ML091520487

From kanterella
Revision as of 05:12, 14 November 2019 by StriderTol (talk | contribs) (Created page by program invented by StriderTol)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Jump to navigation Jump to search
NRC Region III, Initial License Exam, Job Performance Measure, JPM: RO, SRO-U System B, Title: Manually Initiate Containment Isolation
ML091520487
Person / Time
Site: Palisades Entergy icon.png
Issue date: 07/07/2008
From:
NRC/RGN-III
To:
Entergy Nuclear Palisades
Shared Package
ML082200319 List:
References
Download: ML091520487 (8)


Text

NRC REGION III INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM: RO, SRO-U SYSTEM b TITLE: MANUALLY INITIATE CONTAINMENT ISOLATION CANDIDATE: _____________________________________________

EXAMINER: _____________________________________________

JPM: RO, SRO-U SYSTEM b JOB PERFORMANCE MEASURE DATA PAGE Task: All Containment Isolation pathways have at least one isolation valve closed.

Alternate Path: YES Facility JPM #: PL-OPS-ESF-002J K/A: 103A2.03 Importance: RO: 3.5 SRO: 3.8 K/A Statement: Ability to (a) predict the impacts of the following malfunctions or operations on the containment system ..Phase A and B isolation Task Standard: Manual Containment Isolation initiated with all pathways having at least one isolation valve closed.

Preferred Evaluation Location: Simulator __X__ In Plant _____

Preferred Evaluation Method: Perform __X__ Simulate _____

References:

EOP-4.0, Loss of Coolant Accident EOP Supplement 6, Checksheet for Containment Isolation and CCW Restoration Validation Time:10 minutes Time Critical: NO Candidate:

Time Start: ________ Time Finish: ________

Performance Time: ________ minutes Performance Rating: SAT______ UNSAT ______

Comments:

Examiner: _______________________________ Date: ______________

Signature PALISADES NUCLEAR PLANT Page 2 of 8 JULY 2008

JPM: RO, SRO-U SYSTEM b EXAMINER COPY ONLY Tools/Equipment/Procedures Needed:

EOP Supplement 6, Checksheet for Containment Isolation and CCW Restoration, Rev. 7 Also see Simulator Operator Instructions (last page of this document).

READ TO CANDIDATE DIRECTION TO CANDIDATE:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

  • A Loss of Coolant Accident has occurred.
  • The Reactor has been tripped and EOP 1.0, "Standard Post Trip Actions" have been performed.
  • Containment radiation is above 10 R/hr.
  • Automatic Containment isolation has not occurred.

INITIATING CUES:

  • During performance of EOP 4.0, "Loss of Coolant Accident Recovery", the Control Room Supervisor directs you to manually initiate Containment isolation, referring to Step 13.

PALISADES NUCLEAR PLANT Page 3 of 8 JULY 2008

JPM: RO, SRO-U SYSTEM b Proc. Step TASK ELEMENT 1 STANDARD Grade Locate EOP-4.0, Step 13 EOP-4.0 Step 13 located.

n/a S U Comment:

Proc. Step TASK ELEMENT 2 STANDARD Grade IF ANY of the following conditions exit:

Containment pressure is greater CIS INITIATED (EK-1126) has not alarmed.

than or equal to 4.0 psig Either HIGH RADIATION INITIATE pushbuttons Any operable Containment Radiation 1 on Panel EC-13 pushed:

EOP- Monitor rises to 1 X 10 R/hr, S U 4.0, 13.a THEN PERFORM ALL of the CHRL-CS following:

CHRR-CS

a. VERIFY CIS INITIATED (EK-1126) is alarmed Comment:

NOTE: Operator verifies CIS INITIATED (EK-1126) is in alarm once pushbutton is pushed, it is permissible, but not necessary, to push both pushbuttons.

CRITICAL STEP Proc. Step TASK ELEMENT 3 STANDARD Grade IF ANY of the following conditions exit:

Containment pressure is greater than or equal to 4.0 psig EOP Supplement 6 obtained.

Any operable Containment Radiation 1

EOP- Monitor rises to 1 X 10 R/hr, THEN PERFORM ALL of the S U 4.0, 13.b following:

b. VERIFY Containment Isolation, Refer to EOP Supplement 6 Comment:

PALISADES NUCLEAR PLANT Page 4 of 8 JULY 2008

JPM: RO, SRO-U SYSTEM b Proc. Step TASK ELEMENT 4 STANDARD Grade Verifies that all valves closed as required, ENSURE CLOSED all valves unless Supp.6, checking them off on the checklist, except for otherwise specified by the notes. S U 1.0 the CWRT Vent Valves, CV-1064 and CV-1065.

Comment:

NOTE: Determining that the CWRT Vent Valves failed to close is the only action needed to satisfactorily perform this critical step.

Evaluator Que: If asked by the operator what should be done with CV-1064 and CV-1065, RESPONSE: direct operator to perform EOP Supplement 6.

CRITICAL STEP Proc. Step TASK ELEMENT 5 STANDARD Grade CWRT Vent Valves, CV-1064 and CV-1065 have failed to isolate, ENSURE CLOSED all valves unless

  • Handswitches for both CV-1064 and otherwise specified by the notes. CV-1065 are placed to close.

Supp.6, S U 1.0

  • CV-1064 is verified closed (green light on), CV-1065 remains open (red light on)

Comment:

NOTE: CV-1064 closes, CV-1065 remains open.

NOTE: Placing the handswitch for CV-1064 to close is the critical component of this step.

CRITICAL STEP PALISADES NUCLEAR PLANT Page 5 of 8 JULY 2008

JPM: RO, SRO-U SYSTEM b Proc. Step TASK ELEMENT 6 STANDARD Grade CRS informed of completion of EOP Supplement Report status of EOP Supplement 6 for 6 and all containment isolation valves are closed, n/a Containment Isolation to the CRS. S U with the exception of CV-1065.

Comment:

END OF TASK PALISADES NUCLEAR PLANT Page 6 of 8 JULY 2008

JPM: RO, SRO-U SYSTEM b CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER TO UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

  • A Loss of Coolant Accident has occurred.
  • The Reactor has been tripped and EOP 1.0, "Standard Post Trip Actions" have been performed.
  • Containment radiation is above 10 R/hr.
  • Automatic Containment isolation has not occurred.

INITIATING CUES:

  • During performance of EOP 4.0, "Loss of Coolant Accident Recovery", the Control Room Supervisor directs you to manually initiate Containment isolation, referring to Step 13.

PALISADES NUCLEAR PLANT Page 7 of 8 JULY 2008

Proc No EOP Supplement Supplement 6 PALISADES NUCLEAR PLANT Revision 7 EMERGENCY OPERATING PROCEDURE Page 1 of 2 TITLE: Checksheet For Containment Isolation And CCW Restoration 1.0 ENSURE CLOSED all valves unless otherwise specified by the notes.

PALISADES NUCLEAR PLANT Page 8 of 8 JULY 2008