ML060310564

Final - Section B Operating Exam (Folder 3)

ML060310564
Person / Time
Site:	Susquehanna
Issue date:	12/11/2005
From:	Susquehanna
To:	Fish T H Operations Branch I
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Download: ML060310564 (162)

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PPL SUSQUEHANNA, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET SIR0 79.0P.006.102 0 9/28/05 223001 Al.10 3.413.6 ADDI. JPM Number Rev. No. Date NUREG 1123 WA No. WA Imp. .. To Sys. No. Task Title:

Startup The Containment Radiation Monitor System After Maintenance (CRM A) Completed By: Rich Chin Writer Approval : Nuclear Trng.

Supv. Date of Performance: JPM Performed By: Validated 9/28/05 Date I nstructorNV riter Date Date 15 Validation Time (Min.) Time Taken (Min.) Student Name: Last First M.I. Employee # / S.S. # Performance ( ) Satisfactory ( ) Unsatisfactory Evaluation:

Evaluator Name: Signature Typed or Printed Comments:

Form NTP-QA-31.8-1, Rev. 0, Page 1 of 2 2005 NRC Exam As Given REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE S/RO 79.0P.006.102

1. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.

6. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example: 1. Whenever any electrical panel is opened for inspection during JPM performance.

2. Whenever entering any plant area where specific safety equipment; such as hearing or eye protection, safety shoes, hardhats, etc; is required and/or posted as being necessary.

C. If in the judgement of the evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.

D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required.

II. REFERENCES OP-179-003, Containment Radiation Monitoring (Revision

5) 111. REACTIVITY MAN1 PULATIONS This JPM satisfies the requirements of Operational Activity(s):

NONE IV. TASK CONDITIONS A. CRM A was shutdown and isolated IAW OP-179-003 section 3.4, to support routine maintenance inspection checks.

B. Maintenance has completed their inspections.

C. CRM A is ready to be returned to service. D. No Containment Isolation signals are present. E. All prerequisites have been met. V. INITIATING CUE Startup CRM A from the control room IAW the appropriate operating procedure.

Use Pump 1 to start the monitor. VI. TASK STANDARD CRM A is sampling the Containment atmosphere.

VII. TASK SAFETY SIGNIFICANCE Provides a diverse means of detecting RCS leakage into the Containment atmosphere.

Form NTP-QA-31.8-1, Rev. 0, Page 2 of 2 2005 NRC Exam As Given 1 PERFORMANCE CHECKLIST Page 3 of 9 Appl. To/JPM No.: 79.0P.006.102 Action From any at power IC, shutdown and isolate CRM A IAW OP-179-003. Place the simulator in Freeze, and write an IC snap. Check "time" on CRM A screen display to verify it is current, the CRM has a separate processor and could be out of sync with simulator/real time.

IC-784 for LOC-27 NRC Exam Locates correct procedure.

References correct procedure section. Reviews prerequisites EVALUATOR CUE:

If necessary, Inform candidate that all prerequisites have been met. Reviews Precautions Open Supply and Return Primary Containment Isolation Valves at Containment Monitoring and Recording Panel 1 C693 RI 15799A. Place HS 1571 1 OAl CRM A Drywell Air Sample Inboard Supply & Return Isolation Valves Div I, SV 1571 OON102A in the OPEN position.

• Critical Step #Critical Sequence Student Name: Standard Obtains controlled copy of OP-179-003 Refers to section 3.1 Reviews prerequisites Reviews Precautions Places: HS 1571 10A1 CRM A Drywell Air Sample Inboard Supply & Return Isolation Valves C,J SV 1571 OON102A in the OPEN position.

Comments Form NTP-QA-31.8-2, Rev.

0, Page 1 of 1 2005 NRC Exam As Given Appl. To/JPM No.: 79.0P.006.102 PERFORMANCE CHECKLIST Action Observe red open indication for SV 1571 OOA. Observe red open indication for SV 1571 02A. Place HS 1571 1 OA2 CRM A Drywell Air Sample Inboard Supply & Return Isolation Valves Div II, SV 1571 01 N103A in the OPEN position.

Observe red open indication for SV 1571 01 A. *Critical Step #Critical Sequence Student Name: Standard Verifies:

SV 157100A Red Light - LIT Amber Light - NOT LIT Verifies:

SV 157102A Red Light - LIT Amber Light - NOT LIT Places: HS 1571 10A2 CRM A Drywell Air Sample Inboard Supply & Return Isolation Valves Div II, SV 1571 01 N103A in the OPEN position.

Verifies:

SV 1571 01 A Red Light - LIT Amber Light - NOT LIT I Page 4 of 9 Comments Form NTP-QA-31.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam As Given Appl. To/JPM No.: 79.0P.006.102 PERFORMANCE CHECKLIST Page 5 of 9 Step I Action 10 Observe red open indication for SV 1571 03A. NOTE: CRMS may be operated locally or from the Control Room as determined by Shift Supervision.

• Critical Step #Critical Sequence Student Name: Standard Verifies:

SV 157103A Red Light - LIT Amber Light - NOT LIT Based on initiating cue: Refers to section 3.1.5 Eva1 Comments Form NTP-OA-31.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam As Given Appl. To/JPM No.: 79.0P.006.102 - Step 11 12 13 14 PERFORMANCE CHECKLIST Page 6 of 9 Action To Place Containment Radiation Monitor A in service from CONTAINMENT MONITORING AND RECORDING PANEL 1 C693 RI 15799A: Observe CRM A Air Sample Rad Monitor CRT parameters:

Correct approximate time. "OFF" OR "IS0 Control Status Blocks lit. "LO Temp" Alarm Block NOT lit. "LO Flow" Alarm Block lit. "LLO Flow" Alarm Block lit. "LO Filter Delta PI' Alarm Block lit.

Press ACK to acknowledge local alarms. Confirm CONTAINMENT MONITORING AND RECORDING PANEL 1 C693, Annunciator A02 "CONTN RAD DET SYSTEM A TROUBLE" lit.

IF CRM A is isolated (i.e., IS0 status block lit), the CRM pumps will not start until this status is cleared. *Critical Step #Critical Sequence Student Name: Standard Verifies the following status of CRM A Air Sample Rad Monitor CRT:

Correct approximate time. "IS0 Control Status Blocks LIT. "LO Temp" Alarm Block NOT LIT. "LO Flow" Alarm Block LIT. "LLO Flow" Alarm Block LIT. "LO Filter Delta P" Alarm Block LIT. Presses ACK pushbutton on CRM A keypad Verifies the following alarm window is LIT: CONTAINMENT MONITORING AND RECORDING PANEL 1 C693, Annunciator A02 "CONTN RAD DET SYSTEM A TROUBLE".

Verifies: "ISO" Status Block is LIT Eva1 - Comments Form NTP-QA-31.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam As Given Appl. To/JPM No.: 79.0P.006.102 PERFORMANCE CHECKLIST Page 7 of 9 Action IF CRM "ISO" (isolate) lit, UNISOLATE system as follows: Press #O on CRM A on CRM A keypad. Observe screen change.

Press #1 "System Controls." Press #6 "lsolate/Off" on CRM A keypad. Observe "ISO" status block clear. Press #O on CRM A keypad. Ensure CRM A heat trace to reach operating temperature of approximately 135°F. *Critical Step #Critical Sequence Student Name: Standard Verifies: "ISO" Status Block is LIT Presses 0 on CRM A on CRM A keypad. Verifies screen changes Presses 1 on CRM A on CRM A keypad. Presses 6 on CRM A on CRM A keypad Verifies "ISO" status block clears.

Presses 0 on CRM A on CRM A keypad Contacts NPO to verify CRM A heat trace to reach operating temperature of approximately 135°F. Comments Form NTP-QA-31.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam As Given Appl. To/JPM No.: 79.0P.006.102 PERFORMANCE CHECKLIST Page 8 of 9 Action EVALUATOR CUE:

Role-play NPO and Acknowledge the request, and report that you will ensure that the heat tracing reaches 135°F. Press #O on CRM A keypad. Press #1 "System Controls" on CRM A keypad. Observe screen change.

NOTE: It may be necessary to repeat steps 3.1.5 f. and g. several times in order to clear the LLO Flow alarm block.

If the pump will not remain running after three attempts, contact I&C (or alternatively Chemistry) for assistance.

Start CRM Pump 1 P262A1 or 1 P262A2 by:

Press #O on CRM A keypad. *Critical Step #Critical Sequence Student Name: Standard Presses 0 on CRM A on CRM A keypad Presses 1 on CRM A on CRM A keypad Verifies screen changes Presses 0 on CRM A on CRM A keypad Verifies small block next to pump 1 is LIT. - Eva1 Comments Form NTP-QA-31.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam As Given Appl. To/JPM No.: 79.0P.006.102 PERFORMANCE CHECKLIST Page 9 of 9 Student Name: This completes the JPM *Critical Step #Critical Sequence Form NTP-QA-31 .a-2, Rev. 0, Page 1 of 1 2005 NRC Exam As Given TASK CONDITIONS A. CRM A was shutdown and isolated IAW OP-179-003 section 3.4, to support routine maintenance inspection checks. B. Maintenance has completed their inspections.

C. CRM A is ready to be returned to service. D. No Containment Isolation signals are present.

E. All prerequisites have been met. INITIATING CUE Startup CRM A from the control room IAW the appropriate operating procedure. Use Pump 1 to start the monitor. 2005 NRC Exam As Given 1 of2 TASK CONDITIONS A. CRM A was shutdown and isolated IAW OP-179-003 section 3.4, to support routine maintenance inspection checks. 6. Maintenance has completed their inspections.

C. CRM A is ready to be returned to service. D. No Containment Isolation signals are present.

E. All prerequisites have been met. INITIATING CUE Startup CRM A from the control room IAW the appropriate operating procedure. Use Pump 1 to start the monitor. 2005 NRC Exam As Given 2 of 2 PPL SUSQUEHANNA, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET SIR0 00.ON.015.104 0 09/28/05 29501 6 AA1.07 4.014.0 APPl. JPM Number Rev. No. Date NUREG 1123 WA No. WA Imp. To Sys. No. Task Title: Completed By: Establish and Maintain Reactor Pressure With SRVs from the RSDP IAW ON-100-009 Rich Chin Writer Approval:

Nuclear Trng. Supv. Date of Performance:

JPM Performed By: Validated 09/28/05 Date InstructorNVriter Date Date 20 Validation Time (Min.) Time Taken (Min.) Student Name: Last First M.I. Employee #I S.S. # Performance ( ) Satisfactory ( ) Unsatisfactory Evaluation:

Evaluator Name: Signature Typed or Printed Comments:

Form NTP-QA-3 1.8-1, Rev. 0, Page 1 of 2 2005 NRC Exam As Given REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE S/RO 00.ON.015.104

1. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.

B. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example: 1. Whenever any electrical panel is opened for inspection during JPM performance.

2. Whenever entering any plant area where specific safety equipment; such as hearing or eye protection, safety shoes, hardhats, etc; is required and/or posted as being necessary.

C. If in the judgment of the evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.

D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required.

II. REFERENCES A. ON-100-009, Control Room Evacuation (Rev. 11) 111. RE ACTIVITY MAN1 PU LATIONS This JPM satisfies the requirements of Operational Activity(s):

None IV. TASK CONDITIONS A. A Hazardous GAS condition exists in the control room requiring abandonment of the Control Room. B. ON-100-009, Control Room Evacuation has been completed through step 4.2. C. Reactor vessel water level is being maintained by RCIC. D. Reactor pressure is being maintained by SRVs cycling. V. INITIATING CUE Transfer control to the RSDP and commence a RCS cooldown NOT TO EXCEED 1 OO°F/Hr with SRVs from the Remote Shutdown Panel beginning at step 4.3 of ON-100-009, Control Room Evacuation.

VI. TASK STANDARD Control transferred to the RSDP and a RCS cooldown 5 1 OO"F/Hr is commenced.

VILTASK SAFETY SIGNIFICANCE Ability to cooldown the RPV at less than Tech Spec maximum allowed rate; provide control power to critical plant equipment at the RSDP. Form NTP-QA-3 I .8- 1, Rev. 0, Page 2 of 2 2005 NRC Exam As Given

! Appl. To/JPM No.: S/RO 00.ON.015.104 - Step PERFORMANCE CHECKLIST Page 3 of 26 ~~ Action - EVALUATOR NOTE: Establish task conditions as directed on attached setup instructions.

IC-20 Place Mode SW to S/D S/D CRD pump to avoid 54" level and excessive vessel C/D Place IRMs to range 1 Perform ON-100-009 up to step 4.2 Snap into an IC for the JPM Prepare a signed-off copy of ON-100-009, Control Room Evacuation up through step 4.2 When student is ready to begin JPM, place the simulator in RUN. EVALUATOR CUE: Provide candidate with a signed-off copy of ON-lOO- 009, Control Room Evacuation up through step 4.2. EVALUATOR NOTE: Student may review previous sections of procedure.

• Critical Step #Critical Sequence Student Name: Standard Eva1 ~ ~~~ Comments Form NTP-QA-3 1.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam As Given PERFORMANCE CHECKLIST Page 4 of 26 Appl. To/JPM No.: S/RO 00.ON.015.104 - Step 1 2 3 Action Candidate refers to appropriate procedural section. Upon arrival at Remote Shutdown Panel, Perform following to determine plant status and gain control of critical systems: NOTE: Since the laptop is for monitoring purposes only, this should not impact completing the following steps to gain control of the plant. As time and manpower allows, Connect the PlCSY laptop per Attachment E. EVALUATOR CUE:

Inform the candidate that the STA will commence Connecting the PlCSY laptop per Attachment E. NOTE: Attachment D contains lists of all functions performed by placing transfer switches to EMERG position.

• Critical Step #Critical Seq uence Student Name: Standard Candidate refers to ON-1 00-009, Control Room Evacuation step

4.3. Requests

STA to begin Connecting the PlCSY laptop per Attachment E. Eva1 - Comments Form NTP-QA-3 1.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam As Given PERFORMANCE CHECKLIST Page 5 of 26 Appl. To/JPM No.:

S/RO 00.ON.015.104 Step *4 *5 Transfer control to Remote Shutdown Panel as follows, Observe Green Light ILLUMINATES for each transfer switch when placed in EMERG position:

Place HSS-14901 A INSTR TRANSFER SWITCH A INSTR SET 1 , 2 in EMERG position (located near the top center of the panel). Place HSS-1511 OA INSTR TRANSFER SWITCH B INSTR SET 3,4 in EMERG position (located near the top right of the panel). *Critical Step #Critical Sequence Student Name: Standard Places: SET 1 , 2 in EMERG position HSS-14901A INSTR TRANSFER SWITCH A INSTR Verifies:

Green Light - LIT Red Light - NOT LIT Places: SET 3, 4 in EMERG position HSS-1511 OA INSTR TRANSFER SWITCH B INSTR Verifies:

Green Light - LIT Red Light - NOT LIT - Eva1 Comments Form NTP-QA-3 1.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam As Given Appl. To/JPM No.: S/RO 00.ON.015.104 PERFORMANCE CHECKLIST Page 6 of 26 Action Transfer HSS-14902A CONTROL TRANSFER SWITCH A as follows: Ensure 1 P-220 BAROMETRIC CDSR COND PUMP aligned to AUTO. Place HSS-14902A CONTROL TRANSFER SWITCH A in EMERG position.

• Critical Step #Critical Sequence Student Name:

-.Is Standard Verifies: 1 P-220 BAROMETRIC CDSR COND PUMP Control switch in AUTO. THEN Places: HSS-14902A CONTROL TRANSFER SWITCH A in EMERG position Verifies:

Green Light - LIT Red Light - NOT LIT Eva1 Comments Form NTP-QA-3 1.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam As Given Appl. To/JPM No.:

S/RO 00.ON.015.104 Step *7 PERFORMANCE CHECKLIST Page 7 of 26 Action Transfer HSS-14902B CONTROL TRANSFER SWITCH M as follows: Ensure HV-149-F059 TURB EXH TO SUPP POOL aligned to OPEN. Ensure 1 P-219 BAROMETRIC VACUUM PUMP aligned to STOP. Place HSS-149028 CONTROL TRANSFER SWITCH M in EMERG position.

• Critical Step #Critical Sequence Student Name: Standard Verifies:

HV-149-FO59 TURB EXH TO SUPP POOL in OPEN. 1 P-219 BAROMETRIC VACUUM PUMP Control switch in STOP. THEN Places: HSS-149028 CONTROL TRANSFER SWITCH M in EMERG position Verifies:

Green Light - LIT Red Light - NOT LIT - Eva1 Comments Form NTP-QA-31.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam As Given PERFORMANCE CHECKLIST Page 8 of 26 Appl. To/JPM No.: S/RO 00.ON.015.104 - Step +a *9 Action Transfer HSS-14903A CONTROL TRANSFER SWITCH B as follows: Ensure HV-149-F060 VAC PP DSCH TO SUPP POOL aligned to OPEN. Place HSS-14903A CONTROL TRANSFER SWITCH B in EMERG position. Place HSS-149038 CONTROL TRANSFER SWITCH N in EMERG position.

• Critical Step #Critical Sequence Student Name: Standard Verifies:

HV-149-F060 VAC PP DSCH TO SUPP POOL in OPEN. THEN Places: HSS-14903A CONTROL TRANSFER SWITCH B in EMERG position Verifies: Green Light - LIT Red Light - NOT LIT Places: HSS-149038 CONTROL TRANSFER SWITCH N in EMERG position Verifies: Green Light - LIT Red Light - NOT LIT Comments Form NTP-QA-3 1.8-2, Rev. 0. Page 1 of 1 2005 NRC Exam As Given PERFORMANCE CHECKLIST Page 9 of 26 Appl. To/JPM No.: S/RO 00.ON.015.104 Student Name:

Action Place HSS-14904A CONTROL TRANSFER SWITCH C in EMERG position.

Place HSS-14905A CONTROL TRANSFER SWITCH D in EMERG position. *Critical Step

1. Critical Sequence Standard Places: HSS-14904A CONTROL TRANSFER SWITCH C in EMERG position Verifies: Green Light - LIT Red Light - NOT LIT Places: HSS-14905A CONTROL TRANSFER SWITCH D in EMERG position Verifies: Green Light - LIT Red Light - NOT LIT Eva1 Comments Form NTP-QA-31.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam As Given PERFORMANCE CHECKLIST Page 10 of 26 Appl. To/JPM No.: S/RO 00.ON.015.104 Student Name: Action Transfer HSS-15111 B CONTROL TRANSFER SWITCH R as follows: Ensure SV-12651 INSTR GAS TO CONTN IS0 aligned to OPEN. Place HSS-15111 B CONTROL TRANSFER SWITCH R in EMERG position. Place HSS-1 51 12A CONTROL TRANSFER SWITCH F in EMERG position.

