Text

Initial Exam 2015-301 Draft Sim In-Plant JPMs
	ML15119A491
Person / Time
Site:	Turkey Point
Issue date:	04/29/2015
From:	; Division of Reactor Safety II
To:	; Florida Power & Light Co
References
	Download: ML15119A491 (415)
	v • d • e

LOIT L-15-1 NRC Exam material controlled by TR-AA-230-1009, Training Examination Security.

Simulator - JPM A LOIT L-15-1 NRC Exam material controlled by TR-AA-230-1009, Training Examination Security.

u ,J Page 2 of 19 NRC l-15-1 EXAM SECURE JPM TITLE: Recover a Dropped Rod JPM NUMBER: L-15-1 NRC JPM A REV. 0-0 TASK NUMBER(S) I 01028010300 I TASK TITLE(S): Perform a Dropped Rod Recovery KIA NUMBERS: 001 A2.11 KIA VALUE: RO 4.4 /SRO 4.7 Justification (FOR KIA VALUES <3.0): N/A TASK APPLICABILITY:

~RO ~SRO D STA D Non-Uc D SRO CERT D OTHER: _ _

APPLICABLE METHOD OF TESTING: Simulate/Walkthrough: D Perform: ~

EVALUATION LOCATION: In-Plant: D Control Room: D Simulator: cu other:

Lab: D Time for Completion: 20 Minutes Time Critical: No Alternate Path [NRC]: Yes Alternate Path [INPO]: Yes Date rainin~Supervision Approved by: ---~----~--L==~---~---l-/_" _______

Training Program Owner Date TR-AA-230-1003-F10, Revision 2 L-15-1 NRC Simulator - JPM A

L-15-1 NRC JPM A, Recover a Dropped Rod, Rev. 0 JPM NRC L-15-1 EXAM SECURE INFORMATION Page 3 of 19 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED PRIOR TO USE.

REVIEW STATEMENTS YES NO N/A

1. Are all items on the signature page filled in correctly?

2. Has the JPM been reviewed and validated by SMEs?

3. Can the required conditions for the JPM be appropriately established in the simulator if required?

4. Do the performance steps accurately reflect trainees actions in accordance with plant procedures?

5. Is the standard for each performance item specific as to what controls, indications and ranges are required to evaluate if the trainee properly performed the step?

6. Has the completion time been established based on validation data or incumbent experience?

7. If the task is time critical, is the time critical portion based upon actual task performance requirements?

8. Is the job level appropriate for the task being evaluated if required?

9. Is the K/A appropriate to the task and to the licensee level if required?

10. Is justification provided for tasks with K/A values less than 3.0?

11. Have the performance steps been identified and classified (Critical /

Sequence / Time Critical) appropriately?

12. Have all special tools and equipment needed to perform the task been identified and made available to the trainee?

13. Are all references identified, current, accurate, and available to the trainee?

14. Have all required cues (as anticipated) been identified for the evaluator to assist task completion?

15. Are all critical steps supported by procedural guidance? (e.g., if licensing, EP or other groups were needed to determine correct actions, then the answer should be NO.)

16. If the JPM is to be administered to an LOIT student, has the required knowledge been taught to the individual prior to administering the JPM?

TPE does not have to be completed, but the JPM evaluation may not be valid if they have not been taught the required knowledge.

All questions/statements must be answered YES or N/A or the JPM is not valid for use. If all questions/statements are answered YES or N/A, then the JPM is considered valid and can be performed as written. The individual(s) performing the initial validation shall sign and date the cover sheet.

Protected Content: (CAPRs, corrective actions, licensing commitments, etc. associated with this material)

{C001}

TR-AA-230-1003-F10, Revision 2 L-15-1 NRC Simulator - JPM A NRC L-15-1 EXAM SECURE INFORMATION

L-15-1 NRC JPM A, Recover a Dropped Rod, Rev. 0 JPM NRC L-15-1 EXAM SECURE INFORMATION Page 4 of 19 UPDATE LOG: Indicate in the following table any minor changes or major revisions (as defined in TR-AA-230-1003) made to the material after initial approval. Or use separate Update Log form TR-AA-230-1003-F16.

PREPARER DATE

DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR#

SUPERVISOR DATE TR-AA-230-1003-F10, Revision 2 L-15-1 NRC Simulator - JPM A NRC L-15-1 EXAM SECURE INFORMATION

L-15-1 NRC JPM A, Recover a Dropped Rod, Rev. 0 JPM NRC L-15-1 EXAM SECURE INFORMATION Page 5 of 19 SIMULATOR SET-UP:

SIMULATOR SETUP INSTRUCTIONS:

_____ 1. Reset to IC 12 or equivalent IC.

_____ 2. Place Simulator in RUN.

_____ 3. Ensure applicable portions of Simulator Operator Checklist are complete.

Open and Execute L-15-1 NRC JPM A.lsn.

1. Verify SETUP - Drop L5 triggers

_____ 4.

2. Verify SETUP - Remove L5 Failure triggers (5sec delay)

3. Trigger Drop M10 and verify in CONDITION state Perform following switch manipulations:

1. Place Rod Motion Control Selector Switch to MANUAL

2. Adjust Turbine load to match Tavg/Tref within 3°F (adjust as necessary

_____ 5.

as plant stabilizes following rod drop)

3. Place N41 Dropped Rod Mode switch to RESET and then back to NORMAL (this should clear B 7/1)

_____ 6. Ensure Key #1 is in locker and put clean copy of Operation Keylog in binder.

_____ 7. Allow the plant to stabilize.

_____ 8. Acknowledge alarms and place Simulator in FREEZE.

_____ 9. Save as a temporary IC if JPM will be repeated.

_____ 10. When ready to begin, then place Simulator in RUN.

SIMULATOR MALFUNCTIONS:

TFLISB31 - Drop Rod L-5.

TFLIC81 - Drop Rod M-10.

SIMULATOR OVERRIDES:

Delete TFLISB31 - Drop Rod L-5.

