ML041070054

Initial Admin RO JPM 1405.0401

ML041070054
Person / Time
Site:	Clinton  (NPF-062)
Issue date:	01/06/2004
From:	Delaney T, Pickley T, Ryan P Exelon Generation Co, Exelon Nuclear
To:	Office of Nuclear Reactor Regulation
References
-RFPFR, 50-461/04-301, JPM 1405.0401, Rev 01 50-461/04-301
Download: ML041070054 (23)

Text

CLINTON POWER STATION Job Performance Measure Prepare an ENW Form JPM Number: 1405.0401 Revision Number: 01 Date: 7/25/03 Developed By:

T. Pickley 7/25/03 Instructor Date Validated By:

T. Delaney 10/16/03 SME or Instructor Date Review By:

P. K. Ryan

_7/28/03 Operations Representative Date

Page 2 of 14 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 8 through 11 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, or simulator)

4. Initial setup conditions are identified.

5. Initiating and terminating cues 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. Verify the procedure referenced by this JPM matches the most current revision of that procedure:

Procedure Rev. _____ Date _____________

9. Pilot test the JPM:

a. verify cues both verbal and visual are free of conflict, and

b. ensure performance time is accurate.

10. If the JPM cannot be performed as written with proper responses, then revise the JPM.

11. When JPM is revalidated, SME or Instructor sign and date JPM cover page.

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

CLINTON POWER STATION SYSTEM JPM JPM NUMBER: 1405.0401 REVISION: 01 Page 3 of 14 Revision Record (Summary)

1. Revision 00, This is a new JPM

2. Revision 01, Revised for new format and procedure

CLINTON POWER STATION SYSTEM JPM JPM NUMBER: 1405.0401 REVISION: 01 Page 4 of 14 Operators Name:

SSN:

Job

Title:

NLO RO SRO STA SRO Cert JPM Title/Number: 1405.0401, Prepare an ENW Form Revision Number:

01 Task Number and

Title:

140504.01, Apply the administrative requirements for NRC NOTIFICATION REQUIREMENTS.

Suggested Testing Environment:

Any Actual Testing Environment: I Simulator Plant Control Room Testing Method:

Simulate Faulted:

No I

Perform Alternate Path:

No Time Critical:

No Estimated Time to Complete: 12 _minutes Actual Time Used:

minutes

References:

EVALUATION

SUMMARY

Were all the Critical Elements performed satisfactorily?

Yes

No The operators performance was evaluated against the standards contained in this JPM, and has been determined to be:

Satisfactory

Unsatisfactory Comments:

Evaluators Name: __________________________

Evaluators Signature:

Date:

CLINTON POWER STATION SYSTEM JPM JPM NUMBER: 1405.0401 REVISION: 01 Page 5 of 14 READ TO THE OPERATOR I will explain the initial conditions, which step(s) to simulate or discuss, and provide the initiating cues. When you complete the task successfully, the objective of this Job Performance Measure will be satisfied.

SIMULATOR SET-UP CONDITIONS:

None TASK STANDARDS:

ENW Form completed for an ALERT and NRC informed within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of initiation of event.

TOOLS, EQUIPMENT, OTHER SPECIAL REQUIREMENTS:

None PROCEDURAL/

REFERENCES:

EP-AA-114r4, NOTIFICATIONS EVALUATOR INSTRUCTIONS:

Amplifying cues are provided within the JPM steps.

Provide the operator with the following:

EP-AA-114r4, NOTIFICATIONS ENW Form Initial Conditions And Initiating Cue INITIAL CONDITIONS AND INITIATING CUE:

The plant was at 90% power when a sudden reactor coolant leakage developed in the Drywell. An ALERT has been declared due to the leak being in excess of 50 gpm. The cause of the leak has not been determined. Currently the plant is in mode 3 with plans to cool down to mode 4. Notifications have been made to the NRC Resident, the State the County, the Sheriff department and a press release has been issued.

The plant response was as expected and all systems functioned as required. A restart date will not be determined until the extent of the damage has been analyzed. Chemistry is analyzing a Reactor Coolant sample. No release has occurred or is expected. You are called to the MCR to complete and send an ENW form to the NRC within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

START TIME:

CLINTON POWER STATION SYSTEM JPM JPM NUMBER: 1405.0401 REVISION: 01 Page 6 of 14

==============================================================

PERFORMANCE INFORMATION Critical steps are denoted with an asterisk (*) to the left of the step number and appear in BOLDED letters. Failure to meet the standards for a critical step constitutes failure of the Job Performance Measure. The sequence of steps is assumed unless denoted in the comments section of the JPM.