• Critical Step #Critical Sequence Standard Verifies:

SV-12651 INSTR GAS TO CONTN IS0 in OPEN. THEN Places: HSS-15111 B CONTROL TRANSFER SWITCH R in EMERG position Verifies: Green Light - LIT Red Light - NOT LIT Places: HSS-15112A CONTROL TRANSFER SWITCH F in EMERG position Verifies:

Green Light - LIT Red Light - NOT LIT - Eva1 Comments Form NTP-QA-3 1.8-2, Rev. 0. Page 1 of I 2005 NRC Exam As Given PERFORMANCE CHECKLIST Page 11 of 26 Appl. To/JPM No.: S/RO 00.ON.015.104 Student Name: - Step Action Place HSS-15112B CONTROL TRANSFER SWITCH S in EMERG position. Place HSS-15113A CONTROL TRANSFER SWITCH G in EMERG position.

Transfer HSS-151138 CONTROL TRANSFER SWITCH T as follows: Ensure HV-151 -F006B SHUTDOWN CLG SUCT aligned to CLOSE. *Critical Step #Critical Sequence Standard Places: HSS-15112B CONTROL TRANSFER SWITCH S in EMERG position Verifies:

Green Light - LIT Red Light - NOT LIT Places: HSS-15113A CONTROL TRANSFER SWITCH G in EMERG position Verifies:

Green Light - LIT Red Light - NOT LIT Verifies:

HV-1 51 -F006B SHUTDOWN CLG SUCT in CLOSE. - Eva1 Comments Form NTP-QA-31.8-2, Rev. 0, Page I of 1 2005 NRC Exam As Given Appl. To/JPM No.: S/RO 00.ON.015.104 PERFORMANCE CHECKLIST Page 12 of 26 ~ Action NOTE: Indication for HV-151 -FO1 OB RHR LOOP B CROSSTIE will not illuminate due to supply breaker being open. Ensure HV-151-FOlOB RHR LOOP B CROSSTIE aligned to CLOSE. Place HSS-151136 CONTROL TRANSFER SWITCH T in EMERG position.

• Critical Step Student Name: ~ ~~~ Standard Verifies:

HV-151-FOlOB RHR LOOP B CROSSTIE in CLOSE. THEN Places: HSS-151138 CONTROL TRANSFER SWITCH T in EMERG position Verifies: Green Light - LIT Red Light - NOT LIT Verifies:

1. Critical Sequence - Eva1 Comments Form NTP-QA-31.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam As Given PERFORMANCE CHECKLIST Page 13 of 26 Appl. To/JPM No.: S/RO 00.ON.015.104 Student Name: - Step *18 *19 Action Transfer HSS-15114A CONTROL TRANSFER SWITCH H as follows: Ensure HV-151 -F004B RHR PUMP B SUCT aligned to OPEN. Place HSS-15114A CONTROL TRANSFER SWITCH H in EMERG position. Transfer HSS-151148 CONTROL TRANSFER SWITCH U as follows: Ensure SV-12605 INSTR GAS CMP OB SUCT IS0 aligned to OPEN. Place HSS-15114B CONTROL TRANSFER SWITCH U in EMERG position.

Standard Verifies:

HV-151-FO04B RHR PUMP B SUCT in OPEN. THEN Places: HSS-15114A CONTROL TRANSFER SWITCH H in EMERG position Verifies:

Green Light - LIT Red Light - NOT LIT Verifies:

SV-12605 INSTR GAS CMP OB SUCT IS0 in OPEN. THEN Places: HSS-151148 CONTROL TRANSFER SWITCH U in EMERG position Verifies:

Green Light - LIT Red Light - NOT LIT Eva1 Comments *Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0, Page I of 1 2005 NRC Exam As Given 1 PERFORMANCE CHECKLIST Page 14 of 26 Appl. To/JPM No.: S/RO 00.ON.015.104 Student Name: Step

• 20 *21 ~ Action Place HSS-15115A CONTROL TRANSFER SWITCH J in EMERG position.

Transfer HSS-15115B CONTROL TRANSFER SWITCH V as follows: Ensure HV-151 -F047B HX B SHELL SIDE INLET aligned to OPEN. Place HSS-15115B CONTROL TRANSFER SWITCH V in EMERG position.

• Critical Step #Critical Sequence Standard Places: HSS-15115A CONTROL TRANSFER SWITCH J in EMERG position Verifies: Green Light - LIT Red Light - NOT LIT Verifies: HV-151 -F047B HX B SHELL SIDE INLET in OPEN. THEN Places: HSS-15115B CONTROL TRANSFER SWITCH V in EMERG position Verifies: Green Light - LIT Red Light - NOT LIT Eva1 Comments Form NTP-QA-31.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam As Given PERFORMANCE CHECKLIST Page 15 of 26 Appl. To/JPM No.: S/RO 00.ON.015.104 Step

• 22

• 23 Action Transfer HSS-15116A CONTROL TRANSFER SWITCH K as follows:

Ensure HV-151 -F003B HX B SHELL SIDE OUTLET aligned to OPEN. Place HSS-15116A CONTROL TRANSFER SWITCH K in EMERG position.

Place HSS-151166 CONTROL TRANSFER SWITCH W in EMERG position.

• Critical Step #Critical Sequence Student Name: Standard Verifies:

HV-151-FO03B HX 6 SHELL SIDE OUTLET in OPEN. THEN Places: HSS-15116A CONTROL TRANSFER SWITCH K in EMERG position Verifies: Green Light - LIT Red Light - NOT LIT Places: HSS-15116B CONTROL TRANSFER SWITCH W in EMERG position Verifies:

Green Light - LIT Red Light - NOT LIT Eva1 - Comments Form NTP-QA-3 1.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam As Given

/ , PERFORMANCE CHECKLIST Page 16 of 26 Appl. To/JPM No.: S/RO 00.ON.015.104 Step

• 24 I25 26 Action Place HSS-15117A CONTROL TRANSFER SWITCH L in EMERG position.

Place HSS-151178 CONTROL TRANSFER SWITCH X in EMERG position. Ensure Main Steam Lines ISOLATED by EITHER: Observing IB MSIV's indicate CLOSED. LOCALLY Observing OB MSIV's CLOSED. *Critical Step #Critical Sequence Student Name: Standard Places: HSS-15117A CONTROL TRANSFER SWITCH L in EMERG position Verifies: Green Light - LIT Red Light - NOT LIT Places: HSS-151176 CONTROL TRANSFER SWITCH X in EMERG position Verifies:

Green Light - LIT Red Light - NOT LIT Verifies:

Main Steam Line IB IS0 VLVS A, B, C, and D Amber CLOSED Lights - LIT Red OPEN Lights - NOT LIT Eva1 Comments Form NTP-QA-31.8-2.

Rev. 0, Page 1 of 1 2005 NRC Exam As Given PERFORMANCE CHECKLIST Appl. To/JPM No.: S/RO 00.ON.015.104 - Step 27 - Action Monitor available parameters to determine plant status. NOTE : If PlCSY computer available all information that was available in the control room via computer displays will be available at the Remote Shutdown Panel using the PlCSY laptop computer.

NOTE : If PlCSY computer is not available, the following step is not necessary for control of the plant, but will make the control by the operators smoother. EVALUATOR CUE:

Inform the candidate that the PlCSY computer is not ye available, the STA is still in the process of connecting and starting-up the laptop computer.

• Critical Step #Critical Sequence Page 17 of 26 Student Name: Standard - Eva1 ~ Comments Form NTP-QA-3 1.8-2. Rev. 0, Page 1 Of 1 2005 NRC Exam As Given 1 PERFORMANCE CHECKLIST Appl. To/JPM No.: S/RO 00.ON.015.104 Action IF PlCSY is not available Notify I&C to install: Temporary Shutdown level indication in accordance with IC-180-004, LT-621-1 NO27 Reactor Range Level Measurement at Rack 1 COO5 Temporary reactor coolant temperature indication in accordance with IC-149-005, Installation and Removal of Temporary RTD Readers for Local Monitoring of RHR Heat Exchanger B Inlet (TE-Ell-1 N004B) and Outlet (TE-E1 1-1 N027B)Temperatures. EVALUATOR CUE:

If candidate elects to have I & C begin installing, Role- play I&C and acknowledge the request, and inform candidate to continue with the procedure.

IF PlCSY is not available and the Control Room was evacuated prior to scramming the reactor, Ensure the reactor scrammed by locally Observing the positions of the scram valves on a few HCUs. (The scram valve indication should be open (up) for both inlet and exhaust valves.) Page 18 of 26 Student Name: Standard Determines N/A since PlCYS was available.

Based on initial conditions, determines this to be N/A. - Eva1 Comments *Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0, Page 1 of I 2005 NRC Exam As Given PERFORMANCE CHECKLIST Page 19 of 26 Appl. To/JPM No.: S/RO 00.ON.015.104 Student Name: Step 30 - Action NOTE: Transferring HSS-14454 CONTROL TRANSFER SWITCH Y to EMERG will cause RWCU OB IS0 HV-144-FO04 to close. Opening Breaker 18 in 1 Y219 will de-energize SV-14433 closing HV-144FO33.

EVALUATOR NOTE: Since there was no indication of RWCU piping leak OR indication of flow being diverted to condenser or Radwaste through RWCU in the initial conditions, the candidate may not contact the NPO to perform the check in the next step.

IF there is indication of RWCU piping leak OR indication of flow being diverted to condenser or Radwaste through RWCU, Perform the following: Place HSS-14454 CONTROL TRANSFER SWITCH Y to EMERG (located near the top of the panel)

Observe Green Light ILLUMINATED. Open Breaker 1 Y219-018 (Area 29/71 9'). AND EVALUATOR CUE: If necessary, Role-play NPO and inform candidate that there is NO indication of RWCU piping leak OR indication of flow being diverted to condenser or Radwaste through RWCU

• Critical Step #Critical Sequence Standard May Contact NPO and request checks for: Indication of RWCU piping leak OR indication of flow being diverted to condenser or Radwaste through RWCU Eva1 Comments Form NTP-QA-3 1.8-2, Rev. 0. Page 1 of 1 2005 NRC Exam As Given I I I PERFORMANCE CHECKLIST Page 20 of 26 Appl. To/JPM No.: S/RO 00.ON.015.104 Student Name: Action IF Control Room evacuation was because of fire: Verify that the following Control Structure HVAC Systems are operating:

a. b. c. Control Structure H&V System d. Battery Room Exhaust System IF one or more of the above systems are found inoperable, Enter ON 030 001, Loss of Control Structure HVAC within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />. Perform DC OP 001, Post Fire Recovery Actions within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. Computer Room Floor Cooling System Control Room Floor Cooling System CAUTION RHR Pump 1 P202A may spuriously start preventing Unit 2 from running RHR Pump 2P202A when required.

IF RHR Pump 1 P202A must be tripped, Perform the following at 1 A201 02: Place Lateral Control Switch to HANDLE OUT position. Place Lateral Control Switch to OPEN. *Critical Step #Critical Sequence Standard Determines N/A Determines N/A Comments Form NTP-QA-3 1.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam As Given Appl. To/JPM No.: S/RO 00.ON.015.104 - Step 33 34 PERFORMANCE CHECKLIST Page 21 of 26 Action IF Suppression Pool Level drops below 22 feet, WITHIN 10 HOURS: Ensure no systems are in operation that could cause the decrease.

Ensure no other condition(s) exist that could cause the decrease.

Locally Close manual valve 157025 (Area 27/645').

IF the fire has caused hot shorts that have resulted in damage to MOVs required for the operation of RCIC, RHR Suppression Pool Cooling or RHR Shutdown Cooling from the Remote Shutdown Panel, Depressurize the RPV using the available SRVs and Use RHWLPCI in the alternate shutdown cooling mode in accordance with ON-149-001.

• Critical Step #Critical Sequence Student Name: Standard ~~ ~ Determines N/A Determines N/A Eva1 Comments Form NTP-QA-31.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam As Given Appl. To/JPM No.: S/RO 00.ON.015.104 - Step PERFORMANCE CHECKLIST Page 22 of 26 Action CAUTION Fires in the Control Room could cause an inadvertent and uncontrolled RPV injection from either Condensate, Core Spray, or the RHR Division not installed on the RSP. The SRV discharge piping has been analyzed for the loading conditions that will result from this condition.

To minimize the loads on the SRV discharge piping, assure that an SRV is open as RPV pressure is being reduced and the RPV pressure approaches the shutoff head for each of these systems (Condensate approximately 600 psig; Core Spray and RHR approximately 300 psig). Should Condensate begin to inject, monitor RPV level to assure that the fire has not damaged the FW LO LOAD controller prior to closing the SRV. NOTE: Relief mode of SRV's A, B, and C will not auto initiate when applicable Control Transfer Switches are in EMERG position, however, safety function is always operable.

Also when SRV Transfer Switches are in EMERG spurious auto actuation is prevented due to a Control Room fire. *Critical Step #Critical Sequence Student Name: Standard Eva1 ~ Com men ts Form NTP-QA-3 1.8-2, Rev. 0. Page I of 1 2005 NRC Exam As Given Appl. To/JPM No.: S/RO 00.ON.015.104 Step 35 36 PERFORMANCE CHECKLIST Page 23 of 26 Action To control reactor pressure Perform the following: Ensure following valves OPEN: SV-12651 INSTR GAS TO CONTN ISO. SV-12605 INSTR GAS CMP OB SUCT ISO. CAUTION Level 1 (-129")

or high drywell pressure (1.72 psig) LOCA Isolation Signal is defeated for CIG valves when controlled from the remote shutdown panel. NOTE: Placing HSS-15114B Transfer Switch U in EMERG causes lnstr Gas CMP OB suction to cycle possibly tripping CIG compressors on low suction pressure.

IF CIG Compressors tripped, Reset as follows at 1 C239 (Area 25/71 9'): Depress Logic Reset push button. Ensure CIG Compressor STARTS.

• Critical Step #Critical Sequence Student Name: Standard Verifies:

SV-12651 INSTR GAS TO CONTN ISO. SV-12605 INSTR GAS CMP OB SUCT ISO. Amber Lights - NOT LIT Red Lights - LIT Contacts NPO and requests NPO to determine the status of the CIG Compressors Eva1 Comments Form NTP-QA-31.8-2, Rev. 0, Page I of I 2005 NRC Exam As Given Appl. To/JPM No.: S/RO 00.ON.015.104 Step

• 37 Page 24 of 26 PERFORMANCE CHECKLIST Action EVALUATOR CUE:

Role-play NPO and inform candidate that the CIG Compressors are running. CAUTION If RPV pressure drops below 650 psig, condensate pumps will inject when RPV level < +35 inches. CAUTION Wide range level indication becomes less accurate as RPV pressure decreases. EVALUATOR NOTE:

It may be necessary for the candidate to perform several OPEN/CLOSE sequences on the SRVs to obtain the required cooldown rate. Operate SRV's as follows: Open SRV's A, 6, and C as needed. *Critical Step #Critical Sequence Student Name: Standard Places: Safety Relief Valve PSV-141 -FO13A, 6, or C control switch to OPEN Verifies: Reactor Vessel Pressure PI-1 4262 Dropping - Eva1 Corn men ts Form NTP-QA-3 1.8-2. Rev. 0, Page 1 of 1 2005 NRC Exam As Given Appl. To/JPM No.: S/RO 00.ON.015.104 - Step 30

• 39 PERFORMANCE CHECKLIST Page 25 of 26 Action NOTE: Keys to operate SRV's are located in sealed Pink sound powered phone storage box, labeled "JP1207, JP1402, JP2201 ,'I inside the Remote Shutdown Panel Room. IF pneumatic supply to SRV's A, B, and C not available, Operate SRV's G, J, K, L, M, or N (ADS valves) individually from upper (lower) relay room Panel 1 C628 (1 C631) using Keylock switches.

EVALUATOR NOTE: Pay close attention to the actual RPV pressure in the next step. This pressure will be used to determine if the candidate has violated the Tech Spec RCS cooldown rate. Refer to Attachment A for RPV Pressurenemperature Correlation.

• Critical Step #Critical Sequence Student Name: Standard Determines N/A Refers to Attachment A and Determines the lowest RPV pressure necessary to achieve the less than 1 OO°F/Hr cooldown - Eva1 Comments Form NTP-QA-31.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam As Given Appl. To/JPM No.: S/RO 00.ON.015.104 - Step

• 40 PERFORMANCE CHECKLIST Page 26 of 26 ~~~ Action Plot cooldown in accordance with Attachment A and B. EVALUATOR CUE: This completes the JPM *Critical Step #Critical Sequence Student Name: Standard Refers to Attachment A and B 0 Observes Reactor Vessel Pressure PI-1 4262 Using Attachment A Determines RCS temperature Plots this temperature on Attachment B 0 Verifies cooldown rate is within 1 OO"F/Hr limit Comments Form NTP-QA-31.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam As Given TASK CONDITIONS A. A Hazardous GAS condition exists in the control room requiring abandonment of the Control Room. B. ON-100-009, Control Room Evacuation has been completed through step 4.2. C. Reactor vessel water level is being maintained by RCIC. D. Reactor pressure is being maintained by SRVs cycling. INITIATING CUE Transfer control to the RSDP and commence a RCS cooldown NOT TO EXCEED 1 OO"F/Hr with SRVs from the Remote Shutdown Panel beginning at step 4.3 of ON-100-009, Control Room Evacuation.

2005 NRC Exam As Given Page 1 of 2 TASK CONDITIONS A. A Hazardous GAS condition exists in the control room requiring abandonment of the Control Room. 6. ON-100-009, Control Room Evacuation has been completed through step 4.2. C. Reactor vessel water level is being maintained by RCIC. D. Reactor pressure is being maintained by SRVs cycling. INITIATING CUE Transfer control to the RSDP and commence a RCS cooldown NOT TO EXCEED 10O0F/Hr with SRVs from the Remote Shutdown Panel beginning at step 4.3 of ON-100-009, Control Room Evacuation.

2005 NRC Exam As Given Page 2 of 2 PPL SUSQUEHANNA, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET SIR0 98.G0.001.151 0 0912 8/05 262001 A4.04 3.613.7 APPl. JPM Number Rev. No. Date NUREG 1123 WA No. WA Imp. To Sys. No. Task Title: Completed By: Validated Synchronize the Main Generator Rich Chin 0912 8/05 Writer Date InstructorNVriter Date Approval:

Nuclear Trng. Supv. Date of Performance:

Date 25 Validation Time (Min.) Time Taken (Min.) JPM Performed By: Student Name: Last First M.I. Employee # I S.S. ## Performance ( ) Satisfactory ( ) Unsatisfactory Eva1 uation: Evaluator Name: Signature Typed or Printed Comments:

Form NTP-QA-3 1 .&I, Rev. 0. Page 1 of 2 2005 NRC Exam As Given REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE S/RO 98.G0.001 .lo1 1. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.

6. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example:

1. Whenever any electrical panel is opened for inspection during JPM performance.

2. Whenever entering any plant area where specific safety equipment; such as hearing or eye protection, safety shoes, hardhats, etc; is required and/or posted as being necessary.

C. If in the judgment of the evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.

D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required.

II. REFERENCES A. OP-198-001, Main Generator System (Rev.

3) B. GO-100-002, Plant Startup, Heatup And Power Operation (Rev. 49) 111. R EACTlVlTY MANIPULATIONS This JPM satisfies the requirements of Operational Activity(@:

None IV. TASK CONDITIONS A. A Plant Startup is in progress, Reactor Power is - 19% 6. Main turbine Startup is complete, the turbine is Q - 1800 RPM awaiting Main Generator Startup. C. Generator Prestart Lineup is complete.

