Latest revision as of 17:08, 12 March 2020

Text

2009-02 - Final Operating Exam
	ML090420378
Person / Time
Site:	San Onofre
Issue date:	02/05/2009
From:	Mckernon T; NRC Region 4
To:	; Southern California Edison Co
References
	Download: ML090420378 (131)
	v • d • e

JPM INFORMATION SHEET JPM NUMBER 2009A NRC SRO A-1a INITIAL PLANT CONDITIONS You have been directed to perform a blended makeup to the RWSTs at a total flow of 50 gpm.

The Plant Computer System (PCS) is UNAVAILABLE.

RWST Boron concentration is 2700 ppm.

BAMU Tank concentration is 5950 ppm.

TASK TO BE PERFORMED Determine required Boric Acid Flow Rate and PMW Flow Rate for the required RWST makeup per SO23-3-2.2, MAKEUP OPERATIONS 2009A NRC A-1a rev 0.doc Page 1 of 6

JOB PERFORMANCE MEASURE 2009A NRC SRO A-4 SUGGESTED TESTING ENVIRONMENT: PLANT +- SIMULATOR X ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATORS NAME:

The operators performance was evaluated against the standards contained in this JPM and is determined to be:

SATISFACTORY:

UNSATISFACTORY:

Examiner:__________________________________ ___________________

Signature Date Comments:

2009A NRC A-1a rev 0.doc Page 2 of 6

DOCUMENTATION 2007 NRC SRO A-4 JPM LEVEL: RO ESTIMATED TIME TO COMPLETE: 10 minutes TIME CRITICAL JPM: NO CRITICAL TIME: N/A POSITION: CO TASK SYS ID: 141358 TASK DESCRIPTION Calculate a blend for automatic or manual makeup operations.

KA NUMBER: G2.1.23 KA VALUES: RO 3.9 SRO 4.0 10CFR55.45 APPLICABILITY: 11

REFERENCES:

SO23-3-2.2, Makeup Operations, Rev 23.

AUTHOR: DATE:

OPERATIONS REVIEW: DATE:

APPROVED BY: DATE:

2009A NRC A-1a rev 0.doc Page 3 of 6

MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOT BY MODIFIED APPROVAL 0 From 2003 Audit Exam JPM RO/SRO new new new A.1b.

2009A NRC A-1a rev 0.doc Page 4 of 6

SET-UP EXAMINER:

Provide candidate with a copy of SO23-3-2.2, Makeup Operations.

2009A NRC A-1a rev 0.doc Page 5 of 6

JPM: 2009A NRC A-1.a TITLE: Perform an RWST Blended Makeup Calculation.

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)

NOTE: Provide the Examinee with a copy of SO123-VIII-1, Recognition and Classification of Emergencies.

NOTE: The following steps can be performed in any order.

1 Identify proper attachment for Identifies Attachment 10, section 2.2, formula Start Time: ________

performing the required calculations.. to Calculate a Blended Makeup to the RWST.

2* Determines Boric Acid flow rate RWST ppm (2700)/ BAMU ppm (5950) X Desired Flow Rate (50 gpm) = 22.69 gpm.

(*22-23 is acceptable) 3* Determines PMW flow rate Desired Total Flow (50 gpm) - gpm Acid for Blend (22-23) = gpm for blend.

(*27-28 is acceptable)

TERMINATING CUE:

This JPM is complete.

TERMINATING CUE: Stop Time: ________

This JPM is complete.

2009A NRC A-1a rev 0.doc Page 6 of 6

JPM INFORMATION SHEET JPM NUMBER 2009A A-1b INITIAL PLANT CONDITIONS Unit 2 is at 100% power. RCS Flow Rate must be determined to comply with Technical Specification Surveillance Requirement 3.4.1.3. The PMS computer is not available.

TASK TO BE PERFORMED The Control Room Supervisor directs you to perform SO23-3-3.3, RCS Flow Rate Determination, Attachment 2, RCP P Flow Calculation for SONGS Unit 2 and determine if Acceptance Criteria is met.

2009A NRC A-1b rev 0.doc Page 1 of 9

JOB PERFORMANCE MEASURE SO-05 NRC RO JPM A.1.b SUGGESTED TESTING ENVIRONMENT: PLANT X SIMULATOR X ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATORS NAME:

The operators performance was evaluated against the standards contained in this JPM and is determined to be:

SATISFACTORY:

UNSATISFACTORY:

2009A NRC A-1b rev 0.doc Page 2 of 9

DOCUMENTATION SO-05 NRC RO JPM A.1.b JPM LEVEL: RO / SRO ESTIMATED TIME TO COMPLETE: 20 minutes TIME CRITICAL JPM: NO CRITICAL TIME: N/A POSITION: CO TASK SYS ID: 179879 TASK DESCRIPTION Perform an RCS Flow Rate Determination.

KA NUMBER: 2.1.19 KA VALUES: RO 3.0 SRO 3.0 10CFR55.45 APPLICABILITY: 12

REFERENCES:

SO23-3-3.3, RCS Flow Rate Determination, EC 6-2, Attachment 2, RCP P Flow Calculation Technical Specification 3.4.1 AUTHOR: L. Zilli DATE: 04/05/05 OPERATIONS REVIEW: M. Jones DATE: 04/08/05 APPROVED BY: A. Hagemeyer DATE: 04/08/05 2009A NRC A-1b rev 0.doc Page 3 of 9

MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOT BY MODIFIED APPROVAL 2 Compared against SO23-3-3.3, LRZ 04/05/05 REV Rev. 6 and modified calculations to conform with new RCP Curves and procedure changes.

2009A NRC A-1b rev 0.doc Page 4 of 9

SET-UP Obtain a copy of SO23-3-3.3 and markup Attachment 2, complete up to Step 3.1.2 with the following data:

Step 3.1.1:

Ch. A TC1 RAW Avg. - 542°F TC2 RAW Avg. - 541°F Ch. B TC1 RAW Avg. - 540°F TC2 RAW Avg. - 539°F Ch. C TC1 RAW Avg. - 539°F TC2 RAW Avg. - 538°F Ch. D TC1 RAW Avg. - 538°F TC2 RAW Avg. - 539°F Step 3.1.2:

P001 P AVG - 102 psid P002 P AVG - 105 psid P003 P AVG - 103 psid P004 P AVG - 104 psid 2009A NRC A-1b rev 0.doc Page 5 of 9

JPM: 2009A NRC A-1.b TITLE: Perform an RCS Flow Rate Determination

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)

NOTE: Provide the candidate with a copy of SO23-3-3.3 completed to Step 3.1.2 of Attachment 2.

CUE: Steps 3.1.1 and 3.1.2 of Attachment 2 were completed last shift.

1 Calculate Average RCS Cold Leg Calculates TC1 using the data from Start Time: ______

Temperature TC1. Attachment 2, Step 3.1.1.

TC1 = 539.75°F TC1 = (Sum all CPC Ch. TRC1 RAW) / 4 2 Calculate Average RCS Cold Leg Calculates TC2 using the data from Temperature TC2. Attachment 2, Step 3.1.1.

TC2 = 539.25°F TC2 = (Sum all CPC Ch. TRC2 RAW) / 4 3 Determine density TC1 for RCS Cold Determines TC1, using TC1 and Attachment Leg Temp TC1. 12.

TC1 = 47.4947 4 Determine density TC2 for RCS Cold Determines TC2, using TC2 and Attachment Leg Temp TC2. 12.

TC2 = 47.5545 2009A NRC A-1b rev 0.doc Page 6 of 9

JPM: 2009A NRC A-1.b TITLE: Perform an RCS Flow Rate Determination

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)

NOTE: The Formula for this step: Pc = Pavg (Step 3.1.2) x (46.654 lbm/ft3 ) / TC1 (Step 3.1.4) 5 Calculate Pc, the Compensated Calculates Pc for RCP P001 using TC1 Pump Average P for RCP P001. and the data from Steps 3.1.2 & 3.1.4.

Pc = 100.2 +/- 0.1 psid NOTE: The Formula for this step: Pc = Pavg (Step 3.1.2) x (46.654 lbm/ft3 ) / TC2 (Step 3.1.5) 6 Calculate Pc, the Compensated Calculates Pc for RCP P002 using TC2 Pump Average P for RCP P002. and the data from Steps 3.1.2 & 3.1.5.

Pc = 103.0 +/- 0.1 psid NOTE: The Formula for this step: Pc = Pavg (Step 3.1.2) x (46.654 lbm/ft3 ) / TC1 (Step 3.1.4) 7 Calculate Pc, the Compensated Calculates Pc for RCP P003 using TC1 Pump Average P for RCP P003. and the data from Steps 3.1.2 & 3.1.4.

Pc = 101.2 +/- 0.1 psid NOTE: The Formula for this step: Pc = Pavg (Step 3.1.2) x (46.654 lbm/ft3 ) / TC2 (Step 3.1.5) 8 Calculate Pc, the Compensated Calculates Pc for RCP P004 using TC2 Pump Average P for RCP P004. and the data from Steps 3.1.2 & 3.1.5.

Pc = 102.0 +/- 0.1 psid 2009A NRC A-1b rev 0.doc Page 7 of 9

JPM: 2009A NRC A-1.b TITLE: Perform an RCS Flow Rate Determination

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 9 Determine the flow for RCP P001. Determines the flow for RCP P001 using Pc and Attachment 3.

P001 flow = 112,500 +/- 1000 gpm 10 Determine the flow for RCP P002. Determines the flow for RCP P002 using Pc and Attachment 4.

P002 flow = 108,750 +/- 1000 gpm 11 Determine the flow for RCP P003. Determines the flow for RCP P003 using Pc and Attachment 5.

P003 flow = 114,000 +/- 1000 gpm 12 Determine the flow for RCP P004. Determines the flow for RCP P004 using Pc and Attachment 6.

P004 flow = 112,500 +/- 1000 gpm 2009A NRC A-1b rev 0.doc Page 8 of 9

JPM: 2009A NRC A-1.b TITLE: Perform an RCS Flow Rate Determination

Denotes a CRITICAL STEP NOTE: The Formula for next step: Qt = P001 gpm + P002 gpm + P003 gpm + P004 gpm 13* Calculate the total RCS volumetric flow Calculates the total RCS volumetric flow rate rate (Qt). (Qt) by summing the flow for each RCP.

Qt = 447,750 gpm +/- 5,000 gpm CUE: Another operator will independently verify the calculations.

14* Verify Acceptance Criteria per Verifies Acceptance Criteria of 396,000 Technical Specifications. gpm is met per Technical Specifications.

TERMINATING CUE: Stop Time: ______

This JPM is complete.

2009A NRC A-1b rev 0.doc Page 9 of 9

JPM INFORMATION SHEET JPM NUMBER 2009A A-2 INITIAL PLANT CONDITIONS The Condensate Transfer pump 2MP049 has recently been overhauled and is ready to be aligned for return to service.

Condensate Storage Tank level valve 2HV-3293 is aligned for semi-automatic makeup to T-121.

2MP049 motor has been meggered SAT.

TASK TO BE PERFORMED The Shift Manager directs you to review the Return to Service document and report your finding when complete.

2009A NRC A-2 rev 0.doc Page 1 of 6

JOB PERFORMANCE MEASURE 2009A NRC SRO A-2 SUGGESTED TESTING ENVIRONMENT: PLANT X SIMULATOR X ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATORS NAME:

The operators performance was evaluated against the standards contained in this JPM and is determined to be:

SATISFACTORY:

UNSATISFACTORY:

2009A NRC A-2 rev 0.doc Page 2 of 6

DOCUMENTATION SO-05 NRC SRO JPM A.2 JPM LEVEL: SRO only ESTIMATED TIME TO COMPLETE: 30 minutes TIME CRITICAL JPM: NO CRITICAL TIME: N/A POSITION: SM TASK SYS ID: 182220 TASK DESCRIPTION Manage the control of equipment status.

KA NUMBER: 2.2.13 KA VALUES: RO 3.6 SRO 3.8 10CFR55.45 APPLICABILITY: 13

REFERENCES:

SO123-XX-5, Work authorizations, Revision 22.

SO23-9-5, Condensate Storage and Transfer System, Revision 24.

Condensate Pumps System (Tanks) P&ID #40150D, Revision 44.

Condensate Transfer Pump P&ID #30967, Revision 7.

480V Motor Control Center 2BF P&ID #30139, Revision 17.

480V Motor Control Center 2BV One Line Diagram #30159, Revision 35.

AUTHOR: R. Hampton DATE: 12/18/2008 OPERATIONS REVIEW: DATE:

APPROVED BY: DATE:

2009A NRC A-2 rev 0.doc Page 3 of 6

MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOT BY MODIFIED APPROVAL 0 New 2009A NRC A-2 rev 0.doc Page 4 of 6

SET-UP Prepare a Work Authorization Return to Service WAM that is complete up to the SRO review of the Return to Service WAM sheet. Include errors associated with the Return to Service WAM sheet.

Obtain P&IDs for:

Condensate Storage Transfer Pump #40150D

Condensate Storage Transfer Pump #40150D Obtain One-Line Diagram for:

480 V Load Center Bus 2BV43E

480 V Load Center Bus 2BF-17 The P&IDs should be prepared as follows:

Highlight in BLUE the problem area(s)

Highlight in YELLOW the Cleared line(s)

Highlight in RED the isolation area(s)

The completed Return to Service List should be prepared as follows:

Obtain a blank work document and complete as necessary.

Modify the document to include errors as listed in the JPM body by cutting and pasting.

NOTE: Provide the examinee with a copy of SO123-XX-5, Work Authorizations, the applicable P&IDs and drawings, and the completed Work document.

2009A NRC A-2 rev 0.doc Page 5 of 6

JPM: 2009A NRC A-4 TITLE: Review the Return to Service WAM List of a Completed Work Authorization

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)

NOTE: The following steps may be performed in a sequence other than indicated below.

1 Check the Equipment ID, Checks the Equipment ID, Equipment Start Time: _______

Equipment Description and Work Description and Work Description on the Description. WAR to compare with the information on the Tagging List and the applicable drawings.

2 Check the Work Authorization Checks the Work Authorization Numbers Numbers match for each page of match on each page of the Request.

the Request.

3* Examine the Return to Service Examines the adequacy and accuracy of (RTS) WAM to determine if it is the RTS alignment and identifies:

correct and adequate for system

S21414MU008 should be OPEN.

restoration.

S21414MU077 should be OPEN.

2BVE42E should be CLOSED.

NOTE: SEALED positions are optional. e.g. Locked, capped, flanged, etc.

4 Report to the Shift Manager the Reports to the Shift Manager the incorrect Return to Service incorrect Return to Service alignment alignment and return the WAM and returns the WAM Installation Sheet Installation Sheet without signature. without signature.

TERMINATING CUE: Stop Time: _______

This JPM is complete.

2009A NRC A-2 rev 0.doc Page 6 of 6

JPM INFORMATION SHEET JPM NUMBER 2009A A-3 INITIAL PLANT CONDITIONS You have been directed to perform a valve alignment in the Shutdown Cooling Heat Exchanger 3E004 Room. The task involves uncapping and opening several drain valves and attaching drain hoses directed to the floor drain.