==============================================================

PERFORMANCE STEPS 1.

Facility or Organization Standard CPS CUE Comments SAT UNSAT Comment Number 2.

Unit Standard 1

CUE Comments SAT UNSAT Comment Number

CLINTON POWER STATION SYSTEM JPM JPM NUMBER: 1405.0401 REVISION: 01 Page 7 of 14 3.

Callers Name Standard As applicable CUE Comments SAT UNSAT Comment Number 4.

Callback #

Standard (217) 935-9812 CUE Comments SAT UNSAT Comment Number 5.

EVENT TIME Standard Present time minus 15 minutes CUE The event occurred 15 minutes ago.

Comments SAT UNSAT Comment Number

CLINTON POWER STATION SYSTEM JPM JPM NUMBER: 1405.0401 REVISION: 01 Page 8 of 14

• 6.

Power/Mode before Standard 90%/1 CUE Comments SAT UNSAT Comment Number

• 7.

Power/mode after Standard 0%/3 CUE Comments SAT UNSAT Comment Number

• 8.

Classification Standard ALERT CUE Comments SAT UNSAT Comment Number

CLINTON POWER STATION SYSTEM JPM JPM NUMBER: 1405.0401 REVISION: 01 Page 9 of 14 9.

Description as follows:

Standard RCS leakage into Drywell in excess of 50 gpm, cause is unknown, currently in mode 3 plan to cool down to mode 4 CUE Comments SAT UNSAT Comment Number 10.

Notifications to:

Standard NRC Resident - YES State - YES Local - YES Other Agencies - YES Media/Press - YES CUE Comments SAT UNSAT Comment Number 11.

Anything unusual or not understood Standard No CUE Comments SAT UNSAT Comment Number

CLINTON POWER STATION SYSTEM JPM JPM NUMBER: 1405.0401 REVISION: 01 Page 10 of 14 12.

All systems function as required Standard Yes CUE Comments SAT UNSAT Comment Number 13.

Mode of operation until corrected Standard UNKNOWN or MODE 4 CUE Comments SAT UNSAT Comment Number 14.

Additional information on back Standard Yes CUE Comments SAT UNSAT Comment Number

CLINTON POWER STATION SYSTEM JPM JPM NUMBER: 1405.0401 REVISION: 01 Page 11 of 14

• 15.

LOCATION OF LEAK Standard UNKNOWN CUE Comments SAT UNSAT Comment Number

• 16.

Leak Rate Standard EXCEEDS 50 GPM CUE Comments SAT UNSAT Comment Number 17.

Sudden or long term Standard Sudden CUE Comments SAT UNSAT Comment Number

CLINTON POWER STATION SYSTEM JPM JPM NUMBER: 1405.0401 REVISION: 01 Page 12 of 14 18.

Coolant Activity Standard Sampling in Progress CUE Comments SAT UNSAT Comment Number 19.

Safety Systems not operational Standard None CUE Comments SAT UNSAT Comment Number

• 20.

Calls NRC (Simulated) and completes form by filling in Notification Time on page 1 of 2.

Standard Examinee simulates calling NRC either on FTS2000 or via commercial line.

CUE Evaluator acts as NRC and provides applicable time.

Comments SAT UNSAT Comment Number

CLINTON POWER STATION SYSTEM JPM JPM NUMBER: 1405.0401 REVISION: 01 Page 13 of 14 STOP TIME:_____________

TERMINATING CUES:

ENW Form completed for an ALERT and NRC informed of event.

K/A REFERENCE NUMBERS Importance Rating K/A SYSTEM NUMBER K/A NUMBER RO SRO 2.4.43 2.8 3.5

CLINTON POWER STATION SYSTEM JPM JPM NUMBER: 1405.0401 REVISION: 01 Page 14 of 14 INITIATING CUE The plant was at 90% power when a sudden reactor coolant leakage developed in the Drywell. An ALERT has been declared due to the leak being in excess of 50 gpm. The cause of the leak has not been determined. Currently the plant is in mode 3 with plans to cool down to mode 4. Notifications have been made to the NRC Resident, the State the County, the Sheriff department and a press release has been issued.

The plant response was as expected and all systems functioned as required. A restart date will not be determined until the extent of the damage has been analyzed. Chemistry is analyzing a Reactor Coolant sample. No release has occurred or is expected. You are called to the MCR to complete and send an ENW form to the NRC within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.