D. GO-100-002, Plant Startup, Heatup And Power Operation has been completed through step 5.61.2 V. INITIATING CUE Synchronize the Main Generator to the Grid IAW section 2.2 of OP-198-001, Main Generator System, using MANUAL synchronization.

VI. TASK STANDARD Main generator synchronized to grid. VII. TASK SAFETY SIGNIFICANCE Incorrect performance of this task could lead to grid instabilities and/or LOOP (challenging the EDG to perform their function).

FormNTP-QA-31.8-1, Rev. 0, Page 2of 2 2005 NRC Exam As Given Appl. To/JPM No.:

S/RO 98.G0.001.101 - Step 1 - PERFORMANCE CHECKLIST Page 3 of 16 Action EVALUATOR NOTE: Establish task conditions as directed on attached setup instructions.

When student is ready to begin JPM, place the simulator in RUN. 0 Due to the nature of this JPM, the candidate may perform an extensive board walkdown to determine current plant status "Prior" to beginning the JPM: The FAULTED step in this JPM is preceded by a fault statement in BOLD TYPE WITH ALL CAPITAL LETTERS. Simulator Setup 0 0 Place Simulator in RUN (IC-186 for LOC-21 NRC Exam) IC- 13 Reactor Power -19 %, Turbine @ 1800 RPM ready for Generator Sychronization Obtains controlled copy of procedure Student Name: Standard Obtains controlled copy of OP-198-001, Main Generator System and refers to section 2.2 Eva1 Comments *Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam As Given PERFORMANCE CHECKLIST Page 4 of 16 Appl. To/JPM No.: S/RO 98.G0.001.101 Student Name: Action Reviews prerequisites and precautions EVALUATOR NOTE: If necessary inform candidate that service water to the H2 coolers was aligned as part of the Generator Prestart Lineup. CAUTION Allowing Main Turbine To Remain Unloaded At Rated Speed Causes Overheating Of Exhaust Hoods. Ensure the following for EHC: Main Turbine Speed Status AT SET SPEED light ILLUMINATED.

LOAD LIMIT SET vernier set at 8.9 (corresponding to MAXIMUM COMBINED FLOW LIMIT vernier set at 12.5 (corresponding to 125%). 1 00%). Standard Determines from initial conditions:

Main Turbine S/U complete.

Generator Prestart Lineup complete.

0 If service water is isolated to the H2 coolers, the Main Generator will overheat. There is NO Control Room indication for the isolation valves Verifies:

AT SET SPEED red light - LIT LOAD LIMIT SET dial pot is at 8.9 MAXIMUM COMBINED FLOW LIMIT dial pot is at 12.5 Eva1 Comments *Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0, Page 1 of I 2005 NRC Exam As Given I i Page 5 of 16 PERFORMANCE CHECKLIST Appl. To/JPM No.: S/RO 98.G0.001.101 Student Name: Action EVALUATOR NOTE: The next several steps will cause alarms to come in and clear. The candidate is expected to acknowledge the alarms as they are received. Since these are "Expected" alarms, it will not be necessary to refer to the AR, rather just acknowledge them as "Expected alarms. Place Generator Core Monitor and H2 Gas Analyzer in service as follows: BOOTH CUE: Insert MRF EC197002 IN-SVC to place Generator Core Monitor and H2 Gas Analyzer in service. EVALUATOR CUE:

Role-play NPO and report Generator Core Monitor and H2 Gas Analyzer IN service. Establish generator field: Ensure VOLT REG XFER SELECT HS 10006 switch in MANUAL. Standard Contacts an NPO to Place Generator Core Monitor and H2 Gas Analyzer are in service Verifies: VOLT REG XFER SELECT HS 10006 switch in MANUAL. AND Red light - LIT Amber light - NOT LIT Eva1 Comments *Critical Step #Critical Sequence Form NTP-QA-31.8-2.

Rev. 0, Page 1 of 1 2005 NRC Exam As Given PERFORMANCE CHECKLIST Page 6 of 16 Appl. To/JPM No.: SIR0 98.G0.001.101 Step 6 7 *8 Action Ensure MAN VOLT REG ADJUST HC 10002 at ZERO percent. Ensure AUTO VOLT REG ADJUST HC 10001 at ZERO percent. Close EXCITER FIELD BKR HS 10005. Observe: UNIT 1 MAIN GENERATOR AC KILOVOLTS, X1 10006 (Gen Terminal Voltage) Increases to about 20Kv. Is0 Phase Bus Duct Cooler Starts if NOT already in OPERATI ON. EVALUATOR CUE:

If necessary, Role-play the NPO and Inform the candidate that the Is0 Phase Bus Duct Coolers are in operation.

Student Name: Standard Verifies:

MAN VOLT REG ADJUST HC 10002 at ZERO Verifies: AUTO VOLT REG ADJUST HC 10001 at ZERO Places: EXCITER FIELD BKR HS 10005 control switch to CLOSE Verifies:

Red light - LIT Amber light - NOT LIT UNIT 1 MAIN GENERATOR AC KILOVOLTS, X1 10006 Increases to about 20 KV Is0 Phase Bus Duct Cooler (at 1C628) Red light - LIT 0 Amber light - NOT LIT Eva1 - Comments *Critical Step #Critical Sequence Form NTP-QA-3 1.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam As Given I PERFORMANCE CHECKLIST Page 7 of 16 Appl. To/JPM No.: S/RO 98.G0.001.101 Student Name: - Step 9 10 11 12 Action Using MAN VOLT REG ADJUST HC 10002 potentiometer, Raise SYNCHRONIZING BKR UNIT 1 GEN VOLTS to MATCH SYNCHRONIZING BKR GRID VOLTS XI 10009. Check proper operation of auto voltage regulation by Adjusting AUTO VOLT REG ADJUST HC 10001 potentiometer in INCREASE and DECREASE direction while Observing deviation on VR XFER XI 10012. To balance Auto and Manual Voltage Regulators, Adjust AUTO VOLT REG ADJUST HC 10001 potentiometer until VR XFER XI 10012 Reads ZERO volts. WHEN VR XFER XI 10012 Indicates ZERO, (nulled), Place the VOLT REG XFER SELECT HS 10006 switch to AUTO. Standard Turns MAN VOLT REG ADJUST HC 10002 potentiometer CLOCKWISE until: SYNCHRONIZING BKR UNIT 1 GEN VOLTS are MATCHED with SYNCHRONIZING BKR GRID VOLTS XI 10009. Turns AUTO VOLT REG ADJUST HC 10001 potentiometer CLOCKWISE then COUNTERCLOCKWISE:

Verifies:

VR XFER XI 1001 2 raises and lowers with the adjustments to the AUTO VOLT REG ADJUST HC 10001 potentiometer Turns AUTO VOLT REG ADJUST HC 10001 potentiometer as necessary to:

Verify: VR XFER XI 10012 is at ZERO Places: VOLT REG XFER SELECT HS 10006 switch to AUTO. Verifies:

Red light - NOT LIT Amber light - LIT - Eva1 Comments *Critical Step #Critical Sequence Form NTP-QA-3 1.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam As Given Appl. To/JPM No.: S/RO 98.G0.001.101 PERFORMANCE CHECKLIST Page 8of 16 Action To Ensure Auto Voltage Regulator has Control using AUTO VOLT REG ADJUST HC 10001 potentiometer:

Lower voltage slightly. Raise voltage back to original value. Notify Generation Control Center (GCC) of impending synchronization with the Grid. EVALUATOR CUE:

Role-play GCC and acknowledge the report. EVALUATOR NOTE: The next step of the procedure would have been reviewed in the pre-job brief. Since this JPM is NOT faulted in this manner, it will NOT be necessary for the candidate to exercise this Main Generator Connected Single Phase procedure. After the candidate reads the step and attempts to review the procedure, provide the candidate with the EVALUATOR CUE. PRIOR to Performing next step, Review ON 198 003, Unit 1 Main Generator Connected Single Phase to Grid During Startup. Student Name: Standard Turns AUTO VOLT REG ADJUST HC 10001 potentiometer COUNTERCLOCKWISE then CLOCKWISE:

Verifies:

VR XFER XI 10012 lowers and raises with the adjustments to the AUTO VOLT REG ADJUST HC 10001 potentiometer Calls GCC on phone and Notifies them of impending synchronization with the Grid. Attempts to review ON 198 003, Unit 1 Main Generator Connected Single Phase to Grid During Startup Eva1 Comments *Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam As Given I PERFORMANCE CHECKLIST Page 9 of 16 Appl. To/JPM No.: S/RO 98.G0.001.101 Student Name: Action EVALUATOR CUE: Role-play the Unit Supervisor and inform the candidate that another PCO has been assigned to monitor the Main Generator for potential single phase connection and will implement the Off Normal procedure if necessary.

CAUTION RPV Water Level May Decrease As A Result Of Condenser Parameter Changes During Generator Synchronization.

CAUTION Moisture Separator Drain Tank Levels Will Increase For A Short Duration As A Result Of Steam Flow Changes In The Moisture Separators During Generator Synchronization.

Perform either Automatic (preferred) or Manual SYNCHRONIZATION and LOADING section of this procedure EVALUATOR CUE: Role-play the Unit Supervisor and inform the candidate that MANUAL SYNCHRONIZATION will be performed for this startup. Standard - Eva1 ~ Comments *Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0. Page 1 of 1 2005 NRC Exam As Given Page 10 of 16 PERFORMANCE CHECKLIST Appl. To/JPM No.: S/RO 98.G0.001.101 Student Name: Step 17 18 19

• 20 Action Locates appropriate section of procedure for Manual SYNCHRONIZATION Reviews prerequisites and precautions Obtain Shift Supervision approval to Manually Synchronize main generator.

Place GEN SYNC SEL 1T HS 10002 switch to MAN. EVALUATOR NOTE:

It may not be necessary to adjust voltage in the next step. This was previously performed back in step 20 of the JPM "PRIOR" to the Fault. If the candidate determines that no adjustment is necessary at this point, then step 20 becomes the critical step. Standard Refers to section 2.4 of procedure Determines:

Main Generator S/U complete.

Determines:

Shift Supervision approval to Manually Synchronize main generator has been received Places: GEN SYNC SEL 1T HS 10002 keylock switch to MAN Verifies:

SYNCHROSCOPE meter is rotating and the lights are LIT when the meter is NOT at 12 O'clock position - Eva1 Comments *Critical Step #Critical Sequence Form NTP-QA-3 I .8-2, Rev. 0, Page 1 of 1 2005 NRC Exam As Given PERFORMANCE CHECKLIST Page 11 of 16 Appl. To/JPM No.: S/RO 98.G0.001.101 - Step *21 22

• 23 I24 Action Adjust generator output voltage by using AUTO VOLT REG ADJUST HC 10001 potentiometer so SYNCHRONIZING BKR UNIT 1 GEN VOLTS are slightly higher than SYNCHRONIZING BKR GRID VOLTS XI 10009. Ensure SYNCHRONIZING DlFF VOLTS, XI 10007, is slightly to the RIGHT of ZERO Adjust generator frequency using LOAD SELECTOR INCREASWDECREASE push buttons until SYNCHROSCOPE is rotating in the CLOCKWISE (FAST) direction at approximately 1 revolution per 60 seconds. Perform next three steps Expeditiously to reduce possibility of a reverse power trip. To Synchronize Main Generator with the grid, when synchroscope is at or slightly before "1 2 O'clock" position Close GEN SYNC BKR 1T HS 10001. Student Name: Standard Turns AUTO VOLT REG ADJUST HC 10001 potentiometer COUNTERCLOCKWISE then Verifies:

SYNCHRONIZING BKR UNIT 1 GEN VOLTS are slightly higher than SYNCHRONIZING BKR GRID VOLTS XI 10009. Verifies:

SYNCHRONIZING DlFF VOLTS, XI 10007, is slightly to the RIGHT of ZERO Depresses:

LOAD SELECTOR DECREASE pushbutton until the SYNCHROSCOPE is rotating in the CLOCKWISE (FAST) direction at approximately 1 revolution per 60 seconds. When synchroscope is at or slightly before "12 O'clock" position, Places: GEN SYNC BKR 1T HS 10001 control switch to CLOSE - Eva1 Comments *Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0, Page 1 of I 2005 NRC Exam As Given Appl. To/JPM No.: S/RO 98.G0.001.101 - Step 25 26 27 PERFORMANCE CHECKLIST Page 12 of 16 Action Ensure GEN SYNC BKR 1 T Closes by Observing:

Red indicating light GEN SYNC BKR 1T HS 10001 is I LLUMl NATED. Megawatts Increase.

Depress Increase push button on LOAD SELECTOR until all BYPASS VALVES are CLOSED. Place GEN SYNC SEL 1 T HS 10002 Switch to OFF. Student Name: Standard Verifies GEN SYNC BKR 1T HS 10001: Red light - LIT Amber light - NOT LIT Megawatts Increase Depresses: LOAD SELECTOR INCREASE pushbutton until: BPV1 POSITION indicates ZERO and BPV2 POSITION indicates ZERO and BPV3 POSITION indicates ZERO and BPV4 POSITION indicates ZERO and BPV5 POSITION indicates ZERO Places: GEN SYNC SEL 1T HS 10002 keylock switch to OFF Verifies:

SYNCHROSCOPE meter is NOT rotating and the lights are NOT LIT. - Eva1 Comments *Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0, Page 1 of I 2005 NRC Exam As Given Appl. To/JPM No.: S/RO 98.G0.001.101 Step 28 PERFORMANCE CHECKLIST Page 13 of 16 Action Maintain LOAD SET at 100 MWe ABOVE actual load EVALUATOR CUE:

This completes the JPM Student Name: Standard Depresses:

LOAD SET INCREASE pushbutton until: 100 MWe ABOVE actual load Eva1 Comments *Critical Step #Critical Seq uence Form NTP-QA-3 1.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam As Given TASK CONDITIONS A. A Plant Startup is in progress, Reactor Power is - 19% B. Main turbine Startup is complete, the turbine is 8 - 1800 RPM awaiting Main Generator Startup. C. Generator Prestart Lineup is complete.

D. GO-100-002, Plant Startup, Heatup And Power Operation has been completed through step 5.61.2 INITIATING CUE Synchronize the Main Generator to the Grid IAW section 2.2 of OP-198-001, Main Generator System, using MANUAL synchronization.

2005 NRC Exam As Given Page 1 of 2 TASK CONDITIONS A. A Plant Startup is in progress, Reactor Power is - 19% 6. Main turbine Startup is complete, the turbine is Q - 1800 RPM awaiting Main Generator Startup. C. Generator Prestart Lineup is complete.

D. GO-100-002, Plant Startup, Heatup And Power Operation has been completed through step 5.61.2 INITIATING CUE Synchronize the Main Generator to the Grid IAW section 2.2 of OP-198-001, Main Generator System, using MANUAL synchronization.

2005 NRC Exam As Given Page 2 of 2 PPL SUSQUEHANNA, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET SIR0 52.0P.009.151 0 10/4105 206000 A4.14 4.2l4.1 APPl. JPM Number Rev.

No. Date NUREG 1123 WA No. WA Imp. To Sys. No. Task Title:

Completed By: Terminate HPCl injection (With several malfunctions inserted) Rich Chin Writer Approval:

Nuclear Trng. Supv. Date of Performance: JPM Performed By: Validated 1014105 Date InstructorMlriter Date Date 10 Validation Time (Min.) Time Taken (Min.) Student Name: Last First M.I. Employee # / S.S. # Performance ( ) Satisfactory ( ) Unsatisfactory Eva1 uat ion : Evaluator Name: Signature Typed or Printed Comments:

Form NTP-QA-31.8-1, Rev. 0, Page 1 of 2 2005 NRC Exam As Given R EQUl RED TASK INFORMATION JOB PERFORMANCE MEASURE S/RO 52.0P.009.151

1. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.

B. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example: 1. Whenever any electrical panel is opened for inspection during JPM performance.

2. Whenever entering any plant area where specific safety equipment; such as hearing or eye protection, safety shoes, hardhats, etc; is required andor posted as being necessary.

C. If in the judgment of the evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.

D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required.

II. REFERENCES A. OP-152-001, High Pressure Coolant Injection (HPCI) System (Rev.

36) II I. R EACTlVlTY MANIPULATIONS This JPM satisfies the requirements of Operational Activity(s):

None IV. TASK CONDITIONS A. The plant is in Condition 1 at approximately 68 percent reactor power. B. An inadvertent HPCl initiation has occurred.

V. INITIATING CUE Override HPCl injection IAW the appropriate Hardcard VI. TASK STANDARD HPCl injection stopped with HPCl turbine shutdown.

VILTASK SAFETY SIGNIFICANCE Ability to control RPV water level.

Form NTP-QA-31.8-1, Rev. 0. Page 2 of 2 2005 NRC Exam As Given PERFORMANCE CHECKLIST Page 3 of 8 Appl. To/JPM No.: S/RO 52.0P.009.151 Step 1 Action EVALUATOR NOTE:

Establish task conditions as directed on attached setup instructions.

The IC MUST be set up such that an inadvertent HPCl initiation has just occurred AND no action has yet been taken. A malfunction or override should be used to prevent manual override of HPCl injection, requiring the operator to isolate HPCI. With the given the Task Conditions/lnitiating Cue Sheet and allowed to observe the panel.

When student is ready to begin JPM, place the simulator in RUN. The FAULTED step in this JPM is preceded by a fault statement in BOLD TYPE WITH ALL CAPITAL LElTERS. (IC-185 for LOC-21 NRC exam) (Y P P . I 0 LN R C J P M D E F) Insert pfs 4 IMF HP152004 to initiate HPCl inadver start Candidate refers to appropriate procedural section.

en Student Name: Standard OP-158-001 Attachment C step 2 Comments *Critical Step #Critical Sequence Form NTP-QA-3 1.8-2, Rev. 0, Page I of 1 2005 NRC Exam As Given PERFORMANCE CHECKLIST Page 4 of 8 Appl. To/JPM No.: S/RO 52.0P.009.151 - Step 2 3 4 Action To stop injection place HPCl pump on minimum flow as follows: 0 Place or CHECK PLACED HPCl AUXILIARY OIL PUMP 1 P213 switch to START. FAULT STATEMENT HPCl INJECTION FLOW WILL NOT DECREASE TO ZERO WHEN PRESSURE IS REDUCED TO LESS THANREACTORPRESSURE.

Place HPCl TURBINE FLOW CONTROL FC E41 1 R600 in MANUAL. Adjust HPCl TURBINE FLOW CONTROL FC E41 1 R600 to reduce HPCl discharge pressure less than Reactor pressure.

• Critical Step #Critical Sequence Student Name: Standard Places the control switch for HPCl Aux Oil Pump 1 P213 in the START position.

Places the ManuaVAuto switch on HPCl Turbine Flow Control FC-E41-1 R600 to the M position Depresses the Close pushbutton on HPCl Turbine Flow Control FC-E41-1 R600 until the HPCl pump discharge pressure is less than reactor pressure.