SIMULATOR REMOTE FUNCTIONS:

N/A TR-AA-230-1003-F10, Revision 2 L-15-1 NRC Simulator - JPM A NRC L-15-1 EXAM SECURE INFORMATION

L-15-1 NRC JPM A, Recover a Dropped Rod, Rev. 0 JPM NRC L-15-1 EXAM SECURE INFORMATION Page 6 of 19 Required Materials:

HANDOUT 3-ONOP-028.3, Dropped RCC

Key #1 to the Rod Disconnect Switch cabinet.

Blank key sign out forms.

General

References:

3-ONOP-028.3, Dropped RCC

3-ARP-097.CR, Annunciator Response Procedures Task Standards:

Attempts to recover dropped rod L-5, per procedure.

Identifies that an additional rod has dropped.

Trips the reactor.

TR-AA-230-1003-F10, Revision 2 L-15-1 NRC Simulator - JPM A NRC L-15-1 EXAM SECURE INFORMATION

L-15-1 NRC JPM A, Recover a Dropped Rod, Rev. 0 JPM NRC L-15-1 EXAM SECURE INFORMATION Page 7 of 19 HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME!

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 job performance measure will be satisfied.

DURING THE JPM, ENSURE PROPER SAFETY PRECAUTIONS, FME, AND/OR RADIOLOGICAL CONCERNS AS APPLICABLE ARE FOLLOWED.

INITIAL CONDITIONS:

Four hours ago while at 75% power, control rod L-5 dropped fully into the reactor.

Load has been reduced to 50% power.

The reason for the dropped rod has been identified and corrected.

3-ONOP-028.3 has been completed up to Step 18.

Rx Engineering Supervisor has approved a withdrawal rate of up to 10 steps/min.

R-20 has been stable the last 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

INITIATING CUES:

In accordance with Step 18 of 3-ONOP-028.3, the Shift Manager directs you to retrieve dropped rod L5.

NOTES:

The presence of a reactivity SRO, Reactor Engineer, and a peer checker are simulated in the Control Room.

Due to dynamic conditions, an instructor will acknowledge non-essential BOP alarms to facilitate the role of the RO (Turbine) and RO (S/G).

NOTE: Ensure the turnover sheet is returned to the evaluator when the JPM is complete.

TR-AA-230-1003-F10, Revision 2 L-15-1 NRC Simulator - JPM A NRC L-15-1 EXAM SECURE INFORMATION

L-15-1 NRC JPM A, Recover a Dropped Rod, Rev. 0 JPM NRC L-15-1 EXAM SECURE INFORMATION Page 8 of 19 JPM PERFORMANCE INFORMATION Start Time:

NOTE: When providing Evaluator Cues to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinees actions warrant receiving the information (i.e., the examinee looks or asks for the indication).

NOTE: Critical steps are marked with a Y below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM.

CAUTION: The Simulator Operator/Instructor acknowledges non-essential BOP alarms to facilitate the role of an Administrative RO.

Performance Step: 18. Continue Rod Recovery Actions Using Attachment 1 Of This Critical N (SEQ-1) Procedure.

Standard:

Obtains 3-ONOP-028.3. Refers to Step 18 to confirm the need to perform Attachment 1.

Proceeds to Attachment 1, Page 1.

Evaluator Note: If a peer check is requested for any of the following steps, then acknowledge the request for the operator to continue performance.

Evaluator Cue:

Provide the operator with a copy of HANDOUT 3-ONOP-028.3, Dropped RCC Performance: SATISFACTORY UNSATISFACTORY Comments:

TR-AA-230-1003-F10, Revision 2 L-15-1 NRC Simulator - JPM A NRC L-15-1 EXAM SECURE INFORMATION

L-15-1 NRC JPM A, Recover a Dropped Rod, Rev. 0 JPM NRC L-15-1 EXAM SECURE INFORMATION Page 9 of 19 Performance Step: 3-ONOP-028.3 Attachment 1 step 1:

Critical N (SEQ-2)

CAUTIONS If the dropped RCC has been dropped and retrieved in the previous 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , then any further retrieval attempts require the permission of the Plant General Manager.

In cases of power operation with a dropped RCC, power peaking may affect fuel integrity if caution is not employed.

If PRMS R-20 shows an unexpected increase due to the dropped RCC, a Reactor Engineering evaluation is required prior to retrieving the dropped rod.

Standard:

The operator reads the CAUTIONS, compares them to initial conditions, and determines that it is satisfactory to proceed.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 3-ONOP-028.3 Attachment 1 step 1:

Critical N (SEQ-3)

Verify Reactor Power Is Stable Standard:

The operator verifies Reactor Power Is Stable.

Per simulator readings.

Cue:

Performance: SATISFACTORY UNSATISFACTORY Comments:

TR-AA-230-1003-F10, Revision 2 L-15-1 NRC Simulator - JPM A NRC L-15-1 EXAM SECURE INFORMATION

L-15-1 NRC JPM A, Recover a Dropped Rod, Rev. 0 JPM NRC L-15-1 EXAM SECURE INFORMATION Page 10 of 19 Performance Step: 3-ONOP-028.3 Attachment 1 step 2:

Critical N (SEQ-4)

NOTE If Initial Reactor Startup or Physics Testing after refueling was in progress, boration to All-Rods-Out, H o t S t a n d b y b o r o n concentration will e n s u r e a d e q u a t e SHUTDOWN MARGIN in xenon-free conditions while the cause of the dropped rod is being determined prior to reactor shutdown.

Standard:

Operator reads note, realizes it does not apply per Initial Conditions.

Cue:

Per Initial Conditions.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 3-ONOP-028.3 Attachment 1 step 2:

Critical N (SEQ-5)

Check Reactor Mode Status

a. Reactor in Mode 2 or 3 (NO)

(RNO) Go to Step 3 Standard:

The operator reads the step, knows the reactor is in Mode 1, and goes to step 3.

