ML101240879

CP-2009-03-PUBLIC Final Operating Test

ML101240879
Person / Time
Site:	Comanche Peak
Issue date:	05/04/2010
From:	NRC Region 4
To:
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Download: ML101240879 (173)

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ES-301 Administrative Topics Outline Form ES-301-1 Facility: CPNPP Units 1 & 2 Date of Examination: 03/30109 Examination Level RO D Operating Test Number: NRC I

r Administrative Topic (see Note)

Type Code* Describe Activity to be Performed 2 .1.25 Ability to interpret reference materials such as graphs, curves, tables, etc . (3.9).

Conduct of Operations M,R JPM : Calculate Shutdown Margin During a Cooldown From the Remote Shutdown Panel I (R01010) .

2.1 .23 Ability to perform specific system and integrated plant procedures during all modes Conduct of Operations M,R of plant operation (4.3) .

JPM : Determine Time to Core Uncovery on a Loss of RHR (R05153) .

2.2.37 Ability to determine operability and/or availability of safety related equipment (3.6).

Equipment Control N,S JPM : Verify Pressurizer Heater Bank operability (New) .

2.3.7 Ability to comply with radiation work permit requirements during normal or abnormal Radiation Control M,R conditions (3.5).

JPM : Determine RWP Entry Requirements and Identify Low Dose Waiting Area (R07533).

Emergency Plan -

NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless I they are retaking only the administrative topics, when all 5 are required .

• Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (~ 3 for ROs ; ~ for 4 for SROs & RO retakes)

I (N)ew or (M)odified from bank (~ 1)

(P)revious 2 exams (~ 1; randomly selected)

NUREG-1021, Revision 9.1 Page 1 of 2 CPNPP Mar 2009 RO ES-301-1 Rev Final

Administrative Topics Outline Task Summary A.1.a The candidate will perform a Shutdown Margin Calculation per OPT-301, Shutdown Margin Calculation, during a cooldown from the Remote Shutdown Panel in accordance with ABN-803A, Response to a Fire in the Control Room or Cable Spreading Room. Critical tasks include identifying individual parameters and determining the Shutdown Margin. This is a modified bank JPM.

A.1.b The candidate will determine the time to boil, time to core uncovery, and time to achieve Containment Closure on a total loss of Residual Heat Removal cooling per ABN-104, RHR System Malfunction. Critical tasks include determining the time for each evolut ion. This is a modified bank JPM.

A.2 The candidate will verify Pressurizer Heater Bank OPERABILITY per IPO-001A, Plant Heatup From Cold Shutdown to Hot Standby, Section 5.3, Heatup and Pressurization for MODE 3 Entry. The critical tasks include verifying Pressurizer Heater Bank capacities. This is a new JPM.

A.3 The candidate will determine the radiological requirements for entering an area in the RCA for implementing a Clearance per STA-656, Radiation Work Control. Critical tasks include identifying proper RWP , identify dress-out requirements, determine dosimetry requirements, coverage requirements, and determine what briefings are required. This is modified bank JPM.

A.4 N/A NUREG-1021 , Revision 9.1 Page 2 of 2 CPNPP Mar 2009 RO ES-301-1 Rev Final

ES-301 Administrative Topics Outline Form ES-301-1 I Facility : CPNPP Units 1 and 2 Date of Examination: 03/30109 I Examination Level SRO D Operating Test Number: NRC I

Administrative Topic Type Code* Describe Activity to be Performed (see Note)

I 2.1.25 Ability to interpret reference materials such as I I graphs, curves , tables , etc. (4.2).

I Conduct of Operations M,R JPM : Calculate Shutdown Margin During a I

Cooldown From the Remote Shutdown Panel (R01010).

2. 1.23 Ability to perform spec ific system and integrated plant procedures during all modes I Cond uct of Operations M,R of plant operation (4.4).

I II JPM :

2.2 .12 Determ ine Time to Core Uncovery on a Loss of RHR (R0 5153).

Knowledge of surveillance procedures (4.1).

I Equipment Control N,R JPM: Review a completed surveillance (New).

2 .3.6 Ability to approve release permits (3.8).

I Radiat ion Control N, R JPM : Approve a Liquid Waste Release Permit (New). I 2.4.29 Knowledge of the emergency plan (4.4).

Emergency Plan M,R JPM : Review a Notification Message Form (SRO 8004) .

NOTE: All items (5 total) are requ ired for SROs . RO applicants requ ire only 4 items unless they are retaking only the administrative topics, when all 5 are required.

"Type Codes & Criteria: (C)ontrol room , (S)imulator, or Class(R)oom (D)irect from bank (s 3 for ROs; s for 4 for SROs & RO retakes)

(N)ew or (M)od ified from bank (~ 1)

(P)revious 2 exams (s 1; randomly selected)

L .. I NUREG-1021 , Revision 9.1 Page 1 of 2 CPNPP Mar 2009 SRO ES-301-1 Rev Final

Administrative Topics Outline Task Summary A.1.a The candidate will perform a Shutdown Margin Calculation per OPT-301 ,

Shutdown Margin Calculation, during a cooldown from the Remote Shutdown Panel in accordance with ABN-803A, Response to a Fire in the Control Room or Cable Spreading Room. Critical tasks include identifying individual parameters and determining the Shutdown Margin. This is a modified bank JPM.

A.1.b The candidate will determine the time to boil, time to core uncovery, and time to achieve Containment Closure on a total loss of Residual Heat Removal cooling per ABN-104, RHR System Malfunction. Critical tasks include determining the time for each evolution. This is a modified bank JPM.

A.2 The candidate will perform the review of a completed Centrifugal Charging Pump surveillance per OPT-201 A, Charging System. Critical tasks include identifying that unsatisfactory data is obtained during testing. This is a new JPM.

A.3 The candidate will be given a Liquid Release Permit for approval prior to release per STA-603, Control of Station Radioactive Effluents. Critical tasks include determining that release conditions will have changed and not approve the release until proper conditions are established. This is a new JPM.

A.4 The candidate will review a Notification Message Form per EPP-203-8, Notification Message Form. The critical task is to determine if the proper notifications and classification are being transmitted . This is a modified bank JPM.

NUREG-1021 , Revision 9.1 Page 2 of 2 CPNPP Mar 2009 SRO ES-301-1 Rev Final

ES-301 Control Room 1 In-Plant Systems Outline Form ES-301-2 Facility: CPNPP Units 1 and 2 Date of Examination : 03/30109 Exam Level: RO 0 SRO(I) 0 SRO (U) 0 Operating Test No.: NRC l

I Control Room systems" (8 for RO; 7 for SRO-I ; 2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code" Safety Function

~ 8-1 001 - Control Rod Drive System (R01022) A ,D,S 1 I Respond to a Continuous Rod Withdrawal (RO ONL Y)

S-2 004 - Chemical and Volume Control System (R01307) D,S 2 I Perform Manual Makeup to the RWST I

010- Pressurizer Pressure Control System (R08082) A, M, S 3 I S-3 Respond to Pressurizer Spray Valve Failure S-4 005 - Residual Heat Removal System (New) L,N,S 4-P Respond to a Shutdown Loss of Coolant I S-5 026 - Containment Spray System (R02008B) A,D,EN,S 5 Operate Containment Spray with Inadvertent Spray Flow S-6 S-7 062 - AC Electrical Distribution System (New)

Transfer Buses from Transformer XST2 to xsn 016 - Non-Nuclear Instrumentation System (New)

Respond to Turbine Impulse Pressure Instrument Malfunction N,S A, N, S 6

7 S-8 029 - Containment Purge System (New) A ,N ,S 8 Operate the Conta inment Purge System In-Plant Systems@(3 for RO; 3 for SRQ-I ; 3 or 2 for SRO-U)

P-1 062 - AC Electrical Distribution System (A04204) D 6 Energize a Protection System Inverter P-2 068 - Liquid Radwaste System (R08063) A,D,E,R 9 Respond to Accidental Release of Radioactive Liquid P-3 061 - Auxiliary/Emergency Feedwater System (A06405) D,E,S 4-5 Reset and Open TDAFW Pump Trip & Throttle Valve NUREG-1021, Revision 9.1 Page 1 of 3 CPNPP Mar 2009 ES-301-2 Rev Final

Control Room / In-Plant Systems Outline Task Summary

@ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may over1ap those tested in the control room.

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• Type Codes Criteria for RO / SRQ-I / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 I (C)ontrol room I (D)irect from bank 9/ 8/ 4 I (E)mergency or abnormal in-plant 1/ 1/ 1 I

I (EN)gineered safety feature / - / 1 (control room system)

(L)ow Power / Shutdown 1/ 1/ 1 (N)ew or (M)odified from bank including 1(A) 2/ 2/ 1 (P)revious 2 exams 3/ 3/ 2 (randomly selected)

(R)CA 1/ 1/ 1 (S)imulator NRC JPM Examination Summary Description S-1 The candidate will perform actions per ABN-712 , Rod Control System Malfunction, in response to improper Control Rod motion. The alternate path includes actions to deenergize the Rod Drive Motor Generator Sets when the Control Rods fails to insert. This is a bank JPM under the Control Rod Drive System-Reactivity Control Safety Function.

S-2 The candidate will perform actions to makeup to the Refueling Water Storage Tank per SOP-104A, Reactor Makeup and Chemical Control System. This is a bank JPM under Chemical and Volume Control System-Reactor Coolant System Inventory Control Safety Function .

8-3 The candidate will perform the actions for a Pressurizer Spray Valve failing open per ABN-705 , Pressurizer Pressure Malfunction. The alternate path includes actions to trip the Reactor and Reactor Coolant Pump when the Pressurizer Spray Valve fails to close. This is a modified bank JPM under the Pressurizer Pressure Control System-Reactor Pressure Control Safety Function. This is a PRA significant action .

S-4 The candidate will respond to a leak in the Reactor Coolant System per ABN-108, Shutdown Loss of Coolant. This is a new JPM under the Residual Heat Removal System-Primary System Heat Removal From Reactor Core Safety Function. This is a PRA significant action.

NUREG-1021 , Revision 9.1 Page 2 of 3 CPNPP Mar 2009 ES-301-2 Rev Final

Control Room lin-Plant Systems Outline Task Summary 5-5 The candidate will align Refueling Water Storage Tank recirculation with the Containment Spray Pump per the Alarm Response Procedures. The alternate path is to respond to an inadvertent Containment Spray flow actuation . This is a bank JPM under Containment Spray System-Containment Integrity Safety Function .

S-6 The candidate will perform the actions of SOP-603A, 6900 V Switchgear to support maintenance on Transformer XST2. This is a new JPM under AC Electrical Distribution System- Electrical Safety Function.

S-7 The candidate will respond to a Turbine Impulse Pressure Instrument Malfunction per ABN-709, Steam Line , Steam Header, Turbine 1st Stage Pressure, and Feed Header Pressure Instrument Malfunction. This is a new JPM under Non-Nuclear Instrumentation System-Instrumentation Safety Function .

8-8 The candidate will perform the actions specified in SOP-801 A, Containment Ventilation System, Section 5.6.1, Containment Purge and Exhaust System Startup. The alternate path occurs when the Containment Purge System fails to isolate on a high airborne activity. This is a new JPM under Containment Purge System-Plant Service Systems Safety Function .

P-1 The candidate will perform the actions to return a Protection System Inverter to service per SOP-607 A, 118V AC Distribution System and Inverters. This is a bank JPM under the AC Electrical Distribution System-Electrical Safety Function .

P-2 The candidate will perform actions for a Liquid Waste Processing Discharge high radiation alarm per ABN-903, Accidental Release of Radioactive Liquid. The alternate path requires closing of valves when it is determined that a Liquid Waste Processing Panel alarm is not dark. This is a bank JPM under the Liquid Radwaste System-Radioactivity Release Safety Function.

P-3 The candidate will locally reset the Trip and Throttle Valve on the Turbine Driven Auxiliary Feedwater Pump per ABN-305, Auxiliary Feedwater System Malfunction. This is a bank JPM under the Auxiliary Feedwater System Secondary System Heat Removal from Reactor Core Safety Function. This is a PRA significant action .

NUREG-1021, Revision 9.1 Page 3 of 3 CPNPP Mar 2009 ES-301-2 Rev Final

ES-301 Simulator Scenario Quality Checklist Form ES-301-4 ility : CPNPP Date of Exam: 03/30/09 Scenario Numbers: 1/2/3 Operating Test No .: NRC QUALITAlWE A TIRIBUTES Initials a b* C#

1. The initial conditions are realistic, in that some equipment and/or instrumentation may be out of service, but it does not cue the operators into expected events. :zg.. I@

2. The scenarios consist mostly of related events. ~

3. Each event description consists of

• the point in the scenario when it is to be initiated

• the malfunction(s) that are entered to initiate the event J ~

• the symptoms/cues that will be visible to the crew

• the expected operator actions (by shift position)

• the event termination point (if applicable) l ~

4. No more than one non-mechanistic failure (e.g., pipe break) is incorporated into the scenario without a credible preceding incident such as a seismic event.

5. The events are valid with regard to physics and thermodynamics . 1 ()

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6. Sequencing and timing of events is reasonable, and allows the examination team to obtain complete evaluation results commensurate with the scenario objectives . .:t

7. If time compression techniques are used, the scenario summary clearly so indicates. Operators have sufficient time to carry out expected activities without undue time constraints. Cues are given. ~ q) I

8. The simulator modeling is not altered. c:& C I

~

9. The scenarios have been validated. Pursuant to 10 CFR 55.46(d), any open simulator performance deficiencies or deviations from the referenced plant have been evaluated to ensure that functional fidelity is maintained while running the planned scenarios .

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10. Every operator will be evaluated using at least one new or significantly modified scenario. All other scenarios have been altered in accordance with Section D.5 of ES-301. s@

~ ~

11. All individual operator competencies can be evaluated, as verified using Form ES-301-6 (submit the form along with the simulator scenarios).

12. Each applicant will be significantly involved in the minimum number of transients and events specified on Form ES-301-5 (submit the form with the simulator scenarios) .  :& ~

13. The level of difficulty is appropriate to support licensing decisions for each crew position. I~ <1 Target Quantitative Attributes Actual Attributes . I. .

(Per Scenario; See Section D.5.d) 1 2 3

1. Total malfunctions (5-8) 7 6 7

2. Malfunctions after EOP entry (1-2) 2 2 2

3. Abnormal events (2-4) 4 4 3

4. Major transients (1-2) 1 1 2

5. EOPs entered/requiring substantive actions (1-2) 1 1 2

6. EOP contingencies requiring substantive act ions (0-2) 0 1 1

7. Critical tasks (2-3) 3 3 2 NUREG-1 021, Revision 9.1 CPNPP Mar 2009 ES-301-4 Rev Final

ES-301 Transient and Event Checkl ist Form ES-301-5 Facility: CPNPP 1 and 2 Date of Exam : 03/30109 Operating Test No.: NRC II A E SCENARIOS P V P E CPNPP #1 CPNPP #2 L N I T MINIMUM(")

I T CREW CREW CREW CREW 0 C

POSITION POSITION POSITION POSITION T A T I A

N Y S A B S A B S A B S A B R T 0 R T 0 R T 0 R T 0 L R I U T P E 0 c p 0 c p 0 c p 0 c p I

RX - - 0 1 1 0 NOR - 1 1 1 1 1 SROU I/C 1,2,3, 2,7 1,2,3 6 4 4 2 4 I MAJ 5 6 2 2 2 1 TS I 3,4 - 2 0 2 2 RX - - I 0 1 1 0 NOR - 1 I I 1 1 1 1 SROU-4 I/C 1,2 ,3, 2,3,4 7 4 4 2 4 I MAJ I 5 6 2 2 2 1 TS 3,4 2,4 - I 4 0 2 2 RX - - O* 1 1 0 NOR - 1 1 1 1 1 I SROI 1,2,3 I/C 2,4,6 2,3,4 6 4 4 2 MAJ 5 6 I I 2 2 2 1 TS I - 2,4 2 0 , "

2 2 RX - 1 1 1 1 0 NOR - - O* 1 1 1 RO-1 ,3 I I/C I 1,3,7 I 3,4 5 4 4 2 MAJ 5 6 2 2 2 1 TS I - - 0 0 2 2 RX I - - O* 1 1 0 NOR I - 1 1 1 1 1 RO-4 I/C 2,4,6 2,7 5 4 4 I 2 MAJ 5 6 2 2 2 1 TS - - 0 0 2 2 RX - 1 1 1 1 0 NOR - - I O* 1 1 I 1 RO-5 I/C 1,3,7 3,4 5 4 4 I 2 MAJ 5 6 2 2 2 1 TS - - 0 0 2 2

• Reactivity and normal evolutions replaced with instrument or component malfunctions on a 1-for-1 basis.

NUREG 1021 Revision 9.1 Page 1 of 2 CPNPP Mar 2009 ES-301-5 Rev Final

ES-301 Transient and Event Checklist Form ES-301-5

,I Instructions:

11. Che ck the appl icant level and enter the operating test number and Form ES-D -1 event numbers for eac h event type ;

TS are not applicable for RO applicants. ROs must serve in both the "at-the-controls (ATC)" and "balance-of-plant (BOP)" positions: Instant SROs must serve in both the SRO and the ATC positions , including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position . If an Instant SRO additionally serves in the BOP position, one IIC malfunction can be credited toward the two I/C malfunctions required for the ATC position .

2 Reactivity man ipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendi x D. n Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis.

3. Whenever pract ical, both instrument and component malfunctions should be included ; only those that require verifiable actions that provide insight to the applicant's competence count toward the minimum requirements specified for the applicant's license level in the right-hand columns NUREG 1021 Revision 9.1 Page 2 of 2 CPNPP Mar 2009 ES-301-5 Rev Final

ES-301 Competencies Checklist Form ES-301-6 I Facility: CPNPP Date of Examination: 03/31/09 Operating Test No. NRC 1-2

~ Applicants SROU-1 SROU-2 SROU-3 Competencies SCENARIO SCENARIO SCENARIO 1

1 2 1 2 1 2 I

[ lnterpreti Diag 1,2,3,4, 1,2,3,4, 1,2,3,4, nose Events 2,6,7 2,6,7 2,6,7

~ and Conditions 5 5 5 Ii

• I Comply With 1,2,5, 1,2,5, 1,2,5, and Use ALL 6,7 ALL 6,7 ALL 6,7 l

[' Procedures (1) I

\ Operate 1,2,5, 1,2,5, I 1,2,5, Control Boards N/A 6,7 N/A 6,7 N/A 6,7

, (2)

Communicate 1,2,5, 1,2,5, 1,2,5, and ALL 6,7 ALL 6,7 ALL 6,7 Interact I Demonstrate Supervisory ALL N/A ALL N/A ALL N/A Ability (3) I Comply With and Use Tech . 3,4 N/A 3,4 N/A 3,4 N/A Specs . (3) I Notes:

(1) Includes Technical Specif ication compliance for an RO.

I (2) Optional for an SRO-U .

(3) Only applicabl e to SROs .

I J

NUREG-1021, Revision 9.1 CPNPP Mar 2009 ES-301-6 Rev Final

ES-301 Competencies Checklist Form ES-301-6 Facility: CPNPP Date of Examination : 03/31/09 Operating Test No. NRC 1-2 II Ir I Applicants SROU-4 Competencies i SCENARIO SCENARIO SCENARIO 1 2 I

InterpretiDiag 1,2,3,4, nose Events 5 2,3,4,6 and Conditions Comply With and Use ALL ALL r Procedures (1)

Operate I Control Boards N/A N/A I (2)

Communicate I I and ALL ALL Interact I Demonstrate I

Supervisory ALL ALL Ability (3 Comply With and Use Tech. 3,4 2,4 Specs . (3)

Notes:

(4) Includes Technical Specification compliance for an RO.

(5) Optional for an SRO-U .

(6) Only applicable to SROs .

NUREG-1021 , Revision 9.1 CPNPP Mar 2009 ES-301-6 Rev Final

ES-301 Competencies Checklist Form ES-301-6 I Facility: CPNPP Date of Examination : 03/31/09 Operating Test No. NRC 1-2 Applicants ,

i SROI-1 SROI-2 SROI-3 I

Competencies SCENARIO SCENARIO SCENARIO I

IlnterpretiDia g 1 2 1 2 1 2 I

1,2,4, 1,2,4, 1,2,4 ,

nose Events 5,6 2 ,3,4,6 5,6 2,3 ,4,6 5,6 2,3,4 ,6 I and Conditions I

Comply With 1,2,4, 1,2 ,4, 1,2,4, and Use 5,6 ALL 5,6 ALL 5,6 ALL I Procedures (1) I Operate 1,2,3, 1,2 ,3, 1,2 ,3, Control Boards N/A N/A 4,5,6 N/A 4,5,6 4,5,6 (2) ,

Communicate 1,2,3, 1,2 ,3, 1,2 ,3, and 4,5,6 ALL 4,5,6 ALL 4,5,6 ALL I

Interact Demonstrate Supervisory N/A ALL N/A ALL N/A ALL Ability (3)

Comply With and Use Tech . N/A 2,4 N/A 2,4 N/A 2,4 Specs. (3)

Noles :

(7) Includes Technical Specification compliance for an RO .

(8) Opt ional for an SRO-U .

(9) Only applicable to SROs.

II NUREG-1021 , Revision 9.1 CPNPP Mar 2009 ES-301-6 Rev Final

ES-301 Competencies Checklist Form ES-301-6 Facility: CPNPP Date of Examination : 03/31/09 Operating Test No. NRC 1-2 Ii Applicants RO-1 RO-3 RO-4 Competencies SCENARIO SCENARIO SCENARIO 1 2 1 2 1 2 I lnterpreti Diag 1,2,4, nose Events 1,3,5,7 1,3,4,6 1,3,5,7 1,3,4,6 5,6 2,6,7 and Conditions Comply With 1,2,4, 1,2,5, and Use 1,3,5,7 1,3,4,6 1,3,5,7 1,3,4,6 5,6 6,7 I Procedures (1) ,

Operate 1,3,4, 1,3,4, 1,2,3, 1,2,5, Control Boards 5,7 1,3,4,6 5,7 1,3,4,6 4,5,6 6,7 (2)

Communicate 1,3,4, 1,3,4, 1,3,4, 1,3,4, 1,2,3, 1,2,5, and 1 5,6 5,7 5,6 4,5,6 6,7 I 5,7 Interact Demonstrate Supervisory N/A N/A N/A N/A N/A N/A Ability (3) I Comply With and Use Tech . N/A N/A N/A N/A N/A N/A Specs . (3)

Notes:

( 10) Includes Technical Specification compliance for an RD .

I (11) Optional for an SRO-U.

I (12) Only applicable to SROs .

L ~

NUREG-1021, Revision 9.1 CPNPP Mar 2009 ES-301-6 Rev Final

ES-301 Competencies Checklist Form ES-301-6 I Facility: CPNPP Date of Examination : 03/31/09 Operating Test No. NRC 1-2 Applicants RO-S I

Competencies SCENARIO -

SCENARIO SCENARIO 1 2 I InterpretiDiag nose Events 1,3,5,7 1,3,4,6 and Conditions I Comply With and Use 1,3,5,7 1,3,4,6 Procedures (1) I Operate 1,3,4, Control Boards 5,7 1,3,4 ,6 (2)

Communicate 1,3,4, 1,3,4, and 5,7 5,6 Interact I Demonstrate Supervisory N/A N/A Ability (3)

Comply With and Use Tech. N/A N/A Specs . (3)

Notes:

(13) Includes Technical Specification compliance for an RO .

(14) Optional for an SRO-U .

(15) Only applicable to SROs . j NUREG-1021 , Revision 9.1 CPNPP Mar 2009 ES-301-6 Rev Final

Facility: CPNPP Units 1 & 2 Date of Examination: 03/30109 Examination Level RO D Operating Test Number: NRC I AdministrativeTopic Type Code*

DescribeActivity to be Performed (see Note) 2.1.25 Ability to interpret reference materials such as r graphs, curves, tables, etc. (3.9).

M,R Conduct of Operations JPM : Calculate Shutdown Margin During a Cooldown From the Remote Shutdown Panel I (R01010).

2.1 .23 Ability to perform specific system and integrated plant procedures during all modes of plant operation (4.3) .

M,R Conduct of Operations JPM : Determine Time to Core Uncovery on a Loss of RHR (R05153).

2.2.37 Ability to determine operability and/or availability of safety related equipment (3.6). Equipment Control N,S JPM : Verify Pressurizer Heater Bank operability (New) .

2.3.7 Ability to comply with radiation work permit requirements during normal or abnormal conditions (3.5).

M,R JPM : Determine RWP Entry Requirements and Identify Low Dose Waiting Area (R07533).

Radiation Control Emergency Plan NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

I

• Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (~ 3 for ROs; ~ for 4 for SROs & RO retakes)

I (N)ew or (M)odified from bank (~ 1)

(P)revious 2 exams (~ 1; randomly selected)

NUREG-1021, Revision 9.1 Page 1 of 2 CPNPP Mar 2009 RO ES-301-1 Rev Final

Administrative Topics Outline Task Summary A.1.a The candidate will perform a Shutdown Margin Calculation per OPT-301, Shutdown Margin Calculation, during a cooldown from the Remote Shutdown Panel in accordance with ABN-803A, Response to a Fire in the Control Room or Cable Spreading Room. Critical tasks include identifying individual parameters and determining the Shutdown Margin. This is a modified bank JPM.

A.1.b The candidate will determine the time to boil, time to core uncovery, and time to achieve Containment Closure on a total loss of Residual Heat Removal cooling per ABN-104, RHR System Malfunction. Critical tasks include determining the time for each evolution. This is a modified bank JPM.

A.2 The candidate will verify Pressurizer Heater Bank OPERABILITY per IPO-001A, Plant Heatup From Cold Shutdown to Hot Standby, Section 5.3, Heatup and Pressurization for MODE 3 Entry. The critical tasks include verifying Pressurizer Heater Bank capacities. This is a new JPM.

A.3 The candidate will determine the radiological requirements for entering an area in the RCA for implementing a Clearance per STA-656, Radiation Work Control. Critical tasks include identifying proper RWP, identify dress-out requirements, determine dosimetry requirements, coverage requirements, and determine what briefings are required. This is modified bank JPM.

A.4 N/A NUREG-1021,Revision9.1 Page2of2 CPNPPMar2009RO ES-301-1 RevFinal I

ES-301 Administrative Topics Outline Form ES-301-1 I Facility : CPNPP Units 1 and 2 Date of Examination: 03/30109 I Examination Level SRO D Operating Test Number: NRC Administrative Topic Type Code* Describe Activity to be Performed (see Note)

I 2.1.25 Ability to interpret reference materials such as I I graphs, curves , tables , etc. (4.2).

I Conduct of Operations M,R JPM : Calculate Shutdown Margin During a I

Cooldown From the Remote Shutdown Panel (R01010).

Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC RO/SRO A.1.a Task # RO1010 K/A # 2.1.25 3.9 / 4.2

Title:

Calculate Shutdown Margin During a Cooldown From the Remote Shutdown Panel Examinee (Print):

Testing Method:

Simulated Performance: Classroom: X Actual Performance: X Simulator:

Plant:

READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.

When you complete the task successfully, the objective for this JPM will be satisfied.

Initial Conditions: At 1200 on 03/02/2009 the Unit 1 Reactor was tripped from 100% power and the Control Room was evacuated due to a fire. A plant cooldown was initiated at 1500 and RCS temperatures from the Remote Shutdown Panel are as follows:

• Reactor Coolant System temperature is 485°F.

• A SHUTDOWN MARGIN calculation is required every hour while cooling down from the Remote Shutdown Panel.

• RCS boron concentration at the time of trip was 400 ppm.

• At 1445, concentration by sample was 593 ppm.

• All control rods were fully inserted on the trip.

• Core Burnup is 18,500 MWD/MTU.

• Unit 1 was stable at 100% power for 47 days prior to the trip.

• A Subcritical Margin Calculation is NOT required.

Initiating Cue: The Unit Supervisor directs you to PERFORM the 1500 SHUTDOWN MARGIN Calculation per OPT-301, Reactor Shutdown Margin Verification.

• SDM Boron Concentration __________ ppm

• SDM Acceptance Criteria Satisfied YES / NO (Circle one)

Task Standard: Locate and correctly perform Critical Steps of OPT-301.

Required Materials: OPT-301, Reactor Shutdown Margin Verification, Rev. 10 Comanche Peak Unit 1 Cycle 14 Nuclear Design Report, Rev. 0 Comanche Peak Unit 1 Cycle 14 Core Operating Limits Report (COLR), Rev. 0 Validation Time: 45 minutes Time Critical: N/A Completion Time: ________ minutes NUREG 1021, Revision 9.1 Page 1 of 9CPNPP Mar 2009 RO & SRO Admin JPM A.1.a Rev Final.doc

Appendix C JPM WORKSHEET Form ES-C-1 Comments:

Result: SAT UNSAT Examiner (Print / Sign): Date:

NUREG 1021, Revision 9.1 Page 2 of 9CPNPP Mar 2009 RO & SRO Admin JPM A.1.a Rev Final.doc

Appendix C JPM WORKSHEET Form ES-C-1 CLASSROOM SETUP EXAMINER:

PROVIDE the examinee with a copy of:

• OPT-301, Reactor Shutdown Margin Verification.

• Comanche Peak Unit 1 Cycle 14 Nuclear Design Report.

• Comanche Peak Unit 1 Cycle 14 Core Operating Limits Report (COLR).