Verifies:

HPCl PP DISCH PRESS PI-E41-1 R601 pressure is GREATER THAN any RPV pressure indication Eva1 Comments Form NTP-QA-31.8-2, Rev. 0. Page 1 of 1 2005 NRC Exam As Given PERFORMANCE CHECKLIST Page 5 of 8 Appl. To/JPM No.: S/RO 52.0P.009.151 Ensure HPCl MIN FLOW TO SUPP POOL HV 155 F012 opens when HPCl flow < 500 gpm and discharge pressure > 125 psig. IF HPCl flow indication does not decrease to zero gpm with HPCl pump discharge pressure less than reactor pressure, Shut Down HPCl per following step. To stop injection/shutdown HPCI: Ensure HPCl AUXILIARY PUMP 1 P213 switch placed to START. Depress HPCl INT SIG RESET HS E41 1S17 RESET pushbutton.

IF HPCl initiation resets, Shut Down HPCl in accordance with "Shutdown" section of OP 152 001. Student Name: Standard Verifies: HPCl MIN FLOW TO SUPP POOL HV 155 F012 Red light - NOT LIT Amber light - LIT AND HPCl Flow FI-E41-1 R600-1 is STILL INDICATED Determines: HPCl will need Shutdown IAW next step Previously performed Depresses: HPCl INT SIG RESET HS E41 1S17 RESET pushbutton Verifies:

Green light - LIT Eva1 - Comments *Critical Step #Critical Sequence Form NTP-QA-3 1.8-2, Rev. 0, Page 1 of I 2005 NRC Exam As Given Appl. To/JPM No.: S/RO 52.0P.009.151 Step 9 *10 PERFORMANCE CHECKLIST Page 6 of 8 Action IF HPCl initiation does not reset, stop injectionkhut down using following sections (1 ) preferred, OR (2): EVALUATOR NOTE: HPCl Flow controller steps were previously performed and were unsuccessful, candidate should proceed to Isolate HPCl per section 2.2 To isolate HPCI: Depress HPCl STM SUPPLY MAN IS0 HS E41 1S32 pushbutton.

EVALUATOR NOTE: Depressing the PI3 will stop the pump, HOWEVER with pre-programmed malfunction, HV-155 F003 will FAIL to close. *Critical Step #Critical Sequence Student Name: Standard Determines HPCl initiation did NOT reset Verifies HPCl INT SIG RESET HS E41 1 S17 RESET Green light - LIT Depresses:

HPCl STM SUPPLY MAN IS0 HS E41 1S32 pushbutton - Eva1 Comments Form NTP-QA-31.8-2.

Rev. 0, Page I of 1 2005 NRC Exam As Given Appl. To/JPM No.: S/RO 52.0P.009.151 PERFORMANCE CHECKLIST Page 7 of 8 Action Ensure HPCl STM SUPPLY OB IS0 HV 155 F003 CLOSES. EVALUATOR CUE:

If necessary, Role-play the SRO and instruct the candidate to continue with the procedure. Ensure HPCl PUMP SUCT FROM SUPP POOL HV 155 F042 CLOSES. Ensure HPCl INJECTION HV 155 F006 CLOSES. *Critical Step #Critical Sequence Student Name: Standard Inserts key into keylock switch HPCl STM SUPPLY OB IS0 HV 155 F003 and places to CLOSE position Verifies: Red light - NOT LIT Amber light - LIT Verifies: PUMP SUCT FROM SUPP POOL HV 155 F042 Red light - NOT LIT Amber light - LIT Verifies: HPCl INJECTION HV 155 F006 Red light - NOT LIT Amber light - LIT Eva1 Comments Form NIT-QA-3 1.8-2, Rev. 0, Page I of 1 2005 NRC Exam As Given Appl. To/JPM No.: S/RO 52.0P.009.151 - Step 14 f15 16 Page 8 of 8 PERFORMANCE CHECKLIST Action Ensure HPCl AUX OIL PUMP 1 P213 starts as HPCl turbine coasts down. Close HPCl STM SUPPLY IB IS0 HV 155 F002. Place HPCl STM SUPPLY OB IS0 HV 155 F003 KEYSWITCH to CLOSE. EVALUATOR CUE: This completes the JPM *Critical Step #Critical Sequence Student Name: Standard Verifies:

HPCl AUX OIL PUMP 1 P213 Red light - LIT Amber light - NOT LIT Places: HPCl STM SUPPLY IB IS0 HV 155 F002 to CLOSE AND Verifies: Red light - NOT LIT Amber light - LIT Previously completed in step 11 of this JPM - Eva1 Comments Form NTP-QA-3 I .8-2, Rev. 0, Page 1 of 1 2005 NRC Exam As Given TASK CONDITIONS A. The plant is in Condition 1 at approximately 68 percent reactor power.

B. An inadvertent HPCl initiation has occurred.

INITIATING CUE Override HPCl injection IAW the appropriate Hardcard 2005 NRC Exam As Given Page 1 of 2 TASK CONDITIONS A. The plant is in Condition 1 at approximately 68 percent reactor power. B. An inadvertent HPCl initiation has occurred.

INITIATING CUE Override HPCl injection IAW the appropriate Hardcard 2005 NRC Exam As Given Page 2 of 2 PPL SUSQUEHANNA, LLC SIR0 Appl. To Task Title: JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET 58.0P.008.101 0 0912 8/05 21 2000 K4.03 3.013.1 JPM Number Rev. No. Date NUREG 1123 WA No. KIA Imp. Sys. No. Transferring Power Supply From RPS M-G Set To Alternate Completed By: Validated:

Rich Chin 09/28/05 Writer Date InstructorNVriter Date Approval: Nuclear Trng.

Supv. Date Date of Performance:

JPM Performed By: 15 Validation Time (Min.)

Time Taken (Min.) Student Name: Last First M.I. Employee #/S.S. # Performance Evaluation: ) Satisfactory ( ) Unsatisfactory Evaluator Name: Signature Typed or Printed Comments:

Form NTP-QA-31.8-1, Rev. 0, Page 1 of 2 2005 NRC Exam As Given REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE S/RO 58.0P.008.101

1. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.

B. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example: 1. Whenever any electrical panel is opened for inspection during JPM performance.

2. Whenever entering any plant area where specific safety equipment; such as hearing or eye protection, safety shoes, hardhats, etc; is required and/or posted as being necessary.

C. If in the judgment of the evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved. D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required.

II. REFERENCES OP-158-001 RPS System (Revision

29) I I I. R E ACT1 V ITY MAN I P U LATlO N S This JPM satisfies the requirements of Operational Activity(s):

NONE IV. TASK CONDITIONS A. Unit 1 is in Mode 1 at - 68% power B. RPS Shorting Links are installed C. Attachment A of OP-158-001, RPS System, is complete D. RPS Alternate Power supply is available E. All required Tech Spec LCO entries have been made. V. INITIATING CUE Transfer Power Supply from "A RPS M-G Set to Alternate and restore plant systems, IAW the appropriate Attachment.

VI. TASK STANDARD "A' RPS Bus powered from Alternate with all reset functions RESET. VII. TASK SAFETY SIGNIFICANCE Provide reliable power source to RPS Form NTP-QA-31.8-1, Rev. 0, Page 2 of 2 2005 NRC Exam As Given Appl. To/JPM No.: 58.0P.008.101 Step 1 2 PERFORMANCE CHECKLIST Page 3 of 8 Action EVALUATOR NOTE:

0 0 Select Mode 1 IC 0 This JPM must be performed in the simulator.

Complete Attachment A of OP-158-001 (run auto exercise file RPSAXFER-SU) and write an IC Insert pref YPP.CERTJPM-0401 which contains:

0 pfs 1 MRF RM179024 RESET resets MSL rad monitor RIS-D12-1 K603A pfs 2 MRF RM179026 RESET resets MSL rad monitor RIS-D12-1 K603C pfs 3 MRF DB106360 CLOSE Closes breaker for RWCU valve HV-144-FOO1 0 When student is ready to begin JPM, place the simulator in RUN. 0 /YPP.ILONRcJpMDEF for LOC-21 NRC exam) 0 /IC 185 for LOC-21 NRC exam) Obtain a controlled copy of OP-158-001 RPS System Selects the correct section to perform. *Critical Step #Critical Sequence Student Name: Standard Controlled copy obtained.

Selects section 2.4 Eva1 - Comments Form NTP-QA-31.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam As Given Appl. To/JPM No.: 58.0P.008.101 Step 3 4 5 6 I I PERFORMANCE CHECKLIST Page 4 of 8 Student Name: Action Review the prerequisites.

Review all precautions.

Prepare Plant for isolation in accordance with Attachment A for A RPS, EVALUATOR NOTE: Alternate Power Supply can supply only one RPS Bus at a time. At Reactor Control Rod Test Instrument Panel 1 C610: Check Alternate A Feed To RPS Bus A white indicating light ILLUMINATED.

Check M-G Set Transfer switch in NORM position.

• Critical Step #Critical Sequence Standard Based on initial conditions, Determines all prerequisites have been met. Follows all precautions as applicable.

Based on initial conditions, determines that this has already been done.

Verifies:

Alternate A Feed To RPS Bus A white indicating light LIT RPS M-G Set Transfer switch HS-C72B-S1 in NORM position - Eva1 Comments Form NTP-QA-31.8-2, Rev. 0. Page 1 of 1 2005 NRC Exam As Given Appl. To/JPM No.:

58.0P.008.101 Step *7 8 9 *lo I PERFORMANCE CHECKLIST Action EVALUATOR NOTE: Following step must be Performed Slowly (approximately 2 seconds) to allow sufficient time for all expected actuations and isolations to occur prior to Transfer Switch reaching Alt A position. Multiple alarms will be received when M-G Set Transfer switch HS-C72B-S1 is placed in RPS ALT-A position. Slowly Place RPS M-G Set Transfer switch HS-C72B-S1 in the ALT-A position.

Acknowledges the numerous alarms Restore systems in accordance with Attachment C Reset A RPS half scram by Momentarily Positioning 1/4 position and then to GRP 2/3 position. REACTOR SCRAM RESET HS-C72A-lS05 to GRP *Critical Step #Critical Sequence Student Name: ~~ Standard Slowly Places RPS M-G Set Transfer Switch HS-C72B-S1 in the ALT-A position. Depresses Silent and Reset pushbuttons for all panels in alarm. Selects Attachment C Places the RX SCRAM RESET switch to the GRP 1/4 position then to the GRP 2/3 position and returns to the NORM position.

Verifies:

The following alarm is clear 0 RPS CHANNEL B1/B2 AUTO SCRAM, AR-104-A01. - Eva1 Page 5 of 8 Comments Fo~ NTP-QA91.8-2, Rev. 0, Page 1 Of 1 2005 NRC Exam As Given PERFORMANCE CHECKLIST Page 6 of 8 Appl. To/JPM No.: 58.0P.008.101 - Step *11 12 13 *14 *15 Action Reset NSSSS isolation logic as follows: Depress MN STM LINE DIV 1 IS0 RESET Depress MN STM LINE DIV 2 IS0 RESET HS-B21-1 S32. HS-B21-1 S33. Recover from RBCW isolation as follows: Ensure RRP A CLG WTR OB IS0 VALVES HV-18791 A1 &A2 CLOSED. Ensure RRP B CLG WTR IB IS0 VALVES HV-18792A1

&A2 CLOSED. Depress HV-18791 A1 &A2 ISOLATION RESET. Depress HV-18792A1

&A2 ISOLATION RESET. *Critical Step #Critical Sequence Student Name: Standard Depresses:

MN STM LINE DIV 1 IS0 RESET MN STM LINE DIV 2 IS0 RESET HS-B21-1 S32. HS-B21-1 S33. Verifies:

Amber light LIT and red light NOT LIT for RRP A CLG WTR OB IS0 VALVES HV-18791 A1 &A2 Verifies:

Amber light LIT and red light NOT LIT for RRP B CLG WTR IB IS0 VALVES HV-18792A1

&A2 Depresses: push button HV-18791 A1 &A2 ISOLATION RESET Depresses:

pushbutton HV-18792A1

&A2 ISOLATION RESET Comments Form NTP-QA-31.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam As Given PERFORMANCE CHECKLIST Page 7 of 8 Appl. To/JPM No.: 58.0P.008.101 Step 16 17 18 19 Action Ensure RRP A CLG WTR OB IS0 VALVES HV-18791A1

&A2 OPEN. Ensure RRP B CLG WTR I6 IS0 VALVES HV-18792A1 &A2 OPEN.

Recover from CAC System isolation as follows: Ensure CONTN GAS ANLZR IB IS0 LOOP A Ensure CONTN GAS ANLZR OB IS0 LOOP A HS-15740A CLOSED. HS-15742A CLOSED. EVALUATOR CUE: Role-play Shift supervision, and inform candidate that It is NOT desired to place "A H202 Analyzer in service IF RHR Shutdown Cooling isolations were defeated, Restore as follows *Critical Step #Critical Sequence Student Name:

Standard Verifies:

Amber light NOT LIT and red light LIT for RRP A CLG WTR OB IS0 VALVES HV-18791 A1 &A2 Verifies:

Amber light NOT LIT and red light LIT for RRP B CLG WTR IB IS0 VALVES HV-18792A1

&A2 Verifies:

CONTN GAS ANLZR I6 IS0 LOOP A CONTN GAS ANLZR OB IS0 LOOP A Amber lights LIT Red lights NOT LIT HS-15740A HS-15742A Determines RHR is NOT in Service - Eva1 Comments Fom NTP-QA-31.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam As Given Appl. To/JPM No.: 58.0P.008.101 - Step *20 - PERFORMANCE CHECKLIST Page 8 of 8 Action IF RWCU isolations were defeated, Restore as follows: Close breaker 18236-053 power supply to RWCU INLET IB IS0 HV-144-FOO1. EVALUATOR CUE: Role-play the NPO and Acknowledge the request BOOTH CUE: Depress pfs 3 MRF DB106360 CLOSE Contact PCO and inform the PCO that breaker 18236-053 power supply to RWCU INLET I8 IS0 HV-144-FOO1 is CLOSED EVALUATOR CUE: Role-play Shift supervision, and inform candidate that another operator is available to complete Attachment C This completes the JPM. Student Name: ~____ Standard Contacts NPO to Close breaker 18236-053 power supply to RWCU INLET IB IS0 HV-144-F001. *Critical Step #Critical Sequence Eva1 Comments Form NTP-QA-31.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam As Given TASK CONDITIONS

\ A. Unit 1 is in Mode 1 at - 68% power 6. RPS Shorting Links are installed C. Attachment A of OP-158-001, RPS System, is complete D. RPS Alternate Power supply is available E. All required Tech Spec LCO entries have been made. INITIATING CUE Transfer Power Supply from "A RPS M-G Set to Alternate and restore plant systems, IAW the appropriate Attachment.

2005 NRC Exam As Given 1 of2 PPL SUSQUEHANNA, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET S/RO 55.0N.007.152 0 10/4/05 201 003 A2.01 3.4/3.6 APPl. JPM Number Rev. No. Date NUREG 1123 WA No. WA Imp. To Sys. No. Task Title: Respond To A Stuck Control Rod IAW ON-1 55-001 Completed By: Validated Rich Chin 10/4/05 Writer Date I nstructorMl riter Date Approval: Nuclear Trng. Supv.

Date of Performance:

Date 20 Validation Time (Min.) Time Taken (Min.) JPM Performed By: Student Name:

Last First M.I. Employee # / S.S. # Performance Evaluation:

Evaluator Name: ( ) Satisfactory ( ) Unsatisfactory Signature Typed or Printed Comments:

FormNTP-QA-31.8-1, Rev. 0, Page 1 of 2 2005 NRC Exam As Given REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE WRO 55.0N.007.152 I. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations. B. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example: 1. Whenever any electrical panel is opened for inspection during JPM performance. 2. Whenever entering any plant area where specific safety equipment; such as hearing or eye protection, safety shoes, hardhats, etc; is required and/or posted as being necessary.

C. If in the judgment of the evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.

D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required.

II. REFERENCES A. ON-1 55-001, CONTROL ROD PROBLEMS (Rev. 23) B. Startup Sequence

82. 111. REACTIVITY MAN1 PU LATIONS This JPM satisfies the requirements of Operational Activity(s):

None IV. TASK CONDITIONS A. Unit 1 is at 68%

power B. A Plant Startup is in progress at Unit 1 IAW GO-100-102; step 5.75 has been completed.

V. INITIATING CUE The Unit Supervisor directs you to raise Reactor Power to 75% by SINGLE NOTCH Withdrawing Rods IAW startup sequence B2 beginning at step 554. Notify Reactor Engineering when 75% power is achieved. Assume the p briefing for this power change has been completed. VI. TASK STANDARD Rods 18 55, 42-07, and 18-07 withrdrawn to notch 12; Rod 42-55 withdrawn to notch 06 VII. TASK SAFETY SIGNIFICANCE Ability to safely add positive Reactivity with control rod motion Form NTP-QA-31.8-1, Rev.

0, Page 2 of 2 2005 NRC Exam As Given Appl. To/JPM No.: S/RO 55.0N.007.152 - Step PERFORMANCE CHECKLIST Page 3 of 16 > Action EVALUATOR NOTE: 0 Establish task conditions as directed on attached setup instructions.

Prepare a Startup Sequence B2 signed -off up to step 554. The FAULTED step in this JPM is preceded by a fault statement in BOLD TYPE WITH ALL CAPITAL LETTERS. 0 When student is ready to begin JPM, place the simulator in RUN. Simulator Setup 0 MODE 1 68% IC. Place Simulator in RUN Run Display ROD 42-55 select Stuck Rod and Accept Ensure RNFE is on the Venturis Ensure PlCYS screen is on CRDA *Critical Step #Critical Sequence Student Name: Standard Eva1 - Comments Form NTP-QA-31.8-2.

