... __....._ .. _._._-_.... _ .. _ ...._.-.... _ ....... .... -.... -.... -.... _

STEP The following assumptions apply to a . Candidate reviews the NOTE. Critical:

Grade #3 manual RCS leakage calculation

..... y [ ] S [ ] U [ ] step Comments:

If the Candidate questions the validity of the assumptions in the NOTE, provide the following Cue: These assumptions were valid during the data gathering " Candidate recognizes that step 4.3.1 is Critical:

Grade RECORD applicable initial readings on SP complete. Y [ ] S [ ] 3601 F.6---001 from the computer report 3601 N[X] U [ ] step previously printed or from sources using the instruments Comments:

If the Candidate questions whether initial readings are from the computer report previously printed or from secondary sources, provide the following cue: Cue: Initial readings on the surveillance form are from secondary sources using the instruments listed. STEP Divert is necessary at EOL when dilution Candidate reviews the NOTE. Critical:

Grade #5 makeup is required to maintain Tavg Y [ ] S [ ] N[X] U [ 1 constant.step , , Cue: Candidate reviews step 4.3.2. Critical:

Grade IF VCT divert is required during leak rate Y [ ] S [ ] data gathering interval, PERFORM the N[XJ U [ ] step 4.3.2 following

... Comments:

When the Candidate questions whether VCT divert was required during the leak rate data gathering period, provide the following cue: -...._.-.... -.... _-.....-.... ...-.-.... _ ... __.....6 i Cue: VCT divert was not required.

STEP The normal required data gathering interval Candidate reviews the NOTE and Critical:

Grade #7 is four to six hours. This interval may be recognizes from the Data Table on FORM Y [ ] S [ ] changed by the SM/US, depending on why SP 3601 F.6 -001 that the data gathering N[X] U ( J step 4.3.3 the surveillance is being performed.

A data interval was 4.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />. NOTE 1 gathering interval less than four hours may provide less accurate leak rate results. Comments:

Cue: STEP If the computer is being used, the printed Candidate reviews the NOTE and Critical:

Grade #8 report contains initial and final readings recognizes that it does not apply. Y ( ] S [ ] step 4.3.3 N[X] U [ ] since the report has been setup to run NOTE Comments:

Cue: STEP WHEN the required data gathering interval Candidate recognizes that step 4.3.3 is Critical:

Grade #9 has elapsed, RECORD applicable final complete. Y [ ] S [ ] N[X] U [ ] readings on SP 3601 F.6---001 from the step 4.3.3 computer report or from secondary using local instruments Comments:

Cue: STEP If desired, calculations may be performed Candidate reviews the NOTE. Critical:

Grade #10 after restoration of plant equipment. Y [ ] S [ ] step 4.3.4 N[X] U ( ] NOTE 1 Comments:

Cue: _ .... 7

--Evaluator For the following steps involving calculatio, .... on the SP 3601 F.6 -001 Tables, if the Candidate questions NOTE: the validity of the assumptions listed on a given Table, provide the following cue: Cue: These assumptions were valid during the data gathering period. STEP Refer To SP 3601 F.6---001 and Candidate refers to Table 1A on SP Critical:

Grade #11 PERFORM the following:

3601F.6 -001, and records Data Table Y [ } S [ ] N[X] U [ ] values for initial and final PZR level and step CALCULATE and RECORD change in volume using initial and final data for following components in the Tables listed for

• Pressurizer, Calculation Table 1A Comments:

Candidate calculations should be accurate however, the number of significant digits is not part of the critical nature of calculations.

Candidate refers to Table 1 Bon SP Critical:

Grade 3601 F.6 -001, and determines the Y[X] S [ J U [ ] appropriate

'K' value for plant conditions N [ J is 74.15. Candidate records 74.15 as the value for Critical:

Grade 'K' on Table 1A. Y [ ] S [ ] N[X] U [ J Using the recorded values for initial and Critical:

Grade final PZR level and 'K', the Candidate Y[X] S [ ] N [ ] U [ ] calculates and records a change in PZR volume of 7.42 gallons. Comments:

The candidate may interpolate the value of 'K' between the pressure values of 2240 and 2250 psia. This is acceptable.

Interpolated value for 'K' is about 74.19. Cue: : 8 STEP

• VCT, Calculation Table 2 Candidate refers to Table 2 on SP Critical:

Grade #12 3601 F.6 -001, and records Data Table Y [ J s [ ] N[X] U [ ] values for initial and final VCT Using the recorded values for initial and Critical: final VCT level and the conversion factor Y[X] S [ N [ ] U [ ] 18.92 gal/%, the Candidate calculates and records a change in VCT volume of 185.42 g_allons.

Comments: .. , STEP RCS, Calculation Table 3 Candidate refers to Table 3 on Critical:

Grade'*#13 3601F.6 -001, and records Data Y [ ] S [ ] N[XJ U [ ] values for initial PZR pressure (CVPZRP) and initial calculated average temperature.

! Using the values recorded for initial Critical:

Grade pressure and temperature, the Candidate Y [ ] S [ ] N[X] U [ ] records initial specific volume obtained . from R*Time.

For R*Time: Unit 3 Top Menu> NSSS Menu >Reactivity Utilities Menu> Properties of Water. Then enter the initial values of pressure and temperature.

Evaluator If this JPM is administered in the classroom, provide the following Cue: ror initial and final specific volume use the value 0.02258 ft.:l Using the value recorded for initial Critical:

Grade specific volume, the Candidate calculates VeX] S [ ] N [ ] U [ ] and records initial density. _ --....._.... _ .... _.... .... _ .... _ .... _.... _.... _.... _.... -L...... .. __.__.__._. _ _.... _ ..

Candidate refers to Table 3 on SP Critical:

Grade 3601 F.6 -001, and records Data Table Y [ ] ! S [ ] N[X] U [ ] values for final PZR pressure (CVPZRP) and final calculated average temperature.

Comments:

Cue: Using the values recorded for final Critical:

Grade pressure and temperature, the Candidate Y [ ] S [ ] records final specific volume obtained N[X] U [ ] from R*Time. Comments:

Cue: Critical:

Grade Using the value recorded for final specific Y[X] S [ ] volume, the Candidate calculates and N [ ] U [ ] records final density. Comments:

Cue: Using the recorded values for initial and Critical:

Grade final density and the conversion factor Y[X1 S [ ] N [ ] U [ ] 1251.9 gal ft3 Ilbm, the Candidate calculates and records a change in RCS volume of 0.0 gailons. Comments:

Initial and final specific volume are effectively the same value, thus there is no change in RCS volume. Cue: STEP

• PRT, Calculation Table 4 Candidate refers to Table 4 on SP Critical:

Grade #14 Y [ ] S [ ] 3601 F.6 -001, and records Data Table N[X] U [ J values for initial and final PRT level. , Comments: , Cue: 10 Critical:

Grade Using the recorded values for initial and Y[X] S [ ] final PRT level and the conversion factor N [ ] U [ ] 126.57 gal/%, the Candidate calculates and records a change in PRT volume of 0.0 gal/ons. Comments:

Initial and final PRT levels are the same value, thus there is no change in PRT volume. Cue: i STEP POTT, Calculation Table 5 Critical:

Grade* Candidate refers to Table 5 on SP #15 Y [ ] S [ ] 3601 F.6 -001, and records Oata Table N[X] U [ ] values for initial and final POTT level. Comments:

Cue: I Critical:

Grade*Using the recorded values for initial and Y[X] S [ ] final PDTT level, the Candidate calculates N [ ] U [ J and records a change in POTT volume of 24.90 gallons. Comments:

Cue: I I STEP COTT, Calculation Table 6 Critical:

Grade* Candidate refers to Table 6 on SP #16 Y [ ] S [ ] 3601 F.6 -001, and records Data Table N[X] U [ ] values for initial and final COTT level. Comments:

Cue: Critical:

Grade Using the recorded values for initial and Y[X] S [ ] final COTT level, the Candidate N [ ] U [ ] calculates and records a change in CDTT volume of 15.60 gallons. Comments:

Cue: 11 STEP CALCULATE and RECORD volume of Critical:

Grade Candidate refers to Table 7 on SP #17 makeups using initial and final makeup Y [ ] S [ ] 3601 F.6 -001, and records Data Table step 4.3.4.b N[XJ U [ ] totalizer flow in Calculation Table 7. values for initial and final makeup totalizer flow. Comments:

Cue: Critical:

Grade Using the recorded values for initial and Y[X] S [ J final makeup totalizer flow, the Candidate N [ ] U [ ] calculates and records a total volume of makeup of 0.0 gallons. Comments:

No makeup occurred during the calculational period. , Cue: STEP CALCULATE volume diverted by Critical:

Grade Candidate recognizes that VCT divert #18 performing the following in Calculation Y [ ] S [ ] was NOT required during the leak rate step 4.3.4.c N[X] U [ ] Table 7 ..... data gathering period. Comments:

Cue: STEP CALCULATE total leakage from other Critical:

Grade Candidate reviews step 4.3.4.d. #19 known sources in Calculation Table 8 as Y [ ] S [ ] step 4.3.4.d N[X] U [ J follows: Comments:

When the Candidate questions whether there are other sources of leakage, provide the following cue: Cue: There is no leakage from other known sources. STEP CALCULATE and RECORD time difference Critical:

Grade Candidate refers to Table 9 on SP #20 from initial data collection to final data Y [ ] S [ ] 3601 F.6 -001, and records Data Table Step 4.3.4.e N[X] U [ ] collection in Calculation Table 9. values for the initial and final times associated with the data gathering period. Comments:

Cue: ,

Using the recorded values for initial and final times, the Candidate calculates and records a time difference of 240 minutes. Critical:

Y[X] N [ ] Grade S [ ] U [ ] Comments:

Cue: STEP #21 Step 4.3.4.f CALCULATE and RECORD total RCS leakage using the previously calculated volumes in Calculation Table 9. Candidate refers to Table 9 on SP 3601 F.B 001, and records the previously calculated volume changes associated with the PZR, VCT and RCS. Critical: Y ( J N[X] Grade s [ ] U ( ] Comments:

Makeup or VCT divert were NOT required during the leak rate data gathering period. Cue: Using the recorded values for volumes, the Candidate calculates and records a Critical:

Y[X] Grade S [ ] total RCS leakage of 192.84 gallons. N [ J U [ J Comments:

Cue: 1 STEP #22 Step 4.3.4.g CALCULATE and RECORD total RCS leak rate by dividing total RCS leakage by the time difference in Calculation Table

9. Using the recorded values for total RCS leakage (189.121 gal) and the time difference (240 min), the Candidate calculates and records a total RCS leak Critical:

Y[X] N [ ] Grade S [ ] U [ ] rate of 0.804 gal/min. Comments:

Cue: STEP CALCULATE and RECORD IDENTIFIED Candidate refers to Table 10 on SP Critical:

Grade #23 Step 4.3.4.h LEAKAGE by dividing the sum of the total collected leakage by the time difference in Calculation Table 10. 3601 F.B 001, and records the previously calculated volume changes associated with the PRT, PDTT and Y [ ] N[X] S [ ] U [ ] CDTT. Comments:

-_ ....13

-Cue: Using the recorded values for collected Critical:

Grade leakage (40.50 gal) and the time Y[X] S [ ) N [ ] U [ ] difference (240 min), the Candidate calculates and records an IDENTIFIED LEAKAGE of 0.169 gpm. Comments:

Cue: STEP CALCULATE and RECORD Candidate refers to Table 11 on SP Critical:

Grade #24 UNIDENTIFIED LEAKAGE by subtracting 3601 F.6 -001, and records total RCS Y [ J s [ ] N[X] U [ ] IDENTIFIED LEAKAGE from total RCS leak rate (0.804 gpm), IDENTIFIED Step 4.3.4.i leak rate and adding the change in PDTT LEAKAGE (0.169 gpm), the volume in Calculation Table 11. volume change (24.90 gal) and the difference (240 Cue: Using the recorded values above, the Critical:

Grade Candidate calculates and records an Y[X] S [ ] N [ ) U [ ] UNIDENTIFIED LEAKAGE of 0.739 gpm. Comments:

Cue: STEP IF leakage approaches either of the Candidate recognizes that Critical:

Grade #25 following limits, INITIATE a Condition UNIDENTIFIED LEAKAGE (0.739 gpm) Y [ S [ ] N[X] U [ ] Report to ensure compliance with is approaching 0.75 gpm, and a Condition Step 4.3.5 Maintenance Rule requirements:

Report needs to be initiated. IDENTIFIED LEAKAGE ---2.5 (25% of T.S. UNIDENTIFIED LEAKAGE ---gpm (75% of T.S. , -..._-....-... _---_ .... _ .... _ ....14 i Comments:

When the Candidate identifies the reQuirelllont for a CR, provide the following Cue: Another licensed operator will initiate the STEP IF UNIDENTIFIED LEAKAGE is Critical:

Grade Candidate calls or requests the US call#26 abnormally high, greater than 0.6 gpm Y [ ] S [ ] Engineering to inform them of the leak N[X) U [ ] or a step increase of 0.2 gpm, PERFORM rate.Step 4.3.6.a the following:

NOTIFY Engineering of leak rate.

Cue: All notifications to Engineering are STEP REVIEW computer printout or SP 3601 F.6 Critical:

Grade Candidate refers to Table 5 on SP #27 -001, Table 5, and DETERMINE the Y [ ) S [ ) 3601 F.6 -001, and reviews data N[X) U [ ] volume changes associated with the PDTT. associated with the PDTT volume Step STEP VERIFY all inventory changes to the Critical:

Grade Candidate requests from the US the #28 are related to RCS or CVCS changes as Y [ ] S [ ] status of the SI and RHR pumps during follows: N[X] U [ J the data gathering period. Step 4,3.6,c No SI pumps run No RHR pumps run 3DGS---V831, radioactive waste AOV58 leakoff 3DGS---V826, radioactive waste AOV54 leakoff 3GWS---V073, degasifier exchange A tube drain, 3GWS---V071, degasifier exchange B tube drain, Comments:

When the Candidate requests status of the SI and RHR pumps, provide the following No SI or RHR pumps were run during the measurement.

Critical:

Grade Candidate determines that 3DGS-V831 Y[X] S [ ] and V826 are supposed to be OPEN by N [ ) U [ ] using P&ID EM-107A or OP 3335A-001.

--Comments:

Cue: Critical:

Grade Candidate determines that 3GWS-V073 Y [ ] S [ ] and V071 are supposed to be closed by N[X] U [ J using P&ID EM-109A or OP 3337-001.

Comments: The Candidate should dispatch a PEa to determine the actual position of these valves. Once the PEa is dispatched, provide the following cue: Cue: 3DGS-V831 and V826 are OPEN. 3GWS-V073 and V071 are closed. Critical:

Grade ' Candidate determines that all inventory Y[X] S [ ] changes to the PDTT are NOT related to N [ ] U [ ] RCS orCVCS Comments:

Cue: STEP I F all PDTT inventory changes are RCS or Candidate reviews step 4.3.6.d and Critical:

Grade #29 CVCS related, Refer To SP 3601 F.6---001, recognizes that it does not apply. Y [ ] S [ ] N[X] U [ ] Table 12 .....Step 4.3.6.d Comments:

Cue: STEP IF PDTT inventory changes can not be Critical:

Grade Candidate takes action (or requests from #30 verified to be all RCS or CVCS related Y [ ] S [ ] the US) to enter the Table 11 value for N[X] U [ ] leakage, Refer To SP 3601 F.6---001, Table UNIDENTIFIED LEAKAGE in the SM log. Step 4.3.6.e 11, and RECORD LEAKAGE from Table 11 in the SM log the TIS Comments:

17

--Cue: STEP #31 Step 4.3.7 STEP #32 Step STEP #33 Step 4.3.8 Comments:

Cue: The value for UNIDENTIFIED LEAKAGE k. ,.Itered in the SM log. . IF leakage calculation was initiated for the Critical:

Grade Candidate recognizes that the last page required daily leakage determination (per Y [ ] S [ ] of the surveillance form needs to be N[X] U [ ] SP 3670.1---001), ATTACH a copy of the attached to the Control Room Rounds. last page of SP 3601 F.6---001, to SP 3670.1---001, "MODE 1---4 Daily and Shiftly Control Room Rounds." j I Page 7 of SP 3601 F.6 -001 is attached to the Control Room Rounds. If data is used from secondary sources Candidate reviews the NOTE. Critical:

Grade because of unavailability of computer Y [ ] S [ ] I N[X] U [ ] points, leak rate results may be less accurate or may trend differently than any computer generated leak rate results. IF leakage exceeds any of the following Critical:

Grade Candidate recognizes the need to refer to limits, Refer To C OP 200.15, "RCS Y [ ] S [ ] COP 200.15 to determine required N[X] U [ ] Leakage Trending and Investigation," and actions. PERFORM required actions .... When the Candidate requests C OP 200.15, provide the following cue: TERMINATION CUE: The US will refer to C OP 200.15. The evaluation for this JPM is concluded.

_ .......-.... __ ....._ ... __.... _-_.... -STOP TIME: ___ 18

--VERIFICATION OF JPM JPM Number: NRC RO A.2 Revision:

o Date Performed:

Student: Evaluator:

To achieve a satisfactory grade, ALL critical steps must be completed correctly.

If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade. Time Critical Task? Yes No X Validated Time (minutes):

30 Actual Time to Complete (minutes):

Overall Result of JPM: SAT UNSAT Areas for Improvement I Comments:

STUDENT JPM Number: Initial Conditions:

Initiating Cues: NRC RO A.2 Revision:

o The plant is at 100% power and you are the Extra Licensed Operator on night shift. The PPC Program for RCS Leakage is malfunctioning and the RCS Leakage calculation is due. Computer Services has been notified.

The US has directed you perform a manual RCS water inventory balance using SP 3601 F.6, Reactor Coolant System Water Inventory Measurement.

The on-shift ROs have gathered the initial and final data to be used in the manual calculation.

JOB PERFORMANCE MEASURE APPROVAL SHEET JPM Title: Actions and Expected Response for RMS Equipment failure Alarms JPM Number: NRC ROA.3 (2K7 ROA.3) Revision:

1 Initiated:

Dave Minnich 03/03/11 Developer Date Reviewed: , I Technical Re' er Date Approved:

I

SUMMARY

OF All & DESCRIPTION REV/CHANGE Updated JPM to revision 008-04 to OP 3362. Changed the nomenclature of the equipment failure light override to TRex designator.

---

JPM Facility:

-'--M__P_3____ Examinee:

JPM Number: NRC ROA.3 Revision:

1 Task Title: Actions and Expected Response for RMS Equipment failure Alarms. System: Radiation Control Time Critical Task: ( ) YES (X) NO Validated Time (minutes):

10 Task Number(s):

073-01-043 Applicable To: SRO X RO X PEO KIA Number: 2.3.5 KIA Rating: __2_.9__1._2_._9__ Method of Testing: Simulated Actual X Performance:

Performance:

Location:

Simulator:

X In-Plant:

Task Correctly determines the required actions for an RMS Equipment failure Alarm. Reguired Materials:

OP 3362, Radiation Monitor Display and Control System (rev. 00B-04) (procedures, equipment, etc.) OP 3353.MB2B-002-09, "RMS TROUBLE" (2-9), rev 000 Simulator General

References:

• • • READ TO THE EXAMINEE I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this JPM will be satisfied.

You may use any approved reference material normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.

JPM WORKSHEET JPM Number: NRC Revision:

Simulator Reset to any 100% power certified IC. Insert Annunciator override MB2B B-9 to "ON". Override the CMS22 RIC equipment failure light to 'ON' [(\0 RML00045 (3CMS*RE22 EQFAIL) to 'ON']. Initial The plant is at 100% power and you are the Extra Licensed Operator on shift. MB2B 2-9 "RMS TROUBLE" has alarmed. Initiatinq The US has directed you to respond to the annunciator.

• * *

• NOTES TO TASK PERFORMANCE EVALUATOR

• * *

• Critical steps for this JPM are indicated by checking "Y". For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly. When the student states what his/her simulated action/observation would be, read the appropriate "Cue". If necessary, question student for details of simulated actions/observations (Le. "What are you looking at?" or "What are you observing?"). Under NO circumstances must the student be allowed to manipulate any devices during the performance of this JPM (in-plant only).

PERFORMANCE INFORMATION JPM Number: NRC RO Revision: Task Title: Actions and Expected Response for RMS Equipment failure START TIME: ____ PERFORMANCE STANDARD STEP Obtains OP 3353.MB2B and refers to Critical:

Grade Obtain proper Annunciator Response #1 "RMS TROUBLE" (2-9). Y [ ] S [ ] Procedure.

N[X1 U [ ] Evaluator The Candidate may refer to the RMS alarm display monitor on the RO/BOP desk to determine alarm NOTE: source. If so, provide cue card #1 (where the events are listed) and verbally give the following The screen displays the following events. STEP DETERMINE the cause of RMS trouble Candidate proceeds to the RMS Console. Critical:

Grade #2 indication at RMS Control Room Operator If the Candidate observes the bottom Y [ ] S [ ] N[X] U [ ]

the monitor screen to determine the MB2B 2-9 specific alarm. Step 1 Comments:

When the candidate observes the RMS Console monitor screen, provide cue card #2 (where the events are listed) and verbally give the following cue: Cue: The yellow alarm line displays the following events. Evaluator Any active RMS alarm will show up at the bottom of the RMS console monitor screen, regardless of what NOTE: else is displayed.

--..... ....-.-.......---.... .......-.......--.... _---.......-......_-....

Candidate proceeds to the RMS Console Critical:

Grade and calls up the status grid Y [ ] S [ ] N[X] U [ ] and/or data base for 3 CMS*RE22 and determines that 'filter step' is in alarm. Evaluator On the status grid function, all the RMUs are shown with a corresponding number that indicates NOTE: status. '3' correlates to an equipment failure. If Candidate calls up status grid, provide the following Cue: A blue '3' is displayed for CMS22 2 monitor status.

On the 3CMS*RE22 particulate database display, top right, there is indication of whether the RMU is online, reachable and if there are any alarms in. When the Candidate calls up the database display and observes the top right of the screen, provide the following cue: I Cue: Screen shows a yellow 'ALARM'. Evaluator On the 3CMS*RE22 particulate database display, there is an equipment failure column. When NOTE: Candidate observes the equipment failure column, provide the following Cue: Filter step indicates

'yes' and is yellow for alarm status. STEP IF alarm is due to equipment failure, Critical:

Grade Candidate obtains and refers to OP 3362, #3 To OP 3362, "Radiation Monitor System Y [ ] S [ ] Section 4.13, Equipment Failure Alarms. MB2B N[X] U [ ] Display and Control," and TAKE required Step 2 actions for equipment failure alarms. Comments:

Cue: STEP Candidate refers to OP 3362, Attachment Critical:

Grade Refer To Attachment 6 and PERFORM 6 and verifies that 3CMS*RE22 is listed. Y[X] S [ ] the following:

OP N [ ] U [ ] Section 4.13 CHECK monitor number is listed. Step4.13.1.a Comments:

Cue: 6 STEP IF monitor is listed, DETERMINE applicable

1. 5 "Trouble Response(s)." Step 4.13.1.b Comments:

Cue: STEP PERFORM applicable Trouble #6 Response(s)" listed. Step 4.13.1.c Evaluator NOTE: provide the following cue: Cue: Yes, perform the applicable trouble responses.

The Candidate may ask whether the US desires him/her to perform the applicable trouble responses.

If so, STEP NOTIFY Instrument and #7 Department to check OP AU. Action Comments:

Cue: All notifications to I & C are complete.

STEP NOTI FY Health Physics Department for #8 area monitoring and sampling as required.

OP AU. Action Comments:

Cue: All notifications to Health Physics are complete. Candidate refers to Attachment 6 and determines that for 3CMS*22, trouble responses 1, 2. 3, 6, 7, 10. and 12 are required.

Candidate refers to Attachment 6 begins to perform the identified responses.

Critical:

Grade Y[X1 S [ N [ ] U [ Critical:

Grade Y [ ] S [ N[X] U [ Candidate notifies I &C that 3CMS*RE22 has an equipment failure alarm and to check the monitor. Telephone call is adequate for this notification.

Candidate notifies Health Physics that 3CMS*RE22 has an equipment failure alarm and to conduct necessary monitoring and sampling.

Telephone call is adequate for this notification.

Criticpl:

Grade Y [ ] S [ N[X] U [ . Critical:

Grade Y [ ] S [ N[X] U [ i

--STEP NOTIFY Chemistry Department for Candidate notifies Chemistry Department Critical:

Grade #9 sampling medium. that 3CMS*RE22 has an equipment Y [ ] S [ ] OP 3362 failure alarm and to ready appropriate N[X] U [ J AU. 6 Action 3 sampling medium. Telephone call is adequate for this notification.

Comments:

Cue: All notifications to Chemistry are complete.

STEP IF a filter step alarm is recorded, ATTEMPT Informs the US that an attempt must be Critical:

Grade #10 to step the filter as follows: made to step the 3CMS*22 filter at the Y [ ] S [ ] OP 3362 N (X] U [ ] 'RIC'.Action 6 IF 3CMS*RE22 filter needs to be stepped, Go To Section 4.16. Candidate proceeds to Section 4.16. Critical:

Grade Y[X] S [ ] N [ ] U [ ] Comments:

Cue: If required, as US, direct the Candidate to attempt to step the filter. STEP When the radiation monitor filter is Candidate reviews the NOTE. Critical:

Grade #11 manually stepped, the monitor will be Y [ ] S [ ] inoperable until the unit finishes the N[X] U [ ] OP 3362, process which includes a new calculation of Section NOTE background and returns to normal readings for plant conditions.

This can take up to Candidate informs the US that when the Critical:

Grade filter is stepped, the monitor will be Y [ ] S [ ] N[X] U [ ] inoperable for up to two hours. Comments:

8 Cue: Acknowledge as the US. STEP #12 Step 4.16.1 Refer to the following and PERFORM applicable ACTIONs:

• TIS 3.3.3.1, "Radiation Monitoring for Plant Operations" Candidate informs the US to refer to TIS 3.3.3.1 and 3.4.6.1, and perform required actions. Critical:

Y[X] N [ J Grade S [ ] u [ ] I

• TIS 3.4.6.1, "Leakage Detection Systems" Comments:

When the Candidate informs the US to refer to Tech Specs, provide the following cue: Cue: The US will refer to Tech Specs. STEP #13 Step 4.16.2 Comments:

Cue: STEP #14 Step 4.16.3 Comments:

Cue: STEP #15 Step 4.16.4 At RIC-8B, 3CMS*RIY22A1B KERIC, PLACE keyswitch to "ENABLE." PRESS "STP -2 ENT." CHECK "PROC FUNC" light cycles on and then off. Candidate obtains the key from the simulator key locker for 3CMS*22 and proceeds to the 3CMS*22 'RIC'. At the 3CMS*22 'RIC', Candidate inserts the key and turns the keys witch to "ENABLE." On the 'RIC' keyboard, Candidate presses 'STP' (step), followed by 12', followed by lENT' (enter). Candidate observes the "PROC FUNC" (process function) light. Critical:

Y[X] N [ ] Critical:

Y[X] N [ ] Critical:

Y[X] N [ ] Critical: Y [ ] N[X] Grade S [ ] U [ ] Grade S [ ] U [ ] Grade S [ J U [ ] Grade S [ ] U [ ] 9 Comments:

When the Candidate monitors the process runction light, provide the following cue: Cue: The process function light cycles on and then off. STEP At RIC-8B, 3CMS*RIY22A1B KERIC, At the 3CMS*22 'RIC', Candidate turns #16 PLACE keyswitch to "DISABLE." the keyswitch to "DISABLE", removes and returns the key to the key locker. Step 4.16.5 Comments:

Removing and returning the key is not part of the critical nature of this step. Cue: STEP WHEN two hours have elapsed AND Candidate informs the US that two hours #17 monitor readings have stabilized for plant must elapse and monitor readings conditions, Refer to the following and stabilize before TIS 3.3.3.1 and 3.4.6.1 Step 4.16.6 PERFORM applicable ACTIONs ...... can be exited. Comments:

When the Candidate informs the US, provide the following cue: Cue: The US will monitor the time from stepping the filter and then refer to Tech Specs. Candidate returns to Attachment 6 to perform the rest of the identified trouble responses (7,10, and 12). Comments:

Cue: STEP IF a radiation monitor indicates "OFF-Candidate proceeds to the RMS Console #18 LINE," DECLARE the radiation monitor and calls up the status grid function or INOPERABLE and LOG into all applicable data base for 3CMS*RE22 and OP 3362 LCOs. determines that the Rad Monitor does not Att Action 7 indicate Comments:

Cue: 10 Critical:

Grade Y[X] S [ ] N [ ] U [ ] Critical: Y [ ] S [ N[X] U [ .. Critical:

Grade Y [ ] S [ ] N[X] U [ ] Critical:

Grade Y [ ] S [ ] N[X] U [ ]

I STEP Critical:

Grade Refer To TIS 3.3.3.1 and Table 3.3-6, Candidate informs the US that TIS#19 Y[X] S [ ] "Radiation Monitoring Instrumentation for 3.3.3.1, "Radiation Monitoring OP 3362 N [ ] U [ ] Att.6 Plant Operations," and PERFORM Instrumentation for Plant Action 10 applicable actions. must be referred Comments:

Cue: Acknowledge the Candidate's report and reply that the US is referring to TIS 3.3.3.1. STEP Candidate informs the US that TIS Critical:

Grade Refer To TIS 3.4.6.1, "Reactor Coolant #20 3.4.6.1, "Reactor Coolant System Y[X] S [ ] System Leakage Detection Systems," and OP 3362 N [ ] U [ ] Leakage Detection Systems," must be AU. 6 PERFORM applicable Action 12 referred Comments:

Cue: Acknowledge the Candidate's report and reply that the US is referring to TIS 3.4.6.1. STEP Candidate Reports Task Completion.

Candidate reports to the US that the Critical:

Grade #21 applicable trouble responses have been Y [ ] S [ ] N[X] U [ ] performed.

Comments:

Cue: TERMINATION CUE: The evaluation for this JPM is concluded.

STOP TIME:

--1 VERIFICATION OF JPM COMPLETION JPM Number: NRC RO A.3 Revision:

Date Performed:

Student: Evaluator:

To achieve a satisfactory grade, ALL critical steps must be completed correctly.

If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade. Time Critical Task? Yes No X Validated Time (minutes):

10 Actual Time to Complete (minutes):

Overall Result of JPM: SAT UNSAT Areas for Improvement I Comments:

STUDENT HANDOUT JPM Number: NRC RO A.3 Revision:

1 Initial Conditions:

The plant is at 100% power and you are the Extra Licensed Operator on shift. MB2B 2-9 "RMS TROUBLE" has alarmed. Initiating Cues: The US has directed you to respond to the annunciator.

13 l JOB PERFORMANCE MEASURE APPROVAL JPM Title: JPM Number: Initiated:

Reviewed:

Approved:

Administrative Requirements for Shift Manning Activities

-Minimum Crew Complement and Working Hour Limitations.

NRC SRO A.1.1 (JPM-197)

Dave Supervisor, Nuclear Training Revision:

o 04/20/11 Date } Date I Date

SUMMARY

OF DATE DESCRIPTION I

._. I

---

JPM Facility:

MP3 Examinee:

JPM Number: NRC SRO A.1.1 Revision:

o Task Title: Administrative Requirements for Shift Manning Activities

-Minimum Crew Complement and Working Hour Limitations.