NUREG 1021, Revision 9.1 Page 3 of 9CPNPP Mar 2009 RO & SRO Admin JPM A.1.a Rev Final.doc

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Perform Step: 1 Record the Unit, Cycle, MODE, and the date and time of this calculation.

Standard: RECORD Unit 1, Cycle 14, MODE 3, Date and Time of this calculation on OPT-301-9 at top of Page.

Comment: SAT UNSAT Perform Step: 2 Record the following plant conditions:

• The RCS boron concentration and the date and time at which the sample was taken.

Standard: RECORD 593 ppm, Date and Time sample was taken on OPT-301-9, Step A.1.

Comment: SAT UNSAT Perform Step: 3 Record the following plant conditions:

• The RCS average coolant temperature.

• IF the reactor is subcritical in MODE 2, 3, 4 or 5, THEN enter the average Tave.

Standard: RECORD Tave of 485°F on OPT-301-9, Step A.2.

Comment: SAT UNSAT Perform Step: 4 Record the following plant conditions:

• The core average burnup in MWD/MTU.

• This value may be obtained from the Core History Data Base.

• Mark the appropriate burnup range per Section 5.1 of the SOR or NDR.

Standard: RECORD 18,500 and CHECK the EOL box on OPT-301-9, Step A.3.

Comment: SAT UNSAT Perform Step: 5 Record the following plant conditions:

• The number of known stuck RCCAs.

Standard: RECORD zero (0) on OPT-301-9, Step A.4.

Comment: SAT UNSAT NUREG 1021, Revision 9.1 Page 4 of 9CPNPP Mar 2009 RO & SRO Admin JPM A.1.a Rev Final.doc

Appendix C JPM STEPS Form ES-C-1 Perform Step: 6 Record the following plant conditions:

• The Shutdown Margin reactivity requirement for the current MODE in units of pcm (e.g., 1.3% K/K = 1300 pcm). This value may be found in the COLR.

Standard: REFER to Unit 1 COLR, DETERMINE required SDM and RECORD 1300 pcm on OPT-301-9, Step A.5.

Comment: SAT UNSAT Perform Step: 7 Determine the uncorrected minimum boron concentration using NDR Table 5.13 or NDR Table 5.13, SDM BORON CONCENTRATION (ppm)

AS A FUNCTION OF BURNUP AND CORE AVERAGE TEMPERATURE.

• The boron concentration for temperature values A.2 +10°F and A.2 -10°F are evaluated to determine the highest boron concentration. The highest boron concentration is the uncorrected minimum boron concentration used for B.1.

Standard: PLOT 485°F vs burnup on NDR Figure 5.13. EVALUATE +/- 10 degrees either side to arrive at the most conservative value. DETERMINE that the required Boron is higher at 475°F vs 495°F and choose 475°F.

DETERMINE Boron required at 18,500 MWD/MTU and RECORD 1171

+/- 10 PPM on OPT-301-9, Step B.1.

Comment: SAT UNSAT Perform Step: 8 Determine the xenon worth and samarium worth as described in this section.

• Enter the shutdown date, time and duration.

• IF the reactor is subcritical in MODE 2, 3, 4 or 5, THEN record the date and time that the reactor achieved 0% RTP and the duration of the shutdown from that point to the time of the SDM calculation.

Standard: RECORD Date, Time and 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> since time of the trip on OPT-301-9, Step C.1.

Comment: SAT UNSAT NUREG 1021, Revision 9.1 Page 5 of 9CPNPP Mar 2009 RO & SRO Admin JPM A.1.a Rev Final.doc

Appendix C JPM STEPS Form ES-C-1 Perform Step: 9 Determine the xenon worth and samarium worth as described in this section.

• Enter the Power or Power-at-trip as follows:

• If the reactor is subcritical in MODE 2, 3, 4 or 5 AND it is desired to use tables from the NDR to determine xenon or samarium worth based on the following restrictions, THEN check the Power At Trip box AND enter the power level at time of trip:

• The reactor tripped from equilibrium conditions.

Standard: CHECK Power at Trip box and RECORD 100% on OPT-301-9, Step C.2.

Comment: SAT UNSAT Perform Step: 10 Determine the xenon worth at the current plant condition.

• With equilibrium conditions while the core is critical in MODE 1 or 2 OR with the core subcritical in MODE 2, 3, 4 or 5 following equilibrium conditions at time of reactor shutdown, it is preferable to use NDR Tables indicated below and the duration in C.1.

Standard: PLOT 100% vs 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> on NDR Table 5.20 and INTERPOLATE between 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> value. RECORD 4505 +/- 10 pcm on OPT-301-9, Step C.3.

Comment: SAT UNSAT Perform Step: 11 Determine the samarium worth at the current plant condition.

• With equilibrium conditions while the core is critical in MODE 1 or 2 OR with the core subcritical in MODE 2, 3, 4 or 5 following equilibrium conditions at time of reactor shutdown, it is preferable to use NDR Tables for the equilibrium value (time after plant trip = 0).

Standard: REFER to NDR Table 5.23 and CHOOSE the T=0 value for 100%

power and RECORD 1057 pcm on OPT-301-9, Step C.4.

Comment: SAT UNSAT NUREG 1021, Revision 9.1 Page 6 of 9CPNPP Mar 2009 RO & SRO Admin JPM A.1.a Rev Final.doc

Appendix C JPM STEPS Form ES-C-1 Perform Step: 12 Determine the Shutdown Margin boron concentration as described in this section.

• Determine the IBW using NDR Table 5.9.

Standard: REFER to NDR Table 5.9 and PLOT 1171 +/- 10 ppm vs 475°F and interpolate between the values at 1150 ppm and 1200 ppm. RECORD 11415 +/- 50 pcm on OPT-301-9, Step D.1.

Comment: SAT UNSAT Perform Step: 13 Determine the Shutdown Margin boron concentration as described in this section.

• Determine most reactive RCCA worth using the MOST REACTIVE RCCA STUCK OUT value from NDR Table 6.1,

SUMMARY

OF REACTIVITY REQUIREMENTS AND SHUTDOWN MARGIN (use the highest value for Stuck Rod).

Standard: REFER to NDR Table 6.1 and DETERMINE most reactive stuck rod worth at EOL and RECORD 877 pcm on OPT-301-9, Step D.2.

Comment: SAT UNSAT Perform Step: 14 Determine the Shutdown Margin boron concentration as described in this section.

• Calculate the worth correction using the formula shown on OPT-301-9.

Standard: ADD 4505 pcm and 1057 pcm = 5562 +/- 10 pcm. RECORD 5562 +/- 10 pcm on OPT-301-9, Step D.3.

Comment: SAT UNSAT Perform Step: 15 Determine the Shutdown Margin boron concentration as described in this section.

• Determine the boron correction factor using NDR Figure 5.35, BORON CORRECTION FACTOR AS A FUNCTION OF XENON AND EFFECTIVE SAMARIUM WORTH.

Standard: PLOT 5562 +/- 10 pcm on NDR Figure 5.35 and RECORD 0.9275 +/-

0.005 on OPT-301-9, Step D.4.

Comment: SAT UNSAT NUREG 1021, Revision 9.1 Page 7 of 9CPNPP Mar 2009 RO & SRO Admin JPM A.1.a Rev Final.doc

Appendix C JPM STEPS Form ES-C-1 Perform Step: 16 Determine the Shutdown Margin boron concentration as described in this section.

• Calculate the integral boron worth for minimum Shutdown Margin by using the formula shown on OPT-301-9.

Standard: 11415 - 5562 / 0.9275 = 6428 RECORD 6307 +/- 10 pcm on OPT-301-9, Step D.5.

Comment: SAT UNSAT Perform Step: 17 Determine the Shutdown Margin boron concentration as described in this section.

• Determine the Shutdown Margin boron concentration using the NDR Table 5.9 for EOL.

Standard: PLOT 475°F and 6310 pcm on NDR Table 5.9 and INTERPOLATE between the 600 ppm and 650 ppm values.

RECORD 630 +/- 15 ppm on OPT-301-9, Step D.6.

Comment: SAT UNSAT Perform Step: 18 Determine if the Shutdown Margin acceptance criteria is satisfied by the relationships shown on OPT-301-9.

• Circle the appropriate result of the SDM determination, YES or NO.

Standard: COMPARE current RCS Boron concentration of 593 ppm to required Boron concentration of 630 +/- 15 ppm, and DETERMINE Shutdown Margin is not being met. CIRCLE the NO box on OPT-301-9, Step F.1.

Terminating Cue: This JPM is complete.

Comment: SAT UNSAT STOP TIME:

NUREG 1021, Revision 9.1 Page 8 of 9CPNPP Mar 2009 RO & SRO Admin JPM A.1.a Rev Final.doc

Appendix C JPM CUE SHEET Form ES-C-1 INITIAL CONDITIONS: At 1200 on 03/02/2009 the Unit 1 Reactor was tripped from 100%

power and the Control Room was evacuated due to a fire. A plant cooldown was initiated at 1500 and RCS temperatures from the Remote Shutdown Panel are as follows:

• Reactor Coolant System temperature is 485°F.

• A SHUTDOWN MARGIN calculation is required every hour while cooling down from the Remote Shutdown Panel.

• RCS boron concentration at the time of trip was 400 ppm.

• At 1445, concentration by sample was 593 ppm.

• All control rods were fully inserted on the trip.

• Core Burnup is 18,500 MWD/MTU.

• Unit 1 was stable at 100% power for 47 days prior to the trip.

• A Subcritical Margin Calculation is NOT required.

INITIATING CUE: The Unit Supervisor directs you to PERFORM the 1500 SHUTDOWN MARGIN Calculation per OPT-301, Reactor Shutdown Margin Verification.

• SDM Boron Concentration __________ ppm

• SDM Acceptance Criteria Satisfied YES / NO (Circle one)

NUREG 1021, Revision 9.1 Page 9 of 9CPNPP Mar 2009 RO & SRO Admin JPM A.1.a Rev Final.doc

Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC RO/SRO A.1.b Task # RO1413 K/A # 2.1.23 4.3 / 4.4

Title:

Determine Time to Core Uncovery on a Loss of RHR Examinee (Print):

Testing Method:

Simulated Performance: Classroom: X Actual Performance: X Simulator:

Plant:

READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.

When you complete the task successfully, the objective for this JPM will be satisfied.

Initial Conditions: Given the following conditions:

• Unit 2 is in Mode 5 with water level in the Reactor Vessel at 53 above the core plate.

• The Pressurizer manway has been removed.

• Reactor Coolant System temperature is 100°F.

• The Reactor was shutdown on February 2nd at 12:00 noon after operating at 100% power for the last 100 days.

• Today is February 12th and the Unit experienced a total loss of Residual Heat Removal cooling at 1215 PM.

Initiating Cue: The Unit Supervisor directs you to PERFORM the following per ABN-104, Residual Heat Removal System Malfunction, Attachments 5 and 19:

• DETERMINE Time to Saturation _______________

• DETERMINE Time to Core Uncovery _______________

• DETERMINE Containment Closure time _______________

Task Standard: Correctly perform Critical Steps of ABN-104.

Required Materials: ABN-104, Residual Heat Removal System Malfunction, Rev. 8, PCN-4 Validation Time: 15 minutes Time Critical: N/A Completion Time: ________ minutes NUREG 1021, Revision 9.1 Page 1 of 5CPNPP Mar 2009 RO & SRO Admin JPM A.1.b Rev Final.doc

Appendix C JPM WORKSHEET Form ES-C-1 Comments:

Result: SAT UNSAT Examiner (Print / Sign): Date:

NUREG 1021, Revision 9.1 Page 2 of 5CPNPP Mar 2009 RO & SRO Admin JPM A.1.b Rev Final.doc

Appendix C JPM WORKSHEET Form ES-C-1 CLASSROOM SETUP EXAMINER:

PROVIDE the examinee with a copy of:

• ABN-104, Residual Heat Removal System Malfunction, Attachments 5 and 19.

NUREG 1021, Revision 9.1 Page 3 of 5CPNPP Mar 2009 RO & SRO Admin JPM A.1.b Rev Final.doc

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Perform Step: 1 Determine Time to Saturation:

• Calculate TIME AFTER SHUTDOWN.

Standard: CALCULATE TIME AFTER SHUTDOWN = 240 hours0.00278 days <br />0.0667 hours <br />3.968254e-4 weeks <br />9.132e-5 months <br /> and 15 minutes.

Comment: SAT UNSAT Perform Step: 2 Determine Time to Saturation:

• Find TIME TO SATURATION from Attachment 5, Page 1.

Standard: REFER to Page 1 of Attachment 5 and PLOT the intersection of TIME AFTER SHUTDOWN (240 hours0.00278 days <br />0.0667 hours <br />3.968254e-4 weeks <br />9.132e-5 months <br />) and INITIAL TEMP (100°F) and DETERMINE:

TIME TO SATURATION = 19 +/- 1 minutes.

Comment: SAT UNSAT Perform Step: 3 Determine Time to Core Uncovery:

• Find TIME TO CORE UNCOVERY from Attachment 5, Page 2 Standard: REFER to Page 2 of Attachment 5 and PLOT the intersection of TIME AFTER SHUTDOWN (10 days) and INITIAL RCS LEVEL (53 inches above the core plate) and DETERMINE:

TIME TO CORE UNCOVERY = 1.9 +/- 0.1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

Comment: SAT UNSAT Perform Step: 4 Determine Containment Closure time:

• Find CONTAINMENT CLOSURE TIME from Attachment 19.

Standard: REFER to Attachment 19 of ABN-104 and PLOT the intersection of Time After Shutdown and RADIOLOGICAL ENVIRONMENT CURVE and DETERMINE:

CONTAINMENT CLOSURE TIME = 60 +/- 10 minutes.

Terminating Cue: This JPM is complete.

Comment: SAT UNSAT STOP TIME:

NUREG 1021, Revision 9.1 Page 4 of 5CPNPP Mar 2009 RO & SRO Admin JPM A.1.b Rev Final.doc

Appendix C JPM CUE SHEET Form ES-C-1 INITIAL CONDITIONS: Given the following conditions:

• Unit 2 is in Mode 5 with water level in the Reactor Vessel at 53 above the core plate.

• The Pressurizer manway has been removed.

• Reactor Coolant System temperature is 100°F.

• The Reactor was shutdown on February 2nd at 12:00 noon after operating at 100% power for the last 100 days.

• Today is February 12th and the Unit experienced a total loss of Residual Heat Removal cooling at 1215 PM.

INITIATING CUE: The Unit Supervisor directs you to PERFORM the following per ABN-104, Residual Heat Removal System Malfunction, Attachments 5 and 19:

• DETERMINE Time to Saturation _______________

• DETERMINE Time to Core Uncovery _______________

• DETERMINE Containment Closure time _______________

NUREG 1021, Revision 9.1 Page 5 of 5CPNPP Mar 2009 RO & SRO Admin JPM A.1.b Rev Final.doc

Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC RO A.2 Task # RO5013 K/A # 2.2.37 3.6 / 4.6

Title:

Verify Pressurizer Heater Bank Operability Examinee (Print):

Testing Method:

Simulated Performance: Classroom:

Actual Performance: X Simulator: X Plant:

READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.

When you complete the task successfully, the objective for this JPM will be satisfied.

Initial Conditions: Unit 1 is in MODE 4 performing a Plant Heatup to MODE 3 per IPO-001A, Plant Heatup From Cold Shutdown To Hot Standby.

Initiating Cue: The Unit Supervisor directs you to VERIFY Pressurizer Heater Operability per IPO-001A, Plant Heatup From Cold Shutdown To Hot Standby, Section 5.3, Heatup and Pressurization for MODE 3 Entry, Step 5.3.1.

• Pressurizer Heater OPERABILITY Satisfied (Circle one):

• YES / NO Task Standard: Locate and correctly perform Critical Steps of IPO-001A.

Required Materials: IPO-001A, Plant Heatup From Cold Shutdown To Hot Standby, Rev. 20, PCN-11 Validation Time: 20 minutes Time Critical: N/A Completion Time: ________ minutes Comments:

Result: SAT UNSAT Examiner (Print / Sign): Date:

NUREG 1021, Revision 9.1 Page 1 of 6 CPNPP Mar 2009 RO Admin JPM A.2 Rev Final.doc

Appendix C JPM WORKSHEET Form ES-C-1 SIMULATOR SETUP BOOTH OPERATOR:

INITIALIZE to IC-5 or any Mode 4 Initial Condition and then perform the following:

• VERIFY Pressurizer Heater Groups are OPERABLE.

• PLACE MANUAL flags on the following instruments:

• 1-PK-455A, PRZR PRESS CTRL Controller.

• 1-PK-455B, RC LOOP 1 SPR VLV CTRL Controller.

• 1-PK-455C, RC LOOP 4 SPR VLV CTRL Controller.

PERFORM the following after each JPM:

• CLEAR data from the Plant Computer.

EXAMINER:

PROVIDE the examinee with a copy of:

• IPO-001A, Plant Heatup from Cold Shutdown to Hot Standby with initials and N/As as appropriate up to Step 5.3.1.

NUREG 1021, Revision 9.1 Page 2 of 6 CPNPP Mar 2009 RO Admin JPM A.2 Rev Final.doc

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Perform Step: 1 Verify at least two groups of pressurizer heaters have a capacity of at least 150 KW each.

• Energize each group of heaters, as required, to measure current.

Standard: ENERGIZE Backup Heater Group A by SELECTING 1/1-PCPR1, PRZR BACKUP HTR GROUP A to ON.

Comment: SAT UNSAT Perform Step: 2 Verify at least two groups of pressurizer heaters have a capacity of at least 150 KW each.

• Record voltage and current AND calculate power for each group of heaters. (Voltage x current x 0.001732 = power)

Standard: RECORD Voltage from 1EB3 or V6303A and Current from 1-II-PCPR1 or A6801A.

• PERFORM and RECORD the power calculation and VERIFY result is greater than 150 KW.

Examiner Cue: If contacted, REPORT as PEO that 1EB3 voltage is 488 volts.

Comment: SAT UNSAT Perform Step: 3 Verify at least two groups of pressurizer heaters have a capacity of at least 150 KW each.

• Energize each group of heaters, as required, to measure current.

Standard: ENERGIZE Backup Heater Group B by SELECTING 1/1-PCPR2, PRZR BACKUP HTR GROUP B to ON.

Comment: SAT UNSAT Perform Step: 4 Verify at least two groups of pressurizer heaters have a capacity of at least 150 KW each.

• Record voltage and current AND calculate power for each group of heaters. (Voltage x current x 0.001732 = power)

Standard: RECORD Voltage from 1EB2 or V6302A and Current from 1-II-PCPR2 or A6802A.

• PERFORM and RECORD the power calculation and VERIFY result is greater than 150 KW.

Examiner Cue: If contacted, REPORT as PEO that 1EB2 voltage is 488 volts.

Comment: SAT UNSAT NUREG 1021, Revision 9.1 Page 3 of 6 CPNPP Mar 2009 RO Admin JPM A.2 Rev Final.doc

Appendix C JPM STEPS Form ES-C-1 Examiner Note: The operator may choose not to energize the group C heaters as it requires lowering the demand on the master pressure controller which impacts plant pressure. The operator may determine that two other heaters are operable satisfying the operability check and not energize the group C heaters due to plant conditions.

Perform Step: 5 Verify at least two groups of pressurizer heaters have a capacity of at least 150 KW each.

• Energize each group of heaters, as required, to measure current.

Standard: ENERGIZE Control Heater Group C by SELECTING 1/1-PCPR, PRZR CTRL HTR GROUP C to ON.

Comment: SAT UNSAT Perform Step: 6 Verify at least two groups of pressurizer heaters have a capacity of at least 150 KW each.

• Record voltage and current AND calculate power for each group of heaters. (Voltage x current x 0.001732 = power)

Standard: RECORD Voltage from 1EB1 or V6301A and Current from 1-II-PCPR or A6803A.

• PERFORM and RECORD the power calculation and VERIFY result is greater than 150 KW.

Examiner Cue: If contacted, REPORT as PEO that 1EB1 voltage is 488 volts.

Comment: SAT UNSAT Perform Step: 7 Verify at least two groups of pressurizer heaters have a capacity of at least 150 KW each.

• Energize each group of heaters, as required, to measure current.

Standard: ENERGIZE Backup Heater Group D by SELECTING 1/1-PCPR3, PRZR BACKUP HTR GROUP D to ON.

Comment: SAT UNSAT NUREG 1021, Revision 9.1 Page 4 of 6 CPNPP Mar 2009 RO Admin JPM A.2 Rev Final.doc

Appendix C JPM STEPS Form ES-C-1 Perform Step: 8 Verify at least two groups of pressurizer heaters have a capacity of at least 150KW each.

• Record voltage and current AND calculate power for each group of heaters. (Voltage x current x 0.001732 = power)

Standard: RECORD Voltage from 1EB4 or V6304A and Current from 1-II-PCPR3 or A6804A.

• PERFORM and RECORD the power calculation and VERIFY result is greater than 150 KW.

Examiner Cue: If contacted, REPORT as PEO that 1EB4 voltage is 488 volts.

Comment: SAT UNSAT Perform Step: 9 Operate pressurizer heaters as needed for plant conditions.

Standard: CONTROL Pressurizer Heaters manually to maintain pressure in band.

Examiner Cue: Stabilize pressure at existing pressure +/- 25 psig.

Comment: SAT UNSAT Perform Step: 10 IF any group(s) of pressurizer heaters does NOT have a capacity of 150 KW, THEN initiate a LCOAR per ODA-308.

Standard: DETERMINE all Pressurizer Heater Groups are OPERABLE.

Terminating Cue: This JPM is complete.

Comment: SAT UNSAT STOP TIME:

NUREG 1021, Revision 9.1 Page 5 of 6 CPNPP Mar 2009 RO Admin JPM A.2 Rev Final.doc

Appendix C JPM CUE SHEET Form ES-C-1 INITIAL CONDITIONS: Unit 1 is in MODE 4 performing a Plant Heatup to MODE 3 per IPO-001A, Plant Heatup From Cold Shutdown To Hot Standby.

INITIATING CUE: The Unit Supervisor directs you to VERIFY Pressurizer Heater Operability per IPO-001A, Plant Heatup From Cold Shutdown To Hot Standby, Section 5.3, Heatup and Pressurization for MODE 3 Entry, Step 5.3.1.

• Pressurizer Heater OPERABILITY Satisfied (Circle one):

• YES / NO NUREG 1021, Revision 9.1 Page 6 of 6 CPNPP Mar 2009 RO Admin JPM A.2 Rev Final.doc

Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC RO A.3 Task # RO5005 K/A # 2.3.7 3.5 / 3.6

Title:

Determine RWP Entry Requirements and Identify Low Dose Waiting Area Examinee (Print):

Testing Method:

Simulated Performance: Classroom: X Actual Performance: X Simulator:

Plant:

READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.

When you complete the task successfully, the objective for this JPM will be satisfied.

Initial Conditions: There is a leak on the sample line from Steam Generator 1-03. A clearance DANGER tag must be hung on 1MS-0159, SG 1-03 SMPL ISOL VLV 2407 UPSTRM ISOL VLV SB 810 NORTH PENETRATION VLV RM

// N. SIDE to isolate the sample line as it leaves Containment.

Initiating Cue: The Unit Supervisor directs you to PERFORM the following:

• DETERMINE the Dose Monitoring Requirements to enter the area where the valve is located.

• DETERMINE the Protective Clothing Requirements to enter the area where the valve is located.

• IDENTIFY the Low Dose Waiting Area for the room you will be entering and the dose rate in that area.

Task Standard: Correctly perform Critical Steps of STA-656 and RPI-606.

Required Materials: STA-656, Radiation Work Control, Rev.14 STA-656-2, CPSES Radiation Work Permit, Rev. 4 STA-660, Control of High Radiation Areas, Rev. 13 RPI-606, Radiation Work and General Access Permits, Rev. 18 Valve Locator Map for Unit 1 Safeguards Building EL 810 Room #S 77N and 77S Survey Map for U-1 SG 810 Pipe Pen Area Train B 1-077A Validation Time: 20 minutes Time Critical: N/A Completion Time: ________ minutes Comments:

Result: SAT UNSAT Examiner (Print / Sign): Date:

NUREG 1021, Revision 9.1 Page 1 of 4 CPNPP Mar 2009 RO Admin JPM A.3 Rev Final.doc

Appendix C JPM WORKSHEET Form ES-C-1 CLASSROOM SETUP EXAMINER:

PROVIDE the examinee with a copy of:

• STA-656-2, CPSES Radiation Work Permit.

• Valve Locator Map for Unit 1 Safeguards Building EL 810 Room #S 77N and 77S.

• Survey Map for U-1 SG 810 Pipe Pen Area Train B 1-077A.

PROVIDE the following references:

• STA-656, Radiation Work Control.

• STA-660, Control of High Radiation Areas.

• RPI-606, Radiation Work and General Access Permits.

NUREG 1021, Revision 9.1 Page 2 of 4 CPNPP Mar 2009 RO Admin JPM A.3 Rev Final.doc

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Perform Step: 1 Determine location of 1MS-0159 with respect to the survey map.

Standard: LOCATE 1MS-0159 using the Valve Locator Map for Unit 1 Safeguards Building EL 810 Room #S 77N and 77S and COMPARE the location to the survey map. DETERMINE 1MS-0159 is located inside the High Radiation Area, near a Hot Spot and the area is contaminated.

Comment: SAT UNSAT Perform Step: 2 Review the RWP and STA-660 for requirements to enter the High Radiation / Contaminated Area.

Standard: DETERMINE the Dose Monitoring Requirements to enter the area where the valve is located includes High Radiation Area Entry Requirements:

• Dosimetry, in addition to OSL Badge, consisting of a radiation monitoring device which continuously indicates the radiation dose rate in the area, or

• Electronic Dosimeter, or

• Radiation Protection coverage.

Comment: SAT UNSAT Perform Step: 3 Review the RWP and STA-660 for requirements to enter the High Radiation / Contaminated Area.

Standard: DETERMINE the Protective Clothing Requirements to enter the area where the valve is located includes Contaminated Area Entry Requirements:

• Cloth Booties, Cloth Coveralls, and Cloth Hood

• Glove Liners

• Rubber Gloves and Rubber Overshoes Comment: SAT UNSAT Perform Step: 4 Determine Low Dose Waiting Area and the dose rate in that area.

Standard: DETERMINE that once inside the HRA the Low Dose Waiting Area is at the South end near the entrance with a Dose Rate of 1.7 mrem/hr.

Terminating Cue: This JPM is complete.

Comment: SAT UNSAT STOP TIME:

NUREG 1021, Revision 9.1 Page 3 of 4 CPNPP Mar 2009 RO Admin JPM A.3 Rev Final.doc

Appendix C JPM CUE SHEET Form ES-C-1 INITIAL CONDITIONS: There is a leak on the sample line from Steam Generator 1-03. A clearance DANGER tag must be hung on 1MS-0159, SG 1-03 SMPL ISOL VLV 2407 UPSTRM ISOL VLV SB 810 NORTH PENETRATION VLV RM // N. SIDE to isolate the sample line as it leaves Containment.

INITIATING CUE: The Unit Supervisor directs you to PERFORM the following:

• DETERMINE the Dose Monitoring Requirements to enter the area where the valve is located.

• DETERMINE the Protective Clothing Requirements to enter the area where the valve is located.

• IDENTIFY the Low Dose Waiting Area for the room you will be entering and the dose rate in that area.

Dose Monitoring Requirements to Enter the Area where the Valve is Located:

Protective Clothing Requirements to Enter the Area where the Valve is Located:

Low Dose Waiting Area (location and area dose rate):

NUREG 1021, Revision 9.1 Page 4 of 4 CPNPP Mar 2009 RO Admin JPM A.3 Rev Final.doc

Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC SRO A.2 Task # SO1202 K/A # 2.2.12 3.7 / 4.1

Title:

Review Centrifugal Charging Pump Surveillance Examinee (Print):

Testing Method:

Simulated Performance: Classroom: X Actual Performance: X Simulator:

Plant:

READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.

When you complete the task successfully, the objective for this JPM will be satisfied.

Initial Conditions: Unit 1 is in MODE 1 and the Surveillance testing of Centrifugal Charging Pump, 1-01, was just completed.

Initiating Cue: The Shift Manager directs you to REVIEW the completed surveillance for Centrifugal Charging Pump, 1-01 and CIRCLE each Acceptance Criteria:

• Step 8.2.1.G, 1-FI-121A Flow of 80 gpm SAT / UNSAT

• Step 8.2.1.J, CCP 1-01 Diff Press (P) SAT / UNSAT

• Step 8.2.1.J, Vibration Amplitude SAT / UNSAT

• Step 8.2.1.J, Run Time SAT / UNSAT

• Step 8.2.1.L, 1-FI-121A CHRG Flow SAT / UNSAT

• Step 8.2.1.Q, Loop Charging Flow SAT / UNSAT

• Step 8.2.1.S, Head/Flow Curve ABOVE / BELOW

• Step 8.2.1.T, Full Stroke Closed Test SAT / UNSAT

• Step 8.2.1.U, 1-8381 Full Stroke Open SAT / UNSAT

• Step 8.2.1.U, Charging Check Valve Open SAT / UNSAT

• Step 8.2.1.V, Measured Data Within Limits YES / NO

• Step 8.2.1.V, Tech Spec ACTION Required YES / NO Task Standard: Locate and correctly perform Critical Steps of OPT-201A.