Rev. 0. Page 1 of 1 2005 NRC Exam As Given I PERFORMANCE CHECKLIST Page 4 of 16 Appl. To/JPM No.: S/RO 55.0N.007.152 Step *1 $2 Action Selects Rod 18-55 for withdraw Withdraws Rod 18-55 to notch 12 *Critical Step #Critical Sequence Student Name: Standard Depresses 18 - 55 Verifies 18 and 55: White lights - LIT Full core display reads notch 04 Depresses W/DRAW ROD pushbutton Verifies:

Full core display changes to notch 06 Depresses W/DRAW ROD pushbutton Verifies:

Full core display changes to notch 08 Depresses W/DRAW ROD pushbutton Verifies: Full core display changes to notch 10 Depresses W/DRAW ROD pushbutton Verifies: Full core display changes to notch 12 - Eva1 Comments Form NTP-QA-3 1.8-2. Rev. 0, Page 1 of 1 2005 NRC Exam As Given Appl. To/JPM No.: S/RO 55.0N.007.152 Step *3 f4 PERFORMANCE CHECKLIST Page 5 of 16 Action ~ ~~~ Selects Rod 42-07 for withdraw Withdraws Rod 42-07 to notch 12 *Critical Step #Critical Sequence Student Name: Standard Depresses 42-07 Verifies 42 and 07: White lights - LIT Full core display reads notch 04 Depresses W/DRAW ROD pushbutton Verifies:

Full core display changes to notch 06 Depresses W/DRAW ROD pushbutton Verifies: Full core display changes to notch 08 Depresses W/DRAW ROD pushbutton Verifies: Full core display changes to notch 10 Depresses W/DRAW ROD pushbutton Verifies: Full core display changes to notch 12 - Eva1 Comments Form NW-QA-3 1.8-2, Rev. 0, Page 1 of I 2005 NRC Exam As Given Appl. To/JPM No.: S/RO 55.0N.007.152 Step *5 PERFORMANCE CHECKLIST Page 6 of 16 Action Selects Rod 18-07 for withdraw Withdraws Rod 18-07 to notch 12 *Critical Step #Critical Sequence Student Name: Standard Depresses 18-07 Verifies 18 and 07: White lights - LIT Full core display reads notch 04 Depresses W/DRAW ROD pushbutton Verifies: Full core display changes to notch 06 Depresses W/DRAW ROD pushbutton Verifies:

Full core display changes to notch 08 Depresses W/DRAW ROD pushbutton Verifies: Full core display changes to notch 10 Depresses W/DRAW ROD pushbutton Verifies: Full core display changes to notch 12 Eva1 Comments Form NTP-QA-31.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam As Given Appl. To/JPM No.: S/RO 55.0N.007.152 - Step f7 8 PERFORMANCE CHECKLIST Page 7 of 16 Action Selects Rod 42-55 for withdraw FAULT STATEMENT:

ROD 42-55 WILL NOT MOVE IN THE NEXT STEP Withdraws Rod 42-55 to notch 12 EVALUATOR CUE:

Candidate may request permission to attempt to move rod ONE MORE time before proceeding to the Off- Normal procedure.

IF necessary, Role-play Unit Supervisor and grant permission to attempt ONE MORE withdrawal sequence.

• Critical Step #Critical Sequence Student Name: Standard Depresses 42-55 Verifies 42 and 55: White lights - LIT Full core display reads notch 04 Depresses W/DRAW ROD pushbutton Verifies:

Full core display DID NOT CHANGE to notch 06 - Eva1 Comments Form NTP-QA-31.8-2, Rev. 0, Page I of 1 2005 NRC Exam As Given Appl. To/JPM No.: S/RO 55.0N.007.152 Step 9 PERFORMANCE CHECKLIST Page 8 of 16 Action Proceed to applicable section of OFF-Normal procedure ON-1 55-001, Control Rod Problems as indicated.

Stuck Control Rod Step 3.3 Rod Drift or Rod Scram Step 3.4 Rod Overtravel Step 3.5 Mispositioned Rod Step 3.6 Multiple Rod Notching Step 3.7 Slow to Settle Rod Step 3.8 NOTE: Rx Engineering notification is desired, when this section is performed because a control rod has failed to settle properly.

• Critical Step #Critical Sequence Student Name: Standard Determines step 3.3 is applicable based on initial conditions.

Eva1 Comments Form NTP-QA-31.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam As Given PERFORMANCE CHECKLIST Page 9 of 16 Appl. To/JPM No.: SIR0 55.0N.007.152 Action IF rod position indication does not change when valid withdraw OR insert signal applied, Perform the following:

Confirm control rod position using any 3 of the svailable rod position indication as follows: CRT and SIP 4 ROD DISPLAY.

FULL IN/FULL OUT DISPLAY push button. *OD7 0 Alarm logging printer, System Event Display Message RSCS Display when below Low Power Alarm Point. 0 RWM Main Display when below Low Power Alarm Point. CAUTION Scramming a stuck control rod will cause damage to CRD mechanism.

• Critical Step #Critical Sequence Student Name: Standard Uses any 3 of the following to confirm Rod 42-55 is STILL AT NOTCH 4 CRT and SIP 4 ROD DISPLAY.

OD7 FULL IN/FULL OUT DISPLAY push button.

Alarm logging printer, System Event Display Message RSCS Display when below Low Power Alarm Point. RWM Main Display when below Low Power Alarm Point.

Eva1 Comments Form NTP-QA-3 I .8-2. Rev. 0, Page 1 of 1 2005 NRC Exam As Given

- (D O 0 a, w a 7 Y- 7 a c -I Y I 0 W 0 z 4 E U % Y 2 a n W .. W z 5 k 0 PERFORMANCE CHECKLIST Page 11 of 16 Appl. To/JPM No.: S/RO 55.0N.007.152 - Step 11 - Action IF rod failed to withdraw:

Attempt to operate drive by: Perform either 1 ) OR 2) below: 1. Depress withdraw rod pushbutton.

2. With Shift Supervision approval, Depress withdraw and continuous withdraw rod pushbuttons. EVALUATOR CUE: Role-play Unit Supervisor and grant permission to Depress withdraw and continuous withdraw rod pushbuttons.

Simultaneously Momentarily Depress the continuous insert AND withdraw pushbuttons to Withdraw rod to appropriate position (one notch at power). *Critical Step #Critical Sequence Student Name: Standard Simultaneously Momentarily Depresses the: W/DRAW ROD CONTINSERT pushbuttons AN D/O R Requests permission from Unit Supervisor to Depress withdraw and continuous withdraw rod pushbuttons Simultaneously Momentarily Depresses the: W/DRAW ROD CONT W/DRAW ROD CONTINSERT pushbuttons Uses the following to confirm Rod 42-55 is STILL AT NOTCH 4 0 CRT and SIP 4 ROD DISPLAY. Eva1 - Comments Form NTP-QA-3 1.8-2. Rev. 0, Page 1 of 1 2005 NRC Exam As Given Appl. To/JPM No.: S/RO 55.0N.007.152 - Step 12 13 PERFORMANCE CHECKLIST Page 12 of 16 Action IF rod position does not change on 4 rod display, Confirm control rod position using available rod position indications. - IF rod failed to move, Attempt to move control rod, as follows: Complete rod data on Attachment A. *Critical Step #Critical Sequence Student Name: Standard Uses any 3 of the following to confirm Rod 42-55 is STILL AT NOTCH 4 0 CRT and SIP 4 ROD DISPLAY. 0 FULL IN/FULL OUT DISPLAY push button. OD7 0 Alarm logging printer, System Event Display Message 0 RSCS Display when below Low Power Alarm Point. 0 RWM Main Display when below Low Power Alarm Point. Records the following on Attachment A Date Time Rod 42-55 Position 04 Reactor Pressure Eva1 Comments Form NIT-QA-31.8-2, Rev. 0. Page 1 of 1 2005 NRC Exam As Given PERFORMANCE CHECKLIST Page 13 of 16 Appl. To/JPM No.: S/RO 55.0N.007.152 Action In - 50 psid increments, Increase drive water pressure AND Perform following at each increment until 5350 psid reached: CAUTION Elevated drive pressure increases the risk of multiple notch movement.

Attempt to operate drive one notch in intended direction, authorized by procedure governing original Control Rod motion, while observing drive water flows (4 gpm inserU2.5 gpm withdraw). EVALUATOR CUE: Normally, another operator would be assigned to observe drive water flows. If necessary, inform candidate that drive water flow was 2.5 gpm during the withdrawal attempt. Student Name: Standard Places DRIVE WTR PRESS THLTG PV-146FOO3 to CLOSE UNTIL DRIVE WATER DlFF PRESSURE PDI-C12-1 R602 INCREASES FROM

-250 TO 300 PSlD Depresses W/DRAW ROD pushbutton Verifies: Full core display FOR ROD 42-55 DID NOT CHANGE to notch 06 AND Verifies:

DRIVE WATER FLOW FI-C12-1 R604 RAISE to -2.5 gpm Eva1 Comments *Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0, Page I of I 2005 NRC Exam As Given PERFORMANCE CHECKLIST Page 14 of 16 Appl. To/JPM No.: S/RO 55.0N.007.152 Student Name: Step f16 Action BOOTH CUE: Remove ROD 42-55 Stuck Rod malfunction CAUTION Elevated drive pressure increases the risk of multiple notch movement.

Attempt to operate drive one notch in intended direction, authorized by procedure governing original Control Rod motion, while observing drive water flows (4 gpm insed2.5 gpm withdraw). EVALUATOR CUE:

Normally, another operator would be assigned to observe drive water flows. If necessary, inform candidate that drive water flow was 2.5 gpm during the withdrawal attempt. EVALUATOR CUE: Role-play Unit Supervisor and acknowledge the report and direct candidate to complete the ON procedure

• Critical Step #Critical Sequence Standard Depresses W/DRAW ROD pushbutton Verifies: Full core display FOR ROD 42-55 CHANGES to notch 06 AND Verifies:

DRIVE WATER FLOW FI-C12-1 R604 RAISE to -2.5 gpm Reports ROD 42-55 is at NOTCH 06 to Unit Supervisor Eva1 Comments Form NTP-QA-31.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam As Given Appl. To/JPM No.: S/RO 55.0N.007.152 Step 17 18 19 PERFORMANCE CHECKLIST Page 15 of 16 Action IF rod moves one notch in intended direction, Go to step 3.3.1 .f. Record drive water pressure required to move control rod on Attachment A. Record drive water flow that is indicated while attempting to move stuck control rod on Attachment A. NOTE (1): - IF control rod testing is being performed IAW TP-055-001 or TP-055-006, multiple control rod notch movement is allowed at elevated drive water pressure.

Drive water pressure must be returned to 250 psid prior to testing next control rod. NOTE (2): Multiple notch movement is permitted for control rods with identified friction (except during startup single notch restraint).

If excessive control rod speed is observed, control rod movement must be stopped and drive pressure returned to 250 psid. *Critical Step Student Name: Standard Proceeds to step 3.3.1 .f. Records the following on Attachment A: 300 psid drive water pressure required to move control rod Records the following on Attachment A: Indicated drive water flow required to move control rod - Eva1 Comments #Critical Sequence Form NTP-QA-3 1.8-2, Rev. 0, Page 1 of I 2005 NRC Exam As Given Appl. To/JPM No.: S/RO 55.0N.007.152 PERFORMANCE CHECKLIST Page 16 of 16 Action Return drive water pressure to - 250 psid, for each subsequent rod notch. Document on Attachment A. EVALUATOR CUE: This completes the JPM

• Critical Step #Critical Sequence Student Name: Standard Places DRIVE WTR PRESS THLTG PV-146FOO3 to OPEN UNTIL DRIVE WATER DlFF PRESSURE PDI-C12-1 R602 INCREASES FROM -250 PSlD AND Records the following on Attachment A: 250 psid Comments Form NTP-QA-31.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam As Given TASK CONDITIONS A. Unit 1 is at 68% power B. A Plant Startup is in progress at Unit 1 IAW GO-1 00-1 02; step 5.75 has been completed.

INITIATING CUE The Unit Supervisor directs you to raise Reactor Power to 75% by SINGLE NOTCH Withdrawing Rods IAW startup sequence 82 beginning at step 554. Notify Reactor Engineering when 75% power is achieved. Assume the p briefing for this power change has been completed.

2005 NRC Exam As Given Page 1 of 2 TASK CONDITIONS A. Unit 1 is at 68% power B. A Plant Startup is in progress at Unit 1 IAW GO-100-102; step 5.75 has been completed.

INITIATING CUE The Unit Supervisor directs you to raise Reactor Power to 75% by SINGLE NOTCH Withdrawing Rods IAW startup sequence B2 beginning at step 554. Notify Reactor Engineering when 75% power is achieved.

Assume the p briefing for this power change has been completed.

2005 NRC Exam As Given Page 2 of 2 PPL SUSQUEHANNA, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET SIR0 45.0P.004.151 0 1014105 259001 A3.10 3.413.4 APPl. JPM Number Rev. No. Date NUREG 1123 KIA No. KIA Imp. To Sys. No. Task Title: Completed By: Validated Commence Feeding with an additional RFPlShutdown RFP due to High vibrations Rich Chin 1014/05 Writer Date I nstructorMl riter Date Approval : Nuclear Trng. Supv. Date of Performance:

JPM Performed By: Date 15 Validation Time (Min.) Time Taken (Min.) Student Name: Last First M.I. Employee # / S.S. # Performance Evaluation: ( ) Satisfactory ( ) Unsatisfactory Evaluator Name: Signature Typed or Printed Comments:

Form NTP-QA-31.8-1, Rev. 0, Page 1 of 2 2005 NRC Exam As Given REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE S/RO 45.0P.004.151

1. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.

B. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example: 1. Whenever any electrical panel is opened for inspection during JPM performance.

2. Whenever entering any plant area where specific safety equipment; such as hearing or eye protection, safety shoes, hardhats, etc; is required and/or posted as being necessary.

C. If in the judgement of the evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.

D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required.

II. REFERENCES OP-145-001, RFP and RFP Lube Oil System (Revision

42) II I. R EACTlVlTY MANIPULATIONS This JPM satisfies the requirements of Operational Activity(s):

NONE IV. TASK CONDITIONS A. Unit 1 is Q 48% power with a plant startup in progress.

B. RFP A and B are feeding the RPV in Automatic level control C. RFP C has been started and warmed, and is ready to feed the RPV. D. Feedwater venturies selected as input to PlCSY Core Thermal Power Heat Balance. V. INITIATING CUE Commence feeding the RPV with RFP C IAW with the appropriate procedure.

VI. TASK STANDARD RFP C is shutdown and isolated, with RFP A and B in automatic level control VII. TASK SAFETY SIGNIFICANCE Failure to secure the RFP could lead to unacceptable RPV water level fluctuations, or catastrophic failure of the RFP. Form NTP-QA-31.8-1, Rev. 0, Page 2 of 2 2005 NRC Exam As Given I PERFORMANCE CHECKLIST Appl. To/JPM No.: 45.0P.004.151 Action From any 48% power IC Insert YPP.ILONRCJPMGH Places F condensate Demin in service IOR QDIHSS116OOF SRVC "C RFP TURBINE HI VIBRATION TO 4.2 MILS OVER 15 SECONDS D 0 PFS 9 IMF FW145007C 4.2 15 0 The FAULTED step in this JPM is preceded by a fault statement in BOLD TYPE WITH ALL CAPITAL LETTERS. Verify Feedwater venturies as input to PlCSY Core Thermal Power Heat Balance IC-782 OR 183 for LOC-21 NRC Exam Locates correct procedure. References correct procedure section. Reviews prerequisites 'Critical Step

1. Critical Sequence Student Name: Page 3 of 15 Standard Obtains controlled copy of OP-145-00 Refers to section

2.5 Reviews

prerequisites - Eva1 Comments Form NTP-QA-31.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam As Given PERFORMANCE CHECKLIST I Page 4 of 15 Appl. To/JPM No.: 45.0P.004.151 - Action EVALUATOR CUE:

If necessary, Inform candidate that all prerequisites have been met. Reviews Precautions ChecWEstablish RFP C discharge pressure 50 - 100 psig below Reactor pressure as follows: Increase RFP/T C speed using RFP CSPD controller, AND Throttle FV 10604C using RX FEED PUMP C RECIRC FLOW FIC-10604C in MANUAL to maintain RFP C FLOW FI-lO604C indication greater RFP C MIN FLOW SET PT FI-10612C indication.

CTUDEMAND SIGNAL SIC-C32-1 R601 C Check RFP C discharge temperature approximately equal to in-service reactor feed pump discharge temperature as indicated on RFP DSCH TEMP TR-10608.

• Critical Step #Critical Sequence Student Name:

Standard Reviews Precautions Verifies:

RFP C discharge pressure is 50-1 00 psig below Reactor pressure Verifies: RFP DSCH TEMP TR-10608 reactor feed pump discharge temperatures are all approximately equal Comments Form NTP-QA-31.8-2.

Rev. 0, Page 1 of 1 2005 NRC Exam As Given Appl. To/JPM No.: 45.0P.004.151 Step 7 8 PERFORMANCE CHECKLIST Page 5 of 15 Action IF feeding with second feed pump and not already performed per GO-1 00-002, Ensure following:

RFP C START UP IS0 HV-10651 C CLOSED. RFP C DSCH IS0 HV-10603C OPEN by depressing OPEN push button. Perform following to feed Reactor Vessel with RFP C: IF placing a RFP in service with HWC in service in Power Determine Setpoint Mode, Restore a Hydrogen Injection string to service IAW HWC OPERATION When Placing Additional Reactor Feed Pump C In Service section of OP-145-002. EVALUATOR CUE: Role-play NPO and acknowledge the request. *Critical Step #Critical Sequence Student Name: Standard Verifies RFP C START UP IS0 HV-10651 C Red light - NOT LIT Amber Light - LIT AND RFP C DSCH IS0 HV-10603C Red light -LIT Amber Light - NOT LIT Contacts NPO to Restore a Hydrogen Injection string to service IAW HWC OPERATION When Placing Additional Reactor Feed Pump C In Service section of OP-145-002 Eva1 Comments Form NTP-QA-31.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam As Given Appl. To/JPM No.:

45.0P.004.151 - Step 9 10 PERFORMANCE CHECKLIST Page 6 of 15 Action Adjust RFP C SPD CTUDEMAND SIGNAL SIC- C32-1 R601 C controller to increase turbine speed until incoming pump just begins to feed. Monitor Reactor Vessel level to ensure it remains stable. FAULT STATEMENT When the candidate begins the next step, the Hi Vibration alarm will annunciate. The candidate should refer to the AR. *Critical Step #Critical Sequence Student Name: Standard Depresses INC pushbutton on : 1 R601 C controller RFP C SPD CTUDEMAND SIGNAL SIC-C32- Until FEEDFLOW is observed Monitors Reactor Vessel level to ensure it remains stable. - Eva1 Comments Form NTP-QA-31.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam As Given PERFORMANCE CHECKLIST Page 7 of 15 Appl. ToNPM No.: 45.0P.004.151 Student Name: BOOTH OPERATOR CUE: Insert PFS 9 IMF FW145007C 4.2 15 0 (4.7 mils 8 3240 rpm during validation) "C" RFP TURBINE HI VIBRATION TO 4.2 MILS OVER 15 SECONDS DO NOT INCREASE to 5 mils, this would require tripping of the pump. Monitor vibration, increase malfunction magnitude until alarm is received. Slowly Reduce RF P minimum flow by depressing RX FEED PUMP C RECIRC FLOW FIC-1 0604C CLOSE push button Refers to AR 101 -001 A1 6, RFPT A,B,C HI Vibration

• Critical Step #Critical Sequence Standard Depresses CLOSE push button on 10604C RX FEED PUMP C RECIRC FLOW FIC- Refers to AR 101 -001 A1 6, RFPT A,B,C HI Vibration Comments Form NTP-OA-31.8-2.

Rev. 0, Page 1 Of 1 2005 NRC Exam As Given PERFORMANCE CHECKLIST Page 8 of 15 Appl. To/JPM No.: 45.0P.004.151 Action Check alarm condition and trend on RFPT Reduce load on RFP to determine if vibration load related. IF vibration increases to 5 mils, THEN Ensure RFPT trips. IF alarm occurs during startup, THEN Reduce warmup rate of Turbine. Check bearing oil temperatures prior to trip to determine if oil temperature induced vibration. VIBRATION XRSH-12728. EVALUATOR CUE:

Role-play Unit supervisor and direct candidate to Shutdown RFP C IAW appropriate procedure.

