ML112270532

301 Draft Administrative JPMs

ML112270532
Person / Time
Site:	Vogtle
Issue date:	05/10/2011
From:	NRC/RGN-II/DRS/OLB
To:	Southern Nuclear Operating Co
References
05-424/11-301, 05-425/11-301
Download: ML112270532 (57)

Text

RO-SRO Job Performance Measure A Facility: Vogtle Task No: V-LO-TA-37004 Task

Title:

Monitor / Evaluate CSFSTs - Integrity JPM No: V-NRC-JP-19200-20 K/A: G2.1.7 ( 4.4 /4.7)

Examinee:___________________________ NRC Examiner: _____________________

Facility Evaluator: ____________________ Date: ______________________________

Method of testing:

Simulated Performance ________________ Actual Performance ___________________

Classroom ______________ Simulator ______________ Plant _____________

Read to the examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues.

When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions: A Reactor trip occurred 30 minutes ago.

Following a transition from 19000-C, the crew determined that Critical Safety Function monitoring should be implemented.

Task Standard: Properly identify the status of all CSFSTs, determine that Integrity is the highest priority and a transition to 19241-C is required.

Required Materials: 19200-C, F-0 Critical Safety Function Status Trees Steam Tables Provided table of plant data (attached following student cue sheet)

General

References:

None Initiating Cue: The SS has directed you to use 19200-C to evaluate all CSFSTs and identify any required transition. Document your evaluation of CSFSTs on 19200-C.

Time Critical Task: No Validation Time: 10 minutes 1

Performance Information Critical steps denoted with an asterisk

• Sheet 1 Evaluates F- 0.1, the Subcriticality Status Tree Power Range greater than 5% - NO Intermediate Range SUR positive - NO Intermediate Range P-6 present - YES Intermediate Range SUR >-0.2 DPM- YES Go to 19212-C (YELLOW)

Standard: Properly evaluates Subcriticality to be YELLOW status.

Continues with evaluation of the other CSFST status trees.

Comment:

• Sheet 2 Evaluates F- 02, the Core Cooling Status Tree Core Exit TCs less than 1200 °F - YES RCS Subcooling greater than 24 (38) °F - YES CSF Sat (GREEN)

Standard: Properly evaluates Core Cooling to be GREEN status (sat)

Continues with evaluation of the other CSFST status trees.

Comment:

2

• Sheet 3 Evaluates F- 0.3, the Heat Sink Status Tree Narrow Range level in at least one SG greater than 10% (32%) - NO Total Available Feedwater flow to SGs greater than 570 gpm - YES Pressure in all SGs less than 1240 psig - YES Narrow Range level in all SGs Less than 82% - YES Pressure in all SGs less than 1180 psig - YES Narrow Range level in all SGs greater than 10% (32%) - NO Go to 19235-C (YELLOW)

Standard: Properly evaluates Heat Sink to be YELLOW status.

Continues with evaluation of the other CSFST status trees.

Comment:

• Sheet 4 Evaluates F- 0.4, the Integrity Status Tree Temperature decreases in all RCS Cold Legs less than 100 °F in the last 60 minutes. - NO All RCS Pressure WR Cold Leg temperature points to the right of Limit A -

YES All RCS WR Cold Leg temperatures greater than 265 °F - NO Go to 19241-C (ORANGE)

Standard: Properly evaluates Integrity to be ORANGE status.

Continues with evaluation of the other CSFST status trees.

Comment:

3

• Sheet 5 Evaluates F- 0.5, the Containment Status Tree Containment Pressure less than 52 psig - YES Containment Pressure less than 21.5 psig - YES Containment Sump level less than 105 inches - NO Go to 19252-C (ORANGE)

Standard: Properly evaluates Containment to be ORANGE status.

Continues with evaluation of the other CSFST status trees.

Comment:

• Sheet 6 Evaluates F- 0.6, the Inventory Status Tree PRZR level less than 92% - NO At least one RCP running - NO RVLIS indicates upper head greater than 98% full - NO Go to 19263-C (YELLOW)

Standard: Properly evaluates Inventory to be YELLOW status.

Comment:

• Notifies SS of required procedural transition based on CSFST status.

Standard: Determines F- 0.4 Integrity is highest priority CSFST Determines transition to 19241-C is required.

Comment:

Terminating cue: Student returns initiating cue sheet 4

Verification of Completion Job Performance Measure No. V-RQ-JP-19200-20 Examinees Name:

Examiners Name:

Date Performed:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:__________________________________________________________________

Response:_________________________________________________________________

Result: Satisfactory/Unsatisfactory Examiners signature and date: _______________________________ ________

5

Initial Conditions: A Reactor trip occurred 30 minutes ago.

Following a transition from 19000-C, the crew determined that Critical Safety Function monitoring should be implemented.

Initiating Cue: The SS has directed you to use 19200-C to evaluate all CSFSTs and identify any required transition. Document your evaluation of CSFSTs on 19200-C.