System: Conduct of Operations Time Critical Task: ) YES (X) NO Validated Time (minutes):

xx Task Number{s):

119-03-009 Applicable To: SRO X RO PEO KIA 2.1.5 KIA Rating: __----'3...;..

.. 9----'__ Method of Simulated Actual X Performance:

Performance:

Classroom:

X Simulator:

In-Plant:

Task Standards:

Examinee correctly determines minimum shift crew composition requirements and 10CFR26 Fatigue Rule limititations.

Required Materials: (procedures.

eqUipment.

etc.) General

References:

Unit 3 Technical Specifications LI-AA-700, Fatigue Management and Work Hour Limits for Covered Workers. SY-AA-FFD-101, Fitness for Duty Program. Calculator Unit 3 Technical Specifications LI-AA-700.

Fatigue Management and Work Hour Limits for Covered Workers. 3

--*** READ TO THE EXAMINEE I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this JPM will be satisfied.

You may use any approved reference material normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.

JPM WORKSHEET JPM Number: NRC RO Revision:

o Initial Conditions:

The plant is in MODE 1 and stable at 100% power. You are the Unit Supervisor on day shift. Several Licensed Operators are on vacation and the crew is at minimum staffing.

The crew began its 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shift at 0600. The Balance of Plant Operator has become ill early (0630) on this last day of day Shift and has been sent home, which places the shift below minimum staffing levels. Current time and Date is 0630 on Wednesday, 13 July 2011. Initiating Cues: The SM has directed you to determine how soon a relief must be found. Simulator Requirements:

None * * *

• NOTES TO TASK PERFORMANCE EVALUATOR * * *

• Critical steps for this JPM are indicated by checking "Y". For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly. When the student states what his/her simulated action/observation would be, read the appropriate "Cue". If necessary, question student for details of simulated actions/observations (Le. "What are you looking at?" or "What are you observing?"). Under NO circumstances must the student be allowed to manipulate any devices during the performance of this JPM (in-plant only).

___ _ PERFORMANCE INFORMATION JPM Number: Task Title: NRC RO A.1.1 Revision:

0 Administrative Requirements for Shift Manning Activities

-Minimum Crew Complement and Working Hour Limitations.

START TIME: PERFORMANCE STANDARD Evaluator When requested, provide the candidate a copy of Unit 3 Technical Specifications.

NOTE: STEP Obtains and refers to proper procedure.

1. 1 Comments:

Cue: STEP Refer To Technical Specifications, Section #2 6, ADMINISTRATIVE CONTROLS, TIS 6.2.2 for FACILITY STAFF; to determine MP3 minimum shift crew composition. Data Table NOTE 3 Applicant obtains and refers to a copy of MP3 technical Specifications.

Candidate Refers to T.S. 6.2.2.a for FACILITY STAFF and determines the LCO is specifed as follows: "Each on-duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1" Candidate refers to Table 6.2-1 and correctly determines that the minimum shift crew composition for the RO position is 2 individuals for MODE 1. 5 Critical:

Grade Y [ ] S [ ] N[X] U [ ] Critical:

Grade Y [ ] S [ ] N[X] U [ 1 Critical:

Grade Y [ ] S [ ] N[X] U [ ]

--Comments:

Cue: 'The shift crew composition may be one Candidate determines that another RO Critical:

Grade STEP less than the minimum requirements of must report within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. Y[X] S [ ] #3 Table 6.2-1 for a period of time not to N [ J u [ ] exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate M Tech unexpected absence of on-duty shift Specs members provided immediate action is Ta b I e taken to restore the shift crew composition 6.2.1 to within the minimum requirements Table Comments:

When the SRO candidate states or otherwise indicates recognition of the 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> limitation, provide the candidate with Handout 2. Comments:

When requested, provide the candidate a copy of the following:

• SY-AA-FFO-101, Fitness for Duty Program .

• LI-AA-700, Fatigue Management and Work Hour Limits for Covered Workers . The Candidate may evaluate Operator responses in any order. If the Candidate attempts to contact other 'additional' individuals, provide the following cue: Cue: No additional Operators will answer the phone or reply to a page. L...--.

3.18 STEP Determine if Operator 1 can be called in, #4 and if not, determine the reason.

101, Fitness For Duty Call-Out Process EXHAUST all other options prior to requiring an individual who has consumed a/cohol within the previous five hours to report for work. Comments:

Candidate refers to the response of Operator 1 and determines that Operator 1 is NOT available due to the consumption of alcoholic beverages within the past 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />. (SY 101 ). Critic'ill:

Grade Y[X] S [ N [ J U [ If the Candidate requests additional information from Operator 1, provide any of the following cues as requested:

Cue: Closing time was 0230./1 had at least 5 drinks I Started drinking at 210011 weigh about 180 pounds. STEP Determine if Operator 5 can be called in, #5 and if not, determine the reason.

101, 3.17 Fitness For Duty Self Reporting IF notified of the legitimate use of prescription or over-the-counter drugs which may adversely affect an individual's ability to perform work duties, THEN PERFORM the following:

a. CONTACT the FFDA for evaluation

..... Comments:

Critical:

Grade Candidate refers to the response of Y[X] S [ J Operator 5 and determines that Operator N [ ] U [ ] 1 is NOT available due to the use of the-counter medication that may affect his/her ability to perform required duties. (SY-AA-FFD-101 ) Although not explicitly restricted by SY-M-FFD-1 01, an individual's availability if using over-the-counter medication that may affect his/her ability to the required duties, needs to be evaluated prior to assuming those duties. -_.... _... 7 Determine if Operator 3 can be called in, #6 and if not, determine the reason. Determine if Operator 4 can be called in, #7 and if not, determine the reason.

section Work Hours, Breaks, and Days Off APPLY the following limits to individuals regardless of unit status: No more than 16 work hours in any rolling 24-hour period At least a 10-hour break between successive work periods Comments:

Cue: Candidate refers to the response of Operator 3 and determines that Operator 3 is available.

Even though although the Operator does not want to come in , he/she is the only individual that can assume shift duties. Candidate refers to the response of Operator 4 and determines that Operator 4 is NOT available because he/she would work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in any rolling 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period or because he/she would NOT have a break of at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> between successive work periods. AA-700) [6 hours of night shift, plus 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of day shift (18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br />)]. Also, the time between 0000 and 0710, is less than 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> (7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />, 10 minutes)].

Critical:

Grade VEX] S [ ] N [ ] U [ ] I Critical:

Grade Y[X] S [ ] N [ ] U [ ]

STEP Determine if Operator 5 can be called in, #8 and if not, determine the reason.

section Work Hours, Breaks, and Days Off APPL Y the following limits to individuals regardless of unit status: No more than 72 work hours in any rolling 168-hour (7 -day) period Comments:

Cue: Candidate refers to the response of Operator 5 and determines that Operator 5 is NOT available because he/she would work more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any rolling 168 hour0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br /> period. (1I-AA-700)

[4, twelve hour night shifts (48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />), plus 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> of holdover Monday morning (49.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />), plus 2, twelve hour day shifts on 13 and 14 July (73.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />) TERMINATION CUE: The evaluation for this JPM is concluded.

Critical:

Grade Y[X] S [ ] N [ ] U [ ] I STOP TIME: __

--VERIFICATION OF JPM COMPLETION JPM Number: NRC RO A.1.1 Revision: Date To achieve a satisfactory grade, ALL critical steps must be completed correctly. If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade. Time Critical Task? Yes No X Validated Time (minutes):

xx Actual Time to Complete (minutes):

Overall Result of JPM: SAT UNSAT Areas for Improvement I Comments:

EXAMINEE HANDOUT 2 DO NOT provide this handout until cued Initial The SM directed you to call Licensed Operators that are not on vacation to determine availability to take the shift. Their responses follow: .---.. Response-----_._-c--.----------.

Operator "I'm on the last day of my seven days off. It was my wife's birthday and we went to Margaritaville's last night to celebrate.

I had some cocktails until closing time and my wife drove home. I'll come in if you want me to. usually takes me 45 minutes to get to work, but I can be there in about Operator "I have a bad cold and just took some Nyquil but, if you really need me, I can be there in about an hour and 15 minutes. I just need to clean up before I come in."

Operator "It's the last day of my seven days off. I've been sleeping most of the day because I start Night Shift tomorrow night. There's a ball game on TV and I'd rather not come in, but, if you can't find anyone else, then I can be there In about an hour, if I really have to." Operator "I was called in to work control for 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> on Night Shift last night (got off at 2400) and I start Night Shift tomorrow night. IF I hurry, I could probably be there in about 40 minutes." Operator "I worked my fourth day of night shift on Sunday. I was held over about an and a half following the last night shift to discuss a performance issue management.

I start day shift tomorrow.

I can be there in about 30 Initiating Determine the following:

• From the list provided, who is eligible to assume shift duties? For those who are NOT eligible, what is the reason? 11

STUDENT HANDOUT JPM Number: NRC RO A.1.1 Revision:

oInitial Conditions:

The plant is in MODE 1 and stable at 100% power. You are the Unit Supervisor on day shift. Several Licensed Operators are on vacation and the crew is at minimum staffing.

The crew began its 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shift at 0600. The Balance of Plant Operator has become ill early (0630) on this last day of day Shift and has been sent home, which places the shift below minimum staffing levels. Initiating Cues: Current time and Date is 0630 on Wednesday, 13 July 2011. The SM has directed you to determine how soon a relief must be found.

JPM Title: JPM Number: Initiated:

Reviewed:

Approved:

JOB PERFORMANCE MEASURE APPROVAL SHEET Review a Surveillance for RCS Leakage, Analyze Results and Take Appropriate Action. NRC SRO A.1.2 Dave

/iv'I 1 Technical Reviewer Supervisor, Nuclear Tral g Revision:

o 03/16/11 Date 'nlte I

SUMMARY

OF DATE DESCRIPTION I REV/CHANGE -.

---

JPM Facility:

MP3 Examinee:

JPM Number: NRC SRO A.1.2 Revision:

o Task Title: Review a Surveillance for RCS Leakage, Analyze Results and Take Appropriate Action. System: Equipment Control Time Critical Task: ) YES (X) NO Validated Time (minutes):

___3-,-0Task Number(s):

Applicable To: SRO X RO PEO __KIA Number: 2.1.7 KIA Rating: ___4,-,-.7__Method of Testing: Simulated Performance:

Performance:

Location:

Classroom:

X Simulator:

In-Plant:

Review and correctly disposition the surveillance for RCS Task Standards:

Inventory Balance. Reguired Materials:

SP 360'IF.6 (procedures, equipment.

etc.) Completed surveillance Form SP 3601 F.6 -001 Calculator SP 3601 F.6, Reactor Coolant System Water Inventory Measurement General

References:

(revision Surveillance Form SP 3601 F.6 -001, RCS Inventory

Balance, 003-01 Unit 3 Technical 3 X

• • • READ TO THE EXAMINEE *** I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this JPM will be satisfied.

You may use any approved reference material normally available in the Control Room, including logs. Make all written reports, oral : reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.

JPM WORKSHEET JPM Number: NRC RO Revision:

o Initial The plant is at 100% power and you are the Unit on shift. The PPC RCS Leakage Program is and the RCS Leakage calculation is due. Computer has been notified.

You directed the Reactor Operator perform a manual RCS water inventory balance using 3601 F.6, Reactor Coolant System Water Measurement, which he just Initiating Review and disposition the completed Surveillance Form 3601 F.6 -001, ReS Inventory Simulator None * * *

• NOTES TO TASK PERFORMANCE EVALUATOR * * *

• Critical steps for this JPM are indicated by checking ny". For the student to achieve satisfactory grade, ALL critical steps must be completed When the student states what his/her simulated action/observation would be, read appropriate If necessary, question student for details of simulated actions/observations (Le. 'What you looking at?" or "What are you Under NO circumstances must the student be allowed to manipulate any devices during performance of this JPM (in-plant __4 PERFORMANCE INFORMATION JPM Number: NRC RO A.1.2 Revision:

0 Task Title: Review a Surveillance for RCS Leakage, Analyze Results and Take Appropriate Action. START TIME: ____ PERFORMANCE STANDARD Evaluator Provide copy of SP 3601F.6 and a copy of the completed Surveillance Form SP 3601F.6 -001 (with math NOTE: error) to the Candidate.

STEP #1 Review 'Specific Information' blocks on the surveillance cover sheet. "General Prerequisites" . Verifies "Prerequisites Completed" block is initialed on FORM SP 3601 F.6 -001. Critical: Y [ J N[X] Grade s [ ] U [ ] Verifies "Precautions Noted" block is Critical:

Grade initialed on FORM SP 3601 F.6 -001. Y [ ] S [ ] N[X] U []

• Verifies "Test Authorized By" block is signed on FORM SP 3601 F.6 -001. Critical: Y [ ] N[X] Grade S [ ] U [ J

• Comments:

If the Candidate questions the validity of the assumptions in the NOTE prior to step 4.3.1 of SP 3601 F.6, or

• any of the assumptions listed in the various Tables of the surveillance form, provide the following cue: Cue: These assumptions were valid during the data gathering period. * ., -._-.... -.... 5 STEP #2 001 Pg 2 of 7 Comments:

Review the Data Table. Candidate observes that initial and final data are filled in for the 3 channels of 'PZR LVL'. Critical: Y [ J N[X] Grade S [ J U [ ] Cue: , Data Table NOTE 3 Candidate observes that computer point 'CVPZRP' is available, entered as average narrow range PZR pressure, and therefore N/A entered in "NARROW RANGE PRES" indication blocks. Critical: Y [ ] N[X] Grade S [ ] U [ ] Comments:

Cue: Data Table NOTES 4, 5 Comments:

Candidate observes that since ReS temperature is > 530 of, data is entered in the "LOOP 1-4 AVG TEMP" blocks for calculated average temperature.

The blocks for "COLD and HOT LEG WR TEMP" are N/A'd. Critical: Y [ ] N[X] Grade S [ ] U [ ] Cue: Data Table NOTE 6 Candidate observes that since RCS pressure is above 1,700 psia, data blocks for "WIDE RANGE LOOP PRES" are N/A'd. Critical: Y [ ] N[X] Grade S [ ] U [ J Comments:

I Cue: -........... ........_ .....___ --___ I Candidate observes that initial and final Critical:

Grade I data are filled in for PRT, VCT, PDTT, Y [ ] S [ ] Data Table N[X] U [ ] and CDTT tank levels, as well as Make-NOTE 6 up Totalizer and the start and end time of the data gathering interval.

Comments:

I Cue: I STEP #3 Review Calculation Table 1A: tlV PZR Candidate observes that Data Table values for initial and final PZR level and Critical: Y [ ] Grade S [ ] 001 pressure are entered, and that the correct N[X] U [ J Pg 3 of 7 Table 1 B value for 'K' (74.15) for current plant conditions is entered on Table 1 A. , Comments:

Cue: Candidate reviews the calculation for the Critical:

Grade change in PZR volume (bVPZR ) and Y [ ] S [ ] N[X] U [ ] determines the calculation is performed correctly.

Comments:

Cue: STEP Candidate observes that Data Table Critical:

Grade Review Calculation Table 2: Ll VVCT#4 values for initial and final VCT level are Y[X] S [ ] 3601F.6-N [ ] U [ ] 001 entered, but the final value of VCT level Pg 4 of 7 entered is incorrect.

Comments:

The final value of VCT level as entered on the Data Table is .12.2, as opposed to the incorrect value of .§2.2 entered on Table 2 (LlV VCT). -_L-----------------....-_ ...7

---

Cue: Candidate reviews the calculation for the Critical:

Grade change in VCT volume (tlVVCT) and Y[X1 S [ ] N [ ] U [ ] determines the calculation is performed correctly, but with the incorrect value of final VCT level. Therefore the change in VCT volume is incorrect.

Evaluator Once the Candidate recognizes that the incorrect value of final VCT level was used in the calculation, Note: I he/she may direct the 'RO' to reperform the surveillance again using the correct value. This is satisfactory.

If so provide the following cue: Cue: Here is the redone completed surveillance form up through calculating UNIDENTIFIED LEAKAGE. Evaluator I F the Candidate intends to continue the surveillance review, provide the following Cue: You have directed the Reactor Operator to reperform the manual RCS water inventory Here is the redone completed surveillance form up through calculating UNIDENTIFIED I STEP Candidate observes that Data Table Critical:

Grade Second review Calculation Table 2: #5 values for initial and final VCT level are Y [ ] S [ ] tlVVCTN[X] U [ ] correctly entered.001 Pg 4 of 7 Comments:

Cue:

Candidate reviews the calculation for the Critical:

Grade change in VCT volume (tl VVCT) and Y [ ] S [ ] N[X] U [ ] determines the calculation is performed correctly.

Comments:

8

---Cue: Candidate observes that initial and final Critical:

Grade Review Calculation Table 3: !1VRCSData Table values for PZR pressure y [ ] S [ ] N[X] U [ ] (CVPZRP).

calculated average 001 Pg 4 of 7 temperature and specific volume are entered. Comments:

Cue: Candidate reviews the calculation for Critical:

Grade initial and final density (p) and determines Y [ ] S [ ] N[X] U [ ] the calculations are performed correctly.

Comments:

Cue: Candidate reviews the calculation for the Critical:

Grade change in RCS volume (!1V Rc s) and Y [ ] S [ ] N[X] U [ ] determines the calculation is performed correctly.

Comments:

, Cue: Candidate observes that Data Table Critical:

Grade Review Calculation Table 4: !1 V PRT#7 values for initial and final PRT level are Y [ ] S [ ] N[X] U [ ] 00 entered, and reviews the calculation for Pg 5 of the change in PRT volume (!1V PR T) and determines the calculation is performed correctly.

Comments:

i Cue: ! i Candidate observes that Data Table Critical:

Grade Review Calculation Table 5: dVPDTT ! #8 values for initial and final PDTT level are Y [ ] S [ ] N[X] U [ ] entered, and reviews the calculation for Pg 5 of the change in PDTT volume (dV POTT) and determines the calculation is performed correctly.

Comments:

Cue: Candidate observes that Data Table Critical:

Grade Review Calculation Table 6: dV CDTT#9 values for initial and final CDTT level are Y [ ] S [ ] entered, and reviews the calculation for N[XJ U [ ] Pg 5 of the change in CDTT volume (d V COTT) and determines the calculation is performed correctly.

Comments:

Cue: STEP Review Calculation Table 7: VMakeup and Candidate observes that Data Table Critical:

Grade #10 V Divert values for initial and final makeup totalizer Y [ ] S [ J flow are entered, and reviews the N[X] U [ ] 001 Pg 6 of 7 calculation for the volume of makeup and determines that Makeup did not occur during the data gathering interval.

I Comments:

Cue: 10 Candidate recognizes that the portion of Critical:

Grade* Table 7 that addresses the total volume Y [ J S [ J N[X] U [ ] diverted has been NA'd by the RO. i Comments:

If the Candidate questions whether VCT divert was required during the leak rate data gathering period, provide the following cue: Cue: VCT divert was not required.

STEP Review Calculation Table 8: Other Candidate recognizes that Calculation Critical:

Grade #11 Source of Leakage Table 8 for other sources of leakage has Y [ ] S [ ] 3601F.6* N[X] U [ ] 001 been NA'd by the Pg 6 of Comments:

If the Candidate questions whether there are other sources of leakage, provide the following cue: Cue: There is no leakage from other known sources. Comments:

A detailed review of the calculation is not required to meet the critical nature of the step; only that Total RCS Leakage and Total RCS Leak Rate will not be accurate values. Cue: STEP Review Calculation Table 9: liTime, Total Candidate observes that Data Table Critical:

Grade #12 RCS Leakage, and Total RCS Leak Rate values for initial and final times are Y [ ] S [ ] 3601F.6-U [ ] entered and reviews the calculation for N[X]Pg 6 of 7 li Time and determines the calculation performed Comments:

Cue: L..

Candidate observes that previously Critica\:

Grade calculated Table volumes are entered for Y [ ] S [ ] N[X] U [ ] the total RCS leakage calculation.

Comments:

Cue: Candidate reviews the calculation for Critical:

Grade Total RCS Leakage and determines Y [ ] S [ ] N[X] U [ ] calculation is performed correctly.

Comments:

Cue: Candidate reviews the calculation for the Critical:

Grade Total RCS Leak Rate and determines the Y [ ] S [ ) N[X] U [ ] calculation is performed correct/yo Comments:

The candidate may express concern about the significantly high total RCS Leak Rate (0.961 gpm) and desire to initiate immediate action. If so provide the following cue: Cue: Continue with your review. STEP Review Calculation Table 10: Candidate observes that previously Critical:

Grade #13 IDENTIFIED LEAKAGE calculated collected volumes and Time Y [ ] S [ ] 001 are entered for the identified leakage N[X] U [ ] Pg 7 of 7 calculation. -_.... __.. __.... _.-.... _._...... _-_.... --.... ........-.......12 I Candidate reviews the calculation for IDENTIFIED LEAKAGE and determines the calculation is performed correctly.

Critical: Y [ ] N[X] Grade S [ ] U [] i I Comments:

Cue: Candidate recognizes that IDENTIFIED LEAKAGE is less than 10 gpm, and therefore the TIS acceptance criteria is met. Critical:

Y[X] N [ ] Grade S [ ] U [ ] STEP #15 001 Pg 7 of 7 Review Calculation Table 11: UNIDENTIFIED LEAKAGE Candidate observes that previously calculated values Total RCS Leak Rate, IDENTIFIED LEAKAGE, change in PDTT volume and L1 Time are entered for the unidentified leakage calculation, Critical: Y [ ] N[X] Grade S [ ] U [ ] Comments:

Cue: Candidate reviews the calculation for UNIDENTIFIED LEAKAGE and determines the calculation is performed correctly.

Critical: Y [ ] N[X] Grade S [ ] U [ ] Comments:

-Cue: 13 Candidate recognizes that Critical:

Grade UNIDENTIFIED LEAKAGE is less than 1 Y[X] S [ J N [ ] U [ J gpm, and therefore the TIS acceptance criteria is met. Comments:

The candidate may express concern about the significantly high value of UNIDENTIFIED LEAKAGE (0.913 gpm) and desire to initiate immediate action to get the organization involved.

If so provide the following cue: Cue: Continue with your review, including any SP 3601 F.6 actions required.

STEP IF leakage approaches either of the Candidate recognizes that actual Critical:

Grade #16 following limits, INITIATE a Condition UNIDENTIFIED LEAKAGE (0.913 gpm) Y[X] S [ ] N [ ] U [ ] Report to ensure compliance with is in excess of 0.75 gpm, and a Condition SP 3601F.6 Maintenance Rule requirements:

Report needs to be initiated.

Step 4.3.5 IDENTIFIED LEAKAGE ---2.5 (25% of T.S. UNIDENTIFIED LEAKAGE ---gpm (75% of T.S. Comments:

When the Candidate identifies the requirement for a CR, provide the following cue: Cue: Another licensed operator will initiate the CR. I I STEP IF UNIDENTIFIED LEAKAGE is Critical:

Grade Candidate calls or requests the US call #17 high, greater than 0.6 gpm or a step Y[X] S [ ] Engineering to inform them of the leak N [ ] increase of 0.2 gpm, PERFORM U [ J rate.Step 4.3.6.a following:

NOTIFY Engineering of leak rate. Comments:

--._-14

---

f Cue: All notifications to Engineering are compleh...

REVIEW computer printout or SP Critical:

Grade Candidate refers to Table 5 on SP Step 4.3.6.b S [ ] 3601 F.6 -001, Table 5, and Y [ ] 3601 F.6 --001, and reviews data N[X] U [ ] DETERMINE the volume changes associated with the PDTT volume associated with the PDTT. change. Comments:

Cue: VERIFY all inventory changes to the Critical:

Grade Candidate requests from the SM the Step 4.3.S.c PDTT are related to RCS or CVCS Y [ ] S [ ] status of the SI and RHR pumps during N[X] U [ ] changes as follows ..... the data gathering period. _i Comments:

When the Candidate requests status of the SI and RHR pumps, provide the following cue: Cue: I No SI or RHRpumps were run during the measurement, but 3DGS-V831 and V826 are OPEN. All PDTT inventory changes cannot be verified to be all RCS or CVCS related. I Critical:

Grade !Candidate determines that since Y [ ] S [ ] inventory changes to the PDTT are NOT N[X] U [ ] all related to RCS or CVCS, UNIDENTIFIED LEAKAGE cannot be corrected.

Comments:

Cue: IF all PDTT inventory changes are RCS or Candidate reviews step 4.3.6.d and Critical:

Grade CVCS related, Refer To SP 3601 F.6---001, recognizes that it does not apply. Y [ ] S [ ] Step 4.3.S.d N[X] U [ ] Table 12 ..... Comments:

Cue: --.......-..... ...-.-....--.....-..... ...15 STEP #18 Step 4.3.6.e STEP #19 Step 4.3.7 IF PDTT inventory changes can not be verified to be all RCS or CVCS related leakage, Refer To SP 3601 F.6---001, Table 11, and RECORD UNIDENTIFIED LEAKAGE from Table 11 in the SM log for the TIS surveillance.

Candidate takes action or otherwise recognizes that the actual value for UNIDENTIFIED LEAKAGE needs to be entered in the SM log. Critical:

Y[X1 N [ ] Grade S [ ] U [ ] The value for UNIDENTIFIED LEAKAGE is entered in the SM log. IF leakage calculation was initiated for the Candidate recognizes that the RO should required daily leakage determination (per have already attached a copy of the last SP 3670.1---001), ATTACH a copy of the page to the Shiftly Control Room Rounds. last page of SP 3601 F.6---001, to SP 3670.1---001, "MODE 1---4 Daily and Shiftly Control Room Rounds." Critical: Y [ ] N[X] Grade S [ ] U [ ] The value for UNIDENTIFIED LEAKAGE is entered in the SM log.

STEP #20 Step 4.3.8 STEP #21 COP 200.15 Step 4.1.1 IF leakage exceeds any of the Critical:

Grade Candidate recognizes the need to refer to limits, Refer To C OP 200.15, "RCS Y [ ] S [ ] C OP 200.15 to determine required Leakage Trending and Investigation," N[X] U [ J actions. PERFORM required actions: I One seven (7) day rolling average daily RCS LEAKAGE rates greater than Two consecutive daily UNIDENTIFIED LEAKAGE greater than 0.15 One daily RCS LEAKAGE rate greater than 0.3 Provide the Candidate with a copy of C OP 200.15. Determining Required Response Candidate reviews step 4.1 .1 Critical:

Grade Y [ ] S [ ]

N[X] U [ ] IF leakage is PRESSURE BOUNDARY LEAKAGE, PERFORM the following

.... After the Candidate reviews the step, provide the following cue: The leakage is not pressure boundary leakage. 17 STEP IF any of the following Action Level 3 limits Candidate recognizes that the Critical:

Grade #22 are exceeded, Go To Section 4.4: UNIDENTIFIED LEAKAGE rate IS Y[X] S [ ] greater than 0.3 gpm, and proceeds to N [ 1 u [ ] COP 200.15 Step 4.1.4

• One daily RCS UNIDENTIFIED Section 4.4. LEAKAGE rate greater than 0.3 gpm One daily RCS UNIDENTIFIED LEAKAGE rate greater than the sum of the baseline mean plus three times the standard deviation , Comments:

Cue: STEP Response for Exceeding Action Level 3 Candidate reviews step 4.4.1. Critical:

Grade #23 Limits Y [ ] S [ ] N[X) U [ ] Step 4.4.1 VERIFY Action Level 1 and 2 have been Comments:

When the Candidate refers to the sections for Action Level 1 and 2 responses, provide the following cue: Cue: Action Level 1 and 2 responses have been performed.

STEP IF the increased leak rate is indicated Candidate reviews the NOTE. Critical:

Grade #24 inside containment, PERFORM the Y [ ] S [ ] N[X] U [ ] following:

Step 4.4.2.a PREPARE for a containment entry, Comments:

When the Candidate recognizes that a CTMT entry needs to be made, provide the following cue: Cue: The OMOC will designate a CTMT entry team which will carry out this step (step 4.4.2). STEP IDENTIFY source of the leak. Candidate reviews step 4.4.3. Critical:

Grade #25 Y [ ] S [ ] N[X] U [ J Step 4.4.3 Comments:

Cue: The OMOC has assigned a team to develop leak investigation troubleshooting plan including identifying the source. STEP QUANTIFY the leakage. Candidate reviews step 4.4.3. Critical:

Grade #33 Y [ ] S [ ] N[X] U [ J Step 4.4.4 Comments:

Cue: The SM has assigned the STA to conduct an independent manual RCS water inventory balance.

STEP INITIATE a Condition Report to develop a Candidate reviews the NOTE. Critical:

Grade #26 corrective action plan to address or correct Y [ ] S [ ] N[X] U [ J the leak. Step 4.4.5 Comments: , Cue: The STA has initiated a Condition Report to develop a corrective action plan to address the leak. , STEP Refer To AOP 2568, "Reactor Coolant Candidate recognizes AOP 3555 may Critical:

Grade #27 System Leak," or AOP 3555, "Reactor provide additional guidance. Y [ J s [ ] N[X] U [ ] Coolant System Leak,1\ as appropriate, for Step NOTE additional Comments:

When the Candidate requests a copy of AOP 3555, provide the following cue: I Cue: ReS UNIDENTIFIED LEAKAGE has increased to 1.2 gpm. What are the required actions? STEP Calculation Table 11: UNIDENTIFIED Notes or otherwise verbalizes that Critical:

Grade #36 LEAKAGE UNIDENTIFIED LEAKAGE TIS Y[X] S [ J N [ ] U [ ] acceptance criteria is NOT satisfied. 001 TIS ACCEPTANCE CRITERIA Pg 7 of 7 UNIDENTIFIED LEAKAGE shall not greater than 1 Comments:

Cue:

STEP Refer To the applicable Technical Refers to 3.4.6.2.b and enters #28 Specification(s) and PERFORM applicable STATEMENT TIS 3.4.6.2 Comments:

Candidate can either verbalize intention of enterinQ TIS or record as such in a rough 10Q. Cue: STEP With any RCS operational LEAKAGE not #29 within limits, other than TIS 3.4.6.2 BOUNDARY LEAKAGE, LEAKAGE Action b. Reactor Coolant System Pressure Isolation Valves or primary to secondary LEAKAGE, reduce the leakage rate to within limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. Comments:

Candidate verbalizes or otherwise recognizes that there is a 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Allowed Outage Time reduce the leakage rate to within limits, and if not, followed by the requirement to be in Hot Standby within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. Critical:

Grade Y[X] S [ ] N [ ] U [ ] Critical:

Grade Y[X] S [ ] N [ ] U [ ] Cue: TERMINATION CUE: The evaluation for this JPM is concluded. STOP TIME: ___

---VERIFICATION OF JPM COMPLETION JPM Number: NRC RO A.2 Revision: Date To achieve a satisfactory grade. ALL critical steps must be completed correctly. If task is Time Critical.

it MUST be completed within the specified time to achieve a satisfactory grade. Time Critical Task? Yes No X Validated Time (minutes):

30 Actual Time to Complete (minutes):

Overall Result of JPM: SAT UNSAT Areas for Improvement I Comments:

JPM Number: Initial Conditions:

Initiating Cues: STUDENT HANDOUT NRC RO A.2 Revision:

aThe plant is at 1 00% power and you are the Unit Supervisor on shift. The PPC RCS Leakage Program is malfunctioning and the RCS Leakage calculation is due. Computer Services has been notified.