Field report suggests unusual noises and vibrations at the RFP References correct procedure section. Reviews prerequisites

• Critical Step #Critical Sequence Student Name: Standard Verifies Vibration is rising to 4.2 mils on RFPT Depresses DEC pushbutton on : 1 R601 C controller VIBRATION XRSH-12728 RFP CSPD CTUDEMAND SIGNAL SIC-C32-AND Rechecks Vibration on RFPT VIBRATION XRSH-12728 Refers to OP-145-001 section 2.6 Reviews prerequisites Comments Form NTP-QA-31.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam As Given Appl. To/JPM No.: 45.0P.004.151 I PERFORMANCE CHECKLIST Page 9 of 15 Student Name: Action EVALUATOR CUE:

If necessary, Inform candidate that all prerequisites have been met. IF less than three reactor feed pumps will be in service, Direct Shift Technical Advisor to SELECT Feedwater venturies as input to PlCSY Core Thermal Power Heat Balance (OD3) in accordance with 01-TA-021, Selection of Feedwater Inputs for Calculation of Core Thermal Power. IF RFP A or B is to be shut down, Realign to the appropriate RFP OR Shut Down Depleted Zinc Oxide (DZO)

Injection System in accordance with OP-144-001.

Remove Hydrogen Injection String from service for Reactor Feed Pump being Shutdown IAW HWC System Power Operations section of OP- 145-002. EVALUATOR CUE: Role-play NPO and acknowledge the request. *Critical Step #Critical Sequence Standard Determines from initial conditions that Feedwater venturies are already selected as input to PlCSY Core Thermal Power Heat Balance. Determines this step to be N/A. Contacts NPO to Remove a Hydrogen Injection string to service IAW HWC OPERATION When Placing Additional Reactor Feed Pump C In Service section of OP-145-002 Comments Form NTP-QA-31.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam As Given Appl. To/JPM No.: 45.0P.004.151 PERFORMANCE CHECKLIST Page 10 of 15 Action Monitor Reactor Vessel level closely to insure Reactor Feed Pump(s) left in service will maintain reactor vessel level.

NOTE: A Recirculation Flow Controller FIC-10604 demand signal of - 40 will provide pump with adequate minimum flow. Place RFP C SPD CTUDEMAND SIGNAL SIC- C32-1 R601 C in MANUAL. Slowl! Adjust RX FEED PUMP C RECIRC FLOVl FIC-10604C in MANUAL to - 40% demand. *Critical Step #Critical Sequence Student Name: Standard Monitors Reactor Vessel level to ensure it remains stable.

Verifies:

1 R601 C RFP C SPD CTUDEMAND SIGNAL SIC-C32- Amber M light - LIT Verifies RX FEED PUMP C RECIRC FLOW FIC-10604C switch in M position AND Depresses OPEN Pushbutton on RX FEED PUMP C RECIRC FLOW FIC-10604C until - 40% demand is achieved. - Eva1 ~ Comments Form NTP-QA91.8-2, Rev. 0, Page 1 Of 1 2005 NRC Exam As Given Appl. To/JPM No.: 45.0P.004.151 Step 22 23 24 25 26 PERFORMANCE CHECKLIST Page 11 of 15 Student Name: ~ Action Slowly Decrease RFPn C speed using RFP C controller to obtain RFP C discharge pressure - 100 psig below reactor pressure; AND SPD CTL /DEMAND SIGNAL SIC-C32-1 R601 C Throttle FV 10604C using RX FEED PUMP RECIRC FLOW FIC-10604C in MANUAL to maintain RFP C FLOW FI-lO604C indication greater RFP C MIN FLOW SET PT FI-lO612C indication.

Monitor Rx Vessel level closely and Maintain level with in service pump(s).

IF Reactor Feed Pump to be placed in Standby on minimum flow during Low Load Operations, Perform following:

IF Reactor Feed Pump C to be trippedkhutdown:

Ensure Reactor Feed Pump C discharge pressure - 100 psig below Reactor pressure.

• Critical Step #Critical Sequence Standard Depresses DEC Pushbutton on controller Until RFP C discharge pressure is 50 100 psig below Reactor pressure RX FEED PUMP C RECIRC FLOW FIC-10604C Depresses Open/Close Pushbuttons on RX maintain RFP C FLOW FI-lO604C indication greater RFP C MIN FLOW SET PT FI-lO612C indication FEED PUMP C RECIRC FLOW FIC-10604C to Monitors Reactor Vessel level to ensure it remains stable. Determines step to be N/A Verifies:

RFP C discharge pressure is - 100 psig below Reactor pressure Eva1 Comments Form NTP-OA-31.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam As Given Appl. To/JPM No.: 45.0P.004.151 I Page 12 of 15 PERFORMANCE CHECKLIST Action Close/Check Closed RFP C DSCH IS0 HV- 10603C. Close/Check Closed RFP START UP IS0 HV- 10651 C. Ensure or Slowly Decrease turbine speed to EAP LOW SPEED STOP (- 1850 rpm), THEN *Critical Step #Critical Sequence Student Name: Standard Depresses CLOSED pushbutton on RFP C Verifies: Red light - NOT LIT Amber Light - LIT DSCH IS0 HV-10603C.

Verifies: RFP START UP IS0 HV-10651C. Red light - NOT LIT Amber Light - LIT Depresses DEC Pushbutton on: 1 R601 C controller Until RFP C turbine speed is at EAP LOW SPEED STOP (- 1850 rpm) RFP C SPD CTUDEMAND SIGNAL SIC-C32-Eva1 Comments FOtm NTP-QA91.8-2, Rev. 0, Page 1 Of 1 2005 NAC Exam As Given Appl. To/JPM No.: 45.0P.004.151 Step

• 30 - 31 I PERFORMANCE CHECKLIST Page 13 of 15 Action Trip RFPT C at RFPT C TRIP RESET HS- 12745C. At 1 C668, Observe following:

RFPT C LP IS0 HV-12709C CLOSES. RFPT C HP IS0 HV-12710C CLOSES. RFPT C FIRST STAGE DRN HV- 1271 7C OPENS. RFP C DSCH CKV HV-10606C CLOSES. *Critical Step #Critical Sequence Student Name: Standard Depresses TRIP pushbutton on: RFPT C TRIP RESET HS-1274%.

Verifies:

Red light - NOT LIT Amber Light - LIT Verifies:

Red light - NOT LIT Amber Light - LIT For the following valves: RFPT C LP IS0 HV-12709C RFPT C HP IS0 HV-1271OC RFP C DSCH CKV HV-10606C AND Red light - LIT Amber Light - NOT LIT 1271 7C RFPT C FIRST STAGE DRN HV- Eva1 - Comments Form NTP-QA-31.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam As Given PERFORMANCE CHECKLIST Page 14 of 15 Appl. To/JPM No.: 45.0P.004.151 Student Name: Action Fast Lower RFP C MTR SPD CHANGER, HS- 12730C1, to LOW SPEED STOP. Ensure RFPT C MTR SPD CHANGER at LOW SPEED STOP by only Amber (LSS) light ILLUMINATED above RFPT C MTR SPD CHANGER push buttons or locally on upper stop. NOTE: Decreasing (SIC-C32-1 R601 A,B,C) SPD CTUDEMAND SIGNAL to less than 'O', may cause RFPT Control Signal Failure to annunciate.

Ensure RFP C SPD CTUDEMAND SIGNAL SIC- C32-1 R601 C in MANUAL with speed output signal (horizontal meter) set at 0. *Critical Step #Critical Sequence Standard Depresses FAST pushbutton on: 12730C1 until: RFPT C MTR SPD CHANGER at LOW SPEED STOP AMBER (LSS) light - LIT LOWER RFP C MTR SPD CHANGER, HS- Verifies:

RFPT C MTR SPD CHANGER at LOW SPEED STOP AMBER (LSS) light - LIT Verifies:

1 R601 C Amber M light - LIT RFP C SPD CTUDEMAND SIGNAL SIC-C32-AND Speed output signal (horizontal meter) set at 0 Eva1 - Comments Form NTP-QA-31.8-2, Rev. 0. Page 1 of 1 2005 NRC Exam As Given Appl. To/JPM No.: 45.0P.004.151 PERFORMANCE CHECKLIST Page 15 of 15 Student Name: - Step

• 35 Action Standard Eva1 Comments Close FV 10604C using RX FEED PUMP C RECIRC FLOW FIC-10604C in MANUAL. EVALUATOR CUE: This completes the JPM Depresses CLOSE pushbutton on RX FEED PUMP C RECIRC FLOW FIC-10604C until it reaches zero demand. *Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam As Given TASK CONDITIONS A. Unit 1 is Q 48% power with a plant startup in progress.

6. RFP A and B are feeding the RPV in Automatic level control C. RFP C has been started and warmed, and is ready to feed the RPV. D. Feedwater venturies selected as input to PlCSY Core Thermal Power Heat Balance.

INITIATING CUE Commence feeding the RPV with RFP C IAW with the appropriate procedure.

_- 2005 NRC Exam As Given 1 of2 TASK CONDITIONS A. Unit 1 is 8 48% power with a plant startup in progress.

6. RFP A and B are feeding the RPV in Automatic level control C. RFP C has been started and warmed, and is ready to feed the RPV. D. Feedwater venturies selected as input to PICSY Core Thermal Power Heat Balance.

INITIATING CUE Commence feeding the RPV with RFP C IAW with the appropriate procedure.

2005 NRC Exam As Given 2 of 2 PPL SUSQUEHANNA, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET SIR0 73.0P.001.101 0 1014105 288000 A2.01 3.313.4 Apple JPM Number Rev. No. Date NUREG 1123 WA No. WA Imp. To Sys. No. Task Title: Vent the Drywell IAW OP-173-003 Completed By: Rich Chin lOl4105 Writer Date InstructorMlriter Date Approval: Nuclear Trng.

Supv. Date of Performance:

Date 15 Allowed Time (Min.) Time Taken (Min.) JPM Performed By: Student Name: Last First M.I. Employee # I S.S. # Performance ( ) Satisfactory ( ) Unsatisfactory Evaluation:

Evaluator Name: Signature Typed or Printed Comments:

Form NTP-QA-31.8-1, Rev. 0, Page I of 2 2005 NRC Exam As Given REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE S/RO 73.0P.001.101

1. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.

6. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example: 1. Whenever any electrical panel is opened for inspection during JPM performance.

2. Whenever entering any plant area where specific safety equipment; such as hearing or eye protection, safety shoes, hardhats, etc; is required and/or posted as being necessary.

C. If in the judgment of the evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved. D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required.

II. REFERENCES A. OP-173-003, Primary Containment Nitrogen Makeup And Venting (Rev. 9)

6. OP-070-001, Standby Gas Treatment System (Rev. 19)

II 1. REACTIVITY MAN I PULATIONS This JPM satisfies the requirements of Operational Activity(s):

None IV. TASK CONDITIONS A. B. Unit 1 is in Mode 1 Drywell pressure is 0.4 psig V. INITIATING CUE Your supervisor directs you to reduce Drywell pressure to 0.1 psig IAW OP-173-003, Primary Containment Nitrogen Makeup and Venting section 2.3. All prerequisites have been met.

All TFUS requirements are satisfied. VI. TASK STANDARD SGTS in operation, Drywell venting with pressure being reduced. VILTASK SAFETY SIGNIFICANCE Avoid an unnecessary high drywell pressure SCRAM. Form NTP-QA-3 1.8- 1, Rev. 0, Page 2 of 2 2005 NRC Exam As Given PERFORMANCE CHECKLIST Page 3 of 10 Appl. To/JPM No.: S/RO 73.0P.001.101 Student Name: - Step 1 2 3 Action EVALUATOR NOTE: 0 0 0 This JPM must be performed in the simulator.

Select any Mode 1 IC Secure Drywell cooling fans until Drywell pressure rises to 0.4 psig. Restart drywell cooling fans.

0 Place simulator in FREEZE. B When student is ready to begin JPM, place the simulator in RUN. (IC-182 or 183 for LOC-21 NRC Exam) Obtain controlled copy of OP-173-003, Primary Containment Nitrogen Makeup And Venting. Select the correct section to perform. Review the prerequisites and precautions. EVALUATOR CUE:

If necessary inform the student all prerequisites and precautions have been met. Standard Controlled copy obtained.

Selects section 2.3 Ensures all prerequisites and precautions have been met. Eva1 Comments *Critical Step #Critical Sequence Form NTP-QA-3 I .8-2, Rev. 0, Page I of 1 2005 NRC Exam As Given Appl. To/JPM No.: S/RO 73.0P.001.101 - Step 4 5 6 PERFORMANCE CHECKLIST Page 4 of 10 Action Manually Start SGTS in accordance with OP-070-001 Obtain controlled copy of OP-070-001, Standby Gas Treatment. EVALUATOR CUE:

Role-play the Unit Supervisor and instruct candidate to start the "A train of SGTS. Select the correct section to perform. Review the prerequisites and precautions. EVALUATOR CUE:

If necessary inform the student all prerequisites and precautions have been met. Student Name: Standard Controlled copy obtained.

Selects section 3.2 Ensures all prerequisites and precautions have been met. Eva1 Comments *Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0, Page I of 1 2005 NRC Exam As Given PERFORMANCE CHECKLIST Page 5 of 10 Appl. To/JPM No.:

S/RO 73.0P.001 .lo1 Action NOTE: HD 0755A remains open for approximately 70 seconds and HD 0755B remains open for approximately 120 seconds after their respective pushbuttons are released.

Steps 3.2.3 through 3.2.5 must be performed expeditiously to establish a flow path and allow SGTS to start. At Panel OC681, DEPRESS SGTS Clg OA Dmp HD07555A OPEN pushbutton. OBSERVE SGTS Clg OA Dmp HD07555A OPENS to allow suction flow path for start of SGTS Fan A. At Panel OC681, START Standby Gas Treatment System A by placing selector switch for SGTS Fan OV109A to START. Student Name:

Standard Depresses SGTS CLG OA DMP HD 07555A OPEN pushbutton.

Verifies:

SGTS CLG OA DMP HD 07555A Amber light - NOT LIT Red light - LIT Places selector switch for SGTS FAN OV109A to START Verifies:

Amber light - NOT LIT Red light - LIT - Eva1 Comments *Critical Step #Critical Sequence Form NTP-QA-3 1.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam As Given PERFORMANCE CHECKLIST Page 6 of 10 Appl. To/JPM No.: S/RO 73.0P.001.101 - Step 10 11 Action When Fan starts, OBSERVE flow increases >3000 CFM on SGTS Air Flow FR07553A. EVALUATOR NOTE: SGTS Fans may not obtain 10,100 CFA, due to insufficient suction flow path through SGTS Makeup OA Dmp FD07551 A2. EVALUATOR NOTE: Flowrate for this JPM should be (-4,800 CFM) Check SGTS Makeup OA Dmp FD07551A2 MODULATED/OPEN approximately 70 seconds after SGTS Fan OV109A started. Student Name: Standard Verifies:

SGTS AIR FLOW FR-07553A increases to greater than 3000 CFM. Approximately 70 seconds after SGTS Fan OV109A started. Verifies:

SGTS Makeup OA DMP FD 07551A2 Amber light - LIT Red light - LIT 7 Eva1 Comments *Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0, Page I of 1 2005 NRC Exam As Given Appl. To/JPM No.: SIR0 73.0P.001.101 Step 12 13 14 15 PERFORMANCE CHECKLIST Page 7 of 10 Action CHECK following positioned as indicated: SGTS Fan Inlet Dmp HD07552A FULL OPEN. SGTS A Inlet Dmp HD07553A FULL OPEN.

Refers to appropriate venting procedure.

Ensure Drywell pressure does not become >0.5 psig below suppression chamber pressure, to prevent opening vacuum breakers.

• Critical Step #Critical Sequence Form NTP-QA-3 1.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam As Given Student Name: Standard Verifies:

SGTS FAN INLET DMP HD 07552A Amber light - NOT LIT Red light - LIT Verifies:

SGTS A INLET DMP HD 07553A Amber light - NOT LIT Red light - LIT Refers to OP-173-003 section

2.3.5 Checks

drywell pressure and determines N/A for current conditions. - Eva1 Comments PERFORMANCE CHECKLIST Page 8 of 10 Appl. To/JPM No.: S/RO 73.0P.001 .lo1 Student Name: - Step 16 Action NOTE: If pressure decreased to low pressure alarm setpoint (approximately 0.1 psig), pressure will have to be increased to approximately 0.5 psig to reset alarm. EVALUATOR CUE: Role-play the Unit Supervisor and inform the candidate that it will not be necessary to actually log the vent start time in the next step. Log vent start time in Unit 1 Log. EVALUATOR NOTE:

HD17508A & B are on back panel lC681 HV 15713 & HV 1571 1 are on front panel 1C601 Standard N/A Comments *Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam As Given i PERFORMANCE CHECKLIST Page 9 of 10 Appl. To/JPM No.: S/RO 73.0P.001.101 Student Name: Action HV HV Open following:

HD17508A DRWUWETWELL BURP DMP HD17508B DRWUWETWELL BURP DMP 5713 DRWL VENT IB IS0 571 1 DRWL VENT BYPS OB IS0 Standard Places Control switches for the following to the OPEN position:

HD17508A DRWUWETWELL BURP DMP HD17508B DRWUWETWELL BURP DMP HV 1571 3 DRWL VENT IB IS0 HV 15711 DRWL VENT BYPS OB IS0 AND Verifies:

Amber lights - NOT LIT Red lights - LIT Comments *Critical Step #Critical Sequence Form NTP-QA-3 I .8-2, Rev. 0, Page 1 of 1 2005 NRC Exam As Given Appl. To/JPM No.: SIR0 73.0P.001.101 Step 18 PERFORMANCE CHECKLIST Page 10 of 10 Action Monitor Drywell Pressure using any of the following: Computer point MAP01 or MAP001Z PlCSY screen CONTN PI 15702 CONTN OR SUPP CHMBR PRESS with selector switch HSS 15702 selected to CONTN EVALUATOR CUE:

This completes the JPM Student Name: Standard Determines Drywell pressure is dropping by checking:

Computer point MAP01 or MAP001 Z AND/OR PlCSY screen CONTN AND/OR PI 15702 CONTN OR SUPP CHMBR PRESS with selector switch HSS 15702 selected to CONTN Comments *Critical Step #Critical Sequence FormNTP-QA-31.8-2.

Rev. 0. Page 1 of 1 2005 NRC Exam As Given TASK CONDITIONS A. Unit 1 is in Mode 1 6. Drywell pressure is 0.4 psig INITIATING CUE Your supervisor directs you to reduce Drywell pressure to 0.1 psig IAW OP-173-003, Primary Containment Nitrogen Makeup and Venting section 2.3. All prerequisites have been met.

All TWTS requirements are satisfied.