Required Materials: OPT-201A, Charging System, Rev. 13, PCN-7 OPT-201A-2, Centrifugal Charging Pump 01 Data Sheet, Rev. 15 NUREG 1021, Revision 9.1 Page 1 of 8 CPNPP Mar 2009 SRO Admin JPM A.2 Rev Final.doc

Appendix C JPM WORKSHEET Form ES-C-1 Validation Time: 25 minutes Time Critical: N/A Completion Time: ________ minutes Comments:

Result: SAT UNSAT Examiner (Print / Sign): Date:

NUREG 1021, Revision 9.1 Page 2 of 8 CPNPP Mar 2009 SRO Admin JPM A.2 Rev Final.doc

Appendix C JPM WORKSHEET Form ES-C-1 CLASSROOM SETUP EXAMINER:

PROVIDE the examinee with a copy of:

• OPT-201A, Charging System and a completed OPT-201A-2, Centrifugal Charging Pump 01 Data Sheet.

NUREG 1021, Revision 9.1 Page 3 of 8 CPNPP Mar 2009 SRO Admin JPM A.2 Rev Final.doc

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Perform Step: 1 Reviews Centrifugal Charging Pump 01 Data Sheet:

• Step 8.2.1.G 1-FI-121 Flow is 80 GPM.

Standard: DETERMINE documented flow of 80 GPM is SAT.

Comment: SAT UNSAT Perform Step: 2 Reviews Centrifugal Charging Pump 01 Data Sheet:

• Verify documentation of Step 8.2.1.H Data.

Standard: DETERMINE Step 8.2.1.H Data is documented.

Comment: SAT UNSAT Perform Step: 3 Reviews Centrifugal Charging Pump 01 Data Sheet:

• Verify pump data Step 8.2.1.J is documented and pump head calculation is correct and is within limits.

Standard: DETERMINE pump data Step 8.2.1.J is 2387 PSID which is LESS than the required minimum of ACTION LIMIT LOW (2400.2) and is UNSAT.

Comment: SAT UNSAT Perform Step: 4 Reviews Centrifugal Charging Pump 01 Data Sheet:

• Verify Step 8.2.1.J vibration measurements are within specifications given.

Standard: DETERMINE all vibration readings are SAT.

Comment: SAT UNSAT Perform Step: 5 Reviews Centrifugal Charging Pump 01 Data Sheet:

• Verify temperatures and times in Step 8.2.1.J are documented.

Standard: DETERMINE that temperatures in Step 8.2.1.J are documented; however, the time documented does NOT meet the requirement for a minimum of two (2) minutes at the test parameters and is UNSAT.

Comment: SAT UNSAT NUREG 1021, Revision 9.1 Page 4 of 8 CPNPP Mar 2009 SRO Admin JPM A.2 Rev Final.doc

Appendix C JPM STEPS Form ES-C-1 Perform Step: 6 Reviews Centrifugal Charging Pump 01 Data Sheet:

• Verify charging flow documented and within specification in Step 8.2.1.L.

Standard: DETERMINE charging flow is documented and greater than or equal to 100 GPM and is SAT.

Comment: SAT UNSAT Perform Step: 7 Reviews Centrifugal Charging Pump 01 Data Sheet :

• Verify Step 8.2.1.L seal injection flows and charging pump suction and discharge pressures documented.

Standard: DETERMINE seal injection flows, Charging Pump suction and discharge pressures are documented and Charging flow is 100 GPM is SAT.

Comment: SAT UNSAT Perform Step: 8 Reviews Centrifugal Charging Pump 01 Data Sheet:

• Verify Step 8.2.1.M 1/1-8110 and 1/1-8111 are documented as open.

Standard: DETERMINE Step 8.2.1.M 1/1-8110 and 1/1-8111 are documented as OPEN.

Comment: SAT UNSAT Perform Step: 9 Reviews Centrifugal Charging Pump 01 Data Sheet:

• Verify Step 8.2.1.P seal injection flows and calculations.

Standard: DETERMINE proper values from Step 8.2.1.L and that the flow calculation is 35.3 GPM.

Comment: SAT UNSAT Perform Step: 10 Reviews Centrifugal Charging Pump 01 Data Sheet:

• Verify Step 8.2.1.Q charging flow data and calculation is accurate and greater than 50 GPM.

Standard: DETERMINE that Step 8.2.1.Q charging flow calculation data is correct and flow is 66.7 GPM. VERIFY calculated flow is > 50 GPM and is SAT.

Comment: SAT UNSAT NUREG 1021, Revision 9.1 Page 5 of 8 CPNPP Mar 2009 SRO Admin JPM A.2 Rev Final.doc

Appendix C JPM STEPS Form ES-C-1 Perform Step: 11 Reviews Centrifugal Charging Pump 01 Data Sheet:

• Verify Step 8.2.1.R pump head calculation and data is correct.

Standard: DETERMINE Step 8.2.1.R pump head calculation and data is correct.

Comment: SAT UNSAT Perform Step: 12 Reviews Centrifugal Charging Pump 01 Data Sheet:

• Verify Step 8.2.1.S calculated head is above the Figure 1 curve.

Standard: DETERMINE that calculated pump head is BELOW the Figure 1 curve.

Comment: SAT UNSAT Perform Step: 13 Reviews Centrifugal Charging Pump 01 Data Sheet:

• Verify Step 8.2.1.T 1-8481B, 1-8497 and 1-8480B full closed stroke test is satisfactory by flow being greater than or equal to 50 GPM and above the Figure 1 curve.

Standard: DETERMINE that flow is greater than 50 GPM but is BELOW Figure 1 curve and pump head and closure tests are UNSAT.

Comment: SAT UNSAT Perform Step: 14 Reviews Centrifugal Charging Pump 01 Data Sheet:

• Verify Step 8.2.1.U 1-8381 full open by flow being greater than or equal to 50 GPM.

Standard: DETERMINE 1-8381 full open test is greater than 50 GPM flow and is SAT.

Comment: SAT UNSAT Perform Step: 15 Reviews Centrifugal Charging Pump 01 Data Sheet:

• Verify Step 8.2.1.U charging line check valve tested is circled.

Standard: DETERMINE Step 8.2.1.U Charging Line check valve tested is CIRCLED.

Comment: SAT UNSAT NUREG 1021, Revision 9.1 Page 6 of 8 CPNPP Mar 2009 SRO Admin JPM A.2 Rev Final.doc

Appendix C JPM STEPS Form ES-C-1 Perform Step: 16 Reviews Centrifugal Charging Pump 01 Data Sheet:

• Verify Step 8.2.1.U selected check valve full open test results are greater than 50 GPM.

Standard: DETERMINE Step 8.2.1.U selected check valve full open test results are greater than 50 GPM and is SAT.

Comment: SAT UNSAT Perform Step: 17 Reviews Centrifugal Charging Pump 01 Data Sheet:

• Step 8.2.1.V Verify measured data is within limits.

Standard: DETERMINE that measured data is NOT within limits and CIRCLE NO and Technical Specification ACTION is required and CIRCLE YES.

Terminating Cue: This JPM is complete.

Comment: SAT UNSAT STOP TIME:

NUREG 1021, Revision 9.1 Page 7 of 8 CPNPP Mar 2009 SRO Admin JPM A.2 Rev Final.doc

Appendix C JPM CUE SHEET Form ES-C-1 INITIAL CONDITIONS: Unit 1 is in MODE 1 and the Surveillance testing of Centrifugal Charging Pump, 1-01, was just completed.

INITIATING CUE: The Shift Manager directs you to REVIEW the completed surveillance for Centrifugal Charging Pump, 1-01 and CIRCLE each Acceptance Criteria:

• Step 8.2.1.G, 1-FI-121A Flow of 80 gpm SAT / UNSAT

• Step 8.2.1.J, CCP 1-01 Diff Press (P) SAT / UNSAT

• Step 8.2.1.J, Vibration Amplitude SAT / UNSAT

• Step 8.2.1.J, Run Time SAT / UNSAT

• Step 8.2.1.L, 1-FI-121A CHRG Flow SAT / UNSAT

• Step 8.2.1.Q, Loop Charging Flow SAT / UNSAT

• Step 8.2.1.S, Head/Flow Curve ABOVE / BELOW

• Step 8.2.1.T, Full Stroke Closed Test SAT / UNSAT

• Step 8.2.1.U, 1-8381 Full Stroke Open SAT / UNSAT

• Step 8.2.1.U, Charging Check Valve Open SAT / UNSAT

• Step 8.2.1.V, Measured Data Within Limits YES / NO

• Step 8.2.1.V, Tech Spec ACTION Required YES / NO NUREG 1021, Revision 9.1 Page 8 of 8 CPNPP Mar 2009 SRO Admin JPM A.2 Rev Final.doc

Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC SRO A.3 Task # SO1039 K/A # 2.3.6 2.0 / 3.8

Title:

Approve a Liquid Waste Release Permit Examinee (Print):

Testing Method:

Simulated Performance: Classroom: X Actual Performance: X Simulator:

Plant:

READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.

When you complete the task successfully, the objective for this JPM will be satisfied.

Initial Conditions: Unit 1 is shutdown for Refueling and the following conditions exist:

• Residual Heat Removal Pump 1-01 is operating with Residual Heat Removal Pump 1-02 in standby.

• Circulating Water Pump 1-03 is operating and the water boxes are open on the other three Circulating Water Pumps.

• X-RE-5253, Liquid Waste Effluent Radiation Monitor is out-of-service.

• Waste Water Holdup Tank #2 is being released.

• Unit 2 is operating at 100% with all systems in normal alignments.

• The previous shift placed Plant Effluent Tank (PET) #1 on recirculation and initiated a request for release.

• The permit has just been received in the Control Room to release PET #1 and the Unit 1 Circulating Water System has been selected as the discharge path.

Initiating Cue: The Shift Manager directs you to REVIEW the Release Permit and Plant Conditions and CIRCLE the results:

• Correct tank is being discharged YES / NO

• Radiation Monitor is OPERABLE YES / NO

• LCOAR is required YES / NO

• STA-603-13 is required YES / NO

• Unit #1 Discharge flowpath allowed YES / NO

• Unit #2 Discharge flowpath allowed YES / NO

• PET & WWHT simultaneous release allowed YES / NO Task Standard: Locate and correctly perform Critical Steps of STA-603.

NUREG 1021, Revision 9.1 Page 1 of 5 CPNPP Mar 2009 SRO Admin JPM A.3 Rev Final.doc

Appendix C JPM WORKSHEET Form ES-C-1 Required Materials: STA-603, Control of Station Radioactive Effluents, Rev. 20, PCN-1 STA-603-10, Batch Liquid Radioactive Effluent Release Data Sheet, Rev. 17 Validation Time: 10 minutes Time Critical: N/A Completion Time: ________ minutes Comments:

Result: SAT UNSAT Examiner (Print / Sign): Date:

NUREG 1021, Revision 9.1 Page 2 of 5 CPNPP Mar 2009 SRO Admin JPM A.3 Rev Final.doc

Appendix C JPM WORKSHEET Form ES-C-1 CLASSROOM SETUP EXAMINER:

PROVIDE the examinee with a copy of:

• STA-603, Control of Station Radioactive Effluents.

• COMPLETE STA-603-10, Batch Liquid Radioactive Effluent Release Data Sheet up to the Shift Manager review with the following errors:

• NONE of the requirements for X-RE-5253 being OOS will have been performed.

NUREG 1021, Revision 9.1 Page 3 of 5 CPNPP Mar 2009 SRO Admin JPM A.3 Rev Final.doc

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Perform Step: 1 Review Release Permit, STA-603-10, Batch Liquid Radioactive Effluent Release Data Sheet.

Standard: REVIEW STA-603-10, Release Permit and DETERMINE the following:

• Correct tank is being discharged and CIRCLE YES.

• Radiation Monitor is OPERABLE and CIRCLE NO.

• LCOAR is required and CIRCLE YES.

• STA-603-13 is required and CIRCLE YES.

Comment: SAT UNSAT Perform Step: 2 Based on the initial conditions determine the required minimum dilution requirements are not met for a release via Unit 1.

Standard: DETERMINE that a minimum of two Circulating Water pumps are required for a release and CIRCLE Unit #1 Discharge flowpath allowed is NO.

Comment: SAT UNSAT Perform Step: 3 Determine if dilution requirements for release are met on Unit 2.

Standard: DETERMINE that all four Circulating Water Pumps are running on Unit 2 which exceeds the minimum required of two Circulating Water pumps running and CIRCLE Unit #2 Discharge flowpath allowed is YES.

Comment: SAT UNSAT Perform Step: 4 Determine if simultaneous release of the Plant Effluent Tank #1 and Waste Water Holdup Tank #1 is allowed.

Standard: REVIEW STA-603, Control of Station Radioactive Effluents, and DETERMINE that simultaneous release from Plant Effluent Tank #1 and Waste Water Holdup Tank #1 is allowed and CIRCLE YES.

Terminating Cue: This JPM is complete.

Comment: SAT UNSAT STOP TIME:

NUREG 1021, Revision 9.1 Page 4 of 5 CPNPP Mar 2009 SRO Admin JPM A.3 Rev Final.doc

Appendix C JPM CUE SHEET Form ES-C-1 INITIAL CONDITIONS: Unit 1 is shutdown for Refueling and the following conditions exist:

• Residual Heat Removal Pump 1-01 is operating with Residual Heat Removal Pump 1-02 in standby.

• Circulating Water Pump 1-03 is operating and the water boxes are open on the other three Circulating Water Pumps.

• X-RE-5253, Liquid Waste Effluent Radiation Monitor is out-of-service.

• Waste Water Holdup Tank #2 is being released.

• Unit 2 is operating at 100% with all systems in normal alignments.

• The previous shift placed Plant Effluent Tank (PET) #1 on recirculation and initiated a request for release.

• The permit has just been received in the Control Room to release PET #1 and the Unit 1 Circulating Water System has been selected as the discharge path.

INITIATING CUE: The Shift Manager directs you to REVIEW the Release Permit and Plant Conditions and CIRCLE the results:

• Correct tank is being discharged YES / NO

• Radiation Monitor is OPERABLE YES / NO

• LCOAR is required YES / NO

• STA-603-13 is required YES / NO

• Unit #1 Discharge flowpath allowed YES / NO

• Unit #2 Discharge flowpath allowed YES / NO

• PET & WWHT simultaneous release allowed YES / NO NUREG 1021, Revision 9.1 Page 5 of 5 CPNPP Mar 2009 SRO Admin JPM A.3 Rev Final.doc

Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC SRO A.4 Task # SO1138 K/A # 2.4.41 2.9 / 4.6

Title:

Notification Message Form Examinee (Print):

Testing Method:

Simulated Performance: Classroom: X Actual Performance: X Simulator:

Plant:

READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.

When you complete the task successfully, the objective for this JPM will be satisfied.

Initial Conditions: Given the following Unit 1 conditions:

• A Steam Generator Tube Rupture is in progress on Steam Generator #2.

• A Loss of Offsite Power occurred and both Emergency Diesels are supplying Safeguards Buses.

• All Engineered Safety Feature functions have actuated successfully.

• A Main Steam Safety Valve on Steam Generator #2 lifted and will not reseat.

• The Pressurizer is empty.

• Reactor Coolant System pressure has stabilized at approximately 1800 psig.

• Radiation Monitor FFL-160 is reading 10 µc/ml.

• From the plant computer, wind speed is 10 mph at 180° with no precipitation.

• From the plant computer, stability class is E.

• The Shift Manager made his declaration at 1210 on 03/01/2009.

• Radiation Protection estimates the radiological release will last for four (4) hours.

NUREG 1021, Revision 9.1 Page 1 of 5 CPNPP Mar 2009 SRO Admin JPM A.4 Rev Final.doc

Appendix C JPM WORKSHEET Form ES-C-1 Initiating Cue: The Shift Manager directs you to EVALUATE the Notification Message Form and CIRCLE each criteria:

• Line #2 data is SAT / UNSAT

• Line #4 data is SAT / UNSAT

• Line #5 data is SAT / UNSAT

• Line #6 data is SAT / UNSAT

• Line #7 data is SAT / UNSAT

• Line #9 data is SAT / UNSAT

• If required, MAKE any corrections to the Notification Message Form and LIST below:

Task Standard: Locate and correctly perform Critical Steps of EPP-203.

Required Materials: EPP-203, Notifications, Rev. 15 EPP-203-8, Notification Message Form, Rev. 12 EPP-201, Assessment of Emergency Action Levels Emergency Classification and Plan Activation, Rev. 11 Validation Time: 15 minutes Time Critical: N/A Completion Time: ________ minutes Comments:

Result: SAT UNSAT Examiner (Print / Sign): Date:

NUREG 1021, Revision 9.1 Page 2 of 5 CPNPP Mar 2009 SRO Admin JPM A.4 Rev Final.doc

Appendix C JPM WORKSHEET Form ES-C-1 CLASSROOM SETUP EXAMINER:

PROVIDE the examinee with a copy of:

• A completed 203-8, Notification Message Form for the Initial Conditions stated (with errors).

• EPP-203, Notifications.

• EPP-201, Assessment of Emergency Action Levels Emergency Classification and Plan Activation.

NUREG 1021, Revision 9.1 Page 3 of 5 CPNPP Mar 2009 SRO Admin JPM A.4 Rev Final.doc

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Perform Step: 1 Review the provided 203-8, Notification Message Form.

Standard: REVIEW the provided 203-8, Notification Message Form and CIRCLE Line #2 as SAT.

Comment: SAT UNSAT Perform Step: 2 Review the provided 203-8, Notification Message Form.

Standard: DETERMINE that flowpath of 3A, 3J, 3K, and 3H with a classification of SITE AREA EMERGENCY is incorrect for the given conditions and CIRCLE Lines #4 and #5 as UNSAT.

Comment: SAT UNSAT Perform Step: 3 Review the provided 203-8, Notification Message Form.

Standard: REVIEW the provided 203-8, Notification Message Form and CIRCLE Lines #6, #7, and #9 as SAT.

Comment: SAT UNSAT Examiner Note: Based on the Bases for 3J with RCS pressure stabilizing at greater than SI pump discharge head.

Perform Step: 4 Determine correct flowpath and classification.

Standard: DETERMINE correct flowpath for the Notification Message Form is 3A, 3J, 3M, 3N, and 3O and is classified as an ALERT.

Comment: SAT UNSAT Perform Step: 5 Make corrections to the provided 203-8, Notification Message Form.

Standard: CORRECT the Notification Message Form as follows:

• CHANGE Line #4 to ALERT.

• CHANGE Line #5 to 3A, 3J, 3M, 3N, and 3O.

Terminating Cue: This JPM is complete.

Comment: SAT UNSAT STOP TIME:

NUREG 1021, Revision 9.1 Page 4 of 5 CPNPP Mar 2009 SRO Admin JPM A.4 Rev Final.doc

Appendix C JPM CUE SHEET Form ES-C-1 INITIAL CONDITIONS: Given the following Unit 1 conditions:

• A Steam Generator Tube Rupture is in progress on Steam Generator #2.

• A Loss of Offsite Power occurred and both Emergency Diesels are supplying Safeguards Buses.

• All Engineered Safety Feature functions have actuated successfully.

• A Main Steam Safety Valve on Steam Generator #2 lifted and will not reseat.

• The Pressurizer is empty.

• Reactor Coolant System pressure has stabilized at approximately 1800 psig.

• Radiation Monitor FFL-160 is reading 10 µc/ml.

• From the plant computer, wind speed is 10 mph at 180° with no precipitation.

• From the plant computer, stability class is E.

• The Shift Manager made his declaration at 1210 on 03/01/2009.

• Radiation Protection estimates the radiological release will last for four (4) hours.

INITIATING CUE: The Shift Manager directs you to EVALUATE the Notification Message Form and CIRCLE each criteria:

• Line #2 data is SAT / UNSAT

• Line #4 data is SAT / UNSAT

• Line #5 data is SAT / UNSAT

• Line #6 data is SAT / UNSAT

• Line #7 data is SAT / UNSAT

• Line #9 data is SAT / UNSAT

• If required, MAKE any corrections to the Notification Message Form and LIST below:

NUREG 1021, Revision 9.1 Page 5 of 5 CPNPP Mar 2009 SRO Admin JPM A.4 Rev Final.doc

Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # RO NRC S-1 Task # RO1022 K/A # 001.A2.18 3.2 / 3.8 SF-1

Title:

Respond to Continuous Control Rod Withdrawal Examinee (Print):

Testing Method:

Simulated Performance: Classroom:

Actual Performance: X Simulator: X Plant:

READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.

When you complete the task successfully, the objective for this JPM will be satisfied.

Initial Conditions: Given the following conditions:

• Unit 1 Reactor Startup is in progress per IPO-002A, Plant Startup from Hot Standby with Control Bank D at 6 steps.

• Rod Control is in MANUAL.

• The Estimated Critical Condition (ECC) predicts criticality at 100 steps on Control Bank D.

• Core Performance Engineering is performing the 1/M, Inverse Count Rate Ratio (ICRR).

• Current 1/M plot predicts criticality at 90 Steps on Control Bank D.

Initiating Cue: The Unit Supervisor directs you to WITHDRAW Control Bank D to 50 steps per IPO-002A, Plant Startup from Hot Standby, Step 5.2.17.P.

Task Standard: Locate and correctly perform Critical Steps of ABN-712.

Required Materials: IPO-002A, Plant Startup From Hot Standby, Rev. 20, PCN-7 ABN-712, Rod Control System Malfunction, Rev. 10, PCN-10 Validation Time: 4 minutes Time Critical: N/A Completion Time: ________ minutes Comments:

Result: SAT UNSAT Examiner (Print / Sign): Date:

NUREG 1021, Revision 9.1 Page 1 of 6 CPNPP Mar 2009 RO JPM S-1 Rev Final.doc

Appendix C JPM WORKSHEET Form ES-C-1 SIMULATOR SETUP BOOTH OPERATOR:

INITIALIZE to IC-30 (password protected; password = gary) and then PERFORM the following:

• INSERT malfunction RP01, Automatic Reactor Trip Failure.

• INSERT malfunction RP13C, Manual Reactor Trip Failure (both).

• INSERT malfunction RD01D, Continuous Rod Withdrawal (conditional: upon rod withdrawal) when examinee starts rod withdrawal.

• ENSURE Control Bank D is at CBO (6 steps).

• PLACE GTGC MODE 2 on front PC Screen.

EXAMINER:

PROVIDE the examinee with a copy of:

• IPO-002, Plant Startup From Hot Standby, with initials and N/As as appropriate up to Step 5.2.17.P.

NUREG 1021, Revision 9.1 Page 2 of 6 CPNPP Mar 2009 RO JPM S-1 Rev Final.doc

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Booth Operator: ACTIVATE RD01D when rods are being withdrawn.

Perform Step: 1 Verify control bank D begins to withdraw when control bank C reaches 122 steps.

Standard: PLACE 1/1-FLRM, Control Rod Motion Control Switch in the OUT position and WITHDRAW Control Bank D rods.

Comment: SAT UNSAT Examiner Note: Control Bank D rods are at CBO (6 steps) with rod bottom lights off per the Initial Conditions.

Perform Step: 2 IF rod bottom lights are ON, THEN verify the control bank D DRPI rod bottom lights are OFF before the control rods reach 6 steps.

Standard: VERIFY Control Bank D DRPI rod bottom lights are OFF before the control rods reach 6 steps by OBSERVING DRPI Indication.

Comment: SAT UNSAT Perform Step: 3 Release IN-HOLD-OUT Switch after Control Bank D is at 50 steps.

Standard: RELEASE 1/1-FLRM, Control Rod Motion Control Switch when Control Bank D reaches 50 steps on Group 1 and 2 Step Counters and IDENTIFY continued outward rod motion.

Comment: SAT UNSAT Perform Step: 4 Verify Rod Motion - NORMAL

• Rod direction

• Rod speed

• Rod demand

• Rod sequencing

• Bank overlap

• Rod alignment (+/-12 steps)

Standard: DETERMINE rod demand is not normal.

Comment: SAT UNSAT NUREG 1021, Revision 9.1 Page 3 of 6 CPNPP Mar 2009 RO JPM S-1 Rev Final.doc

Appendix C JPM STEPS Form ES-C-1 Perform Step: 5 Perform the following:

• Ensure 1/u-RBSS, CONTROL ROD BANK SELECT - NOT IN AUTO Standard: VERIFY 1/1-RBSS, CONTROL ROD BANK SELECT in MANUAL.

Comment: SAT UNSAT Examiner Note: The following steps represent the alternate path for this JPM.

Perform Step: 6 Perform the following:

• IF any of following occurs, THEN trip Reactor AND GO TO EOP-0.0A/B while other operators continue this procedure:

• Rod motion with NO demand.

• Rod withdrawal with rod insertion demand AND rod motion required.

• Rods stationary with rod insertion required.

• Rods moving in different direction simultaneously AND rod motion required.

Standard: INITIATE a Reactor Trip by PLACING 1/1-RTC, RX TRIP Switch and 1/1-RT, RX TRIP Switch in TRIP position and DETERMINE Reactor is NOT tripped.

Comment: SAT UNSAT Perform Step: 7 Perform the following:

• IF any of following occurs, THEN trip Reactor AND GO TO EOP-0.0A/B while other operators continue this procedure:

• Rod motion with NO demand.

Standard: OPEN CS-1B3-1, INCOMING BREAKER 1B3-1 and CS-1B4-1, INCOMING BREAKER 1B4-1 and OBSERVE green TRIP lights illuminated then RECLOSE CS-1B3-1, INCOMING BREAKER 1B3-1 and CS-1B4-1, INCOMING BREAKER 1B4-1 and OBSERVE red CLOSE lights illuminated.

Comment: SAT UNSAT NUREG 1021, Revision 9.1 Page 4 of 6 CPNPP Mar 2009 RO JPM S-1 Rev Final.doc

Appendix C JPM STEPS Form ES-C-1 Perform Step: 8 Verify Reactor trip.

Standard: VERIFY Reactor Trip by OBSERVING:

• 1-NI-35B, IR CURRENT CHAN I is lowering.

• 1-NI-36B, IR CURRENT CHAN II is lowering.

• 1-NI-35D, IR START-UP RATE is negative.

• 1-NI-36D, IR START-UP RATE is negative.

• All Control Rods INSERTED on CTRL ROD POSN (DRPI).

Terminating Cue: This JPM is complete.

Comment: SAT UNSAT STOP TIME:

NUREG 1021, Revision 9.1 Page 5 of 6 CPNPP Mar 2009 RO JPM S-1 Rev Final.doc

Appendix C JPM CUE SHEET Form ES-C-1 INITIAL CONDITIONS: Given the following conditions:

• Unit 1 Reactor Startup is in progress per IPO-002A, Plant Startup from Hot Standby with Control Bank D at 6 steps.

• Rod Control is in MANUAL.

• The Estimated Critical Condition (ECC) predicts criticality at 100 steps on Control Bank D.

• Core Performance Engineering is performing the 1/M, Inverse Count Rate Ratio (ICRR).

• Current 1/M plot predicts criticality at 90 Steps on Control Bank D.

INITIATING CUE: The Unit Supervisor directs you to WITHDRAW Control Bank D to 50 steps per IPO-002A, Plant Startup from Hot Standby, Step 5.2.17.P.

NUREG 1021, Revision 9.1 Page 6 of 6 CPNPP Mar 2009 RO JPM S-1 Rev Final.doc

Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # RO/SRO NRC S-2 Task # RO1307 K/A # 004.A2.13 3.6 / 3.9 SF-2

Title:

Perform Manual Makeup to the Refueling Water Storage Tank Examinee (Print):

Testing Method:

Simulated Performance: Classroom:

Actual Performance: X Simulator: X Plant:

READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.

When you complete the task successfully, the objective for this JPM will be satisfied.

Initial Conditions: Given the following conditions on Unit 1:

• Refueling Water Storage Tank (RWST) level is currently at 95% and preparations are being made to raise level.

• 8000 gallons of makeup at 2500 ppm boron is required.

• A Boric Acid flowrate of 25 gpm is desired.

• Boric Acid Tank concentration is 7447 ppm.

• All prerequisites have been met and a Tracking LCOAR has been initiated.

• An operator is standing by in the field.

Initiating Cue: The Unit Supervisor directs you to PERFORM a blended makeup of 8000 gallons to the Refueling Water Storage Tank per SOP-104A, Reactor Make-Up And Chemical Control System, Section 5.2.6, Makeup to RWST.

Task Standard: Locate and correctly perform Critical Steps of SOP-104A.

Required Materials: SOP-104A, Reactor Make-Up And Chemical Control System, Rev. 11, PCN-9 TDM-201A, CVCS Calculations/Blended Flow, Rev. 5, PCN-1 TDM-203A, CVCS Controller Data, Rev. 3 Validation Time: 15 minutes Time Critical: N/A Completion Time: ________ minutes NUREG 1021, Revision 9.1 Page 1 of 8 CPNPP Mar 2009 RO & SRO JPM S-2 Rev Final.doc

Appendix C JPM WORKSHEET Form ES-C-1 Comments:

Result: SAT UNSAT Examiner (Print / Sign): Date:

NUREG 1021, Revision 9.1 Page 2 of 8 CPNPP Mar 2009 RO & SRO JPM S-2 Rev Final.doc

Appendix C JPM WORKSHEET Form ES-C-1 SIMULATOR SETUP BOOTH OPERATOR:

INITIALIZE to IC-18 or any MODE 1 Initial Condition and then PERFORM the following:

• ENSURE VCT level is between 56% and 62% to begin JPM.