TASK TO BE PERFORMED The Work Control Supervisor directs you to select the appropriate REP for the work to be performed, select the appropriate Survey Map and determine stay time in the general work area.

REP Number ____________

Survey Map Number ____________

Stay Time ____________

2009A NRC A-3 rev 0.doc Page 1 of 6

JOB PERFORMANCE MEASURE SO 10-05 NRC RO/SRO A.3 SUGGESTED TESTING ENVIRONMENT: PLANT X SIMULATOR X ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATORS NAME:

The operators performance was evaluated against the standards contained in this JPM and is determined to be:

SATISFACTORY:

UNSATISFACTORY:

2009A NRC A-3 rev 0.doc Page 2 of 6

DOCUMENTATION SO 10-05 NRC RO/SRO A.3 JPM LEVEL: RO/SRO ESTIMATED TIME TO COMPLETE: 10 minutes TIME CRITICAL JPM: NO CRITICAL TIME: N/A POSITION: ACO TASK SYS ID: N/A TASK DESCRIPTION Determine Stay Time.

KA NUMBER: G2.3.2 KA VALUES: RO 2.5 SRO 2.9 10CFR55.45 APPLICABILITY: 8, 9

REFERENCES:

SO123-VII-20.9, Radiological Surveys, Rev. 6-3 AUTHOR: L. Zilli DATE:

OPERATIONS REVIEW: M. Jones DATE:

APPROVED BY: A. Hagemeyer DATE:

2009A NRC A-3 rev 0.doc Page 3 of 6

MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOT BY MODIFIED APPROVAL 0 New - - -

1 Compared against LRZ 07/25/05 AHH SO123-VII-20.9, Rev 6-3 with minor changes required. Modified JPM with new Survey Maps and REPs. Selected different location for JPM to be performed.

2009A NRC A-3 rev 0.doc Page 4 of 6

SET-UP Provide examinee with a copy of SO123-VII-20.9, Radiological Surveys, six survey maps and three REPs to choose from. Also supply Unit 3 Safety Equipment Building Floor Plan. (SAP & IHPS will NOT be available.)

Note to Examiner: Information regarding methods of posting Radiological conditions on Survey Maps can be found in Section 6.2 of SO123-VII-20.9. Definitions for Survey Map abbreviations and acronyms can be found in Attachment 2 of SO123-VII-20.9.

REPs:

200116 200198 200214 Survey maps:

080210-006 (PAGES 1-4) U3 SB 8 & -15 HP (2/3)1259-1652 HP (2/3)1259-1653 HP (2/3)1259-1678 HP (2/3)1259-1677 080216-004 (PAGES 1-2) U3 SB -2 & -15 HP (2/3)1259-1654 HP (2/3)1259-1680 Plant layouts:

SE.6 U3 SEB -15 6 & 5 3 SE.7 U3 SEB 8 0 Blank survey maps can be obtained via SAP CASE management, nuclear controlled forms. Active REPs and survey maps can be obtained via IHPS.

2009A NRC A-3 rev 0.doc Page 5 of 6

JPM: 2009A NRC A.3 TITLE: Determine Stay Time for Work to be Performed

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)

NOTE: Provide applicant with references listed on the Setup Page.

CUE: Direct examinee to assume all radiation exposure received is in the general area.

1* Determine applicable survey map. LOCATE survey map #080216-004, Page 1 Start Time: _______

of 2 for the task to be performed. (Safety Equipment Building: Train A Shutdown Cooling Heat Exchanger Room 3E-004 Room.)

2* Determine REP that provides coverage LOCATE and REVIEW REP #200198, which of the task performed. allows vent and drain activities.

3* Determine Stay Time in work area. Based upon general area radiation levels in area and required setpoint of alarming dosimeter, DETERMINE that stay time will be 200 minutes based on 30 mR/hr general area radiation and 100 mR dose alarm.

TERMINATING CUE: Stop Time: ________

This JPM is complete.

2009A NRC A-3 rev 0.doc Page 6 of 6

JPM INFORMATION SHEET JPM NUMBER 2009A NRC SRO A-4 INITIAL PLANT CONDITIONS Unit 2 has had a Steam Generator Tube Rupture on E088. The following conditions exist:

U2 reactor is tripped.

All of the U2 control room annunciators were lost 16 minutes ago.

The unit has transitioned to SO23-12-4, STEAM GENERATOR TUBE RUPTURE.

All three charging pumps operating with 128 gpm total flow indicated to RCS.

The following have automatically actuated:

o SIAS o CCAS

RE7874A and B both indicate 65 mr/hr.

RCS leakage is calculated to be 88 gpm.

2HV8419 and 2HV8421 Automatic Dump Valves indicate CLOSE in the control room. Reports from outside the control room indicate no steam coming from 2HV8421 but 2HV8419 is blowing steam heavily.

The Plant Computer System (PCS) is operating normally.

TASK TO BE PERFORMED Classify the event using SO123-VIII-1, Recognition and Classification of Emergencies.

2009A NRC A-4 rev 0.doc Page 1 of 6

JOB PERFORMANCE MEASURE 2009A NRC SRO A-4 SUGGESTED TESTING ENVIRONMENT: PLANT X SIMULATOR X ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATORS NAME:

The operators performance was evaluated against the standards contained in this JPM and is determined to be:

SATISFACTORY:

UNSATISFACTORY:

Examiner:__________________________________ ___________________

Signature Date Comments:

2009A NRC A-4 rev 0.doc Page 2 of 6

DOCUMENTATION 2007 NRC SRO A-4 JPM LEVEL: SRO ESTIMATED TIME TO COMPLETE: 10 minutes TIME CRITICAL JPM: NO CRITICAL TIME: N/A POSITION: SM/EC TASK SYS ID: 192840 TASK DESCRIPTION Classify emergency events requiring emergency plan implementation.

KA NUMBER: 2.4.41 KA VALUES: RO 2.9 SRO 4.6 10CFR55.45 APPLICABILITY: 11

REFERENCES:

SO123-VIII-1, Recognition and Classification of Emergencies, Revision 27.

AUTHOR: R L Hampton DATE:

OPERATIONS REVIEW: DATE:

APPROVED BY: DATE:

2009A NRC A-4 rev 0.doc Page 3 of 6

MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOT BY MODIFIED APPROVAL 0 New 2009A NRC A-4 rev 0.doc Page 4 of 6

SET-UP EXAMINER:

Provide the Examinee with a copy of SO123-VIII-1, Recognition and Classification of Emergencies when identified.

2009A NRC A-4 rev 0.doc Page 5 of 6

JPM: 2009A NRC A-4 TITLE: Classification and Reporting Requirement for an Emergency Event.

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)

NOTE: Provide the Examinee with a copy of SO123-VIII-1, Recognition and Classification of Emergencies.

NOTE: The following steps can be performed in any order.

1 CLASSIFY the Emergency by Event DETERMINE the event to be a Steam Start Time:_______

Code: Generator Tube Rupture.

2 Identify the Event Code using REVIEW EAL descriptions to determine Attachment 1. EVENT CODES the EAL that most closely matches the TABLE and Attachment 2, UNITS plant conditions.

2/3 AND SITE-WIDE EVENT CATEGORY TABS or Attachment 3, UNIT 1 EVENT CATEGORY TABS.

3 Review the notes preceding the REVIEW notes preceding Event applicable Event Category tabs. Categories.

4 Review the notes following the REVIEW notes following the Emergency applicable Emergency Action Action Levels.

Levels.

5* Classify the emergency using the CLASSIFY event as an D4-2.

highest applicable Event Code.

TERMINATING CUE: Stop Time:________

This JPM is complete.

2009A NRC A-4 rev 0.doc Page 6 of 6

JPM INFORMATION SHEET JPM NUMBER 2009A NRC P-1 INITIAL PLANT CONDITIONS You are the Auxiliary Operator.

Unit 2 (Unit 3) is in Mode 3, HOT STANDBY.

The Unit 2 (Unit 3) Atmospheric Dump Valve, 2(3)HV-8419, needs to be tested to prove operability following maintenance.

2(3)HV-8419 is currently closed.

TASK TO BE PERFORMED Manually OPEN the Atmospheric Dump Valve 2(3)HV-8419 per procedure SO23-3-2.18.1, , LOCAL MANUAL OPERATION OF HV-8419 ATMOSPHERIC DUMP VALVE.

2009A NRC P-1 rev 0.doc Page 1 of 10

JOB PERFORMANCE MEASURE 2009A NRC P-1 SUGGESTED TESTING ENVIRONMENT: PLANT X SIMULATOR ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATORS NAME:

The operators performance was evaluated against the standards contained in this JPM and is determined to be:

SATISFACTORY:

UNSATISFACTORY:

Examiner:__________________________________ ___________________

Signature Date Comments:

2009A NRC P-1 rev 0.doc Page 2 of 10

DOCUMENTATION 2009A7 NRC P-1 JPM LEVEL: RO / SRO ESTIMATED TIME TO COMPLETE: 16 minutes TIME CRITICAL JPM: NO CRITICAL TIME: N/A POSITION: PPEO TASK SYS ID: 141183 TASK DESCRIPTION Operate the Atmospheric Dump Valve in Local Manual KA NUMBER: 039-A2.04 KA VALUES: RO 3.4 SRO 3.7 10CFR55.45 APPLICABILITY: 3, 5, 13

REFERENCES:

SO23-3-2.18.1, Atmospheric Dump Valve Operation, Rev 15.

AUTHOR: S Popowski DATE: 11/05/91 OPERATIONS REVIEW: D.J. Turner DATE: 10/02/93 APPROVED BY: M Kirby DATE: 10/14/93 2009A NRC P-1 rev 0.doc Page 3 of 10

MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOT BY MODIFIED APPROVAL 1-4 Compared against SO23-3-2.18.1, JJM 10/27/99 WLL Rev. 9 with no changes required.

Changed equipment designations so that JPM can be performed on either unit. Updated KA designation and changed old task number to VISION SYS ID 1-5 JJM 09/14/00 WLL Compared against SO23-3-2.18.1, TCN 9-1 with no changes required.

Changed cue near end of JPM that directs the operator to realign the isolation valve in the locked open position. Changed note to provide the examinee with the entire procedure rather than attachment 6 only.

1-6 JJM 10/21/02 WLL Compared against SO23-3-2.18.1, Rev 12 with no changes required.

Corrected typos 1-7 Compared against SO23-3-2.18.1, RCW 08/18/04 AHH Rev. 12-1, with no changes required.

1-8 Compared against SO23-3-2.18.1, LRZ 03/10/05 AHH Rev. 12-4, with no changes required.

2009A NRC P-1 rev 0.doc Page 4 of 10

SET-UP EXAMINER:

Provide examinee with a copy of SO23-3-2.18.1, Atmospheric Dump Valve Operation.

On the candidates copy of the cover sheet, circle the unit on which this JPM will be performed.

2009A NRC P-1 rev 0.doc Page 5 of 10

JPM: 2009A NRC P-1 TITLE: Manually OPEN Atmospheric Dump Valve.

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)

NOTE: Provide examinee with a copy of SO23-3-2.18.1.

1 Establish communications between the Indicate the form of communication to be Start Time: _______

Control Room and the Operator at used between the control room operator and HV-8419. the operator at the valve.

NOTE: Communications may be established via radio, telephone (Hear-here booth) or sound powered phone. If sound powered phone is selected, examinee should point out location of jack on west fence.

CUE: Communications have been established.

2* CLOSE S2(3)1301MU1304, HV-8419 Simulate closing S2(3)1301MU1304, Positioner Instrument Air Isolation 2(3)HV-8419 Positioner Instrument Air Valve. Isolation Valve.

CUE: The Valve is CLOSED.

3* CLOSE S2(3)1301MU1328, HV-8419 Simulate closing S2(3)1301MU1328, Positioner Nitrogen Isolation Valve. HV-8419 Positioner Nitrogen Isolation Valve.

CUE: The Valve is CLOSED.

4* OPEN ADV S2(3)1301MU1264, Simulate opening ADV S2(3)1301MU1264, Positioner Equalizing Valve. Positioner Equalizing Valve.

CUE: The valve is OPEN.

5* Engage the Manual Override Shaft, as Simulate unscrewing the clevis from the follows: Manual Override Shaft.

UNSCREW the clevis from the Manual Override Shaft.

CUE: The Clevis is UNSCREWED from the shaft.

2009A NRC P-1 rev 0.doc Page 6 of 10

JPM: 2009A NRC P-1 TITLE: Manually OPEN Atmospheric Dump Valve.

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 6* Engage the Manual Override Shaft, as Simulate turning 2(3)HV-8419 handwheel in follows: the close (clockwise) direction.

TURN the handwheel in the CLOSE (clockwise) POSITION until the clevis detent on the Actuator Shaft is exposed.

CUE: The detent is exposed.

7* Engage the Manual Override Shaft, as Simulate sliding the clevis into the detent.

follows:

When the clevis detent on the Actuator Shaft is exposed below the Manual Override Shaft, then SLIDE the clevis into the detent.

CUE: The clevis is in the detent.

8 OPERATE HV-8419 Handwheel as Simulate informing the Control Room that directed by the NCO or CRS. 2(3)HV-8419 is ready to operate locally.

CUE: No leverage device is needed.

CUE: The Control Room directs opening the Atmospheric Dump Valve 2(3)HV-8419 approximately 5%.

9 OPERATE HV-8419 Handwheel as Simulate turning 2(3)HV-8419 handwheel in directed by the NCO or CRS. the counterclockwise direction.

CUE: The handwheel will not turn. The valve stem did not move.

2009A NRC P-1 rev 0.doc Page 7 of 10

JPM: 2009A NRC P-1 TITLE: Manually OPEN Atmospheric Dump Valve.

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 10 IF HV-8419 cannot be opened Simulate contacting the Control Room to manually due to high P across the inform them that Atmospheric Dump Valve valve seat, then perform the following: 2(3)HV-8419 will not open.

Perform Section 2.2.

CUE: The Control Room directs you to restore the ADV per section 2.2 of this attachment.

11* MANUALLY CLOSE HV-8419. Simulate closing 2(3)HV-8419.

CUE: The valve is CLOSED.

12* ROTATE the Handwheel back and forth Simulate rotating 2(3)HV-8419 handwheel until pressure is relieved from the back and forth.

clevis.

CUE: The pressure is relieved from the clevis.

13* REMOVE the clevis from the detent in Simulate removing the clevis from the detent the Actuator Shaft. in the shaft.

CUE: The clevis is removed.

14* FULLY EXTEND the Manual Override Simulate fully extending the Manual Override Shaft by TURNING the Handwheel Shaft by turning the handle counterclockwise.

Counter-Clockwise until resistance is encountered.

CUE: You feel resistance.

15* When the Manual Override Shaft is fully Simulate screwing the clevis into the Manual extended, then SCREW the clevis fully Override Shaft.

into the Manual Override Shaft.

CUE: The clevis is in the Manual Override Shaft.

2009A NRC P-1 rev 0.doc Page 8 of 10

JPM: 2009A NRC P-1 TITLE: Manually OPEN Atmospheric Dump Valve.