2005 NRC Exam As Given Page 1 of 2 TASK CONDITIONS A. Unit 1 is in Mode 1 B. Drywell pressure is 0.4 psig INITIATING CUE Your supervisor directs you to reduce Drywell pressure to 0.1 psig IAW OP-173-003, Primary Containment Nitrogen Makeup and Venting section 2.3. All prerequisites have been met. All TFUTS requirements are satisfied.

Page 2 of 2 2005 NRC Exam As Given PPL SUSQUEHANNA, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET SIR0 55.0P.007.001 1 1015105 201 001 A2.07 3.213.1 APPl- JPM Number Rev. No. Date NUREG 1123 KIA No. KIA Imp. To Sys. No. Task Title: Completed By: Validated Shift The CRD Flow Stations From A To B In Accordance With OP-255-001 Task Title: Completed By: Validated Shift The CRD Flow Stations From A To B In Accordance With OP-255-001 Rich Chin 1015105 Writer Date InstructorNVriter Date Approval:

Nuclear Trng. Supv. Date of Performance:

~~ Date 20 Validation Time (Min.) Time Taken (Min.) JPM Performed By: Student Name: Last First M.I. Employee #I S.S. # Performance Evaluation: ( ) Satisfactory ( ) Unsatisfactory Evaluator Name: Signature Typed or Printed Comments:

FormNTP-QA-31.8-1, Rev. 0, Page 1 of 2 2005 NRC Exam As Given REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE S/RO 55.0P.007.001

1. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.

B. All applicable safety precautions shall be taken in accordance with established PP&L safety policies and the Safety Rule Book, for example: 1. Whenever any electrical panel is opened for inspection during JPM performance.

2. Whenever entering any plant area where specific safety equipment; such as hearing or eye protection, safety shoes, hardhats, etc; is required and/or posted as being necessary.

C. If in the judgment of the evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.

D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required.

II. REFERENCES OP-255-001 , Control Rod Drive Hydraulic System (Rev. 35)

I II . RE ACTIVITY MAN I PU LATlO N S This JPM satisfies the following Operational Activity(s):

None IV. TASK CONDITIONS A. Unit 2 is at 80 percent reactor power. B. While adjusting Control Rods per Reactor Engineering Instructions, it is noted that the "A CRD Flow Control station is not responding properly.

C. The "B CRD Flow Control Station needs to be placed in service so that I&C can investigate.

V. INITIATING CUE Swap CRD flow control stations from CRD DRIVE WATER HEADER FLOW VALVE FV-2F002A to CRD DRIVE WATER HEADER FLOW VALVE FV-ZFOOZB.

VI. TASK STANDARD CRD DRIVE WATER HEADER FLOW VALVE FV-2FOO2B in service and CRD DRIVE WATER HEADER FLOW VALVE FV-2F002A removed from service VII. TASK SAFETY SIGNIFICANCE Provide reliable drive water flow to the control rod drive mechanisms Form NTP-QA-3 1 .%I, Rev. 0, Page 2 of 2 2005 NRC Exam As Given PERFORMANCE CHECKLIST Appl. To/JPM No.: S/RO 55.0P.007.001 Page3of 14 Student Name: Action EVALUATOR NOTE: With the A flow control station in service the following conditions exist:

0 M/A-2D009A is in auto. 0 Closed and Open position indicator lights for FCV are illuminated.

0 WA-2D009B is in MAN. 0 FCV B closed light is ILLUMINATED and the open light is EXTINGUISHED.

Obtain a controlled copy of OP-255-001.

Select the correct section to perform. Review the prerequisites. EVALUATOR CUE: Inform the student that all prerequisites have been met. *Critical Step #Critical Sequence Standard Obtains controlled copy. Selects Section 2.4. Ensures prerequisites are met. Eva1 Comments Form NTP-QA-31.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam As Given Appl. To/JPM No.: S/RO 55.0P.007.001 Step 4 5 Action NOTE Following steps change from Flow Control Valve FV-2F002A to FV-2FOO2B.

To change from valve B to A, use valves in parentheses.

Ensure FC-Cl2-2R600, CRD Flow Controller, in AUTO EVALUATOR CUE: FIC-Cl2-2R600 is located on Panel 2C601 in the Control Room. Role-play the control room and inform the candidate that the controller is in automatic. Ensure M/A-2D009B Man/Auto Station Control Valve B controller in MAN with Red pen indicating

0. Red pen displays MANUAL demand on the local controller.

• Critical Step #Critical Sequence Page 4 of 14 PERFORMANCE CHECKLIST Student Name: Standard Calls the Control Room and confirms that is in AUTO. CRD FLOW CONTROLLER FIC-Cl2-2R600 Verifies: M/A-2D009B Man/Auto Station in MAN AND Red pen is at

0. - Eva1 Comments Form NTP-QA-31.8-2, Rev. 0, Page I of 1 2005 NRC Exam As Given Appl. To/JPM No.: S/RO 55.0P.007.001 Action EVALUATOR CUE:

M/A-2D009B Man/Auto Station in MAN AND Red pen is at 0. Ensure FV-2F002B CLOSED, as indicated by Position Indicator Flow Control Valve B Amber light ILLUMINATED AND Red light EXTl NGU I SH ED. EVALUATOR CUE:

Amber light LIT Red light NOT LIT Ensure 246F0468, Flow Control Valve B Iso, OPEN. *Critical Step #Critical Sequence PERFORMANCE CHECKLIST Page 5 of 14 Student Name: Standard Verifies: Position Indicator Flow Control Valve B Amber light LIT Red light NOT LIT Rotates: Flow Control Valve B Is0 246F046B handwheel CLOCKWISE until valve stem moves in close direction then rotates handwheel COUNTER CLOCKWISE until valve stem is returned to full open. Eva1 - Comments Form NTP-QA-31.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam As Given Appl. To/JPM No.: S/RO 55.0P.007.001 Action EVALUATOR CUE:

Inform the candidate that the valve is FULL COUNTER CLOCKWISE NOTE To prevent large (20 to 25 gpm) flow changes, following step should be performed very slowly. EVALUATOR CUE:

In the next step, as the candidate begins opening the valve, provide a cue that an audible sound can be heard coming from the flow through the pipe. AFTER candidate stops moving valve, provide cue that the Audible sound change has STOPPED. Slowly Crack Open Flow Control Valve B Is0 246F047B.

• Critical Step #Critical Sequence Page 6 of 14 PERFORMANCE CHECKLIST Student Name: Standard Very slowly rotates: Flow Control Valve B Is0 246F047B handwheel COUNTER CLOCKWISE until flow is established.

Eva1 Comments Form NTP-QA-3 1.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam As Given PERFORMANCE CHECKLIST Appl. To/JPM No.: S/RO 55.0P.007.001 - Step 9 10 Action Observe following, indicating flow stabilized: Audible sound change has STOPPED WA-2D009A Man/Auto Station Control Valve A Black pen STABLE. The black pen displays control room demand. Flow Control Station Total Water Flow FI- 2R019 - 63 gpm. EVALUATOR CUE: Audible sound change has STOPPED. M/A-2D009A Man/Auto Station Control Valve A Black pen STABLE. Flow Control Station Total Water Flow FI- 2R019 - 63 gpm. WHEN stable flow indicated, THEN Fully Open 246F0478, Flow Control Valve B Iso. EVALUATOR CUE:

Flow Control Valve B Is0 246F047B is full COUNTER CLOCKWISE

• Critical Step #Critical Sequence Student Name: Standard Page 7 of 14 Verifies: Audible sound change has STOPPED. WA-2D009A Man/Auto Station Control Valve A Black pen STABLE. Flow Control Station Total Water Flow FI- 2R019 - 63 gpm. Rotates: Flow Control Valve B Is0 246F047B handwheel COUNTER CLOCKWISE until full open is reached. - Eva1 Comments Form NTP-QA-31.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam As Given Appl. To/JPM No.: SIR0 55.0P.007.001 - Step *11 - Action EVALUATOR NOTE In the next step Flow Control Valve A will go in the closed direction as Flow Control Valve B is opened. Both indicating lights for both valves will be LIT during this transition.

Slowly Rotate the manual adjust knob on WA- 2D009B Man/Auto Station Control Valve UNTIL Black and red pens CLOSELY MATCHED as possible EVALUATOR CUE: WA-2D009B Man/Auto Station Control Valve Black and red pens are MATCHED, Amber and Red lights are BOTH - LIT *Critical Step PERFORMANCE CHECKLIST Page 8 of 14 Student Name: Standard Slowly Rotates:

Manual adjust knob on WA-2D009B Man/Auto Station Control Valve UNTIL Black and red pens CLOSELY MATCHED as possible. #Critical Sequence Eva1 Comments Form NTP-QA-31.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam As Given PERFORMANCE CHECKLIST Page 9 of 14 Appl. To/JPM No.: S/RO 55.0P.007.001 Step 12 - Action Observe following indicating flow stabilized: Audible sound change STOPPED. WA-2D009A Man/Auto Station Control Valve A Black pen DECREASES AND STABILIZES Flow Control Station Total Water Flow FI- 2R019 2R019 - 63 gpm EVALUATOR CUE: Audible sound change HAS STOPPED. WA-2D009A Man/Auto Station Control Valve A Black pen DECREASED AND IS NOW STAB I LE. Flow Control Station Total Water Flow FI- 2R019 2R019 - 63 gpm. EVALUATOR NOTE: Nothing will occur when this step is performed. The candidate should match these needles as closely as possible. The closer the match the smaller the change when the controller is placed in manual later.

• Critical Step #Critical Sequence Student Name: Standard Observes the following indicating flow stabilized: Audible sound change STOPPED. WA-2D009A Man/Auto Station Control Valve A Black pen DECREASES AND STAB I LI ZES . Flow Control Station Total Water Flow FI-2R019 2R019 - 63 gpm. Eva1 Comments Form NTP-QA-31.8-2, Rev. 0. Page 1 of 1 2005 NRC Exam As Given Appl. To/JPM No.: S/RO 55.0P.007.001 Step 13 14 15 Action Slowly Rotate manual adjust knob on M/A- 2D009A Man/Auto Station Control Valve until Black and Red pens CLOSELY MATCHED. EVALUATOR CUE: WA-2D009A Man/Auto Station Pens are matched. Ensure Flow Control Station Total Water Flow FI-2R019 - 63 gpm and stable EVALUATOR CUE:

Total Water Flow FI-2R019 is 63 gpm and STABLE Place WA-2D009A Man/Auto Station Control Valve A control switch to MAN. *Critical Step #Critical Sequence PERFORMANCE CHECKLIST Page 10 of 14 Student Name: Standard Slowly Rotates: Manual adjust knob on M/A-2D009A Man/Auto Station Control Valve CLOCKWISE until Black and Red pens CLOSELY MATCHED.

Verifies:

Flow Contr I Station T tal Water Flow FI- 2R019 - 63 gpm and stable. Rotates: WA-2D009A Man/Auto Station Control Valve A control switch CLOCKWISE to MAN. - Eva1 Comments Form NTP-QA-3 1.8-2. Rev. 0, Page 1 of 1 2005 NRC Exam As Given Appl. To/JPM No.: S/RO 55.0P.007.001 Action EVALUATOR CUE: M/A-2D009A Man/Auto Station is in MAN Place M/A-2D009B Man/Auto Station Control Valve B control switch to AUTO. EVALUATOR CUE: M/A-2D009B Man/Auto Station is in AUTO Slowly Rotate manual adjust knob on M/A- 2D009A Man/Auto Station Control Valve A UNTIL Red pen indicates

0. *Critical Step #Critical Sequence PERFORMANCE CHECKLIST Page 11 of 14 Student Name: Standard Rotates: WA-2D009B Man/Auto Station Control Valve B control switch CLOCKWISE to AUTO. Slowly Rotates:

Manual adjust knob on WA-2D009A Man/Auto Station Control Valve A COUNTER CLOCKWISE UNTIL Red pen indicates

0. AND Verifies:

Position Indicator Flow Control Valve A Red light-NOT LIT. Eva1 Comments Form NTP-QA-3 1.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam As Given Appl. To/JPM No.: S/RO 55.0P.007.001 Action EVALUATOR CUE: WA-2D009A Man/Auto Station Red pen is at 0 AND Position Indicator Flow Control Valve A Red light is NOT LIT. Ensure Flow Control Station Total Water Flow FI-2R019 - 63 gpm and stable. EVALUATOR CUE:

Total Water Flow FI-2R019 is 63 gpm and STABLE NOTE To prevent large (20 to 25 gpm) flow changes, following step should be performed very slowly. *Critical Step PERFORMANCE CHECKLIST Page 12 of 14 Student Name:

Standard Ensure Flow Control Station Total Water Flow FI-2R019 - 63 gpm and stable. - Eva1 ~ ~~ Comments #Critical Sequence Form NTP-QA-31.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam As Given f Appl. To/JPM No.: S/RO 55.0P.007.001 Step 19 20 Action Slowly Close Flow Control Valve A Is0 246F047A. EVALUATOR CUE:

Flow Control Valve A Is0 246F047A valve is FULL CLOCKWISE IF the in-service CRD Flow Control Valve, FV-2F002B is at a mid-position and dual indication is not indicated, THEN Perform the following at panel 2C601 EVALUATOR CUE:

Position Indicator Flow Control Valve A Red light-NOT LIT. Red light and Amber light - LIT *Critical Step #Critical Sequence PERFORMANCE CHECKLIST Page 13 of 14 Student Name: Standard Slowly Rotates:

Flow Control Valve A Is0 246F047A valve handwheel CLOCKWISE until full closed is reached Verifies the following indicating lights for FV-2F002A : Position Indicator Flow Control Valve A Red light-NOT LIT. Red light and Amber light - LIT AND Determines no additional actions needed Eva1 Com men ts Form NTP-QA-3 1.8-2, Rev. 0, Page I of 1 2005 NRC Exam As Given 1 Appl. To/JPM No.: S/RO 55.0P.007.001 Action Check following for normal CRD System parameters:

EVALUATOR CUE: Flow Control Station Total Water Flow FI- 2R019 is 63 gpm. Downstream P-C/Rea Differential Pressure PDI-2R005 is 40 psid. Upstream P-C/Rea Differential Pressure PDI-2R009 is 250 psig. EVALUATOR CUE:

This completes the JPM. *Critical Step #Critical Sequence Page 14 of 14 PERFORMANCE CHECKLIST Student Name: ~ Standard Check following for normal CRD System parameters:

0 Flow Control Station Total Water Flow FI-2R019 - 63 gpm. 0 Downstream P-C/Rea Differential Pressure PDI-2R005

< 50 psid. Upstream P-C/Rea Differential Pressure PDI-2R009 - 250 psig.

Eva1 Comments Form NTP-QA-31.8-2, Rev. 0, Page 1 of I 2005 NRC Exam As Given TASK CONDITIONS:

A. Unit 2 is at 80 percent reactor power.

B. While adjusting Control Rods per Reactor Engineering Instructions, it is noted that the "A CRD Flow Control station is not responding properly.

C. The "B" CRD Flow Control Station needs to be placed in service so that I&C can investigate.

INITIATING CUE: Swap CRD flow control stations from CRD DRIVE WATER HEADER FLOW VALVE FV- 2F002A to CRD DRIVE WATER HEADER FLOW VALVE FV-2FOO2B.

2005 NRC Exam As Given Page 1 of 2 TASK CONDITIONS:

A. Unit 2 is at 80 percent reactor power.

B. While adjusting Control Rods per Reactor Engineering Instructions, it is noted that the "A CRD Flow Control station is not responding properly.

C. The "B CRD Flow Control Station needs to be placed in service so that I&C can investigate.

INITIATING CUE: Swap CRD flow control stations from CRD DRIVE WATER HEADER FLOW VALVE FV- 2F002A to CRD DRIVE WATER HEADER FLOW VALVE FV-2FOO2B.

2005 NRC Exam As Given Page 2 of 2 PPL SUSQUEHANNA, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET SIR0 50.0P.004.152 2 1015105 29501 6 AA1.06 4.014.1 APPl. JPM Number Rev. No.

Date NUREG 1123 KIA No. WA Imp. To Sys. No. Task Title: Establish and Maintain Reactor Vessel Level (RCIC Not Injecting) from the RSDP Using the Trip and Throttle Valve Completed By: Validated Rich Chin 1015105 Writer Date InstructorNVriter Date Approval: Nuclear Trng.

Supv. Date 20 Date of Performance: Validation Time (Min.) Time Taken (Min.) JPM Performed By: Student Name: Last First M.I. Employee # I S.S. # Performance ( ) Satisfactory ( ) Unsatisfactory Evaluation:

Evaluator Name: Signature Typed or Printed Comments:

Form NTP-QA-31.8-1, Rev. 0, Page 1 of 2 2005 NRC Exam As Given REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE S/RO 50.0P.004.152

1. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.

B. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example: 1. Whenever any electrical panel is opened for inspection during JPM performance.

2. Whenever entering any plant area where specific safety equipment; such as hearing or eye protection, safety shoes, hardhats, etc; is required and/or posted as being necessary.

C. If in the judgement of the evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.

D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required.

II. REFERENCES OP-150-001, RClC System (Revision

24) 111. REACTIVITY MANIPULATIONS This JPM satisfies the requirements of Operational Activity(s):

39 RClC Manual Start IV. TASK CONDITIONS A. B. C. D. E. F. G. A condition has occurred requiring abandonment of the Control Room. All required immediate operator actions of ON-100-009, Control Room Evacuation have been completed prior to abandoning the Control Room. Transfer switch positions have been changed on the RSDP IAW ON-100-009, Control Room Evacuation Section

4.3. Reactor

vessel wide range water level is 0 inches and lowering.

Reactor pressure is being maintained by SRVs cycling. RClC is not running. There has been no initiation signal. All personnel have been evacuated from RClC pump room and RClC pipe areas 670' Reactor Building V. INITIATING CUE Manually initiate RClC and inject at 625 gpm to restore RPV water level. VI. TASK STANDARD RClC started and feeding the reactor vessel at 625 gpm. VII. TASK SAFETY SIGNIFICANCE Provides cooling water to the reactor core. Form NTP-QA-31.8-1, Rev. 0, Page 2 of 2 2005 NRC Exam As Given Form NTP-QA-31.8-1, Rev. 0, Page 2 of 2 2005 NRC Exam As Given Appl. To/JPM No.: 50.0P.004.152 - Step 1 2 3 4 PERFORMANCE CHECKLIST Page 3 of 11 Action EVALUATOR NOTE: 0 The FAULTED step in this JPM is preceded by a fault statement in BOLD TYPE WITH ALL CAPITAL LETTERS. Obtain a controlled copy of OP-150-001, RClC System Selects the correct section to perform. Review the prerequisites. EVALUATOR CUE:

Inform the student all prerequisites I ,ave been met. Review all precautions.

• Critical Step #Critical Sequence Student Name: Standard c- Controlled copy obtained.

Selects section 2.1 5 Ensures all prerequisites have been met. Follows all precautions as applicable.