• When directed by examinee, EXECUTE remote function CVR03, Boric Acid Blender to RWST Isolation Valve [CS-8432, CS-8434] to OPEN.

PERFORM the following after each JPM:

• RESET potentiometer for 1-FK-110 to 3.88.

• RESET potentiometer for 1-FK-111 to 7.50.

• RESET flow counter for 1-FY-110B to 500.

• RESET flow counter for 1-FY-111B to 35.

EXAMINER:

PROVIDE the examinee with a copy of:

• SOP-104A, Reactor Make-Up and Chemical Control System with Prerequisite Section 2.1 signed-off and all other Sections up to 5.2.6 marked as N/A.

• TDM-201A, CVCS Calculations/Blended Flow.

• TDM-203A, CVCS Controller Data.

NUREG 1021, Revision 9.1 Page 3 of 8 CPNPP Mar 2009 RO & SRO JPM S-2 Rev Final.doc

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Perform Step: 1 Ensure the VCT is at the top of its operating band (56-62%).

Standard: VERIFY VCT level is between 56% and 62% by OBSERVING 1-LI-185, VCT LEVEL.

Comment: SAT UNSAT Perform Step: 2 Place 1/1-MU, RCS MU MAN ACT in STOP.

Standard: PLACE 1/1-MU, RCS MU MAN ACT in STOP and OBSERVE green STOP light illuminated.

Comment: SAT UNSAT Perform Step: 3 Place 43/1-MU, RCS MU MODE SELECT in MAN.

Standard: PLACE 43/1-MU, RCS MU MODE SELECT in MAN.

Comment: SAT UNSAT Perform Step: 4 Place 1/1-FCV-111B, RCS MU TO VCT ISOL VLV in CLOSE.

Standard: PLACE 1/1-FCV-111B, RCS MU TO VCT ISOL VLV in CLOSE and OBSERVE green CLOSE light illuminated.

Comment: SAT UNSAT Perform Step: 5 Place 1/1-FCV-110B, RCS MU TO CHRG PMP SUCT ISOL VLV in CLOSE.

Standard: PLACE 1/1-FCV-110B, RCS MU TO CHRG PMP SUCT ISOL VLV in CLOSE and OBSERVE green CLOSE light illuminated.

Comment: SAT UNSAT Perform Step: 6 IF NO RCPs are operating in Modes 3, 4 or 5 AND Steps 5.2.6D and E have been performed, THEN the dilution clearance may be removed from the following valve(s):

Standard: DETERMINE that UNIT is in MODE 1 with RCPs running and this step is N/A.

Comment: SAT UNSAT NUREG 1021, Revision 9.1 Page 4 of 8 CPNPP Mar 2009 RO & SRO JPM S-2 Rev Final.doc

Appendix C JPM STEPS Form ES-C-1 Perform Step: 7 IF it is desired to fill the RWST directly from the BATs, THEN Close 1/1-FCV-111A, RMUW BLNDR FLO CTRL VLV AND go to Step 5.2.6.K.

Standard: DETERMINE that blended flow is required based on Unit Supervisor directive.

Comment: SAT UNSAT Perform Step: 8 Set 1-FK-110, BA BLNDR FLO CTRL to obtain a blended flow which will yield boron concentration of 2400 to 2600 ppm per TDM-201A and TDM-203A.

Standard: SET 1-FK-110, BA BLNDR FLO CTRL potentiometer to 6.25 (6.0 to 6.5) based on desired flow of 25 gpm using TDM-203A, Page 11 Figure for 1-FK-110, BA BLNDR FLO CTRL.

Comment: SAT UNSAT Perform Step: 9a Set 1-FK-111, RMUW BLNDR FLO CTRL to obtain 127 gpm OR at the value determined by the following:

FT = Cb (BAT) x Fb where:

C

• FT = 1-FK-111 Total Flow (1-FR-110 Pen 2)

• Fb = Boric Acid Flow (1-FR-110 Pen 1)

• C = Desired Blend Concentration

• Cb (BAT) = Current concentration of the in-service BAT Standard: CALCULATE a total flow of ~ 75 gpm based on 7447 ppm BAT concentration and a flowrate of 25 gpm for a 2500 ppm makeup.

Comment: SAT UNSAT Perform Step: 9b Set 1-FK-111, RMUW BLNDR FLO CTRL to obtain 127 gpm OR at the value determined by the following:

FT = Cb (BAT) x Fb where:

C

• FT = 1-FK-111 Total Flow (1-FR-110 Pen 2)

• Fb = Boric Acid Flow (1-FR-110 Pen 1)

• C = Desired Blend Concentration

• Cb (BAT) = Current concentration of the in-service BAT Standard: SET 1-FK-111, RMUW BLNDR FLO CTRL potentiometer to 4.65 (4.50 to 4.80) based on desired flow of ~ 75 gpm using TDM-203A, Page 12 Figure for 1-FK-111, RMUW BLNDR FLO CTRL.

Comment: SAT UNSAT NUREG 1021, Revision 9.1 Page 5 of 8 CPNPP Mar 2009 RO & SRO JPM S-2 Rev Final.doc

Appendix C JPM STEPS Form ES-C-1 Perform Step: 10 Set 1-FY-111B, RCS MU BATCH FLO at a value sufficient to complete the makeup operation.

Standard: SET 1-FY-111B, RCS MU BATCH FLO at 8000 gallons.

Comment: SAT UNSAT Perform Step: 11 Set 1-FY-110B, BA BATCH FLO at a value sufficient to fill the RWST.

Standard: SET 1-FY-110B, BA BATCH FLO at ~ 2685 gallons based on pumping at 25 gpm for ~107 minutes.

Comment: SAT UNSAT Perform Step: 12 Open 1CS-8432, U1 CVCS MU TO RWST/REHUT ISOL VLV.

Standard: DIRECT PEO to OPEN 1-CS-8432, U1 CVCS MU TO RWST/REHUT ISOL VLV.

Booth Operator: EXECUTE remote function CVR03, Boric Acid Blender to RWST Isolation Valve to OPEN and REPORT that 1-CS-8432 is OPEN.

Comment: SAT UNSAT Perform Step: 13 Open 1CS-8434, CVCS MU TO RWST 1-01 DNSTRM ISOL VLV.

Standard: DIRECT PEO to OPEN 1-CS-8434, CVCS MU TO RWST 1-01 DNSTRM ISOL VLV.

Booth Operator: EXECUTE remote function CVR03, Boric Acid Blender to RWST Isolation Valve to OPEN and REPORT that 1-CS-8434 is OPEN.

Comment: SAT UNSAT Perform Step: 14 Ensure Closed 1BR-8553, U1 CVCS BA BLEND TO BRS EVAP FD DEMIN IN HDR ISOL VLV.

Standard: DIRECT PEO to ENSURE 1-BR-8553, U1 CVCS BA BLEND TO BRS EVAP FD DEMIN IN HDR ISOL VLV is CLOSED.

Booth Operator: REPORT that 1-BR-8553 is CLOSED.

Comment: SAT UNSAT NUREG 1021, Revision 9.1 Page 6 of 8 CPNPP Mar 2009 RO & SRO JPM S-2 Rev Final.doc

Appendix C JPM STEPS Form ES-C-1 Perform Step: 15 Start makeup to the RWST by placing 1/1-MU, RCS MU MAN ACT in START.

Standard: PLACE 1/1-MU, RCS MU MAN ACT in START.

• OBSERVE red START light illuminated.

• VERIFY 1-FR-110 red pen indicates approximately 25 gpm and green pen indicates approximately 75 gpm.

Comment: SAT UNSAT Perform Step: 16 Perform the following:

• IF BA FLO TO BLNDR (1-FR-110, Red pen) is not at the required value, THEN adjust 1-FK-110, BA BLNDR FLO CTRL to obtain the required boric acid flow.

Standard: If necessary, ADJUST potentiometer on 1-FK-110, BA BLNDR FLO CTRL to obtain required boric acid flow.

Comment: SAT UNSAT Perform Step: 17 Perform the following:

• Notify Chemistry to obtain a sample of the blend.

Standard: CONTACTS Chemistry to obtain a sample of the blend using Gaitronics.

Terminating Cue: Chemistry has been notified. This JPM is complete.

Comment: SAT UNSAT STOP TIME:

NUREG 1021, Revision 9.1 Page 7 of 8 CPNPP Mar 2009 RO & SRO JPM S-2 Rev Final.doc

Appendix C JPM CUE SHEET Form ES-C-1 INITIAL CONDITIONS: Given the following conditions on Unit 1:

• Refueling Water Storage Tank (RWST) level is currently at 95% and preparations are being made to raise level.

• 8000 gallons of makeup at 2500 ppm boron is required.

• A Boric Acid flowrate of 25 gpm is desired.

• Boric Acid Tank concentration is 7447 ppm.

• All prerequisites have been met and a Tracking LCOAR has been initiated.

• An operator is standing by in the field.

INITIATING CUE: The Unit Supervisor directs you to PERFORM a blended makeup of 8000 gallons to the Refueling Water Storage Tank per SOP-104A, Reactor Make-Up And Chemical Control System, Section 5.2.6, Makeup to RWST.

NUREG 1021, Revision 9.1 Page 8 of 8 CPNPP Mar 2009 RO & SRO JPM S-2 Rev Final.doc

Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # RO/SRO NRC S-3 Task # RO1222 K/A # 010.A2.02 3.9 / 3.9 SF-3

Title:

Respond to Pressurizer Spray Valve Failure Examinee (Print):

Testing Method:

Simulated Performance: Classroom:

Actual Performance: X Simulator: X Plant:

READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.

When you complete the task successfully, the objective for this JPM will be satisfied.

Initial Conditions: Unit 1 is in MODE 1 at 100% power. You are the Reactor Operator.

Initiating Cue: The Unit Supervisor directs you to RESPOND to any Primary System alarms.

Task Standard: Locate and correctly perform the critical steps of ABN-705.

Required Materials: ABN-705, Pressurizer Pressure Malfunction, Rev. 12, PCN-0 ALM-0053A, 1-ALB-5C-3.3, PRZR PRESS LO BACKUP HTRS ON, Rev. 6, PCN-14 Validation Time: 5 minutes Time Critical: N/A Completion Time: ________ minutes Comments:

Result: SAT UNSAT Examiner (Print / Sign): Date:

NUREG 1021, Revision 9.1 Page 1 of 6 CPNPP Mar 2009 RO & SRO JPM S-3 Rev Final.doc

Appendix C JPM WORKSHEET Form ES-C-1 SIMULATOR SETUP BOOTH OPERATOR:

INITIALIZE to IC-18 or any MODE 1 Initial Condition and then PERFORM the following:

• ADJUST all RCP Seal Injection flows to ~ 10 gpm to preclude CHG FLO HI / LO alarm.

When examinee has ASSUMED the watch:

• INSERT malfunction RX15B, Pressurizer Spray Valve [PCV-455C] failure to 60%.

EXAMINER:

When located, PROVIDE the examinee with a copy of:

• ABN-705, Pressurizer Pressure Malfunction, Section 3.0, Pressurizer Spray Valve Failure.

NUREG 1021, Revision 9.1 Page 2 of 6 CPNPP Mar 2009 RO & SRO JPM S-3 Rev Final.doc

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Examiner Note: Applicant may go directly to ABN-705 if it is noted that the spray valve is failed.

Perform Step: 1 Respond to alarms.

Standard: ACKNOWLEDGE and RESPOND to annunciator alarm 1- ALB-05C-3.3, PRZR PRESS LO BACKUP HTRS ON.

Comment: SAT UNSAT Examiner Note: Step from 1-ALB-5C-3.3, PRZR PRESS LO BACKUP HTRS ON.

Perform Step: 2 Monitor pressurizer pressure.

• If one channel is indicating >60 psig difference between remaining operable channels, go to ABN-705.

Standard: OBSERVE 1-PI-455A (456/457/458) PZRZ PRESS CHAN I (II/III/IV) and DETERMINE NO channel is indicating >60 psig difference between remaining operable channels.

Comment: SAT UNSAT Perform Step: 3 Stop any secondary power changes.

Standard: DETERMINE no secondary power changes in progress by OBSERVING RCS turbine load stable on the PWROPS plant computer screen at the front of the control room.

Comment: SAT UNSAT Perform Step: 4 Verify pressurizer PORVs and auxiliary spray valve are closed.

Standard: DETERMINE pressurizer PORVs and auxiliary spray valve are closed by OBSERVING green lights ON and red lights OFF on handswitches 1/1-PCV-455A PRZR PORV, 1/1-PCV-456 PRZR PORV and 1/1-8145 PRZR AUX SPR VLV on Main Control Board panel CB-05.

Comment: SAT UNSAT NUREG 1021, Revision 9.1 Page 3 of 6 CPNPP Mar 2009 RO & SRO JPM S-3 Rev Final.doc

Appendix C JPM STEPS Form ES-C-1 Perform Step: 5 Ensure pressurizer spray valves are closed.

Standard: DETERMINE pressurizer spray valve 1-PCV-455B is CLOSED by OBSERVING green light ON and red light OFF per 1-ZL-455B RC LOOP 1 PRZR SPR VLV and 1-PCV-455C is partially OPEN by OBSERVING green light ON and red light ON per 1-ZL-455C RC LOOP 4 PRZR SPR VLV on Main Control Board panel CB-05.

Comment: SAT UNSAT Examiner Note: When located, PROVIDE the examinee with a copy of ABN-705, Pressurizer Pressure Malfunction, Section 3.0, Pressurizer Spray Valve Failure.

Perform Step: 6 CLOSE Pressurizer Spray Valve(s).

• 1-PK-455C, RC LOOP 4 PRZR SPR VLV CTRL Standard: DEPRESS 1-PK-455C, RC LOOP 4 PRZR SPR VLV CTRL amber MANUAL pushbutton and green OUTPUT () pushbutton to CLOSE valve and DETERMINE Loop 4 Pressurizer Spray Valve is OPEN.

Comment: SAT UNSAT Perform Step: 7 IF Pressurizer pressure is decreasing in an uncontrolled manner, THEN perform the following:

Standard: DETERMINE Pressurizer pressure is decreasing in an uncontrolled manner by OBSERVING RCS pressure indications 1-PI-455A (456/457/

458), PRZR PRESS CHAN I (II/III/IV) and/or 1-PR-455, PRZR PRESS.

Comment: SAT UNSAT NUREG 1021, Revision 9.1 Page 4 of 6 CPNPP Mar 2009 RO & SRO JPM S-3 Rev Final.doc

Appendix C JPM STEPS Form ES-C-1 Examiner Note: The following steps represent the alternate path for this JPM.

Perform Step: 8 IF Pressurizer pressure is decreasing in an uncontrolled manner, THEN perform the following:

• Trip the Reactor.

Standard: PLACE 1/1-RTC, RX TRIP Switch to the TRIP position.

• VERIFY Reactor Trip Breakers OPEN by OBSERVING 1/1-RTBAL and 1/1-RTBBL Reactor Trip Breaker green OPEN lights illuminated.

• OBSERVE all Control Rods inserted on DRPI Indication using CTRL ROD POSN.

Examiner Cue: Another operator will perform immediate actions of EOP-0.0A, Reactor Trip or Safety Injection; CONTINUE with ABN-705 actions.

Comment: SAT UNSAT Perform Step: 9 IF Pressurizer pressure is decreasing in an uncontrolled manner, THEN perform the following:

• STOP RCP(s) as necessary to stop spray flow.

Standard: PLACE 1/1-PCPX4, RCP 4 to STOP and OBSERVE the green STOP light illuminated.

Terminating Cue: This JPM is complete.

Comment: SAT UNSAT STOP TIME:

NUREG 1021, Revision 9.1 Page 5 of 6 CPNPP Mar 2009 RO & SRO JPM S-3 Rev Final.doc

Appendix C JPM CUE SHEET Form ES-C-1 INITIAL CONDITIONS: Unit 1 is in MODE 1 at 100% power. You are the Reactor Operator.

INITIATING CUE: The Unit Supervisor directs you to RESPOND to any Primary System alarms.

NUREG 1021, Revision 9.1 Page 6 of 6 CPNPP Mar 2009 RO & SRO JPM S-3 Rev Final.doc

Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # RO/SRO NRC S-4 Task # RO1412 K/A # 005.A2.03 2.9 / 3.1 SF-4-P

Title:

Respond to a Shutdown Loss of Coolant Examinee (Print):

Testing Method:

Simulated Performance: Classroom:

Actual Performance: X Simulator: X Plant:

READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.

When you complete the task successfully, the objective for this JPM will be satisfied.

Initial Conditions: Unit 1 is in MODE 4 with the following conditions:

• Both Residual Heat Removal Trains are in service.

• A Loss of Coolant Accident has occurred.

• ABN-108, Shutdown Loss of Coolant is being implemented.

Initiating Cue: The Unit Supervisor directs you to PERFORM ABN-108, Shutdown Loss of Coolant, starting at Step 2.3.8, Check RCS Status.

Task Standard: Locate and correctly perform Critical Steps of ABN-108.

Required Materials: ABN-108, Shutdown Loss of Coolant, Rev. 4, PCN-1 Validation Time: 10 minutes Time Critical: N/A Completion Time: ________ minutes Comments:

Result: SAT UNSAT Examiner (Print / Sign): Date:

NUREG 1021, Revision 9.1 Page 1 of 9CPNPP Mar 2009 RO & SRO JPM S-4 Rev Final.doc

Appendix C JPM WORKSHEET Form ES-C-1 SIMULATOR SETUP BOOTH OPERATOR:

INITIALIZE to IC-25 or any MODE 4 Initial Condition and then PERFORM the following:

• ENSURE Train A and Train B RHR Systems in service.

• START TREND GTGC MODE 4 for current plant condition.

• PERFORM the 1st seven actions of ABN-108:

• START both CCPs.

• SECURE RCPs 1 and 4.

• ISOLATE Letdown (PK-131, HC-128, and HC-123 closed).

• HANG red TAG on PDP.

• INSERT malfunction RC17A at 30,000 gpm to lower RCS level and allow Cold Calibrated PRZR level to lower to 80% then FREEZE the Simulator.

When directed, PERFORM the following:

• INSERT remote functions SIR01 for SI Pump 1-01 or SIR02 for SI Pump 1-02 as directed by the Reactor Operator.

PERFORM the following after each JPM:

• REMOVE the key from 1/1-8835, SI to CL 1-4 INJ ISOL VLV and RETURN to Key Locker.

EXAMINER:

PROVIDE the examinee with a copy of:

• ABN-108, Shutdown Loss of Coolant with initials as appropriate through Step 2.3.7.

NUREG 1021, Revision 9.1 Page 2 of 9CPNPP Mar 2009 RO & SRO JPM S-4 Rev Final.doc

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Booth Operator: When examinee is ready, PLACE Simulator in RUN.

Perform Step: 1 Verify RCS Subcooling - GREATER THAN 25°F:

• u-TI-3611-1, RCS SAT MARGIN

• u-TI-3612-1, RCS SAT MARGIN Standard: DETERMINE RCS SAT MARGIN is > 25°F as read on 1-TI-3611-1 and 1-TI-3612-1, RCS SAT MARGIN.

Comment: SAT UNSAT Perform Step: 2 Verify Pressurizer Level - STABLE OR INCREASING.

Standard: DETERMINE Pressurizer Level LOWERING by OBSERVING 1-LI-462, PRZR LVL COLD CAL.

Comment: SAT UNSAT Booth Operator: INSERT remote functions SIR01 for SI Pump 1-01 or SIR02 for SI Pump 1-02 as directed by the Reactor Operator.

Perform Step: 3 Dispatch operators to rack in breakers to affected units non-operating CCP AND ONE safety injection pump.

Standard: DISPATCH operator to rack in breaker for one (1) Safety Injection Pump.

Comment: SAT UNSAT Examiner Note: Examinee will obtain key from Key Locker.

Perform Step: 4 Ensure 1/u-8835, SI TO CL 1-4 INJ ISOL VLV, OPEN.

Standard: INSERT key in switch and TURN to ON position then PLACE 1/1-8835, SI TO CL 1-4 INJ ISOL VLV in OPEN and OBSERVE red OPEN light illuminated.

Comment: SAT UNSAT NUREG 1021, Revision 9.1 Page 3 of 9CPNPP Mar 2009 RO & SRO JPM S-4 Rev Final.doc

Appendix C JPM STEPS Form ES-C-1 Perform Step: 5 Stop both RHR pumps:

• 1/u-APRH1, RHRP 1 Standard: PLACE 1/1-APRH1, RHRP 1, in STOP and OBSERVE the following:

• Green PUMP and red FAN lights illuminated.

• 1-PI-614, RHRP 1 DISCH PRESS lowers to ~30 psig.

• 1-FI-618, RHR TO CL 1 & 2 INJ FLO lowers to 0 gpm.

Comment: SAT UNSAT Perform Step: 6 Stop both RHR pumps:

• 1/u-APRH2, RHRP 2 Standard: PLACE 1/1-APRH2, RHRP 2, in STOP and OBSERVE the following:

• Green PUMP and red FAN lights illuminated.

• 1-PI-615, RHRP 2 DISCH PRESS lowers to ~30 psig.

• 1-FI-619, RHR TO CL 3 & 4 INJ FLO lowers to 0 gpm.

Comment: SAT UNSAT Perform Step: 7 Close 1/u-8701A, RHRP 1 HL RECIRC ISOL VLV AND 1/u-8702B, RHRP 2 HL RECIRC ISOL VLV.

Standard: PLACE 1/1-8701A, RHRP 1 HL RECIRC ISOL VLV in CLOSE and OBSERVE green CLOSE light illuminated.

Comment: SAT UNSAT Perform Step: 8 Close 1/u-8701A, RHRP 1 HL RECIRC ISOL VLV AND 1/u-8702B, RHRP 2 HL RECIRC ISOL VLV.

Standard: PLACE 1/1-8702B, RHRP 2 HL RECIRC ISOL VLV in CLOSE and OBSERVE green CLOSE light illuminated.

Comment: SAT UNSAT NUREG 1021, Revision 9.1 Page 4 of 9CPNPP Mar 2009 RO & SRO JPM S-4 Rev Final.doc

Appendix C JPM STEPS Form ES-C-1 Perform Step: 9 Identify AND Isolate Leak per Attachment 7, while continuing this procedure.

Standard: IDENTIFY and ISOLATE Leak per Attachment 7, RCS Leak Identification and Isolation.

Examiner Cue: Another operator will perform Attachment 7, RCS Leak Identification and Isolation.

Comment: SAT UNSAT Perform Step: 10 GO TO Step 11.

Standard: GO TO Step 11.

Comment: SAT UNSAT Perform Step: 11 Verify RWST level - GREATER THAN 33%:

• u-LI-932, RWST LVL CHAN III

• u-LI-933, RWST LVL CHAN IV Standard: DETERMINE RWST level greater than 33% by OBSERVING 1-LI-932, RWST LVL CHAN III and 1-LI-933, RWST LVL CHAN IV.

Comment: SAT UNSAT Perform Step: 12 Verify at least one CCP-RUNNING.

Standard: DETERMINE both Centrifugal Charging Pumps 1-01 and 1-02 are RUNNING.

Comment: SAT UNSAT Perform Step: 13 STOP 1/u-APPD, PDP.

Standard: VERIFY 1/1-APPD, PDP is TAGGED OUT by OBSERVING green FAN light illuminated and PDP handswitch in STOP.

Comment: SAT UNSAT NUREG 1021, Revision 9.1 Page 5 of 9CPNPP Mar 2009 RO & SRO JPM S-4 Rev Final.doc

Appendix C JPM STEPS Form ES-C-1 Perform Step: 14 Verify CCP suction aligned from RWST:

• 1/u-LCV-112D RWST TO CHRG PMP SUCT VLV - OPEN Standard: VERIFY 1/1-LCV-112D RWST TO CHRG PMP SUCT VLV in OPEN and OBSERVE red OPEN light illuminated.

Comment: SAT UNSAT Perform Step: 15 Verify CCP suction aligned from RWST:

• 1/u-LCV-112E RWST TO CHRG PMP SUCT VLV - OPEN Standard: VERIFY 1/1-LCV-112E RWST TO CHRG PMP SUCT VLV in OPEN and OBSERVE red OPEN light illuminated.

Comment: SAT UNSAT Perform Step: 16 Verify CCP suction aligned from RWST:

• 1/u-LCV-112B, VCT TO CHRG PMP SUCT VLV - CLOSED Standard: VERIFY 1/1-LCV-112B, VCT TO CHRG PMP SUCT VLV in CLOSE and OBSERVE green CLOSE light illuminated.

Comment: SAT UNSAT Perform Step: 17 Verify CCP suction aligned from RWST:

• 1/u-LCV-112C, VCT TO CHRG PMP SUCT VLV - CLOSED Standard: VERIFY 1/1-LCV-112C, VCT TO CHRG PMP SUCT VLV in CLOSE and OBSERVE green CLOSE light illuminated.

Comment: SAT UNSAT NUREG 1021, Revision 9.1 Page 6 of 9CPNPP Mar 2009 RO & SRO JPM S-4 Rev Final.doc

Appendix C JPM STEPS Form ES-C-1 Perform Step: 18 Verify the following valves closed:

• u-ZL-8220, CHRG PMP SUCT HI POINT VENT VLV - CLOSED

• u-ZL-8221, CHRG PMP SUCT HI POINT VENT VLV - CLOSED

• 1/u-8210A, H2/N2 SPLY VLV - CLOSED

• 1/u-8210B, H2/N2 SPLY VLV - CLOSED

• 1/u-8202A, VENT VLV - CLOSED

• 1/u-8202B, VENT VLV - CLOSED Standard: Verify the following valves closed:

• 1-ZL-8220, CHRG PMP SUCT HI POINT VENT VLV - CLOSED

• 1-ZL-8221, CHRG PMP SUCT HI POINT VENT VLV - CLOSED

• 1/1-8210A, H2/N2 SPLY VLV - CLOSED

• 1/1-8210B, H2/N2 SPLY VLV - CLOSED

• 1/1-8202A, VENT VLV - CLOSED

• 1/1-8202B, VENT VLV - CLOSED Comment: SAT UNSAT Perform Step: 19 Align CCP injection:

• 1/u-8801A, CCP SI ISOL VLV - OPEN Standard: PLACE 1/1-8801A, CCP SI ISOL VLV in OPEN and OBSERVE red OPEN light illuminated.

Comment: SAT UNSAT Perform Step: 20 Align CCP injection:

• 1/u-8801B, CCP SI ISOL VLV - OPEN Standard: PLACE 1/1-8801B, CCP SI ISOL VLV in OPEN and OBSERVE red OPEN light illuminated.

Comment: SAT UNSAT NUREG 1021, Revision 9.1 Page 7 of 9CPNPP Mar 2009 RO & SRO JPM S-4 Rev Final.doc

Appendix C JPM STEPS Form ES-C-1 Perform Step: 21 Verify ECCS flow:

• u-FI-917, CCP SI FLO Standard: OBSERVE flow indication on 1-FI-917, CCP SI FLO.

Terminating Cue: This JPM is complete.

Comment: SAT UNSAT STOP TIME:

NUREG 1021, Revision 9.1 Page 8 of 9CPNPP Mar 2009 RO & SRO JPM S-4 Rev Final.doc

Appendix C JPM CUE SHEET Form ES-C-1 INITIAL CONDITIONS: Unit 1 is in MODE 4 with the following conditions:

• Both Residual Heat Removal Trains are in service.

• A Loss of Coolant Accident has occurred.

• ABN-108, Shutdown Loss of Coolant is being implemented.

INITIATING CUE: The Unit Supervisor directs you to PERFORM ABN-108, Shutdown Loss of Coolant, starting at Step 2.3.8, Check RCS Status.

NUREG 1021, Revision 9.1 Page 9 of 9CPNPP Mar 2009 RO & SRO JPM S-4 Rev Final.doc

Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # RO/SRO NRC S-6 Task # RO4204 K/A # 062.A2.16 2.5 / 2.9 SF-6

Title:

Transfer Safeguards Bus Power From Transformer XST2 to XST1 Examinee (Print):

Testing Method:

Simulated Performance: Classroom:

Actual Performance: X Simulator: X Plant:

READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.

When you complete the task successfully, the objective for this JPM will be satisfied.

Initial Conditions: Given the following conditions:

• Unit 1 is in MODE 1 with all controls in AUTOMATIC.

• Transformer XST2 has been scheduled for Glen Rose Transmission maintenance.

• All Prerequisites have been met for transferring the 6900 V Safeguard Buses to Transformer XST1.

Initiating Cue: The Unit Supervisor directs you to TRANSFER the 6900 V Safeguard Buses to Transformer XST1 per SOP-603A, 6900 V Switchgear, Step 5.3.3.C, Transferring a 6.9 kV Safeguards Bus from Startup Transformer XST2 to Startup Transformer XST1.

Task Standard: Locate and correctly perform the Critical Steps of SOP-603A.

Required Materials: SOP-603A, 6900 V Switchgear, Rev. 14, PCN-6 Validation Time: 5 minutes Time Critical: N/A Completion Time: ________ minutes Comments:

Result: SAT UNSAT Examiner (Print / Sign): Date:

NUREG 1021, Revision 9.1 Page 1 of 6 CPNPP Mar 2009 RO & SRO JPM S-6 Rev Final.doc

Appendix C JPM WORKSHEET Form ES-C-1 SIMULATOR SETUP BOOTH OPERATOR:

INITIALIZE to IC-18 or any Mode 1 Initial Condition.

