ML14225A202

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(Quad Cities) Systems JPM E
ML14225A202
Person / Time
Site: Quad Cities  Constellation icon.png
Issue date: 03/31/2013
From:
NRC/RGN-III
To:
Exelon Generation Co, Exelon Nuclear
Bruce Palagi
Shared Package
ML13093A398 List:
References
Download: ML14225A202 (15)
v • d • e


Text

Page 1 of 15 SRRS: 3D.105 (when utilized for operator initial or continuing training)

Exelon Nuclear Job Performance Measure Place Shutdown Cooling In Operation with RHR system leak JPM Number: 2014 ILT NRC JPM e Revision Number: 00 Date: 10 / 14 / 2013 Developed By:

Instructor Date Validated By:

SME or Instructor Date Reviewed By:

Operations Representative Date Approved By:

Training Department Date

2014 ILT NRC JPM e - rev 00 Page 2 of 15 SRRS: 3D.105 (when utilized for operator initial or continuing training)

JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation.

Prior to JPM usage, revalidate JPM using steps 9 and 13 below.

1.

Task description and number, JPM description and number are identified.

2.

Knowledge and Abilities (K/A) references are included.

3.

Performance location specified. (in-plant, control room, simulator, or other)

4.

Initial setup conditions are identified.

5.

Initiating cue (and terminating cue if required) are properly identified.

6.

Task standards identified and verified by SME review.

7.

Critical steps meet the criteria for critical steps and are identified with an asterisk (*).

8.

If an alternate path is used, the task standard contains criteria for successful completion.

9.

Verify the procedure(s) referenced by this JPM reflects the current revision:

Procedure QCOP 1000-05 Rev: 49 Procedure Rev:

Procedure Rev:

10. Verify cues both verbal and visual are free of conflict.
11. Verify performance time is accurate
12. If the JPM cannot be performed as written with proper responses, then revise the JPM.
13. When JPM is initially validated, sign and date JPM cover page. Subsequent validations, sign and date below:

SME / Instructor Date SME / Instructor Date SME / Instructor Date

2014 ILT NRC JPM e - rev 00 Page 3 of 15 SRRS: 3D.105 (when utilized for operator initial or continuing training)

Revision Record (Summary)

Revision 00, Created for the ILT 12-1 NRC exam. The setup creates a flowpath from the 1A RHR pump to the torus [masked by overrides], initiated at RHR pump start. In addition, a torus leak is initiated to mask the torus level rise and give indications that the RHR piping is leaking into the Reactor Building basement.

2014 ILT NRC JPM e - rev 00 Page 4 of 15 SRRS: 3D.105 (when utilized for operator initial or continuing training)

SIMULATOR SETUP INSTRUCTIONS

1. Reset the simulator to IC 6 (ready for shutdown cooling)

NOTE:

It is okay to use a similar IC to the IC listed above, provided the IC actually used is verified to be compatible with this and other JPMs that are scheduled to be run concurrently.

2. Place the 1A RHRSW pump online to the 1A RHR heat exchanger
3. Run the following commands (contained in caep file E caep.cae)

Fail group 2 to work (4 commands)l00:00:00l01 imf rp08Al00:00:02l02 imf rp08Bl00:00:04l03 imf rp08Cl00:00:06l04 imf rp08Dl00:00:08l05 Rack out 1-1001-34A breakerl00:00:00l06 irf rh23ar openl00:00:10l07 override lights for 1-1001-34Al00:00:00l08 ior lohs1100134A1 onl00:00:12l09 Rack out 1-1001-36A breakerl00:00:00l10 irf rh24ar openl00:00:14l11 override lights for 1-1001-36Al00:00:00l12 ior lohs1100136A1 onl00:00:16l13 open the 1-1001-36Al00:00:00l14 irf rh34ar 100l00:00:18l15 override the A RHR containment flow to zerol00:00:00l16 ior aofi1104011a 0l00:00:20l17 set trigger 1 true when RHR pump A is taken to normal-after-startl00:00:00l18 trgset 1 "zdihs110021A(4)"l00:00:22l19 open 1-1001-34A 10% when trigger 1 is truel00:00:00l20 trg 1 "irf rh33ar 10"l00:00:24l21 cause a torus leak when trigger 1 is truel00:00:00l22 imf pc07 (1) 1.6l00:00:26l23 set trigger 2 true when RHR pump A is taken to trip or PTL or tripped lightl00:00:00l24 trgset 2 "zdihs110021A(1).or. zdihs110021A(2).or. zlohs110021a(2)"l00:00:28l25 delete the torus leak on trigger 2l00:00:00l26

2014 ILT NRC JPM e - rev 00 Page 5 of 15 SRRS: 3D.105 (when utilized for operator initial or continuing training) trg 2 "dmf pc07"l00:00:30l27 Override the Torus low level alarm (annunciator 901-3 A-14) offl00:00:00l28 imf ser0202 offl00:00:32l29 Increase 1-1001-34A open amount by 2% if neededl00:00:00l30 irf rh33ar 12l10:00:00l31 Rack out 1-1001-18A when directedl00:00:00l32 irf rh17ar openl10:00:00l33 When the above steps are completed for this and other JPMs to be run concurrently then validate, if not previously validated, the concurrently run JPMs using the JPM Validation Checklist.