Performance: SATISFACTORY UNSATISFACTORY Comments:

TR-AA-230-1003-F10, Revision 2 L-15-1 NRC Simulator - JPM A NRC L-15-1 EXAM SECURE INFORMATION

L-15-1 NRC JPM A, Recover a Dropped Rod, Rev. 0 JPM NRC L-15-1 EXAM SECURE INFORMATION Page 11 of 19 Performance Step: 3-ONOP-028.3 Attachment 1 step 3:

Critical N (SEQ-6)

Check Elapsed Time of Dropped Rod.

a. Time less than 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months .

Standard:

The operator reads the step, time was 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months per initial conditions, and proceeds.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 3-ONOP-028.3 Attachment 1 step 4:

Critical N (SEQ-7)

Cause of Rod Drop Repaired.

Standard:

The operator reads the step, and it was corrected per Initial Conditions.

Performance: SATISFACTORY UNSATISFACTORY Comments:

TR-AA-230-1003-F10, Revision 2 L-15-1 NRC Simulator - JPM A NRC L-15-1 EXAM SECURE INFORMATION

L-15-1 NRC JPM A, Recover a Dropped Rod, Rev. 0 JPM NRC L-15-1 EXAM SECURE INFORMATION Page 12 of 19 Performance Step: 3-ONOP-028.3 Attachment 1 step 5.a:

Critical Y (SEQ-8)

Prepare To Retrieve Dropped RCC.

a. Position the Rod Motion Control Selector switch to the RCC bank with the dropped RCC.

Standard:

Position the Rod Motion Control Selector switch to Shutdown Bank B.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 3-ONOP-028.3 Attachment 1 step 5.b:

Critical Y (SEQ-9)

Place all the lift coil disconnect switches for the dropped rod bank to the disconnect position (toggle switch down) except for the dropped RCC lift coil disconnect switch.

Standard: Places all the lift coil disconnect switches for Shutdown Bank B to the disconnect position (toggle switch down), except for L-5.

Evaluator Note: Key #1 is needed to open panel to lift coil disconnect switches. Key locker is located outside of SM office.

Performance: SATISFACTORY UNSATISFACTORY Comments:

TR-AA-230-1003-F10, Revision 2 L-15-1 NRC Simulator - JPM A NRC L-15-1 EXAM SECURE INFORMATION

L-15-1 NRC JPM A, Recover a Dropped Rod, Rev. 0 JPM NRC L-15-1 EXAM SECURE INFORMATION Page 13 of 19 Performance Step: 3-ONOP-028.3 Attachment 1 step 5.c:

Critical N (SEQ-10)

Ensure the lift coil disconnect switch for the dropped RCC is in the connect position (toggle switch up).

Standard: Candidate ensures the lift coil disconnect switch for the dropped RCC L-5 is in the connect position (toggle switch up).

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 3-ONOP-028.3 Attachment 1 step 5.d:

Critical N (SEQ-11)

Record the step position for the dropped RCC group demand step counter in the Unit Narrative Log as follows:

Bank __________________

Group _________________

Position ________________ steps Standard: Record step position L5.

Bank SBB .

Group GR1 .

Position 229 steps Cue: If candidate proceeds to make log entry, state another operator will make the log entry.

Performance: SATISFACTORY UNSATISFACTORY Comments:

TR-AA-230-1003-F10, Revision 2 L-15-1 NRC Simulator - JPM A NRC L-15-1 EXAM SECURE INFORMATION

L-15-1 NRC JPM A, Recover a Dropped Rod, Rev. 0 JPM NRC L-15-1 EXAM SECURE INFORMATION Page 14 of 19 Performance Step: 3-ONOP-028.3 Attachment 1 step 5.e:

Critical Y (SEQ-12)

Manually set the associated group demand step counter to zero.

Standard: Set SBB Group 1 step counters to 0 (zero).

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 3-ONOP-028.3 Attachment 1 step 6:

Critical N (SEQ-13)

NOTE

Annunciators B 8/1, ROD BANK A/B/C/D LO-LIMIT, and B 8/2, ROD BANK EXTRA LO-LIMIT, will alarm when the RPI bank demand alignment on the DCS screen is reset below the Low and Extra Low Rod Insertion Limits.

Standard: Candidate reads the note. It does not apply for Shutdown Bank B.

Performance: SATISFACTORY UNSATISFACTORY Comments:

TR-AA-230-1003-F10, Revision 2 L-15-1 NRC Simulator - JPM A NRC L-15-1 EXAM SECURE INFORMATION

L-15-1 NRC JPM A, Recover a Dropped Rod, Rev. 0 JPM NRC L-15-1 EXAM SECURE INFORMATION Page 15 of 19 Performance Step: 3-ONOP-028.3 Attachment 1 step 6:

Critical N (SEQ-14)

Check If Dropped Rod is in a Shutdown Bank Standard: Candidate identifies Shutdown Bank B Rod L-5.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 3-ONOP-028.3 Attachment 1 step 7:

Critical N (SEQ-15)

CAUTIONS

If a dropped RCC is retrieved within 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months of dropping, it may be withdrawn at a rate not to exceed 10 steps per minute.

If a dropped RCC is retrieved after 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months of dropping, it should be withdrawn at a rate not to exceed 3 steps per hour.

The actual withdrawal rate shall be approved by the Reactor Engineering Supervisor or designee prior to commencing, and may be modified from the above if conditions warranted (i.e., PRMS R-20 Alarm, Unit in Mode 3 etc.).

If the unit experiences a transient which requires rod motion during the dropped rod retrieval, all lift coil disconnect switches are required to be placed in the connect position (toggle switch up), rod control alarm reset PB depressed, and the rod control selector switch placed in MANUAL prior to rod motion.

Standard: Candidate reviews the Cautions. All information needed is provided by the Initial Conditions and the simulator.