PERFORM the following after each JPM:

• TRANSFER Sync Switch to SS-1EG1, BKR 1EG1 SYNCHROSCOPE position.

EXAMINER:

PROVIDE the examinee with a copy of:

• SOP-603A, 6900 V Switchgear with Section 2.3 signed and Step 5.3.3.A signed with Step 5.3.3.B marked as not applicable.

NUREG 1021, Revision 9.1 Page 2 of 6 CPNPP Mar 2009 RO & SRO JPM S-6 Rev Final.doc

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Perform Step: 1 Turn synchroscope ON for the selected Bus Feeder Breaker AND ensure proper phasing and frequency.

• SS-1EA1-2, BKR 1EA1-2 SYNCHROSCOPE Standard: SELECT SS-1EA1-2, BKR 1EA1-2 SYNCHROSCOPE to ON and OBSERVE synchroscope to be stationary at ~ 12 oclock position.

Comment: SAT UNSAT Perform Step: 2 Close the selected Bus Feeder Breaker from the Startup Transformer XST1.

• CS-1EA1-2, INCOMING BKR 1EA1-2 Standard: PLACE CS-1EA1-2, INCOMING BKR 1EA1-2 in CLOSE and OBSERVE red CLOSE light illuminated.

Comment: SAT UNSAT Perform Step: 3 Ensure the Bus Feeder Breaker from Startup Transformer XST2 to the bus being transferred trips open.

• CS-1EA1-1, INCOMING BKR 1EA1-1 Standard: VERIFY CS-1EA1-1, INCOMING BKR 1EA1-1 in OPEN and OBSERVE green TRIP and amber MISMATCH lights illuminated.

Comment: SAT UNSAT Examiner Note: JPM Steps 4 and 5 will be performed three times.

Perform Step: 4 Position applicable switch to check phase voltage:

• VS-1EA1-1, BUS 1EA1 VOLT SELECT Standard: SELECT VS-1EA1-1, BUS 1EA1 VOLT SELECT to PHASE AB /

PHASE BC / PHASE CA.

Comment: SAT UNSAT Perform Step: 5 Verify approximately 6900 VOLTS on the applicable indication (6480-7150 volts required).

• V-1EA1-1, BUS 1EA1 VOLT Standard: OBSERVE voltage on V-1EA1-1, BUS 1EA1 VOLT is between 6480 and 7150 volts for PHASE AB then PHASE BC then PHASE CA.

Comment: SAT UNSAT NUREG 1021, Revision 9.1 Page 3 of 6 CPNPP Mar 2009 RO & SRO JPM S-6 Rev Final.doc

Appendix C JPM STEPS Form ES-C-1 Perform Step: 6 Match handswitch target by placing the selected breaker, for the bus transferred, in NEUTRAL-AFTER-TRIP.

• CS-1EA1-1, INCOMING BKR 1EA1-1 Standard: PLACE CS-1EA1-1, INCOMING BKR 1EA1-1 momentarily in TRIP position then spring return to NEUTRAL and OBSERVE green TRIP light illuminated and amber MISMATCH light extinguished.

Comment: SAT UNSAT Perform Step: 7 Turn synchroscope OFF for the selected breaker.

• SS-1EA1-2, BKR 1EA1-2 SYNCHROSCOPE Standard: PLACE SS-1EA1-2, BKR 1EA1-2 SYNCHROSCOPE in OFF.

Comment: SAT UNSAT Perform Step: 8 Turn synchroscope ON for the selected Bus Feeder Breaker AND ensure proper phasing and frequency.

• SS-1EA2-2, BKR 1EA2-2 SYNCHROSCOPE Standard: SELECT SS-1EA2-2, BKR 1EA2-2 SYNCHROSCOPE to ON and OBSERVE synchroscope to be stationary at ~ 12 oclock position.

Comment: SAT UNSAT Perform Step: 9 Close the selected Bus Feeder Breaker from the Startup Transformer XST1.

• CS-1EA2-2, INCOMING BKR 1EA2-2 Standard: PLACE CS-1EA2-2, INCOMING BKR 1EA2-2 in CLOSE position and OBSERVE red CLOSE light illuminated.

Comment: SAT UNSAT Perform Step: 10 Ensure the Bus Feeder Breaker from Startup Transformer XST2 to the bus being transferred trips open.

• CS-1EA2-1, INCOMING BKR 1EA2-1 Standard: OBSERVE CS-1EA2-1, INCOMING BKR 1EA2-1 in TRIP and OBSERVE green TRIP and amber MISMATCH lights illuminated.

Comment: SAT UNSAT NUREG 1021, Revision 9.1 Page 4 of 6 CPNPP Mar 2009 RO & SRO JPM S-6 Rev Final.doc

Appendix C JPM STEPS Form ES-C-1 Examiner Note: JPM Steps 11 and 12 will be performed three times.

Perform Step: 11 Position applicable switch to check phase voltage:

• VS-1EA2-1, BUS 1EA2 VOLT SELECT Standard: SELECT VS-1EA2-1, BUS 1EA2 VOLT SELECT to PHASE AB /

PHASE BC / PHASE CA.

Comment: SAT UNSAT Perform Step: 12 Verify approximately 6900 VOLTS on the applicable indication (6480-7150 volts required).

• V-1EA2-1, BUS 1EA2 VOLT Standard: OBSERVE voltage on V-1EA2-1, BUS 1EA2 VOLT is between 6480 and 7150 volts for PHASE AB then PHASE BC then PHASE CA.

Comment: SAT UNSAT Perform Step: 13 Match handswitch target by placing the selected breaker, for the bus transferred, in NEUTRAL-AFTER-TRIP.

• CS-1EA1-1, INCOMING BKR 1EA1-1 Standard: PLACE CS-1EA2-1, INCOMING BKR 1EA2-1 momentarily in TRIP position then spring return to NEUTRAL and OBSERVE green TRIP light illuminated and amber MISMATCH light extinguished.

Comment: SAT UNSAT Perform Step: 14 Turn synchroscope OFF for the selected breaker.

• SS-1EA2-2, BKR 1EA2-2 SYNCHROSCOPE Standard: PLACE SS-1EA2-2, BKR 1EA2-2 SYNCHROSCOPE in OFF.

Terminating Cue: This JPM is complete.

Comment: SAT UNSAT STOP TIME:

NUREG 1021, Revision 9.1 Page 5 of 6 CPNPP Mar 2009 RO & SRO JPM S-6 Rev Final.doc

Appendix C JPM CUE SHEET Form ES-C-1 INITIAL CONDITIONS: Given the following conditions:

• Unit 1 is in MODE 1 with all controls in AUTOMATIC.

• Transformer XST2 has been scheduled for Glen Rose Transmission maintenance.

• All Prerequisites have been met for transferring the 6900 V Safeguard Buses to Transformer XST1.

INITIATING CUE: The Unit Supervisor directs you to TRANSFER the 6900 V Safeguard Buses to Transformer XST1 per SOP-603A, 6900 V Switchgear, Step 5.3.3.C, Transferring a 6.9 kV Safeguards Bus from Startup Transformer XST2 to Startup Transformer XST1.

NUREG 1021, Revision 9.1 Page 6 of 6 CPNPP Mar 2009 RO & SRO JPM S-6 Rev Final.doc

Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # RO/SRO NRC S-7 Task # RO1827 K/A # 016.A2.01 3.0 / 3.1 SF-7

Title:

Respond to Turbine Impulse Pressure Instrument Malfunction Examinee (Print):

Testing Method:

Simulated Performance: Classroom:

Actual Performance: X Simulator: X Plant:

READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.

When you complete the task successfully, the objective for this JPM will be satisfied.

Initial Conditions: Unit 1 is in MODE 1 at 100% power. You are the Reactor Operator.

Initiating Cue: The Unit Supervisor directs you to RESPOND to any alarms.

Task Standard: Locate and correctly perform Critical Steps of ABN-709 and PLR 2007-0165.

Required Materials: ABN-709, Steam Line, Steam Header, Turbine 1st Stage Pressure, and Feed Header Pressure Instrument Malfunction, Rev. 8, PCN-0 PLR 2007-0165, Transferring the Steam Dump System to the Steam Pressure Mode Validation Time: 10 minutes Time Critical: N/A Completion Time: ________ minutes Comments:

Result: SAT UNSAT Examiner (Print / Sign): Date:

NUREG 1021, Revision 9.1 Page 1 of 8 CPNPP Mar 2009 RO & SRO JPM S-7 Rev Final.doc

Appendix C JPM WORKSHEET Form ES-C-1 SIMULATOR SETUP BOOTH OPERATOR:

INITIALIZE to IC-18 or any 100% power Initial Condition and then PERFORM the following:

• INSERT malfunction RX09A, Main Turbine 1st Stage Pressure Transmitter failure

[PT-505A] to 0%.

• ENSURE Rod Control is in AUTO.

PERFORM the following after each JPM:

• ENSURE PLR 2007-0165, Transferring the Steam Dump System to the Steam Pressure Mode Job Aid for the Steam Dump System is CLEAN.

• ENSURE 1-ALB-6D-1.10, AVE Tave Tref DEV procedure book is CLEAN.

EXAMINER:

When located, PROVIDE the examinee with a copy of:

• ABN-709, Steam Line, Steam Header, Turbine 1st Stage Pressure, and Feed Header Pressure Instrument Malfunction.

• PLR 2007-0165, Transferring the Steam Dump System to the Steam Pressure Mode.

NUREG 1021, Revision 9.1 Page 2 of 8 CPNPP Mar 2009 RO & SRO JPM S-7 Rev Final.doc

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Booth Operator: INSERT malfunction RX09A, Main Turbine 1st Stage Pressure Transmitter failure [PT-505A] to 0%.

Perform Step: 1 RESPOND to Annunciator alarm.

Standard: ACKNOWLEDGE and RESPOND to Annunciator alarm 1-ALB-6D-1.10, AVE Tave Tref DEV.

Comment: SAT UNSAT Examiner Note: Step from 1-ALB-6D-1.10, AVE Tave Tref DEV.

Perform Step: 2 Stop all secondary system power changes and allow the primary and secondary to stabilize, if possible.

Standard: DETERMINE NO secondary system power changes are in progress.

Comment: SAT UNSAT Examiner Note: Step from 1-ALB-6D-1.10, AVE Tave Tref DEV.

Perform Step: 3 Verify RCS temperature is >551°F:

• 1-TI-412, RC LOOP 1 TAVE CHAN I

• 1-TI-422, RC LOOP 2 TAVE CHAN II

• 1-TI-432, RC LOOP 3 TAVE CHAN III

• 1-TI-442, RC LOOP 4 TAVE CHAN IV Standard: DETERMINE RCS temperature is >551°F:

• 1-TI-412, RC LOOP 1 TAVE CHAN I

• 1-TI-422, RC LOOP 2 TAVE CHAN II

• 1-TI-432, RC LOOP 3 TAVE CHAN III

• 1-TI-442, RC LOOP 4 TAVE CHAN IV Comment: SAT UNSAT NUREG 1021, Revision 9.1 Page 3 of 8 CPNPP Mar 2009 RO & SRO JPM S-7 Rev Final.doc

Appendix C JPM STEPS Form ES-C-1 Examiner Note: Step from 1-ALB-6D-1.10, AVE Tave Tref DEV.

Perform Step: 4 Monitor turbine impulse chamber pressure.

• 1-PI-505, TURB IMP PRESS CHAN I

• 1-PI-506, TURB IMP PRESS CHAN II If pressure indicates >3% difference between channels, refer to ABN-709.

Standard: DETERMINE Turbine Impulse Chamber Pressure indicates >3%

difference between channels and REFER to ABN-709.

Examiner Cue: The Unit Supervisor directs entry into ABN-709.

Comment: SAT UNSAT Examiner Note: When located, PROVIDE the examinee with a copy of ABN-709, Steam Line, Steam Header, Turbine 1st Stage Pressure, and Feed Header Pressure Instrument Malfunction.

Perform Step: 5 Place 1/u-RBSS, CONTROL ROD BANK SELECT Switch in - MANUAL.

Standard: PLACE 1/1-RBSS, CONTROL ROD BANK SELECT Switch in MANUAL and OBSERVE rod motion stops.

Comment: SAT UNSAT Perform Step: 6 Verify Steam Dumps - CLOSED WITH NO OPEN DEMAND.

Standard: DETERMINE Steam Dumps CLOSED via STM DMP TRIP GRP 1 and GRP 2 green lights on all 12 Steam Dump Valves, however, OBSERVE 1-UI-500, STM DMP DEMAND indicating 100% DEMAND.

Comment: SAT UNSAT Examiner Note: The following step represents the alternate path for this JPM.

Perform Step: 7 IF steam dump operation NOT required, THEN place at least one steam dump interlock select switch - OFF:

• 43/u-SDA, STM DMP INTLK SELECT

• 43/u-SDB, STM DMP INTLK SELECT Standard: PLACE 43/1-SDA, STM DMP INTLK SELECT or 43/1-SDB, STM DMP INTLK SELECT in OFF position and OBSERVE Steam Dump Valves CLOSED.

Comment: SAT UNSAT NUREG 1021, Revision 9.1 Page 4 of 8 CPNPP Mar 2009 RO & SRO JPM S-7 Rev Final.doc

Appendix C JPM STEPS Form ES-C-1 Examiner Cue: The Unit Supervisor directs you to refer to the Job Aid for Transferring the Steam Dump System to the Steam Pressure Mode.

Examiner Note: When located, PROVIDE the examinee with a copy of PLR 2007-0165, Transferring the Steam Dump System to the Steam Pressure Mode.

Perform Step: 8 Restore steam dump availability

• Place Steam Dumps in STM PRESS Mode.

• Ensure steam dump selector switches - ON Standard: REFER to the Job Aid, Transferring the Steam Dump System to the STEAM PRESSURE Mode.

Comment: SAT UNSAT Perform Step: 9 Ensure 1-PK-507, STM DMP PRESS CTRL is in MANUAL.

Standard: VERIFY 1-PK-507, STM DMP PRESS CTRL in MANUAL and OBSERVE amber MANUAL light illuminated.

Comment: SAT UNSAT Examiner Note: This step is not performed.

Perform Step: 10 Match 1-PK-507, STM DMP PRESS CTRL demand to 1-UI-500, STM DMP DEMAND.

Standard: DETERMINE matching of 1-PK-507, STM DMP PRESS CTRL to 1-UI-500, STM DMP DEMAND is NOT desired.

Comment: SAT UNSAT Perform Step: 11 Verify 1-PCIP, 1.4, CNDSR AVAIL STM DMP ARMED C-9, is ON.

Standard: OBSERVE 1-PCIP-1.4, CNDSR AVAIL STM DMP ARMED C-9 window illuminated.

Comment: SAT UNSAT NUREG 1021, Revision 9.1 Page 5 of 8 CPNPP Mar 2009 RO & SRO JPM S-7 Rev Final.doc

Appendix C JPM STEPS Form ES-C-1 Examiner Note: This step may not be performed per Job Aid PLR 2007-0165. This step may be performed by Step 3.b of ABN-709. If performed per ABN-709, Step 3.b then it will be done between steps 16 and 17 of this JPM.

Perform Step: 12 Ensure BOTH STM DMP INTLK SELECT switches are ON.

Standard: PLACE 43/1-SDA, STM DMP INTLK SELECT and 43/1-SDB, STM DMP INTLK SELECT in ON position.

Comment: SAT UNSAT Perform Step: 13 Place 43/1-SD, STM DMP MODE SELECT in STM PRESS and verify proper response of steam dump valves.

Standard: PLACE 43/1-SD, STM DMP MODE SELECT in STM PRESS position and VERIFY Steam Dump Valves remain CLOSED by OBSERVING STM DMP TRIP GRP 1 and GRP 2 green lights on all 12 Steam Dump Valves and 1-UI-500, STM DMP DEMAND to 0%.

Comment: SAT UNSAT Perform Step: 14 Ensure 1-PK-507, STM DMP PRESS CTRL set to 6.86.

Standard: VERIFY potentiometer on 1-PK-507, STM DMP PRESS CTRL set to 6.86.

Comment: SAT UNSAT Perform Step: 15 Place 1-PK-507, STM DMP PRESS CTRL in AUTO.

Standard: DEPRESS the white pushbutton on 1-PK-507, STM DMP PRESS CTRL and OBSERVE white AUTO light illuminated.

Comment: SAT UNSAT Examiner Note: Main Steam header pressure listed is for Hot Zero Power, therefore, examinee should determine observed value is appropriate.

Perform Step: 16 Verify 1-PI-507, MS HDR PRESS is approximately 1092 psig.

Standard: DETERMINE 1-PI-507, MS HDR PRESS at approximately 950 psig and appropriate for 100% power.

Comment: SAT UNSAT NUREG 1021, Revision 9.1 Page 6 of 8 CPNPP Mar 2009 RO & SRO JPM S-7 Rev Final.doc

Appendix C JPM STEPS Form ES-C-1 Examiner Note: The examinee should refer to ABN-709 to complete restoration.

Perform Step: 17 Transfer u-PS-505Z, TURB IMP PRESS CHAN SELECT to operable channel.

Standard: Transfer 1-PS-505Z, TURB IMP PRESS CHAN SELECT to Channel PS-506 and ACKNOWLEDGE alarm 1-ALB-6D-2.9, TURB IMP PRESS CHAN OUT OF SERV.

Terminating Cue: This JPM is complete.

Comment: SAT UNSAT STOP TIME:

NUREG 1021, Revision 9.1 Page 7 of 8 CPNPP Mar 2009 RO & SRO JPM S-7 Rev Final.doc

Appendix C JPM CUE SHEET Form ES-C-1 INITIAL CONDITIONS: Unit 1 is in MODE 1 at 100% power. You are the Reactor Operator.

INITIATING CUE: The Unit Supervisor directs you to RESPOND to any alarms.

NUREG 1021, Revision 9.1 Page 8 of 8 CPNPP Mar 2009 RO & SRO JPM S-7 Rev Final.doc

Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # RO/SRO NRC S-8 Task # RO4004 K/A # 029.A3.01 3.8 / 4.0 SF-8

Title:

Monitor the Containment Purge System Examinee (Print):

Testing Method:

Simulated Performance: Classroom:

Actual Performance: X Simulator: X Plant:

READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.

When you complete the task successfully, the objective for this JPM will be satisfied.

Initial Conditions: Given the following conditions:

• Unit 1 is in MODE 5.

• A Containment Purge is in progress per SOP-801A, Containment Ventilation System, Section 5.6.1, Containment Purge and Exhaust System Startup.

• A Release Permit has been issued.

Initiating Cue: The Unit Supervisor directs you to RESPOND to any alarms.

Task Standard: Locate and correctly perform Critical Steps of SOP-801A and ALM-0032A.

Required Materials: SOP-801A, Containment Ventilation System, Rev. 13, PCN-1 ALM-0032A, 1-ALB-3B-4.1, CNTMT AIR RAD HI, Rev. 7, PCN-8 ABN-902, Release of Radioactive/Toxic Gas, Rev. 6, PCN-1 Validation Time: 4 minutes Time Critical: N/A Completion Time: ________ minutes Comments:

Result: SAT UNSAT Examiner (Print / Sign): Date:

NUREG 1021, Revision 9.1 Page 1 of 6 CPNPP Mar 2009 RO & SRO JPM S-8 Rev Final.doc

Appendix C JPM WORKSHEET Form ES-C-1 SIMULATOR SETUP BOOTH OPERATOR:

INITIALIZE to IC-4 or any MODE 5 Initial Condition and then PERFORM the following:

• INSERT remote function CHR17, Containment Purge Supply and Exhaust Isolation Damper Fuses for HV-5536/5537/5538/5539 - INSTALL.

• INSERT OVERRIDES to OPEN:

• 1-HS-5538, AIR PRG EXH ISOL DMPR.

• 1-HS-5539, AIR PRG EXH ISOL DMPR.

• 1-HS-5537, AIR PRG SPLY ISOL DMPR.

• 1-HS-5536, AIR PRG SPLY ISOL DMPR.

• When Containment Dampers are fully OPEN, then REMOVE OVERRIDES.

• INSERT remote function RMR02, RM-80 Actuations to OFF.

• ENSURE PC-11 is RESET and CAG-197 is GREEN.

When directed by the Examiner, PERFORM the following:

• INSERT malfunction RM03B3, PRM Radiation Monitor Failure 1-RE-5503 / CAG-197 @ 1E6.

• INSERT remote function AN3B_4 to place ALB-03B-4.1, CNTMT AIR RAD HI -

ALARM ON.

PERFORM the following after each JPM:

• ENSURE PC-11 is RESET and CAG-197 is GREEN.

• ENSURE 1-ALB-3B-4.1, CNTMT AIR RAD HI procedure book is CLEAN.

• INSERT remote function RMR11 to ON to clear RM-80 file.

EXAMINER:

PROVIDE the examinee with a copy of:

• SOP-801A, Containment Ventilation System Section 5.6.1 with initials and N/As as appropriate through Step 5.6.1.M and Section 5.6.4 with initials and N/As as appropriate through Step 5.6.4.A.

If referenced, PROVIDE the examinee with a copy of:

• ABN-902, Release of Radioactive/Toxic Gas.

NUREG 1021, Revision 9.1 Page 2 of 6 CPNPP Mar 2009 RO & SRO JPM S-8 Rev Final.doc

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Booth Operator: When examinee has reviewed system alignment, EXECUTE malfunction RM03B3, PRM Radiation Monitor Failure 1-RE-5503 /

CAG-197 @ 1E6 and INSERT remote function AN3B_4 to place ALB-03B-4.1, CNTMT AIR RAD HI alarm to ON.

Perform Step: 1 RESPOND to Annunciator alarm.

Standard: ACKNOWLEDGE and RESPOND to Annunciator alarm 1-ALB-3B-4.1, CNTMT AIR RAD HI.

Examiner Cue: Acknowledge and respond to any annunciator alarms.

Comment: SAT UNSAT Examiner Note: Due to the ESFAS automatic actions associated with this alarm, the examinee may immediately isolate the Containment Purge Valves.

Examiner Note: Step from 1-ALB-3B-4.1, CNTMT AIR RAD HI Perform Step: 2 Verify the alarm on PC-11.

• CAG-197, GASEOUS Standard: At PC-11, DEPRESS F7 then 197 then ENTER and OBSERVE high radiation on 1-RE-5503, CNTMT AIR PIG GAS, CAG-197.

Comment: SAT UNSAT Examiner Note: Step from 1-ALB-3B-4.1, CNTMT AIR RAD HI Perform Step: 3 Verify Containment Ventilation Isolation has occurred. (1-CB-02)

• 1-MLB-45A, SI/CNTMT VENT ISOL

• 1-MLB-45B, SI/CNTMT VENT ISOL Standard: DETERMINE Containment Ventilation Isolation has NOT occurred on 1-MLB-45A, SI/CNTMT VENT ISOL or 1-MLB-45B, SI/CNTMT VENT ISOL by OBSERVING 1-HV-5536, 1-HV-5537, 1-HV-5538, and 1-HV-5539 green lights DARK and green lights for remaining CVI valves illuminated.

Comment: SAT UNSAT NUREG 1021, Revision 9.1 Page 3 of 6 CPNPP Mar 2009 RO & SRO JPM S-8 Rev Final.doc

Appendix C JPM STEPS Form ES-C-1 Examiner Note: The following steps represent the alternate path for this JPM.

Examiner Note: The examinee can reference SOP-801A, ABN-902, or 1-ALB-03B-4.1 to perform Containment Purge Isolation actions.

Perform Step: 4 If Containment Purge Isolation is NOT complete, manually align components as necessary.

Standard: PLACE Containment Purge Supply and Exhaust Isolation Valve switches in CLOSE.

• 1-HS-5538, AIR PRG EXH ISOL DMPR.

• 1-HS-5539, AIR PRG EXH ISOL DMPR.

• 1-HS-5537, AIR PRG SPLY ISOL DMPR.

• 1-HS-5536, AIR PRG SPLY ISOL DMPR.

Examiner Note: If referenced, PROVIDE examinee with copy of ABN-902, Release of Radioactive / Toxic Gas.

Comment: SAT UNSAT Examiner Note: The next four steps from ABN-902 can be performed in any order.

Perform Step: 5 Verify dampers closed, manually close dampers as necessary.

• CB-03 1-HS-5538, AIR PRG EXH ISOL DMPR ORC Standard: PLACE 1-HS-5538, AIR PRG EXH ISOL DMPR handswitch in CLOSE and OBSERVE green CLOSE light illuminated and/or the green light on 1-MLB-45B illuminated.

Comment SAT UNSAT Perform Step: 6 Verify dampers closed, manually close dampers as necessary.

• CB-03 1-HS-5539, AIR PRG EXH ISOL DMPR IRC Standard: PLACE 1-HS-5539, AIR PRG EXH ISOL DMPR handswitch in CLOSE and OBSERVE green CLOSE light illuminated and/or the green light on 1-MLB-45A illuminated.

Comment: SAT UNSAT NUREG 1021, Revision 9.1 Page 4 of 6 CPNPP Mar 2009 RO & SRO JPM S-8 Rev Final.doc

Appendix C JPM STEPS Form ES-C-1 Perform Step: 7 Verify dampers closed, manually close dampers as necessary.

• CB-03 1-HS-5537, AIR PRG SPLY ISOL DMPR IRC Standard: PLACE 1-HS-5537, AIR PRG SPLY ISOL DMPR handswitch in CLOSE and OBSERVE green CLOSE light illuminated and/or the green light on 1-MLB-45A illuminated.

Comment: SAT UNSAT Perform Step: 8 Verify dampers closed, manually close dampers as necessary.

• CB-03 1-HS-5536, AIR PRG SPLY ISOL DMPR ORC Standard: PLACE 1-HS-5536, AIR PRG SPLY ISOL DMPR handswitch in CLOSE and OBSERVE green CLOSE light illuminated and/or the green light on 1-MLB-45B illuminated.

Terminating Cue: This JPM is complete.

Comment: SAT UNSAT STOP TIME:

NUREG 1021, Revision 9.1 Page 5 of 6 CPNPP Mar 2009 RO & SRO JPM S-8 Rev Final.doc

Appendix C JPM CUE SHEET Form ES-C-1 INITIAL CONDITIONS: Given the following conditions:

• Unit 1 is in MODE 5.

• A Containment Purge is in progress per SOP-801A, Containment Ventilation System, Section 5.6.1, Containment Purge and Exhaust System Startup.

• A Release Permit has been issued.

INITIATING CUE: The Unit Supervisor directs you to RESPOND to any alarms.

NUREG 1021, Revision 9.1 Page 6 of 6 CPNPP Mar 2009 RO & SRO JPM S-8 Rev Final.doc

Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # RO/SRO NRC P-1 Task # AO4204 K/A # 062.A3.04 2.7 / 2.9 SF-6

Title:

Energize a Protection System Inverter Examinee (Print):

Testing Method:

Simulated Performance: X Classroom:

Actual Performance: Simulator:

Plant: X READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.

When you complete the task successfully, the objective for this JPM will be satisfied.

Initial Conditions: Given the following conditions on Unit 1 (Unit 2):

• uPC4 Protection Bus is aligned to its Alternate Power Source uEC4 via uPC4/00/BKR-2.

• Inverter IVuPC4 has been turned over to Operations to place in service on the uPC4 Protection Bus.

• SOP-607A/B, 118 VAC Distribution System and Inverters, Section 5.8.1, Energizing IVuPC4 and Distribution Panel uPC4 is complete through Step B.

• All power supplies to the Inverter are off.

Initiating Cue: The Unit Supervisor directs you to ALIGN the Unit 1 (Unit 2) Inverter IVuPC4 to supply the uPC4 Bus.

Task Standard: Locate and correctly perform Critical Steps of SOP-607A/B.

Required Materials: SOP-607A, 118 VAC Distribution System and Inverters, Rev. 22, PCN-9 SOP-607B, 118 VAC Distribution System and Inverters, Rev. 15, PCN-5 Validation Time: 16 minutes Time Critical: N/A Completion Time: ________ minutes Comments:

Result: SAT UNSAT Examiner (Print / Sign): Date:

NUREG 1021, Revision 9.1 Page 1 of 8 CPNPP Mar 2009 RO & SRO JPM P-1 Rev Final.doc

Appendix C JPM WORKSHEET Form ES-C-1 PLANT SETUP EXAMINER:

PROVIDE the examinee with a copy of:

• SOP-607A, 118 VAC Distribution System and Inverters with initials and N/As as appropriate up through Step 5.8.1.B for Unit 1.

• SOP-607B, 118 VAC Distribution System and Inverters with initials and N/As as appropriate up through Step 5.8.1.B for Unit 2.

This JPM can be performed on either Unit. CIRCLE the Unit on which the JPM is to be performed on the JPM Worksheet and the JPM Cue Sheet.

NOTE: This JPM has been modified to reflect Unit 1 or Unit 2 designations (as identified in the Perform Step and Standard) by replacing them with a u where appropriate.

NUREG 1021, Revision 9.1 Page 2 of 8 CPNPP Mar 2009 RO & SRO JPM P-1 Rev Final.doc

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Examiner Cue: Remind examinee to simulate all steps of this JPM.

Perform Step: 1 Ensure uEC4/8/BKR, IVuPC4 BYP SOURCE is ON.

Standard: VERIFY uEC4/8/BKR, IVuPC4 BYP SOURCE is ON.

Examiner Cue: The Breaker is ON.