4. This completes the setup for this JPM.

JPM E QCOP 1000-05, Rev 049, SH E caep.cae

2014 ILT NRC JPM e - rev 00 Page 6 of 15 SRRS: 3D.105 (when utilized for operator initial or continuing training)

INITIAL CONDITIONS

  • Reactor water temperature has been steady for the last hour.
  • One RHRSW pump is running on loop A.
  • RHR Loop A is in a standby lineup per QCOP 1000-02.
  • EOs are standing by in the Reactor Building.
  • Pre-start checks are complete the 1A RHR pump.
  • A slow cooldown is NOT required.

INITIATING CUE Start Shutdown cooling on Unit 1 using the 1A RHR pump.

Provide student with QCOP 1000-05 Fill in the JPM Start Time when the student acknowledges the Initiating Cue.

Information For Evaluators Use:

Prepare a copy of QCOP 1000-05 completed through step F.1.b UNSAT requires written comments on respective step.

  • Denotes critical steps.
  • Brackets the critical portion of the critical steps Number any comments in the Comment Number column on the following pages. Then annotate that comment in the Comments section. The comment section should be used to document: the reason that a step is marked as unsatisfactory, marginal performance relating to management expectations, or problems the examinee had while performing the JPM.

Comments relating to procedural or equipment issues should be entered and tracked using the sites appropriate tracking system.

Some operations that are performed from outside of the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed.

The timeclock starts when the candidate acknowledges the initiating cue.

2014 ILT NRC JPM e - rev 00 Page 7 of 15 SRRS: 3D.105 (when utilized for operator initial or continuing training)

JPM Start Time:

STEP ELEMENT STANDARD SAT UNSAT Comment Number

Places keylock switch for the 1-1001-19A to close and waits for green light to be lit and red light extinguished.

NOTE:

The student should evaluate step F.1.d as Not Applicable

  • F.1.e

.(1)

  • Places control switch for 1-1001-18A to close and releases. Waits for green light to be lit and red light extinguished.

F.1.e.

(1).(a)

Verify closed MO 1-1001-18A.

Requests another NSO to verify 1-1001-18A RHR LOOP MIN FLOW VLV is shut CUE As another NSO, agree with the candidate regardless of valve indication.

  • F.1.e

.(2)

Directs EO to open the breaker for the 1-1001-18A RHR LOOP MIN FLOW VLV at MCC 18-1A-1 NOTE:

Direct the Sim Op to open the breaker for the MO 1-1001-18A using caep file command irf rh17ar open. Verify the MO 1-1001-18A lights are extinguished prior to giving the cue.

CUE As EO, report that the MO 1-1001-18A RHR LOOP MIN FLOW VLV breaker at MCC 18-1A-1 is open.

CUE If the candidate directs closing 1-1001-141A & 141B per steps F.1.e.(3), report that the handwheel is spinning freely on the 1-1001-141A and you are unable to close it.

[This is to prompt the student to close the MO 1-1001-18A. The simulator does not have the 1-1001-141A & 141B modeled.]

  • F.1.f
  • Close MO 1-1001-7A, A RHR PMP TORUS SUCT VLV.
  • Places keylock switch for 1-1001-7A to close and waits for green light to be lit and red light extinguished.

2014 ILT NRC JPM e - rev 00 Page 8 of 15 SRRS: 3D.105 (when utilized for operator initial or continuing training)

STEP ELEMENT STANDARD SAT UNSAT Comment Number

  • F.1.g *Close MO 1-1001-7B, B RHR PMP TORUS SUCT VLV.
  • Places keylock switch for 1-1001-7B to close and waits for green light to be lit and red light extinguished.
  • F.1.h *Open MO 1-1001-43A, RHR PUMP SDC SUCT VLV.*

Places keylock switch for 1-1001-43A to open and waits for red light to be lit and green light extinguished.

  • F.1.i.