Performance: SATISFACTORY UNSATISFACTORY Comments:

TR-AA-230-1003-F10, Revision 2 L-15-1 NRC Simulator - JPM A NRC L-15-1 EXAM SECURE INFORMATION

L-15-1 NRC JPM A, Recover a Dropped Rod, Rev. 0 JPM NRC L-15-1 EXAM SECURE INFORMATION Page 16 of 19 Performance Step: 3-ONOP-028.3 Attachment 1 step 7:

Critical N (SEQ-16)

NOTES

Boration at 10 gpm is equivalent to 1 ppm/min (10 pcm/min) negative reactivity insertion.

Annunciator B 9/4, ROD CONTROL URGENT FAILURE, and the RCC Power Cabinet URGENT FAILURE will alarm for the group with the lift coils disconnected.

Boration of the RCS may be required to maintain Tavg equal to Tref.

Standard: Candidate reads Note.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 3-ONOP-028.3 Attachment 1 step 7:

Critical Y (SEQ-17)

Withdraw The Dropped RCC

a. Withdraw the dropped rod at the rate determined by the Reactor Engineering Supervisor.

b. Borate as necessary to maintain Tavg within 3°F of Tref.

c. Adjust turbine load as necessary to maintain required power level determined in procedure Step 8.

d. Continue to withdraw the RCC until it is aligned with its group.

Standard: Place IN-HOLD-OUT switch to OUT to withdraw L5.

Booth Operator Cue: When Rod L-5 exceeds 2 steps, verify trigger DROP M10 triggers Performance: SATISFACTORY UNSATISFACTORY No adjustments to Boron or Generator should be necessary during rod Comments: withdrawal.

TR-AA-230-1003-F10, Revision 2 L-15-1 NRC Simulator - JPM A NRC L-15-1 EXAM SECURE INFORMATION

L-15-1 NRC JPM A, Recover a Dropped Rod, Rev. 0 JPM NRC L-15-1 EXAM SECURE INFORMATION Page 17 of 19 This begins the alternate portion of the JPM.

Performance Step: Candidate responds to ROD BOTTOM LIGHT for rod M-10.

Critical Y (SEQ-18)

Standard:

Stop withdraw of L5 and Trip Reactor Evaluator Notes:

If candidate attempts to notify US/SM act as US/SM and confirm communication.

Once Reactor is tripped proceed to Terminating Cue.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Terminating Cues:

Once the reactor is tripped, state Another operator will complete the remaining steps of this procedure. This completes the JPM.

NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.

Stop Time:

TR-AA-230-1003-F10, Revision 2 L-15-1 NRC Simulator - JPM A NRC L-15-1 EXAM SECURE INFORMATION

L-15-1 NRC JPM A, Recover a Dropped Rod, Rev. 0 JPM NRC L-15-1 EXAM SECURE INFORMATION Page 18 of 19 Examinee: Evaluator:

RO SRO STA Non-Lic SRO CERT Date:

LOIT RO LOIT SRO PERFORMANCE RESULTS: SAT: UNSAT:

Remediation required: YES NO COMMENTS/FEEDBACK: (Comments shall be made for any steps graded unsatisfactory).

EXAMINER NOTE: ENSURE ALL EXAM MATERIAL IS COLLECTED AND PROCEDURES CLEANED, AS APPROPRIATE.

EVALUATORS SIGNATURE:

NOTE: Only this page needs to be retained in examinees record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.

TR-AA-230-1003-F10, Revision 2 L-15-1 NRC Simulator - JPM A NRC L-15-1 EXAM SECURE INFORMATION

NRC L-15-1 EXAM SECURE INFORMATION JPM Page 19 of 19 TURNOVER SHEET INITIAL CONDITIONS:

Four hours ago while at 75% power, control rod L-5 dropped fully into the reactor.

Load has been reduced to 50% power.

The reason for the dropped rod has been identified and corrected.

3-ONOP-028.3 has been completed up to Step 18.

Rx Engineering Supervisor has approved a withdrawal rate of up to 10 steps/min.

R-20 has been stable the last 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

INITIATING CUES:

In accordance with Step 18 of 3-ONOP-028.3, the Shift Manager directs you to retrieve dropped rod L5.

NOTES:

The presence of a reactivity SRO, Reactor Engineer, and a peer checker are simulated in the Control Room.

Due to dynamic conditions, an instructor will acknowledge non-essential BOP alarms to facilitate the role of the RO (Turbine) and RO (S/G).

NOTE: Ensure the turnover sheet is returned to the evaluator when the JPM is complete.

TR-AA-230-1003-F10, Revision 2 NRC L-15-1 EXAM SECURE INFORMATION

Florida Power & Light Company Turkey Point Nuclear Plant Unit3 3-0NOP-028.3 CAUTION Performance of this procedure may affect core reactivity.

Title:

DroppedRCC Continuous Use Safety Related Procedure Responsible Department: Operations Revision Number: 4A Issue Date: 9/4/14 Revision Approval Date: 8/17/14 ARs 590548, 1611268, 1734453, 1982626 PCRs 08-5732, 09-0989, 10-0931 PC/Ms93-005, 09-006 W9:/cls/mr/ab

Procedure No.: Procedure

Title:

Page:

2 Approval Date:

3-0NOP-028.3 Dropped RCC 8/17/14 LIST OF EFFECTIVE PAGES (Rev. 4A)

Revision Page Date 1 08/17/14 2 08/17/14 3 04/07/09 4 03/28/12 5 08/02/10 6 03/28/12 7 03/28/12 8 03/28/12 9 08/17 /14 10 04/07/09 11 03/28/12 12 04/07/09 13 04/07/09 14 08/02/10 15 04/07/09 16 04/07/09 17 04/07/09 18 04/07/09 Foldout 04/07/09 v vJ./vl.JI lll!CIU

Procedure No.: Procedure

Title:

Page:

3 Approval Date:

3-0NOP-028.3 Dropped RCC 4/7/09 1.0 PURPOSE 1.1 This procedure provides instructions to be followed m the event of one or more dropped RCCs.