Comment: SAT UNSAT Perform Step: 2 Verify uED4/1-1/DSW, 125 V DC STATION BATTERY BTuED4 FUSED DISCONNECT SWITCH is ON.

Standard: VERIFY uED4/1-1/DSW, 125 V DC STATION BATTERY BTuED4 FUSED DISCONNECT SWITCH is ON.

Examiner Cue: The Disconnect Switch is ON.

Comment: SAT UNSAT Perform Step: 3 Ensure uED4/2-10/BKR, IVuPC4 SPLY is ON.

Standard: VERIFY uED4/2-10/BKR, IVuPC4 SPLY is ON.

Examiner Cue: The Breaker is ON.

Comment: SAT UNSAT Perform Step: 4 Ensure the following breakers and transfer switches are in the position indicated:

• TRS2-IVuPC4, XFER SW S2 is in NORMAL SOURCE AND key inserted in lock with lock extended.

Standard: VERIFY TRS2-IVuPC4, XFER SW S2 is in NORMAL SOURCE AND key inserted in lock with lock extended.

Examiner Cue: The Transfer Switch is in NORMAL SOURCE with key inserted in lock and lock extended.

Comment: SAT UNSAT NUREG 1021, Revision 9.1 Page 3 of 8 CPNPP Mar 2009 RO & SRO JPM P-1 Rev Final.doc

Appendix C JPM STEPS Form ES-C-1 Perform Step: 5 Ensure the following breakers and transfer switches are in the position indicated:

• TRS1-IVuPC4, BYP SW S1 is in BYPASS SOURCE.

Standard: VERIFY TRS1-IVuPC4, BYP SW S1 is in BYPASS SOURCE.

Examiner Cue: The Switch is in the BYPASS SOURCE position.

Comment: SAT UNSAT Perform Step: 6 Ensure the following breakers and transfer switches are in the position indicated:

• IVuPC4/CB1/BKR, DC INPUT is OFF AND key inserted in lock.

Standard: VERIFY IVuPC4/CB1/BKR, DC INPUT is OFF AND key inserted in lock.

Examiner Cue: The Breaker is in OFF and key is inserted in the lock.

Comment: SAT UNSAT Perform Step: 7 Ensure the following breakers and transfer switches are in the position indicated:

• IVuPC4/CB2/BKR, AC OUTPUT is OFF.

Standard: VERIFY IVuPC4/CB2/BKR, AC OUTPUT is OFF.

Examiner Cue: The Breaker is in OFF.

Comment: SAT UNSAT Perform Step: 8 Ensure the following breakers and transfer switches are in the position indicated:

• IVuPC4/CB4/BKR, BYP SOURCE is OFF.

Standard: VERIFY IVuPC4/CB4/BKR, BYP SOURCE is OFF.

Examiner Cue: The Breaker is in OFF.

Comment: SAT UNSAT NUREG 1021, Revision 9.1 Page 4 of 8 CPNPP Mar 2009 RO & SRO JPM P-1 Rev Final.doc

Appendix C JPM STEPS Form ES-C-1 Perform Step: 9 IF Distribution Panel uPC4 is deenergized, THEN ensure ALL load breakers on Panel uPC4 (CPu-ECDPPC-04) are OFF.

Standard: DETERMINE that uPC4 is energized from Alternate Source per Initial Condition.

Examiner Cue: PC4 was energized from its Alternate Source and the Load Breakers are CLOSED.

Comment: SAT UNSAT Examiner Note: DC INPUT Breaker should be closed immediately after the Precharge Pushbutton is released.

Perform Step: 10 Press PRECHARGE pushbutton until yellow PRECHARGE light is lit.

Standard: PRESS PRECHARGE pushbutton until yellow PRECHARGE light is lit.

Examiner Cue: Yellow PRECHARGE light is lit.

Comment: SAT UNSAT Perform Step: 11 While the Precharge light is lit, Turn ON IVuPC4/CB1/BKR, DC INPUT Standard: PLACE IVuPC4/CB1/BKR, DC INPUT, to ON.

Examiner Cue: The Breaker is ON.

Comment: SAT UNSAT Perform Step: 12 Verify Inverter AC OUTPUT voltage is 118 to 128 VAC.

Standard: VERIFY Inverter AC OUTPUT voltage is 118 to 128 VAC.

Examiner Cue: Inverter AC OUTPUT voltage is 120 volts.

Comment: SAT UNSAT Perform Step: 13 Turn ON IVuPC4/CB2/BKR, AC OUTPUT.

Standard: PLACE IVuPC4/CB2/BKR, AC OUTPUT to ON.

Examiner Cue: The Breaker is ON.

Comment: SAT UNSAT NUREG 1021, Revision 9.1 Page 5 of 8 CPNPP Mar 2009 RO & SRO JPM P-1 Rev Final.doc

Appendix C JPM STEPS Form ES-C-1 Perform Step: 14 Turn ON IVuPC4/CB4/BKR, BYP SOURCE.

Standard: PLACE IVuPC4/CB4/BKR, BYP SOURCE to ON.

Examiner Cue: The Breaker is ON.

Comment: SAT UNSAT Perform Step: 15 Verify IN SYNC light is LIT.

Standard: VERIFY IN SYNC light is LIT.

Examiner Cue: The IN SYNC light is LIT.

Comment: SAT UNSAT Perform Step: 16 Depress BYPASS SOURCE TO LOAD pushbutton (Static Switch) and verify BYPASS SOURCE SUPPLYING LOAD red light is LIT.

Standard: DEPRESS BYPASS SOURCE TO LOAD pushbutton (Static Switch) and VERIFY BYPASS SOURCE SUPPLYING LOAD red light is LIT.

Examiner Cue: BYPASS SOURCE SUPPLYING LOAD red light is LIT.

Comment: SAT UNSAT Perform Step: 17 Place TRS1-IVuPC4, BYP SW S1 in NORMAL SOURCE.

Standard: PLACE TRS1-IVuPC4, BYP SW S1 in NORMAL SOURCE.

Examiner Cue: The Switch is in the NORMAL SOURCE position.

Comment: SAT UNSAT NUREG 1021, Revision 9.1 Page 6 of 8 CPNPP Mar 2009 RO & SRO JPM P-1 Rev Final.doc

Appendix C JPM STEPS Form ES-C-1 Examiner Note: The Panel is located in the Cable Spreading Room Elevation 807.

Perform Step: 18 IF Panel uPC4 is powered from the alternate source (uEC4), THEN perform the following steps SIMULTANEOUSLY to transfer Panel uPC4 to the preferred source:

• Turn ON uPC4/00/BKR-1, IVuPC4 TO 118 VAC INSTRUMENT DISTR PANEL uPC4 PREFERRED FEEDER BREAKER.

• Turn OFF uPC4/00/BKR-2, uEC4 TO 118 VAC INSTRUMENT DISTR PANEL uPC4 ALTERNATE FEEDER BREAKER.

Standard: LOOSEN slide bar and SIMULTANEOUSLY :

• PLACE uPC4/00/BKR-1, IVuPC4 TO 118 VAC INSTRUMENT DISTR PANEL uPC4 PREFERRED FEEDER BREAKER to ON.

• PLACE uPC4/00/BKR-2, uEC4 TO 118 VAC INSTRUMENT DISTR PANEL uPC4 ALTERNATE FEEDER BREAKER to OFF.

Examiner Cue: Breaker #1 is ON and Breaker #2 is OFF.

Comment: SAT UNSAT Perform Step: 19 Verify IVuPC4 alarm lamps are OFF.

Standard: VERIFY IVuPC4 INVERTER FAILURE / LOW DC VOLTAGE / FAN FAILURE alarm lamps are OFF.

Examiner Cue: The alarm lamps are OFF.

Comment: SAT UNSAT Perform Step: 20 Depress INVERTER TO LOAD pushbutton (Static Switch) and verify INVERTER SUPPLYING LOAD yellow light is LIT.

Standard: DEPRESS INVERTER TO LOAD pushbutton (Static Switch) and VERIFY INVERTER SUPPLYING LOAD yellow light is LIT.

Examiner Cue: INVERTER SUPPLYING LOAD yellow light is LIT.

Comment: SAT UNSAT Perform Step: 21 Verify Inverter AC OUTPUT voltage is 118 to 128 VAC.

Standard: VERIFY Inverter AC OUTPUT voltage is 118 to 128 VAC.

Terminating Cue: Inverter AC OUTPUT voltage is 120 VAC. This JPM is complete.

Comment: SAT UNSAT STOP TIME:

NUREG 1021, Revision 9.1 Page 7 of 8 CPNPP Mar 2009 RO & SRO JPM P-1 Rev Final.doc

Appendix C JPM CUE SHEET Form ES-C-1 INITIAL CONDITIONS: Given the following conditions on Unit 1 (Unit 2):

• uPC4 Protection Bus is aligned to its Alternate Power Source uEC4 via uPC4/00/BKR-2.

• Inverter IVuPC4 has been turned over to Operations to place in service on the uPC4 Protection Bus.

• SOP-607A/B, 118 VAC Distribution System and Inverters, Section 5.8.1, Energizing IVuPC4 and Distribution Panel uPC4 is complete through Step B.

• All power supplies to the Inverter are off.

INITIATING CUE: The Unit Supervisor directs you to ALIGN the Unit 1 (Unit 2)

Inverter IVuPC4 to supply the uPC4 Bus.

PERFORM THIS JPM ON UNIT 1 (UNIT 2).

NUREG 1021, Revision 9.1 Page 8 of 8 CPNPP Mar 2009 RO & SRO JPM P-1 Rev Final.doc

Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # RO/SRO NRC P-2 Task # RO4005 K/A # 059.AA1.03 3.0 / 2.9 SF-9

Title:

Respond to Accidental Release of Radioactive Liquid Examinee (Print):

Testing Method:

Simulated Performance: X Classroom:

Actual Performance: Simulator:

Plant: X READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.

When you complete the task successfully, the objective for this JPM will be satisfied.

Initial Conditions: Given the following conditions:

• An accidental release of radioactive liquid is in progress.

• The Shift Manager has provided the key to operate X-HS-5253, Laundry Holdup & Monitor Tank Discharge Valve.

Initiating Cue: The Unit Supervisor DIRECTS you to:

• ENTER the Radiation Control Area.

• LOG onto an appropriate Radiation Work Permit.

• PERFORM actions at the Liquid Waste Processing System Panel per ABN-903, Accidental Release of Radioactive Liquid starting at Step 2.3.2.

Task Standard: Locate and correctly perform Critical Steps of ABN-903.

Required Materials: ABN-903, Accidental Release of Radioactive Liquid, Rev. 6, PCN-2 Validation Time: 10 minutes Time Critical: N/A Completion Time: ________ minutes Comments:

Result: SAT UNSAT Examiner (Print / Sign): Date:

NUREG 1021, Revision 9.1 Page 1 of 7 CPNPP Mar 2009 RO & SRO JPM P-2 Rev Final.doc

Appendix C JPM WORKSHEET Form ES-C-1 PLANT SETUP EXAMINER:

PROVIDE the examinee with a copy of:

• ABN-903, Accidental Release of Radioactive Liquid, INITIAL and/or N/A as appropriate up to Step 2.3.2.

NOTE: This JPM includes an evaluation of entry into the RCA. The candidate will perform the RCA entry and then the Accidental Release of Radioactive Liquid tasks. The JPM is then temporarily suspended while the second RCA JPM is completed (P-3). Once JPM P-3 is finished, the examiner will return to JPM P-1 and complete the RCA exit portion of this JPM.

NUREG 1021, Revision 9.1 Page 2 of 7 CPNPP Mar 2009 RO & SRO JPM P-2 Rev Final.doc

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Perform Step: 1 Radiation Workers should obtain their TLD at the TLD Storage Racks on the 810' Hallway.

Standard: OBTAIN TLD at the TLD Storage Racks on the 810' Hallway.

Comment: SAT UNSAT Perform Step: 2 Radiation Workers should obtain an electronic dosimeter at Access Control.

Standard: OBTAIN an electronic dosimeter at Access Control.

Comment: SAT UNSAT Perform Step: 3 Radiation Workers should log into the Access computer by:

• Provide EID Bar-Code for identification.

Standard: LOG into the Access computer using EID Bar-Code for identification.

Comment: SAT UNSAT Perform Step: 4 Radiation Workers should log into the Access computer by:

• Provide TLD No. Bar-Code for verification.

Standard: LOG into the Access computer using TLD No. Bar-Code for verification.

Comment: SAT UNSAT Perform Step: 5 Radiation Workers should log into the Access computer by:

• Specifying their RWP/GAP and Task numbers.

Standard: SPECIFY a Radiation Work Permit and Task Number(s).

Comment: SAT UNSAT Perform Step: 6 Radiation Workers should log into the Access computer by:

• Providing the appropriate response to the electronic signature for RWP authorization.

Standard: PROVIDE the appropriate response to the electronic signature for RWP authorization.

Comment: SAT UNSAT NUREG 1021, Revision 9.1 Page 3 of 7 CPNPP Mar 2009 RO & SRO JPM P-2 Rev Final.doc

Appendix C JPM STEPS Form ES-C-1 Perform Step: 7 Radiation Workers should log into the Access computer by:

• Inserting their electronic dosimeter to set up parameters and reset the dosimeter.

Standard: INSERT the electronic dosimeter to set up parameters and reset the dosimeter.

Examiner Note: The examinee will enter the RCA and perform required tasks.

Comment: SAT UNSAT Examiner Cue: Remind examinee to simulate these steps of this JPM.

Perform Step: 8 Verify the Liquid Waste Processing Discharge - HIGH Radiation alarm -

DARK

• X-LP-01 (AB 790 Rm X-174 LWPS Panel)

Standard: TRANSIT to the Liquid Waste Processing Panel and DETERMINE the ALM-0301-2.6, LWPS EFFLUENT MONITOR ALERT radiation alarm is illuminated.

Examiner Cue: LWPS alarm window 2.6, LWPS EFFLUENT MONITOR ALERT alarm is illuminated.

Comment: SAT UNSAT Perform Step: 9 Ensure liquid waste processing discharge valve CLOSED.

• X-RV-5253, LWPS LHMT X-01/X-02 DISCH HDR RAD ISOL VLV Standard: OBSERVE X-RV-5253, Laundry Holdup & Monitor Tank Discharge Valve position indication on the Liquid Waste Process Panel.

Examiner Cue: The red OPEN light is illuminated and the green CLOSE light is extinguished.

Comment: SAT UNSAT NUREG 1021, Revision 9.1 Page 4 of 7 CPNPP Mar 2009 RO & SRO JPM P-2 Rev Final.doc

Appendix C JPM STEPS Form ES-C-1 Examiner Note: The key operated valve has CLOSE/AUTO/OPEN positions.

Perform Step: 10 Ensure liquid waste processing discharge valve CLOSED.

• X-RV-5253, LWPS LHMT X-01/X-02 DISCH HDR RAD ISOL VLV Standard: INSERT key and TURN XHS-5253 handswitch to CLOSE position and OBSERVE X-RV-5253, Laundry Holdup & Monitor Tank Discharge Valve position indication on the Liquid Waste Process Panel.

Examiner Cue: The red OPEN light is illuminated and the green CLOSE light is extinguished.

Comment: SAT UNSAT Examiner Note: The following step represents the alternate path for this JPM.

Perform Step: 11 IF the valve can NOT be closed manually, THEN locally close its upstream isolation.

• XWP-0117, LWPS DISCH HDR VLV 5253 UPSTRM ISOL VLV (AB 790 near entrance to CCW HX Rm, X-175).

Standard: CLOSE XWP-0117, LWPS DISCH HDR VLV 5253 UPSTRM ISOL VLV by ROTATING the valve handwheel in the CLOCKWISE direction.

Examiner Cue: The upstream isolation is closed. This JPM will be completed upon exit from the RCA.

Comment: SAT UNSAT Perform Step: 12 Upon exit from the RCA, Radiation Workers should log out of the Access computer system by:

• Providing their EID Bar-Code identification.

Standard: Upon exit from the RCA, SCAN the EID Bar-Code identification.

Comment: SAT UNSAT NUREG 1021, Revision 9.1 Page 5 of 7 CPNPP Mar 2009 RO & SRO JPM P-2 Rev Final.doc

Appendix C JPM STEPS Form ES-C-1 Perform Step: 13 Upon exit from the RCA, Radiation Workers should log out of the Access computer system by:

• Inserting their electronic dosimeter to record dose and log off the system.

Standard: Upon exit from the RCA, INSERT the electronic dosimeter to record dose and LOG OFF the system.

Terminating Cue: This JPM is complete.

Comment: SAT UNSAT STOP TIME:

NUREG 1021, Revision 9.1 Page 6 of 7 CPNPP Mar 2009 RO & SRO JPM P-2 Rev Final.doc

Appendix C JPM CUE SHEET Form ES-C-1 INITIAL CONDITIONS: Given the following conditions:

• An accidental release of radioactive liquid is in progress.

• The Shift Manager has provided the key to operate X-HS-5253, Laundry Holdup & Monitor Tank Discharge Valve.

INITIATING CUE: The Unit Supervisor DIRECTS you to:

• ENTER the Radiation Control Area.

• LOG onto an appropriate Radiation Work Permit.

• PERFORM actions at the Liquid Waste Processing System Panel per ABN-903, Accidental Release of Radioactive Liquid starting at Step 2.3.2.

NUREG 1021, Revision 9.1 Page 7 of 7 CPNPP Mar 2009 RO & SRO JPM P-2 Rev Final.doc

Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # RO/SRO NRC P-3 Task # AO6405 K/A # 061.A2.04 3.4 / 3.8 SF-4S

Title:

Manually Latch and Open the Turbine Driven Auxiliary Feedwater Pump Trip & Throttle Valve Examinee (Print):

Testing Method:

Simulated Performance: X Classroom:

Actual Performance: Simulator:

Plant: X READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.

When you complete the task successfully, the objective for this JPM will be satisfied.

Initial Conditions: The Unit 1 (Unit 2) Turbine Driven Auxiliary Feedwater Pump has tripped on overspeed.

Initiating Cue: The Unit Supervisor directs you to RESET the Unit 1 (Unit 2) u-HV-2452, Trip and Throttle Valve for the Turbine Driven Auxiliary Feedwater Pump per ABN-305, Auxiliary Feedwater System Malfunction, Attachment 1.

Task Standard: Locate and correctly perform Critical Steps of ABN-305, Attachment 1.

Required Materials: ABN-305, Auxiliary Feedwater System Malfunction, Rev. 6, PCN-2 Validation Time: 5 minutes Time Critical: N/A Completion Time: ________ minutes Comments:

Result: SAT UNSAT Examiner (Print / Sign): Date:

NUREG 1021, Revision 9.1 Page 1 of 5 CPNPP Mar 2009 RO & SRO JPM P-3 Rev Final.doc

Appendix C JPM WORKSHEET Form ES-C-1 PLANT SETUP EXAMINER:

PROVIDE the examinee with a copy of:

• ABN-305, Auxiliary Feedwater System Malfunction, Attachment 1.

This JPM can be performed on either Unit. CIRCLE the Unit on which the JPM is to be performed on the JPM Worksheet and the JPM Cue Sheet.

NUREG 1021, Revision 9.1 Page 2 of 5 CPNPP Mar 2009 RO & SRO JPM P-3 Rev Final.doc

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Examiner Cue: Remind examinee to simulate all steps of this JPM.

Perform Step: 1 If the turbine has tripped on overspeed then manually reset the overspeed trip linkage.

Standard: MOVES linkage towards latch.

Examiner Cue: Trip linkage remains in the RESET position Comment: SAT UNSAT Perform Step: 2 Ensure flat surface of tappet nut lined up correctly with trip tappet head lever.

Standard: VERIFY tappet nut and trip tappet head lever alignment matches the picture on Attachment 1 of ABN-305.

Examiner Cue: Tappet nut is aligned correctly with trip tappet head lever.

Comment: SAT UNSAT Perform Step: 3 Turn handwheel clockwise until latch mechanism is fully engaged.

(Notice in photograph #2).

Standard: TURN handwheel clockwise until latch mechanism is fully engaged.

Examiner Cue: Latch mechanism is engaged.

Comment: SAT UNSAT Perform Step: 4 Turn handwheel counter clockwise until actuator is in the Fully Up position. ( Notice that the valve stem is now showing in photograph #3)

Standard: TURN handwheel counter clockwise until actuator is in the Fully Up position.

Examiner Cue: Actuator indicates full up.

Comment: SAT UNSAT NUREG 1021, Revision 9.1 Page 3 of 5 CPNPP Mar 2009 RO & SRO JPM P-3 Rev Final.doc

Appendix C JPM STEPS Form ES-C-1 Perform Step: 5 Notify the control room that the TDAFWP Trip and Throttle Valve is latched and open.

Standard: NOTIFY the control room that the TDAFWP Trip and Throttle Valve is latched and open.

Terminating Cue: Control room acknowledges the valve is latched and open. This JPM is complete.

Comment: SAT UNSAT STOP TIME:

NUREG 1021, Revision 9.1 Page 4 of 5 CPNPP Mar 2009 RO & SRO JPM P-3 Rev Final.doc

Appendix C JPM CUE SHEET Form ES-C-1 INITIAL CONDITIONS: The Unit 1 (Unit 2) Turbine Driven Auxiliary Feedwater Pump has tripped on overspeed.

INITIATING CUE: The Unit Supervisor directs you to RESET the Unit 1 (Unit 2) u-HV-2452, Trip and Throttle Valve for the Turbine Driven Auxiliary Feedwater Pump per ABN-305, Auxiliary Feedwater System Malfunction, Attachment 1.

PERFORM THIS JPM ON UNIT 1 (UNIT 2).

NUREG 1021, Revision 9.1 Page 5 of 5 CPNPP Mar 2009 RO & SRO JPM P-3 Rev Final.doc

Appendix D Scenario Outline Form ES-D-1 Facility: CPNPP 1 & 2 Scenario No.: 1 Op Test No.: March 2009 NRC Examiners: Operators:

Initial Conditions:

• 67% power MOC - RCS Boron is 922 ppm (by sample).

• Motor Driven Auxiliary Feedwater Pump 1-02 OOS for coupling repair. RTS in 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

• Heater Drain Pump 1-02 OOS for seal repair. RTS in 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

Turnover: Maintain steady-state power conditions while Heater Drain Pump repairs are made.

Critical Tasks:

• Emergency borate due to two (2) stuck Control Rods.

• Perform actions to identify and isolate the ruptured Steam Generator.

• Perform actions to cooldown and depressurize the Reactor Coolant System.

Event No. Malf. No. Event Type* Event Description 1 TC09D C (BOP, SRO) Main Feedwater Pump B trip with Auto Turbine Runback failure.

+10 min FW03B 2 OVRDE C (RO, SRO) Letdown Isolation Valve (HV-8160) fails closed.

+25 min CLOSE Place Excess Letdown in service.

3 SW01B C (BOP, SRO) Station Service Water Pump (1-02) trip.

+35 min TS (SRO) 4 SG01A C (RO, SRO) Steam Generator #1 Tube Leak at 175 gpd.

+45 min TS SRO 5 SG01A M (ALL) Steam Generator #1 Tube Rupture at 500 gpm.

+55 min 6 RD04M14 C (RO) Two (2) Control Rods fail to insert on Reactor trip. Emergency boration

+55 min RD04P8 required.

7 RH01C C (BOP) Residual Heat Removal Pump (1-01) fails to auto start on Safety

+60 min Injection signal.

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS)Technical Specifications CPNPP March 2009 NRC Sim Scenario #1 Rev Final.doc

Scenario Event Description NRC Scenario #1 SCENARIO

SUMMARY

NRC #1 The crew will assume the watch with power reduced due to a Heater Drain Pump Seal failure. Power is maintained per IPO-003A, Power Operations until repairs are made. Auxiliary Feedwater Pump 1-02 is out-of-service for coupling repair.

The first event is a trip of Main Feedwater Pump B with an automatic Turbine Runback failure. The crew responds per ABN-302, Feedwater, Condensate, Heater Drain System Malfunction. When it is determined that automatic plant response has not activated, a manual Turbine Runback will be initiated. The crew will stabilize load at 700 MWe.

When ABN-302 actions are complete, a loss of Letdown occurs due to a Letdown Isolation Valve failing closed. Actions are per ABN-105, Chemical and Volume Control System Malfunction, and require controlling Charging and Seal Injection flows until Letdown can be restored. The RO will be directed to place Excess Letdown in service.

This is followed by a trip of Station Service Water Pump 1-02. The crew will enter ABN-501, Station Service Water System Malfunction. Initial operator actions include placing the Train B Emergency Diesel Generator in PULL-OUT. The SRO will refer to Technical Specifications.

The next event is a Steam Generator #1 tube leak of 175 gpd. Crew actions are per ABN-106, High Secondary Activity. The SRO will refer to Technical Specifications.

When Technical Specifications are referenced, a Steam Generator #1 tube rupture occurs and leakage rises to 500 gpm. An uncontrolled loss of Pressurizer level will require a Reactor trip, initiation of Safety Injection and entry into EOP-0.0A, Reactor Trip or Safety Injection. At Step 13, a transition to EOP-3.0A, Steam Generator Tube Rupture will occur to isolate the ruptured Steam Generator. The event is complicated when two Control Rods fail to insert. Additionally, Residual Heat Removal Pump 1-01 fails to auto start on the Safety Injection signal.

The scenario is terminated when the ruptured Steam Generator is isolated, feedwater flow is properly aligned and the Reactor Coolant System cooldown is commenced.

Risk Significance:

• Risk important components out of service: Auxiliary Feedwater Pump 1-02

• Failure of risk important system prior to trip: Station Service Water Pump 1-02

• Risk significant core damage sequence: Steam Generator Tube Rupture

• Risk significant operator actions: Emergency borate due to 2 stuck rods Start Residual Heat Removal Pump 1-01 Identify and isolate the ruptured SG Cooldown and depressurize the RCS CPNPP March 2009 NRC Sim Scenario #1 Rev Final.doc

Scenario Event Description NRC Scenario #1 CPNPP March 2009 NRC Scenario #1 Initial License Examination BOOTH OPERATOR INSTRUCTIONS for SIMULATOR SETUP Initialize to IC #17 and Event File for NRC Scenario #1.

EVENT TYPE MALF # DESCRIPTION DEMAND INITIATING VALUE PARAMETER Setup N/A MDAFW Pump 1-02 OOS PULLOUT N/A Heater Drain Pump 1-02 OOS PULLOUT RD04M14 Two (2) Control Rods fail to insert - K0 RD04P8 RH01C Residual Heat Removal Pump (1-01) start failure - K0 1 TC09D Automatic Turbine Runback disabled - K1 1 FW03B Main Feedwater Pump B trip TRIP K1 2 OVRDE Letdown Isolation Valve (HV-8160) failure CLOSE K2 CLOSE 3 SW01B Station Service Water Pump (1-02) trip TRIP K3 4 SG01A Steam Generator #1 Tube Leak at 175 gpd 0.121528 K4 gpm 5 SG01A Steam Generator #1 Tube Rupture 500 gpm K5 (180 sec. ramp) 6 RD04M14 Two (2) Control Rods fail to insert on Reactor trip - K0 RD04P8 7 RH01C Residual Heat Removal Pump (1-01) start failure - K0 CPNPP March 2009 NRC Sim Scenario #1 Rev Final.doc

Scenario Event Description NRC Scenario #1 Booth Operator: INITIALIZE to IC #17 and NRC Scenario #1 SETUP file.

ENSURE all Simulator Annunciator Alarms are ACTIVE.

STOP Heater Drain Pump 1-02 and allow plant to stabilize.

ENSURE Control Board Tags are hung:

- Red tag Motor Driven Auxiliary Feedwater Pump 1-02.

- Red tag Heater Drain Pump 1-02.

ENSURE Operator Aid Tags reflect current boron conditions.

ENSURE Control Rods are in AUTO with Bank D at 176 steps.

ENSURE Turbine Load Rate set at 100 MWe/minute.

ENSURE Reactivity Briefing Sheet printout provided with Turnover.

ENSURE Runback is CLEAR and CLEAR the Alarm Screen on the ASD.

ENSURE procedures in progress are on SRO desk:

- COPY of IPO-003A, Power Operations, Section 5.5, Operating at Constant Turbine Load.

Significant Control Room Annunciators in Alarm:

PCIP-1.1 - SR TRN A RX TRIP BLK PCIP-1.2 - IR TRN A RX TRIP BLK PCIP-1.4 - CNDSR AVAIL STM DMP ARMED C-9 PCIP-1.6 - RX 10% PWR P-10 PCIP-2.1 - SR TRN B RX TRIP BLK PCIP-2.2 - IR TRN B RX TRIP BLK PCIP-2.5 - SR RX TRIP BLK PERM P-6 PCIP-3.2 - PR TRN A LO SETPT RX TRIP BLK PCIP-4.2 - PR TRN B LO SETPT RX TRIP BLK CPNPP March 2009 NRC Sim Scenario #1 Rev Final.doc

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 1 Page 5 of 20 Event

Description:

Main Feedwater Pump B Trip / Automatic Turbine Runback Disabled Time Position Applicants Actions or Behavior Booth Operator: When directed, EXECUTE Event 1.

- FW03B, Main Feedwater Pump B trip.

- TC09D, Auto Turbine Runback failure.

Indications available:

8A-1.3 - FWPT B TRIP

+30 secs RO/BOP RESPOND to Annunciator Alarm Procedures.