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 16 Contact the control room to verify that Simulate contacting the control room to verify the Atmospheric Dump Valve Position that the Atmospheric Dump Valve Position Controller is adjusted to Zero and the Controller is adjusted to zero, and the Atmospheric Dump Valve Control Atmospheric Dump Valve control switches Switches are selected to close at are selected to close at CR-52, and L-042.

CR-52, and L-042.

CUE: The positioners are at zero. The hand switches are selected to close.

17* CLOSE S2(3)1301MU1264, HV-8419 Simulate closing S2(3)1301MU1264, Controller Equalizing Valve. HV-8419 Controller Equalizing Valve.

CUE: The valve is CLOSED.

18* OPEN S2(3)1301MU1304, HV-8419 Simulate opening S2(3)1301MU1304, Controller Instrument Air Isolation HV-8419 Controller Instrument Air Isolation Valve. Valve.

CUE: The valve is OPEN.

19* OPEN S2(3)1301MU1328, HV-8419 Simulate opening S2(3)1301MU1328, Positioner Nitrogen Isolation Valve. HV-8419 Positioner Nitrogen Isolation Valve.

CUE: The valve is OPEN.

20 Contact the control room and inform Simulate informing the Control Room that the them that Atmospheric Dump Valve Atmospheric Dump Valve is aligned for 2(3)HV-8419 is aligned for remote remote operation.

functional stroke test.

CUE: The Control Room directs you to CLOSE ADV Isolation Valve 2(3)1301MU231 per step 2.2.10.1.

CUE: You have the appropriate Train Key.

2009A NRC P-1 rev 0.doc Page 9 of 10

JPM: 2009A NRC P-1 TITLE: Manually OPEN Atmospheric Dump Valve.

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 21* IF excessive cooldown, OR loss of N2 Simulate unlocking Atmospheric Dump Valve will occur when opening HV-8419, 2(3) HV-8419 Manual Isolation Valve THEN UNLOCK (ESF A Lock) and S2(3)1301MU231.

CLOSE S2(3)1301MU231, HV-8419 Isolation Valve.

CUE: The valve is UNLOCKED.

22* IF excessive cooldown, OR loss of N2 Simulate closing S2(3)1301MU231, HV-8419 will occur when opening HV-8419, Isolation Valve.

THEN UNLOCK (ESF A Lock) and CLOSE S2(3)1301MU231 HV-8419 Isolation Valve CUE: The valve is CLOSED.

CUE: The Atmospheric Dump Valve 2HV-8419 has been successfully opened from the control room.

You are directed to realign ADV isolation Valve MU231 in the LOCKED OPEN position per 2.2.10.7.

23* LOCK OPEN (ESF A Lock) Simulate opening S2(3)1301MU231, S2(3)1301MU231, HV-8419 HV-8419 Atmospheric Dump Valve Isolation Atmospheric Dump Valve Isolation Valve.

Valve.

24 LOCK OPEN (ESF A Lock) Simulate locking S2(3)1301MU231, HV-8419 S2(3)1301MU231, HV-8419 Atmospheric Dump Valve Isolation Valve.

Atmospheric Dump Valve Isolation Valve.

TERMINATING CUE: The valve is Stop Time: ________

This JPM is complete. locked OPEN.

2009A NRC P-1 rev 0.doc Page 10 of 10

JPM INFORMATION SHEET JPM NUMBER 2009A NRC P-2 INITIAL PLANT CONDITIONS The Control Room has been evacuated.

Both Units completed necessary actions prior to evacuation.

You are the Radwaste Operator (Auxiliary Primary Operator).

You have been to the Safe Shutdown Locker, and have obtained all of the required equipment.

TASK TO BE PERFORMED Perform the Unit 2(3) duties of the Radwaste Operator (Auxiliary Primary Operator) following a Control Room evacuation, using SO23-13-2, Shutdown From Outside The Control Room, 0(11), Radwaste Operator Duties (Auxiliary Primary Operator) - Unit 2(3).

2009A NRC P-2 rev 0.doc Page 1 of 7

JOB PERFORMANCE MEASURE 2009A NRC P-2 SUGGESTED TESTING ENVIRONMENT: PLANT X SIMULATOR ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATORS NAME:

The operators performance was evaluated against the standards contained in this JPM and is determined to be:

SATISFACTORY:

UNSATISFACTORY:

Examiner:__________________________________ ___________________

Signature Date Comments:

2009A NRC P-2 rev 0.doc Page 2 of 7

DOCUMENTATION 2009A NRC P-2 JPM LEVEL: RO / SRO ESTIMATED TIME TO COMPLETE: 20 minutes TIME CRITICAL JPM: NO CRITICAL TIME: N/A POSITION: CO, ACO TASK SYS ID: 191625 TASK DESCRIPTION Perform the Radwaste Operator/Auxiliary Reactor Operator (Auxiliary Primary ACO) tasks during a shutdown from outside the control room KA NUMBER: 068-AA1.08 KA VALUES: RO 4.2 SRO 4.2 10CFR55.45 APPLICABILITY: 6, 8, 12

REFERENCES:

SO23-13-2, Shutdown from Outside the Control Room, Rev 11.

AUTHOR: R Whitehouse DATE: 9/20/04 OPERATIONS REVIEW: M. Jones DATE: 9/20/04 APPROVED BY: S. Whitley DATE: 9/20/04 2009A NRC P-2 rev 0.doc Page 3 of 7

MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOT BY MODIFIED APPROVAL 0 New - from J123F: J123F was Unit 3 RCW 8/17/04 NEW only and J122 was dual unit for the same task but not faulted. Converted J123F to J122F to be the faulted version of the dual unit JPM.

1 Removed the requirement to go to the RCW 9/20/04 REV SSD locker. This was a critical step.

1-1 Compared against SO23-13-2, rev HJW 9/14/06 AH 8-1. Updated titles to match procedure.

2009A NRC P-2 rev 0.doc Page 4 of 7

SET-UP EXAMINER:

Provide Examinee with a copy of SO23-13-2, Shutdown from Outside the Control Room, Attachment (10)11.

Be prepared to provide attachment 27, Miscellaneous Cooling Systems Recovery.

2009A NRC P-2 rev 0.doc Page 5 of 7

JPM: 2009A NRC P-2 TITLE: Perform duties of Primary Operator on Shutdown from Outside Control Room

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)

NOTE: Provide the Examinee with a copy of SO23-13-2, Shutdown from Outside the Control Room, Att #10(11).

CUE: You have been to the SSD locker, and have all of the required equipment.

1 Proceed to Radwaste via Control Proceeds to Radwaste via the Control Start Time: ________

Building Central Stairwell and the Building Central Stairwell and the Health Health Physics Control Point. Physics Control Point.

2* At 24' Radwaste: Simulates opening 2(3)HV9235, BORIC ACID OPEN 2(3)HV-9235, BAMU Gravity MAKEUP TANK 2(3)T072 GRAVITY FEED Feed. TO CHARGING PUMP SUCTION ISO VALVE.

CUE: The valve is OPEN.

3* At 24' Radwaste: Simulates opening 2(3)HV9240, BORIC ACID OPEN 2(3)HV-9240, BAMU Gravity MAKEUP TANK 2(3)T071 GRAVITY FEED Feed. TO CHARGING PUMP SUCTION ISO VALVE.

CUE: The valve is OPEN.

4* At 37' Radwaste: Simulates closing 2(3)LV-0227B, VCT CLOSE 2(3)LV-0227B, VCT Outlet OUTLET VALVE in Room 319A(B). A key (RM. 319A(B), Key No. HR) may not be needed for this room depending on present radiological conditions.

CUE: The valve is CLOSED.

5 At 9' Radwaste: Verifies 2(3)LV0227C, RWST TO CHARGING ENSURE CLOSED 2(3)LV-0227C, PUMP SUCTION ISOLATION VALVE is RWST to Charging Pump suction. closed.

CUE: The valve is CLOSED.

2009A NRC P-2 rev 0.doc Page 6 of 7

JPM: 2009A NRC P-2 TITLE: Perform duties of Primary Operator on Shutdown from Outside Control Room

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)

CUE: The U2 CRS directs you to step #13 of this attachment and directs you to perform SO23-13-2 attachment # 27. Another operator has initiated this attachment and the section you are to perform is section 5.0.

6* Open BA-02, MP-001 CCW TV-9144 Simulates positioning breaker 2BA02, MP-001 CCW 2TV-9144 to off.

CUE: 2BA-02 IS OPEN.

7* Open BA-03, MP-003 CCW TV-9154 Simulates positioning breaker 2BA03, MP-003 CCW 2TV-9154 to off.

CUE: 2BA-03 IS OPEN.

8* Open BN-26, MP-004 CCW TV-9164 Simulates positioning breaker 2BN26, MP-004 CCW 2TV-9164 to off.

CUE: 2BN-26 IS OPEN.

9* Open BN-27, MP-002 CCW TV-9174 Simulates positioning breaker 2BN27, MP-002 CCW 2TV-9174 to off.

CUE: 2BN-27 IS OPEN. Another operator will complete the alignment inside containment.

TERMINATING CUE: Stop Time: ________

This JPM is complete.

2009A NRC P-2 rev 0.doc Page 7 of 7

JPM INFORMATION SHEET JPM NUMBER 2009A NRC P-3 INITIAL PLANT CONDITIONS A Station Blackout has occurred on Unit 2.

Offsite power has just been restored to Unit 3.

Buses 3A04 and 3B04 are energized from Off-Site power.

The Unit 2 Crew has determined that Bus 2B04 needs to be energized from Unit 3.

3G003 has been secured.

Declaration of 10CFR50.54(x) and (y) has been made.

MCC BQ is currently aligned to Unit 2.

TASK TO BE PERFORMED Energize 1E 480V bus 2B04 from Unit 3 per SO23-12-11, Attachment 23. Use MCC BQ for the cross-connect. You have been issued an extra interlock key for MCC BQ.

2009A NRC P-3 rev 0.doc Page 1 of 12

JOB PERFORMANCE MEASURE 2009A NRC P-3 SUGGESTED TESTING ENVIRONMENT: PLANT X SIMULATOR ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATORS NAME:

The operators performance was evaluated against the standards contained in this JPM and is determined to be:

SATISFACTORY:

UNSATISFACTORY:

Examiner:__________________________________ ___________________

Signature Date Comments:

2009A NRC P-3 rev 0.doc Page 2 of 12

DOCUMENTATION 2009A NRC P-3 JPM LEVEL: RO / SRO ESTIMATED TIME TO COMPLETE: 13 minutes TIME CRITICAL JPM: NO CRITICAL TIME: N/A POSITION: PEO TASK SYS ID: 188352 TASK DESCRIPTION Energize class 1E 4KV buses from the other unit during response to a station blackout.

KA NUMBER: 055 EA2.03 KA VALUES: RO 3.9 SRO 4.7 10CFR55.45 APPLICABILITY: 6, 12

REFERENCES:

SO23-12-11, EOI Supporting Attachments, Attachment 23, Rev. 6 AUTHOR: H. J. Wurtz DATE: 10/9/07 OPERATIONS REVIEW: DATE:

APPROVED BY: DATE:

2009A NRC P-3 rev 0.doc Page 3 of 12

MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOT BY MODIFIED APPROVAL 0 New - - -

0-1 Compared against SO23-12-11, LRZ 2/24/05 AHH Rev. 2, Attachment 23 with minor changes required.

0-2 Incorporated changes made for 2005B RCW 11/27/05 MRN NRC Exam. Compared against SO23-12-11, Rev. 3, Attachment 23 with no changes required.

1 Compared against SO23-12-11, Rev HJW 10/09/07 N/A

5. Updated steps for procedure changes. Changed some critical steps.

2009A NRC P-3 rev 0.doc Page 4 of 12

SET-UP EXAMINER:

NOTE: Provide the Examinee with a copy of SO23-12-11, EOI Supporting Attachments, 3, Cross Connecting Class 1E 480V Buses between Units.

2009A NRC P-3 rev 0.doc Page 5 of 12

JPM: 2009A NRC P-3 TITLE: Cross tie electrical bus B04 through BQ to other unit.

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)

NOTE: Provide the Examinee with a copy of SO23-12-11, EOI Supporting Attachments, Attachment 23, Cross Connecting Class 1E 480V Buses Between Units.

1 VERIFY BS Contact Control Room to determine BS Start Time: _______

- required by Attachment 9, CONTROL required by attachment 9.

BUILDING VENTILATION EMERGENCY ACTIONS.

CUE: BS is required by attachment 9.

2 VERIFY A04 and B04 on other unit Contact Control Room to verify A04 and B04

- energized. on other unit energized.

CUE: 3A04 and 3B04 are energized from off site power.

3 VERIFY A04 and B04 energized on Contact Control Room to verify A04 and B04 other unit on other unit not energized from diesel

- NOT supplied by Diesel Generator. generators.

CUE: 3A04 and 3B04 are not energized from Diesel Generators.

4* ENERGIZE B04 from energized B04 on Contact Unit 2 Control Room and request that other unit: they open breaker 2A0420 OR simulate OPEN affected B04 supply breakers: opening 2(3)A0420(17) LOADCENTER XFMR 2(3)B04X by turning the handswitch to 4kV - 2A0420 (3A0417)

TRIP.

CUE: Breaker 2(3)A0420(17) is OPEN.

2009A NRC P-3 rev 0.doc Page 6 of 12

JPM: 2009A NRC P-3 TITLE: Cross tie electrical bus B04 through BQ to other unit.

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 5* ENERGIZE B04 from energized B04 on Simulate opening 2(3)B0401 FEEDER FROM other unit: XFMR 2(3)B04X by pressing the TRIP OPEN affected B04 supply breakers: pushbutton.

480V - 2B0401 (3B0401)

CUE: Breaker 2(3)B0401 is OPEN.

6* ENERGIZE B04 from energized B04 on Simulate opening all breakers on 2B04 by other unit: pressing the TRIP pushbuttons.

OPEN all breakers on affected unit B04.

NOTE: Trainee does not have to simulate opening each individual breaker. After first breaker is done, and identifies he will open the remaining breakers, provide the Cue below.

CUE: All breakers on 2B04 are OPEN.

7 ENERGIZE B04 from energized B04 on Verify 2B0417 TRANSFER SWITCH MCC other unit: BQ is open by checking indicating flag in the Ensure both MCC BQ supply breakers breaker window (breaker was opened on OPEN: previous step).

2B0417 NOTE: Breaker is already open due to initial condition of BQ aligned to Unit 2.

CUE: Breaker 2B0417 is OPEN.

2009A NRC P-3 rev 0.doc Page 7 of 12

JPM: 2009A NRC P-3 TITLE: Cross tie electrical bus B04 through BQ to other unit.

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 8 ENERGIZE B04 from energized B04 on Verify 3B0417 TRANSFER SWITCH MCC other unit: BQ is open by checking indicating flag in the Ensure both MCC BQ supply breakers breaker window.

OPEN:

3B0417 CUE: Breaker 3B0417 is OPEN.

NOTE: The next three (3) steps can be done in any order.