You directed the Reactor Operator to perform a manual RCS water inventory balance using SP 360'1 F .6, Reactor Coolant System Water Inventory Measurement, which he just completed.

Review and disposition the completed Surveillance Form SP 3601 F.6 -001, ReS Inventory Balance.

JOB PERFORMANCE MEASURE APPROVAL JPM Title: Perform an Operability Determination.

JPM Number: NRC SRO A.2 Revision:

o Initiated:

Dave Minnich 04/26/11 Developer Date Reviewed:

5 /'0/ If / Technical Revie tw---Date sf}1 Supervisor, Nuclear D te

SUMMARY

OF CHANGES REV/CHANGE

---

JPM Facility:

Millstone Unit 3 Examinee:

JPM Number: NRC SRO A.2 Revision:

0 Task Title: Perform an Operability Determination.

System: GENERIC Time Critical Task: ) YES (X) NO Validated Time (minutes) 30 Task Number{s):

119-03-179 Applicable To: SRO X RO PEO KiA Number: 2.2.37 KiA Rating: 4.6 Method of Testing: Simulated Actual Performance:

Performance:

Location:

Classroom:

X Simulator:

In-Plant:

Task Standards:

Determine the OPERABILITY of a safety related component.

Required Materials:

Unit 3 Technical Specifications (procedures, equipment, etc.) ARP OP 3353.VP1C, Main Ventilation and Air Conditioning Panel VP1C Annunciator Response OP 3314F, Control Building Heating, Ventilation, Air Conditioning and Chill Water General

References:

OP-AA-102, Operability Determination X

• • • READ TO THE EXAMINEE I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this JPM will be satisfied.

You may use any approved reference material normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.

JPM WORKSHEET

...IPM Number: Revision:

o Initial Conditions:

The plant is at 100% power, and you are the Extra Senior Licensed Operator on shift. About five minutes ago VP1 C 2-1 A "CB INLET VENT SMOKE" alarmed. Subsequently, it was determined that a small class 'A' fire is in progress just outside the 'A' EDG Enclosure.

The Fire Brigade has been dispatched and the Control Room Team is carrying out the actions of EOP 3509, Fire Emergency. Initiating Cues:

The SM has directed you to respond to the annunciator for VP1C 2-1A nCB INLET VENT SMOKE" Simulator Requirements:

NONE * * *

• NOTES TO TASK PERFORMANCE EVALUATOR

• * *

• Critical steps for this JPM are indicated by checking "Y". For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly. When the student states what his/her simulated action/observation would be, read the appropriate "Cue". If necessary, question student for details of simulated actions/observations (Le. "What are you looking at?" or "What are you observing?") . . Under NO circumstances must the student be allowed to manipulate any devices during the performance of this JPM (in-plant only).

PERFORMANCE INFORMATION JPM Number: NRC SRO A.2 Revision: Task Title: Perform an Operability START TIME: ____ PERFORMANCE STANDARD Evaluator When requested, provide the candidate a copy of OP 3353VP1C 2-1A "CB INLET VENT STEP Obtains and refers to proper Candidate refers to a copy of OP 3353.VP1 C Critical:

Grade #1 procedure.

2-1A. Y [ ] S [ ] N[X] U [ J Comments:

Cue: STEP CHECK 3CES---PNLFPS, fire detection Critical:

Grade Candidate recognizes the need to check #2 console, for fire alarms. Y [ ] S [ ] the fire detection console for fire alarms. N[X] U [ ] VP1C step Comments:

When the Candidate requests the status of alarms on the fire detection console, provide the following cue: Cue: The fire detection console is not in alarm. STEP #3 VP1C 2-1A, step 2 SEND Operator to check for source of smoke to control building ventilation inlet. Candidate takes action to or otherwise recognizes the need to dispatch a PEO to determine the source of the fire. Critical: Y [ ] N[X] Grade S [ ] U [ ] I Comments:

When the Candidate requests a PEO be dispatched, provide the following cue: Cue: A PEO has already been dispatched and reported the source of the fire (initial cue). STEP IF smoke or fire is present, PERFORM the #4 following:

VP1C 2*1A. step 3.1 IF smoke is present in Control Room, Refer To OP 3314F, "Control Building Heating, Ventilation, Air Conditioning and Chill Water," and PLACE control room ventilation on full filtered recirc. Comments:

Critical:

Grade Candidate recognizes the need to refer to Y [ ] S [ ] OP 3314F, if smoke is in the Control N[X] U [ ] Room. When the Candidate questions the status of smoke in the control room, provide the following cue: Cue: A light and small amount of smoke is in the Control Room; the US has directed the BOP to place Train 'A' of control room ventilation on full filtered recirculation, The SM directs you to review the alignment for full recirculated filtered air, and then refer to Tech Specs, Comments:

When requested, provide the candidate a copy of OP 3314F. STEP Obtains and refers to proper procedure and Candidate refers to a copy of OP 3314F, #5 section. Section 4.10, Operation of Control Room Emergency Ventilation System (Train A), VP1C 2-1A. step and determines that section 4,10.3 (full recirculated filtered air) is the desired section. Comments:

Cue: Critical:

Grade Y [ ] S [ ] N[X] U [ ]

STEP #6 OP 3314F, step 4.10.3 CAUTION Comments:

Cue: STEP #7 OP 3314F, step 4.10.3 NOTE 1 Comments:

Cue: STEP #8 OP 3314F, step4.1Q.3 NOTE 2 Comments:

Cue: The Control Room Emergency Ventilation System must be operated with recirculated outside filtered air (step 4.10.2) during post accident conditions.

To operate Train A Control Room Emergency Ventilation System with full recirculated filtered air using filter 1 A, PERFORM the following:

The Control Room will not pressurized in this The full recirculated filtered air MODE of operation should only be used when directed by the Alarm Response Procedure for smoke in the Control Room inlet duct. Candidate reviews the CAUTION and recognizes that post accident is referring to Design Basis Accidents.

Candidate reviews the NOTE. Candidate reviews the NOTE and recognizes that the Alarm Response Procedure DID direct full recirculated filtered air MODE of operation.

Critical: Y [ ] N[X] Y [ N[X] Y [ N[X] Grade S [ J U [ ] Grade S [ ] U [ ] Grade S [ ] U [ ]

STEP Critical:

Grade 3HVC*AOV25 and 3HVC*AOV26, Candidate reviews the NOTE. #9 Y [ ] S [ ] control building outside air isolations, are N[X] U [ ] maintained open with air isolated to OP step 4.10.3 ensure the ability to establish the NOTE Room Emergency Ventilation System recirculated outside filtered air mode Design Basis Accident Comments:

Cue: STEP Critical:

Grade Refer To TIS 3.7.7, "Control Room Candidate recognizes the need to refer to #10 Y [ ] S [ ] Emergency Ventilation System," for TIS 3.7.7. N[X] U [ ] appropriate ACTIONs. OP 3314F, step 4.1 0.3.a Comments:

If the Candidate requests a copy of Tech Specs, provide the following cue: Cue: Continue your review the alignment for full recirculated filtered air, and then refer to Tech Specs. Comments:

The following steps of OP 3314F are not intended to be carried out in the Simulator; only reviewed by the SRO Candidate.

STEP To stop Kitchen Exhaust Ventilation

1. 11 System, PERFORM the following (VP1): OP 3314F, step 4.10.3.b PLACE 3HVC---FN6, "KITCHEN EXH FAN," to "OFF." CLOSE the following: 3HVC*AOV20, "KITCHEN EXH AIR ISOL" 3HVC*AOV21, "KITCHEN EXH AIR ISOL" 3HVC*AOD27A, "NORM SPLY DMPR" 3HVC*AOD278, "NORM SPL Y DMPR" OPEN instrument air supply to #12 3HVC*AOV25, "CNTRL Room Ventilation Inlet 1501 W" (locally).

OP 3314F, step 4.10.3.c Candidate reviews Step 4.1 O.3.b. Candidate reviews Step 4.1 O.3.c. Critical: Y [ ] S [

N[XJ U [ Critical: Y [ ] S [

N[X] U [ The following step has the potential to affect the OPERABILITY of the Control Room Emergency Note: Ventilation System (TIS 3.7.7). -9 STEP CLOSE 3HVC*AOV25, "OUTSIDE AIR #13 ISOL" (VP1). OP step 4.1 Comments:

Cue: STEP VERIFY one of the following, running #14 (VP1 ): OP 3314F,

• 3HVC*ACU1A, "CNTL RM ACU" step 4.10.3.e

• 3HVC*ACU1 B, "CNTL RM ACU" Comments:

Cue: STEP IF Purge System is in service, Refer To #15 step 4.12.2 and SHUTDOWN Control Building Purge System. OP step Comments:

Cue: Candidate reviews Step 4.10.3.d and recognizes that 3HVC* AOV25 is normally maintained open to ensure the ability to establish the recirculated outside filtered air mode for Design Basis Accident mitigation.

Candidate reviews Step 4.1 0.3.e. Candidate reviews Step 4.10.3.f.

Critical:

Y[X] N [ ] , Critical: Y [ ] N[X] Critical: Y [ ] N[X] Grade S [ ] U [ ] Grade S [ ] U [ ] Grade S [ ] U [ ]

STEP #16 OP 3314F. step 4.10.3.9 STEP #17 OP 3314F. step 4.1 0.3.a PLACE 3HVC*FN1A, "FL TR UNIT Candidate reviews Step 4.1 0.3.g. Critical: FAN/DMPRS" to "ON," and OBSERVE Y [ ] S [ N[X] U [ ] the following (VP1): 3HVC*MOD33A, "FL TR UNIT FAN/DMPRS," opens. 3HVC*FN1A, "FL TR UNIT FAN/DMPRS," starts. I 3HVC*FLT1A, "FL TR BANK HTR," on. 3HVC*AOD119A. "RECIRC DMPR," in "EMERGENCY." * *After the Candidate reviews step 4.10.3 and if helshe requests additional guidance, provide the following cue: *Now carry out OP 3314F, Step 4.10.3.a.

When requested, provide the Candidate with a copy of Tech Specs. Critical:

Grade Refer To TIS 3.7.7, "Control Room Candidate Refers to TIS 3.7.7 for Y [ ] S [ ] Emergency Ventilation System," for CONTROL ROOM EMERGENCY N[X] U [ ] appropriate ACTIONs. VENTI LA TlON SYSTEM determines the LCO is specified "Two independent Control Room Emergency Air Filtration Systems shall be OPERABLE.*." 11

--

Cue: STEP Candidate Refers to TIS 3.7.7 LCO Critical:

Grade #18 actions associated for MODES 1, 2, 3, 4 Y [ ] S [ ] N[X] U [ ] and determines the action statement that TIS 3.7.7 MAY apply is action 'b' which follows: LCO action 'b' "With both Control Room Emergency Air Filtration Systems inoperable, except as specified in ACTION c., restore at least one inoperable system to OPERABLE status within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and COLD SHUTDOWN within the following

, 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />." Comments:

This assessment is based on 3HVC* AOV25 being closed which isolates the source of outside air for recirculated outside filtered air mode for Design Basis Accident mitigation.

The Candidate should refer to Tech Spec Bases to determine if this action statement is met. Cue: -_ ....... _._ ......._. __......_.. -

STEP #19 TIS 3.7.7 Bases Refer to Tech Spec 3.7.7 Bases: Gontrol Room inlet isolation valves 3HVG*AOV25 and 3HVG*AOV26 are maintained open with air isolated whenever Technical Specification 3.7.7 is applicable.

Candidate Refers to TIS 3.7.7 LCO Bases for interpretational guidance and correctly determines that both Control Room Emergency Filtration trains remain OPERABLE, but degraded.

Critical:

Y[X] N [ ] Grade S [ ] U [ J The only procedural guidance to close 3HVG*A 0 V25 when this specification is applicable is in the alarm response procedure for smoke in the control room air inlet ventilation duct. The alarm response procedure will provide direction to establish the filtered recirculation mode of operation by restoring air and closing 3HVG*AOV25.

During this limited time period, both Gontrol Room Emergency Filtration trains remain OPERABLE, but degraded.

Comments:

The Candidate may already know that the Control Room Emergency Filtration trains remain OPERABLE, but degraded, without referring to TIS Bases. This is satisfactory and meets the critical nature of the step. Cue: Evaluator During restoration from Control Room Emergency Ventilation System with full filtered Follow on air, it is determined that 3HVC*AOV25 is mechanically stuck closed and will NOT open. Determine Question:

the OPERABILITY of the Control Room Emergency Air Filtration Systems. STEP Candidate Refers to TIS 3.7.7 LCO Critical:

Grade Refer to Tech Spec 3.7.7 Bases: #20 Bases and correctly determines that both Y[X] S [ J Even though 3HVG*AOV25 is closed, it is Control Room Emergency Filtration trains N [ 1 U [ ] TIS 3.7.7 a fail open valve and will automatically are INOPERABLE.

Bases open on a Gontrol Building Isolation signal, making it OPERABLE.

However, should it fail to open, the system will not function.

_ __.. _.... _. .... _._._-.---....-_ ....-.... _... _-.... _ .. _ .... _.... -....-.... _.. __.... --.... -.... _ ... _-.... _ ....-13 Comments:

The Candidate may have already made this determination from first reviewing the Bases, and may not need to refer to the Bases a second time. Also, The Candidate may already know that the Control Room Emergency Filtration trains are now INOPERABLE, without referring to TIS Bases. This is satisfactory and meets the critical nature of the step. Cue: STEP #21 Refer To Technical Specification 3.7.7 to determine the Limiting Condition for TIS 3.7.7 Operation.

Bases Comments:

Termination I The evaluation for this JPM is complete.

Cue: Candidate Refers to TIS 3.7.7 LCO actions associated for MODES 1, 2, 3, 4 and determines the action statement fb' DOES apply and enters LCO ACTION statement fb'. SRO Candidate should state or otherwise indicate recognition of LCO requirement.

Critical:

Grade Y[X] S [ ] N [ ] U [ ]

STOP TIME: __

--VERIFICATION OF JPM JPM Number: SRO A.2 Revision: o Date Performed:

Student: Evaluator:

For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.

If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade. Time Critical Task? Yes No X Validated Time (minutes):

30 Actual Time to Complete Overall Result of JPM: SAT Areas for Improvement I Comments:

JPM Number: Initial Conditions:

Initiating Cues: STUDENT SROA.2 Revision:

o The plant is at 100% power, and you are the Extra Senior Licensed Operator on shift. About five minutes ago VP1C 2-1A "CB INLET VENT SMOKE" alarmed. Subsequently, it was determined that a small class 'A' fire is in progress just outside the 'A' EDG Enclosure.

The Fire Brigade has been dispatched and the Control Room Team is carrying out the actions of EOP 3509, Fire Emergency.

The SM has directed you to respond to the annunciator for VP1 C 1A "CB INLET VENT SMOKE" JOB PERFORMANCE MEASURE APPROVAL JPM Title: JPM Number: Initiated:

Reviewed:

Evaluation of an Unplanned Gaseous Release. NRC SRO A.3 Revision:

o Dave Minnich D!+/-

__ Developer Date 5(/0(U I T echnical Date .. Supervisor, Dk

SUMMARY

OF DATE DESCRIPTION REV/CHANGE

---

JPM WORKSHEET Facility:

Millstone Unit 3 Examinee:

JPM NRC SRO A.3 Revision:

o Task Title: Evaluation of an Unplanned Gaseous Release. System: GENERIC Time Critical Task: ( ) YES (X) NO Validated Time (minutes) 30 Task Number{s):

301-05-366 Applicable To: SRO x RO PEO KIA Number: 2.3.11 KIA Rating: 4.3 Method of Testing: Simulated Actual X Performance:

Performance:

Location:

Classroom:

X In-Plant:

Task Evaluate an unplanned gaseous release and as a result, the proper notifications and event reporting requirements.

Required Materials: (procedures, equipment.

RAC 14, Non-Emergency Station Events, Rev 003-01 etc.) General RAC 05, Reportability Determinations and Licensee Event Reports AOP 3573, Radiation Monitor Alarm Response MP-26-EPA-REF03, Millstone Unit 3 Emergency Action Level (EAL) Technical Basis Document L___3

• • • READ TO THE EXAMINEE I will explain the initial conditions, which step(s} to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this JPM will be satisfied.

You may use any approved reference material normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.

JPM WORKSHEET JPM Number: SRO Revision:

o Initial The plant is at 100% power, and you are the Extra Licensed Operator on shift. About 15 minutes ago MB2B "RADIATION ALERT" alarmed, followed shortly thereafter MB2B 2-8 URAD HI". The RO has determined and reported 3HVR*RE10B is in alarm. The Control Room Team has AOP 3573, Radiation Monitor Alarm Response, and are appropriate actions for 3HVR*RE1 OB, including attempting identify the source of radiation.

There is no indication that is an equipment problem associated with The SM has directed you to carry out action step 4 of Initiating Attachment lA' to AOP 3573 for 3HVR*1 OB, "Take action using MP-26-EPI-FAP06-003, Unit 3 Emergency Levels (Offsite Write down your response(s) below: Simulator Requirements:

NONE * * *

• NOTES TO TASK PERFORMANCE EVALUATOR * * *

• Critical steps for this JPM are indicated by checking "Y". For the student to achieve satisfactory grade, ALL critical steps must be completed When the student states what his/her simulated action/observation would be, read appropriate If necessary, question student for details of simulated actions/observations (Le. "What you looking at?" or "What are you Under NO circumstances must the student be allowed to manipulate any devices during the performance of this JPM (in-plant only). I PERFORMANCE INFORMATION JPM Number: NRC SRO A.3 Revision:

o Task Title: Evaluation of an Unplanned Gaseous Release. START TIME: ____ PERFORMANCE STANDARD STEP Take appropriate action using MP-26-Candidate obtains or requests copy Critical:

Grade #1 EPI-FAP06-003, Unit 3 Emergency of MP-26-EPI-FAP06-003, MP3 Y[] N[X] S[]U[] Action Levels (Offsite Releases)

Emergency Action Levels. At t A HVR*10 S t ep_ 4 Candidate Refers to the 'OFFSITE Critical:

Grade RELEASES' column on page 1 of 3 Y[JN[X] S[]U[] of the MP3 EAL Tables. I Comments:

To properly evaluate if the Offsite Release is classifiable, the Candidate will need to know the specific level of radiation as detected by 3HVR*1 DB. When requested, provide the following cue: Cue: 3HVR*10B is still in 'alert' but has cleared its alarm setpoint.

It is currently reading 2 x 10-4 J,lCilcc and slowly lowering.

The highest reading was 9 x 10-4 ..,Ci/cc.r-Candidate eliminates classification Critical: levels General Emergency, Site Area Y[X] N[] Emergency and Alert, based HVR*10 reading < 0.01 STEP #2 MP3 Ta b I -Eve n Effluent Monitors in Alarm OR Candidate reviews the criteria for an Critical:

Grade Unplanned, Unmonitored, or unplanned release for UNUSUAL Y [ ] N [X] S[]U[] Uncontrolled Offsite Release AND EVENT -DELTA-TWO.

DEL T A-TWO Posture Code Limits as Determined from MP*26*EPI*FAP06 "Classification and PARs" Exceeded.

Note: Effluent Monitors Indicate release Above Alarm Setpoint Continuing>

60 Minutes AND Reportability Evaluations NOT Complete.

Candidate obtains or requests copy Critical:

Grade of MP-26-EPI-F AP06 "Classification Y[ J N[X] S[JU[J and PARs.

I Event Classification Based on EAL -Critical:

Grade Candidate calls Chemistry and STEP Tables requests assistance in determining Y [ ] N [X J S[]U[]#3 Determine whether a classifiable the magnitude of the emergency exists as s t e 2.1 .2. d IF the event involves an unplanned release at the UE level, Refer To Attachment 3, "OU1-0etermination Criteria (Delta-Two Posture Code Limits)," and perform the following to determine the classification and notification requirements as appropriate:

Notify the Unit Supervisor to provide in determining the magnitude the release for OU Provide the following as the Chemistry Supervisor:

Comments:

Cue: The Chemistry Supervisor and one additional Chern Tech are on the way to the Control Room. Evaluate the magnitude of the Candidate refers to Attachment 3, Critical:

Grade STEP release. "OU 1-Determination Criteria (Oelta-Y [ ] N [X] S[]U[]#4 Two Posture Code Limits)." s t e 2.1 .2. d. 2 )

Comments:

Cue: STEP Initiating Condition 1 Candidate reviews 'Initiating Critical:

Grade #5 Condition l' of Attachment

3. Y [ ] N [X] S[]U[] Any airborne radioactive release that, FAP06 when averaged over a period of 1 At t 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />, results in concentrations unrestricted areas that exceeds times the applicable limits specified in the , Once the Candidate reviews 'Initiating Condition l' of Attachment 3, provide the following , (Time compression)

The Chemistry Department is has determined that Posture Code have NOT been If the Candidate fails to continue in the 'Classification and PARs' procedure (assuming that it was Comments: 'classification' JPM), provide the following The SM directs you to continue in MP-26-EPI-FAP06.

STEP IF the event has been evaluated and Obtains and refers to a copy of RAC Critical:

Grade #6 is not addressed by the Emergency 14, Station Events. Y [ J N [X] S[]U[] Action Level tables. Go To RAC 14, FAP06 "Non-Emergency Station Events." s t e p 2.1 .3 -.... -...-.-....8

--Comments:

Cue: Critical:

Grade Review Precautions. (RAC 14, Candidate reviews precautions 3.1#7 Y [ ] N [X] S[]U[]Section through 3.8. Cue: Comments:

STEP Initial Event Reportability Candidate recognizes that sufficient Critical:

Grade #8 Determination cause may exist for reporting this Y [ ] N [X] S[]U[] event.IF sufficient cause exists for reporting RAG 14, step a non-emergency event, the ANAL YZE available information DEVELOP a general of event in Comments:

Cue: Candidate requests additional staff. Critical:

Grade ASSIGN staff to collect and track Y [ ] N [X] S[]U[]information.

RAG 14, step 4.1.1.b Comments:

If the Candidate requests additional personnel to track the event, or requests additional assistance, provide the above cue: 9 I Additional assistance will be available shortly. Continue with your task. Requests assistance as necessary.

Critical:

Grade IF necessary, REQUEST Y[ J N[X] S[]U[]assistance from any of the following, as applicable, to RAC 14, step determine reportability and to If the Candidate requests additional assistance provide the following cue: Additional assistance will be available shortly. Continue with your task. STEP As required, REQUEST Station Duty Candidate recognizes the need to Critical:

Grade #11 Officer (typically the non-affected unit call Unit 2 to request the Station Duty Y[] N[X] S[]U[] STA) and Emergency Communicator Officer and Emergency RAC 14, step (typically the non-affected unit WC Communicator report to the Unit 3 SRO) report to the Control Room and Control prepare to send a Non Event Comments:

The Candidate may wait to determine if the event is reportable prior to requesting the SDO and EC. This is acceptable.

Cue: STEP Certain reportable environmental Candidate reviews the NOTE. Critical:

Grade #12 events, including those not reportable Y [ ] N [X] S[]U[] to the NRC, have reportable time RAC 14, step limits listed in Attachments 1 through NOTE Comments:

--....-.... -.... _....__ .... _ .... _ .... _ ....__ .... _ .... -.... _...__... _ .... 10 Cue: STEP IF event is an unplanned or Candidate recognizes that the event Critical:

Grade #13 unmonitored radioactive release, potentially is an unplanned Y[X]N[ ] S[]U[] Refer To and PERFORM Section 4.2, radioactive release, and proceeds to RAC 14, step "Evaluation of an Unplanned Section 4.2. Radioactive Comments:

Cue: STEP Leaks from plant systems, e.g., aux Candidate reviews the CAUTION. Critical:

Grade #14 steam, condensate.

etc., that have the Y [ J N [X 1 S[]U[] potential to be radioactive could RAC 14, step constitute an unplanned, unmonitored CAUTION radioactive release and must evaluated.

Comments:

Cue: L .... _ .... _ .... _ .... _ .... _ .... _

--4.2.1 STEP #15 RAC 14, step Comments:

Cue: STEP #16 RAG 14, step 4.2.2 Comments:

-.... -.._.-.... -.... _... IF an unplanned or unmonitored Candidate recognizes the need to Critical:

Grade radioactive release has occurred call Health Physics, Environmental Y [ ] N [X] S[JU[J including any spills and/or leaks of and Licensing.

radioactive liquid, NOTIFY the following, as applicable, for assistance in determining reportability requirements: Health Physics Supervision Unit Chemistry Environmental Licensing i Chemistry is already i i IF release source is not identified, Candidate refers to Attachment 8, Critical:

Grade Refer To Attachment 8, Section 6, Section 6. Y [ ] N [X J S[]U[] "Maintenance Operations," and REVIEW current plant operations to identify source of release. Once the Candidate starts the review of Section 6, provide the following cue:

Cue: STEP #17 RAe 14, step 4.2.3 Comments:

Cue: STEP #18 RAe 14, step 4.2.4 Comments:

Cue: STEP #19 RAe 14, step 4.2.5 Comments:

Cue: The Control Room Team has determined that the cause of the release was a Oegasifier overpressure event that lifted the degasifier condenser relief valve (3GWS-RV35).

Initially, the relief valve failed to reseat, but has since drifted closed. IF applicable, Refer To and IMPLEMENT C OP 200.4 "Response to Plant Leaks." IF applicable, Refer To and IMPLEMENT C OP 200.5, "Oil, Hazardous Material, Hazardous Waste, and Mixed Waste Contingency Plan." IF applicable, Refer To COP 200.11, "Operation of a Cross Contaminated System," and simultaneously COMPLETE requirements.

Candidate recognizes that C OP 200.4 does not apply and proceeds to step 4.2.4. Candidate recognizes that C OP 200.5 does not apply and proceeds to step 4.2.5. Candidate recognizes that C OP 200.11 does not apply and proceeds to step 4.2.6. The Oegasifier relief valve and associated piping are considered contaminated.

-.... _ .... _ .... _.__ .... -.... -.... -..--.. ... ..-.-.--.--.-.-

.. -.... 13 Critical: Y [ J N [X] Critical: Y[] N[X] Critical: Y[] N[X]

STEP #20 RAC 14, step 4.2.6 Comments:

Refer To Attachment 8, Section 2, "Reportable Releases," and REVIEW for type of release involved.

Candidate refers to Attachment 8, Section 2, and reviews for type of release involved.

Critical: Y [ ] N [X] Grade S[]U[] I Cue: RAG 14, Att 8 Section 2 Candidate recognizes the following types of release may be involved:

Critical: Y ( ] N [X J Grade S[]U[] 1. Releases Exceeding Gaseous Release Rate Limit 2. Unplanned Gaseous Releases Comments:

Cue: STEP #21 RAG 14, step 4.2.7 Refer To Attachment 8, Section 3, "Release Calculations," and COMPLETE calculations listed for released material, or other method as approved by the Chemistry Department.

Candidate refers to Attachment 8, Section 3, and reviews various the Release Calculations to determine which may apply. Critical: Y [ ] N [X] Grade S[]U[] Comments:

The various Release Calculations listed in Section 3 follow in JPM steps 22 through 25. Cue: 14 STEP GASEOUS RELEASE RATE LIMIT Candidate recognizes that HVR-Critical:

Grade #22 RE10B did exceed its alarm setpoint, Y [ ] N [X] S[]U[] If an effluent radiation monitor and requests Chemistry enter SP RAC 14, AU 8 (HVR-RE10B), exceeds the alarm 823/2823/3823 to determine if the Section 3 setpoint request that Chemistry instantaneous release rate limit has enter SP 823/2823/3823 to been exceeded.

determine if the instantaneous release rate limit has been exceeded.

Comments:

Once the Candidate calls Chemistry, provide the following cue: I Cue: The Chern Tech is already performing SP 823/2823/3823.

STEP UNMONITOREO GASEOUS Candidate recognizes that the Critical:

Grade #23 RELEASES:

release was monitored, therefore this Y [ ] N [X] S[lU[l calculation does not apply. RAe 14, AU Section Cue: _ ..-._-.... _.... _.... _ .. _.-

STEP UNPLANNED GASEOUS RELEASES Candidate recognizes that the Critical:

Grade #24 release path was via the Unit 3 Vent Y[X] N[] S[]U[J Unit 3 Vent (Turbine Building stack); therefore RAe 14, Att 8 this calculation does apply. Section 3 Average 10 Minute Net Increase HVR-RE10B in IJci/cc Flow Rate (CFM) x 472 cc/sec Pressure

=

Comments:

I When the Candidate requests information to begin the calculation, or requests Chemistry to perform the calculation, provide the following cue: Cue: I The unplanned gaseous release rate was 2478 J.Ici/sec.

Also SP 823/2823/3823 is complete and the instantaneous release rate limit has NOT been exceeded.

Unit 3 SLCRS Candidate recognizes that any Critical:

Grade contribution from the SLCRS or ESF Y [ ] N [X] S[]U[] Unit 3 ESF Bldg. Building effluent release paths will be negligible compared to Unit 3 Vent Unit 3 Total = <1500 path release. Comments:

Cue:

Candidate recognizes that 2478 Critical: J.lci/sec is NOT <1500 \JCi/sec.

VeX] N[l Therefore, an unplanned release has occurred from Unit Comments:

Cue: , STEP UNPLANNED OR UNMONITORED Candidate recognizes that the Critical:

Grade #25 LIQUID RELEASE: release was gaseous, therefore this Y[ J N[X] S[]U[] calculation does not apply. , Comments:

Cue: , STEP Refer To the following and Candidate refers to Attachment 8, Critical:

Grade #26 DETERMINE if release exceeds limits: Section 2, and reviews to determine if Y [ ] N [X] S[]U[] the release exceeds a limit. RAC 14, step Attachment 8, Section 2, 4.2.8 "Reportable Releases." Attachment 8, Section 4, Reportable Releases." Comments:

Cue:

STEP Unplanned Gaseous Releases (State Candidate recognizes that 2478 Critical:

Grade #27 Regulation)

..,ci/sec is NOT <1500 Y[X] N[l S[lU[] Therefore, an unplanned gaseous RAG 14, Att 8 Any increase in noble gas release release has occurred from Unit 3.Section 2 rates which, when averaged over 10 minutes, is greater than 1500 microcuries/sec above the normal (existing) release rate and this increase is not due to a planned or expected event as listed in Section 6, "Maintenance Operations." Comments:

Cue: Candidate refers to Attachment 8, Critical:

Grade Section 4 (EPA Reportable Y [ ] N [X] S[]U[] Releases), and reviews to determine if the release exceeds a limit. Comments:

Once the Candidate refers to Section 4 (EPA Reportable Releases), provide the following cue: Cue: Chemistry has determined that the release did NOT exceed 40CFR302 limits. STEP IF release exceeds limits, Refer To Candidate refers to Attachments 1 Critical:

Grade #28 appropriate Attachments 1 through 7 through 7 and determines that Y [ ] N [X 1 S[lU[l and DIRECT Emergency Attachment 2, "Radiological RAG 14, step Communicator to perform Section 4.7, Events", is the applicable 4.2.9 I"Radiopager Notifications." attachment.