(1)

  • Reset Group 2 isolation: ISOL VLV RESET switch at Panel 901-5.*

Places ISOL VLV RESET to INBD momentarily, then to OTBD momentarily then releases.

  • F.1.i.

(2)

  • Reset Group 2 isolation:

RESET FOR GRP 2 ISOL VLV 1-1001-29 pushbutton at Panel 901(2)-3.*

  • Pushes RESET FOR GRP 2 ISOL VLV 1-1001-29 pushbutton for A loop*

Pushes RESET FOR GRP 2 ISOL VLV 1-1001-29 pushbutton for B loop

  • F.1.j
  • Open MO 1-1001-47, SDC HDR DOWNSTREAM SV.
  • Places control switch for 1-1001-47 to open and releases.

Waits for red light lit and green light extinguished.

  • F.1.k *Open MO 1-1001-50, SDC HDR UPSTREAM SV.
  • Places control switch for 1-1001-50 to open and releases.

Waits for red light lit and green light extinguished.

F.1.l Verify open MO 1-1001-16A, A RHR HX BYP VLV.

Verifies red light lit and green light extinguished for 1-1001-16A.

F.1.m Close MO 1-1001-28A, A LPCI LOOP UPSTREAM SV.

Places control switch for 1-1001-28A to close and holds until the green light is lit and red light is extinguished.

2014 ILT NRC JPM e - rev 00 Page 9 of 15 SRRS: 3D.105 (when utilized for operator initial or continuing training)

STEP ELEMENT STANDARD SAT UNSAT Comment Number

  • F.1.n *Open MO 1-1001-29A, A LPCI LOOP DOWNSTREAM SV.
  • Places control switch for 1-1001-29A to open and releases.

Waits until the red light is lit and green light is extinguished.

NOTE:

The student should evaluate steps F.1.o and F.1.p as Not Applicable NOTE:

In preparation for starting the 1A RHR pump, the candidate will make a plant announcement. Ensure the student does not use the PA system to prevent interacting with other candidates.

In preparation for starting the 1A RHR pump, makes a plant announcement Makes a plant announcement of the impending start of the 1A RHR pump.

Directs EO to leave the 1A RHR pump area (safety concern)

Directs EO to leave the 1A RHR pump area.

CUE As EO, acknowledge the direction to leave the area.

(1) Throttle open MO 1-1001-28A for approximately 2 seconds.

(2) Start 1A RHR Pump.

  • Places control switch for 1-1001-28A to open for approximately 2 seconds and releases.

Without delay, places control switch for 1A RHR pump to start and releases.

NOTE:

Alternate path starts here. Starting the 1A RHR pump causes an unexplained loss in Reactor Water Level and the candidate may immediately perform step E.2. The remaining steps in F.1 may not be completed.

The Group 2 isolation is faulted, making manual isolation a critical step.

In the following steps, IF asked as EO to investigate water in the Reactor Building area, THEN report that there is a large amount of water coming from somewhere. Do NOT prompt the student as to the source.

NOTE:

If Reactor Water Level is dropping inadequately (perhaps due to other JPMs),

increase the leak size an additional amount by opening the 1-1001-34A from 10% to 12% using irf rh33ar 12. As necessary, throttle the 34A by modifying the percent open (12 in the command above).

2014 ILT NRC JPM e - rev 00 Page 10 of 15 SRRS: 3D.105 (when utilized for operator initial or continuing training)

STEP ELEMENT STANDARD SAT UNSAT Comment Number F.1.r Throttle open MO 1-1001-28A and maintain > 2500 gpm flow.

Throttles 1-1001-28A open as necessary to achieve >2500 gpm flow

2014 ILT NRC JPM e - rev 00 Page 11 of 15 SRRS: 3D.105 (when utilized for operator initial or continuing training)

STEP ELEMENT STANDARD SAT UNSAT Comment Number F.1.s Monitor Reactor water temperature and maintain cooldown rate < 100°F per hour while maintaining > 2500 gpm flow:

(1) To increase cooldown rate, perform any of the following:

(a) Throttle closed MO 1-1001-16A.

(b) Throttle open MO 1-1001-28A.

(2) To decrease cooldown rate, perform any of the following:

(a) Throttle open MO 1-1001-16A.

(b) Throttle closed MO 1-1001-28A.

(c) IF cooldown rate is excessive OR Reactor vessel temperature can NOT be maintained, THEN:

Unlock 1-1001-17A.

Throttle 1-1001-17A (approximately 28.5 turns closed initially or as directed by US).

Throttle MO 1-1001-16A MO 1-1001-28A as necessary to maintain Reactor water cooldown rate < 100°F/hour.

Verify Equipment Status Tag placed on MO 1-1001-16A control switch stating 1-1001-17A is throttled.