9* ENERGIZE B04 from energized B04 on Simulate opening all breakers on MCC 2BE other unit: by pulling the breaker levers down to the OFF OPEN all MCC breakers on: position.

BE (affected unit).

NOTE: Examinee does not have to simulate opening each individual breaker. After trainee simulates opening the first breaker, and identifies he will open the remaining breakers, provide the Cue below.

CUE: All breakers on MCC 2BE are OPEN.

10* ENERGIZE B04 from energized B04 on Simulate opening all breakers on MCC 2BY other unit: by pulling the breaker levers down to the OFF OPEN all MCC breakers on: position.

BY (affected unit).

NOTE: Examinee does not have to simulate opening each individual breaker. After examinee simulates opening the first breaker and identifies they will open the remaining breakers, provide the Cue below.

CUE: All breakers on MCC 2BY are OPEN.

2009A NRC P-3 rev 0.doc Page 8 of 12

JPM: 2009A NRC P-3 TITLE: Cross tie electrical bus B04 through BQ to other unit.

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 11* ENERGIZE B04 from energized B04 on Simulate opening all breakers on MCC by BQ other unit: by pulling the breaker levers down to the OFF OPEN all MCC breakers on: position. (Unit 2 supply breaker BQ-01 is currently closed and does not have to be BQ.

opened.)

NOTE: Examinee does not have to simulate opening each individual breaker. After examinee simulates opening the first breaker and identifies he will open the remaining breakers, provide the Cue below.

CUE: All breakers on MCC 2BQ are OPEN.

12 ENERGIZE B04 from energized B04 on Simulates obtaining 2nd key from NOA.

other unit:

OBTAIN second MCC BQ power supply interlock key.

CUE: You have an additional interlock key.

13 ENERGIZE B04 from energized B04 on Verify BQ-01 FROM 480V LOAD CENTER other unit: BREAKER 2B0417 is closed by observing ENSURE both Unit 2 and Unit 3 power breaker lever up in the ON position.

supply feeders to MCC BQ

- closed.

BQ-01 BQ-02 CUE: Breaker BQ-01 is closed.

2009A NRC P-3 rev 0.doc Page 9 of 12

JPM: 2009A NRC P-3 TITLE: Cross tie electrical bus B04 through BQ to other unit.

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 14* ENERGIZE B04 from energized B04 on Simulate opening the Kirk Key Panel door to other unit: the right of the BQ-02 supply breaker to ENSURE both Unit 2 and Unit 3 power expose the Kirk Key lock.

supply feeders to MCC BQ

- closed.

BQ-01 BQ-02 CUE: The panel door is open and the kirk key lock is exposed.

15* ENERGIZE B04 from energized B04 on Simulate inserting the second Kirk Key into other unit: the BQ-02 Kirk Key lock.

ENSURE both Unit 2 and Unit 3 power supply feeders to MCC BQ

- closed.

BQ-01 BQ-02 CUE: The second kirk key is inserted into the BQ-02 kirk key lock.

16* ENERGIZE B04 from energized B04 on Simulate turning the BQ-02 Kirk Key to unlock other unit: the breaker.

ENSURE both Unit 2 and Unit 3 power supply feeders to MCC BQ

- closed.

BQ-01 BQ-02 CUE: The breaker is unlocked.

2009A NRC P-3 rev 0.doc Page 10 of 12

JPM: 2009A NRC P-3 TITLE: Cross tie electrical bus B04 through BQ to other unit.

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 17* ENERGIZE B04 from energized B04 on Simulate closing the MCC supply breaker other unit: BQ-02 FROM 480V LOAD CENTER ENSURE both Unit 2 and Unit 3 power BREAKER 3B0417 by raising the breaker supply feeders to MCC BQ lever up to the ON position.

- closed.

BQ-01 BQ-02 NOTE: If examinee opened BQ-01 in Step 10, they will have to re-close it here.

If examinee attempts to close BQ-02 without using Kirk Key, tell him, CUE: The breaker didnt CLOSE.

CUE: The breaker is CLOSED.

18* ENERGIZE B04 from energized B04 on Simulate closing 3B0417 by pressing the other unit: CLOSE pushbutton.

ENERGIZE MCC BQ by closing supply breaker from energized B04:

2B0417 OR 3B0417.

CUE: The breaker is CLOSED.

2009A NRC P-3 rev 0.doc Page 11 of 12

JPM: 2009A NRC P-3 TITLE: Cross tie electrical bus B04 through BQ to other unit.

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 19* ENERGIZE B04 from energized B04 on Simulate closing 2B0417 by pressing the other unit: CLOSE pushbutton.

ENERGIZE affected B04 by closing MCC BQ supply breaker:

2B0417 OR 3B0417 CUE: The breaker is CLOSED.

TERMINATING CUE: Stop Time: ________

Another operator will energize loads.

This JPM is complete.

2009A NRC P-3 rev 0.doc Page 12 of 12

JPM INFORMATION SHEET JPM NUMBER 2009A NRC S-1 INITIAL PLANT CONDITIONS You are operating at a power level of 69% and ESI is determined to be negative (-)0.06.

TASK TO BE PERFORMED The CRS directs you to restore ASI to the 70% power level ESI using group 6 CEAs:

SO23-5-1.7, Power Operations, Attachment 6, section 4.0.

SO23-3-2.19, Control Element Drive Mechanism Control System (CEDMCS) Operation, section 6.2 and/or 6.12.

2009A NRC S-1 rev 0.doc Page 1 of 7

JOB PERFORMANCE MEASURE 2009A NRC S-1 SUGGESTED TESTING ENVIRONMENT: PLANT SIMULATOR X ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATORS NAME:

The operators performance was evaluated against the standards contained in this JPM and is determined to be:

SATISFACTORY:

UNSATISFACTORY:

Examiner:__________________________________ ___________________

Signature Date Comments:

2009A NRC S-1 rev 0.doc Page 2 of 7

DOCUMENTATION 2009A NRC S-1 JPM LEVEL: RO/SRO ESTIMATED TIME TO COMPLETE: 10 minutes TIME CRITICAL JPM: NO CRITICAL TIME: N/A POSITION: ACO TASK SYS ID: 188098 TASK DESCRIPTION Monitor and control ASI during steady state operations.

KA NUMBER: 001 A2.19 KA VALUES: RO 3.6 SRO 4.0 10CFR55.45 APPLICABILITY: 2, 4, 5, 6

REFERENCES:

SO23-5-1.7, Power Operations, Rev. 39 SO23-3-2.19, CEDMCS, Rev. 20 SO23-13-13, Misaligned or Immovable Control Element Assembly, Rev.11-2 AUTHOR: L. Zilli DATE: 03/10/05 OPERATIONS REVIEW: M. Jones DATE: 03/18/05 APPROVED BY: A. Hagemeyer DATE: 03/18/05 2009A NRC S-1 rev 0.doc Page 3 of 7

MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOT BY MODIFIED APPROVAL 0 New - - -

0-1 Compared against SO23-5-1.7, Rev. LRZ 03/10/05 AHH 24 with minor changes required.

0-2 Incorporated changes made for 2005A RCW 11/27/05 MRN NRC Exam.

2009A NRC S-1 rev 0.doc Page 4 of 7

SET-UP 2009A NRC JPM Exam Reset to IC #241. Event file is part of IC. No setup installation required.

Malfunction numbers:

RD0103 for CEA # 01 RD2003 for CEA # 20 Ensure the PCS screen at the ACO desk is set up as follows; MAIN MENU NSSS Under COLLSS PRIMARY CEA MONITORING Select CEA GROUP & POSITION Ensure the ASI PCS indication is aligned at the ACO desk (upper scale @ -0.08 and lower scale @ .04).

Ensure the Tc PCS indication is aligned at the ACO desk (upper scale @ 541.8 oF and lower scale @ 537.8 oF)

Provide the examinee with a copy of:

SO23-5-1.7, Power Operations.

SO23-3-2.19, Control Element Drive Mechanism Control System (CEDMCS) Operation.

CAUTION: Leave the simulator in freeze until the examinee is ready to move the CEAs.

Ensure the PCS screen at the ACO desk is set up as follows; MAIN MENU NSSS Under COLLSS PRIMARY CEA MONITORING Select CEA GROUP & POSITION 2009A NRC S-1 rev 0.doc Page 5 of 7

JPM: 2009A NRC S-1 TITLE: Restore ASI to ESI.

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)

NOTE: The applicant should refer to SO23-3-2.19, CEDMCS Operation.

1 VERIFY all CEA Regulating Group Rod VERIFY all Regulating Group Rod Bottom Start Time: _______

Bottom Lamps on the Core Mimic Panel Lamps on the Core Mimic Panel are are EXTINGUISHED. extinguished.

2* POSITION Mode Select switch to MS. PLACE the MODE SELECT Switch to MS.

3* WITHDRAW or INSERT Regulating POSITIONS shim switch to the WITHDRAW Group as required. direction and moves regulating groups in small frequent steps.

4* WITHDRAW or INSERT Regulating OBSERVE PCS screen and/or chart for ASI Group as required. trend. DETERMINE that a second CEA withdrawal is required.

POSITIONS shim switch to the WITHDRAW direction and moves regulating groups in small frequent steps.

5 When Manual Sequential positioning is PLACE Mode Select Switch in OFF when rod completed, then POSITION the Mode withdrawal is complete.

Select Switch to OFF.

NOTE: Steps 1-4 will be repeated as necessary to restore ASI to ESI.

NOTE: Cue the Machine Operator to insert the dropped rod malfunctions once the second CEA movement is initiated by the examinee.

M. O. CUE: When Examiner directs, initiate malfunction to drop CEAs #01 and #20.

NOTE: The following steps represent the alternate path of this JPM.

NOTE: Applicant may immediately trip the reactor or may refer to SO23-13-13, Misaligned Control Element Assembly, to determine appropriate action.

2009A NRC S-1 rev 0.doc Page 6 of 7

JPM: 2009A NRC S-1 TITLE: Restore ASI to ESI.

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 6 VERIFY Special Test Exception 3.1.12 VERIFY Special Test Exception is NOT (Low Power Physics Testing) is NOT invoked.

invoked.

CUE: Special Test Exception is NOT invoked.

7 VERIFY NOT more than one CEA is VERIFY Rod Bottom indication for CEAs #01 misaligned > 7 inches. and #20.

8* ENSURE Reactor - tripped INITIATE a Reactor Trip by DEPRESSING at AND least two manual Reactor trip pushbuttons:

GO TO SO23-12-1. 2HS-9132-2 and 2HS-9132-3 or 2HS-9132-1 and 2HS-9132-4.

TERMINATING CUE: This JPM is complete. Stop Time: ________

2009A NRC S-1 rev 0.doc Page 7 of 7

JPM INFORMATION SHEET JPM NUMBER 2009A NRC S-2 INITIAL PLANT CONDITIONS The following plant conditions exist:

$ A Unit 2 Reactor trip occurred 8 minutes ago.

$ SG pressures are approximately 1000 psia.

$ EFAS-1 and EFAS-2 has actuated.

The Control Room Supervisor (CRS) has directed the ARO to verify proper EFAS-1and EFAS-2 actuation in accordance with SO23-3-2.22, ESFAS System Operation.

TASK TO BE PERFORMED As the ARO, verify proper EFAS-1and EFAS-2 actuation per SO23-3-2.22, ESFAS System Operation, Attachment 13.

2009A NRC S-2 rev 0.doc Page 1 of 8

JOB PERFORMANCE MEASURE 2009A NRC S-2 SUGGESTED TESTING ENVIRONMENT: PLANT SIMULATOR X ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATORS NAME:

The operators performance was evaluated against the standards contained in this JPM and is determined to be:

SATISFACTORY:

UNSATISFACTORY:

Examiner:__________________________________ ___________________

Signature Date Comments:

2009A NRC S-2 rev 0.doc Page 2 of 8

DOCUMENTATION 2009A NRC S-2 JPM LEVEL: RO/SRO ESTIMATED TIME TO COMPLETE: 10 minutes TIME CRITICAL JPM: NO CRITICAL TIME: N/A POSITION: CO TASK SYS ID: 186173 TASK DESCRIPTION Verify the proper operation of the Auxiliary Feedwater System following an EFAS or DEFAS.

KA NUMBER: 061-A3.02 KA VALUES: RO 4.1 SRO 4.2 10CFR55.45 APPLICABILITY: 5, 7

REFERENCES:

SO23-3-2.22, Engineered Safety Features Actuation System, EC 15-5.

AUTHOR: H. J. Wurtz DATE: 09/27/07 OPERATIONS REVIEW: H. Luque DATE: 10/09/07 APPROVED BY: William E. Arbour DATE: 10/18/07 2009A NRC S-2 rev 0.doc Page 3 of 8

MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOT BY MODIFIED APPROVAL 3 Compared against SO23-3-2.22, Rev LRZ 06/30/00 REV 13, TCN 13-3 with minor changes required. Updated reviews.

3-1 Compared to SO23-3-2.22, Rev. 13-4 KM 7-25-01 KR with no changes required.

Updated setup page to use IC 80 which was developed for 2001 JPM exams. This IC might be deleted after the exams.

3-2 Compared against SO23-3-2.22, Rev. RCW 11-05-03 AHH 14-2. Minor modification to Initial Plant Conditions. Modified Simulator Setup.

3-3 Fixed typo on cover page: ESFAS vs. RCW 01-06-04 n/a EFAS.

3-4 Compared against SO23-3-2.22, Rev. RCW 11/03/05 AHH 14-7. Minor modification to Initial Plant Conditions.

4 Compared against SO23-3-2.22, EC HJW 09/27/07 NA 15-5. Updated setup. Minor editorial changes to steps due to rewording in procedure. Revised for signed copy purposes.

2009A NRC S-2 rev 0.doc Page 4 of 8

SET-UP SIMULATOR 2009A use IC-242. Set up file has been run. Event #2 needs to be activated after this IC goes to run.

Perform the following:

$ Insert RP01P to block P141 starting on EFAS

$ Override A394 Red light OFF

$ Override A394 Green light ON

$ Override A394 Red light ON on condition when A394 START PB depressed

$ Override A394 Green light OFF on condition when A394 START PB depressed

$ Trip the plant

$ Trip both MFWPs

$ Wait until EFAS has actuated

$ Run event #2 for fan 2A394 setup INSTRUCTOR/MACHINE OPERATOR NOTES Provide the Examinee with a copy of SO23-3-2.22, ESFAS System Operation, 3, EFAS/DEFAS Actuation Verification, with the Prerequisites completed, step 1.2 should have the first block checked.

NOTE: Maintain the simulator in freeze until the Examinee is ready to start the JPM. This will assist in keeping the level low in the Steam Generators.

2009A NRC S-2 rev 0.doc Page 5 of 8

JPM: 2009A NRC S-2 TITLE: Verify the proper operation of AFW System following an EFAS.

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)

NOTE: Provide the Examinee with a copy of SO23-3-2.22, Attachment 13, EFAS/DEFAS Actuation Verification, with the Prerequisites completed.

NOTE: If SG level is greater than 26%, the AFW valves may be cycling open &/or closed.