Comments:

18 I Cue: Candidate directs the Emergency Critical:

Grade Communicator to perform Section Y[] N[X] S[]U[] 4.7, "Radiopager Notifications." Comments:

Provide the following cue: Cue: The Emergency Communicator is performing Section 4.7, "Radiopager Notifications." STEP Candidate matches the event in Critical:

Grade #29 progress with the following event Y [ ] N [X] S[]U[] description in attachment 2: "Any unplanned, unmonitored, or unauthorized release of radiological material to the environment." Critical:

Grade Candidate correctly determines the Y[X]N[ ] S[]U[]NRC Reporting Requirement for the event is as follows: "Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> via ENS" (1 OCFR50.72(b

)(2)(xi) Critical:

Grade Candidate correctly determines the Y[X]N[] S[]U[]State posture code for the event is an "Foxtrot" -_.... _ .... _-_.. _.-'----_... _._._.... _...__.... -.... -... _-.... -_ .... _-------_.... _ .... _ ... _-.... -.... _ .... _ .... _ .... _.... _ .... __

Candidate correctly determines the State Reporting Requirement for the event is as follows: Critical:

Y[X]N[] Grade S[]U[] I "Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of report to NRC" (State Reg. 22a-135-11 ENV 4.1.6.1) Comments:

Cue: STEP #30 Determine additional requirements.

Candidate correctly determines that NOTEs 1, 17 and 19 to Attachment 2 of RAC 14 apply. Critical:

Y[] N[X] Grade S[]U[] Comments:

NOTES are located in Attachment 7 to RAC 14. I RAC 14, Att 7 NOTE 1 RAC 14, Att 7 NOTE 17 I Refer To Attachment 15 for additional notifications.

When Federal and State reporting requirements overlap, the "Clock" for the State reporting does not start until the report is made to the Federal Authority.

Candidate reviews Attachment 15 and determines that no additional notifications are required.

Candidate reviews the NOTE. Critical:

Y[] N[X] Critical:

Y[] N[X] Grade S[]U[] Grade S[]U[] 20 I I RAG 14, Att 7 NOTE 19 The existing CR process is to be used to identify any spills and/or leaks of radioactive liquid. Chemistry, HP and/or Station Licensing personnel will Candidate recognizes that the release was gaseous, therefore this NOTE does not apply. Critical:

Y[] N[X] Grade S[]U[] perform any necessary evaluations based on CR information and subsequent investigations as appropriate, and determine if GPI reporting is necessary.

STEP IF applicable, Refer To Section 4.9, Candidate refers to Section 4.9. Critical:

Grade #31 "NRC Notifications." Y [ ] N [X] S[}U[] RAG 14, step 4.2.10 Comments:

Once the Candidate refers to Section 4.9, provide the following cue: Cue: The Emergency Communicator will prepare and send the Non Emergency Event Report and the Station Duty Officer will complete the remaining required notifications.

_____

for this JPM is STOP TIME: ___

---VERIFICATION OF ..IPM

• .IPM Number: SROA.3 Revision: Date For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.

If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade. Time Critical Task? Yes No X Validated Time (minutes):

30 Actual Time to Complete (minutes):

Overall Result of JPM: SAT UNSAT Areas for Improvement

/ Comments:

STUDENT JPM Number: Initial Conditions:

Initiating Cues: SROA.3 Revision:

o The plant is at 100% power, and you are the Extra Senior Operator on shift. About 15 minutes ago MB2B 2-8 ALERT" alarmed, followed shortly thereafter by MB2B 2-8 "RAD The RO has determined and reported that 3HVR*RE1 OB is in The Control Room Team has entered AOP 3573, Radiation Alarm Response, and are taking appropriate actions 3HVR*RE10B, including attempting to identify the source radiation.

There is no indication that there is an equipment associated with The SM has directed you to carry out action step 4 of Attachment to AOP 3573 for 3HVR*1 OB, "Take appropriate action using EPI-FAP06-003, Unit 3 Emergency Action Levels Releases Write down your response(s)

JOB PERFORMANCE MEASURE APPROVAL JPM Title: Align Safety Grade Boration Path ...IPM Number: 2K11 NRC S.1 Revision:

o Initiated:

2/18/11 Developer Date Reviewed:

5/5 III Technical Reviek Date Approved:

SUMMARY

OF I DATE DESCRIPTION !

---JPM Facility: Examinee: MP_3____ JPM Number: 2K11 NRC S.1 Revision:

o Task Title: Align Safety Grade Soration Path System: 004 -CVCS Time Critical Task: ) YES (X) NO Validated Time (minutes):

___5__Task Number(s):

344-05-043, Applicable To: SRO X RO X PEO KJA APE: 024 AA1.17 KJA Rating: 3.9/3.9 Number: 004-A4.07 3.9/3.7 Method of Simulated Actual Performance:

Performance:

Classroom:

Simulator:

X In-Plant:

Task All critical steps are performed satisfactorily.

All sequential steps are performed in proper procedural sequence.

Reguired Materials:

AOP 3566, Immediate Boration. (procedures, equipment, etc.) MP3 Simulator General AOP 3566, Immediate Boration, Rev 010-01 ES-0.1, Reactor Trip Response, Rev 024 X

• • • READ TO THE EXAMINEE I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this JPM will be satisfied.

You may use any approved reference material normally available i[l the Control Room, including logs. Make all written reports, oral reports. alarm acknowledgements, and log entries as if the eVolution was actually being performed.

JPM WORKSHEET JPM Number: 2K11 NRC Revision:

o Simulator Requirements:

1. Reset to IC 291 .... OR Reset IC 18 (or any 100% Pwr IC), and carry out steps 6 below: Insert malfunction RD16 (Control Rods Fail to Fully Insert) Insert malfunction ED040 (loss of emergency bus 340), and place the simulator in RUN. Carry out the first 9 steps of AOP 3577 to stabilize the primary and secondary. Insert malfunction CV18 at 0% (Fails 3CHS*FCV121 closed), and then TC01 (turbine trip): Carry out the immediate actions of E-O and the first 5 steps of ES-0.1. Place the simulator in "Freeze" Approximate setup time is 10 minutes. Initial The plant was at 100% power with emergency bus 340 deenergized due to a bus differential lockout relay actuation.

Moments ago the turbine tripped which caused a reactor trip. Several control rods failed to fully insert. The US has entered ES-O.1 , Reactor Trip Response, and actions are complete up through step 5. Initiating The US has directed you to initiate an immediate boration of the RCS, starting with step 1 of AOP 3566. * * *

• NOTES TO TASK PERFORMANCE EVALUATOR * * *

• Critical steps for this JPM are indicated by checking lOY". For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly. When the student states what his/her simulated action/observation would be, read the 4 appropriate "Cue". If necessary, question student for details of simulated actions/observations (i.e. "What are you looking at?" or "What are you observing?"). Under NO circumstances must the student be allowed to manipulate any devices during the performance of this JPM (in-plant only).

---PERFORMANCEJNFORMATION JPM Number: 2K11 NRC Revision:

° Task Title: Align Safety Grade Soration Path START TIME: ____ PERFORMANCE STEP STANDARD STEP Obtains copy of AOP Critical:

Grade Obtains a copy of AOP 3566, and Y[]N[X] 8[]U[]refers to the CAUTION prior to step 1 Comments:

Cue: STEP If SI actuation occurs during Critical:

Grade Candidate reviews CAUTION. procedure, Go to E-O, Reactor Trip Y[]N[X] 8 [ ] U [ ]

or Safety Injection, and restore from 3566 s t e p 1 immediate boration lineup. CAUTION Comments:

Cue: STEP Initiate Immediate Boration Critical:

Grade Determines that that the 'A' charging RCS. Y[]N[X] 8[]U[]pump is running by observation 3566 indicating lights, amps, flow 1 step Check one charging pump Comments:

Cue:

---

STEP Align boration flow path. Starts at least one boric acid transfer Critical:

Grade #4 pump by depressing the START push Y[]N[X] S[]U[) 3566 1 ) START at least one boric acid button on pump controller and s t e p 1.b.1) transfer pump observes START push button lights and STOP push button extinQuishes.

Comments:

Cue: STEP 2) OPEN emergency boration Recognizes emergency boration valve Critical:

Grade #5 valve (3CHS*MV81

04) (3CHS*MV81

04) will not open Y[]N[X] S[]U[]3566 indicating lights are all OFF. s t e p 1 . b . 2 )

Transitions to the RNO column. Comments:

3CHS*MV8104 is powered from 340 which is deenergized.

Cue: STEP Perform the following:

Opens the 'A' gravity boration valve, Critical:

Grade #6 3CHS*MV8507 A, by depressing the Y[X]N[ ] S[]U[]3566 OPEN at least one gravity feed OPEN push button and observing step 1.b RNO boration valve. lights shift to green OFF, red ON. Comments:

3CHS*MV85078 is powered from 340. Cue: STEP Observes 3CHS*FCV121 indicates in Critical:

Grade Limit net charging flow to the RCS to #7 the closed position.

The candidate may Y[] N[X] S[]U[]LESS THAN 75 gpm (Charging attempt to throttle FCV121 seal injection

-RCP seal depressing 11 and/or U push i Comments:

3CHS*FCV121 is failed closed. Cue: STEP CLOSE at least one VCT outlet Critical:

Grade Closes the 'A' VCT outlet isolation

1. 8 isolation valve. Y[X]N[ ] S[]U[]valve 3CHS*LCV1128 by CLOSE push button and indicating lights shift to green ON, red Comments:

3CHS*LCV112C is powered from 340. 7 r-Cue: STEP VERIFY closed both RWST to Determines that RWST to charging Critical:

Grade #9 charging pump suction isolation pump suction isolation valve, Y[] N[X] S[]U[] valves. 3CHS*LCV112D is closed by observing indicating lights green ON, red OFF. Recognizes 3CHS* LCV112E has no power -indicating lights are all OFF. Comments:

Examinee may report to US that 3CHS* LCV112E has no power, but should be closed since SI has not occurred.

If the Candidate asks for US direction, provide the following cue: Cue: Assume 3CHS* LCV112E is closed and continue in AOP 3566. i I STEP Check normal charging flow path Attempts to throttle charging flow Critical:

Grade aligned control valve (3CHS*FCV121) by Y[] N[X] S[]U[]3566 step 1.c Charging flow control valve depressing 11' and/or ij. push CAPABLE OF BEING Recognizes that 3CHS*FCV121 THROTTTLED failed closed and is NOT capable being throttled.

Transitions to the RNO column. Comments:

3CHS*FCV121 is failed STEP Position valves as required to Applicant proceeds to step 2 of AOP Critical:

Grade #11 establish a controllable normal 3566. Y[ ] N[X] S[]U[]3566 charging flow path. step l.c IF a controllable normal flow path can NOT be THEN Proceed to step

---

STEP Align Safety Grade Boration Path Determines Bus 340 is deenergized by Critical:

Grade #12 observation of the MB8 emergency bus Y[] N[X] S[]U[]3566 Check emergency busses 34C voltage indicators reading 0 volts, step 2.a and 340 -BOTH emergency load center ENERGIZED indicators (4) reading 0 volts, MB8C 4-2, BUS 340 BUS DIFF, Applicant transitions to the RNO column. Comments:

The applicant was given that 340 was deenergized in the initiating cue, and may already have verified as such. Cue: STEP Perform the applicable action: Determines Bus 34C is energized by Critical:

Grade #13

• IF emergency bus 34C is observation of the MB 8 emergency Y[] N[X] S[]U[]3566 bus voltage indicators reading about energized, 2.a RNO 4160 volts OR emergency load center Proceed to step voltage indicators (8) reading about 480 volts. Proceeds to step 2.b. Comments:

Cue: STEP OPEN charging header flow control Applicant throttles open Critical:

Grade #14 valve (3CHS*HCV190A) 3CHS*HCV190A by depressing 11 push Y [X] N [ ] S[]U[]3566 step button. Observes valve indicate full Comments:

Cue: STEP OPEN charging header bypass Opens 3CHS*MV8116 by depressing Critical:

Grade #15 isolation (3CHS*MV8116) the OPEN push button and observing Y [Xl N [ ] S[]U[)3566 lights shift to green OFF, red ON. step 2.e Comments:

Cue: 9

-STEP CLOSE charging flow control Recognizes 3CHS*MV81 06 has no Critical:

Grade #16 outlet isolation (3CHS*MV81

06) power -indicating lights are all OFF. Y[] N[X] S[]U[]step Transitions to the RNO column. Comments:

Cue: STEP Perform the applicable action: Observes 'A' charging pump is running Critical:

Grade #17 IF a Train A charging pump by checking red indicating light, proper Y[] N[X] S[]U[]3566

• step 2.d is running, amps, flow, Proceed to step 2.h. Proceeds to step Comments:

Cue: STEP Locally Perform the following while Applicant calls a PEO or requests from Critical:

Grade #18 maintaining RCP seal injection the US a PEO to be dispatched to the Y [X] N [ ] S[JU[]3566 between 8 and 13 gpm: Aux Building and establish step 2.h. 1 1) Throttle Open the operating communications to throttle charging pump bypass valve For pump Comments:

Cue: BOOTH: Insert remote CVR84 and adjust to obtain 8 to 9 gpm (about 70%). Report as PEO that 3CHS*V272 has been throttled open. STEP 2) Close the charging header Applicant directs the PEO to close Critical:

Grade #19 to seals isolation valve (3CHS*V273) 3CHS*V273.

Y[] N[X] S[]U[]3566 step 2.h. 2 ) Comments:

Cue: BOOTH: Insert remote CVR87 and adjust to 0% (closed).

Report as PEO that 3CHS*V273 is closed. ---...................

.........-.-.......-.. 10

-STEP Check Train A charging pump Observes 'A' charging pump is running Critical:

Grade #20 -RUNNING by checking red indicating light, proper Y[] N[X] S[]U[]3566 amps, flow, etc. step 2.i Comments:

Cue: STEP CLOSE charging header isolation Closes 3CHS*MV8438A by depressing Critical:

Grade #21 valve (3CHS*MV8438A)

CLOSE push button and observing Y [Xl N [ ] S[]U[]3566 indicating lights shift to green ON, red step 2.j OFF. Comments:

If the applicant reports that immediate boration has been initiated, give the following cue: Cue: Continue in AOP 3566. STEP Verify Boration Flow Verifies pressurizer pressure is less Critical:

Grade #22 than 2350 psia by checking any of the Y[] N[X] S[]U[]3566 Check PZR pressure -following:

step 3.8 LESS THAN 2350 Meters: RCS-PI455A, 456A, 457 Recorder:

Comments:

Cue: STEP Check normal charging flow Checks charging flow and valve line up Critical:

Grade #23 path -ALIGNED and recognizes that the Safety Grade Y[ J N[X] S[]U[]3566 Boration flowpath is not the normal step 3.b charging flow path. Transitions to the RNO column. Comments:

Cue:

I STEP Isolate normal Candidate observes that a letdown Critical:

Grade #24 orifice isolation is open, and closes Y[X]N[ ] S[]U[]3566 3CHS*AV8149C by depressing the step 3.b CLOSE push button and indicating lights shift to green ON, Comments:

The Candidate may instead close 3CHS*CV8160 or *CV8152 to isolate letdown. This is satisfactory.

Cue: STEP Perform the following:

Critical:

Grade I F a safety grade boration flow path Y[]N[X] S[]U[] is established, THEN Using GA-14, Establish reactor vessel head vent letdown to the VCT. Comments:

Once the applicant obtains GA-14, provide the following cue; Another RO will establish head vent letdown to the VCT. I CUE: The evaluation forthisJPM is concluded.

TERMINATION CUE: The evaluation for this JPM is concluded.

STOP TIME: ____

---VERIFICATION OF JPM JPM Number: 2K11 NRC S.1 Revision: Date To achieve a satisfactory grade, ALL critical steps must be completed correctly.

If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade. Time Critical Task? Yes No X Validated Time (minutes):

5 Actual Time to Complete (minutes):

Overall Result of JPM: SAT UNSAT Areas for Improvement I Comments:

JPM Number: Initial Conditions:

Initiating Cues: STUDENT HANDOUT 2K11 NRC 5.1 Revision:

o The plant was at 100% power with emergency bus 340 deenergized due to a bus differential lockout relay actuation.

Moments ago the turbine tripped which caused a reactor trip. Several control rods failed to fully insert. The US has entered 0.1, Reactor Trip Response, and actions are complete up through step 5. The US has directed you to initiate an immediate boration of the ReS, starting with step 1 of AOP 3566. l 14 ____------l JOB PERFORMANCE MEASURE APPROVAL JPM Title: Respond to an Inadvertent Containment Isolation Phase JPM Number: 2K11 NRC S.2 Revision: Initiated: Dave Minnich 2/22/11 Developer Date Reviewed:

51s In Technical eVlewer Date Approved:

Supervisor, Nuclear Training

SUMMARY

OF CHANGES DATE DESCRIPTION REV/CHANGE l___2 ___

---JPM Facility:

___ ____

Examinee:

• .lPM Number: 2K11 NRC Revision:

0 Task Title: Respond to an Inadvertent Containment Isolation Phase 'A'. System: ESF (013) Time Critical Task: ) YES (X) NO Validated Time (minutes):

___1....;2__ Task Number(s):

013-04-012 Applicable To: SRO X RO X PEO KJA 013 A4.02 KJA Rating: 4.3/4.4 Number: Method of Testing: Simulated Actual Performance:

Performance:

Location:

Simulator:

X In-Plant:

Task All critical steps are performed satisfactorily.

All sequential steps are performed in proper procedural sequence.

Required Materials:

AOP 3578, Response to an Inadvertent Containment Isolation Phase A (procedures.

equipment.

etc.) MP3 Simulator General AOP 3578, Response to an Inadvertent Containment Isolation Phase A (revision 000) X

• • • READ TO THE EXAMINEE I will explain the initial conditions.

which step(s) to simulate or discuss. and provide initiating cues. When you complete the task successfully.

the objective for this JPM will be satisfied.

You may use any approved reference material normally available in the Control Room. including logs. Make all written reports. oral reports. alarm acknowledgements.

and log entries as if the evolution was actually being performed.

JPM WORKSHEET JPM Number: 2K11 NRC Revision:

o Simulator Requirements:

1. Reset to IC 254 .... OR Reset to Ie 18. 100% steady state. MOL (or any 100% Power IC), and carry out steps 3 -5 below. Insert malfunctions RP03A1B (Containment Isolation phase A, train A and B. Place the simulator in RUN, wait for all CIA actuated components to fully reposition. Remove malfunctions RP03A1B (This will allow the examinee to reset CIA). Place the simulator in "Freeze" Approximate setup time is 5 minutes. Initial The plant was at 100% power when an Inadvertent Containment Isolation Phase A (CIA) occurred while conducting SSPS surveillance testing. Initiating The US has directed you to carry out the actions of AOP 3578, Response to an Inadvertent Containment Isolation Phase A, starting with step 1. 'It 'It 'it 'It NOTES TO TASK PERFORMANCE EVALUATOR 'it 'it 'it

'it Critical steps for this JPM are indicated by checking "Y". For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly. When the student states what his/her simulated action/observation would be, read the appropriate "Cue". If necessary.

question student for details of simulated actions/observations (Le. "What are you looking at?" or "What are you observing?"). Under NO circumstances must the student be allowed to manipulate any devices during the performance of this JPM (in-plant only). 4

---

PERFORMANCE INFORMATION JPM Number: 2K11 NRC S.2 Revision:

o Task Title: Respond to an Inadvertent Containment Isolation Phase 'A'. START TIME: PERFORMANCE STANDARD STEP Obtains copy of AOP 3578. Obtains a copy of AOP 3578 and refers to Critical:

Grade #1 the CAUTION and NOTE prior to step 1 . Y [ ] S [ J N[X] U [ ] Comments:

Cue: STEP If a Reactor Trip occurs or is required, go to Candidate reviews CAUTION. Critical:

Grade #2 E-O, Reactor Trip or Safety Injection. Y [ ] S [ ] AOP N[X] U [ ] S t e p Comments:

Cue: STEP Components and recovery actions are Candidate reviews NOTE. Critical:

Grade #3 listed in OA 2, "OMOC On-Call Y [ ] S [ ] 3578 Responsibilities" Attachment 3, "ESF N[X] U [ ] S t e p 1 NOTE Actuation Checklist".

Comments:

If the Candidate takes action to reference OA 2, provide the following cue: Cue: The SM will refer to OA 2.

---

STEP Verify Containment Isolation #4 NOT 3578 Step 1.a Check safety injection signal-NOT ACTUATED Comments:

Cue: STEP Reset CIA #5 3578 Step l.b Comments:

Cue: STEP Notify I&C to investigate the cause of the #6 inadvertent CIA signal 3578 Step 1.c Comments:

Cue: STEP Check If Letdown Is Check letdown containment isolation 3578 valves-CLOSED Step 2 3CHS*CV8152 OR

• 3CHS*CV8160 Comments:

Cue: AT MB4 or MB2, observes that the Injection Actuation annunciator is NOT Candidate resets CIA by depressing the Train A and Train B CIA reset push buttons on MB2. Candidate calls I&C to investigate or requests the US make the call to I&C. Candidate checks 3CHS*CV8152 and/or 3CHS*CV8160 are Closed by observing indicating lights as green ON, red OFF. Critical:

Grade V [ ] S [ ]

N[X] U [ ] I Critical: V[X] S [ N [ ] U [

Critical: V [ ] S [

N[X] U [ Critical: V [ ] S [ N[X] U [

STEP CLOSE Letdown orifice Closes the 'C' Letdown orifice isolation Critical:

GraCi"e #8 isolation valves: valve, 3CHS*AV8149C by depressing Y[X] S [ ] 3CHS* AV*8149A CLOSE push button and observing N [ ] U [ ]

3578

• Step 2.b 3CHS*AV*8149B indicating lights shift to green ON, red* OFF.* 3CHS*AV*8149C Comments:

Cue: STEP CLOSE charging flow control Throttle Closed charging flow control Critical:

Grade #9 valve, 3CHS*FCV 121 valve (3CHS*FCV121) by depressing the Y[X] S [ ] U. push button and observes no charging N [ ] U [ ] 3578 Step 2.c flow. Comments:

Cue: STEP Adjust seal injection flow, as necessary to Candidate throttles 3CHS*HCV182 as Critical:

Grade #10 control pressurizer level-necessary by rotating potentiometer of Y[X] S [ ] 3578 8 TO 13 GPM 3CHS*HC182 (MB3). N [ ] U [ ]

Step 2.d Observes seal flow between 8 and 13 Critical:

Grade gpm by checking the RCP seai injection Y [ ] S [ ] flow indicators (3CHS-N[X] U [ ] FI145A1144A1143A1142A).

Comments:

Candidate should throttle seal injection to the low end of the specified band (about 8gpm) to minimize the increase in PZR level. Cue: STEP Establish Instrument Air To Candidate determines that that the 'B' Critical:

Grade #11 Containment instrument air compressor is running by Y [ ] S [ ] observing indicating lights green OFF, red N[X] U [ ] 3578 Check instrument air compressors-ON (MB1). Step 3.a AT LEAST ONE RUNNING Comments:

7

---

Cue: STEP OPEN instrument air Ctmt isolation valves: Opens 3IAS*PV15 by depressing the #12

• 3IAS*PV15 OPEN push button and observing lights 3578 Step 3.b

• shift to green OFF, red ON. Opens 3IAS*MOV72 by depressing the OPEN push button and observing lights shift to green OFF, red ON. Comments:

The instrument air Ctmt isolation valves can be opened in any order. Cue: STEP Align RCP Seal Return Flow To Opens 3CHS*MV81 00 by depressing the #13 Charging Pump Suction OPEN push button and observing lights shift to green OFF, red ON. 3578 Step OPEN seal return containment

• 3CHS*MV8100

• 3CHS*MV8112 Opens 3CHS*MV8112 by depressing the OPEN push button and observing lights shift to green OFF, red ON. Comments:

The seal return containment isolation valves can be opened in any order. Cue: STEP Check If Normal Letdown Can Be Candidate checks PZR level greater than #14 Established 22% by observing CVCS trend for L461 on the PPC, OR checking meters 3578 Check pressurizer level -RCS*Ll459A, Ll460A and Ll461A on Step 5.a GREATER THAN MB4. Comments:

8 -Critical:

Grade Y[X] S [ ] N [ ] U [ ] Critical:

Grade Y[X] S [ ] N [ ] U [ ] Critical:

Grade Y[X] S [ ] N [ ] U [ ] , Critical:

Grade Y[X] S [ ] N [ ] U [ ] Critical: Y [ ] S [ N[X] U [ I

---

Cue: STEP Establish normal letdown flow using GA-13 Critical:

Grade #15 y [ ] S [ ] 3578 N[X] U [ ] Step 5.b Comments:

Once the Candidate obtains GA-13, provide the following cue; Cue: Another RO will establish normal letdown flow using GA*13. STEP Restore RPCCW System To Normal Critical:

Grade Determines that there is adequate#16 y [ ] S [ ] Thermal barrier cooling by observing Check RCP thermal barrier N[X] U [ ] thermal barrier flow low annunciators not 3578 Step 6.a cooling -ESTABLISHED TO ALL RCPs in alarm and/or valves 3CCP*AOV178A1B/C/D open by observing indicating lights green OFF, red ON. Comments:

Cue: STEP Restore Reactor Plant Chill Water System: Candidate informs the US to Refer to T.S. Critical:

Grade #17 3.6.1.4 and 3.7.14. Y [ ] S [ ] 3578 Refer to T.S. 3.6.1.4 and 3.7.14. N[X] U [ ] 6 b. 1 I Comments:

Cue: STEP Refer to OP 3330C, "Recover from Loss Of Critical:

Grade #18 Power, Containment Isolation Phase A, or Y [ ] S [ ] 3578 Loss of Instrument Air" and Restore N[X] U [ ] 6.b.2) containment and non-safety Comments:

Cue: Another RO will restore containment and non-safety headers, and complete step 6. Continue in AOP 3578.

STEP Restore Affected Systems Candidate determines that 3CMS*CTV20, Critical:

Grade #19 21, 23 and MOV24 are CLOSED by Y [ ] S [ ] Check RCS leakage monitor, 3CMS*RE 22 observing indicating lights as green ON, N[X] U [ J Step -IN SERVICE WITH THE FOLLOWING red OFF. VALVES Transitions to the RNO

• 3CMS*CTV 20

• 3CMS*CTV 21

• 3CMS*CTV 23

• 3CMS*MOV 24 Comments:

Cue: STEP Place 3CMS*RE 22 in service as follows: Candidate informs the US to refer to T.S. Critical:

Grade #20 3.3.3.1 and 3.4.6.1. Y [ ] S [ ] 3578 Refer to T.S. 3.3.3.1 and 3.4.6.1 N[X] U [ ] Comments:

Cue: STEP OPEN the following Opens 3CMS*CTV20 by depressing the Critical:

Grade #21 OPEN push button and observing lights Y[X] S [ ] 3CMS*CTV 20 shift to green OFF, red ON. N [ ] U [ ] 3578

• Step

• 3CMS*CTV

• 3CMS*CTV 23

• 3CMS*MOV 24 Opens 3CMS*CTV21 by depressing the Critical:

Grade OPEN push button and observing lights Y[X] S [ ] shift to green OFF, red ON. N [J U [ ] Opens 3CMS*CTV23 by depressing the Critical:

Grade OPEN push button and observing lights Y[X] S [ ] shift to green OFF, red ON. N [ ] U [ ] 10 Opens 3CMS*MOV24 by depressing the Critical:

Grade OPEN push button and observing lights Y[X] S [ ] shift to green OFF, red ON. N [ ] U [ ]

Comments:

The CMS containment isolation valves can be opened in any order. Cue: STEP Refer to OP 33128 and Restore Critical:

Grade #22 3CMS*RE22 to service. Y [ ] S [ ] 3578 N[X] U [ ] S t e Comments:

Cue: Another RO will restore 3CMS*RE22 to service. STEP 3DGS*CTV24 and 3DAS*CTV24 need to Candidate reviews NOTE. Critical:

Grade #23 be reset following CIA by momentarily Y [ ] S [ ] depressing AUTO I OPEN. When N[X] U [ ] 3578 Step 7.b momentarily depressing AUTO I OPEN, 3DGS*CTV24 or 3DAS*CTV24 may open until the next pumping .Comments:

Cue: ! STEP Check Reactor Plant Gaseous Drains -IN Candidate determines that 3DGS*CTV24 Critical:

Grade* #24 SERVICE WITH THE FOLLOWING and 25 CLOSED by observing indicating Y [ ] S [ ] 3578 VALVES OPEN: lights as green ON, red OFF. Transitions N[X] U [ ] Step 7.b to the RNO column.

• 3DGS*CTV24

• 3DGS*CTV25 Comments:

Cue:

STEP Perform the 3578 OPEN 3DGS*CTV25.

Step Comments:

Cue: STEP Momentarily press 3DGS*CTV24

1. 26 AUTO/OPEN.Step RNO Comments:

Cue: STEP Check Reactor Plant Aerated Drains -IN #27 SERVICE WITH THE FOLLOWING VALVES OPEN: Step

• 3DAS*CTV24

• 3DAS*CTV25 Comments:

Cue: STEP Perform the following:

1. 28 3578 Refer to T.S. 3.4.6.1. Step Comments:

Cue: STEP OPEN 3DAS*CTV25.

1. 29 Comments:

Cue: Opens 3DGS*CTV25 by depressing the OPEN push button and observing lights shift to green OFF, red ON. Candidate Momentarily depresses the 3DGS*CTV24 AUTO IOPEN push button and observes the valve remains closed. Candidate determines that 3DGS*CTV24 and 25 CLOSED by observing indicating lights as green ON, red OFF. Transitions to the RNO column. Candidate informs the US to refer to T.S. 3.4.6.1. Opens 3DAS*CTV25 by depressing the OPEN push button and observing lights shift to green OFF, red ON. Critical:

Y[X] N [ ] Y [ Critical: Y [ ] N[X] Y [ Critical:

Y[X] N [ ] Grade S [ U [ S [ U [ S [ U [ S [ U [ S [ U [

--STEP #30 STEP #31 STEP #32 3578 Step 7.d STEP #33 3578 Step 7.d RNO STEP #34 Momentarily press 3DAS*CTV24 AUTO/OPEN.

Verify 3DAS*P2A I Band 3DAS-P10 automatic operation.

Check Reactor Plant Gaseous Vents -IN SERVICE WITH THE FOLLOWING VALVES OPEN:

• 3VRS*CTV20

• 3VRS*CTV21 Perform the following:

OPEN 3VRS*CTV20.

OPEN 3VRS*CTV21.

Candidate Momentarily depresses the 3DAS*CTV24 AUTO /OPEN push button and observes the valve remains closed. Candidate calls up Reactor Plant Aerated Drains -Containment Drains on R*Time (or corollary display on PPC) to monitor CTMT sump level and 3DAS*P2A I Band 3DAS-P10 activity.