2.0 SYMPTOMS OR ENTRY CONDITIONS 2.1 Annunciators 2.1.1 B 212, POWER RANGE UPPERDETHI FLUX DEV/AUTO DEFEAT 2.1.2 B 2/3, POWER RANGE LOWER DET HI FLUX DEV/AUTO DEFEAT 2.1.3 B 7fl, NIS/RPI ROD DROP ROD STOP 2.1.4 B 9/2, AXIAL FLUX TILT 2.1.5 B 9/3, SHUTDOWN ROD OFF TOP/DEVIATION 2.1.6 G 5/1, AXIAL FLUX T.S. LIMIT EXCEEDED 2.1.7 G 5/2, AXIAL FLUX ADMIN LIMIT EXCEEDED 2.2 Indications 2.2.1 DROPPED ROD ROD STOP light illuminated on any one of the power range nuclear instrumentation channels.

2.2.2 Individual rod bottom lights on.

2.2.3 Axial flux indicators indicate flux tilt.

W9:/cls/mr/ab

Procedure No.: Procedure

Title:

Page:

4 Approval Date:

3-0NOP-028.3 Dropped RCC 3/28/12

3.0 REFERENCES

/RECORDS REQUIRED/COMMITMENT DOCUMENTS

3. I References

3. I. I Technical Specifications

1. Section 3/4. I .1, Reactivity Control Systems - Boration Control

2. Section 3/4.1.1.I, Shutdown Margin - Tavg Greater Than 200°F

3. Section 3/4.1.3.1, Reactivity Control Systems - Movable Control Assemblies - Group Height

4. Section 3/4.1.3.5, Reactivity Control Systems - Shutdown Rod Insertion Limit

5. Section 3/4.1.3.6, Reactivity Control Systems - Control Rod Insertion Limits

6. Section 3/4.2.1, Power Distribution Limits - Axial Flux Difference

7. Section 3/4.2.3, Power Distribution Limits - Nuclear Enthalpy Rise Hot Channel Factor

8. Section 3/4.2.4, Power Distribution Limits - Quadrant Power Tilt Ratio 3.1.2 Final Safety Analysis Report

1. Section 14.1.4, Rod Control Cluster Assembly (RCCA) Drop 3 .1.3 Plant Procedures

1. 3-GOP-103, Power Operation To Hot Standby

2. 3-0NOP-059.4, Excessive Axial Flux Difference

3. 3-0NOP-059.9, Excessive Quadrant Power Tilt Ratio

4. O-OSP-028.8, Shutdown Margin Calculation

5. 3-0SP-040.5, Nuclear Design Verification

6. 3-0SP-059.10, Determination of Quadrant Power Tilt Ratio 3.1.4 Regulatory Guidelines

1. SOER 84-2 (1, 2, and 8) Control Rod Mispositioning

2. SOER 84-2, Control Rod Mispositioning -Addendum

Procedure No.: Procedure

Title:

Page:

5 Approval Date:

3-0NOP-028.3 DroppedRCC 8/2/10 3 .1.5 Miscellaneous Documents (i.e., PC/Ms, Correspondence)

1. PC/M 93-005, Elimination of Turbine Runback from Dropped Rod

2. Unit 3 Plant Curve Book

3. PTN Condition Report 2005-7118

4. PC/M 09-006, Rod Position Indication System Replacement 3.1. 6 Commitment Documents

1. None

Procedure No.: Procedure

Title:

Page:

6 Approval Date:

3-0NOP-028.3 Dropped RCC 3/28/12 I ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED C AAY'f110 N

/L/

If this procedure was entered as a result of performing 3-SMl-028.03, RPI HOT CAL/BRA TJON, CRDM STEPPING TEST AND ROD DROP TEST, AND the RCS boron concentration is greater than or equal to test requirements, this procedure shall NOT be performed.

- ----~------- ........................... I

~ Foldout page is required to be monitored throughout this procedure.

~#'Misaligned rods are addressed by 3-0NOP-028.1, RCC Misalignment.

~-------------------

@ Check Number Of RCCs DROPPED - More Than One

( _ / Check the following 7~0 Step 2.

{ ) More than one rod bottom light - ON

/:' JMore than one rod position indicator -

VAT ZERO

b. Manually trip the Reactor

c. Go to 3-EOP-E-O, REACTOR TRIP OR 7 SAFETY INJECTION Check Reactor In Mode 1 IF in Mode 2 or Mode 3, THEN perform the following:

a. Stop all rod motion and dilution.

b. Ensure reactor power is stable or decreasing.

1) IF startup rate is positive and/or reactor power is increasing, THEN manually trip the Reactor and go to 3-EOP-E-O, REACTOR TRIP OR SAFETY INJECTION.

c. Commence boration to the ARO Hot Standby RCS boron concentration specified in the Plant Curve Book, Section 3, Figure 7.

Procedure No.: Procedure

Title:

Page:

7 Approval Date:

3-0NOP-028.3 Dropped RCC 3/28/12 TION/EXPECTED RESPONSE PONSE NOT OBTAINED Place Rod Motion Control Selector Switch To MANUAL CAUTIONS Do NOT dilute the RCS while performing this procedure until the SHUTDOWN MARGIN calculation has been performed using O-OSP-028.8, SHUTDOWN MARGIN CALCULATION.

yoo NOT increase reactor power while performing this procedure.

?o NOT use control rods for power or temperature adjustments until the cause of the dropped rod is identified and determined not to affect any other rods.

Prior to the operation of the controls that could change Reactor Power, a Reactivity Brief should be held. This brief is at the discretion of the Shift Manager or the unit Supervisor.

Verify Automatic Controls Are Functioning To Stabilize The Unit AND No Transient Is In Progress ff Tavg/Tref within 3°F a. Reduce turbine load to control temperature.

~PZR level/pressure trending to program b. Manually control systems to stabilize the unit.

~G level trending to program c. Manually control systems to stabilize the unit.

~ Check AFD Within RAOC Within 30 minutes, reduce reactor power to 0" G 5/1, AXIAL FLUX T.S. LIMIT EXCEEDED

-OFF less than 50% using 3-GOP-100, FAST LOAD REDUCTION, while continuing with this procedure.