1* P-141 Motor Driven AFW Pump Depresses start pushbutton AFWP 2P141 on START. 2HS-4707-1.

2 HV-4713 P-141 Flow Control Valve to Observes OPEN indicating light for AFWP 2E-089 OPEN/CLOSED. 2P141 to SG E089 Discharge Valve on 2HV-4713.

3 HV-4731 S/G E-089 Containment Observes OPEN indicating light for AFW to Isolation Valve OPEN/CLOSED. SG E089 Iso Valve on 2HV-4731.

4 HV-8200 Main Steam to P-140 Isolation Observes OPEN indicating light for Main OPEN. Steam to P-140.

5 HV-4706 P-140 Flow Control Valve to Observes OPEN indicating light for AFWP E-089 OPEN/CLOSED. 2P140 to SG 2E089 Discharge Valve on 2HV-4706.

6 HV-4715 S/G E-089 Containment Observes OPEN indicating light for AFW to Isolation Valve OPEN/CLOSED. SG 2E089 Iso Valve on 2HV-4715.

7 HV-4053 S/G E-089 Blowdown Isolation Observes CLOSE indicating light for SG Valve CLOSED. 2E089 Blowdown Iso Valve on 2HV-4053.

8 HV-4763 P-141 Discharge Bypass Observes CLOSE indicating light for AFWP Valve to E-089 CLOSED. 2P141 to SG 2E089 Discharge Valve Bypass on 2HV-4763.

2009A NRC S-2 rev 0.doc Page 6 of 8

JPM: 2009A NRC S-2 TITLE: Verify the proper operation of AFW System following an EFAS.

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 9 HV-4716 Main Steam Valve to P-140 Observes OPEN indicating light for AFWPT OPEN. 2K007 Steam Inlet Valve on 2HV-4716.

P-504 Motor Driven AFW Pump Observes START indicating light for AFWP 10 START. 2P504 on 2HS-4733-2.

HV-4712 P-504 Flow Control Valve to Observes OPEN indicating light for AFWP 11 E-088 OPEN/CLOSED. 2P504 to SG E088 Discharge Valve on 2HV-4712.

HV-4714 S/G E-088 Containment Observes OPEN indicating light for AFW to 12 Isolation Valve OPEN/CLOSED. SG E088 Iso Valve on 2HV-4714.

HV-8201 Main Steam to P-140 Isolation Observes OPEN indicating light for Main 13 OPEN. Steam to AFWPT 2K007 SG 2E088 Iso Valve on 2HV-8201.

HV-4705 P-140 Flow Control Valve to Observes OPEN indicating light for AFWP 14 E-088 OPEN/CLOSED. 2P140 to SG 2E088 Discharge Valve on 2HV-4705.

HV-4730 S/G 2E-088 Containment Observes OPEN indicating light for AFW to 15 Isolation Valve OPEN/CLOSED. SG 2E-088 Iso Valve on 2HV-4730.

HV-4054 S/G 2E-088 Blowdown Observes CLOSE indicating light for SG 16 Isolation Valve CLOSED. 2E088 Blowdown Iso Valve on 2HV-4054.

HV-4762 P-504 Discharge Bypass Observes CLOSE indicating light for AFWP 17 Valve to E-088 CLOSED. 2P504 to SG 2E088 Discharge Valve Bypass on 2HV-4762.

HV-4716 Steam Supply Valve to P-140 Observes OPEN indicating light for AFWPT 18 OPEN. 2K007 Steam Inlet Valve on 2HV-4716.

A-443 AFW Pump Room Fan START. Observes START indicating light for AFW 19 Pump Area Fan, 2A443, on 2HS-9532-2.

2009A NRC S-2 rev 0.doc Page 7 of 8

JPM: 2009A NRC S-2 TITLE: Verify the proper operation of AFW System following an EFAS.

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)

A-394 AFW Pump Room Fan START. Depresses START pushbutton for AFW 20* Pump Area Fan, 2A394, on 2HS-9581-1.

E-128 Pressurizer Backup Heater on Observes OFF indicating light for Backup 21 CR-50 OFF. Heaters Bank 128 from 2B0402 on 2HS-0100F1.

E-129 Pressurizer Backup Heater on Observes OFF indicating light for Backup 22 CR-50 OFF. Heaters Bank 129 from 2B0602 on 2HS-0100I2.

TERMINATING CUE: Stop Time: ________

This JPM is complete.

2009A NRC S-2 rev 0.doc Page 8 of 8

JPM INFORMATION SHEET JPM NUMBER 2009A NRC S-3 INITIAL PLANT CONDITIONS An ESDE and a LOCA have occurred on Unit 2. 1E 4 kV Vital Bus 2A06 was lost upon plant trip. The Control Room Supervisor has entered SO23-12-9, Functional Recovery.

TASK TO BE PERFORMED The Control Room Supervisor has reviewed the Resource Assessment Charts and directs you to perform SO23-12-9, Functional Recovery Attachment FR-4, PC-1C - Subcooled Pressure Control Recovery Actions (HPSI), Step 9.

2009A NRC S-3 rev 0.doc Page 1 of 9

JOB PERFORMANCE MEASURE 2009A NRC S-3 SUGGESTED TESTING ENVIRONMENT: PLANT SIMULATOR X ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATORS NAME:

The operators performance was evaluated against the standards contained in this JPM and is determined to be:

SATISFACTORY:

UNSATISFACTORY:

Examiner:__________________________________ ___________________

Signature Date Comments:

2009A NRC S-3 rev 0.doc Page 2 of 9

DOCUMENTATION 2009A NRC S-3 JPM LEVEL: RO/SRO ESTIMATED TIME TO COMPLETE: 10 minutes TIME CRITICAL JPM: NO CRITICAL TIME: N/A POSITION: CO TASK SYS ID: 192187 TASK DESCRIPTION Respond to a Loss of Coolant Accident.

KA NUMBER: EA1.3 KA VALUES: RO 3.6 SRO 3.8 10CFR55.45 APPLICABILITY: 6, 7

REFERENCES:

SO23-12-9, Functional Recovery, Attachment FR-4, Recovery - RCS Pressure Control, Rev. 25.

SO23-12-11, EOI Supporting Attachments, FS-7, SI Throttle / Stop Criteria, Rev. 6.

AUTHOR: L. Zilli DATE: 02/15/05 OPERATIONS REVIEW: M. Jones DATE: 03/09/05 APPROVED BY: A. Hagemeyer DATE: 03/09/05 2009A NRC S-3 rev 0.doc Page 3 of 9

MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOT BY MODIFIED APPROVAL 0 New - - -

0-1 Compared against SO23-12-9, Rev. LRZ 09/08/05 AHH 24 with no changes required.

0-2 Compared against SO23-12-9, Rev. LRZ 07/14/06 24 with no changes required.

2009A NRC S-3 rev 0.doc Page 4 of 9

SET-UP MACHINE OPERATOR:

Use IC #243 for 2009A NRC Exam.

Set up file is run for this IC. Event #7 needs to be run when candidate requests p/s close for BY29, HV9420.

2G003 is in Maintenance Lockout. Insert key #78 into maint lockout switch.

Transfer HPSI P-18 to Train B.

HPSI P-17 auto start failure.

RCS leak 75%.

EXAMINER:

Provide the Examinee with a copy of SO23-12-9, Functional Recovery, Attachment FR-4, Recovery - RCS Pressure Control and a copy of FS-7, SI Throttle/Stop Criteria from SO23-12-11, EOI Supporting Attachments.

Have key # 174 ready to give to candidate to operate 2HV-9420 HPSI hot leg iso valve.

2009A NRC S-3 rev 0.doc Page 5 of 9

JPM: 2009A NRC S-3 TITLE: Subcooled Pressure Control Recovery Actions

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)

NOTE: Provide the Examinee with a copy of SO23-12-9, Functional Recovery, Attachment FR-4, Recovery - RCS Pressure Control.

1 VERIFY RWST level VERIFY RWST level greater than 19% by Start Time: _______

- greater than 19%. OBSERVING 2LI-0305-1, -2, -3, or -4 for RWST T006 or 2LI-0301 for RWST T005.

2 INITIATE FS-20, MONITOR RWST INITIATE FS-20, Monitor RWST Level.

Level.

CUE: Another operator will perform FS-20, Monitor RWST Level.

3 ENSURE at least one RWST Outlet VERIFY RWST Outlet Valve OPEN on Train Valve A, HV-9300, RWT 2T005 Outlet ISO Valve

- open: and OBSERVE red OPEN light illuminated.

Train A Train B HV-9300 HV-9301 4 VERIFY PZR pressure VERIFY PZR pressure less than 1500 psia by

- less than 1500 PSIA. OBSERVING any W.R. Pressurizer Pressure instruments on CR-56 or CR-50.

5 VERIFY FS-7, VERIFY SI Throttle/Stop TRANSITION to FS-7, SI Throttle/Stop Criteria - NOT satisfied. Criteria.

6 VERIFY at least one S/G operating: OBSERVE 2PIC-8421-2, SG E089(S)

SBCS available Atmospheric Dump Valve Control in service.

OR ADV available.

7 VERIFY at least one S/G operating - OBSERVE 2P140 in service to Steam Feedwater available. Generator E088 and 2P141 running.

2009A NRC S-3 rev 0.doc Page 6 of 9

JPM: 2009A NRC S-3 TITLE: Subcooled Pressure Control Recovery Actions

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 8 VERIFY PZR level OBSERVE 2LI-0110A, -A1, and/or -A2

-greater than 30% Pressurizer level instruments less than 30%.

AND

-NOT lowering.

9 VERIFY Core Exit Saturation Margin DETERMINE Core Exit Saturation Margin is

-greater than or equal to 20 °F: less than 20 °F.

10 VERIFY Reactor Vessel level DETERMINE Reactor Vessel level is less

-greater than or equal to 100% than 100% Plenum.

(Plenum) 11 VERIFY FS-7, VERIFY SI Throttle/Stop DETERMINE FS-7, SI Throttle/Stop Criteria -

Criteria - NOT satisfied. NOT satisfied.

CUE: Another operator will continue to monitor FS-7, SI Throttle/Stop Criteria.

12 VERIFY at least two HPSI to RCS Cold VERIFY that only HPSI to RCS Cold Leg Leg Injection valves on operating HPSI Injection Valve, 2HV-9327, HDR to Loop 1B train - open: on HPSI Train A is open.

Train A Train B HV-9324 HV-9323 HV-9327 HV-9326 HV-9330 HV-9329 HV-9333 HV-9332 NOTE: The examinee may attempt to open another HPSI to RCS Cold Leg Injection Valve, however, these valves will fail to open.

2009A NRC S-3 rev 0.doc Page 7 of 9

JPM: 2009A NRC S-3 TITLE: Subcooled Pressure Control Recovery Actions

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 13 ESTABLISH HPSI Hot Leg Injection for ESTABLISH HPSI Hot Leg Injection for HPSI operating HPSI trains: Train A.

CLOSE applicable breakers: DIRECT an operator to close Train A breaker Train A Train B BY-29.

BY-29 BZ-39 CUE: Breaker BY-29 is closed.

14* ESTABLISH HPSI Hot Leg Injection for ESTABLISH HPSI Hot Leg Injection for HPSI operating HPSI trains: Train A.

OPEN applicable HPSI to RCS Hot Leg INSERT key #174 and TURN to OPEN on Injection Valves: 2HV-9420, HPSI HDR 1 to Loop 2 Hot Leg Train A Train B ISO Valve and OBSERVE red OPEN light illuminated.

HV-9420 HV-9434 15* ENSURE available HPSI Pumps DEPRESS 2HS-9392-1, HPSI Pump 2P017

-operating. (E) START pushbutton.

16 ENSURE proper system response. VERIFY:

Pump amps of ~ 40 to 50 amps.

17 ENSURE proper system response. VERIFY:

Pressure indication on 2PI-0308, HPSI HDR 1 / P017 Pressure.

18 ENSURE proper system response. VERIFY:

Pressure indication on 2PI-9422, Hot Leg Injection Line Loop 2 Pressure.

2009A NRC S-3 rev 0.doc Page 8 of 9

JPM: 2009A NRC S-3 TITLE: Subcooled Pressure Control Recovery Actions

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 19 ENSURE proper system response. VERIFY:

Flow response on 2FI-0321-1, Cold Leg Injection Line Loop 2 flow.

20 ENSURE proper system response. VERIFY:

Flow response on 2FI-9421-1, Hot Leg Injection Line Loop 2 flow.

TERMINATING CUE: Stop Time:________

This JPM is complete.

2009A NRC S-3 rev 0.doc Page 9 of 9

JPM INFORMATION SHEET JPM NUMBER 2009A NRC S-4 INITIAL PLANT CONDITIONS Unit 2 was operating at 100% power when a Steam Generator Tube Rupture (SGTR) occurred.

Both Steam Generators appear to have tube leakage.

SO23-12-4, Steam Generator Tube Rupture, has been completed through Step 16a.

E088 is isolated.

TASK TO BE PERFORMED Verify isolation of the most affected Steam Generator per SO23-12-4, Steam Generator Tube Rupture, Step 16.

2009A NRC S-4 rev 0.doc Page 1 of 12

JOB PERFORMANCE MEASURE 2009A NRC S-4 SUGGESTED TESTING ENVIRONMENT: PLANT SIMULATOR X ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATORS NAME:

The operators performance was evaluated against the standards contained in this JPM and is determined to be:

SATISFACTORY:

UNSATISFACTORY:

Examiner:__________________________________ ___________________

Signature Date Comments:

2009A NRC S-4 rev 0.doc Page 2 of 12

DOCUMENTATION 2009A NRC S-4 JPM LEVEL: RO/SRO ESTIMATED TIME TO COMPLETE: 25 minutes TIME CRITICAL JPM: NO CRITICAL TIME: N/A POSITION: ACO TASK SYS ID: 186690 TASK DESCRIPTION Respond to a Steam Generator Tube Rupture.

KA NUMBER: 038 EA1.32 KA VALUES: RO 4.6 SRO 4.7 10CFR55.45 APPLICABILITY: 4, 6, 9

REFERENCES:

SO23-12-4, Steam Generator Tube Rupture, Rev. 21.

AUTHOR: R. Whitehouse DATE: 08/18/04 OPERATIONS REVIEW: M. Jones DATE: 08/18/04 APPROVED BY: A. Hagemeyer DATE: 09/10/04 2009A NRC S-4 rev 0.doc Page 3 of 12

MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOT BY MODIFIED APPROVAL 1 Incorporated changes to the procedure RJR 10/07/93 MJK and testing comments. Added critical steps 12, 13, 14, 16, 19, 22, 24, and 25.

1-1 Checked current to Rev 10, will not be SW 12/13/93 N/A updated to Rev 11 this year.

1-2 Compared against SO23-12-4, Rev HJW 01/10/94 N/A 11; renumbered step to be performed in step 1.

2 Upgraded steps 20, 21, 23, & 25 to HJW 02/09/94 MJK require action rather than verify; made steps 20, 21, & 23 critical steps; increased expected time from 15 to 20 minutes based on history.