To throttle the 1-1001-16A, places control switch to desired position and returns to center position. When desired position is reached, pulls out on handle to stop valve movement.

To throttle the 1-1001-28A, places control switch in desired position and holds until desired position is reached and releases.

To throttle the 1-1001-17A, directs the EO to unlock and reposition the 1-1001-17A

2014 ILT NRC JPM e - rev 00 Page 12 of 15 SRRS: 3D.105 (when utilized for operator initial or continuing training)

STEP ELEMENT STANDARD SAT UNSAT Comment Number CUE As EO, if directed to unlock and open the 1-1001-17A, wait two minutes and report the 1-1001-17A is unlocked and throttled (include number of turns closed as directed).

F.1.t Monitor Reactor water level and maintain level > +20 inches.

Identifies that Reactor water level is NOT being maintained and executes step E.2 NOTE:

In the following steps, it is not expected for the student to wait until valve movement completes before moving to the next valve. If the 1A RHR pump is still running, it will trip upon closure of either the -47 or -50 valves in the steps below.

  • E.2 IF an unexplained loss of inventory should occur, THEN:
  • a. Close MO 1-1001-47, SDC SUCT HDR DOWNSTREAM SV, if energized.
  • Places control switch for 1-1001-47 to close and releases.
  • E.2 IF an unexplained loss of inventory should occur, THEN:
  • b. Close MO 1-1001-50, SDC HDR UPSTREAM SV, if energized.
  • Places control switch for 1-1001-50 to close and releases.
  • E.2 IF an unexplained loss of inventory should occur, THEN:
  • Places control switch for 1-1001-29A to close and releases.

Reports to the Unit Supervisor of the unexplained loss of inventory and actions taken to isolate the Reactor Vessel Reports to the Unit Supervisor of the unexplained loss of inventory and actions taken to isolate the Reactor Vessel

2014 ILT NRC JPM e - rev 00 Page 13 of 15 SRRS: 3D.105 (when utilized for operator initial or continuing training)

STEP ELEMENT STANDARD SAT UNSAT Comment Number If Group 2 isolation signal for Reactor Water Level was reached (approximately 6.6),

reports to the Unit Supervisor of the failed Group 2 isolation Reports to the failure of Group 2 to actuate.

CUE As Unit Supervisor, acknowledge the report(s). Inform the candidate you will have the system(s) inspected prior to reinitiating shutdown cooling.

The candidate will inform you the task is complete.

JPM Stop Time:

2014 ILT NRC JPM e - rev 00 Page 14 of 15 SRRS: 3D.105 (when utilized for operator initial or continuing training)

JPM

SUMMARY

Operators Name:

Job

Title:

EO RO SRO FS STA/IA SRO Cert JPM

Title:

Place Shutdown Cooling In Operation with RHR system leak JPM Number: 2014 ILT NRC JPM e Revision Number: 00 Task Number and

Title:

SR-1000-P14 Given a shutdown reactor plant with RHR/SDC in service when an inadvertent drain down to the torus or drywell occurs, isolate RHR/SDC to stop the drain down in accordance with QCOP 1000-05.

K/A Number and Importance: K/A 205000 A2.09 Rating: 3.6/3.8 Ability to (a) predict the impacts of the following on the SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE); and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

Reactor low water level Suggested Testing Environment: Simulator Alternate Path:

Yes No SRO Only:

Yes No Time Critical:

Yes No Reference(s): QCOP 1000-05, SHUTDOWN COOLING OPERATION, Rev 49 Actual Testing Environment:

Simulator Control Room In-Plant Other Testing Method:

Simulate Perform Estimated Time to Complete: 25 minutes Actual Time Used:

minutes EVALUATION

SUMMARY

Were all the Critical Elements performed satisfactorily?

Yes No The operators performance was evaluated against standards contained within this JPM and has been determined to be:

Satisfactory Unsatisfactory Comments:

Evaluators Name:

(Print)

Evaluators Signature:

Date:

[If this page is an odd numbered page, a blank page is automatically generated after this page to keep the student cue sheet separate from this page]

SRRS: 3D.105 (when utilized for operator initial or continuing training)

INITIAL CONDITIONS

  • Reactor water temperature has been steady for the last hour.
  • One RHRSW pump is running on loop A.
  • RHR Loop A is in a standby lineup per QCOP 1000-02.
  • EOs are standing by in the Reactor Building.
  • Pre-start checks are complete the 1A RHR pump.
  • A slow cooldown is NOT required.

INITIATING CUE Start Shutdown cooling on Unit 1 using the 1A RHR pump.

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