RECOGNIZE trip of Main Feedwater Pump B with no automatic Turbine BOP Runback.

DIRECT performance of ABN-302, Feedwater, Condensate, Heater Drain US System Malfunction.

RO VERIFY control rods in AUTO.

US DETERMINE Turbine Runback not in progress.

US DIRECT manual INITIATION of Turbine Runback.

BOP PERFORM the following to LOWER Turbine Load:

• DEPRESS 700 MWe Manual Runback button.

• CLICK on O/I button.

• CLICK on Execute then VERIFY Manual Runback in progress.

RO STABILIZE Reactor power.

BOP VERIFY Main Feedwater flow to Steam Generators.

VERIFY Feedwater header pressure greater than Main Steam header BOP pressure.

BOP ENSURE FK-2290, Feedwater Pump B Recirc Flow Control Valve closed.

CPNPP March 2009 NRC Sim Scenario #1 Rev Final.doc

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 1 Page 6 of 20 Event

Description:

Main Feedwater Pump B Trip / Automatic Turbine Runback Disabled Time Position Applicants Actions or Behavior RO VERIFY Tave trending to Tref.

MONITOR Steam Generator level - STABLE OR TRENDING TO NORMAL BOP OPERATING RANGE.

VERIFY Feedwater to Main Steam differential pressure from 80 PSID to 170 BOP PSID.

BOP VERIFY Steam Generator Feedwater Flow Control Valves in AUTO.

BOP VERIFY Main Feedwater Pump flow less than 22,000 gpm.

RO VERIFY Control Rods above insertion limit.

RO VERIFY Flux within target band.

BOP VERIFY C-7, Steam Dump Arming Signal Interlock is RESET.

+10 min US INITIATE repairs per STA-606.

When Feedwater parameters are stable, or at Lead Examiner discretion, PROCEED to Event 2.

CPNPP March 2009 NRC Sim Scenario #1 Rev Final.doc

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 2 Page 7 of 20 Event

Description:

Loss of Letdown Time Position Applicants Actions or Behavior Booth Operator: When directed, EXECUTE Event 2.

- OVERRIDE CLOSE HV-8160, Letdown Isolation Valve fails closed.

Indications available:

6A-3.8 - CVCS HELB PS-5385A 6A-4.8 - CVCS HELB PS-5385 6A-4.3 - LTDN RLF VLV OUT TEMP HI

+1 min RO RESPOND to Annunciator Alarm Procedures.

RECOGNIZE 1-HV-8160, Letdown Isolation Valve has failed closed and RO isolate letdown per ALM-0061A.

DIRECT performance of ABN-105, Chemical and Volume Control System US Malfunction, Section 5.0.

VERIFY all Pressurizer level channels indicating approximately the same RO level.

RO VERIFY Pressurizer level greater than 17%.

RO DETERMINE 1-FI-132, Letdown Flow is zero (0) gpm.

Slowly manually LOWER 1-FK-121, charging flow control valve to 32 gpm RO while ADJUSTING 1-HC-182, RCP to maintain between 6 gpm and 13 gpm seal injection flow.

DETERMINE 1-PK-131, Letdown heat exchanger outlet pressure control RO valve NOT maintaining 310 psig.

DETERMINE normal Letdown is NOT in service and establish Excess RO Letdown.

RO VERIFY one Charging Pump - RUNNING.

DIRECT performance of SOP-103A, Chemical and Volume Control System US Operation, Section 5.5.3, Placing Excess Letdown in Service.

CPNPP March 2009 NRC Sim Scenario #1 Rev Final.doc

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 2 Page 8 of 20 Event

Description:

Loss of Letdown Time Position Applicants Actions or Behavior RO ALIGN component cooling water to the Excess Letdown heat exchanger.

• VERIFY 1-HS-4710, Excess Letdown Heat Exchanger CCW supply isolation valve is OPEN.

• VERIFY 1-HS-4711, Excess Letdown Heat Exchanger CCW return isolation valve is OPEN.

• OBSERVE 1-FI-4703, Excess Letdown Heat Exchanger CCW return flow.

RO PLACE 1/1-8143, Excess Letdown Divert Valve in RCDT.

RO OPEN Excess Letdown Heat Exchanger loop isolation valves.

• OPEN 1/1-8153, Excess Letdown isolation valve.

• OPEN 1/1-8154, Excess Letdown isolation valve.

RO Slowly OPEN 1-HC-123, Excess Letdown Heat Exchanger flow control valve.

+15 min RO ENSURE seal injection flow is between 6 gpm and 8 gpm on each RCP.

When Excess Letdown is in service, or at Lead Examiner discretion, PROCEED to Event 3.

CPNPP March 2009 NRC Sim Scenario #1 Rev Final.doc

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 3 Page 9 of 20 Event

Description:

Station Service Water Pump Trip Time Position Applicants Actions or Behavior Booth Operator: When directed, EXECUTE Event 3.

- SW01B, Station Service Water Pump 1-02 tripped.

Indications available:

1-1.8 - SSWP 1/2 OVRLOAD / TRIP 1-2.11 - CCP 2 L/O CLR SSW RET FLO LO 1-2.12 - SIP 2 L/O CLR SSW RET FLO LO 1-4.8 - CSP 2 & 4 BRG CLR SSW RET FLO LO

+30 secs BOP RESPOND to Annunciator Alarm Procedures.

RECOGNIZE 1-HS-4251A, Service Water Pump 1-02 amber MISMATCH BOP and white TRIP lights illuminated.

Examiner Note: The next step is an Initial Operator Action.

BOP PLACE CS-1-DG2E, DG2 Emergency Stop / Start Switch in PULL-OUT.

DIRECT performance of ABN-501, Station Service Water System US Malfunction, Section 2.0.

BOP VERIFY Train A SSW Pump running.

BOP VERIFY Train A CCW Pump running.

Booth Operator: When asked about status of SSW Pump, REPORT that the SSW Pump 1-02 50/51 overcurrent relays on Phases A & B are tripped.

RO/BOP VERIFY equipment on Train B not required for operation:

• Centrifugal Charging Pump 2

• Diesel Generator 2

• Component Cooling Water Pump 2

• Safety Injection Pump 2

• Containment Spray Pumps 2 & 4 CPNPP March 2009 NRC Sim Scenario #1 Rev Final.doc

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 3 Page 10 of 20 Event

Description:

Station Service Water Pump Trip Time Position Applicants Actions or Behavior RO/BOP PLACE equipment on Train B in PULL-OUT.

• Centrifugal Charging Pump 2

• Station Service Water Pump 2 (may leave as is due to CAUTION)

• Safety Injection Pump 2

• Containment Spray Pumps 2 & 4 DETERMINE Component Cooling Water Pump and Heat Exchangers on BOP Train B NOT in service.

+10 min US EVALUATE Technical Specifications.

• LCO 3.7.8.B, Station Service Water System.

• CONDITION B - One SSWS Train INOPERABLE.

• ACTION B.1 - Restore SSWS Train to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

• LCO 3.8.1.B, AC Sources - Operating.

• CONDITION B - With one DG INOPERABLE.

• ACTION B.1 - Perform SR 3.8.1.1 for the required offsite circuits within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> AND once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter.

Booth Operator: If contacted, INFORM the Unit Supervisor that another operator will perform required Tech Spec Surveillance.

When Technical Specifications are addressed, or at Lead Examiner discretion, PROCEED to Event 4.

CPNPP March 2009 NRC Sim Scenario #1 Rev Final.doc

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 4 Page 11 of 20 Event

Description:

Steam Generator #1 Tube Leak Time Position Applicants Actions or Behavior Booth Operator: When directed, EXECUTE Event 4.

- SG01A, Steam Generator #1 Tube Leak at 175 gpd (0.121528 gpm).

Indications available:

PC 178 MSL #1 (1-RE-2325) is YELLOW PC N16-174 MSL #1 (1-RE-2325A) is RED

+1 min RO/BOP RESPOND to Annunciator Alarm Procedures.

RO/BOP RECOGNIZE radiation monitor alarms associated with Steam Generator #1.

US DIRECT performance of ABN-106, High Secondary Activity, Section 3.0.

DETERMINE Main Steam Line #1 radiation alarm 1-RE-2325 is YELLOW RO/BOP and 1-RE-2325A is RED on PC-11.

RO/BOP CORRELATE monitor readings to leak rate and rate of change as necessary.

US/RO DETERMINE rate of change in leak rate is > 30 gpd.

Examiner Note: Crew may implement the Reactivity Briefing Sheet for a Rapid Plant Shutdown within one (1) hour since this guidance is readily available.

US REDUCE power to 50% in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> AND be in MODE 3 in the next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

RO DETERMINE PRZR level is stable.

RO PERFORM RCS leak rate per the Job Aid.

ADJUST Steam Generator #1 Atmospheric Relief Controller setpoint to 1160 BOP PSIG per TDM-501A/B.

BOP PLACE 1-HV-2452-2, TDAFW Pump Steam Supply Valve in PULL-OUT.

CPNPP March 2009 NRC Sim Scenario #1 Rev Final.doc

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 4 Page 12 of 20 Event

Description:

Steam Generator #1 Tube Leak Time Position Applicants Actions or Behavior DIRECT load reduction to 200 MWe per IPO-003A, Power Operations, US Section 5.6, Reducing Turbine Power from 100% to MODE 3.

INITIATE RCS boration per SOP-104A, Reactor Make-up and Chemical RO Control System.

SET Turbine Load Rate Setpoint Controller as required and Load Target to BOP 200 MWe.

RO PERFORM the following to COMMENCE RCS boration:

• ENSURE 1/1-MU, RCS Makeup Manual Actuation is in STOP.

• PLACE 43/1-MU, RCS Makeup Mode Select in BORATE.

• SET 1-FK-110, BA Blender Flow Control to desired flowrate.

• SET 1-FY-110B, BA Batch Flow counter for number of gallons.

• ENSURE 1/1-FCV-110A, BA Blender Flow Control Valve in AUTO.

• PLACE 1/1-MU, RCS Makeup Manual Actuation in START.

• VERIFY 1/1-APBA1, Boric Acid Transfer Pump starts.

• VERIFY 1/1-FCV-110A, Boric Acid Blender Flow Control Valve throttles to the preset flow rate.

• VERIFY 1/1-FCV-110B, RCS Makeup to Charging Pump Suction Isolation Valve OPEN.

• VERIFY 1-FR-110, Boric Acid Flow to Blender RED pen operating properly.

• VERIFY 1-FY-110B, Batch Flow counter operating properly.

• When desired amount of boric acid is added, PLACE 1/1-MU, RCS Makeup Manual Actuation in STOP.

• FLUSH the blender with approximately 50 gallons makeup water when boration is complete.

CPNPP March 2009 NRC Sim Scenario #1 Rev Final.doc

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 4 Page 13 of 20 Event

Description:

Steam Generator #1 Tube Leak Time Position Applicants Actions or Behavior BOP PERFORM the following to LOWER Turbine Load:

• CHANGE Turbine Load Rate to desired MWe / min reduction.

• OPEN Load Target OSD.

• SELECT blue bar and ENTER desired load.

• DEPRESS Select then VERIFY value in blue bar is desired Load Target (magnitude and direction).

• DEPRESS Execute then VERIFY Load Target changes to desired load.

+10 min US EVALUATE Technical Specifications.

• LCO 3.4.13.B, RCS Operational Leakage

• CONDITION B - Primary to secondary leakage not within limits.

• ACTION B.1 - Be in MODE 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> AND be in MODE 5 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

When Technical Specifications are addressed, or at Lead Examiner discretion, PROCEED to Events 5, 6, and 7.

CPNPP March 2009 NRC Sim Scenario #1 Rev Final.doc

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 5, 6, & 7 Page 14 of 20 Event

Description:

Steam Generator Tube Rupture / Two Rods Fail to Insert / RHR Pump Auto Start Failure Time Position Applicants Actions or Behavior Booth Operator: When directed, EXECUTE Events 5, 6, and 7.

- SG01A, Steam Generator #1 Tube Rupture (500 gpm on 180 second ramp).

- RD04M14 & RD04P8, two (2) Control Rods fail to insert on Reactor trip.

- RH01C, Residual Heat Removal Pump 1-01 fails to auto start.

Indications available:

5B-3.4 - PRZR 1 OF 4 PRESS LO 5B-3.6 - PRZR LEVEL LO Main Steam Line Radiation level rising Condenser Off-Gas Radiation level rising Numerous Pressurizer pressure alarms

+2 min RECOGNIZE Pressurizer level and pressure decreasing at an increasing RO/BOP rate.

RECOGNIZE PRZR pressure decreasing with steam line radiation monitors RO/BOP in alarm and steam / feed mismatch.

US DIRECT Reactor Trip and Safety Injection.

US DIRECT performance of EOP-0.0A, Reactor Trip or Safety Injection.

RO VERIFY Reactor Trip:

• Reactor trip breakers - OPEN.

• Neutron flux - DECREASING.

RO DETERMINE all control rod position rod bottom lights - NOT on.

Examiner Note: Not performed until Foldout Page items are initiated following completion of Immediate Action verification (After Step 4 of EOP-0.0A is verbally verified complete).

CRITICAL TASK Initiate emergency boration with two (2) or more control rods not inserted.

STATEMENT CRITICAL TASK RO INITIATE emergency boration.

CPNPP March 2009 NRC Sim Scenario #1 Rev Final.doc

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 5, 6, & 7 Page 15 of 20 Event

Description:

Steam Generator Tube Rupture / Two Rods Fail to Insert / RHR Pump Auto Start Failure Time Position Applicants Actions or Behavior BOP VERIFY Turbine Trip:

• All HP turbine stop valves - CLOSED.

BOP VERIFY Power to AC Safeguards Buses:

• AC safeguards buses - BOTH ENERGIZED.

RO DETERMINE both Trains of SI actuated.

Examiner Note: BOP may stop AFW flow to Steam Generator 1-01 per EOP-0.0A Foldout Page if Narrow Range level is > 43 % following completion of Immediate Action verification (After Step 4 of EOP-0.0A is verbally verified complete).

Examiner Note: EOP-0.0A, Attachment 2 steps performed by BOP are identified later in the scenario.

US/BOP INITIATE Proper Safeguards Equipment Operation Per Attachment 2.

RO VERIFY AFW Alignment:

• MDAFW Pump 1 RUNNING.

• Turbine Driven AFW Pump - RUNNING.

• AFW total flow - GREATER THAN 460 GPM.

• AFW valve alignment - PROPER ALIGNMENT.

RO VERIFY Containment Spray Not Required:

• VERIFY 1-ALB-2B window 1-8, CS ACT NOT ILLUMINATED.

• VERIFY 1-ALB-2B window 4-11, CNTMT ISOL PHASE B ACT NOT ILLUMINATED.

• VERIFY Containment pressure < 18.0 PSIG.

• VERIFY Containment spray heat exchanger out valves - CLOSED.

• VERIFY Containment spray pumps 1 & 3 - RUNNING.

CPNPP March 2009 NRC Sim Scenario #1 Rev Final.doc

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 5, 6, & 7 Page 16 of 20 Event

Description:

Steam Generator Tube Rupture / Two Rods Fail to Insert / RHR Pump Auto Start Failure Time Position Applicants Actions or Behavior RO CHECK If Main Steam lines should be Isolated:

• DETERMINE Containment pressure 0 PSIG and stable.

• DETERMINE Main Steam pressure ~ 1080 PSIG and stable.

RO CHECK RCS Temperature -

• RCS average temperature - STABLE AT OR TRENDING TO 557°F.

RO CHECK PRZR Valve Status:

• PRZR Safeties - CLOSED.

• NORMAL PRZR spray valves - CLOSED.

• PORVs - CLOSED.

• Power to at least one block valve - AVAILABLE.

• Block valves - AT LEAST ONE OPEN.

RO CHECK If RCPs Should Be Stopped:

• ECCS pumps - AT LEAST ONE RUNNING.

• CCP Pump 1-01 and SI Pump1 RUNNING.

• RCS subcooling - GREATER THAN 25°F.

US/RO DETERMINE RCPs should remain running.

US/RO CHECK if Any SG Is Faulted:

• DETERMINE pressure in all SGs - NORMAL.

US/RO CHECK if SG Tubes are Not Ruptured:

• DETERMINE SG #1 is ruptured and TRANSITION to EOP-3.0A, Steam Generator Tube Rupture, Step 1.

CPNPP March 2009 NRC Sim Scenario #1 Rev Final.doc

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 5, 6, & 7 Page 17 of 20 Event

Description:

Steam Generator Tube Rupture / Two Rods Fail to Insert / RHR Pump Auto Start Failure Time Position Applicants Actions or Behavior Examiner Note: These steps are performed by the BOP as required per EOP-0.0A, Attachment 2. EOP-3.0A steps are identified later in the scenario.

BOP VERIFY SSW Alignment:

• VERIFY SSW Pumps 1 RUNNING.

• VERIFY diesel generator cooler SSW return flow.

BOP VERIFY Safety Injection Pump 1 RUNNING.

BOP VERIFY Containment Isolation Phase A.

BOP VERIFY Containment Ventilation Isolation.

BOP VERIFY CCW Pumps - RUNNING.

BOP DETERMINE RHR Pump 1 NOT RUNNING and manually START RHR Pump 1-01.

BOP VERIFY Proper CVCS Alignment:

• VERIFY CCP 1 RUNNING.

• VERIFY Letdown Relief Valve isolation:

• Letdown orifice isolation valves - CLOSED.

• Letdown isolation valves - CLOSED.

• 1/1-LCV-459 and 1/1-LCV-460.

BOP VERIFY ECCS flow:

• VERIFY CCP SI flow indicator.

• VERIFY RCS pressure < 1800 PSIG.

• VERIFY SIP 1-01 discharge flow indicator.

• VERIFY RCS pressure > 325 PSIG.

CPNPP March 2009 NRC Sim Scenario #1 Rev Final.doc

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 5, 6, & 7 Page 18 of 20 Event

Description:

Steam Generator Tube Rupture / Two Rods Fail to Insert / RHR Pump Auto Start Failure Time Position Applicants Actions or Behavior BOP VERIFY Feedwater Isolation Complete:

• VERIFY feedwater isolation valves CLOSED.

• VERIFY feedwater isolation bypass valves CLOSED.

• VERIFY feedwater bypass control valves CLOSED.

• VERIFY feedwater control valves CLOSED.

BOP VERIFY Train A Diesel Generator - RUNNING.

BOP VERIFY Monitor Lights For SI Load Shedding - LIT.

BOP VERIFY Proper SI alignment per MLB light indication.

BOP VERIFY Safety Injection components aligned per Table 1.

Examiner Note: EOP-3.0A, Steam Generator Tube Rupture steps begin here.

+15 min US/RO CHECK If RCPs Should Be Stopped:

• ECCS pumps - AT LEAST ONE RUNNING.

• CCP 1-01 and SI pump 1-01 RUNNING.

• RCS subcooling - GREATER THAN 25°F.

US/RO DETERMINE RCPs should remain running.

US/BOP DETERMINE Steam Generator #1 is ruptured.

• Unexpected increase in Steam Generator #1 narrow range level.

• High radiation from Steam Generator #1 blowdown sample line.

• High radiation from Steam Generator #1 Main Steam line.

CPNPP March 2009 NRC Sim Scenario #1 Rev Final.doc

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 5, 6, & 7 Page 19 of 20 Event

Description:

Steam Generator Tube Rupture / Two Rods Fail to Insert / RHR Pump Auto Start Failure Time Position Applicants Actions or Behavior CRITICAL TASK Isolate flow from ruptured Steam Generator prior to operator induced STATEMENT cooldown.

CRITICAL TASK RO/BOP ISOLATE Flow From Ruptured Steam Generator #1.

• VERIFY SG #1 atmospheric controller setpoint at 1160 PSIG.

• CHECK SG #1 atmospheric - CLOSED.

• CLOSE SG #1 main steam line isolation and SG drip pot isolation valves.

• CLOSE SG #1 blowdown valves.

• VERIFY SG #1 TDAFW Pump steam supply valve - CLOSED.

RO/BOP CHECK Ruptured SG #1 Level:

• VERIFY narrow range level > 43%.

• ISOLATE AFW flow to SG #1.

RO/BOP VERIFY SG #1 Pressure > 420 PSIG.

CRITICAL TASK Cooldown and depressurize Reactor Coolant System.

STATEMENT CRITICAL TASK RO/BOP INITIATE RCS Cooldown.

RO/BOP When PRZR pressure decreases to less than 1960 psig, BLOCK the low steamline pressure SI signal.

US DETERMINE required core exit thermocouple (CET) temperature from Table 1.

BOP DUMP steam to condenser from intact SG(s) at maximum rate using the Steam Dump Valves.

BOP TRANSFER the Steam Dump Valves to STEAM PRESSURE Mode.

CPNPP March 2009 NRC Sim Scenario #1 Rev Final.doc

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 5, 6, & 7 Page 20 of 20 Event

Description:

Steam Generator Tube Rupture / Two Rods Fail to Insert / RHR Pump Auto Start Failure Time Position Applicants Actions or Behavior BOP PLACE the Steam Pressure Controller in MANUAL and increase demand.

US/RO DETERMINE required CET temperature is met.

BOP STOP RCS cooldown.

RO/BOP MAINTAIN required CET temperature.

+30 min RO/BOP CHECK Intact SG Levels:

• Narrow range level > 43%.

• CONTROL AFW flow to maintain narrow range level between 50% and 60%.

When required CET temperature is met, TERMINATE the scenario.

CPNPP March 2009 NRC Sim Scenario #1 Rev Final.doc

UNIT: 1 UNIT SUPERVISOR RELIEF CHECKLIST (NRC Scenario #1)

PART I TO BE PREPARED BY THE OFF-GOING UNIT SUPERVISOR.

1.0 SHIFT ACTIVITIES:

1.1 Activities Completed This Shift: None 1.2 Activities In-Progress: None 1.3 Planned Activities: Power ascension once repairs to Heater Drain Pump 1-02 seal are complete. Estimated Return-to-Service time is eight (8) hours.

2.0 PLANT AND EQUIPMENT STATUS:

2.1 Technical Specification Related Equipment Summary:

Train B Motor Driven Auxiliary Feedwater Pump 1-02 out-of-service for bearing replacement.

Estimated Return-to-Service time is four (4) hours.

2.2 Non-Technical Specification Equipment Summary:

3.0 GENERAL INFORMATION:

Maintain power per IPO-003A, Power Operation, Section 5.5, Operating at Constant Turbine Load.

Equilibrium Xenon condition.

4.0 END OF SHIFT REVIEW:

LOGS - RO/BOP X LOGS-PEO X CLOSED eLCOARs ARCHIVED X OPTS COMPLETED X DAILY ACTIVITIES LIST X LCOARs REVIEWED X PART II TO BE COMPLETED BY THE ON-COMING UNIT SUPERVISOR.

1.0 CRITICAL PARAMETERS:

MODE: 1 REACTOR POWER: 67% MWE: 811 RCS CONTROL ROD TAVE: 576 °F POSITION 176 ON BANK D RCS Cb: 922 ppm PRESS: 2235 psig X Protected Train - Train A X Unit 2 is in Mode 1 @ 100% power X Risk Assessment GREEN X BAT CB = 7447 ppm CPNPP March 2009 NRC Scenario #1 Shift Relief Checklist Rev .doc

Appendix D Scenario Outline Form ES-D-1 Facility: CPNPP 1 & 2 Scenario No.: 2 Op Test No.: March 2009 NRC Examiners: Operators:

Initial Conditions: * ~1X10-8 amps BOC - RCS Boron is 1545 ppm (by sample).

• Steam Dump System in service for RCS Temperature Control.

Turnover: Raise Power to 2% in preparation for plant startup to 100% power.

Critical Tasks:

• Restore feedwater flow from the Turbine Driven Auxiliary Feedwater Pump.

• Restore power to at least one 6900 VAC Safeguards Bus.

• Initiate emergency boration due to loss of Digital Rod Position Indication.

Event No. Malf. No. Event Type* Event Description 1 R (RO) Raise Reactor power to 2%.

+20 min N (SRO, BOP) 2 FW24A C (BOP, SRO) Motor Driven Auxiliary Feedwater Pump (1-01) trip.

+30 min TS (SRO) 3 CV16A I (RO, SRO) Volume Control Tank Level Transmitter (LT-112) fails low.

+35 min 4 RX08A I (RO, SRO) Pressurizer Pressure Channel (PT-455) fails low.

+45 min TS (SRO) 5 Tornado Warning from the National Weather Service.

+55 min 6 ED01 M (ALL) Loss of All AC Power due to Loss of Offsite Power.

+55 min 7 EG06A C (BOP) Emergency Diesel Generator (1-01) fails to start.

+60 min EG15B Emergency Diesel Generator (1-02) fails to auto and emergency start; EDG (1-02) starts upon Normal Start Switch actuation.

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS)Technical Specifications CPNPP March 2009 NRC Sim Scenario #2 Rev Final.doc

Scenario Event Description NRC Scenario #2 SCENARIO

SUMMARY

NRC #2 The crew takes the shift with a Plant Startup in progress and will continue raising power to approximately 2% per IPO-002A, Plant Startup from Hot Standby.

When conditions are stable, Motor Driven Auxiliary Feedwater Pump 1-01 will trip. The crew will refer to ABN-305, Auxiliary Feedwater System Malfunction and determine that Steam Generator levels are slowly decreasing and start the Turbine Driven Auxiliary Feedwater Pump. The SRO will refer to Technical Specifications.

The next event is the failure of Volume Control Tank level transmitter LT-112. Actions per ABN-105, Chemical and Volume Control System Malfunction will be performed. This event will disable automatic makeup flow to the Volume Control Tank.

When ABN-105 actions are complete, Pressurizer Pressure Channel PT-455 will fail low. The crew will respond per ABN-705, Pressurizer Pressure Malfunction, and ensure Pressurizer Heaters are controlled and Power Operated Relief Valves remain closed. The SRO will refer to Technical Specifications.

When plant conditions are stable, a tornado warning from the National Weather Service will require entry into ABN-907, Acts of Nature. This is the precursor event to a Loss of Offsite Power.

The next event is a Loss of Offsite Power with a failure on each Emergency Diesel Generator resulting in a Total Loss of All AC. The crew enters EOP-0.0A, Reactor Trip or Safety Injection and then exits to ECA-0.0A, Loss of All AC Power, at Step 3. As an alternative the Unit Supervisor may directly enter ECA-0.0A. While in ECA-0.0A, the crew will take actions that start Emergency Diesel Generator 1-02.

The RO may initiate an emergency boration due to loss of Digital Rod Position Indication (DRPI) while in ECA-0.0A if rod position is not observed prior to loss of DRPI.

Once Emergency Diesel Generator 1-02 is started and the breaker is closed in ECA-0.0A, a return to the procedure and step in effect is required. The crew will return to EOP-0.0A and then transition to EOS-0.1A, Reactor Trip Response when it is determined that Safety Injection is not required.

The scenario is terminated after EOS-0.1A, Reactor Trip Response is entered and the actions to stabilize the Unit are performed.

Risk Significance:

• Risk important components out of service: None

• Failure of risk important system prior to trip: Loss of MDAFW Pump 1-01

• Risk significant core damage sequence: Loss of all AC Power

• Risk significant operator actions: Restore Auxiliary Feedwater flow Restore power to 6.9 KV Safeguards Bus Initiate emergency boration CPNPP March 2009 NRC Sim Scenario #2 Rev Final.doc

Scenario Event Description NRC Scenario #2 CPNPP March 2009 NRC Scenario #2 Initial License Examination BOOTH OPERATOR INSTRUCTIONS for SIMULATOR SETUP Initialize to IC #8 and Event File for NRC Scenario #2.

EVENT TYPE MALF # DESCRIPTION DEMAND INITIATING VALUE PARAMETER Setup EG06A EDG (1-01) start failure - K0 EG15B EDG (1-02) fails to auto and emergency start - K0 1 N/A Raise Reactor power to 2% - K0 2 FW24A MDAFW Pump (1-01) trip. TRIP K2 3 CV16A VCT Level Transmitter (LT-112) failure 0% K3 4 RX08A Pressurizer Pressure Channel (PT-455) failure 1700 K4 5 Tornado Warning from National Weather Service - K0 6 ED01 Loss of All AC Power OFF K6 7 EG06A EDG (1-01) start failure - K0 7 EG15B EDG (1-02) fails to auto and emergency start - K0 CPNPP March 2009 NRC Sim Scenario #2 Rev Final.doc

Scenario Event Description NRC Scenario #2 Booth Operator: INITIALIZE to IC #8 and NRC Scenario #2 SETUP file.

ENSURE all Simulator Annunciator Alarms are ACTIVE.

VERIFY all Control Board Tags are removed.

ENSURE Control Rod Bank D @ 100 steps.

ENSURE Operator Aid Tags reflect current boron conditions.

ENSURE Reactivity Briefing Sheet printout provided with Turnover.

ENSURE procedures in progress are on SRO desk:

- COPY of IPO-002A, Plant Startup from Hot Standby, Section 5.4, Increasing Reactor power to ~2%.

SET Plant Computer screen for MODE 2.