~least 3 channels of AFD indicating within the RAOC limit as defined in the Plant Curve Book, Section 5, Figure 1 w/ _ / Initiate Hourly QPTR Detei-mination Using 3-0SP-059.10, DETERMINATION OF QUADRANT POWER TILT RA TIO Until Either QPTR Results Are Satisfactory OR Reactor Power Is Less Than 50%

Procedure No.: Procedure

Title:

Page:

8 Approval Date:

3-0NOP-028.3 Dro*pped RCC 3/28/12 ESPONSE NOT OBTAINED Declare The Dropped RCC Inoperable

, ~ Reduce Reactor Power To Less Than 50%

,P Within 1 Hour

~thin one hour, reduce reactor power to

)Z/ l~~s than 50% using 3-GOP-100, FAST LOAD REDUCTION, while continuing with this procedure

@ Check The Following:

/ Rod Position and Insertion Monitors - ~re RPls to group step counters every Operable ~~~r~ to comply with Technical

~ Annunciator B 8/1, ROD BANK A/B/C/D/JSpecification Surveillances 4.1.3.1.1 and

~ LO LIMIT - Not Locked In / . 4.1.3.6.

{;? Annunciator B 9/3, SHUTDOWN ROD

¥ OFF TOP/DEVIATION - Not Locked In Notify Reactor Engineering Of Dropped RCC

......... -~- u SHUTDOWN MARGIN shall be 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter.

veri~ 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months of a DROPPED RCC and every p

Verify Shutdown Margin Adequate

~heck RCS boron concentration a. Notify Reactor Engineering to evaluate

~realer than or equal to pre-event SHUTDOWN MARGIN using O-OSP-028.8, SHUTDOWN MARGIN value CALCULATION.

OR

Greater than the Minimum Shutdown Boron Versus RCS Temperature as a Function of Burnup Requirements in the Plant Curve Book, Section 3, Figure 5

/ ' / ,og SHUTDOWN MARGIN satisfied in the P Unit Narrative Log

Procedure No.: Procedure

Title:

Page:

9 Approval Date:

3-0NOP-028.3 Dropped RCC 3/28/12 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED r ..................................................................

~ ................................................ .

PWO will NOT be required; setpoint ~justed using 3-0SP-059.4, POWER RANGE NUCLEAR INSTRUMENTATION ANALOG CHANNEL OPERATIONAL TEST.

Notify l&C Of Dropped RCC AND Potential Need To Reset POWER RANGE HI FLUX TRIP SETPOINT Calculate Shutdown Margin

/VPerform O-OSP-028.8, SHUTDOWN

)# MARGIN CALCULATION, while continuing with this procedure Check Annunciator B 7/1, NIS/RPI Rod Drop Perform the following:

Rod Stop - CLEAR

-~~heck Power Range Drawers N-41 through N-44.

Pd1F*LighttheisDropped Rod I Rod Stop Bistable ON for any channel, THEN place the associated Dropped Rod Mode switch to RESET AND back to NORMAL.

Check Reactor Power Level Less Than 50% WHEN reactor power is less than 50%,

THEN go to Step 16.

Reduce The Power Range Hi Flux Trip Setpoint To Less Than Or Equal To 55%

Using 3-0SP-059.4, POWER RANGE NUCLEAR INSTRUMENTATION ANALOG CHANNEL OPERATIONAL TEST

Procedure No.: Procedure

Title:

Page:

10 Approval Date:

3-0NOP-028.3 Dropped RCC 4/7/09 STEP /EXPECTED RESPONSE RESPONSE NOT OBTAINED Determine If Dropped Rod Can Be Retrieved.

p Check each of the following:

a. Perform the following:

ff Cause of dropped rod is identified.

1) Reduce reactor Power to less than 20%

using 3-GOP-103, Power Operation to

~ause of the dropped rod can be Hot Shutdown.

repaired and the rod recovered within 2) WHEN Reactor power is less than 20%,

10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months of event. THEN TRIP Reactor using 3-GOP-103, I / Shift Manager directs rod recovery Power Operation to Hot Shutdown.

~ actions to continue.

Continue Rod Recovery Actions Using Attachment 1 Of This Procedure END OF TEXT

Procedure No.: Procedure

Title:

Page:

11 Approval Date:

3-0NOP-028.3 Dropped RCC 3/28/12 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT 1 (Page 1 of 8)

DROPPED ROD RECOVERY CAUTIONS

" If the dropped RCC has been dropped and retrieved in the previous 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , then any further retrieval attempts require the permission of the Plant General Manager.

" In cases of power operation with a dropped RCC, power peaking may affect fuel integrity if caution is not employed.

" If PRMS R-20 shows an unexpected increase due to the dropped RCC, a Reactor

Engineering evaluation is required prior to retrieving the dropped rod.

1 Verify Reactor Power Is Stable Perform the following:

a. Verify O-OSP-028.8, SHUTDOWN MARGIN CALCULATION, is complete.

b. WHEN SHUTDOWN MARGIN is verified to be satisfactory, THEN maintain reactor power stable using O-OP-046, CVCS -

BORON CONCENTRATION CONTROL, for dilution or boration.

Procedure No.: Procedure

Title:

Page:

12 Approval Date:

3-0NOP-028.3 Dropped RCC 417/09 ACTION/EXPECTED RESPONSE PONSE NOT OBTAINED ATTACHMENT 1 (Page 2 of 8)

DROPPED ROD RECOVERY NOTE -------1 If Initial Reactor Startup or Physics Testing after refueling was in progress, boration to All-Rods-Out, Hot Standby boron concentration will ensure adequate SHUTDOWN MARG IN in xenon-free conditions while the cause of the dropped rod is being determined prior to reactor shutdown.

2 Check Reactor Mode Status

a. Reactor in Mode 2 or 3 a. Go to Step 3.

b. Verify RCS boron concentration is greater b. WHEN RCS Boron concentration has than or equal to the ARO Hot Standby RCS been verified greater than or equal to boron concentration specified in the Plant ARO Hot Standby Boron concentration, Curve Book, Section 3, Figure 7. THEN go to Step 3.