Candidate determines that 3VRS*CTV20 and 21 CLOSED by observing indicating lights as green ON, red OFF. Transitions to the RNO column. Opens 3VRS*CTV20 by depressing the OPEN push button and observing lights shift to green OFF, red ON. Opens 3VRS*CTV21 by depressing the OPEN push button and observing lights shift to green OFF, red ON. Critical: Y [ J S [ N[X] U [ Critical: Y [ ] S [ N[X] U [ Critical:

Grade Y [ ] S [ 1 N[X] U [ ] . Critical: Y[X] S [ N [ ] U [

Critical: Y[X1 S [ Nll U [

-STEP Reset RCS leak rate program. The Candidate calls up RCS Leakage on Critical:

Grade #35 R*Time (MP3 Top Menu / NSSS / RCS Y [ ] S [ ] Leakage) to reset the RCS leak rate N[X] U [ ] program. Comments:

Cue: STEP Check fire protection water to containment Candidate determines that 3FPW*CTV48 Critical:

Grade #36 valves -OPEN: and 49 are CLOSED by observing Y [ ] S [ ] 3578 indicating lights as green ON, red OFF. N[X] U [ ] Step 7.e 3FPW*CTV49 Transitions to the RNO

• Comments:

Cue: STEP Perform the following:

Candidate informs the US to refer to Critical:

Grade #37 3TRM -3.7.12.2 and 3TRM -3.7.12.5. Y [ ] S [ ] 3578 Refer to 3TRM-3.7.12.2 and N[X] U [ ] Step 7.e RNO 3TRM-3.7.12.5.

Comments:

Cue: STEP OPEN 3FPW*CTV48.

Opens 3FPW*CTV48 by depressing the Critical:

Grade #38 OPEN push button and observing lights Y[X] S [ ] shift to green OFF, red ON. N [ ] U [ ]

• Comments:

Cue: STEP OPEN 3FPW*CTV49.

Opens 3FPW*CTV49 by depressing the Critical:

Grade #39 OPEN push button and observing lights Y[X] S [ ] shift to green OFF, red ON. N [ ] U [ ]

Comments:

Cue: 14

-STEP Check PGS to containment valves-OPEN: Candidate determines that 3PGS* Critical:

--Grade #40 CV8046 and CV8028 are CLOSED by Y [ J S [ ] 3578 Step 7.f

• 3PGS*CV8046 observing indicating lights as green ON, N[X] U [ J

• 3PGS*CV8028 red OFF. Transitions to the RNO column. Comments:

Cue: STEP OPEN valves as directed by SM! US. Candidate requests from the US whether Critical:

Grade #41 to open the PGS to containment valves. Y [ ] S [ ] Step 7.f N[X] U [ Comments:

When asked, provide the following cue: , i Cue: Open the PGS to containment valves. J STEP Opens 3PGS* CV8046 by depressing the Critical:

Grade I #42 OPEN push button and observing lights Y[X1 S [ ] shift to green OFF, red ON. N [ ] U[J_ Comments:

Cue: STEP Opens 3PGS* CV8028 by depressing the Critical:

.-Grade #43 OPEN push button and observing lights Y[X] S [ ] shift to green OFF, red ON. N [ ] U [ ]

Comments:

The PGS to containment valves can be opened in any order. Cue: STEP If Necessary, Refer To OA 2 attachment Candidate informs the US to refer to OA 2 Critical:

Grade #44 3, "ESF Actuation Checklist", And Verify attachment 3, "ESF Actuation Checklist" Y [ ] S [ ] Normal Component Position to verify normal component position.

N[X] U [ ] S t e p Comments:

-Cue: Another RO will carry out attachment 3 to OA 2.

STEP Determine If Plant Operation Can 1) Candidate informs the US to refer to Critical:

Grade #45 Continue T.S. 3.3.2.a, 3.4.6.1, and 3.3.3.1. Y [ ] S [ ] 3578 N[X] U [ ] S t e p 9 Cue: The US will check Tech ..........

_-.........-.-.......-.--........ ........._._--........_._-......._.. _---...........

--TERMINATION CUE: The evaluation for this JPM is concluded.

STOP TIME: ___

---VERIFICATION OF ..IPM JPM Number: 2K11 NRC S.2 Revision: Date To achieve a satisfactory grade, ALL critical steps must be completed correctly.

If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade. Time Critical Task? Yes 1\10 X Validated Time (minutes):

12 Actual Time to Complete (minutes):

Overall Result of JPM: SAT UNSAT Areas for Improvement

/ Comments:

JPM Number: Initial Conditions:

Initiating Cues: STUDENT HANDOUT 2K11 NRC S.2 Revision:

0The plant was at 1 00% power when an Inadvertent Containment Isolation Phase A (CIA) occurred while conducting SSPS surveillance testing. The US has directed you to carry out the actions of AOP 3578, Response to an Inadvertent Containment Isolation Phase A, starting with step 1.

JOB PERFORMANCE MEASURE APPROVAL SHEET "IPM Title: Perform ReS Bleed and Feed Per FR-H.1 JPM Number: 2K11 NRC S.3 (JPM-039A)

Revision:

0 chg 4 Initiated:

Dave Minnich 2/23/11 Developer Date Reviewed: . , Technical eviewer Date Approved:

I /Date ____------I l

SUMMARY

OF DATE DESCRIPTION REV/CHANGE 02/23/11 Modified JPM format to be consistent with the NRC 2K11 0/4 JPM set. Verified JPM updated through Revision 020-01 to FR-H.1. Changed the JPM standard for checking Charging and 81 pumps running to 'andlor', as step 12 in FR-H.1 infers. Combined two JPM steps into one for the check of PORV open indications.

Deleted TR-AA-410 Pass/Fail criteria.

JPM Facility:

_M_P...;..3

____

JPM Number: 2K11 NRC S.3 Revision:

0 chg Task Title: Perform RCS Bleed and Feed Per System: 3 -010 (PZR Pressure Time Critical Task: ) YES (X) Validated Time (minutes):

___Task Number(s):

Applicable To: SRO X RO X PEO __KlA Number: EPE: E05-EA 1.1 KlA Rating: Method of Testing: Simulated Actual X Performance:

Performance:

Location:

Classroom:

Simulator:

X In-Plant:

Task Standards:

Satisfactorily complete the establishment of an ReS bleed and feed using All critical steps are performed satisfactorily.

All sequential are performed in proper procedural Reguired Materials:

FR-H.1 , RESPONSE TO LOSS OF SECONDARY HEA T SINK (procedures, equipment, etc.) MP3 Simulator General

References:

EOP 35 FR-H.1, Rev. 020-01

• • • READ TO THE CANDIDATE I will explain the initial conditions, which step{s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this JPM will be satisfied.

You may use any approved reference material normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.

JPM WORKSHEET JPM Number: 2K11 NRC 5.3 Revision:

o Simulator Requirements:

Initial Conditions:

1. Reset to any 100% Power IC. 2. Insert the following malfunctions (or run schedule JPM039A):

• FW18A -"A" MDAFW pump trip

• FW188 -"8" MDAFW pump trip

• FW19 --TDAFW pump trip

• RC08A -Pzr PORV PCV455 FC 3. Place simUlator in "RUN" and Insert malfunction ED01, Loss of Offsite Power. Carry out EOP E-O and FR-H.1 actions through step 9. Allow the simulator to run until wide range level is < 29% in 3 of 4 SGs. 4. If desired, drain SG using remotes SGR01, 02, 03,04 to help achieve desired SG levels 5. Acknowledge and clear annunciator alarms, place the master silence switch to "normal" and place the simulator in "FREEZE".

6. After the candidate has received the initiating cues and initial conditions, place the simulator in "RUN." Approximate setup time is 25 minutes. or Reset to Ie 171, setup 5 minutes A reactor trip occurred due to a loss of offsite power. A red path condition on heat sink is present due to no AFW pumps running. While carrying out the actions of FR-H.1 , wide range level in 3 S/Gs fell to less than 29%. 4 Initiating The US has directed you to establish an RCS bleed and feed using FR-H.1 steps 10 thru 14. * * *

• NOTES TO TASK PERFORMANCE EVALUATOR

• * *

• Critical steps for this JPM are indicated by checking ny". For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly. When the student states what his/her simulated action/observation would be, read the appropriate "Cue". If necessary, question student for details of simulated actions/observations (Le. "What are you looking at?" or "What are you observing?"). Under NO circumstances must the student be allowed to manipulate any devices during the I performance of this JPIVI (in-plant only). I PERFORMANCE INFORMATION JPM Number: 2K11 NRC Revision:

o chg 4 Task Title: Perform RCS Bleed and Feed Per FR-H.1 START TIME: ____ PERFORMANCE STEP STANDARD STEP Obtains copy of FR-H.1 Critical:

Grade Candidate obtains a copy of FR-H.1,Y[]N[X] S[]U[]refers to CAUTIONS prior to step 10. I Comments:

Cue: STEP

• Steps 10. through 14. must be Candidate reviews the CAUTIONS.

Critical:

Grade #2 performed quickly in order to Y[] N[X] S [ ] U [ ]

establish RCS heat removal by FR*H.1, RCS bleed and feed. step 10 CAUTION During the remainder of procedure, feed flow to the must be established as by step I Comments:

Cue: I I STEP Check All RCPs -STOPPED At MB4, Candidate determines that all Critical:

Grade #3 RCPs are stopped by observation of Y[] N[X] S [ ] U [ ]

FR-H.1, green and amber indicating lights 'ON' step 10 and/or no flow, amps, etc. Comments:

6

--Cue: STEP Initiate 51. Rotates the SI switch on either MB4 or Critical:

Grade #4 MB2 to the "ACTUATE" position.

Y[X] N[] S[]U[] FR-H.1, Observes the safety injection actuation step11 annunciator illuminates.

Annunciator alarms consistent with the SI actuation and opening the PORVs will be received.

The candidate should silence the alarms and acknowledge and clear annunciators as appropriate.

This is not necessary to complete this critical step. Cue: STEP Verify Re5 Feed Path Determines that that the 'A' and/or 'B' Critical:

Grade #5 charging pumps are running by Y [ ] N [X ] S[]U[] FR-H.1, Check charging pumps ---observation of indicating lights, amps, s t e p AT LEAST ONE RUNNING flow etc. 1 2. a Comments:

Cue: STEP OPEN charging pump cold leg Observes GREEN lights for the Critical:

Grade #6 injection valves: charging pump cold leg injection Y[X] N[] S[]U[] FR-H.1, valves. Candidate depresses s t e p 3SIH*MV8801A and 3SIH*MV8801 B 1 2. b

• 3SIH*MV8801 "OPEN" pushbuttons and observes

• that the indicating lights shift to green OFF, red ON. Comments:

Cue: STEP Check SI pumps ---Determines that that the 'A' and/or '8' Critical:

Grade #7 AT LEAST ONE RUNNING SI pumps are running by observation of Y[] N[X] S[]U[] FR-H.1, indicating lights, amps, flow etc. s t e p 1 2. c Comments:

Cue:

---

STEP Check ECCS valve alignment

---Critical:

Grade Candidate checks the valve lineup by #8 PROPER EMERGENCY Y[] N[X] S[]U[]observing appropriate indicating lights. FR-H.1, ALIGNMENT s t e p 12. d Comments:

Cue: STEP Determines PORV block valves Critical:

Grade Establish RCS Bleed Path #9 3RCS*MV8000A and 3RCS*MV8000B Y[] N[X] S[]U[] FR-H.1, open by valve indications red lights s t e p 13. a Verify PZR PORV block valves -ON/green BOTH Comments:

Cue: STEP OPEN both PZR PORVs. Rotates the control switches for the Critical:

Grade #10 PZR PORVs (3RCS*PCV455A and Y[X] N[] S[]U[] FR-H.1, 3RCS*PCV456) to the "OPEN" s te p position.13. b Comments:

3RCS*PCV455A will remain closed. Opening 3RCS*PCV456 is the critical nature of the step. The candidate should silence and acknowledge annunciators that alarm due to the depressurization.

Cue: STEP Observes the indicating lights shift to Critical:

Grade Verify Adequate RCS Bleed Path #11 red ON, green OFF for 3RCS*PCV456 Y[] NIX] S[]U[] FR-H.1, only.step 14 Check PZR PORVs -BOTH Recognizes that 3RCS*PCV*455A has remained Check PZR PORV valves -BOTH Transitions to the RNO Comments:

Cue:

--STEP Perform the following:

1. 12 F R-Establish head vent to H s t e OPEN reactor vessel head 14.a.1) vent isolation valves: RNO

• 3RCS*SV809SA

• 3RCS*SV809S8

• 3RCS*SV8096A

• 3RCS*SV80968 Comments:

Cue: STEP OPEN reactor vessel head #13 vents: FR-H.1, s t e p 3RCS*HC442A2) RNO

• Comments:

Cue: STEP Consult ADTS for #14 recommendations on aligning any FR-H.1, available low pressure water s t e p source to the SGs. 14. b RNO Comments:

Depresses OPEN pushbutton for 3RCS*SV809SA, 8V809S8, SV8096A and 3RCS*SV80968 and observes position indicating lights shift to green OFF and red ON. Candidate depresses OPEN ( ... ) pushbuttons for 3RCS*HC442A and 3RCS*HC4428 and observes ( ... ) open light ON, ( ... ) close lights off. Candidate requests the 8M/US contact ADTS for recommendations on aligning any available low pressure water source to the SGs. Critical: Y[X] N[] Critical: Y[X] N[] Critical: Y[] N[X] , The SM will consult with the ADTS, no low pressure source is immediately available, proceed with the procedure.

9 I

--STEP IE a low pressure water source Candidate proceeds to step 15. Critical:

Grade #15 can NOT be aligned, THEN Y[] N[X] S[]U[] Proceed to step 15 Comments:

Cue: STEP Notify the US that an RCS bleed and Reports to the US that an RCS bleed Critical:

Grade #16 feed is established.

and feed has been established using Y[] N[X] S[]U[] steps 11-140fFR-H.1.

Comments:

Cue: TERMINATION CUE: The evaluation for this JPM is concluded.

STOP TIME: ____

---VERIFICATION OF JPM JPM Number: 2K11 NRC 8.3 Revision:

0 chg Date To achieve a satisfactory grade, ALL critical steps must be completed correctly.

If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade. Time Critical Task? Yes No X Validated Time (minutes):

7 Actual Time to Complete (minutes):

Overall Result of JPM: SAT UNSAT Areas for Improvement I Comments:

JPM Number: Initial Conditions:

Initiating Cues: STUDENT HANDOUT 2K11 NRC 5.3 Revision:

o chg 4 A reactor trip occurred due to a loss of offsite power. A red path condition on heat sink is present due to no AFW pumps running. While carrying out the actions of FR-H.1, wide range level in 3 S/Gs fell to less than 29%. The US has directed you to establish an ReS bleed and feed using FR-H.1 steps 10 thru 14.

JOB PERFORMANCE MEASURE APPROVAL JPM Title: JPM Number: Initiated:

Reviewed:

Approved:

Respond to a Mode 4 LOCA (All. 1) 2K11 NRC SA (JPM*135A)

Revision:

02/23/11 Developer Date Date J Date 1

SUMMARY

OF DATE DESCRIPTION REV/CHANGE 02/23/11 Verified JPM to update to revision 017-02 to AOP 3555, ReS 1. Leak. Modified JPM format to be consistent with the NRC 2K11 JPM set. Deleted TR-AA-41 0 Pass/Fail criteria.

Added a comment that depending on the time to reach step 2.c of AOP 3555, Letdown may have auto -isolated (PZR level 22%). DLM

---

..IPM Facility:

Examinee:

JPM Number: 2K11 NRC S.4 Revision:

1 Task Title: Respond to a Mode 4 LOCA (Alt. 1) System: 005 (RHR) Time Critical Task: ) YES (X) NO Validated Time (minutes):

5 Task Number(s):

344-05-014 Applicable To: SRO X RO X PEO KiA Number: EPE: 009 -EA1.13 KiA Rating: 4.4/4.4 Method of Testing: Simulated Actual x Performance:

Performance:

Location:

Classroom:

Simulator:

X In-Plant:

Task Standards:

Satisfactorily complete actions to respond to a Mode 4 LOCA lAW AOP 3555. Reguired Materials:

AOP 3555 (procedures.

equipment.

etc.) Simulator key #7 (PA2235) General

References:

AOP 3555 Rev. 017-02

• • • READ TO THE EXAMINEE I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this JPM will be satisfied.

You may use any approved reference material normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.

JPM WORKSHEET JPM Number: 2K11 NRC S.4 Revision:

1 Simulator Requirements:

1. Reset to IC 297 .... OR Reset to any Mode 4 IC with both RHR trains in service, and carry out steps 3 -5 below: Verify the 45 GPM orifice isolation (CHS*AV8149A) is open with either 75 GPM orifice in service. Insert the following: MALF RC02A, "RCS HL 1 RUP," severity 80 Ibm/sec I/O [RH] 3RHS*MV8701 B (RHDI0013) to 'OPEN' I/O [RH] 3RHS*MV8702A (RHDI0017) to 'OPEN' Place the simulator in "RUN". Acknowledge/clear annunciators and place the simulator in "FREEZE" once PZR level has decreased

-38%. Ensure key #7 (PA2235) is located in either RHS*MV8701 B or MV8702A control switch. Hang YC Tags on SIL*MV8812A

& B per OP3310A stating "Maintain valve closed unless needed for inventory control" After the examinee has received the initiating cues and initial conditions, place the simulator in "RUN". Approximate simulator setup time is 15 minutes. Initial The plant is in Mode 4 cooling down to Mode 5 in preparation for a refueling outage. Both Trains of RHR are in service in the COOLDOWN Mode. RCS and CTMT parameters began experiencing symptoms of a RCS leak a short time ago and the crew has entered AOP 3555. Initiating The US has directed you to perform AOP 3555, Reactor Coolant System Leak, beginning with step 1. * * *

• NOTES TO TASK PERFORMANCE EVALUATOR

• * *

• 4 Critical steps for this JPM are indicated by checking "Y". For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly. When the student states what his/her simulated action/observation would be, read the appropriate "Cue". If necessary, question student for details of simulated actions/observations (i.e. 'What are you looking at?" or "What are you observing?"). Under NO circumstances must the student be allowed to manipulate any devices during the performance of this JPM (in-plant only).

PERFORMANCE INFORMATION JPM Number: 2K11 NRC S.4 Revision:

1 Task Title: Respond to a Mode 4 LOCA (A It. 1) START TIME: ____ PERFORMANCE STANDARD Comments:

Examinee may elect to trip RCPs any time after NPSH or seal parameters go below minimum specs. I STEP Check PZR Level -DECREASING Verifies PZR level decreasing by Critical:

Grade #1 using hot and/or cold channel Y[]N[X] S[]U[] 3555 step 1 indications.

Comments:

Cue: STEP Verifies normal flow path in service by Critical:

Grade !Increase Charging Flow #2 verifying charging flow indicated Y[]N[X] S[1U[1 Check charging lineup-NORMAL 3555 step and/or open indications for normal 2.8. charging line valves. Comments:

Cue: STEP Throttle Open charging line flow control Depresses increase pushbutton on Critical:

Grade #3 valve to increase charging flow to maximum CHS-FK121 and increases output to Y[X]N[] S[]U[] 3555 step 100%. 2.b. Comments:

Cue: Verifies charging header flow Critical:

Grade increases to maximum. Y[]N[X] S[]U[] Comments:

Cue:

-STEP Check letdown orifice isolation valves -Observes that two letdown orifice Critical:

Grade #4 ONL Y ONE OPEN. isolation valves are open by observing Y[]N[X] S[]U[] 3555 step 2.c. the indicating lights as green OFF, red ON. Transitions to RNO column. Comments:

Cue: STEP CLOSE the 45 gpm letdown orifice isolation Depresses the CLOSE pushbutton for Critical:

Grade #5 valve (3CHS*AV8149A).

3CHS* AV8149A and observes valve Y[ ]N[X] S[]U[] 3555 step 2.c. closes by red indicating light OFF, RNO green ON. Comments:

If PZR level reaches 22% prior to reaching step 2.c, Letdown will auto-isolate.

This is acceptable and meets the intent of this step. Cue: STEP Verify PZR level -STABLE OR Verifies PZR level still decreasing by Critical:

Grade . #6 INCREASING using hot and/or cold channel Y[]N[XJ S [ ] U [ ]

3555 step 2.d indications.

Transitions to RNa column. Comments:

Cue: STEP Proceeds to step 3. Critical:

Grade Perform the applicable action: #7 Y[]N[X] S[l U[J 3555 step ....lE in operational Mode 4, 2.d.RNO Proceed to Step Comments:

Cue: STEP Stops RHS*P1A and RHS*P1 Band Critical:

Grade Align RHR In Mode 4 #8 places control switches in PTL. Y[X] N[] S[]U[]Place RHR pumps lined up for shutdown 3555 step 3.a cooling in PULL-TO-LOCK Comments:

---

..........

.....-..--.........-.--7 I

---

STEP Check -ONE TRAIN OF RHR LINED UP Recognizes that both trains are lined Critical: #9 FOR INJECTION.

up for cooldown mode by either Y[]N[X] S [ ] U [

3555 step 3.b system alignment or from Transitions to RNO STEP Proceeds to either step 4 or step 5. Critical: Perform the applicable action to align one Y[] N[X] Sf] U[l train of RHR for injection:

3555 step RNO

• IE aligning RHR Train A, Proceed to Step IE aligning RHR Train 8, Proceed to Step If examinee requests SM/US direction, provide the following cue: Cue: Align RHR Train "A" for injection Remaining JPM steps are written such that either RHR train may be aligned for injection.

"8" train steps and

• components are indicated in [ ]. , Rotates CHS-HC128 controller Critical:

Grade Align RHR Train A [8] For Injection potentiometer fully counter clockwise Y[X] N[] S[]U[]CLOSE RHR letdown flow control valve 3555 step to 0% output. [5.a] (3CHS-HC128) STEP CLOSE RHR outer Ctmt isolation valve Inserts (if necessary) key #7 (PA2235) Critical: #12 (3RHS*MV87018)

[3RHS*MV8702A]

for RHS*MV8701 8 [8702A] and Y[]N[X] S [ ] U [

3555 step 4.b rotates clockwise to close [S.b] Observes valve does not reposition.

Transitions to RNO column. 8 Comments:

Cue: STEP CLOSE RHR inner Ctmt isolation valve Inserts key #7 (PA2235) for Critical:

Grade #13 (3RHS*MV8701A)

[3RHS*MV87028]

RHS*MV8701A

[87028] and rotates Y[X] N[] S [ ] U [ ]

3555 step 4.b 3555 step 4.b. RNO [5.b.] RNO clockwise to close valve. Observes [S.b] RNO valve closes by red indicating light OFF, green ON. Comments:

Cue: Comments:

Sub steps 4.c. & 4.e. [5.c. & 5.e.] are not critical in nature as sub step 4.d. [5.d.] opens the RHR HX bypass & outlet flow control valves to their SI position by placing the HX flow control switch in "NormaL" Cue: STEP Critical:

Grade CLOSE the Depresses FK618 [FK619] decrease Y[]N[X] S[]U[]pushbutton until output is 100% 3555 step

• RHR heat exchanger bypass valve (3RHS-FK618)

[FK619] RHR heat exchanger outlet control valve Critical:

Grade Rotates HC606 [HC607] Y[] N[X] S [ ] U [ ]

potentiometer clockwise until output is 0% (10.0 pot setting) Comments:

Cue: STEP Rotates the A [8] Flow control switch Critical:

Grade Place the "HX A [8] FLOW CONT" switch in to NORMAL Y [X] N [ 1 Sf] U[l the "NORMAL" position 3555 step 4.d [5.d] Comments:

Cue: 9

-Depresses FK618 [FK619] increase Critical:

Grade Perform the following: pushbutton until output is 0%. Y[]N[X] S [ ] U [ ] Adjust RHR heat exchanger bypass 3555 step valve controller

[619] [5.e} in manual to full open (0% output) Adjust RHR heat exchanger flow valve controller

[607] to Rotates HC606 [HC607] Critical:

Grade potentiometer counter clockwise until Y[]N[X] S[]U[] output is 100% (0.0 pot setting).

Comments:

Cue: STEP OPEN RWST to RHR pump suction Depresses open pushbutton for Critical:

Grade #17 isolation valve (3SIL*MV8812A)

[88128] SIL*MV8812A

[8] and observes valve Y[X] N[] S[]U[] 3555 step 4.f opens by red indicating light ON, [s.f] qreen OFF. Comments:

Cue: STEP Verifies MV8809A [B] open by Critical:

Grade Verify RHR cold leg injection isolation valve observing red indicating light ON, Y[]N[X] S [ ] U [ ]

(3SIL *MV8809A)

[8809B] -OPEN 3555 step green OFF. [5.g] Comments:

Cue: STEP Removes RHS*P1A [P1 B] control Critical:

Grade Place RHR pump 3RHS*P1A [P1B] in switch from PTL and places in Auto. Y[X]N[] Sf] U[]AUTO 3555 step 4.h [5.h] Comments:

Cue: STEP Critical:

Grade Initiate Rotates either SI actuation switch Y[X] N[] S [ ] U [ ] (MB2 or MB4) clockwise until SI 3555 step , actuates.f5.il I Comments:

Cue: Critical:

Grade Verifies SI actuation by SI Y[] N[X] S[] U[]annunciator(s), and/or equipment repositioning, etc. Comments:

Cue: STEP Critical:

Grade Go to E-O, Reactor Trip or Safety Injection Informs SM/US of E-O transition

1. 21 Y[]N[X] S [ ] U [ ]

3555 step 4.j [s.j] Comments:

Cue: Terminating Cue: The evaluation for this JPM is concluded.

STOP TIME: ___

--VERIFICATION OF JPM COMPLETION JPM Number: 2K11 NRC S.4 Revision: Date Student: Evaluator: , To achieve a satisfactory grade, ALL critical steps must be completed correctly.

If task is Time I Critical, it MUST be completed within the specified time to achieve a satisfactory grade. Time Critical Task? Yes No X Validated Time (minutes):

5 Actual Time to Complete (minutes):

Overall Result of JPM: SAT UNSAT Areas for Improvement I Comments:

12 l STUDENT JPM Number: 2K11 NRC S.4 Revision:

1 Initial Conditions:

The plant is in Mode 4 cooling down to Mode 5 in preparation for a refueling outage. Both Trains of RHR are in service in the COOLDOWN Mode. RCS and Ctmt parameters began experiencing symptoms of a RCS leak a short time ago and the crew has entered AOP 3555. Initiating Cues: The US has directed you to perform AOP 3555, Reactor Coolant System Leak, beginning with step 1.

JPM Title: ..IPM Number: Initiated:

Reviewed:

Approved:

JOB PERFORMANCE MEASURE APPROVAL SHEET 8GTR Cooldown Using 8G Atmospheric Relief or Bypass 2K11 NRC 8.5 (JPM-036A)

Revision:

2/24/11 Developer Date SiS/II Technical Reviewer [late oale 5

SUMMARY

OF DESCRIPTION REV/CHANGE Verified JPM to update to revision 022 to E-3 and revision 001 to GA-26. Modified JPM format to be consistent with the NRC 2K11 JPM set. Added several comments in the body of the JPM to enhance the ability of the examiner to navigate the JPM and GA-27. Modified the JPM to start the task from E-3, step 6.d (as opposed to 6.a), and to provide to the examinee the target ReS temperature (which is an SRO task). This did not remove any critical steps and shortened the overall time required to conduct the JPM. Deleted 410 Pass/Fail criteria.

DLM i

---

JPM Facility: Candidate:

JPM 2K11 NRC S.5 Revision:

5Task Title: SGTR Cooldown Using SG Atmospheric Relief or Relief Bypass Valves System: 041 1039 Time Critical Task: ) YES (X) NO Validated Time (minutes):

10 Task Number(s):

000-05-023 Applicable To: SRO X RO X PEO KIA EPE:038-EA 1.16 KIA Rating: 4.4/4.3 Number: Method of Simulated Actual X Performance:

Performance:

Classroom:

Simulator:

x In-Plant:

Task Satisfactorily complete the RCS cooldown at the maximum rate to less than the required temperature per EOP 35 E-3. All critical steps are performed satisfactorily.

All sequential steps are performed in proper procedural sequence.

Required Materials:

GA-26 (procedures, equipment, etc.) MP3 Simulator General EOP 35 E-3, Steam Generator Tube Rupture, Rev 022 EOP 35 GA-26, Dumping Steam To Condenser Or Atmosphere, Rev 001

• • • READ TO THE CANDIDATE I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this JPM will be satisfied.

You may use any approved reference material normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.

JPM WORKSHEET JPM Number: 2K11 NRC Revision:

5 Simulator

1. Reset to IC 302 OR reset to any 100% power IC AND Insert malfunction SG01 B at 40% severity -S/G "B" tube rupture of 400 gpm. Place the simulator in "RUN"; allow the radiation levels to increase on until the "RADIATION ALERT" and "Rad Hi" annunciators are received.

Then trip the reactor and initiate an SI. Carry out the actions of E-O, transition to E-3 and carry out the first 5 steps. Ensure intact SG levels are> 8%. AFW flow should be between 530 to 600 gpm to the intact SGs. Insert malfunction FW01 at 100% to degrade condenser vacuum to > 5 in. Hg. Ensure "LOSS OF CONDENSER AVAILABLE PERM C9" is lit. Place all RCP overcurrent trip switches in cold using REM functions RC23, 24, 25 & 26. Acknowledge and clear annunciators and place the simulator in "FREEZE". After the Candidate has received the initiating cues and initial conditions, place the simulator in "RUN". Approximate setup time is 20 -25 minutes. Initial The plant was operating at 100% power when a tube rupture occurred on the "8" SG. A manual Rx trip and Safety injection was initiated.

The control room team has carried out EOP actions through E-3, step 6.c. Initiating The US has directed you to conduct an RCS cooldown per EOP 35 E-3, Steam Generator Tube Rupture, starting at step 6.d. The required core exit temperature (target) is 515°F. * * * *' NOTES TO TASK PERFORMANCE EVALUATOR

• ' * *

• Critical steps for this JPM are indicated by checking "Y". For the student to achieve a satisfactory grade, ALL critical steps must be cornpleted correctly. When the student states what his/her simulated action/observation would be, read the appropriate "Cue". If necessary, question student for details of simulated actions/observations (Le. "What are you looking at?" or "What are you observing?"). Under NO circumstances must the student be allowed to manipulate any devices during the performance of this ,JPM (in-plant only).

PERFORMANCE INFORMATION JPM Number: 2K11 NRC S.5 Revision:

5 Task Title: SGTR Cooldown Using SG Atmospheric Relief or Relief Bypass Valves START TIME: ____ PERFORMANCE STEP STANDARD STEP #1 Using GA-26, Dump steam from intact SGs at maximum rate Obtains a copy of GA-26, reviews the NOTEs prior to step 1. Critical:

Y[] N[X] Grade S[]U[] E-3 step 6.d The candidate may also request to review E-3 step 6. This is acceptable.

If the Candidate asks the status of the RCP overcurrent trip switches, provide the following cue: Cue: RCP overcurrent trip switches are in the COLD position.