2-1 Compared against SO23-12-4, Rev. HJW 08/16/96 N/A 13 with minor upgrades to information contained in standards.

2-2 Compared against SO23-12-4, Rev. JJM 10/04/99 WLL

17. Changed verb Acheck@ to Averify@;

inserted new step at beginning to verify one S/G isolated; added ASBCS avail@ to step 7; added Aon isol. S/G@ to step 11; deleted reqmt for >200 gpm AFW and added Aif necessary@ to step

14. Updated KA designation and changed old task number to VISION SYS ID.

4 Compared against SO23-12-4, Rev. KM 09/16/01 REV 17 with the following changes required. Made JPM Steps 14 and 15 not critical since they may not need to be done. Made JPM Step 16 critical.

5 Compared against SO23-12-4, Rev. RCW 08/18/04 REV

19. Major changes. Removed steps no longer in procedure, and added new steps.

2009A NRC S-4 rev 0.doc Page 4 of 12

REV DESCRIPTION OF CHANGE MODIFIED DATE SOT BY MODIFIED APPROVAL 5-1 Modified set-up and Initial Plant RCW 09/10/04 AH Conditions. Inserted previous modification history. Removed step to verify one S/G isolated.

2009A NRC S-4 rev 0.doc Page 5 of 12

SET-UP MACHINE OPERATOR:

SIMULATOR 2009A NRC JPM. Use IC-242. The setup file is activated for this IC. No activations required for setup.

Otherwise, use any at power IC, and perform the following:

$ Insert SG06A = 0.01 (SGTR on E088).

$ Insert SG06B = 0.6 (SGTR on E089).

$ Restore Non Qualified Loads.

$ Take actions to lower Th to less than 530°F.

$ Initial conditions should be about 518°F and 1430 psia.

$ Leave 1 MFP and 3 Condensate Pumps running.

$ Perform the following to isolate the incorrect Steam Generator (E-088):

- Press CLOSE on 2HS-8205, MSIV.

- Press CLOSE on 2HS-4048, MFIV.

- Press OVERRIDE and then CLOSE on 2HS-8201, Steam to P140.

- Press CLOSE on 2HS-4058, S/G Sample Isol.

- Press OVERRIDE and then STOP on 2HS-4733, P504 handswitch.

- Ensure E088 level >40%.

INSTRUCTOR/MACHINE OPERATOR Provide the Examinee with a copy of SO23-12-4, Steam Generator Tube Rupture.

BOP OPERATOR Ensure MSIS setpoint remain low enough to prevent MSIS actuation during the performance of this JPM, by resetting the setpoints at regular intervals.

2009A NRC S-4 rev 0.doc Page 6 of 12

JPM: 2009A NRC S-4 TITLE: Verify Isolation of Most Affected Steam Generator per SO23-12-4.

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)

NOTE: Provide the Examinee with a copy of SO23-12-4, Steam Generator Tube Rupture, when located.

1 VERIFY one S/G - isolated. IDENTIFY E088 isolated and E089 is not Time Start: ________

isolated.

NOTE: The Examinee may go to 16 b RNO column for any of the next four steps.

2 VERIFY: Steam Line radiation level Using DAS or 2L-405, Wide Range

- NOT rising. Monitoring Panel, observes Main Steam Line Radiation Monitors 2RI-7874/75A1 (SG E088 low/high range) and 2RI-7874/75B1 (SG E089 low/high range).

CUE: 2RI-7874B1, Steam Generator E089 low range, Main Steam Line Radiation Monitor, indicates a rising trend.

3 VERIFY: Blowdown radiation level Using DAS or Observes Blowdown Radiation

- NOT rising. Monitors 2RR6753 and 2RR6759.

CUE: 2RIT-6753, SG E089 Blowdown Radiation Monitor, indicates a rising trend.

4 VERIFY: Air Ejector radiation level Using DAS or Observes Air Ejector Radiation

- NOT rising. Monitors 2RT-7818 and 2RY-78701.

5* VERIFY: Available S/G samples Identifies Chemistry results that show E089 is

- high activity in isolated S/G. the most affected SG instead of E088. Enters RNO to restore isolated SG to service and isolate opposite SG.

CUE: Chemistry reports Steam Generator E089 activity is 4.1E-2 Fci/ml and Steam Generator E088 activity is 3.9E-3Fci/ml.

2009A NRC S-4 rev 0.doc Page 7 of 12

JPM: 2009A NRC S-4 TITLE: Verify Isolation of Most Affected Steam Generator per SO23-12-4.

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 6 VERIFY Isolated S/G level trend Observes E088 level indications.

- consistent with plant conditions.

NOTE: The SBCS Interlock Setpoint is 10.0 inches of mercury absolute.

7 VERIFY SBCS - available: Observes Condenser back pressure on Condenser Back pressure Condenser absolute pressure recorder or Condenser pressure instruments 2PI-3202A,

- less than SBCS Interlock Setpoint. 2PI-3383A, or 2PI-3395A.

Determines that condenser vacuum is satisfactory for SBCS operation.

8* OPEN MSIV Bypass on isolated S/G: Depresses OPEN/MODULATE pushbutton E-088 for SG 2E088 Main Steam Iso Valve Bypass, 2HV-8203, and operates SG 2E088/2E089 HV-8203 Main Steam Iso Valve Bypass Control 2HV-8203/2HV-8202 to open 2HV-8203.

9 Lower MSIV P to: Compares 2PI-1023A1 through A4, SG E088 E-088 Pressure, with 2PI-8207, Steam Pressure to MFWPT K006, or 2PI-8214, Steam Pressure HV-8205 85 PSID to MFWPT K005, and verifies differential pressure is #85psid.

10* OPEN MSIV on isolated S/G. Depresses both OPEN pushbuttons on Train A 2HV-8205 and Train B 2HV-8205 for SG E088 Main Steam Iso Valve.

NOTE: It takes approximately 8 minutes for the MSIV to open.

2009A NRC S-4 rev 0.doc Page 8 of 12

JPM: 2009A NRC S-4 TITLE: Verify Isolation of Most Affected Steam Generator per SO23-12-4.

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 11 ESTABLISH RCS temperature control Establishes RCS temperature control with with SBCS on isolated S/G. SBCS by adjusting the controller(s) to throttle 2HV-8423 and/or 2HV-8425 as required.

NOTE: The canidate may start either P140 or P504 to supply feedwater to E088. P140 requires both HV-4716 and HV-8201 to be open.

CUE: The CRS authorizes starting either P140 or P504 to feed E088 12 ENSURE at least one associated AFW START 2P-504 or OPEN 2HV-8201 main Pump - operating. steam to 2P-140.

13 OVERRIDE and OPEN AFW Pump Depresses OVERRIDE and then OPEN for Discharge Bypass valve to 35% open: 2HV-4762.

P-504 - HV-4762 P-141 - HV-4763 14 MAINTAIN reduced AFW flow for 5 Monitors AFW flow to E088 by observing minutes. 2FI-4720-2 on CR52.

CUE: 5 minutes have elapsed.

2009A NRC S-4 rev 0.doc Page 9 of 12

JPM: 2009A NRC S-4 TITLE: Verify Isolation of Most Affected Steam Generator per SO23-12-4.

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 15 VERIFY for recovered S/G: Verifies SG E-088 level >40% NR by:

Level - greater than 40% NR Observing 2LI-1123-1,-2,-3 and A4, SG E088 Down comer Level, and verifies feedwater AND available.

Feedwater available.

OR Level

- trending to between 40% NR and 80% NR.

CUE: Steam Generator E088 level is greater than 40% narrow range level.

16 ENSURE all valves to other S/G Transitions to step 9.

- closed per step 9.

17* CLOSE/STOP the following Depresses both CLOSE pushbuttons on Train components for most affected S/G: A 2HV-8204 and/or Train B 2HV-8204, SG MSIV 2E089 Main Steam Iso Valve, and verifies HV-8204 2HV-8204 closed at CR52 or CR57.

18 CLOSE/STOP the following Verifies green closed indicating light on components for most affected S/G: 2HV-8202, SG 2E089 Main Steam Iso Valve MSIV Bypass Bypass.

HV-8202 19 CLOSE/STOP the following Verifies green closed indicating light on components for most affected S/G: 2HV-8421, SG 2E089 Atmospheric Dump ADV Valve.

HV-8421 2009A NRC S-4 rev 0.doc Page 10 of 12

JPM: 2009A NRC S-4 TITLE: Verify Isolation of Most Affected Steam Generator per SO23-12-4.

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 20* CLOSE/STOP the following Depresses both CLOSE pushbuttons on Train components for most affected S/G: A 2HV-4052 and/or Train B 2HV-4052, FW to MFIV SG 2E089 Iso Valve, and verifies 2HV-4052 HV-4052. closed at CR52 or CR57.

21 CLOSE/STOP the following Verifies 2HV-4731, AFW to SG 2E089 Iso components for most affected S/G: Valve, is CLOSED.

AFW valves HV-4731.

22 CLOSE/STOP the following Verifies 2HV-4715, AFW to SG 2E089 Iso components for most affected S/G: Valve, is CLOSED.

AFW valves HV-4715.

23* CLOSE/STOP the following Depresses OVERRIDE and CLOSE components for most affected S/G: pushbuttons for 2HV-8200, Main STM to Steam to AFW P-140 AFWPT 2K007 SG 2E089 Iso Valve.

HV-8200.

24 CLOSE/STOP the following Verifies 2HV-4053-2, SG 2E089 Blowdown components for most affected S/G: Iso Valve, is closed.

S/G Blowdown Isolation HV-4053.

25* CLOSE/STOP the following Depresses CLOSE for 2HV-4057, SG 2E089 components for most affected S/G: Water Sample Iso Valve.

S/G Water Sample Isolation HV-4057 2009A NRC S-4 rev 0.doc Page 11 of 12

JPM: 2009A NRC S-4 TITLE: Verify Isolation of Most Affected Steam Generator per SO23-12-4.

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 26* CLOSE/STOP the following Depresses OVERRIDE and STOP Time Stop: _______

components for most affected S/G: pushbuttons for 2HS-4707-1, AFWP 2P141.

Electric AFW Pump P-141. TERMINATING CUE:

This JPM is complete.

2009A NRC S-4 rev 0.doc Page 12 of 12

JPM INFORMATION SHEET JPM NUMBER 2009A NRC S-5 INITIAL PLANT CONDITIONS Unit 2 was operating at 100% power when a Steam Line Break occurred inside Containment.

Containment Spray Actuation System (CSAS) failed to automatically actuate. Up to this point, all attempts to manually actuate CSAS have been unsuccessful. Containment pressure is rising.

TASK TO BE PERFORMED The Control Room Supervisor directs you to perform Floating Step 12, Monitor Containment Pressure, of SO23-12-11, EOI Supporting Attachments.

2009A NRC S-5 rev 0.doc Page 1 of 9

JOB PERFORMANCE MEASURE 2009A NRC S-5 SUGGESTED TESTING ENVIRONMENT: PLANT SIMULATOR X ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATORS NAME:

The operators performance was evaluated against the standards contained in this JPM and is determined to be:

SATISFACTORY:

UNSATISFACTORY:

Examiner:__________________________________ ___________________

Signature Date Comments:

2009A NRC S-5 rev 0.doc Page 2 of 9

DOCUMENTATION 2009A NRC S-5 JPM LEVEL: RO/SRO ESTIMATED TIME TO COMPLETE: 10 minutes TIME CRITICAL JPM: NO CRITICAL TIME: N/A POSITION: CO TASK SYS ID: 184570 TASK DESCRIPTION Initiate Containment Temperature and Pressure Control Recovery by CSAS.

KA NUMBER: 009 EA1.07 KA VALUES: RO 3.7 SRO 3.9 10CFR55.45 APPLICABILITY: 5, 6

REFERENCES:

SO23-12-11, EOI Supporting Attachments, FS-12, Monitor Containment Pressure, Rev. 6.

SO23-3-2.22, Engineered safety Features Actuation System Operation, Rev. 15-5 AUTHOR: L. Zilli DATE: 02/15/05 OPERATIONS REVIEW: M. Jones DATE: 03/09/05 APPROVED BY: A. Hagemeyer DATE: 03/09/05 2009A NRC S-5 rev 0.doc Page 3 of 9

MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOT BY MODIFIED APPROVAL 1 Reviewed SO23-12-5, Rev. 16 and LRZ 07/05/00 WLL modified as required.

1-1 Compared against SO23-12-5, Rev. LRZ 08/29/01 WLL 16 with no changes required.

2 Revised to reflect new procedure and LRZ 02/15/05 REV Floating Step number SO23-12-11, EOI Supporting Attachments, Rev. 2, Floating Step 12. Added steps required by procedure revision. New VISION ID.

2-1 Compared against SO23-12-11, EOI LRZ 07/27/05 AHH Supporting Attachments, Rev. 3, with no changes required.

2-2 Compared against SO23-12-11, EOI RCW 05/09/07 Supporting Attachments, Rev. 5, with no changes required.

2009A NRC S-5 rev 0.doc Page 4 of 9

SET-UP MACHINE OPERATOR:

2009A NRC JPM. Use IC #245. Set up file has been activated. No other events need to be activated.

Run the Setup to disable CSAS automatic and manual actuation of Containment Spray and Containment Spray Pump P012 to start.

Otherwise, use IC-20, and perform the following instructions to set up the required conditions:

Insert the CSAS and P012 failures prior to initiating the steam leak.

Insert the malfunction for a Steam Line Break inside Containment and allow the Simulator to run until Containment pressure reaches at least 15 psig. Choose the severity such that pressure is rising slowly then FREEZE the simulator.

MS03A = 10% for ~1 minute then reduce to 0.9% (Steam Line Break Inside Ctmt)

RP01M = Failure to Start (CS Pump P012)

On Rose Schematic page for CSAS (RPL104), override the following = TRUE o RP_CSAS_MI1_FAILFAILON o RP_CSAS_MI2_FAILFAILON o RP_CSAS_MI3_FAILFAILON o RP_CSAS_MI4_FAILFAILON o RP_CSAS_SSR1_FAILFAILON o RP_CSAS_SSR2_FAILFAILON o RP_CSAS_SSR3_FAILFAILON o RP_CSAS_SSR4_FAILFAILON EXAMINER:

Provide the Examinee with a copy of SO23-12-11, EOI Supporting Attachments, Floating Step 12, Monitor Containment Pressure, with box checked for 12-5.

NOTE: Ensure DAS alarms are reset.

2009A NRC S-5 rev 0.doc Page 5 of 9

JPM: 2009A NRC S-5 TITLE: Initiate Containment Temperature and Pressure Control Recovery by CSAS.

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)

NOTE: Provide the Examinee with a copy of SO23-12-11, EOI Supporting Attachments, Floating Step 12, Monitor Containment Pressure.

NOTE: Ensure the DAS alarms are reset.

1 VERIFY Containment pressure VERIFY Containment Pressure indications Time Start: _______

- less than 3.4 PSIG greater than 3.4 psig and enters the RNO:

Narrow Range: 2PI-0351-1, 2, 3, 4

Wide Range: 2PI-0352-1, 2, 3, 4 2 ENSURE the following - actuated: VERIFY SIAS actuated by observing the following annunciators:

SIAS

57A01 SIAS TRAIN A ACTUATION

57B01 SIAS TRAIN B ACTUATION.