3 Check Elapsed Time of Dropped Rod.

a. Time less than 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months . a. Perform the following:

1) Notify the Shift Manager that power increases are required to be delayed until equilibrium xenon is established (approximately 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ).

2) Perform an lncore Flux Map within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months to verify that Power Distribution factors Fq AND F.llh, are within limits.

3) Direct Reactor Engineering to perform evaluations specified in Technical Specifications Action 3.1.3.1.d.3.d.

Procedure No.: Procedure

Title:

Page:

13 Approval Date:

3-0NOP-028.3 Dropped RCC 4/7/09 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT 1 (Page 3 of 8)

DROPPED ROD RECOVERY 4 Cause of Rod Drop Repaired. Perform the following:

a. WHEN the cause has been repaired, THEN go to Step 5.

b. IF directed by the Shift Manager, THEN shut down using 3-GOP-103, Power Operation to Hot Standby.

5 Prepare To Retrieve Dropped RCC.

a. Position the Rod Motion Control Selector switch to the RCC bank with the dropped RCC.

b. Place all the lift coil disconnect switches for the dropped rod bank to the disconnect position (toggle switch down) except for the dropped RCC lift coil disconnect switch.

c. Ensure the lift coil disconnect switch for the dropped RCC is in the connect position (toggle switch up).

d. Record the step position for the dropped RCC group demand step counter in the Unit Narrative Log as follows:

Bank - - - - - - - -

Group _ _ _ _ _ __

Position _ _ _ _ _ _ _ steps

e. Manually set the associated group demand step counter to zero.

Procedure No.: Procedure

Title:

Page:

14 Approval Date:

3-0NOP-028.3 DroppedRCC 8/2/10 RESPONSE RESPONSE NOT OBTAINED ATTACHMENT 1 (Page 4 of 8)

DROPPED ROD RECOVERY

- 111!111 - .. - .. - 111121111 - 111111 NOTE 111111111111111 - - - - 1111111 - - - 11111111 - 1111111 I

Annunciators B 811, ROD BANK AIB/CID LO-LIMIT, and B 812, ROD BANK EXTRA LO-LIMIT, will alarm when the RPI bank demand alignment on the DCS screen is reset below the Low and Extra Low Rod Insertion Limits.

Check If Dropped Rod is in a Shutdown Bank IF the dropped rod is in a control bank, THEN 6 reset the bank demand step counters from the DCS as follows:

a. Navigate to the RPI BANK DEMAND ALIGNMENT screen.

b. Select INITIATE ALIGNMENT for the affected control bank.

c. Select NEW VALUE in the overlay.

d. Type in the desired bank demand step value, using the keyboard.

e. Press Enter.

f. Select INITIATE RE ALIGNMENT in the overlay.

g. Select YES in the save changes overlay.

h. Select CLOSE OVERLAY.

Procedure No.: Procedure

Title:

Page:

15 Approval Date:

3-0NOP-028.3 Dropped RCC 4/7/09 ION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT 1 (Page 5 of 8)

DROPPED ROD RECOVERY CAUTIONS

If a dropped RCC is retrieved within 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months of dropping, it may be withdrawn at a rate not to exceed 10 steps per minute.

If a dropped RCC is retrieved after 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months of dropping, it should be withdrawn at a rate not to exceed 3 steps per hour.

The actual withdrawal rate shall be approved by the Reactor Engineering Supervisor or designee prior to commencilJg, and may be modified from the above if conditions warranted (i.e., PRMS R-20 Alarm, Unit in Mode 3 etc.).

If the unit experiences a transient which requires rod motion during the dropped rod retrieval, all lift coil disconnect switches are required to be placed in the connect position (toggle switch up), rod control alarm reset PB depressed, and the rod control selector switch placed in MANUAL prior to rod motion.

" Boration at 10 gpm is equivalent to 1 ppm/min (10 pcm/min) negative reactivity insertion.

" Annunciator B 914, ROD CONTROL URGENT FAILURE, and the RCC Power Cabinet URGENT FAILURE will alarm for the group with the lift coils disconnected.

Boration of the RCS may be required to maintain Tavg equal to Tref.

7 Withdraw The Dropped RCC

a. Withdraw the dropped rod at the rate determined by the Reactor Engineering Supervisor.

b. Borate as necessary to maintain Tavg within 3°F of Tref.

c. Adjust turbine load as necessary to maintain required power level determined in procedure Step 8.

d. Continue to withdraw the RCC until it is aligned with its group.

Procedure No.: Procedure

Title:

Page:

16 Approval Date:

3-0NOP-028.3 Dropped RCC 417/09 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT 1 (Page 6 of 8)

DROPPED ROD RECOVERY Place All Lift Coil Disconnect Switches To 8 The Connect Position (Toggle Switch Up).

Reset Rod Control System Alarms.

9

a. Depress the Rod Control Alarm Reset.

b. Verify the following alarms clear or off:

Annunciator B 9/4, ROD CONTROL URGENT FAILURE

In the 38 MCC Room, RCC power cabinet URGENT FAILURE light Reset NIS Rod Bottom Bistable Light On Any 10 , Applicable Power Range Nuclear Instrumentation Drawer.

a. Check any Rod Bottom bistable light - On a. Go to Step 11.

b. Place applicable Dropped Rod Mode switches to the RESET position AND return to the NORMAL position.

Place The Rod Motion Control Selector 11 Switch To MANUAL OR AUTOMATIC Position.

Procedure No.: Procedure

Title:

Page:

17 Approval Date:

3-0NOP-028.3 Dropped RCC 4/7/09 STEP RESPONSE RESPONSE NOT OBTAINED ATTACHMENT 1 (Page 7 of 8)

DROPPED ROD RECOVERY

'I NOTE I At the discretion of the Reactor Engineering Supervisor, an lncore Flux Map may I be performed.