Significant Control Room Annunciators in Alarm:

PCIP-1.1 - SR TRN A RX TRIP BLK PCIP-1.3 - AMSAC BLK TURB <40% PWR C-20 PCIP-1.4 - CNDNSR AVAIL STM DUMP ARMED C-9 PCIP-1.7 - RX 50% PWR TURB TRIP PERM P-9 PCIP-2.1 - SR TRN B RX TRIP BLK PCIP-2.4 - LO TURB PWR ROD WTHDRWL BLK C-5 PCIP-2.5 - SR RX TRIP BLK PERM P-6 PCIP-3.5 - RX & TURB 10% PWR P-7 PCIP-4.5 - RX 48% PWR 3-LOOP FLO PERM P-8 PCIP-4.6 - TURB 10% PWR P-13 6D-1.1 - SR HI VOLT FAIL 7B-1.6 - FW FLUSH VLV NOT CLOSE HV-2166 7B-4.8 - FWP A/B RECIRC FLUSH VLV NOT CLOSED 8A-1.3 - FWPT B TRIP 8A-1.10 - 1 OF 4 TURB STOP VLV CLOSE Numerous 9A Feedwater alarms CPNPP March 2009 NRC Sim Scenario #2 Rev Final.doc

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 1 Page 5 of 17 Event

Description:

Power Ascension to ~2%

Time Position Applicants Actions or Behavior Booth Operator: PLACE Simulator in FREEZE until crew is ready to assume the watch.

+1 min US DIRECT performance of IPO-002A, Plant Startup from Hot Standby.

RO ESTABLISH a startup rate of ~ 0.5 DPM to increase Reactor power to ~ 2%.

Gradually REDUCE startup rate to ~0.2 DPM as the Intermediate Range RO channels approach 3x10-6 amps.

VERIFY Power Range channels begin to respond when the Intermediate RO Range Channels are between 3x10-6 amps and 5x10-6 amps.

VERIFY Steam Dump operations maintain RCS temperature at 557ºF and BOP Main Steam pressure at 1092 psig.

RO VERIFY annunciator alarm PCIP-3.6, TAVE LO LO P-12 is OFF.

RO MAINTAIN Reactor power between 2% and 3%.

ADJUST Auxiliary Feedwater flow as necessary to maintain SG levels BOP between 60% and 75%.

+20 min NOTIFY Generation Controller of the Reactor startup and the estimated time US for synchronization.

When power has been raised to ~2%, or at Lead Examiner discretion, PROCEED to Event 2.

CPNPP March 2009 NRC Sim Scenario #2 Rev Final.doc

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 2 Page 6 of 17 Event

Description:

Motor Driven Auxiliary Feedwater Pump Trip Time Position Applicants Actions or Behavior Booth Operator: When directed, EXECUTE Event 2.

- FW24A, Motor Driven Auxiliary Feedwater Pump 1-01 trip.

Indications available:

8B-4.3 - MD AFWP 1 / 2 OVRLOAD / TRIP

+1 min BOP RESPOND to Annunciator Alarm Procedure.

BOP RECOGNIZE Motor Driven Auxiliary Feedwater Pump 1-01 trip.

DIRECT performance of ABN-305, Auxiliary Feedwater System Malfunction, US Section 3.0.

DETERMINE MDAFW Pump 1-02 running and PLACE MDAFW Pump 1-01 BOP in STOP or PULL-OUT.

BOP DETERMINE Steam Generator Levels trending down.

CRITICAL TASK Restore feedwater flow to any affected Steam Generator.

STATEMENT CRITICAL BOP START the TDAFW Pump and FEED the affected Steam Generators.

TASK DISPATCH a Plant Equipment Operator to check breaker status of Auxiliary BOP Feedwater Pump 1-01.

• 1EA1/5/BKR, 1APMD1, Auxiliary Feedwater Pump 1-01 BKR.

Booth Operator: When contacted about the condition of the MDAFW Pump breaker, REPORT an acrid smell and overcurrent flag on Phase B 50/51 relays.

BOP VERIFY MDAFW Pump suction pressure 10 psig.

DISPATCH a Plant Equipment Operator to check the Auxiliary Feedwater BOP Pump 1-01.

CPNPP March 2009 NRC Sim Scenario #2 Rev Final.doc

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 2 Page 7 of 17 Event

Description:

Motor Driven Auxiliary Feedwater Pump Trip Time Position Applicants Actions or Behavior Booth Operator: When contacted about the condition of the MDAFW Pump, REPORT that the pump motor is hot.

+10 min US EVALUATE Technical Specifications.

• LCO 3.7.5.B, Auxiliary Feedwater (AFW) System.

• CONDITION B - One AFW train INOPERABLE for reasons other than Condition A.

• ACTION B.1 - Restore AFW train to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

When Technical Specifications are addressed, or at Lead Examiner discretion, PROCEED to Event 3.

CPNPP March 2009 NRC Sim Scenario #2 Rev Final.doc

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 3 Page 8 of 17 Event

Description:

Volume Control Tank Level Transmitter Failure Time Position Applicants Actions or Behavior Booth Operator: When directed, EXECUTE Event 3.

- CV16A, Volume Control Tank (1-LT-112) fails low.

Indications available:

6A-3.5 - VCT LVL LO 6A-4.5 - VCT LVL LO-LO 1-LI-112A - VCT level indication fails low

+1 min RO RESPOND to Annunciator Alarm Procedures.

RECOGNIZE VCT level transmitter (1-LT-112) failed low and stop Reactor RO Makeup to the VCT by placing 1/1-MU RCS MU MAN ACT handswitch in STOP.

DIRECT performance of ABN-105, Chemical and Volume Control System US Malfunction, Section 6.0.

DETERMINE Reactor Makeup System NOT in NORMAL OPERATING RO MODE.

RO DETERMINE Charging Pump Suction - ALIGNED TO VCT.

DETERMINE Reactor Makeup System in service and PLACE 1/1-MU, RCS RO MU MAN ACT in STOP.

+5 min US INITIATE a SMART Form per STA-421.

When the VCT level control is restored, or at Lead Examiner discretion, PROCEED to Event 4.

CPNPP March 2009 NRC Sim Scenario #2 Rev Final.doc

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 4 Page 9 of 17 Event

Description:

Pressurizer Pressure Channel Failure Time Position Applicants Actions or Behavior Booth Operator: When directed, EXECUTE Event 4.

- RX08A, Pressurizer Pressure Channel (1-PT-455) fails low.

Indications available:

5B-3.4 - PRZR 1 OF 4 PRESS LO 5B-4.4 - PRZR 1 OF 4 SI PRESS LO 5C-3.3 - PRZR PRESS LO BACKUP HTRS ON 5C-3.6 - CORE CLG MICROPROC TRN A SYS FAIL

+1 min RO RESPOND to Annunciator Alarm Procedures.

RO RECOGNIZE PRZR pressure rising with PRZR heaters ON.

DIRECT performance of ABN-705, Pressurizer Pressure Malfunction, US Section 2.0.

Examiner Note: The next three (3) steps are Initial Operator Actions.

RO VERIFY PORV closed.

RO PLACE 1-PK-455A, PRZR Master Pressure Control in MANUAL.

RO ADJUST 1-PK-455A for current RCS pressure.

TRANSFER to an alternate controlling channel, 1/1-PS-455F, PRZR Press RO Control Channel Select.

RO PLACE 1-PK-455A in AUTO.

RO VERIFY automatic control restoring pressurizer pressure to 2235 psig.

ENSURE a valid channel selected to recorder 1/1-PS-455G, 1-PR-455 PRZR RO Pressure Select.

CPNPP March 2009 NRC Sim Scenario #2 Rev Final.doc

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 4 Page 10 of 17 Event

Description:

Pressurizer Pressure Channel Failure Time Position Applicants Actions or Behavior Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, VERIFY PCIP window 2.6, PRZR PRESS SI BLK PERM P-11 US in required state for current pressure (DARK).

US/RO VERIFY other instruments on common instrument line - NORMAL.

+10 min US EVALUATE Technical Specifications.

• LCO 3.3.1.E, Reactor Trip System Instrumentation.

• CONDITION E - One channel INOPERABLE.

• ACTION E.1 - Place channel in trip within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

• LCO 3.3.2.D, ESFAS Instrumentation.

• CONDITION D - One channel INOPERABLE.

• ACTION D.1 - Place channel in trip within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

When Technical Specifications are addressed, or at Lead Examiner discretion, PROCEED to Event 5.

CPNPP March 2009 NRC Sim Scenario #2 Rev Final.doc

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 5 Page 11 of 17 Event

Description:

Tornado Warning Time Position Applicants Actions or Behavior Booth Operator: When directed, EXECUTE Event 5.

- CONTACT the Control Room as the Security Shift Supervisor and REPORT Tornado Warning in progress for Somervell County.

Indications available:

None

+1 min US DIRECT performance of ABN-907, Acts of Nature, Section 5.0.

Booth Operator: If asked, REPORT as Security that severe weather and lightning are on site.

DETERMINE severe weather in the vicinity of CPSES and consider US PLACING Source Range High Flux At Shutdown switches in BLOCK.

US DETERMINE PRA risk escalation required per Table 1.

US NOTIFY Work Control Center of severe weather condition.

US DETERMINE Tornado Warning in effect.

OPEN X-HS-5825D and X-HS-5828D, Control Room Makeup Air Supply BOP Dampers 17 and 20.

Booth Operator: If asked, REPORT that Standard Clearance #30 was not installed.

US DETERMINE Standard Clearance #30 NOT installed.

BOP PLACE Control Room HVAC in EMERGENCY RECIRC per Attachment 5.

PLACE X-HS-5877, EMER RECIRC MAN ACT in ACTUATE and VERIFY BOP the following:

• Train A X-HS-5831A, CR EMER PRZN FN 5 is RUNNING.

• Train A X-HS-5845, CR EMER FILT FN 23 and FILT IN DMPR 41 is OPEN.

• Train B X-HS-5834A, CR EMER PRZN FN 6 is RUNNING.

CPNPP March 2009 NRC Sim Scenario #2 Rev Final.doc

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 5 Page 12 of 17 Event

Description:

Tornado Warning Time Position Applicants Actions or Behavior

• Train B X-HS-5846, CR EMER FILT FN 24 and FILT IN DMPR 42 is OPEN.

• X-HS-5825A, CR MU AIR SPLY FN 37 is STOPPED and SUCT DMPR 16 is CLOSED.

• X-HS-5828A, CR MU AIR SPLY FN 38 is STOPPED and SUCT DMPR 19 is CLOSED.

• X-HS-5855, CR EXH FN 1 is STOPPED.

• X-HS-5856, CR EXH FN 2 is STOPPED.

• X-HS-5857, CR KTCHN and TOIL EXH FN 3 is STOPPED and SUCT DMPR 27 is CLOSED.

• X-HS-5858, CR KTCHN and TOIL EXH FN 4 is STOPPED and SUCT DMPR 28 is CLOSED.

• Train A X-HS-5847A, CR A/C FN 1 is RUNNING and SUCT DMPR 11 is OPEN.

• Train B X-HS-5848A, CR A/C FN 3 is RUNNING and SUCT DMPR 13 is OPEN.

PLACE Train A X-HS-5851A in START and VERIFY CR A/C FN 2 is BOP RUNNING and SUCT DMPR 10 is OPEN.

PLACE Train B X-HS-5853A in START and VERIFY CR A/C FN 4 is BOP RUNNING and SUCT DMPR 12 is OPEN.

US VERIFY missile shields installed as required.

+10 min US NOTIFY personnel via plant wide page.

When the plant personnel are notified, or at Lead Examiner discretion, PROCEED to Events 6 and 7.

CPNPP March 2009 NRC Sim Scenario #2 Rev Final.doc

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 6&7 Page 13 of 17 Event

Description:

Loss of All AC Power / EDG 1-01 Emergency/Normal Start Failure / EDG 1-02 Emergency Start Failure Time Position Applicants Actions or Behavior Booth Operator: When directed, EXECUTE Events 6 and 7.

- ED01, Loss of All AC Power.

- EG06A, Emergency Diesel Generator 1-01 fails to start.

- EG15B, Emergency Diesel Generator 1-02 fails to auto and emergency start; EDG starts upon Normal Start Switch activation.

Indications available:

Numerous Loss of All AC Power alarms

+30 secs RO/BOP DETERMINE Reactor Trip required and TRIP Reactor.

US DIRECT performance of EOP-0.0A, Reactor Trip or Safety Injection.

RO VERIFY Reactor Trip:

• DETERMINE Reactor trip breakers - NOT OPEN and INITIATE a manual Reactor trip.

• Neutron flux - DECREASING.

RO DETERMINE all control rod position rod bottom lights - OFF.

BOP VERIFY Turbine Trip:

• All HP turbine stop valves - CLOSED.

BOP VERIFY Power to AC Safeguards Buses:

• AC safeguards buses - NOT ENERGIZED.

US TRANSITION to ECA-0.0A, Loss of All AC Power, Step 1.

Examiner Note: The following steps are from ECA-0.0A, Loss of All AC Power.

RO VERIFY Reactor Trip:

• DETERMINE Reactor trip breakers - NOT OPEN and INITIATE a manual Reactor trip.

• Neutron flux - DECREASING.

CPNPP March 2009 NRC Sim Scenario #2 Rev Final.doc

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 6&7 Page 14 of 17 Event

Description:

Loss of All AC Power / EDG 1-01 Emergency/Normal Start Failure / EDG 1-02 Emergency Start Failure Time Position Applicants Actions or Behavior BOP VERIFY Turbine Trip:

• All HP turbine stop valves - CLOSED.

RO/US CHECK If RCS Is Isolated.

• PRZR PORVS - CLOSED.

• DETERMINE Letdown isolation valves - OPEN and manually CLOSE valves.

• Excess Letdown isolation valves - CLOSED.

BOP VERIFY AFW flow - GREATER THAN 460 GPM.

Examiner Note: Emergency Diesel Generator 1-02 will start when the Normal Start Switch is actuated.

BOP RESTORE Power to Any AC Safeguards Bus:

• ENERGIZE selected AC Safeguards Bus with Diesel Generator.

• PERFORM an Emergency Start on Diesel Generator 1-01.

• PERFORM a Normal Start on Diesel Generator 1-01.

• PERFORM an Emergency Start on Diesel Generator 1-02.

• PERFORM a Normal Start on Diesel Generator 1-02.

CRITICAL TASK Energize a Safeguards Bus prior to exiting ECA-0.0, Loss of All AC Power.

STATEMENT CRITICAL BOP START Diesel Generator 1-02 and VERIFY Safeguards Bus 1EA2 TASK energized.

BOP DETERMINE Diesel Generator 1 RUNNING.

• VERIFY Diesel Generator Safeguards Bus 1EA2 supply breaker closed.

US/BOP CHECK AC Safeguards Buses - AT LEAST ONE ENERGIZED.

RETURN to procedure and step in effect AND implement FRGs as US necessary.

CPNPP March 2009 NRC Sim Scenario #2 Rev Final.doc

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 6&7 Page 15 of 17 Event

Description:

Loss of All AC Power / EDG 1-01 Emergency/Normal Start Failure / EDG 1-02 Emergency Start Failure Time Position Applicants Actions or Behavior Examiner Note: The following steps are from EOP-0.0A, Reactor Trip or Safety Injection.

+15 min RO CHECK if SI is required.

• DETERMINE Steam Line Pressure greater than 610 psig.

• DETERMINE Pressurizer Pressure greater than 1820 psig.

• DETERMINE Containment Pressure less than 3 psig.

Examiner Note: The following CRITICAL TASK may not be performed if the RO/BOP observes all rods on the bottom prior to loss of DRPI. Emergency boration is performed per the Foldout Page of EOP-0.0A.

CRITICAL TASK Initiate emergency boration with loss of Digital Rod Position Indication per STATEMENT EOP-0.0A, Reactor Trip or Safety Injection Foldout Page.

CRITICAL TASK RO INITIATE emergency boration.

US TRANSITION to EOS-0.1A, Reactor Trip Response, Step 1.

Examiner Note: The following steps are from EOS-0.1A, Reactor Trip Response.

RO CHECK RCS Temperature -

• DETERMINE RCS average temperature < 557°F.

• STOP dumping steam.

• REDUCE AFW flow as necessary to minimize cooldown.

• MAINTAIN > 43% in at least one (1) Steam Generator.

BOP CHECK feedwater status:

• VERIFY reactor trip breakers - OPEN.

• CHECK RCS average temperature - LESS THAN 564°F.

• VERIFY feedwater isolation - ISOLATION COMPLETE.

CPNPP March 2009 NRC Sim Scenario #2 Rev Final.doc

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 6&7 Page 16 of 17 Event

Description:

Loss of All AC Power / EDG 1-01 Emergency/Normal Start Failure / EDG 1-02 Emergency Start Failure Time Position Applicants Actions or Behavior BOP VERIFY available AFW flow to SGs - GREATER THAN 460 GPM.

RO CHECK PRZR level - GREATER THAN 17%.

RO VERIFY Charging - IN SERVICE:

• ENSURE a charging pump is running.

• PLACE charging flow control valve in MANUAL and 35% demand.

• ENSURE CCP mini-flow valves 1/1-8110 and 1/1-8111 OPEN.

• ENSURE CCP alternate mini-flow valves 1/1-8511A and 1/1-8511B CLOSED.

• ENSURE charging line isolation valves 1/1-8105 and 1/1-8106 OPEN.

• ADJUST charging flow control valve to establish charging flow.

• ADJUST RCP seal flow to RCPs between 6 gpm and 13 gpm.

RO VERIFY Letdown - IN SERVICE:

• ANNOUNCE that Letdown is being established.

• ENSURE letdown orifice isolation valves are CLOSED.

• ENSURE 1-ALB-3B-1.16, Seal Water HX CCW Return Flow LO - DARK.

• ENSURE letdown containment isolation valves 1/1-8152 and 1/1-8160 -

OPEN.

• OPEN letdown isolation valves 1/1-LCV-459 and 1/1-LCV-460.

• PLACE letdown pressure controller in MANUAL and 30% demand.

• PLACE letdown temperature controller in MANUAL and 50% demand.

• ESTABLISH charging flow through regenerative heat exchanger and MAINTAIN seal flow to RCPs between 6 GPM and 13 GPM.

• OPEN desired letdown orifice valves.

• ADJUST letdown pressure control to obtain 310 psig and placed in AUTO.

• ADJUST letdown temperature control to obtain 95°F and place in AUTO.

• ALIGN CCP suction to the VCT.

• CONTROL charging and letdown to maintain level at 25%.

CPNPP March 2009 NRC Sim Scenario #2 Rev Final.doc

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 6&7 Page 17 of 17 Event

Description:

Loss of All AC Power / EDG 1-01 Emergency/Normal Start Failure / EDG 1-02 Emergency Start Failure Time Position Applicants Actions or Behavior RO CHECK PRZR pressure control:

• Pressurizer pressure - GREATER THAN 1820 PSIG.

• Pressurizer pressure - STABLE AT OR TRENDING TO 2235 PSIG.

BOP CHECK Steam Generator levels:

• Narrow range level - GREATER THAN 43%.

• Control feed flow to maintain narrow range level between 43% and 60%.

+20 min BOP VERIFY all AC buses - ENERGIZED BY OFFSITE POWER:

• ENSURE Train B Diesel Generator has assumed required loads.

• RESTORE offsite power per ABN-601, Response to a 138/345 KV System Malfunction or ABN-602, Response to a 6900/480 System Malfunction.

When Abnormal Procedure ABN-601 is referenced to restore power, TERMINATE the scenario.

CPNPP March 2009 NRC Sim Scenario #2 Rev Final.doc

UNIT: 1 UNIT SUPERVISOR RELIEF CHECKLIST (NRC Scenario #2)

PART I TO BE PREPARED BY THE OFF-GOING UNIT SUPERVISOR.

1.0 SHIFT ACTIVITIES:

1.1 Activities Completed This Shift:

1.2 Activities In-Progress: Plant startup per IPO-002A, Plant Startup from Hot Standby.

1.3 Planned Activities: Raise Reactor power using control rods to ~2% power.

Place Main Feedwater Pump in service when power level is stabilized and all MODE 1 LCOs are met.

2.0 PLANT AND EQUIPMENT STATUS:

2.1 Technical Specification Related Equipment Summary:

None 2.2 Non-Technical Specification Equipment Summary:

None 3.0 GENERAL INFORMATION:

Raise Reactor power using control rods to ~2% power per IPO-002A, Plant Startup from Hot Standby.

4.0 END OF SHIFT REVIEW:

LOGS - RO/BOP X LOGS-PEO X CLOSED eLCOARs ARCHIVED X OPTS COMPLETED X DAILY ACTIVITIES LIST X LCOARs REVIEWED X PART II TO BE COMPLETED BY THE ON-COMING UNIT SUPERVISOR.

1.0 CRITICAL PARAMETERS:

MODE: 2 REACTOR POWER: 1x10-8 MWE: 0 RCS CONTROL ROD TAVE: 557 °F POSITION 100 ON BANK D RCS Cb: 1545 ppm PRESS: 2235 psig X Protected Train - Train A X Unit 2 is in Mode 1 @ 100% power X Risk Assessment GREEN X BAT CB = 7447 ppm CPNPP March 2009 NRC Scenario #2 Shift Relief Checklist Rev .doc

CPNPP Mar 2009 RO & SRO Admin JPM A.1.a Answer Key SHUTDOWN MARGIN Unit 1 Cycle 14 MODE 3 Date 3/2/2009 Time 1500 A. PLANT CONDITIONS Figure 4.1 A.1 RCS Boron 593 ppm A.3 Burnup 18500 MWD/MTU of NDR

@ Date 3/2/2009 Time 1445 [ ] BOL [ ] MOL [X] EOL (485 - 10) A.2 Tave 485 O F A.4 No. of Stuck RCCAs 0 475 used in calculations A.5 COLR Shutdown Margin Requirement (From COLR or OPT-301) 1300 pcm Table 5.13 B.1 UNCORRECTED MIN BORON FOR SDM at A.2 and A.3 1171 +/- 10 ppm of NDR C. XENON AND SAMARIUM WORTH [ ] N/A C.1 Shutdown: Date 3/2/2009 Time 1200 Duration 3 hours C.2 [ ] Power [X] Power at Trip 100 %RTP Table 5.20 C.3 Xenon Worth (1) [X] NDR [ ] PC (-) 4505 +/- 10 pcm of NDR C.4 Samarium Worth [X] NDR [ ] PC (-) 1057 pcm Table 5.23 of NDR D. SHUTDOWN MARGIN BORON CONCENTRATION [ ] N/A D.1 IBW at B.1 Table 5.9 of NDR (-) 11415 +/- 50 pcm D.2 Most Reactive RCCA Worth Table 6.1 of NDR (+) 877 pcm D.3 Worth Correction [ C.3 + C.4 + (A.4

• D.2) ] (- ) 5562 +/- 10 pcm D.4 Boron Correction Factor at C.3 + C.4 Figure 5.35 of NDR 0.9275 +/- 0.005 D.5 IBW for Minimum SDM [ (D.1 - D.3) / D.4 ] (- ) 6307 +/- 10 pcm D.6 SDM Boron Concentration at D.5 and A.2 Table 5.9 of NDR 630 +/- 15 ppm E. SUBCRITICAL MARGIN [X] N/A E.1 IBW at A.1 and A.2 (-) N/A pcm E.2 Total Worth [(E.1

• D.4) + C.3 + C.4 + (A.4

• D.2)] ( ) N/A pcm E.3 Subcritical Margin (D.1 + A.5 - E.2) ( ) N/A pcm F. ACCEPTANCE CRITERIA SATISFIED INITIALS F.1 A.1 > B.1 AND A.4 = 0 YES NO OR A.1 > D.6 (1) When credit is taken for non-equilibrium xenon worth, Shutdown Margin should be recalculated every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. When credit is taken for equilibrium xenon or samarium worth following a reactor down-power, Shutdown Margin should be reverified on a reactor power increase.

Comments:

Performed By (CPE or RO): Date:

Reactor Operator Review: Date:

Unit Supervisor: Date:

Operations Management: Date:

OPT-301-9 Page 1 of 1 R-7 CPNPP Mar 2009 RO & SRO Admin JPM A.1.a Answer Key Rev d

CPNPP Mar 2009 RO & SRO Admin JPM A.1.a Handout SHUTDOWN MARGIN Unit Cycle MODE Date Time A. PLANT CONDITIONS A.1 RCS Boron ppm A.3 Burnup MWD/MTU

@ Date Time [ ] BOL [ ] MOL [ ] EOL O

A.2 Tave F A.4 No. of Stuck RCCAs A.5 COLR Shutdown Margin Requirement pcm B.1 UNCORRECTED MIN BORON FOR SDM at A.2 and A.3 ppm C. XENON AND SAMARIUM WORTH [ ] N/A C.1 Shutdown: Date Time Duration hours C.2 [ ] Power [ ] Power at Trip %RTP C.3 Xenon Worth (1) [ ] NDR [ ] PC (-) pcm C.4 Samarium Worth [ ] NDR [ ] PC (-) pcm D. SHUTDOWN MARGIN BORON CONCENTRATION [ ] N/A D.1 IBW at B.1 (-) pcm D.2 Most Reactive RCCA Worth (+) pcm D.3 Worth Correction [ C.3 + C.4 + (A.4

• D.2) ] ( ) pcm D.4 Boron Correction Factor at C.3 + C.4 D.5 IBW for Minimum SDM [ (D.1 - D.3) / D.4 ] ( ) pcm D.6 SDM Boron Concentration at D.5 and A.2 ppm E. SUBCRITICAL MARGIN [X] N/A E.1 IBW at A.1 and A.2 (-) N/A pcm E.2 Total Worth [(E.1

• D.4) + C.3 + C.4 + (A.4

• D.2)] ( ) N/A pcm E.3 Subcritical Margin (D.1 + A.5 - E.2) ( ) N/A pcm F. ACCEPTANCE CRITERIA SATISFIED INITIALS F.1 A.1 > B.1 AND A.4 = 0 YES NO OR A.1 > D.6 (1) When credit is taken for non-equilibrium xenon worth, Shutdown Margin should be recalculated every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. When credit is taken for equilibrium xenon or samarium worth following a reactor down-power, Shutdown Margin should be reverified on a reactor power increase.

Comments:

Performed By (CPE or RO): Date:

Reactor Operator Review: Date:

Unit Supervisor: Date:

Operations Management: Date:

OPT-301-9 Page 1 of 1 CPNPP Mar 2009 RO & SRO Admin JPM A.1.a Handout Rev d R-7

FOR TRAINING USE CPNPP ONLY Mar 2009 RO Admin NRC

- CPNPP JPM A.3JPM Handout 1 A.3 CPSES RADIATION WORK PERMIT RWP NUMBER TASK NUMBER REVISION BUILDING ELEVATION AREA 2009-1009 1 00 SG1 810 077A RWP TITLE SG #3 SAMPLE LINE REPAIR ACTIVITIES IN TASK TITLE OPERATIONS ACTIVITIES FOR ECO ROOM 1-077A WORK.

WORK DESCRIPTION WORK ACTIVITIES IN THE PIPE PEN ROOM INCLUDING VENTING OPERATIONS, OPERATIONS ACTIVITIES, AND RP SUPPORT MAX RADIATION LEVELS (mrem/hr) 180 @ CONTACT 80 @ 12" 32 GENERAL AREA CONTACT RP FOR CURRENT RADIOLOGICAL CONDITIONS!!

RWP CATEGORY/TYPE ROUTINE/PSE ALARMS (mR) ACCRUED ESTIMATE NON-OUTAGE / RWP ROUTINE DOSE: 20 DOSE(R): 0.000 DOSE(R): 0.50 RATE: 100 HOURS: 0 HOURS: 6 DOSIMETRY REQUIREMENTS JOB COVERAGE REQUIREMENTS Alarming Dosimeter START OF JOB TLD OSL Badge WORKER INSTRUCTIONS

• • • See attachment 1 for general RCA access requirements. ***

1) High Radiation Area entry requires an Area ALARA or Radiologically Significant ALARA briefing, .

2) Contact RP prior to entry into High Radiation area or contaminated areas

3) High Radiation Area entry requires radiation monitoring device which continuously indicates the radiation dose rate in the area, or Electronic Dosimeter or RP coverage.

4) Airborne Radioactivity Area entry is prohibited on this RWP.

5) ENTRY INTO THE RCA ON THIS RWP REQUIRES AUTHORIZATION ON THE ACCESS LIST.

PROTECTIVE CLOTHING REQUIREMENTS FOR CONTAMINATED AREAS Cloth Booties Cloth Coveralls Cloth Hood Glove Liners Rubber Gloves Rubber Overshoes COMMENTS THE FOLLOWING WORK ORDERS/ACTIVITIES HAVE BEEN PREVIEWED IN DETERMINING THE ESTIMATED EXPOSURE FOR THIS RWP. CONTACT THE ALARA GROUP @ X5377 IF YOUR W.O. IS NOT LISTED BELOW.

4-09-130129-00 THE FOLLOWING SURVEY(S) WERE USED TO ACTIVATE THIS RWP.

09-10-1057 PREPARED BY/DATE APPROVED BY/DATE D. GREENWOOD - 02/09/09 EXPIRATION DATE TERMINATED BY/DATE 05/31/09 STA-656-2 R-4 Page 1 of 1 CPNPP Mar 2009 RO Admin JPM A.3 Handout 1 Rev d

CPNPP Mar 2009 RO Admin JPM A.3 Handout 2 CANDIDATE WORKSHEET CPNPP Mar 2009 RO Admin JPM A.3 Handout 2 Rev d

CPNPP Mar 2009 RO Admin JPM A.3 Handout 3 AP B B

AP 1MS-159 CPNPP Mar 2009 RO Admin JPM A.3 Handout 3 Rev d