Eva1 - Comments Form NTP-QA-31.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam As Given Appl. To/JPM No.: 50.0P.004.152 PERFORMANCE CHECKLIST Page 4 of 11 Student Name: Action EVALUATOR NOTE: Following interlocks are defeated for RClC when controlled from remote shutdown panel:

Isolations For HV-149-FO07 AND HV-149-FO08 All Turbine Trips Except Overspeed (1 10% 8, 124%) AND Manual Exhaust Line Vacuum Breaker Isolations RClC Auto Initiations RClC Turbine Shutdown On High Level 8

(+54") Min Flow To Supp Pool HV-149-FO19 Operation On Hi/Low Flow Auto Suction Transfer From CST To Supp Pool On Low CST Level Steam Admission Valve HV-150-FO45 With RClC Turbine Exhaust Valve HV-150-FO59 Closed OBSERVE ES-14901 RClC STATIC INVERTER light ILLUMINATED.

• Critical Step #Critical Sequence Standard Verifies:

RClC STATIC INVERTER 120V AC OUT AVAILABLE Green Light - LIT Comments Form NTP-QA-31.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam As Given Appl. To/JPM No.: 50.0P.004.152 PERFORMANCE CHECKLIST Page 5 of 11 Action EVALUATOR CUE:

ES-14901 RClC STATIC INVERTER Green Light - LIT ENSURE RClC TURBINE FLOW CONTROLLER FIC-14903 in AUTO set at 625 SPm. EVALUATOR CUE:

RClC TURBINE FLOW CONTROLLER FIC-14903 in AUTO set at 625 gpm. EVALUATOR NOTE:

Once RClC is operating, pump room and pipe areas may be accessed again.

If time permits, EVACUATE personnel from RClC pump room and RClC pipe areas 670' Reactor Building prior to pump start. *Critical Step #Critical Sequence Student Name: Standard Verifies:

RClC TURBINE FLOW CONTROLLER FIC-14903 in AUTO set at 625 gpm. Determines:

From initial conditions that this has already been completed.

Comments Form NTP-QA-31.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam As Given Appl. To/JPM No.: 50.0P.004.152 PERFORMANCE CHECKLIST Page 6 of 11 Student Name: *Critical Step Action EVALUATOR NOTE: If malfunction of FIC-1 4903 is observed, proceed to 2.1 5.7 to place RClC in service using Trip & Throttle Valve HV-15012.

FAULT STATEMENT WHEN RClC CONTROLLER IS PLACED IN MANUAL, IT WILL NOT ADJUST TO ZERO "0." PLACE RClC TURBINE FLOW CONTROLLER FIC-14903 in MANUAL set for minimum speed. EVALUATOR CUE: RClC TURBINE FLOW CONTROLLER FIC-14903 output signal is STILL at 100% #Critical Sequence Standard Places: RClC TURBINE FLOW CONTROLLER FIC-14903 in MANUAL AND Depresses CLOSE pushbutton AND Verifies: Output signal decreasing to ZERO Comments Form NTP-QA-31.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam As Given PERFORMANCE CHECKLIST Page 7 of 11 Appl. To/JPM No.: 50.0P.004.152 Step 9 - 10 Action When the controller will not adjust to zero, leave Section 2.1 5.6 and go to Section 2.1 5.7. EVALUATOR NOTE: Once RClC is operating, pump room and pipe areas may be accessed again. If time permits, EVACUATE personnel from RClC pump room and RClC pipe areas 670 Reactor Building prior to pump start.

EVALUATOR NOTE: RClC turbine can be operated utilizing trip and throttle valve if governor valve is in open position.

This could be caused by failure in hydraulic control circuit such as loss of control signal. Loss of control signal will fail governor valve full open and could be caused by inverter failure or loss of power. Time spent in this condition of operation should be limited until full automatic control regained.

• Critical Step #Critical Sequence Student Name: Standard Select Section 2.1 5.7. Determines:

From initial conditions that this has already been completed.

Comments Form NTP-QA-31.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam As Given Appl. To/JPM No.: 50.0P.004.152 PERFORMANCE CHECKLIST Page 8 of 11 Action For manual startup using trip and throttle valve: CLOSE TURBINE TRIP AND THROTTLING HV-15012.

EVALUATOR CUE: HV-15012 Amber light - LIT and Red light NOT LIT OPEN STEAM TO RClC TURBINE HV-150-FO45. EVALUATOR CUE:

HV-150-FO45 Amber light - NOT LIT and Red light - LIT *Critical Step #Critical Sequence Student Name: Standard Places and HOLDS control switch HV-15012 to CLOSE UNTIL Amber light - LIT and Red light NOT LIT Places control switch HV-150-FO45 to OPEN Verifies:

Amber light - NOT LIT and Red light - LIT Eva1 Comments Form NTP-QA-31.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam As Given Appl. To/JPM No.: 50.0P.004.152 - Step 13 14 PERFORMANCE CHECKLIST Page 9 of 11 Action START RClC BARO CDSR VACUUM PP 1 P219. EVALUATOR CUE:

RClC BAR0 CDSR VACUUM PP 1 P219 Amber light - NOT LIT and Red light - LIT ENSURE MIN FLOW TO SUPP POOL FV-149-FO19 OPEN. EVALUATOR CUE:

FV-149-FO19 Amber light - NOT LIT and Red light - LIT *Critical Step #Critical Sequence Student Name: Standard Places control switch RClC BARO CDSR VACUUM PP 1 P219 to START Verifies:

Amber light - NOT LIT and Red light - LIT Verifies:

FV-149-FO19 Amber light - NOT LIT and Red light - LIT Comments Form NTP-QA91.8-2, Rev. 0, Page I of 1 2005 NRC Exam As Given Appl. To/JPM No.: 50.0P.004.152 Page 10 of 11 PERFORMANCE CHECKLIST

~ Action OPEN RClC INJECTION HV-149-F013. EVALUATOR CUE:

HV-149-F013 Amber light - NOT LIT and Red light - LIT INCREASE speed by throttling TURBINE TRIP AND THROTTLING HV-15012 until desired flow obtained.

• Critical Step #Critical Sequence Student Name: Places control switch HV-149-F013 to OPEN Verifies:

Amber light - NOT LIT and Red light - LIT Intermittently places control switch HV-15012 to OPEN Verifies:

HV-15012 Amber light - LIT and Red light - LIT AND RClC PUMP INJECTION FLOW (FI-14903) rising to 625 gpm. Eva1 ~~ Comments Form NTP-QA-31.8-2, Rev. 0. Page 1 of 1 2005 NRC Exam As Given Appl. To/JPM No.: 50.0P.004.152 Page 11 of 11 PERFORMANCE CHECKLIST Action EVALUATOR CUE:

HV-15012 Amber light - LIT and Red light - LIT FI-14903 indicates 625 gpm. When RClC flowrate above 250 gpm, CLOSE MIN FLOW TO SUPP POOL FV-149-FO19. EVALUATOR CUE:

FV-149-FO19 Amber light -LIT and Red light - NOT LIT EVALUATOR CUE: That completes this JPM *Critical Step #Critical Sequence Student Name: Standard Places control switch HV-149-FO19 to CLOSE and Verifies:

Amber light -LIT and Red light - NOT LIT Eva1 - Comments Form NTP-QA-31.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam As Given TASK CONDITIONS A. A condition has occurred requiring abandonment of the Control Room. B. All required immediate operator actions of ON-100-009, Control Room Evacuation have been completed prior to abandoning the Control Room. C. Transfer switch positions have been changed on the RSDP IAW ON-100-009, Control Room Evacuation Section 4.3. D. Reactor vessel wide range water level is 0 inches and lowering.

E. Reactor pressure is being maintained by SRVs cycling. F. RClC is not running. There has been no initiation signal. G. All personnel have been evacuated from RClC pump room and RClC pipe areas 670' Reactor Building INITIATING CUE Manually initiate RClC and inject at 625 gpm to restore RPV water level. 2005 NRC Exam As Given 1 of2 TASK CONDITIONS A. A condition has occurred requiring abandonment of the Control Room. B. All required immediate operator actions of ON-100-009, Control Room Evacuation have been completed prior to abandoning the Control Room. C. Transfer switch positions have been changed on the RSDP IAW ON-100-009, Control Room Evacuation Section 4.3. D. Reactor vessel wide range water level is 0 inches and lowering.

E. Reactor pressure is being maintained by SRVs cycling. F. RClC is not running. There has been no initiation signal. G. All personnel have been evacuated from RClC pump room and RClC pipe areas 670' Reactor Building INITIATING CUE Manually initiate RClC and inject at 625 gpm to restore RPV water level. 2005 NRC Exam As Given 2 of 2 PPL SUSQUEHANNA, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET SIR0 24.0P.001.007 0 10/5105 264000 A2.09 3.71 4.1 APPl. JPM Number Rev.

No. Date NUREG 1123 WA No. WA Imp. To Sys. No. Task Title:

Transfer of DG "E" for DG "C" Completed By: Validated Rich Chin 10/5/05 Writer Date InstructorNVriter Date Approval: Nuclear Trng.

Supv. Date of Performance:

20 Validation Time (Min.) Time Taken (Min.) JPM Performed By: Student Name: Last First M.I. Employee # / S.S. # Performance ( ) Satisfactory ( ) Unsatisfactory Eva1 ua t ion : Evaluator Name: Signature Typed or Printed Comments:

Form NTF-QA-3 1.8-1, Rev. 0, Page 1 of 2 2005 NRC Exam As Given REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE S/RO 24.0P.001.007

1. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.

B. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example: 1. Whenever any electrical panel is opened for inspection during JPM performance.

2. Whenever entering any plant area where specific safety equipment; such as hearing or eye protection, safety shoes, hardhats, etc; is required and/or posted as being necessary.

C. If in the judgment of the evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.

D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required.

II. REFERENCES A. OP-024-004, TRANSFER AND TEST MODE OPERATIONS OF DIESEL GENERATOR E Attachment C (Revision 25) [Steps 1 and 2 signed as being completed]

I II . REACTIVITY MAN1 PU LATIONS This JPM satisfies the requirements of Operational Activity(s):

None IV. TASK CONDITIONS A. Both Units were at 100% Steady State Power B. A Station Blackout occurred C. The "A and "B Diesel generators were started LOCALLY D. The control room crew is performing Unit l(2) Response to Station Blackout EO-1 OO(200)-030, E. To facilitate two diesels in same division operating, the control room is attempting to energize the "C' bus using the "E DIESEL GENERATOR.

F. Another operator is at the "E DG and has already performed steps 1 and 2 of OP-024-004, TRANSFER AND TEST MODE OPERATIONS OF DIESEL GENERATOR E Attachment C. V. INITIATING CUE Prepare the "C" DG for Transfer by performing steps 3 through 11 of OP-024-004, TRANSFER AND TEST MODE OPERATIONS OF DIESEL GENERATOR E Attachment C. VI. TASK STANDARD C D/G removed from service, and E D/G ready to supply power to C ESS busses (IAW steps 3 - 11 of OP-024-004 attachment C)

VILTASK SAFETY SIGNIFICANCE Provide redundant power supply to safety related equipment.

Form NTP-QA-31.8-1, Rev. 0, Page 2 of 2 2005 NRC Exam As Given Appl. To/JPM No.:

S/RO 24.0P.001.007 PERFORMANCE CHECKLIST Student Name: Action Obtain a controlled copy of OP-024-004, TRANSFER AND TEST MODE OPERATIONS OF DIESEL GENERATOR E Attachment C. EVALUATOR NOTE:

Next step produces Control Room and local alarm EVALUATOR CUE:

If necessary inform candidate that all VERIFY initials are assumed to be completed as required.

At OC521 C Diesel Generator C Engine Control Panel, PLACE DG C Control Mode Select Switch 43CM to LOCAL. OBSERVE following:

Control Switches Not Proper for Remote Auto Oper. ALARM. Page 3 of 10 Standard Controlled copy obtained from evaluator.

Places: DG C Control Mode Select Switch 43CM to LOCAL. Verifies:

Control Switches Not Proper for Remc.2 Auto Oper. Alarm window E08 - LIT Eva1 ~~ Comments *Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam As Given PERFORMANCE CHECKLIST Appl. To/JPM No.: S/RO 24.0P.001.007 Student Name: - Step Action EVALUATOR CUE: Alarm window E08 is LIT Remote white light EXTINGUISHES. EVALUATOR CUE: Remote White light is NOT LIT Local white I ig ht I LLU MI N ATED . EVALUATOR CUE:

Local White light is LIT DG C Available for Emergency white light EXTINGUISHES.

Page 4 of 10 Standard Verifies: Remote White light NOT LIT Verifies: Local White light LIT Verifies:

DG C Available for Emergency White light NOT LIT Eva1 Com men ts *Critical Step

1. Critical Sequence Form NTP-QA-3 1.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam As Given PERFORMANCE CHECKLIST Page 5 of 10 Appl. To/JPM No.: S/RO 24.0P.001.007 Student Name:

Action EVALUATOR CUE:

DG C Available for Emergency White light is NOT LIT ENSURE Control Room received DG Panel ALARM. EVALUATOR CUE:

Role play the control room and inform the candidate that DG Panel ALARM has been received At OC521C CLOSE ESW Loop A Valves for DG C by momentarily placing switch to CLOSE for ESW Supply/Return HV-O1112C/HV-O1122C.

c Standard Calls the Control Room to verify DG Panel ALARM has been received.

Places: ESW Supply/Return HV-O1112C/HV-O1122C switch to CLOSE AND Verifies:

Red lights NOT LIT Amber lights LIT - Eva1 Comments *Critical Step #Critical Sequence Form NTP-QA-31.8-2.

Rev. 0, Page 1 of I 2005 NRC Exam As Given PERFORMANCE CHECKLIST Appl. To/JPM No.: S/RO 24.0P.001.007 Student Name: - Step *8. Action EVALUATOR CUE: Both Red lights NOT LIT Both Amber lights LIT At OC521C CLOSE ESW Loop B Valves for DG C by momentarily placing switch to CLOSE for ESW Supply/Return HV-0111 OC/HV-O1120C. EVALUATOR CUE:

Both Red lights NOT LIT Both Amber lights LIT NOTE: Switching protective equipment required at switch,,,. - Page 6 of 10 Standard Places: ESW Supply/Return HV-0111 OC/HV-0 switch to CLOSE AND Verifies:

Red lights NOT LIT Amber lights LIT 120c Eva1 Comments *Critical Step #Critical Sequence Form NTP-QA-3 I .8-2, Rev. 0. Page 1 of 1 2005 NRC Exam As Given PERFORMANCE CHECKLIST Page 7 of 10 Appl. To/JPM No.: S/RO 24.0P.001.007 Student Name: Step 9. *lo. 11. Action EVALUATOR NOTE:

This JPM will not proceed to the point of racking the breakers. Therefore, Switching protective equipment will not be necessary.

At OC512C DG E for DG C Transfer Panel PLACE DG C Bldg Ventil Supply Fan OV512C to STOP. EVALUATOR CUE: Red light NOT LIT Amber light LIT At OC512C PLACE HS-O0057C, DG C Auto Start Control, to DISABLE to prevent inadvertent start while transferring logic. At OC512C OBSERVE DG C Aligned white light EXTINGUISHED.

Standard Places: DG C Bldg Ventil Supply Fan OV512C to STOP. Verifies: Red light NOT LIT Amber light LIT Places: HS-O0057C, DG C Auto Start Control, to DISABLE Verifies:

DG C Aligned white light NOT LIT Eva1 ___ Comments *Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam As Given PERFORMANCE CHECKLIST Page 8 of 10 Appl. To/JPM No.: S/RO 24.0P.001.007 Student Name: - Step *#12. # # # # # ~~ Action EVALUATOR CUE:

DG C Aligned white light NOT LIT At OC512C SEQUENTIALLY PLACE following switches to D/G E position:

Note: Cycle the following HS several times to clean contacts Standard SEQUENTIALLY Places the following switches to D/G E position:

a. HS-00058C Generator Metering

& Computer Monitoring

b. HS-00059C Generator Field Current Computer Monitoring

c. HS-00060C Diesel Alarms to Control Room Annunciator d. HS-00061C ESW Temp Monitoring

& HVAC Alarms e. HS-00062C ESW Loop A Supply Valve Control & Indication - Eva1 Comments *Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0. Page 1 of I 2005 NRC Exam As Given PERFORMANCE CHECKLIST Appl. To/JPM No.: S/RO 24.0P.001.007 Student Name:

Step # # # # # # # # # Action Page 9 of 10 Standard f. HS-00063C ESW Loop A Return Valve Control & Indication

g. HS-00064C ESW Loop 6 Supply Valve Control & Indication

h. HS-00065C DG Bypass Indication Unit 1 i. HS-00066C DG Bypass Indication Unit 2 j. HS-00067C Alignment Alarm

& Indication Only

k. HS-00068C ESW Loop B Return Valve Control & Indication I. HS-00069C ESW Bypass Indication and Auto Loop Transfer m. HS-00070C Ventilation Supply Fans Control

n. HS-00071 C DG Ctl, Indication, Metering & Breaker Trip Interlock Eva1 - Comments *Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0, Page 1 of 1 2005 NRC Exam As Given Appl. To/JPM No.: S/RO 24.0P.001.007 - Step # # # # # PERFORMANCE CHECKLIST Student Name: Page 10 of 10 Action EVALUATOR CUE: This completes the JPM. Standard 0. P. r. S. HS-00072C Generator Relaying

& Breaker Trip Interlock HS-00073C Generator Metering

& Breaker Trip Interlock HS-00074C Engine Control

& Indication HS-00075C Engine, Generator

& ESW Pump Control HS-00076C Generator Breaker Control - Eva1 Comments *Critical Step #Critical Sequence Form NTP-QA-31.8-2, Rev. 0. Page I of I 2005 NRC Exam As Given TASK CONDITIONS A. Both Units were at 100% Steady State Power. B. A Station Blackout Occurred.

C. The "A and "6 Diesel generators were started LOCALLY. D. The control room crew is performing Unit l(2) Response to Station Blackout EO-1 OO(200)-030.

E. To facilitate two diesels in same division operating, the control room is attempting to energize the "C" bus using the "E Diesel generator.

F. Another operator is at the "E" DG and has already performed steps 1 and 2 of OP-024-004, TRANSFER AND TEST MODE OPERATIONS OF DIESEL GENERATOR E Attachment C. INITIATING CUE Prepare the "C' DG for Transfer by performing steps 3 through 11 of OP-024-004, TRANSFER AND TEST MODE OPERATIONS OF DIESEL GENERATOR E Attachment C. 2005 NRC Exam As Given Page 1 of 2 TASK CONDITIONS A. Both Units were at 100% Steady State Power. B. A Station Blackout Occurred.

C. The "A and "B" Diesel generators were started LOCALLY. D. The control room crew is performing Unit l(2) Response to Station Blackout EO-1 OO(200)-030.

E. To facilitate two diesels in same division operating, the control room is attempting to energize the "C" bus using the "E Diesel generator.

F. Another operator is at the "E DG and has already performed steps 1 and 2 of OP-024-004, TRANSFER AND TEST MODE OPERATIONS OF DIESEL GENERATOR E Attachment C INITIATING CUE Prepare the "C DG for Transfer by performing steps 3 through 11 of OP-024-004, TRANSFER AND TEST MODE OPERATIONS OF DIESEL GENERATOR E Attachment C. 2005 NRC Exam As Given Page 2 of 2