Check Flux Distribution Is Normal.

12

a. Perform 3-0SP-059.10, Determination of Quadrant Power Tilt Ratio.

b. No significant axial power shape difference from symmetric assemblies as determined by the Reactor Engineering Supervisor.

c. Axial flux indicators indicate less than 3 percent difference between any two channels.

Verify All RCC Assemblies Are Aligned To 13 Within the Allowed Rod Misalignment Of Step Counters Monitor QPTR In Preparation For Power 14 Ascension

Procedure No.: Procedure

Title:

Page:

18 Approval Date:

3-0NOP-028.3 Dropped RCC 4/7/09 ACTION/EXPECTED RESPONSE ATTACHMENT 1 (Page 8 of 8)

DROPPED ROD RECOVERY Check If All Technical Specifications WHEN all Technical Specification 15 Requirements Are Satisfied requirements are satisfied, THEN perform Step 15a.

a. Reset the Power Range Hi Flux Trip Setpoint to 108% using 3-0SP-059.4, POWER RANGE NUCLEAR INSTRUMENTATION ANALOG CHANNEL OPERATIONAL TEST 16 Notify The Shift Manager That All Subsequent Power Increases Shall Be Done At Approximately 1 Percent Per Hour OR As Directed By Reactor Engineering 17 Go To Procedure And Step In Effect FINAL PAGE

Procedure No.: Procedure

Title:

Page:

Foldout Approval Date:

3-0NOP-028.3 Dropped RCC 4/7/09 FOLDOUT FOR PROCEDURE ONOP-028.3 Following is a list of applicable Technical Specification LCOs and procedure steps that verify compliance. These need to be reviewed by the Shift Manager to ensure compliance.

1. T.S. 3.1.1.1 - SHUTDOWN MARGIN

Covered in Steps 11 and 13

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to verify AND repeat every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

2. T.S. 3.1.3.1 - GROUP ROD HEIGHT

Covered in Steps 1, 7, 8, 9, and 15, Attachment 1 Steps 3 and 13

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months - to restore OR declare inoperable AND be less than 75% power, 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months - to perform Flux Map, and 5 days - to perform re-analysis of accidents.

If 2 Control Rods, 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months - to be in Hot Standby

If 2 or more Shutdown Rods are not fully withdrawn, apply Tech Spec 3.0.3.

If Rod Deviation Monitor is inoperable, compare RPls to Step Counters every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

3. T.S. 3.1.3.5 - SHUTDOWN ROD INSERTION LIMIT

Covered in Steps 7 and 9

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months - to restore OR declare inoperable.

If 2 or more Shutdown Rods are not fully withdrawn, apply Tech Spec 3.0.3.

If Rod Deviation Monitor is inoperable, compare RPls to Step Counters every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

4. T.S. 3.1.3.6 - CONTROL ROD INSERTION LIMIT

Covered in Steps 8 and 9.

2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months - to restore OR to reduce power to within guidelines of COLR.

If Rod Deviation Monitor is inoperable, compare RPls to Step Counters every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

5. T.S. 3.2.1 - AXIAL FLUX DIFFERENCE

Covered in Steps 5 and 8.

30 minutes to get power less than 50% AND the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months to set the NIS trip setpoint to 55%.

6. T.S. 3.2.4 - QUADRANT POWER TILT RA TIO

Covered in Step 6.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to perform AND required every hour thereafter while QPTR exceeds 2%.

If QPTR is greater than 9%, reduce power 3% for every 1% QPTR exceeds 1 within 30 minutes.

If QPTR is greater then 2%, reduce power 3% for every 1% QPTR exceeds 1 within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

Reduce the NIS trip setpoints the same amount within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

OPERATION[ ~y LOG 11 QA RECORD PAGE n System, major component, cubicle or WORK rack door or panel to be manipulated CONTROL KEY ISSUED KEY RETURNED/LOCK RESTORED MODE orop~ned that allows NO. EVAL manipulation TO PERSON ISSUED Vt::RIFIED (INIT) DATE BY(NAME& DATE&

NAME NUMBER (procedure or (NAME & BY. LOCKED clearance No.) &TIME DEPT) TIME DEPT) (NAME) (NOTE 1)

\

""' \

NOTE 1: Each cubicle, rack door, or panel that was unlocked shall be verified to be closed and locked. Enter name ofp~rson perfor:ming the verification (Ref. Step 5.4.4).

Reviewed B y : - - - - - - - - - - - - - - - - - - - Date: ---------..,.,...,.._

Shift Manager or SRO. Designee F-527 -Rev. 2 (05/21/08-0-ADM-205) .

LOIT L-15-1 NRC Exam material controlled by TR-AA-230-1009, Training Examination Security.

Simulator - JPM B LOIT L-15-1 NRC Exam material controlled by TR-AA-230-1009, Training Examination Security.

JPM TITLE: Drain The 38 Accumulator For Boron And Level Adjustment JPM NUMBER: 1064003101 REV. 0-0 TASK NUMBER(S) I 1064003100/

TASK TITLE(S): Drain the Accumulators KIA NUMBERS: 006 A1.13 KIA VALUE: RO 3.5 /SRO 3.7 Justification (FOR KIA VALUES <3.0): N/A TASK APPLICABILITY:

~RO ~SRO D STA D Non-Lie D SRO CERT D OTHER: _ _

APPLICABLE METHOD OF TESTING: Simulate/Walkthrough: Perform: IT]

EVALUATION LOCATION: In-Plant: D Control Room: D Simulator: ITJ Other:

Lab:

Time for Completion: 30 Minutes Time Critical: No Alternate Path [NRC]: Yes Alternate Path [INPO]: Yes Date Training Program Owner TR-M-230-1003-F10, Revision 2 L~ 15-1 NRC Simulator - J PM

1064003101, Drain The 3B Accumulator For Boron And Level Adjustment , Rev. 0 JPM Page 3 of 18 NRC L-15-1 EXAM SECURE INFORMATION JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED PRIOR TO USE.