STEP After Low Steamline Pressure Critical:

Grade Obtains a copy of GA-26, refers to the #2 Injection signal is BLOCKED, MSI Y[]N[X] S [ ] U [ ]

NOTEs prior to step 1 . will occur if the High Steam Pressure GA-26 step 1, Rate setpoint is exceeded.NOTE 3 The third NOTE prior to step 1 infers, the Candidate will block the Low Steam Line Pressure SI when (and if) pressurizer pressure is LESS THAN 2000 psia. When these conditions are met, this action can be taken by the operator at any time during this JPM as follows: Cue: STEP Block Low Steam Line Pressure SI Depresses STEAM LINE ISOL -SI Critical:

Grade #3 block push buttons on MB2 Y[] N[X] S[]U[] Comments:

Cue: 6 Comments:

Cue: STEP Verify Plant Conditions

1. 4 Check instrument air compressors GA-26 AT LEAST ONE RUNNING step 1.a Comments:

Cue: STEP Check Annunciator "MAIN STEAM #5 LINE ISOLATION" (MB2B GA-26 NOT LIT step 1.b Comments:

Cue: STEP Determine Condenser Steam #6 Dump Availability GA-26 Check the following:

2.a Using condenser steam dumps -DESIRED Annunciator "CONDENSER AVAIL FOR STM DUMP C-9" (MB4D 5-6) LIT AT LEAST ONE INTACT SG MSIV OR BYPASS OPEN Observes!

Acknowledges Mn Steam Line SI Block Train AlB Annunciators on MB4D 1-3 and 2-3. Observes that the 'A' IA Compressor is running. Observes that intact SG MSIVs are OPEN and MB2B 5-7 is NOT lit. Candidate recognizes that C-9 is NOT lit and hence the condenser is not available.

Candidate shifts to the RNO column. Critical: Y[]N[X] Sf] Critical:

Grade Y[] N[X] S[]U[] Critical:

Grade Y[] N[X] S[]U[] Critical:

Grade YI] N[X] S[]U[]

Comments:

If!he Candidate asks the US whether using condenser steam dumes is desired, erovide the following cue: Cue: Use the condenser steam dumps if possible. Candidate proceeds to the NOTE prior Critical:

Grade Perform the following: to step 4. Y[] N[X] 's [ J U [ ] GA-26 step Proceed to NOTE prior to step 4. 2.a RNO Candidate may inform the US that steam dumps are not available and the atmospheric relief valves or their associated bypass valves will have to be used for the cooldown.

The candidate may place one or both steam dump interlock switches to OFF. This is satisfactory.

Cue: STEP Following MSI reset, an actuation Candidate reviews NOTE. Critical:

Grade #8 signal will re-initiate MSI. Y[] N[X] S[]U[]GA-26, s t e p 4 NOTE Comments:

Cue: STEP Candidate recognizes that using SG Critical:

Grade Determine SG Atmospheric Relief #9 atmospheric relief or bypass valves is Y[] N[X] S[]U[]Valves Availability desired based on the unavailability of GA-26, Check using SG atmospheric relief the condenser.

step 4.a valves -DESIRED IE the Candidate asks the US for guidance concerning which valves to use, or if the Candidate proceeds to step 6 to use the Bypass Valves, provide the following Cue: Cue: Use the SG Atmospheric Relief Valves.

-STEP Critical:

Grade!Place SG atmospheric relief valve Takes manual control of the#10 Y[X]N[ ] S[]U[]I controllers in MANUAL and Adjust to Atmospheric Relief Valves for zero output intact step (3MSS*PV20A)

(3MSS*PV20C)

(3MSS*PV20D)

By pressing the manual and observing the auto light OFF and the manual light ON. Adjusts each zero STEP Check Annunciator "MAIN STEAM Observes that intact SG MSIVs are Critical: #11 LINE ISOLATION" (MB2B 5-7) -LIT OPEN and MB2B 5-7 is NOT lit. Y[] N[X] step Shifts to the RNO column. Comments:

Cue: STEP Proceed to step 5. Candidate proceeds to step 5. Critical:

Grade #12 Y[] N[X] S[]U[] GA 26, step 4.c RNO STEP Candidate recognizes that an RCS Critical: Dump Steam to Atmosphere

1. 13 cooldown is desired. Y[] N[X] S[]U[]Using SG Atmospheric step Check RCS cooldown or depressurization

-

9 STEP Check the procedure in #14 requires steam dump -AT MAXIMUM GA-26, step 5.b Comments:

Cue: STEP Adjust each selected SG#15 atmospheric relief valve controller evenly over an approximate one GA-26, step 5.c minute time period to open the associated valve

• 3MSS-PIC20A 1

• 3MSS-PIC20B 1

• 3MSS-PIC20C1

• 3MSS-PIC20D1 Candidate recognizes that step 6.d of E-3 directed steam be dumped at the maximum rate from the intact SGs. Using the manual adjust levers, evenly and over the course of about a minute, increases the output signal on the 'A', 'C' and '0' SG atmospheric relief valve controllers until a 100% demand signal is obtained and the indicating lights for the atmospheric relief valves shift to green OFF, red ON. Critical: Y[] N[X] Critical: Y[X]N[] , Comments:

If the Candidate performs the opening of the atmospheric relief valves too fast, a main steamline isolation will occur. The Candidate should recognize this and Return to NOTE prior to step 4 of GA-26. The Candidate should NOT open the 'B' atmospheric relief valve. Comments:

JPM steps 16* *23* are only performed if a main steam line isolation has occurred.

This will involve using the SG Atmospheric Relief Bvpass Valves. Cue: STEP Recognize a main steam line Acknowledges the Main Steam Line Critical:

Grade # 16

• isolation has occurred.

isolation annunciator and realizes the Y[] N[X] S[]U[] atmospheric relief valves are closed and no longer available for cooldown.

Comments:

Cue:

I -STEP IF MSI actuates, THEN Return to Candidate after recognizing a main Critical:

Grade #17* NOTE prior to step 4. steam line isolation has occurred, Y[] N[X] S[]U[] returns to the note prior to step 4. GA-26 step 4.c RNO Comments: STEP Candidate questions the US if using Critical: Determine SG Atmospheric Relief #18* the SG atmospheric relief valves is Y[] N[X] S[]U[]Valves Availability desired. GA-26, Check using SG atmospheric relief step 4.a valves -DESIRED Comments:

When the Candidate asks the US for guidance concerning if using the SG atmospheric relief valves is desired provide the following Cue: Cue: Use the SG Atmospheric Relief Bypass Valves. STEP Candidate proceeds to step 6. Critical:

Grade Proceed to step 6.#19* Y[]N[X] S[]U[] GA-26, step 4.a I RNO Comments:

Cue:

STEP Candidate goes around the back of Critical:

Grade Dump Steam to Atmosphere

1. 20* MB5 and places the 'A', IC' and '0' SG Y[] N[X] S[]U[]Using SG Atmospheric atmospheric relief bypass Bypass Valves GA-26, CONTROL LOCKOUT switches in step 6.a Place the desired SG atmospheric NORMAL, and observes the relief bypass valves' CONTROL indicating lights turn LOCKOUT switches in 3MSS*MOV74A 3MSS*MOV74B 3MSS*MOV74C 3MSS*MOV740 Comments:

The Candidate should not place the 'B' CONTROL LOCKOUT switch in NORMAL. Cue: STEP Critical:

Grade Throttle the desired SG atmospheric Depresses the "open" push buttons for #21* Y[X]N[ ] S[]U[]relief bypass valves to reduce or the atmospheric relief bypass maintain RCS temperature or SG on the "An, "C" and "0" GA-26, step 6.b pressures as specified by the procedure in (3MSS*MOV74A) 3MSS*MOV74A (3MSS*MOV7 4C) 3MSS*MOV74B (3MSS*MOV740)and observes the indicating lights shift to green OFF, red ON then releases the "open" pushbutton. ,

The Candidate should NOT open the 'B' atmospheric relief bypass valve.

It takes about 2 minutes for the MSS*MOV74 valves to stroke fully open. The candidate may ask for SM's permission to use two-handed operation.

If so, provide the following Cue:

Cue: STEP #22* GA-26, step 6.c Comments:

Cue: STEP #23* GA-26 step 6.c RNO Comments:

Cue: STEP #24 GA-26 step 5.c STEP #25 GA-26, step 8.a Comments:

Cue: You may use two-handed operation.

Check dumping steam from any SG using SG atmospheric relief isolation valve{s) -DESIRED Proceed to step 8. Proceed to step 8. Check If RCS Temperature Or Steam Generator Pressures Should Be Stabilized Check RCS temperature or SG pressures

-AT DESIRED VALUE Candidate recognizes that the SG atmospheric relief isolation valve{s) are not needed. Shifts to the RNO column. Candidate proceeds to step 8. Candidate proceeds to step 8. Displays the core exit thermocouple map on the computer display screen or uses ICC cabinet. Monitors the temperatures to ensure temperature is lowering.

Y[

Y[]

Y[]

Y[] -Grade S[]U[]

--STEP Displays the core exit thermocouple Critical:

Grade Continue dumping steam as #26 map on the computer display screen or Y[] N[X] S[]U[]specified by the procedure in uses ICC cabinet. Monitors and, WHEN RCS temperature or SG GA-26, temperatures to ensure temperature is step B.a pressures are at the desired value, RNO lowering.THEN Proceed to step B.b. Comments:

The remaining steps are associated with stopping the cooldown, starting with E-3, step 6.e. Note that the Candidate should also be able to complete steps 27 and 2B using GA-27 alone Cue: STEP Verify core exit TCs -LESS THAN Displays the core exit thermocouple Critical:

Grade #27 REQUIRED TEMPERATURE.

map on the computer display screen or Y[X]N[ ] S[]U[] uses ICC cabinet. Monitors the E-3 step 6.6 temperatures to ensure temperature is below the temperature determined in E-3 step 6.c (given in the initiating cue). Comments:

Cue: STEP Candidate returns to GA-26, step B.b. Critical:

Grade Using GA-26 , Perform the following:

1. 28 Y[] N[X] S[]U[] 1 ) Stop RCS E-3 step Comments:

GA-26 step B.b (Check condenser steam dumps -IN USE), and its associated RNO will direct the operator to step 10 IF SG atmospheric relief valves are in use, or step 11 IF SG atmospheric relief bypass valves are in use. Cue: 14 STEP Stabilize Using SG Atmospheric

1. 29 Relief Valves G A-2 6 Adjust each selected SG s t e p 10. a atmospheric relief valve controller as necessary to stabilize and maintain RCS temperature or SG pressures as specified by the procedure in effect Comments:

Cue: Candidate recognizes that E-3 specified that the cool down be stopped. Uses the atmospheric relief valve controller manual adjust levers to decrease the demand signal to zero and observes the indicating lights shift to green ON, red OFF for all three valves. Critical:

Grade Y[] N[X] S[]U[] Critical:

Grade Y[X]N[ 1 S[]U[] Comments:

JPM step 30* is only performed if a main steam line isolation has occurred.

This will involve closing the SG Atmospheric Relief Bvpass Valves. STEP Candidate recognizes that E-3 Critical:

Grade Stabilize Using SG Atmospheric

1. 30 specified that the cooldown be Y[] N[X] S[]U[l Relief Bypass Or Isolation Valves stopped.GA-26, Throttle the selected SG s t e p 1 1 . a atmospheric relief bypass valves stabilize and maintain temperature or SG pressures specified by the procedure in

• 3MSS*MOV74A

• 3MSS*MOV74B

• 3MSS*MOV74C

• 3MSS*MOV74D 15 Comments: "I !Cue: Depresses the "close" push buttons for Critical:

Grade the atmospheric relief bypass valves Y[X]N[ ] S[]U[] on the "A", "C" and "0" SGs (3MSS*MOV74A, C, D), observes the indicating lights shift to green ON, red OFF and releases the "close" pushbutton.

Comments:

Cue: STEP Informs the US that the required RCS Critical:

Grade Notify the US that the required RCS #32 cooldown in accordance with E-3, Step Y[]N[X] S[]U[]cooldown is complete.

6, has been TERMINATION CUE: The evaluation for this JPM is STOP TIME: ___

---VERIFICATION OF JPM COMPLETION

...IPM Number: 2K11 NRC S.5 Revision:

5 Date Performed:

Student: Evaluator:

To achieve a satisfactory grade, ALL critical steps mllst be completed correctly.

If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade. Time Critical Task? Yes No X Validated Time (minutes):

10 Actual Time to Complete (minutes):

Overall Result of JPM: SAT UNSAT Areas for Improvement I Comments:

17 ------------'

l 5 STUDENT JPM Number: Initial Conditions:

Initiating Cues: 2K11 NRC S.5 Revision:

The plant was operating at 100% power when a tube rupture occurred on the "8" SG. A manual Rx trip and Safety injection was initiated.

The control room team has carried out EOP actions through E-3. step 6.c. The US has directed you to conduct an ReS cooldown per EOP 35 E-3. Steam Generator Tube Rupture, starting at step 6.d. The required core exit temperature (target) is 515°F.

JOB PERFORMANCE MEASURE APPROVAL JPM Title: Respond To High Containment Pressure JPM Number: 2K11 NRC S.6 (JPM-128)

Initiated: "C Dave Minnich Developer Reviewed:

Technical Reviewer Approved:

Supervisor, Nuclear Training 1 Revision:

2/17/11 Date >/5/ l( Date 2

SUMMARY

OF DESCRIPTION REV/CHANGE Updated JPM to revision 016-02 to FR-Z.1. This involved a 2/0 substantial rewrite of this JPIVI. lVIodified JPM format to be consistent with the NRC 2K11 JPM set. DLM

---

JPM Facility:

____ Examinee:

JPM Number: 2K11 NRC S.6 Revision:

2 Task Title: Respond To High Containment Pressure System: 005 -026 (CTMT Spray System) Time Critical Task: ( ) YES (X) NO Validated Time (minutes):

10 Task Number(s):

000-05-052 Applicable To: SRO X RO X PEO KIA EPE: E14 -EA1.1 KIA Rating: 3.7/3.7 Number: Method of Simulated Actual x Performance:

Performance:

Location:

Classroom:

Simulator:

x Task Standards:

Start a containment spray pump by completing the first 5 steps of FR-Z.1, Response To High Containment Required Materials: (procedures.

equipment, etc.) MP3 Simulator FR-Z.1, Response To High Containment Pressure, Revision 016-02 General

References:

• • • READ TO THE EXAMINEE *** I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this JPM will be satisfied.

You may use any approved reference material normally available in the Control Room, including logs._ Make all written reports, oral reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.

JPM WORKSHEET JPM Number: 2K11 NRC Revision:

2 Simulator Requirements:

1. Reset to Ie 301 .... OR Reset to IC-18, or equivalent 100% power IC. Insert the following malfunctions: CS01 B -"B" Quench Spray Pump trip. 4. Insert the following 1/0 overrides: RPDI0004 (PB1 CDA Actuate Train A) 'NACTUATE'. RPDI0006 (PB3 CDA Actuate Train B) -'NACTUATE'. Place the "An Quench Spray Pump in "PULL-TO-LOCK" and place a yellow caution tag on the control switch. Place the simulator in "RUN." Take the MASTER SILENCE SWITCH to "SILENCE." Insert malfunction MS01A -S/G "An faulted inside containment, at 100% severity. Allow the simulator to run for 1-2 minutes. (Adverse CTMT will be met due tn CTMT temperature.)

During this time perform the following:

• Stop the "COl CAR fan. Stop the kitchen exhaust fan. Stop AFW flow to "A" S/G. Throttle AFW flow to 200 gpm to each of the other S/Gs. When the above actions are complete and the Containment HI-3 setpoint is reached, perform the following:

• Acknowledge/clear all alarms

• Come out of Master Silence

• Place the simulator in 'FREEZE." 4

9. When the examinee has received the initial conditions and initiating cues, place the simulator in "RUN." Approximate simulator setup time is 6-8 minutes. Initial A steam-line break inside containment has occurred.

Based on plant conditions, a manual reactor trip and safety injection were initiated.

The Control Room Team is progressing through the EOPs and during the transition to E-2, Faulted Steam Generator Isolation, a COA signal was received and an "orange" path for containment integrity.

The "An Quench Spray Pump is tagged out for maintenance.

Initiating The US has directed you to perform FR-Z.1, Response High Containment Pressure, in an attempt to containment * * *

• NOTES TO TASK PERFORMANCE EVALUATOR * * *

• Critical steps for this JPM are indicated by checking "Y". For the student to achieve satisfactory grade, ALL critical steps must be completed When the student states what his/her simulated action/observation would be, read appropriate If necessary, question student for details of simulated actions/observations (Le. "What you looking at?" or "What are you observing?") . Under NO circumstances must the student be allowed to manipulate any devices during the performance of this JPM (in-plant only).

PERFORMANCE INFORMATION JPM Number: 2K11 NRC S.6 Revision:

2 Task Title: Respond To High Containment Pressure START TIME: ____ PERFORMANCE STEP STANDARD STEP Obtains copy of FR-Z.1. Critical:

Grade Obtains a copy of FR-Z.1, refers to #1 Y [ ] S [ ] Step 1, Caution. N[X] U [ ] Comments:

Cue: STEP If RWST level decreases to LESS Critical:

Grade Applicant reviews CAUTION, and at #2 THAN 520,000 gal, Go to ES-1.3, Y[]N[X] Sf] U[]MB2 observes that RWST level Transfer to Cold Leg greater than 520,000 gallons. FR-Z.1, to align the ECCS system. s t e p 1 CAUTION Comments:

Cue: STEP Check IF CDA Required Applicant checks CTMT pressure is Critical:

Grade #3 greater than 23 psia by checking any of Y[] N[X] Sf] U[] FR-Z.1, Check Ctmt pressure ---the following:

Meters at MB2: step 1.a GREATER THAN 23 psia LMS*PI934, 935, 936 or 937, or recorder 3LMS*PR934.

Comments:

Cue: ,

-STEP Verify annunciator "CONTAINMENT Observes that annunciator MB2B:5-5 Critical:

Grade #4 DEPRES ACTUATION" (MB2B 5-5) IS lit Y[]N[X] S[]U[] FR-Z.1, ---LIT s t e step Cue: STEP Check RPCCW pumps -STOPPED Observes that RPCCW pumps Critical:

Grade #5 3CCP*P1A & P1 B have no running Y [ ] N [X ] S[]U[] FR-Z.1, amps indicated and the indicating lights step 1.c are green ON, red OFF. Comments:

Cue: STEP STOP all RCPs Rotates the 3RCS-P1A control switch Critical:

Grade #6 to "STOP" and observes the flag shifts Y[X] N[] S[]U[] FR-Z.1, to "green;" amperage indication goes to step 1.d zero; and indicating lights shift to green ON, red OFF. Rotates the 3RCS-P1 B control switch Critical:

Grade to "STOP" and observes the flag shifts Y[X] N[] S[]U[]! to "green;" amperage indication goes to zero; and indicating lights shift to green ON, red OFF. Rotates the 3RCS-P1 C control switch Critical:

Grade to "STOP" and observes the flag shifts Y[X] N[] S[]U[] to "green;" amperage indication goes to zero; and indicating lights shift to green ON, red OFF. Rotates the 3RCS-P1 D control switch Critical:

Grade to "STOP" and observes the flag shifts Y[X] N[] S[]U[] to "green;" amperage indication goes to zero; and indicating lights shift to green ON, red OFF. Comments:

The RCPs may be stopped in any order. 7 Cue: STEP Observes at VP1 that the 'A', 'B' and Critical:

Grade

• Check CAR fans -STOPPED #7 'C' CAR fans are stopped. Y[] N[X] S[]U[] FR-Z.1, steR 1.e Comments:

Cue: STEP Check CRDM fans -STOPPED Observes at VP1 that the 'A' and 'B' Critical:

Grade #8 CRDM fans are stopped, but Y[] N[X] S[]U[] FR-Z.1, recognizes the 'C' CRDM fan is still step 1.f running by indicating lights red ON, green OFF. Transitions to the RNO column. Comments:

Cue: STEP STOP CRDM fans. Critical:

Grade Rotates the 3HVR-FN2C control switch #9 Y[X]N[] S[]U[]to "STOP" and observes the flag shifts FR-Z.1, to "green;" and indicating lights shift to step 1.f RNO green ON. red OFF. Comments:

Cue: STEP If ECA-1.1, Loss of Emergency Applicant reviews CAUTION, Critical:

Grade #10 Coolant Recirculation, is in progress, Y[] N[X] S[]U[] FR-Z.1, Ctmt spray should be operated as s t e p 2 directed in ECA-1.1 CAUTION Comments:

If the applicant questions the status of procedure ECA-1.1 due to the caution in FR-Z.1, provide the following cue: Cue: The Control Room Team has not yet entered ECA-1.1.

I --STEP Verify Quench Spray System Observes that annunciator MB2A 5-2 is Critical:

Grade # 11 Operation not lit (dark). Y[] N[X] S[]U[] FR-Z.1, step 2.a Check annunciator RWST ass PP OFF (69,331 gal) (MB2A 2) -NOT !STEP Verify quench spray pumps -Observes that no amperage is Critical:

Grade #12 RUNNING. indicated and the indicating lights are Y[] N[X] S[]U[] FR-Z.1, green ON, red OFF for the "B' ass step 2.b pump. The pump is not running. Applicant transitions to the Comments:

Pump 3aSS*P3A is tagged STEP START pumps. Rotates the control switch for Critical: #13 3aSS*P3B to "START" and observes Y[] N[X] !F no ass pump is running, that no amperage is indicated and the step 2.b RNO THEN indicating lights shift to green Proceed to step 4. amber ON, red OFF. The pump not Applicant proceeds to step STEP Verify CIA Observes that the ESF Group 2 Status Critical: #14 Lights in columns 2 through 10 are lit. Y[] N[X] Check ESF Group 2, step 4.a columns 2 though 10 -LIT Comments:

9 Cue: STEP Verify Recirculation Spray System Observes the indicating lights for Critical:

Grade #15 Operation 3RSS*MOV23A

-0 are green OFF, Y[] N[X] S[]U[] FR-Z.1, red ON. The valves are open. step S.a Check recirculation spray suction isolation valves -Comments:

Cue: STEP Check recirculation spray pumps -Recognizes that NO RSS pumps are Critical:

Grade #16 ANY RUNNING running by no running amps indicated Y[] N[X] S[]U[] FR-Z.1, and the indicating lights are green ON, step S.b red OFF. I Transitions to the RNO column. Comments:

I Cue: STEP Perform the following:

Applicant observes that RWST level is Critical:

Grade #17 1) IF RWST level is GREATER greater than 520,000 gallons by Y[] N[X] S[]U[] FR-Z.1, THAN 520,000 gal, THEN checking level on any of the meters at step S.b RNO Proceed to step 5.d. MB2: QSS*Ll930, 931, 932 or 933. A(:>plicant proceeds to step 5.d. Comments:

Cue: STEP Check Ctmt WR sump level Applicant observes that CTMT Wide Critical:

Grade #18 (3RSS*Ll22A, 3RSS*Ll22B)

-Range sump level is LESS than 7.5 Y[] N[X] S[]U[] FR-Z.1, GREATER THAN 7.5 feet feet by checking meters 3RSS*Ll22A step S.d and / or 3RSS*Ll22B level on Meters at MB2. Transitions to the RNO column. Comments:

Cue: 10

---

STEP Perform the applicable action: Applicant observes that QSS flow is Critical:

Grade #19 not indicated by checking meters QSS-Y[]N[X] IF QSS flow is NOT indicated, FI32A and FI32B at MB2. step S.d THEN Proceed to NOTE prior RNO to step Applicant proceeds to step 6. Comments:

Cue: Applicant reviews NOTE. Critical:

GradeThe Locked Valve Key isY[] N[X] S[]U[]required for performance of some FR-Z.1, s te p 6 of the local actions in the NOTE following step. The preferred priority selecting a recirculation pump is as Pump C or D Pump Aor B After reading the notes, the examinee may ask about which pump to use. If asked, or if the Candidate selects the 'C' RSS pump, provide the following cue: Cue: The US directs you to align recirculation spray pump "D."

--STEP Check If Spray Using An RSS Applicant observes that RWST level is Critical:

Grade #21 Pump From The RWST Should Be greater than 520,000 gallons by Y[] N[X] S[]U[]FR-Z.1, checking level on any of the meters at step , MB2: QSS*Ll930, 931,932 or Check the RWST level-THAN 100,000 Quench Spray pumps NONE AOTS/CR recommends

-USING RSS PUMP FROM RWST SPRAY THE Comments:

Cue: Observes that the indicating lights are Critical:

Grade green ON, red OFF for the 'B' QSS Y[] N[Xl S[]U[l pump. The pump is not running. Pump 3QSS*P3A is tagged out. Comments:

When the applicant asks for a AOTS/CR OS EO recommendation, provide the following cue: Cue: The CR OSEO recommends using one RSS pump from the RWST to spray containment.

STEP RESET SI Applicant depresses the MB2 SI Critical:

Grade #22 RESET pushbuttons.

Y[X] N[] S[]U[]FR-Z.1, step 6.b Comments:

This action will cause several annunciators to clear and alarm. The examinee should acknowledge and reset these annunciators as appropriate.

However, this action is not required to complete the critical nature of this step. Cue: STEP Determine the RSS pump to be The applicant should recognize that the #23 placed in service '0' RSS pump will be placed in service. FR-Z.1, step 6.c Comments:

The "0" recirculation spray pump wi!1 be used (cue provided in JPM step 20) Cue: STEP Place the selected recirculation

1. 24 spray pump in PULL TO LOCK FR-Z.1, step 6.d Comments:

Cue: STEP For the selected RSS pump, #25 START the associated RECIRC FR-Z.1, SPRAY ACU step 6.e (3HVQ*ACUS2A or 3HVQ*ACUS2B)

Comments:

Cue: Rotates the 3RSS*P1 0 control switch to the PULL TO LOCK position and then pulls the switch handle up into "PULL-TO-LOCK".

At VP1, the applicant rotates the 3HVQ*ACU2B control switch to "START" and observes indicating lights shift to green OFF, red ON. Comments:

3QSS*AOV27 and 3QSS*AOV28 may be operated in any order. STEP OPEN RWST recirculation suction

1. 26 valves (MB1) FR-Z.1, step 6.f

• 3QSS*AOV27

• 3QSS*AOV28 Comments:

Cue: Depresses the 3QSS*AOV27 OPEN pushbutton, observes the indicating lights shift to green OFF, red ON, then releases the pushbutton.

Critical: Y[] N[X] I

• Critical:

Grade Y[X] N[] S[]U[] Critical:

Grade Y[X] N[] S[]U[l Critical:

Grade Y[X] N[] S[]U[] I

---

STEP #27 FR-Z.1, step 6.g Comments:

Cue: Comments:

Cue: STEP #28 FR-Z.1, step 6.h -Depresses the 3QSS* AOV28 OPEN Critical: pushbutton, observes the indicating Y[X] N[] lights shift to green OFF, red ON, releases the Using Attachment B, locally align Either contacts the PEO or requests Critical:

Grade selected RSS the US contact the PEO to use Y[] N[X] Attachment B to locally align the recirculation spray As PEO or US acknowledge the request. *BOOTH: At the instructor station enter the following:

I* Remote Functions:

CSR05 to I/O override:

CSL00047 (3RSS*MOV230 red light) to Evaluator:

Once these remotes are active, provide the following cue: The Attachment B lineup for "0" recirculation spray pump has been completed. Check the selected recirculation Observes the indicating lights for Critical: spray pump RHR isolation-3RSS*MV8838B are green ON, red Y[] N[X] CLOSED OFF. The valve is For pump i

__ _ r-STEP #29 FR-Z.1, step 6.i STEP #30 FR-Z.1, step 6.j Comments:

Cue: STEP #31 FR-Z.1, step 6.k STEP #32 Check the selected recirculation spray pump spray header isolation valve -OPEN Observes the indicating lights for 3RSS*MOV20D are green OFF, red ON. The valve is open.

• For pump D -3RSS*MOV20D Check local system alignment

-Verifies that the local system alignment COMPLETED is complete.

The examinee was informed when lineup was completed (JPM step 23). START the selected RSS Pushes down on the "0" recirculation spray pump control switch to take it out of "PULL-TO-LOCK." Rotates the control switch to liST ART" and observes that amperage is indicated and the indicating lights shift to green OFF, red ON. The applicant should also check that flow is present by observing flow indication on 3RSS-FI40D.

Notify the US that containment Applicant informs the US that spray has been initiated containment spray has been initiated using the "0" recirculation s(:lray (:lump. TERMINATION CUE: The evaluation for this JPM is concluded.

15 Y[ J Y(X]

Y[] STOP TIME: -Grade S[]U[] ! Grade S[]U[] Grade S[]U[] i

--VERIFICATION OF JPM "IPM Number: 2K11 NRC S.6 Revision:

2 Date Performed:

Student: Evaluator:

To achieve a satisfactory grade, ALL critical steps must be completed correctly.

If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade. Time Critical Task? Yes No X Validated Time (minutes):

10 Actual Time to Complete (minutes):

Overall Result of JPM: SAT UNSAT Areas for Improvement I Comments:

16 ____-------I l JPM Number: Initial Conditions:

Initiating Cues: STUDENT 2K9 NRC S.3 Revision:

2 A steam-line break inside containment has occurred.

Based on plant conditions, a manual reactor trip and safety injection were initiated.

The Control Room Team is progressing through the EOPs and during the transition to E-2, Faulted Steam Generator Isolation, a COA signal was received and an "orange" path for containment integrity.

The "An Quench Spray Pump is tagged out for maintenance.

The US has directed you to perform FR-Z.1, Response To High Containment Pressure, in an attempt to initiate containment spray. 17 l JOB PERFORMANCE MEASURE APPROVAL JPM Title: JPM Number: Initiated:

Reviewed:

Approved:

Energize SBO Auxiliaries with the SBO Diesel 2K11 NRC S.7 Dave Technical Reviewer Supervisor, Nuclear Training Revision:

o 2/19/11 Date /Date DIte I i

SUMMARY

OF DATE DESCRIPTION REV/CHANGE

-l.___2

---

JPM Facility:

____ Examinee:

JPM Number: 2K11 NRC S.7 Revision:

0 Task Title: Energize SBO Auxiliaries with the SBO Diesel System: 062 -AC Electrical Distribution Time Critical Task: ) YES (X) NO Validated Time (minutes):

___1_2__ Task Number{s):

000-05-124 Applicable To: SRO X RO X PEO __ KIA 062 A1.01 KIA Rating: 3.4/3.8 Number: Method of Simulated Actual Performance:

Performance:

Location:

Classroom:

Simulator:

X In-Plant:

Task Standards:

All critical steps are performed satisfactorily.

All sequential steps are performed in proper procedural sequence.

GA-27, Energizing SBO Diesel Auxiliaries With SBO Diesel Required Materials: (procedures, equipment, etc.) GA-27, Energizing SBO Diesel Auxiliaries With SBO Diesel, Revision General

References:

000 ES-0.1! Reactor Trip Response, Revision 024 X

• • • READ TO THE EXAMINEE I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this JPM will be satisfied.

You may use any approved reference material normally available in the Control Room, including logs. Make all reports, oral reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.

JPM WORKSHEET JPM Number: 2K11 NRC Revision:

o Reg Resetto IC 253 .... OR Reset IC 18 (or any 100% Pwr IC) and perform steps below: Insert malfunction ED01 -Loss of Offsite Power. To give the appearance that the control room team has carried out the actions in E-O and ES-0.1 through step 7, perform the following.

• Close the MSIV's and MSL drains upstream of the MSIVs.

• Take motor driven feed pump control switch to PULL-TO-LOCK.

• Take all condensate pump control switches to PULL-TO-LOCK.