Note: The following steps represent the alternate path for this JPM.

3* ENSURE the following - actuated: Recognizes that Containment Spray Pump SIAS 2P-012 is not running.

START Containment Spray Pump 2P-012 by depressing the START pushbutton, 2HS-9395-1.

4 ENSURE the following - actuated: VERIFY CCAS actuated by observing the CCAS following annunciators:

57A07 CCAS TRAIN A ACTUATION

57B07 CCAS TRAIN B ACTUATION.

5 ENSURE the following - actuated: VERIFY CRIS actuated by observing CRIS annunciator 60B07 CRIS ACTUATION.

2009A NRC S-5 rev 0.doc Page 6 of 9

JPM: 2009A NRC S-5 TITLE: Initiate Containment Temperature and Pressure Control Recovery by CSAS.

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 6 ENSURE the following - actuated: VERIFY CIAS actuated by observing the following indications:

CIAS

57A02 CIAS TRAIN A ACTUATION

57A02 CIAS TRAIN B ACTUATION

CFMS page 342.

CUE: (If CFMS page 342 and/or343 are accessed, give the following information) All CIAS valves are closed.

7 VERIFY Containment Area Radiation VERIFY Containment Area Radiation Monitors Monitors are not alarming or trending to alarm

- NOT alarming or trending to alarm. using DAS or in hallway.

2RISH-7845

2RISH-7848 8 VERIFY Containment High Range Area VERIFY Containment Area Radiation Radiation Monitors reading Monitors are not alarming or trending to alarm

- less than 40R/HR. using DAS or in hallway.

2R-7820-1

2R-7820-2 9 VERIFY Containment pressure VERIFY Containment Pressure indications

- less than 14 PSIG. greater than 14 psig and enters the RNO:

NR: 2PI-0351-1, 2, 3, or 4

WR: 2PI-0352-1, 2, 3, or 4 2009A NRC S-5 rev 0.doc Page 7 of 9

JPM: 2009A NRC S-5 TITLE: Initiate Containment Temperature and Pressure Control Recovery by CSAS.

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 10 ENSURE CSAS - actuated. OBSERVE CSAS not actuated:

57A03 CSAS TRAIN A ACTUATION 57B03 CSAS TRAIN B ACTUATION

2HV-9367, Containment Spray Header 1 Control Valve, did not open

2HV-9368, Containment Spray Header 2 Control Valve, did not open ATTEMPT to actuate CSAS by DEPRESSING at least either pair of CSAS pushbuttons, 2HS-9139-1 & 2, or 3 & 4.

CUE: If asked; An ARO has been sent to L-034 and L-035 and CSAS actuation has been unsuccessful NOTE: The candidate may use SO23-3-2.22, ESFAS OPERATION, for the following steps.

11* ENSURE P-012 Containment Spray VERIFY Containment Spray Pump P-012 has Pump START. started by observing:

Red START light illuminated on 2HS-9396-2.

Pump amps at a normal no flow value of about 25 amps on 2HS-9396-2.

Discharge pressure is approximately 250 psig on 2PI-0303-2.

12* ENSURE HV-9367 Containment Spray OPEN 2HV-9367, CNTMT Spray Hdr No 1 Header Isolation OPEN. Control Valve, by DEPRESSING and HOLDING the JOG OPEN pushbutton and observing the red JOG OPEN light illuminates and the green JOG CLOSED light extinguishes.

2009A NRC S-5 rev 0.doc Page 8 of 9

JPM: 2009A NRC S-5 TITLE: Initiate Containment Temperature and Pressure Control Recovery by CSAS.

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 13* ENSURE HV-6501 SDC HX E-004 OPEN 2HV-6501, SDC HX E-004 CCW CCW Isolation OPEN. Isolation valve.

14 ENSURE P-013 Containment Spray VERIFY Containment Spray Pump P-013 has Pump START. started by observing:

Red START light illuminated on 2HS-9396-2.

Pump amps at a normal no flow value of about 25 amps on 2HS-9396-2.

Discharge pressure is approximately 250 psig on 2PI-0303-2.

15* ENSURE HV-9368 Containment Spray OPEN 2HV-9368, CNTMT Spray Hdr No 2 Header Isolation OPEN. Control Valve by DEPRESSING and HOLDING the JOG OPEN pushbutton and observing the red JOG OPEN light illuminates and the green JOG CLOSED light extinguishes.

16* ENSURE HV-6500 SDC HX E-003 OPEN 2HV-6500, SDC HX E-003 CCW CCW Isolation OPEN. Isolation valve.

17* CLOSE CCW to/from Letdown Heat DEPRESS the CLOSE pushbutton for Exchanger Valves for Train A and 2HV-6293B/A, CCW CLA LTDN HX 2E062 Train A. Supply/Return Valve.

18 CLOSE CCW to/from Letdown Heat VERIFY CLOSED 2HV-6522B/A, CCW CLA Exchanger Valves for Train A and LTDN HX 2E062 Supply/Return Valve.

Train B.

TERMINATING CUE: Stop Time: ________

This JPM is complete.

2009A NRC S-5 rev 0.doc Page 9 of 9

JPM INFORMATION SHEET JPM NUMBER 2009A NRC S-6 INITIAL PLANT CONDITIONS Both units have experienced a loss of off-site power. Both of the Emergency Diesel Generators for Unit 2 are not operating due to mechanical problems. Both of the Emergency Diesel Generators for Unit 3 are functioning normally. The Shift Manager has directed the Unit 2 Control Room Supervisor to re-energize bus 2A06 from the Unit 3 Diesel Generator, 3G003.

The Shift Manager has declared 10 CFR 50.54(x) and 10 CFR 50.54(y) and has given his approval to implement the attachment for restoring power to bus 2A06. The STA will notify the NRC within one hour regarding actions per this attachment.

TASK TO BE PERFORMED The Unit 2 CRS directs you to perform the actions of SO23-12-11, Attachment 24, Supplying 1E 4kV Bus with Opposite Unit Diesel, starting at step 12.

2009A NRC S-6 rev 0.doc Page 1 of 14

JOB PERFORMANCE MEASURE 2009A NRC S-6 SUGGESTED TESTING ENVIRONMENT: PLANT SIMULATOR X ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATORS NAME:

The operators performance was evaluated against the standards contained in this JPM and is determined to be:

SATISFACTORY:

UNSATISFACTORY:

Examiner:__________________________________ ___________________

Signature Date Comments:

2009A NRC S-6 rev 0.doc Page 2 of 14

DOCUMENTATION 2009A NRC S-6 JPM LEVEL: RO/SRO ESTIMATED TIME TO COMPLETE: 12 minutes TIME CRITICAL JPM: NO CRITICAL TIME: N/A POSITION: ACO TASK SYS ID: 188352 TASK DESCRIPTION Respond to a Station Blackout.

KA NUMBER: 055-EA2.03 KA VALUES: RO 3.9 SRO 4.7 10CFR55.45 APPLICABILITY: 6, 8

REFERENCES:

SO23-12-11, EOI Supporting Attachments, Attachment 24, Rev. 6.

AUTHOR: DATE:

OPERATIONS REVIEW: DATE:

APPROVED BY: DATE:

2009A NRC S-6 rev 0.doc Page 3 of 14

MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOT BY MODIFIED APPROVAL 0 NEW 1 Compared against SO23-12-11, Rev 5 RCW 05/08/07 REV with no changes required. Moved CRS direction from INITIAL PLANT CONDITIONS to TASK TO BE PERFORMED. Updated DOCUMENTATION page. Added detail to SETUP page. Made minor enhancements to the CUE prior to JPM step 5. Made major enhancements to most steps, adding proper nomenclature and standardizing format. Made JPM step 5 a Critical Step due to the requirement to have the 50.54X switches in the 50.54X position to be able to proceed with the task assigned.

2009A NRC S-6 rev 0.doc Page 4 of 14

SET-UP MACHINE OPERATOR:

Use IC #246 for the 2009A NRC JPM Exam. Ensure the Maintenance Lockout switches for both Unit 2 Emergency Diesel Generators (2G002 and 2G003) are in the MAINT position (Keys 77 and 78).

Use any full power IC with CCW in a Train A alignment.

Insert malfunctions EG08A and EG08B to disable both Emergency Diesel Generators, and place both diesels in Maintenance Lockout using Keys 77 and 78.

Insert malfunction TU08, and 5 seconds later PG24, to trip the plant and cause a loss of Edison Grid.

Insert malfunction PG57 SDG&E switchyard breakers open.

5 minutes after the trip close both MSIVs.

Place the ADVs in AUTO and OPEN/MODULATE.

Ensure 3A06 is being supplied by 3G003.

Ensure both Bus Tie switches are in AUTO.

Align NCL & LD HX from train A to train B

Ensure SWC bearing seal H2O and pump disch vlvs train A closed and train B are open.

Allow the plant to stabilize for about 10 minutes.

When the examinee calls for the outside operator to position the 50.54X switches, place all 50.54X switches in the 50.54X position using remote functions EG62A, EG62B, EG62C, and EG62D.

EXAMINER:

Provide the Examinee with a copy of SO23-12-11, Attachment 24, Supplying 1E 4KV Bus with Opposite Unit Diesel.

2009A NRC S-6 rev 0.doc Page 5 of 14

JPM: 2009A NRC S-6 TITLE: Perform the Actions of Supplying 1E 4kV Bus with Opposite Units Diesel

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)

NOTE: Provide examinee with a copy of SO23-12-11, Attachment 24.

1 VERIFY opposite unit 1E 4kV bus A06 Observes the following breaker status: Start Time: _______

- energized by Diesel Generator.

Green Trip light illuminated on 3HS-1637-2, Res Aux XFMR 3XR2 Fdr Breaker 3A0618.

Green Trip light illuminated on 3HS-1638-2, Unit Aux XFMR 3XU1 Fdr Breaker 3A0616.

Green Trip light illuminated on 3HS-1639A2, Bus Tie 3A06 to 2A06 Fdr Breaker 3A0603.

Red Close light illuminated on 3HS-1642-2, Generator Breaker 3A0613.

2 ENSURE 1E 4kV Bus Tie breaker DEPRESS the manual pushbutton and AUTO/MANUAL transfer switches to observe the blue backlight illuminated;

- selected to MANUAL:

Blue Manual light illuminated on 2A0619 (2HS-1639B2) 2HS-1639B2, Bus Tie 2A06 to 3A06 Fdr Breaker 2A0619 Selector.

3* ENSURE 1E 4kV Bus Tie breaker DEPRESS the manual pushbutton and AUTO/MANUAL transfer switches to observe the blue backlight illuminated;

- selected to MANUAL:

Blue Manual light illuminated on 3A0603 (3HS-1639B2) 3HS-1639B2, Bus Tie 3A06 to 2A06 Fdr Breaker 3A0619 Selector.

2009A NRC S-6 rev 0.doc Page 6 of 14

JPM: 2009A NRC S-6 TITLE: Perform the Actions of Supplying 1E 4kV Bus with Opposite Units Diesel

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 4 ENSURE 1E 4kV Bus Tie breakers Observes the following breaker status:

- open:

Green Trip light illuminated on 2A0619 3HS-1639A2, Bus Tie 2A06 to 3A06 Fdr AND Breaker 2A0619.

3A0603

Green Trip light illuminated on 3HS-1639A2, Bus Tie 3A06 to 2A06 Fdr Breaker 3A0603.

5 ENSURE affected unit G003 Diesel Observes 2HS1770-2, Maintenance Lockout Generator keyswitch for 2G003, is in MAINT.

- selected to MAINTENANCE LOCKOUT.

6* INITIATE Diesel Generator Cross-Tie Calls an outside operator to perform Step 13.

Permissive switch alignment on 50 Elevation:

On Affected Unit

On Opposite Unit CUE: An outside operator has been dispatched to the 50' elevation to perform step 13. He reports that Step 13 is complete, and there are no relay flags on any of the 2A06 feeder breakers.

MO: Position all Diesel Generator Cross-Tie Permissive Switches on BOTH units to the 50.54X position with EG62A, EG62B, EG62C, and EG62D.

7 VERIFY opposite unit Diesel Generator Observes load on 3JI-1651A2, Diesel Gen G003 loading - less than 3.4 MW. 3G003 Watts, indicates about 0.91 MW.

8 MAINTAIN loads on opposite unit 1E CONTACTS the Unit 3 CRS to verify 3A06 4kV bus A06 - stable. loads will be maintained stable.

CUE: The Unit 3 CRS reports that 3A06 electrical loads will be maintained stable.

2009A NRC S-6 rev 0.doc Page 7 of 14

JPM: 2009A NRC S-6 TITLE: Perform the Actions of Supplying 1E 4kV Bus with Opposite Units Diesel

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 9 VERIFY affected unit 1E 4kV bus A06 Observes voltage on 2EI-1641-2, 4.16 kV Bus

- NOT energized. 2A06 Volts, indicates zero.

VERIFY affected unit Observes the following alarms are reset:

10 over current/ground alarms - reset:

63C15 2A06 SUPPLY BKR 2A0616 OC

63C15 SUPPLY BKR A0616 OC

63C25 2A06 SUPPLY BKR 2A0618 OC

63C25 SUPPLY BKR A0618 OC 11 VERIFY 1E DC bus voltages: Observes voltage on 2EI-1757-2, 125 VDC 2D2 - greater than 108 VDC Bus 2D2 Volts, indicates about 119 volts.

AND 3D2 - greater than 108 VDC CUE: The 32 Watch reports that 3D2 voltage is 131 volts and stable.

2009A NRC S-6 rev 0.doc Page 8 of 14

JPM: 2009A NRC S-6 TITLE: Perform the Actions of Supplying 1E 4kV Bus with Opposite Units Diesel

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 12 ON AFFECTED unit: Observes the following breaker status:

ENSURE 1E 4kV bus A06 supply

No lights illuminated on 2HS-1638-2, Unit breakers (3) - open: Aux XFMR 2XU1 FDR Breaker 2A0616.

A0616 - Unit Aux XFMR

Green Trip light illuminated on A0618 - Reserve Aux XFMR 2HS-1637-2, Res Aux XFMR 2XR2 FDR A0613 - Diesel Generator Breaker 2A0618.

Green Trip light illuminated on 2HS-1642-2, Generator Breaker 2A0613.

13 ENSURE 1E 4kV bus A06 Bus Tie Observes the following breaker status:

Breakers (2) - open:

Green Trip light illuminated on 2A0619 - A06 Bus Tie 2HS-1639A2, Bus Tie 2A06 to 3A06 FDR 3A0603 - A06 Bus Tie Breaker 2A0619.

Green Trip light illuminated on 3HS-1639A2, Bus Tie 3A06 to 2A06 FDR Breaker 3A0603.

2009A NRC S-6 rev 0.doc Page 9 of 14

JPM: 2009A NRC S-6 TITLE: Perform the Actions of Supplying 1E 4kV Bus with Opposite Units Diesel

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 14 ENSURE affected unit 1E 4kV bus A06 Observes the following breaker status:

load breakers - open:

Green Trip light illuminated on 2/3HS-9895-2,

Emergency Chiller Emer Chld Water Chiller E335 (N) Unit 2 Ctl

Containment Spray Pump

Green Trip light illuminated on 2HS-9396-2,

High Pressure Safety Injection Containment Spray Pump 2P013 (NW)

Pumps

No lights illuminated on 2HS-9393-2,

Low Pressure Safety Injection Pump HPSI Pump 2P018 (SW)

Auxiliary Feedwater Pump

Green Trip light illuminated on 2HS-9394-2, HPSI Pump 2P019 (N)

Component Cooling Water Pumps

Green Trip light illuminated on 2HS-9391-2,

Salt Water Cooling Pumps LPSI Pump 2P016 (N)

Green Trip light illuminated on 2HS-4733-2, AFWP 2P504

No lights illuminated on 2HS-6320-2, CCW Pump 2P025 (C)

Green Trip light illuminated on 2HS-6324-2, CCW Pump 2P026 (W)

No lights illuminated on 2HS-6381-2, Salt Water Pump 2P113 (CW)

Green Trip light illuminated on 2HS-6383-2, Salt Water Pump 2P114 (E) Unit 3 Intake 15 VERIFY Train B Diesel Generator Calls outside operator to verify that the Diesel Cross-Tie Permissive switches on both Generator Cross-Tie Permissive Switches on units are in the 50.54X position. both units are in the 50.54X position.

MO: Position all Diesel Generator Cross-Tie Permissive Switches on BOTH units to the 50.54X position with EG62A, EG62B, EG62C, and EG62D if not done yet.

2009A NRC S-6 rev 0.doc Page 10 of 14

JPM: 2009A NRC S-6 TITLE: Perform the Actions of Supplying 1E 4kV Bus with Opposite Units Diesel

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)

CUE: The outside operator reports that all Diesel Generator Cross-Tie Permissive Switches on BOTH units are in the 50.54X position.

NOTE: Of the following steps, all are critical to closing the breaker, with the exception of the last two steps (depressing the SYNC pushbutton and placing the keyswitch to OFF).

16* CLOSE opposite unit Bus Tie breaker: Closes 3A0603 using the following sequence:

3A0603 (2A0619).

Places 3HS-1627-2, Train B Sync Ckt Control, keyswitch to ON.

Depresses the Sync pushbutton on 3HS-1639A2, Bus Tie 3A06 to 2A06 Fdr Breaker 3A0603.

Depresses the Close pushbutton on 3HS-1639A2, Bus Tie 3A06 to 2A06 Fdr Breaker 3A0603.

Depresses the Sync pushbutton on 3HS-1639A2, Bus Tie 3A06 to 2A06 Fdr Breaker 3A0603.

Places 3HS-1627-2, Train B Sync Ckt Control, keyswitch to OFF.

17 VERIFY opposite unit Diesel Generator Observes that the red Closed light remains G003 output breaker remains - closed. illuminated on 3HS-1642-2, Generator Breaker 3A0613.

NOTE: Of the following steps, all are critical to closing the breaker, with the exception of the last two steps (depressing the SYNC pushbutton and placing the keyswitch to OFF).

2009A NRC S-6 rev 0.doc Page 11 of 14

JPM: 2009A NRC S-6 TITLE: Perform the Actions of Supplying 1E 4kV Bus with Opposite Units Diesel

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 18* ENERGIZE A06: Closes 2A0619 using the following sequence:

CLOSE affected unit Bus Tie breaker:

Places 2HS-1627-2, Train B Sync Ckt 2A0619 (3A0603) Control, keyswitch to ON.

Depresses the Sync pushbutton on 2HS-1639A2, Bus Tie 2A06 to 3A06 Fdr Breaker 2A0619.

Depresses the Close pushbutton on 2HS-1639A2, Bus Tie 2A06 to 3A06 Fdr Breaker 2A0619.

Depresses the Sync pushbutton on 2HS-1639A2, Bus Tie 2A06 to 3A06 Fdr Breaker 2A0619.

Places 2HS-1627-2, Train B Sync Ckt Control, keyswitch to OFF.

2009A NRC S-6 rev 0.doc Page 12 of 14

JPM: 2009A NRC S-6 TITLE: Perform the Actions of Supplying 1E 4kV Bus with Opposite Units Diesel

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 19 VERIFY opposite unit Diesel Generator Observes the following indications:

G003:

Red Closed light remains illuminated on Output breaker remains - closed. 3HS-1642-2, Generator Breaker 2A0613.

Droop-In light at HS-1650-2

White Droop-In light is extinguished on

- extinguished. 3HS-1650-2, Governor Control.

Voltage - approximately 4.36 kV.

Voltage on 3EI-1651-2, Diesel Gen Frequency - approximately 60 Hz. 3G003 Volts, indicates about 4.40 kV.

Frequency on 3SI-1651-2, Diesel Gen 3G003 Hertz, indicates about 60 Hz.

20 VERIFY affected unit 1E buses A06 Observes the following indications:

and B06 - energized.

Voltage on 2EI-1641-2, 4.16 kV Bus 2A06 Volts, indicates about 4.40 kV.

Voltage on 2EI-1699A2, 480 V Bus 2B06 Volts, indicates about 508 V.

21 VERIFY Train B supplied 1E DC Buses Observes the following indications:

_ energized:

Voltage on 2EI-1641-2, 4.16 kV Bus VERIFY 1E DC Bus D2: 2A06 Volts, indicates about 4.40 kV.

- energized.

Voltage on 2EI-1699A2, 480 V Bus 2B06 Volts, indicates about 508 V.

CUE: CRS confirms that 2D2 is energized from the battery charger.

CUE: The CRS directs you to establish the following loads on the Diesel Generator per SO23-12-11, att # 24:

Salt water cooling pump 2P114 and THEN Component Cooling Water Pump 2P26 2009A NRC S-6 rev 0.doc Page 13 of 14

JPM: 2009A NRC S-6 TITLE: Perform the Actions of Supplying 1E 4kV Bus with Opposite Units Diesel

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 22* ESTABLISH essential loads as STARTS 2P114 by depressing start push determined by the SRO-in charge: button 2HS-6383-2, SALTWATER PUMP Saltwater Cooling Pump (0.413 MW) 2P114. Monitors diesel loading. Determines load is within limits.

- operating.

23* ESTABLISH essential loads as STARTS 2P026 by depressing start push determined by the SRO-in charge: button 2HS-6324-2, CCW PUMP 2P026.

One CCW Pump (0.594 MW) Monitors diesel loading. Determines load is within limits.

- operating TERMINATING CUE: Stop Time: ________

This JPM is complete.

2009A NRC S-6 rev 0.doc Page 14 of 14

JPM INFORMATION SHEET JPM NUMBER 2009A NRC S-7 INITIAL PLANT CONDITIONS Channel "A" Narrow Range Pressurizer Pressure Channel, 2PI-0101-1, is off-scale low.

TASK TO BE PERFORMED The Control Room Supervisor directs you to respond to alarms for Channel "A" Narrow Range Pressurizer Pressure Transmitter failure.

2009A NRC S-7 rev 0.doc Page 1 of 10

JOB PERFORMANCE MEASURE 2009A NRC S-7 SUGGESTED TESTING ENVIRONMENT: PLANT SIMULATOR X ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATORS NAME:

The operators performance was evaluated against the standards contained in this JPM and is determined to be:

SATISFACTORY:

UNSATISFACTORY:

Examiner:__________________________________ ___________________

Signature Date Comments:

2009A NRC S-7 rev 0.doc Page 2 of 10

DOCUMENTATION 2009A NRC S-7 JPM LEVEL: RO / SRO ESTIMATED TIME TO COMPLETE: 8 minutes TIME CRITICAL JPM: NO CRITICAL TIME: N/A POSITION: CO TASK SYS ID: 608 TASK DESCRIPTION Bypass a Reactor Protective System Trip Channel.

KA NUMBER: 012 A4.03 KA VALUES: RO 3.6 SRO 3.6 10CFR55.45 APPLICABILITY: 4, 6

REFERENCES:

SO23-13-18, Reactor Protection System Failure, Rev. 8.

SO23-3-2.12, Reactor Protection System Operation, Rev. 14.

AUTHOR: L. Zilli DATE:

OPERATIONS REVIEW: M. Jones DATE:

APPROVED BY: A. Hagemeyer DATE:

2009A NRC S-7 rev 0.doc Page 3 of 10

MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOT BY MODIFIED APPROVAL 3 Compared against SO23-13-18 LRZ 07/13/06 REV Rev. 7-2 and SO23-3-2.12 Rev. 12 with changes required to comply with procedure steps.

2009A NRC S-7 rev 0.doc Page 4 of 10

SET-UP MACHINE OPERATOR:

Use IC #247 for 2009A NRC JPM Exam.

Otherwise, use any 100% IC and perform the following:

Ensure Annunciators 56A03, 56A04, and 56A14 are in alarm

Insert Malfunction RC20A and fail low (1500).

EXAMINER:

Provide the examinee with a copy of SO23-13-18, Reactor Protection System Failure/Loss of Vital Bus when located.

Provide the examinee with a copy of SO23-3-2.12, Reactor Protective System Operation, Section 6.2 (Bypass Operation of Trip Channels).

Pictures of the PPS A bypass switches should be in the JPM file folder. If available, use the pictures of the inside of PPS Cabinet 2UI K078 to aid the Examinee.

Station an instructor, in contact with the Machine Operator, who can relay the operation of the pushbuttons inside 2UI K078 Cabinet A.

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JPM: 2009A NRC S-7 TITLE: Channel A Pressurizer Pressure Transmitter Failure.

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 1 Respond to alarms: Using Annunciator Response Start Time: _______

56A03 - LOCAL POWER Procedures 56A03 and 56A04 DENSITY HI CHANNEL DETERMINE that alarms are due to a TRIP failed channel and ENTER SO23-13-18, Reactor Protection

56A04 - DNBR LO System Failure / Loss of Vital Bus.

CHANNEL TRIP

56A14 - DNBR LO RPS PRETRIP

56B06 - PPS CHANNEL 1 TROUBLE

56C01 - CPC CHANNEL 1 SENSOR FAILURE Failed channel If only one channel has tripped due to failure, then Obtain the SRO Operation Supervisors permission and BYPASS the trip.

If channel failure is due to failed instrument of a measured variable channel, then refer to SO23-13-18, Attachment for Affected Functional Units, to determine which units(s) is (are) affected.

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JPM: 2009A NRC S-7 TITLE: Channel A Pressurizer Pressure Transmitter Failure.

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat)

CUE: If candidate addresses ARP for 56C01, CPC Channel 1 Sensor Failure state that SO23-3-2.13 is complete and no auxiliary relay failure was found.

NOTE: Provide the examinee with a copy of SO23-13-18, Reactor Protection System Failure/Loss of Vital Bus.

2* DETERMINE failure by observing VERIFY 2PI-0101-1, Channel A instrumentation for the affected Pressurizer 2E087 Pressure Narrow channel AND alternate Range Pressurizer Pressure, redundant indications monitoring indication is low. COMPARE the same plant parameters. indication to other three channels (2PI-0101-2, 3, & 4) of Pressurizer pressure for validity.

3 CPC Sensor Failure OR A Single VERIFY a single functional unit or a Functional OR a Single PPS single PPS channel has failed and Channel has FAILED. GO TO procedure Step 3.

4* REFER to Attachment 5 and REFER to Attachment 5 and determine Functional Unit(s) DETERMINE:

affected.

Pressurizer Pressure - High

Local Power Density - High

DNBR - Low are the affected Functional Units and must be bypassed.

NOTE: The Operator may place trips in BYPASS without referring to SO23-3-2.12. This action is within the normal skill of the Operator. The three trips may be bypassed in any order.

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JPM: 2009A NRC S-7 TITLE: Channel A Pressurizer Pressure Transmitter Failure.

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 5 PLACE the affected Functional LOCATE copy of SO23-3-2.12, and Unit in BYPASS per IDENTIFY Section 6.3 as the SO23-3-2.12, Section for Bypass appropriate section for Bypass Operation of Trip Channels. Operation of Trip Channels.

NOTE: Provide the Examinee with a copy of SO23-3-2.12, Reactor Protective System Operation, Section 6.3, Bypass Operation of Trip Channels.

6 Verify that the same bistable is VERIFY no other channels are in not in bypass on any other bypass by OBSERVING PPS channel. Channels.

7 UNLOCK and OPEN the Bistable UNLOCK and OPEN the Bistable Control Panel. Control Panel.

NOTE: Provide the cabinet mimic photos to the Examinee.

8* DEPRESS the Bypass DEPRESS Bypass pushbutton 5, for pushbutton on the Bistable HI PZR PRESS, at PPS A Cabinet Control Panel corresponding to 2UI K078.

the trip channel to be bypassed.

9 Verify that the Trip Bypass light is VERIFY that the Trip Bypass white illuminated. light is illuminated.

CUE: The Trip Bypass white light is illuminated. If amber Bypass light is checked, it too is illuminated.

10 Verify the switch remains latched VERIFY the Trip Bypass switch after being depressed. remains latched after being depressed.

CUE: The Trip Bypass pushbutton remains depressed.

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JPM: 2009A NRC S-7 TITLE: Channel A Pressurizer Pressure Transmitter Failure.

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 11 Verify the Trip Channel VERIFY annunciator 56A29, PPS Bypassed Annunciator 56A29 CHANNEL 1 TRIP BYPASSED, alarms. alarms on CR56.

CUE: The Trip Channel Bypass alarm is in.

12* DEPRESS the Bypass DEPRESS Bypass pushbutton 4, for pushbutton on the Bistable LOW DNBR, at PPS A Cabinet Control Panel corresponding to 2UI K078.

the trip channel to be bypassed.

13 Verify that the Trip Bypass light is VERIFY that the Trip Bypass white illuminated. light is illuminated.

CUE: The Trip Bypass white light is illuminated. If amber Bypass light is checked, it too is illuminated.

14 Verify the switch remains latched VERIFY the Trip Bypass switch after being depressed. remains latched after being depressed.

CUE: The Trip Bypass pushbutton remains depressed.

15* DEPRESS the Bypass DEPRESS Bypass pushbutton 3, for pushbutton on the Bistable HI LOCAL POWER, at PPS A Control Panel corresponding to Cabinet 2UI K078.

the trip channel to be bypassed.

16 Verify that the Trip Bypass light is VERIFY that the Trip Bypass white illuminated. light is illuminated.

CUE: The Trip Bypass white light is illuminated. If amber Bypass light is checked, it too is illuminated.

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JPM: 2009A NRC S-7 TITLE: Channel A Pressurizer Pressure Transmitter Failure.

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U COMMENTS (Required for Unsat) 17 Verify the switch remains latched VERIFY the Trip Bypass switch after being depressed. remains latched after being depressed.

TERMINATING CUE: Stop Time: ________

The Trip Bypass pushbutton remains depressed.

This JPM is complete.

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