• Transfer condenser steam dumps to Steam Pressure mode.

• Start the 'B' lAS Compressor, and the "A' and 'B' PZR heaters.

• Reenergize 32-3T.

• Throttle AFW flow to about 150gpm per SG.

• Reset LOP from MB2.

• Allow reactor power to decrease into the source range and shift the NR45 recorder to the source ranges. Acknowledge and clear alarms. Place the simulator in "Freeze" After the has the initiating cues and initial conditions, place the simulator in "RUN". Approximate setup time is 10 minutes.

Initial Conditions:

A turbine trip occurred and the reactor tripped. Moments later, a loss of offsite power occurred.

Information indicates that offsite power will not be restored for an extended period of_ time. The control room team has carried out E-O immediate actions, transitioned to ES-O.1 and completed steps 1 through 7. Initiating Cues: The US has directed you carry out step 8 of ES-O.1, Check Power To SBO Diesel Auxiliaries.

The SBO is not running . .. .. .. .. NOTES TO TASK PERFORMANCE EVALUATOR" ...... Critical steps for this JPM are indicated by checking ny". For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly. When the student states what his/her simulated action/observation would be, read the appropriate "Cue". If necessary, question student for details of simulated actions/observations (Le. 'What are you looking at?" or "What are you observing?"). Under NO circumstances must the stUdent be allowed to manipulate any devices during the performance of this JPM (in-plant only). l,___5 PERFORMANCE INFORMATION JPM Number: 2K11 NRC Revision:

o Task Title: Energize SBO Auxiliaries with the SBO Diesel START TIME: ____ PERFORMANCE STEP STANDARD STEP Obtains copy of Critical:

Grade Obtains a copy of ES-O.1! refers to Y[JN[X] S [ ] U [ ]

Step 8, NOTES. Comments:

Cue: STEP

• If the SBO diesel auxiliaries Candidate reviews the NOTES . Critical:

Grade Y[JN[X] S [ ] U [ ]

are not repowered within hour, the SBO diesel may E SO. 1 , unavailable for starting.

s t e p Power to the SBO auxiliaries should monitored and if power is GA-25 or GA-27, applicable, should be used re-establish Comments:

Cue:

-STEP #2 E S 0.1, step 8.a Comments:

Cue: STEP #3 E SO. 1

• step 8.a RNO Check Power To SBa Diesel At MB8, Candidate observes that Bus Auxiliaries 34A and 34B are both de-energized.

Verify any SBO bus tie breaker -CLOSED TO AN ENERGIZED BUS Bus 34A: 34A 1-2 Bus 34B: 3481-2 8us 24E: A505 (Unit 2) Call Unit 2 for breaker A505 Candidate calls the Unit 2 Control Room and asks for the status of the A505 breaker. As the Unit 2 BOP operator, provide the following cue: The A505 breaker is open. Recognizes that NO SBO bus tie breaker is closed to an energized bus. Transitions to the RNa column. Perform the applicable Candidate recognizes that Bus 34A and 34B are still both de-energized and IF busses 34A AND 34B are GA-27 is NOT energized, THEN GA-27, Establish power SBa diesel 7

Y[] -Grade S[]U[] Grade S[]U[]

• I Grade S[]U[] I Grade S[]U[]

---

---

STEP #4 STEP #5 GA-27, s t e p 1 NOTE Comments:

Cue: STEP #6 s t e p STEP #7 GA-27, step 2.8 Comments:

Cue: Obtains copy of GA-27. Critical:

I Obtains a copy of GA-27 , refers to Grade Y [ ] N [X ] S[]U[]Step 1, NOTE. I If the SBO diesel auxiliaries are not Critical:

Grade Candidate reviews the NOTE. reenergized within an hour, the SBO Y [ ] N [X ] diesel may be unavailable Check SBO Diesel -NOT Candidate recognizes form the initial Critical:

Grade RUNNING cue that the SBO Diesel is not running. Y[]N[X] S[]U[] If the Candidate questions the status of the SBO Diesel, provide the following cue: I he SSO Diesei is not running. Align To Energize Auxiliaries Observes the breaker status, opens Critical:

Grade 34A 1-2 at Bus 34A. Observes that the Y[X] N[] S[]U[] OPEN all SBO bus tie breakers indicting lights for breaker 34A 1-2 are green "ON", red "OFF" and the control

• Bus 34A: 34A 1-2 (MB8) switch flag is green.

• Bus 34B: 34B 1-2 (MB8)

• Bus 24E: A50S (Unit 2) The breaker cubicle associated with Bus tie breaker 34B1-2 has no breaker. The Candidate should recognize that Unit 2 already reported that the A50S breaker is open. ----_.-

I STEP Locally check SSO MCC transfer Candidate simulates contacting PEO or Critical:

Gradel #8 switch (3SGS-TRS1) in -requests US contact PEO to report the Y[JN[X] S[]U[]i GA-27, SACKFEED/NORMAL SOURCE position of 3SGS-TRS 1 . step 2.b After being dispatched, call the Control Room as the PEO in the field, provide the following cue: Cue: The SSO MCC transfer switch is in the SACKFEED/NORMAL SOURCE position.

The substeps associated with step 3 of GA-27 are all local actions. If the Candidate questions whether the PEO has been briefed on GA-27 , step 3 local actions, provide the following cue: Cue: The PEO has been briefed on step 3 local actions, and has a copy ofGA-27 in hand. ... ... STEP At the SSO DIG control panel Critical: #9 (section 1), Start the SSO Diesel Y [ ] N [X ] 5 t e p Comments:

BOOTH: Insert the following Remote Functions to start the SSO and close its output breaker; EGR08 to 'START' and EDR32 to 'CLOSE'. When the remotes are active, call the Control Room as the PEO in the field and provide the following cue; Cue: The SSO Diesel is started and powering auxiliaries STEP Loading of the SSO diesel is Critical:

Grade Candidate reviews the #10 preclude excessive oil going past the Y [ J N [X J piston rings and accumulating in the s t e p 4 exhaust of the SSO Diesel. NOTE Comments:

Cue: STEP Check loading SSO diesel -The Candidate should question the US Critical:

Grade #11 DESIRED which if loading the SSO Diesel is Y [ J N [X J S[]U[] GA-27, desired. s t e p 4 9

-

As the US provide the following cue; Cue: Yes, loading the SSO Diesel is desired. STEP Align For seo Diesel Loading Recognizes that the SBO bus tie Critical:

Grade #12 breaker is racked up in bus 34A. Y[]N[X] S[]U[] GA-27, Check SSO bus tie breaker step S.a ALIGNED TO SELECTED EMERGENCY The Candidate may question the US which is the selected non-emergency bus. Provide the following cue; Cue: Sus 34A is the selected bus. STEP OPEN NSST feeder for selected Rotates the control switch for breaker Critical:

Grade * #13 non-emergency bus (MBS) NSSA-34A-2 to the trip position.

Y[] N[X] S[]U[] GA-27, Observes the indicating flag goes to step S.b For Bus 34A:

green, the amber light goes out and the

• green light remains lit.

Annunciator MBSA 5-9 "BUS 34A NORM SPL Y AUTO TRIP" clears. The examinee should acknowledge the clearing of this alarm. However, this action is not necessary to complete this step. Comments:

Since the breaker is already open, the examinee may elect not to rotate the switch to the trip position.

Either action is acceptable to complete this step. Cue: STEP OPEN tie breaker between selected Rotates the control switch for breaker Critical:

Grade #14 non-emergency and emergency bus 34C*1T-2 to the trip position.

Y[] N[X] S[]U[] GA-27, Observes the indicating flag goes to s t e p green, the amber light goes out and the step S.c For Bus 34A: 34C*1 T-2 green light remains lit.

• Since the breaker is already open, the examinee may elect not to rotate the switch to the trip position.

Either action is acceptable to complete this step. 10 STEP OPEN the following load center For each of the listed breakers, #15 supply breakers for selected non-the control switch to the emergency bus: (MBa) position and observes the flags shift to step 5.d green and the indicating lights shift to For Bus 34A: green "ON", red "OFF". 32A (32A-2) 32B (32B-2) 32C (32C-2) 320 (320-2) 32E (32E-2) 32F (32F-2) 32G (32G-2) Comments:

The Candidate may elect to also open breaker SWYD/FWPH (XFMR SUPPL Y . Cue: STEP Align Selected Non-Emergency At MB6, positions the control switch for #16 Bus the "A" screen wash pump to GA-27, lock" and observes that all the step 6.a Place the following switches in indicating lights go out. PULL-TO-LOCK:

• Screen wash pump

• Circulating water pumps

• TPCCW pump(s) At MB6, positions the control switches for the "A", "C" and "E" circulating water pumps to "pull-to-Iock" and observes that all of the indicating lights go out. , Critical:

Grade Y[X] N[] S[}U[] Critical:

Grade Y[X) N[] S[}U[] Critical:

Grade Y[X] N[} S[]U[]

I r-#17 GA-27, step 6.b At MBo, positions the control switches Critical: for the "A" and "c" TPCCW pumps to Y[X] N[] "pull-to-Iock" and observes that all the indicating lights go The switches may be operated in any order. Candidate may elect to also place the non-selected train switches in PTLIOFF in the following steps. Critical performance is satisfied as long as the selected switches are correctly positioned.

Place the following switches to At MB1, positions the control switches Critical:

Grade STOP: for CDS chillers "1A" (and "1 B" if Y[X]N[] S[]U[] aligned) to the "stop" position and

• CDS chiller(s) observes that the amber light goes out

• Heater drain pump(s) and the green light remains on.

• MSR drain pump The switches may be operated in any order. At MB6, rotates the control switches for Critical:

Grade heater drain pumps "An and "c" to the Y[X] N[] S[]U[] "stop" position and observes that the amber light goes out and the green light remains on. At MB6, rotates the control switch for Critical:

Grade MSR drain pump "AI! to the "stop" Y[X] N[] S[]U[] position and observes that the amber light goes out and the green light remains on. 12 i

---

STEP CLOSE SBO Bus Tie Breaker Rotates the control switch for breaker Critical:

Grade #18 (MBS) To Selected Non-34A 1-2 to the "close" position and Y[X] N[] S[]U[] GA-27, Emergency Bus observes the flag shifts to red and the s t e p 7 indicating lights shift to green OFF, red

• For Sus 34A: 34A1-2 ON. Comments:

Annunciator MS8A 2-9 "SUS 34A UNDERVOL TAGE" will clear. The examinee should acknowledge the clearing of this alarm. However, this is not necessary to complete the critical nature of this step. Cue: STEP Increase SBO Diesel Load To Candidate simulates contacting PEO or Critical:

Grade #19 Greater Than 500 Kw requests US contact PEO to Place the Y [ ] N [X ] S[]U[] GA-27, START MODE switch in NORM. step 8.a At the SSO Engine Control Panel Place the START MODE switch in I NORM Comments:

Call the Control Room as the PEO in the field and provide the following cue; Cue: The START MODE switch is in NORM. STEP Check SSO diesel load (SSO DIG Candidate simulates contacting PEO or Critical:

Grade #20 Control Panel) -requests US contact PEO to report Y[]N[X] LESS THAN 500 Kw SSO Diesel load. step B.b I Comments:

Report as the PEO in the field the following cue; i i Cue: SSO Diesel load is a Kw. STEP Using the load list on Table 1, Candidate refers to Table 1 in GA-27 to Critical:

Grade #21 Energize selected load determine the appropriate load(s) to Y [ ] N [X ] S [ I U [ energize.step B.c 13

---

Note; the only listed loads on Table 1 that are powered from non-emergency bus 34A are load centers 32E," 32G and HVT -FN2A.

The Candidate may question the US which load(s) to energize.

Provide the following cue; Cue: Energize Load Center 32G. STEP Note 3 -Open breaker 32-5G-1 M to Recognizes that Note 3 on Table 1 Critical:

Grade #22 deenergize HVY -FN 1 A before applies if energizing Load Center 32G. Y[] N[X] S[]U[] GA-27, energizing load center. Table 1, Not e 3 Comments:

Cue: Candidate simulates contacting PEO or Critical:

Grade requests US contact PEO to proceed Y[X] N[] S[]U[] to the 'A' Service water cubicle to open breaker 32-5G-1 M.

After being dispatched, call the Control Room as the PEO in the field and provide the following Que; Cue: Breaker 32-5G-1 M is open. For load center supply breaker 32G Critical:

Grade (32G-2), rotates the control switch to Y[X] N[] S[]U[] the "CLOSE" position and observes the flags shift to red and the indicating lights shift to green "OFF", red "ON". Comments:

Cue: 14

-STEP Check SBO diesel load (SBO DIG Candidate simulates contacting PEO or Critical:

Grade #23 Control Panel, section 1) -requests US contact PEO to report Y[]N[X] S[]U[] GA-27, GREATER THAN 500 Kw SBO Diesel load. step S.d Comments:

Report as the PEO in the field the following; Cue: SBO Diesel load is 530 Kw Candidate recognizes the SBO Diesel Critical:

Grade is loaded greater than the required 500 Y [ ] N [X ] S[]U[] Kw. Comments:

Cue: STEP Notify the SMIUS the SBO Diesel is Candidate reports to US that the SBO Critical:

Grade #24 loaded Diesel is loaded by energizing load Y [ ] N [X ] S[]U[] GA-27, center 32G. step S.e Comments:

Cue: TERMINATION CUE: The evaluation for this JPM is concluded.

STOP TIME: ---+__

--VERIFICATION OF JPM JPM Number: 2K11 NRC S.7 Revision: -0 Date Performed:

Student: Evaluator:

To achieve a satisfactory grade, ALL critical steps must be completed correctly.

If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade. Time Critical Task? Yes No X Validated Time (minutes):

12 Actual Time to Complete (minutes):

Overall Result of JPM: SAT UNSAT Areas for Improvement I Comments:

STUDENT JPM Number: Initial Conditions:

Initiating Cues: 2K11 NRC S.7 Revision:

o A turbine trip occurred and the reactor tripped. Moments later, a loss of offsite power occurred.

Information indicates that offsite power will not be restored for an extended period of time. The control room team has carried out E-O immediate actions, transitioned to ES-O.1 and completed steps 1 through 7. The US has directed you carry out step 8 of ES-O.1, Check Power To SSO Diesel Auxiliaries.

The SSO is not running.

JPM Title: JPM Number: Initiated:

Reviewed:

Approved:

JOB PERFORMANCE MEASURE APPROVAL SHEET Aux Bldg EI. 24'6" South Floor Area Fire (All Chg Lost/Alt Path 2) 2K11 NRC S.8 (JPM-206D)

Dave Supervisor, Nuclear Training Revision:

02/25/11 Date , .Date I Date 1 I

SUMMARY

OF DATE DESCRIPTION REV/CHANGE 02/25/11 JPM updated to revision 004-03 to EOP 3509.2. Added 1 -malfunctions RP09A and B (reactor trip switches fail) modify the JPM. Added as the last step of the JPM to Reps (step 21 of EOP 3509.2). Aded that the task is critical to the initiating cue. Modified JPM format to consistent with the NRC 2K11 JPM set. Deleted Pass/Fail criteria.

---

JPM Facility:

____ Candidate:

M_P_3____ JPM Number: 2K11 NRC S.8 Revision:

1 Task Title: Aux Bldg EI. 24'6" South Floor Area Fire (All Chg LostiAlt Path 2) System: 7 -012 Time Critical Task: (X) YES ( ) NO Validated Time (minutes):

5 Task Number(s):

000-05-1 600-05-032 Applicable To: SRO X RO X PEO KIA APE:067-M2.16 KIA Rating: 3.3/4.0 Number: Method of Testing: Simulated Actual x Performance:

Performance:

Location:

Classroom:

Simulator:

x In-Plant:

Task Standards:

Satisfactorily implement EOP 3509.2, "Aux Bldg EL. 24'6", South Floor Area, 43'6" & 66'6" Fire," in response to a fire that disables all charging pumps. Time critical steps must be performed within analyzed times. All critical steps are performed satisfactorily.

All sequential steps are performed in proper procedural sequence.

Required Materials: (procedures, equipment, etc.) EOP 3509.2 MP3 Simulator General

References:

EOP 3509.2, "Aux Bldg EL. 24'6", South Floor Area, 43'6" & 66'6" Fire", Revision 004-03 [,___3 _-------l

• • • READ TO THE CANDIDATE

• • • I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When complete the task successfully, the objective for this JPM will be satisfied.

You may use any reference material normally available in th_e Control Room, including logs. Make all written reports, reports, alarm acknowledgements, and log entries as if the evolution was actually being JPM WORKSHEET JPM Number: 2K11 NRC Revision:

1 Simulator Reset to IC 287 ..... OR Reset to any 100% power IC. Insert 110 [CV] 3CHS*MV8112 red "ON" (CVL00072) Insert malfunctions RP09A and B. Place simulator in "RUN" after the operator receives instructions Initial A fire is in progress in the Auxiliary Building 24'6" South area. The control room team is implementing EOP "Fire Emergency," and EOP 3509.2, "Aux Bldg EL. South Floor Area, 43'6" & 66'6" Fire." The Fire Adviser has just reported probable fire involvement of charging pumps is Initiating The US has directed you to perform EOP 3509.2 with step 15 (Isolate RCS). This is a time critical * * *

• NOTES TO TASK PERFORMANCE EVALUATOR * * *

• Critical steps for this JPM are indicated by checking "Y". For the student to achieve satisfactory grade, ALL critical steps must be completed When the student states what his/her simulated action/observation would be, read appropriate If necessary, question student for details of simulated actions/observations (i.e. "What you looking at?" or "What are you

• Under NO circumstances must the student be allowed to manipulate any devices during the I performance of this JPM (in-plant only). I 4 PERFORMANCE INFORMATION JPM Number: 2K11 NRC S.8 Revision: Task Title: Aux Bldg EI. 24'6" South Floor Area Fire (All Chg Lost/Alt Path START TIME: ____ PERFORMANCE STEP STANDARD STEP Obtains copy of EOP 3509.2. Critical:

Grade Candidate obtains a copy of EOP#1 Y[]N[X] Sf] U[l 3509.2, refers to Step 15. Comments:

Cue: STEP Critical:

Grade Isolate RCS Depresses the CLOSE pushbutton for #2 Y[X] N[] S[]U[]3CHS*AV8149C (or AV8149B if in CLOSE letdown orifice isolation service) and observes vaive closes by 3509.2, valves I s t e p red indicating light OFF, green ON. 1 5. a Comments:

Cue: STEP Verifies that 3RCS*SV8095A1B and Critical:

Grade Verify excess letdown and reactor #3 3RCS*SV8096A1B are closed by Y[ 1 N[XJ S[1U[1 head vent isolation valves 3509.2, observing the indicating lights green s t e p CLOSED 1 5. b ON, red OFF. Comments:

Cue: 5 I Verifies that 3RCS*AV8153 is closed Critical:

by observing the indicating lights green Y[]N[X] S[l U[l ON, red OFF. Comments:

Other valves in the flowpath can be checked closed as well. Cue: STEP STOP all charging pumps and Place Rotates 3CHS*P3B control switch to Critical:

Grade #4 all charging pump control switches in stop, confirms running charging pump Y[X] N[] S[J PULL---TO---LOCK has stopped, and places all charging s t e p 15. C pump control switches in PULL---LOCK. Comments: STEP Depresses close push buttons for Critical: CLOSE RCP sealleakoff

1. 5 3CHS*MV8112 and observes red open Y[]N[X] S[]U[l containment inner isolation valve 3509.2. indication does not extinguish.

s t e p (3CHS*MV8112) 1 5. d Transitions to RNO column Comments:

Cue: STEP Depresses close push buttons for Critical:

Grade CLOSE RCP sealleakoff

1. 6 3CHS*MV8100 and observes valve Y[X] N[ 1 S[]U[l containment outer isolation valve 3509.2, closes by red indicating light OFF, s t e p (3CHS*MV81

00) 1 5. d green ON. .RNO Comments:

• Time must be < 5 minutes from JPM start for SAT grade. Time: Cue:

---

STEP

• DO NOT Go To E-O, Reactor #7 Trip or Safety Injection

• The reactor can be interpreted 3509.2, step 16 as "tripped" when any two of the NOTES three bullet substeps of step 17. are satisfied Comments:

Cue: STEP TRIP The Reactor AND Remain In#8 This Procedure 3509.2, step 16 Comments:

Cue: STEP Verify Reactor Trip #9

• Check reactor trip and bypass 3509.2, breakers -step

• Check rod bottom lights -LIT

• Check neutron flux DECREASING Comments:

Cue: STEP TRIP the reactor. #10 3509.2, IF reactor will NOT trip, step 17 RNO THEN TRIP Bus 328 and 32N. Comments:

Cue: -Candidate reviews the NOTES. Critical:

Grade Y[] N[X] S[]U[] Critical:

Grade Rotates the reactor trip switch on M B4 Y[] N[X] S[JU[J to the "trip" Observes that the reactor trip breakers Critical: are closed, no rod bottom lights are lit Y[] N[X] and that reactor power is decreasing.

The reactor is not Shifts to the actions required in Rotates the reactor trip switch on MB7 Critical: to the "trip" position.

Observes that the Y[] N[X] reactor trip breakers are closed, no bottom lights are lit and that power is not decreasing.

The is still not I 7

---

I Proceeds to MB8 and rotates the Critical:

Grade # supply Breaker switches for load Y[X]N[ ] S[]U[] centers, 328 & 32N to the "open" positions.

Comments:

All 4 breakers {high side and low side supply breakers}

need not be operated.

Comments:

• Time must be < 10 minutes from JPM start for SAT grade. Time: Cue: STEP Observes that all rod bottom lights are Critical:

Grade #12 lit and that neutron flux is decreasing.

Y[] N[X] S[]U[] The reactor is tripped. Comments:

Cue: STEP Dispatch an operator to locally TRIP Either contacts the PEO or requests Critical:

Grade #13 the reactor trip and bypass breakers.

the US contact the PEO to locally trip Y[] N[X] S[]U[] the reactor trip and bypass breakers.

Proceeds to step 18. Comments:

If requested, as the US provide the following cue: Cue: A PEO has been dispatched to trip the reactor trip breakers. Critical:

Grade Verify Turbine Verifies turbine tripped by checking the Y[] N[X] S[]U[]stop valve meter indications on thes t e p 1 8 EHC insert on MB7 and observes Check all turbine stop valves all of the turbine stop valves Comments:

Cue: 8 STEP Checks voltage indication for either bus Critical:

Verify Power To AC Emergency#15 34C or 340 on MBS and observes that Y[] N[X] S[]U[]Busses 3509.2, voltage is present. Both busses 34C s t e p 19. a and 340 are energized.

Check busses 34C and 340 -AT LEAST ONE ENERGIZED Comments:

Cue: STEP Check busses 34C and 340 -Checks voltage indication for busses Critical:

Grade #16 BOTH ENERGIZED 34C and 340 on MBS and observes Y[] N[X] S[]U[] 3509.2, that voltage is present. Both busses s t e p 19. b 34C and 340 are energized.

Comments:

Cue: STEP CLOSE The MSIVs And MSIV Candidate locates on MB5 and rotates Critical:

Grade #17 Bypass Valves the control switch for the 'A', 'B', 'C' Y[X] N[] S[]U[]3509.2, and '0' S/G MSIVs (3MSS*CTV27 A-D) step 20 to the "close" position and observes the indicating lights shift to green ON, red OFF. Comments:

• Time must be:: 11 minutes from JPM start for SAT grade Time: Cue: Candidate verifies the MSIV bypass Critical:

Grade valves are closed by observing the Y[] N[X] S[]U[] indicating lights are green ON, red OFF. Comments:

Cue:

STEP STOP all RCPs Candidate locates on MB4 and rotates Critical:

Grade #18 the control switches for the 'A', 'B', 'c' Y[X] N[] S[]U[] 3509 2. and '0' RCPs to the stop position step 21 observes the indicating lights shift to green ON, red OFF and/or RCS loop flow decrease.

Comments:

Cue: TERMINATION CUE: The evaluation for this JPM is concluded.

STOP TIME: ___

VERIFICATION OF JPM COMPLETION JPM Number: 2K11 NRC S.8 Revision:

1 Date Performed:

Student: Evaluator:

To achieve a satisfactory grade, ALL critical steps must be completed correctly.

If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade. Time Critical Task? YES X NO Validated Time (minutes):

OCA: Req. Actual 1) Isolate Letdown 5min 2) Trip Reactor 10 min 3) Close MSIV's & Bypass Valves 11 min Result of JPM: ("S" for satisfactory, "U" for unsatisfactory)

Result of oral questions (if applicable):

Number of Questions:

Number of Correct Responses:

Score: Areas for Improvement

/ Comments:

1 STUDENT JPM !\lumber:

Initial Conditions:

Initiating Cues: 2K11 NRC S.8 Revision:

A fire is in progress in the Auxiliary Building 24'6" South Floor area. The control room team is implementing EOP 3509, "Fire Emergency," and EOP 3509.2, "Aux Bldg EL. 24'6", South Floor Area, 43'6" & 66'6" Fire." The Fire Brigade Adviser has just reported probable fire involvement of all charging pumps is expected.

The US has directed you to perform EOP 3509.2 beginning with step 15 (Isolate ReS). This is a time critical task.

JPM Title: JPM Number: Initiated:

Reviewed:

Approved:

JOB PERFORMANCE MEASURE APPROVAL SHEET Establish Service Water to Train "B" Control Building Chilled Water Cross Tie 2K11 NRC P.1 (2K2 NRC P.02 New) Revision:

1 03/02/11 Developer Date tfJ ,)/5/0I Technical Revie Date I Supervisor, Nuclear Training Date l___,_----.-...I l

SUMMARY

OF DATE DESCRIPTION REV/CHANGE 03/02/11 Updated to Rev 022-05 of OP 3314F. Added OP 3314F step 1 10 4.22.1.f (close 3SWP*V44) to enhance the JPM. Modified the JPM to lineup the '8' train of service water to the '8' HVK system. Original JPM was 'A' trains. Modified JPM format to be consistent with the NRC 2K11 JPM set. DLM

---JPM Facility:

---

=-:...M"--P...::..3

____ Examinee:

JPM Number: 2K11 NRC P.1 Revision:

1 Task Title: Establish Service Water to Train "B" Control Building Chilled Water Cross Tie System: 4.2 -076 (Service Water) Time Critical Task: ) YES (X) NO Validated Time (minutes):

__

__ Task Number(s):

088-01-059 Applicable To: SRO X RO X PEO X KIA Number: 076-K1.19 KIA Rating: 3.6 I 3.7 Method of Simulated X Actual Performance:

Performance:

Classroom:

Simulator:

In-Plant:

x Task Establish and restore from Service Water supplying the Control Building (HVK) chilled water system. All critical steps are performed satisfactorily.

All sequential steps are performed in proper procedural sequence.

Required Materials:

OP 3314F, Rev. 022-05 (procedures, equipment, etc.) General OP 3314F, Control Building Heating, Ventilation, Air Conditioning and Chill Water, Rev. 022-05 P&IDs; EM-133D, 151 D ES-1.2, Post LOCA Cooldown and Depressurization l,___3 r *** READ TO THE EXAMINEE *** I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this JPM will be satisfied.

You may use any approved reference material normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.

JPM WORKSHEET JPM Number: 2K11 NRC Revision:

1 Initial The unit has experienced a Loss of Coolant accident and is Using ES-1.2, Post LOCA Cooldown and Depressurization, to reduce RCS temperature and pressure.

Both HVK Chillers have been damaged and are not operable.

Initiating The US has directed you to establish service water to Train B of Control Building chilled water cross tie using OP 3314F, Control Building Heating, Ventilation, Air Conditioning and Chill Water, section 4.22. A copy of the procedure section and applicable P&IDs have been provided for your use. Simulator NONE * * *

• NOTES TO TASK PERFORMANCE EVALUATOR * * *

• Critical steps for this . ..IPM are indicated by checking "Y". For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly. When the student states what his/her simulated action/observation would be, read the appropriate "Cue". If necessary, question student for details of simulated actions/observations (i.e. "What are you looking at?" or "What are you observing?"). Under NO circumstances must the student be allowed to manipulate any devices during the performance of this JPM (in-plant only).

PERFORMANCE INFORMATION JPM Number: 2K11 NRC Revision:

1 Task Title: Establish Service Water to Train "B" Control Building Chilled Water Cross Tie START TIME: ____

STANDARD STEP Establishing the cross---tie will require a Candidate reviews CAUTION. Critical:

Grade #1 lengthy outage to clean up the Control Y [ ] S [ ] OP 3314F Building Chilled Water System. Ensure N[X] U [ ] S t e p 4" 22.1 options to establish chiller operation have CAUTION been exhausted prior to establishing this cross---tie.

Comments:

If the candidate questions whether all options have been exhausted, as US provide the following cue: Cue: All options to establishing chiller operation have been exhausted.

Continue with procedure section. STEP The service water cross---tie must be Candidate reviews NOTE. Critical:

Grade #2 functional for the inoperable train to allow a Y [ ] S [ 1 OP 3314F 30 day AOT. In order to credit the N[X] U [ ] Step tie, service water temperature must be NOTE than or equal to 75 degrees Comments:

Cue: 5 STEP IF establishing service water to Train B Candidate calls Control Room to verify Critical:

Grade #3 Control Building chilled water cross tie, the 'B' HVK Chiller breaker is racked Y [ ] S [ J N[X] U [ ] PERFORM the down. Step 4.22.1.a RED TAG 3401---2, "3HVK*CHL racked j Comments:

When the Candidate simulates calling the Control Room, provide the following cue: The Unit Supervisor informs you the '8' HVK Chiller breaker is racked down and tagged out. STEP UNLOCK and CLOSE 3HVK*V83, B chilled Candidate locates 3HVK*V83 and Critical:

Grade #4 water expansion tank isolation valve. simulates removing the locking device. Y[X] S [ ] Step N [ U [ ] 4.22.1.b The locking device is removed.

Candidate rotates the handwheel for Critical:

Grade 3HVK*V83 in the clockwise direction until Y[X] S [ ] N [ ] U [ ] the valve is fully closed. The handwheel for 3HVK*V83 rotates in the clockwise direction.

You observe the stem lower into the valve. Eventually, some resistance is met and the handwheel comes to a hard stop. STEP OPEN 3HVK*V46, A control building chiller Candidate locates and simulates rotating Critical:

Grade #5 bypass valve. the handwheel for 3HVK*V46 in the Y[X] S [ ] N [ ] U [ J counter-clockwise direction until the valve S t e p is fully open. Comments: 6 I The handwheel for 3HVK*V46 rotates in the direction.

Eventually, some resistance is met and the handwheel comes to a hard stop. Simulates rotating valve hand wheel Critical:

Grade turn in the clockwise direction. Y [ ] S [ ] N[X] u [ 1 Cue: .' Comments:

The valves listed within step 4.22.1.d are bulleted.

They can be closed in any order. STEP Close the following:

Candidate locates and simulates rotating Critical:

Grade #6 the handwheel for 3HVK*V41 in the Y[X] S [ ] S t e p

• 3HVK*V41, control building chiller clockwise direction until the valve is fully N [ J u [ ] unit B inlet isolation closed. Comments: The handwheel for 3HVK*V41 rotates in the clockwise direction.

Eventually, some resistance is met and the handwheel comes to a hard stop. STEP 3HVK*V42, control building chiller Candidate locates and simulates rotating Critical:

Grade*#7 unit B inlet isolation the handwheel for 3HVK*V42 in the Y[X] S [ ] N [ ] U [ ] clockwise direction until the valve is fully closed. Comments:

Cue: The handwheel for 3HVK*V42 rotates in the clockwise direction.

Eventually, some resistance is met and the handwheel comes to a hard stop. ! Critical:

Grade* 3HVK*V44, control building chiller Candidate locates and simulates I Y[X] S [ ] unit B outlet the handwheel for 3HVK*V44 in the N [ U [ ] clockwise direction until the valve is fully closed.

I 7

--I The handwheel for 3HVK*V44 rotates in the clockwise direction.

Eventually, some resistance is met and the handwheel comes to a hard stop. STEP

• 3HVK*V45, control building chiller Candidate locates and simulates rotating Critical:

Grade #9 unit B outlet isolation the handwheel for 3HVK*V45 in the Y[X] S [ ] N [ ] U [ ]

clockwise direction until the valve is Cue: The handwheel for 3HVK*V45 rotates in the clockwise direction.

Eventually, some resistance the handwheel.

comes to a hard STEP 3HVK*V985, chiller oil cooler B inlet Candidate locates and simulates rotating Critical:

Grade* #10 isolation valve the handwheel for 3HVK*V985 in the Y[X] S [ ] N [ ] U [ ]

clockwise direction until the valve is Cue: The handwheel for 3HVK*V985 rotates in the clockwise direction.

Eventually, some resistance is met the handwheel comes to a hard STEP 3HVK*V983, chiiler oil cooler B Candidate locates and simulates rotating Critical:

Grade* #11 outlet isolation valve the handwheel for 3HVK*V983 in the Y[X] S [ ] N [ ] U [ ]

clockwise direction until the valve is Cue: The handwheel for 3HVK*V983 rotates in the clockwise direction.

Eventually, some resistance is met the handwheel comes to a hard Comments:

The valves listed within step 4.22.1.e are bulleted.

They can be closed in any order. ..

Candidate locates 3SWP*V105 and Critical:

Grade UNLOCK and OPEN the following: simulates removing the locking device. VeX] S [ ]

• 3SWP*V105, control building N [ ] U [ ] Step chilled water backup supply isolation 4.22.1.e valve The locking device is removed. The Candidate moves the operator for Critical:

Grade 3SWP*V105 in the counter-clockwise VeX] S [ ] N [ ] U [ ] direction until the valve is fully open. The operator for 3SWP*V105 rotates in the counter-clockwise direction.

The operator comesio a hard stop. Candidate locates 3SWP*V106 and Critical:

Grade* 3SWP*V106, control building 8 simulates removing the locking device. VeX] S [ ] chilled water backup supply isolation N [ U [ ] valve The locking device is removed. The Candidate moves the operator for Critical:

Grade 3SWP*V106 in the counter-clockwise VeX] S [ ] N [ ] U [ ] direction until the valve is fully open. The operator for 3SWP*V1 06 rotates in the counter-clockwise direction.

The operator comes to a hard stop.

---

Candidate locates 3SWP*V1 07 and Critical:

Grade* 3SWP*V107, control building B simulates removing the locking device. Y[X] S [ ] chilled water backup return isolation N [ U [ ] valve The locking device is removed. The Candidate moves the operator for Critical:

Grade 3SWP*V107 in the counter-clockwise Y[X] S [ ] N [ ] U [ ] direction until the valve is fully open. The operator for 3SWP*V1 07 rotates in the counter-clockwise direction.

The operator comes to a Candidate locates 3SWP*V108 and Critical:

Grade* 3SWP*V108, control building B simulates removing the locking device. Y[X] S [ ] chilled water backup return isolation N [ U [ ] valve The locking device is removed. The Candidate moves the operator for Critical:

Grade 3SWP*V108 in the counter-clockwise Y[X] S [ ] N [ ] U [ ] direction until the valve is fully open. The operator for 3SWP*V108 rotates in the counter-clockwise direction.

The operator comes to a STEP PERFORM the following for Candidate calls the Control Room to Critical:

Grade #16 3SWP*TIC35B, "CB CHLR SERV WTR," chiller condenser service water request step 4.22.1.f be carried out at VP1. Y [ ] N[X] S [ ] U [ ] S t e p 4.22.1.f temperature controller (VP1 ): PLACE in "MANUAL".

ADJUST to 0%. VERIFY in "NO RECIRC (open to CWS)," (Red indicator lit.)

It is not intended that the candidate perform VP1 operations.

If the Candidate starts to proceed to the Control Room, or after the simulated call to the Control Room is made, provide the following cue: Cue: The BOP reports that 3SWP*TIC35B is in manual, adjusted to 0% and the red indicator is lit. STEP CLOSE 3SWP*V44, Control Building AlC B Candidate locates and simulates moving Critical:

Grade #17 water chiller condenser service water inlet. the operator for 3SWP*V44 in the Y[X] S [ ] S t e p N [ ] U [ ] clockwise direction until the valve is fully 4.22.1.g closed. Comments:

Cue: The operator for 3SWP*V44 rotates in the clockwise direction.

Eventually, some resistance is met and the operator comes to a hard stop.

It is not intended that the candidate perform the remaining steps. Provide the terminating cue. Cue: Terminating Cue: The evaluation for this JPM is concluded. .........-..---..-.---... .......STOP TIME: ___ I

---1 VERIFICATION OF JPM COMPLETION JPM Number: 2K11NRCP.1 Date To achieve a satisfactory grade, ALL critical steps must be completed correctly.

If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade. Time Critical Task? Yes No X Validated Time (minutes):

15 Actual Time to Complete (minutes):

Overall Result of JPM: SAT UNSAT Areas for Improvement I Comments:

1 JPM Number: Initial Conditions:

Initiating Cues: STUDENT 2K11NRCP.1 Revision:

The unit has experienced a L.oss of Coolant accident and is Using ES-1.2, Post LOCA Cooldown and Depressurization, to reduce RCS temperature and pressure.

Both HVK Chillers have been damaged and are not operable.

The US has directed you to establish service water to Train B of Control Building chilled water cross tie using OP 3314F, Control Building Heating, Ventilation, Air Conditioning and Chill Water, section 4.22. A copy of the procedure section and applicable P&IDs have been provided for your use.

JOB PERFORMANCE MEASURE APPROVAL SHEET JPM Title: Primary Side PEO Actions on a Control Room Evacuation (Part 2) JPM Number: 2K11 NRC P.2 ( JPM-011A)

Revision:

1 Initiated:

2/28/11 Developer Date Reviewed:

Date Approved:

Supervisor, Nuclear Training

SUMMARY

OF CHANGES DESCRIPTION REV/CHANGE Verified updated to Rev 013 of EOP 3509.1. Made JPM step 1 10 6 (Place breaker 32-4U-R5H to OFF), non-critical based on the NOTE prior to ATT A step 8. Modified JPM format to be I consistent with the NRC 2K11 JPM set. Deleted TR-M-410 PasslFaii criteria.

DLM I l___2 JPM Facility:

_M_P_3____

JPM Number: 2K11 NRC P.2 Revision: Task Title: Primary Side PEO Actions on a Control Room Evacuation (Part 2) System: 6 -062 Time Critical Task: ) YES (X) NO Validated Time Task Number(s):

069-01-001, 344-05-026 Applicable To: SRO X RO X PEO X KIA 062-A4.04 KIA Rating: 2.6/2.7 APE-068-AA 1 .14 4.2/4.4 APE-068-AA 1 .10 3.7/3.9 Method of Simulated X Actual Performance:

Performance:

Classroom:

Simulator:

In-Plant:

X Task Satisfactorily complete primary side PEO actions on a control room evacuation lAW 3509.1 AU. A, steps 6 -11 All critical steps are performed satisfactorily.

All sequential steps are performed in proper procedural sequence.

Required Materials:

EOP 3509.1, AUachmentA, rev. 013 (procedures, equipment, etc.) EOP 3509.1, Control Room, Cable Spreading Area Or General

References:

Instrument Rack Room Fire, Attachment A, rev. 013 3 r *** READ TO THE EXAMINEE *** I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this JPM will be satisfied.

You may use any approved reference material normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.

JPM WORKSHEET

,,'PM Number:

Revision:

1 Initial A fire event has occurred requiring shut down outside the control room. The control room team is carrying out actions of EOP 3509.1, Control Room, Cable Spreading Area, or Instrument Rack Room Fire. Initiating The US directs you to perform primary side PEO actions on a control room evacuation lAW EOP 3509.1, Attachment A, steps 6 through 11 only, after referring to the "Appendix

'.'R" Lighting Illuminated Path" maps at the end of the attachment.

Another operator is performing steps 1 through 5. You have the locked valve key. Simulator NONE * * *

• NOTES TO TASK PERFORMANCE EVALUATOR * * *

• Critical steps for this JPM are indicated by checking "Y". For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly. When the student states what his/her simulated action/observation would be, read the appropriate "Cue". If necessary, question student for details of simulated actions/observations (i.e. "What are you looking at?" or "What are you observing?"). Under NO circumstances must the student be allowed to manipulate any devices during the performance of this ,,'PM (in-plant only).

---

PERFORMANCE INFORMATION JPM Number: 2K11 NRC P.2 Revision:

1 Task Title: Primary Side PEO Actions on a Control Room Evacuation (Part 2) START TIME: ____ PERFORMANCE STANDARD Comments:

Direction to refer to maps is step 1 of Attachment A and was included as part of initiating cue. Examinee may elect to review all steps prior to step 6. STEP #1 3509.1, Att A Refer to "Appendix R" Lighting Illuminated Path" maps at end of attachment prior to performing local actions. Candidate locates maps at end of attachment and reviews. Critical: Y [ ] N[X] Grade S [ ] U [ ] step 1 Comments:

When examinee reviews maps provide the following cue Cue: Adequate emergency lighting is in operation to allow the use of normal access/egress paths. STEP Verify Reactor Tripped Locates reactor trip breakers, Critical:

Grade #2 3RPS*SWGR-1

& -2] [West MCC*SWGR, Y[X] S [ ] N[X] U [ ] Check Reactor Trip and Bypass Breakers -Aux Bldg 46'] 3509.1, AU A OPEN step 6.a Comments:

Cue: Locates OPEN I CLOSED position Critical:

Grade indicating flags for each breaker and Y[X] S [ ] N [ ] U [ ] determines TRIP breakers Proceeds to RNO ---'----..... -----..........5 I t:.valuator Show the picture of the inside of the reactor trip and bypass breaker cabinets so the candidate can NOTE: determine that the reactor trip breaker flags indicate CLOSED and the bypass breakers indicate OPEN. Cue (if You see the reactor trip breaker CLOSED flags and the bypass breaker OPEN flags. required):

STEP TRIP the reactor trip and bypass breakers.

Locates red TRIP push button (PB) and Critical:

Grade #3 simulates pushing TRIP PB. [RNO VeX] S [ J direction]. N [ ] U [ J AttA step 6.a RNO Locates breaker flag indication; both trip Critical:

Grade breakers are Y [ ] S [ ] N[X] U [ ] Evaluator Show the picture of the inside of the reactor trip breaker cabinet so the candidate can determine that the NOTE: Breaker TRIP/OPEN flag is visible. The RNO must be performed.

Cue (if You see the reactor trip breaker TRIP/OPEN flag. required):

STEP Block Open Auxiliary Building North Locates North doors A-24-2 [inner] &A-Critical:

Grade #4 Doors to Outside on EI. 24'*6" 24-1 [outer] and simulates propping Y[X] S [ ] N [ ] U [ ]

BOTH doors open -applicant explains Att A Door method and component(s) used to step Door A-24-2 achieve blocking Cue: You have material to block the doors open. Comments:

As each door is simulated blocked open, provide the following cue: ------..........

-.--..........

...........6

---

Cue: The door is blocked open. STEP NOTE: Opening the breaker for Reviews the note prior to step #5 3MSS*MOV 17 A at 32-4U-R5H is not Appendix "R" required action. If there is AttA lighting available to access this area Step 8 NOTE action is not required.

Comments:

If examinee questions the status of lighting, provide the following cue: Cue: Adequate emergency lighting is in operation to allow access in this area. Comments:

The following breakers may be operated in any order. STEP De-energize TO AFW Pump Steam Locates breaker R5H on MCC 32-4U #6 Supply Isolation Valves (ESF Bldg 36') and simulates placing the breaker in the OFF position AttA

• For 3MSS*MOV17 A, Place breaker [3MSS*MOV17 A]. step 8 32-4U-R5H to OFF For 3MSS*MOV17B, Place 32-4T-R6E to For 3MSS*MOV17D, Place 32-4T -R6H to STEP Locates breaker R6E on MCC (ESF Bldg 36') and simulates placing the breaker the OFF position [3MSS*MOV17B]

7 Critical: Y [ ] N[X] Y ( N[X] Critical:

Y[X1 N [ ] Grade S [ U [ Grade S [ U [ Grade S [ U [ ! i

---

STEP Locates breaker R6H on MCC 32-4T Critical:

Grade #8 (ESF Bldg 36') and simulates placing the Y[X] S [ ] breaker in the OFF position N [ ] U [ ] [3MSS*MOV17DJ Comments:

As each breaker is located, provide the following cue: Cue: Breaker as-found is ON/CLOSED.

Comments:

As each breaker is simulated operated, provide the following cue: Cue: Breaker is in the OFF position, STEP Block Open TO AFW Pump Cubicle Simulates blocking open the TO AFW Critical:

Grade #9 Att A step 9 Doors Door SF-24-1 Door SF-24-2 pump area outside door and the door to MOV17 A, B &0 -student explains method and component{s) used to achieve blocking OPEN. Y[X] N [ ] S [ ] U [ ] Cue: You have material to block the doors open. ...... Comments:

As each door is simulated blocked open, provide the following cue: Cue: The door is blocked OPEN. Comments:

Location for steps 10 -12 is ESF Bldg. TO AFW pump valve room 24'. The position of the 3MSS*MOV17 valves may be checked in any order. 8 STEP Verify TO AFW Pump Steam Isolation Critical:

Grade Locates valve 3MSS*MOV17 A and #10 Valves -OPEN Y [ ] S ( ] checks the position indicator (rod). N[X] U [ ] Att A 3MSS*MOV17A OR step 10 3MSS*MOV17B Manually checks valve position by 3MSS*MOV170 engaging the manual handwheel.

, Checks SG A TO AFW Pump Valve 3MSS*MOV17A Comments: Cue: Stem position rod is as you see it. (---THIS STEP IS COMPLETE**-)

OR Cue: The MOV clutch is disengaged.

,Rotates the handwheel in the clockwise Critical:

Grade direction to confirm the valve is open. Y ( ] S [ ] N[X] U [ ] Comments:

Cue: Valve handwheel rotates in the clockwise direction.

Rotates the handwheel in the Critical:

Grade counterclockwise direction until the valve Y [ ] S [ ] N[X] U [ ] is fully open. Comments:

Cue: Valve handwheel rotates briefly in the counterclockwise direction, resistance is met and the valve comes to a hard stop.

STEP #11 Checks SG 8 TO AFW Pump Non-Return Valve 3MSS*MOV178 OPEN. Locates valve 3MSS*MOV17B and checks the position indicator (rod). Critical: Y [ ] N[X] Grade S [ ] U [ J OR Manually checks valve position by engaging the manual handwheel.

Comments:

Cue: Stem position rod is as you see it. (---THIS STEP IS COMPLETE---)

OR Cue: The MOV clutch is disengaged.

I Rotates the handwheel in the clockwise Critical:

Grade direction to confirm the valve is open. Y [ ] S [ J N[X1 U [ 1 Comments:

Cue: Valve handwheel rotates in the clockwise direction.

I Rotates the handwheel in the Critical:

Grade counterclockwise direction until the valve Y [ ] S [ ] is fully open. N[X] U[] , Comments:

Cue: Valve handwheel rotates briefly in the counterclockwise direction, resistance is met and the valve comes to I a hard stop. STEP Critical:

Grade *Locates valve 3MSS*MOV170 and #12 Checks SG 0 TO AFW Pump Non-Return Y [ ] S [ ] checks the position indicator (rod). N[X] U [ ] Valve 3MSS*MOV170 OPEN. OR Manually checks valve position by engaging the manual handwheel.

Comments:

10

---

Cue: Stem position rod is as you see it. ---THIS STEP IS OR Cue: The MOV clutch is disengaged.

Rotates the handwheel in the clockwise Critical:

Grade direction to confirm the valve is open. Y [ ] S [ ] N[X] U [ ] Comments:

Cue: Valve handwheel rotates in the clockwise direction.

Rotates the handwheel in the Critical:

Grade counterclockwise direction until the valve Y [ ] S [ ] is fullyopen.

N[X] U [ ] Comments:

Cue: Valve handwheel rotates briefly in the counterclockwise direction, resistance is met and the valve comes to a hard stop. I STEP Perform the Following:

Candidate locates phone, sound-powered Critical:

Grade #13 phone or walkie-talkie and simulates Y [ ] S [ ] N[X] U [ ] Establish communication with the ASP establishing communication with ASP Att A operator operator.step 11 Report Attachment A complete Provide support as required Simulates communicating Attachment A Critical:

Grade steps 6 through 11 are complete. Y [ ] S [ ] N[X] U [ ] 11

"'0 CD "'0 :::l U c: 8 <"l ".....; CL """) ..r:::.-.e c: 0 ctl :::l ctl >CD CD ..r:::. (.) OJ C ; ro c E eI) W 2:::J CL 0 (f)

---VERIFICATION OF JPM COMPLETION JPM Number: 2K11 NRC P.2 Date To achieve a satisfactory grade, ALL critical steps must be completed correctly.

If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade. Time Critical Task? Yes No X Validated Time (minutes):

20 Actual Time to Complete (minutes):

Overall Result of JPM: SAT UNSAT Areas for Improvement I Comments:

1 STUDENT JPM Number: Initial Conditions:

Initiating Cues: 2K11 NRC P.2 Revision:

A fire event has occurred requiring shut down outside the control room. The control room team is carrying out actions of EOP 3509.1, Control Room, Cable Spreading Area, or Instrument Rack Room Fire. The US directs you to perform primary side PEO actions on a control room evacuation lAW EOP 3509.1, Attachment A, steps 6 through 11 only, after referring to the "Appendix "R" Lighting Illuminated Path" maps at the end of the attachment.

Another operator is performing steps 1 through 5. You have the locked valve key.

JOB PERFORMANCE MEASURE APPROVAL SHEET JPM Title: Spent Fuel Pool Emergency Make Up JPM Number: 2K11 NRC P.3 ( JPM-016) Revision:

Initiated:

j)Pq--S; Dave Minnich 03/01/11 Developer Date Reviewed:

sJ;/\1 Technical Revi er Approved: Supervisor, Nuclear Training *zr 8 I

SUMMARY

OF DATE DESCRIPTION REV/CHANGE 03/01/11 Verified updated to Rev 008-02 of EOP 3505A. Modified the 8/0 standard for 'Align discharge of gooseneck into the spent fuel pool', to have the examinee describe the method used. Made the first two standards of "IPM step 15 (3SWP*V30 locking device removal and wingnut loosened) non-critical.

Modified JPM format to be consistent with the NRC 2K11 JPM set. ; Deleted TR-M-41 0 Pass/Fail criteria.

DLM

---r JPM WORKSHEET Facility:

_M_P_3____ Examinee:

JPM 2K11 NRC P.3 Revision:

8 Task Title: Spent Fuel Pool Emergency Make Up System: 8 -033 Time Critical Task: ) YES (X) NO Validated Time (minutes):

___1_5__ Task Number(s):

344-05-042 Applicable To: SRO X RO X PEO X KIA Number: 033.A2.03 KIA Rating: ___3_.1_1_3_._5

__ Method of Testing: Simulated X Actual Performance:

Performance:

Location:

Classroom:

In-Plant:

Task Satisfactorily complete emergency make up to the spent fuel pool using EOP 3505A. All critical steps are performed satisfactorily.

All sequential steps are performed in proper procedural sequence.

Required Materials:

PEO Rounds Key (procedures, equipment, EOP 3505A, Rev. 008-02 General

References:

EOP 3505A, Loss of Spent Fuel Pool Cooling, Rev. X r *** READ TO THE EXAMINEE *** I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When complete the task successfully, the objective for this JPM will be satisfied.

You may use any reference material normally available in the Control Room, including logs. Make all written reports, reports, alarm acknowledgements, and log entries as if the evolution was actually being JPM WORKSHEET JPM Number: 2K11 NRC Revision:

8 Initial A loss of all AC power occurred and the control room team carrying out actions of EOP 35 The spent fuel pool low level alarm has been received and, due to a loss of all AC power, the normal method of make-up is not available.

Additionally, 3SFC-V31, RWST to fuel pool isolation valve, is stuck closed. Initiating While maintenance works on 3SFC-V31, the US directs you make up to the spent fuel pool using the emergency method EOP 3505A starting with Attachment A, Step The OMOC has granted permission to perform this step. Simulator NONE 1< 1<

• 1< NOTES TO TASK PERFORMANCE EVALUATOR 1< 1< 1< 1< Critical steps for this JPM are indicated by checking "Y". For the student to achieve satisfactory grade, ALL critical steps must be completed When the student states what his/her simulated action/observation would be, read appropriate If necessary, question student for details of simulated actions/observations (Le. 'What you looking at?" or "What are you Under NO circumstances must the student be allowed to manipulate any devices during performance of this JPM (in-plant PERFORMANCE INFORMATION JPM Number: 2K11 NRC P.3 Revision:

8 Task Title: Spent Fuel Pool Emergency Make Up START TIME: PERFORMANCE STANDARD If at any time during this JPM, the candidate checks fuel pool level indication or requests level information from the Control Room, provide the following cue: Cue: Spent Fuel Pool level is 34%. STEP Locally Establish Emergency Makeup To Candidate recognizes form the initial cue Critical:

Grade #1 3505A, Att A The Spent Fuel Pool From The Fire Protection Water System that the OMOC granted permission to perform this step. Y [ ] N[X] S [ ] U [ ] step g.a Check OMOC --AUTHORIZES USE OF F!RE VVATER If the Candidate questions OMOC authorization, provide the following cue: Cue: The OMOC authorizes use of fire water. STEP Check radiation levels at spent fuel pool -Candidate requests HP coverage to Critical:

Grade #2 ACCEPTABLE check radiation levels at the spent fuel Y [ ] S [ ] N[X] U [ ] pool to determine if they are acceptable.

Att A step 9.b Comments:

When examinee requests HP coverage to check radiation levels, provide the following cue: Cue: HP conducts a survey and determines the fuel pool area is accessible, highest readings are 6 mr/hr. 5 Locates emergency supply connection Critical:

Grade In the spent fuel pool area Perform the #3 vent (EL 51 '6") and simulates rotating Y [ ] S [ ] following:

N[X] U [ ] valve handwheel in counter clockwise Att A direction until valve is open. step Vent the fire protection water connection using the fuel emergency supply connection 3FPW-V1355 handwheel rotates in the counter clockwise direction until resistance is felt and handwheel no . longer rotates, valve is open. There is no flow out of the vent. f Closes vent when completed venting. Critical:

Grade Y [ ] S [ ] N[X] U [ ] Valve hand wheel rotated in the clockwise direction until hard stop. Comments:

The procedure step only states to vent the connection.

STEP Connect emergency makeup gooseneck Locates emergency make up gooseneck Critical:

Grade #4 to the fire protection water system (EL 51 '6") and simulates connecting Y [ ] S [ ] N[X] U [ ] connection gooseneck to fire protection AttA step 9.c.2) Comments:

Cue: Emergency make up gooseneck is connected to the fire protection water system. -------_........ _._-_.... _.. _-------------.....-.. ........

.........

STEP Align discharge of gooseneck into the Candidate should describe how he/she Critical:

Grade #5 spent fuel pool would align the gooseneck to ensure its Y [ ] S [ ] discharge is to the spent fuel pool. N[X] U [ ] step Comments: Emergency make up gooseneck is aligned to discharge into the spent fuel pool. STEP OPEN fire protection water system supply Locates supply valve 3FPW-V766 (Fuel Critical:

Grade #6 to fuel pool (3FPW-V766) located in Fuel Bldg. EI. 51 '6" by the Fuel Pool). Y [ ] S [ ] Building 51' Simulates rotating the handwheel for N[X] U [ ] AttA 3FPW-V766 in the counter-clockwise step direction until the valve is Valve hand wheel rotates in counter-clockwise direction

-Eventually, some resistance is met and the valve comes to a stop. , Simulates rotating valve hand wheel 14 Critical:

Grade turn in the clockwise direction. Y [ ] S [ ] N[X] U [ ] Cue: The valve hand wheel is rotated 14 turn in the clockwise direction. STEP Check spent fuel pool level --Checks for water flow out of gooseneck Critical:

Grade #7 INCREASING into fuel pool. Y [ ] S [ ] N[X] U [ ] step No flow is visible from the gooseneck.

Transitions to R.N.O. Critical:

Grade Y [ ] S [ ] N[X] U [ ] 7

---

STEP #8 AttA step 9.e RNO Perform the following:

Direct fire water into the spent fuel pool from the following sources as necessary utilizing the connected hose and if necessary connect a hose to the fire department connections: Critical:

Grade Y [ ] S [ ] N[X] U [ ] Hose rack #69 Hose rack #94 Site fire pumper Comments:

When the Candidate initiates action to rig another fire water source, provide the following cue: Cue: The Control Room informs you that the fire water system is not pressurized, and other personnel have been dispatched to the fire pumper. The Control Room has obtained OMOC permission to establish make up to the fuel pool from the service water system and you are to close 3FPW-V766 and proceed to Step 10. STEP #9 Comments:

Close 3FPW-V766 Simulates rotating hand wheel in the clockwise direction and locking valve. Critical: Y [ ] N[X] I Grade S [ J U [ ] Cue: Valve hand wheel rotates in clockwise direction

-Eventually, some resistance is met and valve hand wheel comes to a hard stop. Candidate proceeds to STEP 10 in Attachment A. Critical: Y [ ] N[X] Grade S [ ] U [ ]

---

STEP #10 AU A step 10.a Comments:

Cue: STEP #11 AU step Cue: STEP #12 step 1 O.c.1 Locally Establish Emergency Make Up to Spent Fuel Pool from the Service Water System Check the following:

• OMOC -AUTHORIZES USE OF SERVICE WATER Service water pump A or C RUNNING Candidate recognizes that the Control Critical:

Grade Room has obtained OMOC permission to Y [ ] S [ ] N[X] U [ ] use the service water system, based on a previous cue. Calls Control Room to verify either Critical:

Grade service water pump A or C is running. Y [ ] S [ ] N[X] U [ ] When the Candidate simulates calling the Control Room, provide the following cue: The Unit Supervisor informs you that the SBO Diesel has been started and placed on bus 34C. The "Au service water pump is running. Check service water supply to fuel pool Locates 3SWP*V30 (Fuel Bldg EI 24', fuel Critical:

Grade (3SWP*V30) located in Fuel BuHding 24' -receiving bay) and checks valve closed Y [ ] S [ ] N[X] U [ ] by observing handle is not in the in-line Qosition.

When the Candidate checks the position of 3SWP*V30, provide the following cue: Valve handle is perpendicular to the pipe. In the spent fuel pool area Perform the Locates the service water fuel pool blank Criticql:

Grade following: flange vent (EL 51 '6") and simulates Y[X] S [ ] N [ ] U [ ] rotating valve handwheel in Vent the service water system clockwise direction until valve is connection using the fuel pool flange vent (3SWP*V741 9 i I Comments: 3SWP*V741 handwheel rotates in the counter clockwise direction until resistance is felt and handwheel no longer rotates, valve is open. There is no flow out of the vent. Closes vent when completed venting. ---Critical:

Grade Y [ S [ ] N[X] U [ ] Cue: Valve hand wheel rotated in the clockwise direction until hard stop. I Comments:

To complete the next step, the Candidate needs some tools. It is not necessary that these tools be obtained, however have the candidate explain where he/she obtains the tools. , I STEP Remove blank flanges (2) and Install Locates spool piece, simulates unbolting Critical:

Grade #13 spool piece in service water line to spent flanges and bolting spool piece into the VEX] S [ ] N [ ] U [ ] fuel pool service water line (Fuel Bldg EI 43' AttA filter demin step 10.c.2) Comments: Spool piece is bolted in place. STEP Open service water supply to fuel pool Locates 3SWP*V700 (Aux Bldg EI 4'6") Critical:

Grade #14 isolation (3SWP*V700) located in Aux and simulates turning valve handle to a Y[X] S [ ] N [ ] U [ ] Building position in line with pipe. step Comments:

Valve handle rotates to a position in line with the SWP pipe. For this JPM it is not necessary to obtain ladder; However, the candidate should tell you the location of the nearest ladder when asked. 10 lIlli!, ___--, -STEP Open service water supply to fuel pool Simulates unlocking and removing Critical:

Grade * #15 (3SWP*V30) locking device on valve 3SWP*V30. Y [ ] S [ ] N[X] U [ ] AltA step Cue: Locking device is unlocked and I Simulates loosening wingnut locking Critical:

Grade

• device on valve 3SWP*V30. Y [ ] S []N[X] U [ ] I Cue: Wingnut is loosened (if wingnut is not loosened, inform operator that valve will not move when attempt is

• made to open valve.) Simulates positioning valve handle to the Critical:

Grade in-line position to open the valve. Y[X} S [ ] N [ ] U [ ] Cue: Valve handle is aligned to the in-line position.

Water flow is heard as the valve is opened. STEP Check spent fuel pool level --Verifies spent fuel pool level increasing Critical:

Grade #16 INCREASING by either local (3SFC-Ll26 at the fuel pool Y [ ] S [ ] N[X] U [ ] cooling panel) indication or by requesting Att A information from control room (computer step point Comments:

Candidate may either go to the local spent fuel pool cooling panel or call the control room to obtain level information.

In either case, provide the following cue: Cue: Spent fuel pool level is 34% and slowly increasing.

'.' STEP Notify the control room that emergency Candidate reports to US that he/she has Critical:

Grade #17 make up to the spent fuel pool is initiated, initiated emergency make up from the Y [ ] S [ J controlling level between 36% and service water system to the spent fuel N[X] U [ ] pool in accordance with EOP 3505A, Attachment A. 11

--8 VERIFICATION OF JPM COMPLETION JPM Number: 2K11 NRC P.3 Revision:

Date Performed:

Student: Evaluator:

To achieve a satisfactory grade, ALL critical steps must be completed correctly.

If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade. Time Critical Task? Yes No X Validated Time (minutes):

15 Actual Time to Complete (minutes):

Overall Result of JPM: SAT UNSAT Areas for Improvement I Comments:

l3 8 JPM Number: Initial Conditions:

Initiating Cues: STUDENT HANDOUT 2K11 NRC P.3 Revision:

A loss of all AC power occurred and the control room team is carrying out actions of EOP 35 ECA-O.O. The spent fuel pool low level alarm has been received and, due to a loss of all AC power, the normal method of make-up is not available.

Additionally, 3SFC-V31, RWST to fuel pool isolation valve, is stuck closed. While maintenance works on 3SFC-V31, the US directs you to make up to the spent fuel pool using the emergency method of EOP 3505A starting with Attachment A, Step 9. The OMOC has granted permission to perform this step.