Channel /Loop Channel /Loop Channel / Loop Channel / Loop Parameter 1 2 3 4 PR NI 0% 0% 0% 0%

IR SUR -0.1 DPM -0.12 DPM

-4% -4%

IR NI 3.0x10 3.2x10 SR SUR 0 DPM 0 DPM RCS WR Pressure 1980 psig 2000 psig 1990 psig 2010 psig Core Exit T/Cs 329ºF RCP status Off Off Off Off RVLIS Full Range 100% 100%

RVLIS 97% 97%

Upper Head SG NR Level 10% 0% 15% 20%

AFW flow 205 GPM 0 GPM 210 GPM 200 GPM SG Pressure 950 psig 26 psig 973 psig 987 psig RCS WR Cold Leg Temperature 540ºF 261ºF 538ºF 541ºF CNMT Pressure 7 psig 8 psig 7 psig 8psig CNMT Emergency Sump Levels 108 inches 108 inches CNMT Radiation 24 mR / Hr 31 mR / Hr PRZR level 100% 100% 100%

RO Job Performance Measure B Facility: Vogtle Task No: V-LO-TA-63005 Task

Title:

Perform AFD Monitoring JPM No: V-NRC-JP-14915-004 K/A: G2.1.37 (4.3 / 4.6)

Examinee: __________________________ NRC Examiner: _____________________

Facility Evaluator: ____________________ Date: ______________________________

Method of testing:

Simulated Performance ________________ Actual Performance ___________________

Classroom ______________ Simulator ______________ Plant _____________

Read to the examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues.

When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions: Unit 1 has recently recovered from a load rejection. The unit is at 70% power. NI-42 has a failed detector and is declared inoperable.

I&C has reported that the AFD monitor alarm ALB10-F06 is inoperable.

Task Standard: AFD monitoring per 14915-1 Data Sheet 6 performed correctly .

Required Materials: 14915-1, Data Sheet 6 Unit 1 Plant Technical Data Book Tab 6.0 Calculator Initiating Cue: The SS directs you to perform 14915-1 Data Sheet 6 for AFD monitoring using the data supplied.

Time Critical Task: No Validation Time: 15 minutes 1

Performance Information Critical steps denoted with an asterisk

• Step 1 Determine upper and lower limits of AFD from PTDB-1 Tab 6.0.

Standard: Candidate fills in date and power level 70% and records the value of the doghouse limit at 70% Upper limit +19.6% +/- 0.5% Lower limit -24% +/- 0.5%

Comment:

• Step 2 Record indicated Axial Flux Difference for each operable Excore Channel.

Standard: Candidate records Delta Flux values for all channels except N42, which is marked N/A with note stating channel is inoperable or blank with note stating channel is inoperable.

Comment:

• Step 3 Verify the Axial Flux Difference is within limits of PTDB-1 Tab 6.0.

Standard: Candidate verifies that all three are within limits and initials or signs Verified block to complete the surveillance satisfactory.

Comment:

2

Step 4 With the indicated AFD outside of the above required limits on 2 or more channels and with THERMAL POWER greater than or equal to 50% of RATED THERMAL POWER, reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within 30 minutes.

Standard: This step does not apply.

Comment:

Terminating cue: Student returns initiating cue sheet.

3

DATA SHEET 6 (ANSWER KEY)

DATA SHEET 6 Sheet 2 of 4 AXIAL FLUX DIFFERENCE WITH AFD MONITOR ALARM INOPERABLE Date Todays date Power 70%

Upper Limit = +19.6% +/- 0.5% (from PTDB Tab 6.0)

Lower Limit = -24% +/- 0.5%

TIME 1-NI-41C 1-NI-42C 1-NI-43C 1-NI-44C VERIFIED Current -15 N/A -20 -15 initials time Note 1 Note 1 N42 is inoperable.

4

Verification of Completion Job Performance Measure No: V-NRC-JP-14915-004 Examinees Name:

Examiners Name:

Date Performed:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:__________________________________________________________________

Response:_________________________________________________________________

Result: Satisfactory/Unsatisfactory Examiners signature and date: _______________________________ ________

5

Initial Conditions: Unit 1 has recently recovered from a load rejection. The unit is at 70% power. NI-42 has a failed detector and is declared inoperable.

I&C has reported that the AFD monitor alarm ALB10-F06 is inoperable.

Initiating Cue: The SS directs you to perform 14915-1 Data Sheet 6 for AFD monitoring using the data supplied.

NI Channel Reading N41 70%

N42 67%

N43 70%

N44 70%

Delta Flux Channel N41C -15%

N42C -22%

N43C -20%

N44C -15%

SRO Job Performance Measure B Facility: Vogtle Task No: V-LO-TA-63005 Task

Title:

Evaluate Inoperable AFD monitor alarm JPM No: V-NRC-JP-14915-004 K/A: G2.1.37 (SRO 4.6)

Examinee: __________________________ NRC Examiner: _____________________

Facility Evaluator: ____________________ Date: ______________________________

Method of testing:

Simulated Performance ________________ Actual Performance ___________________

Classroom ______________ Simulator ______________ Plant _____________

Read to the examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues.

When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions: Unit 1 has recently recovered from a load rejection. The unit is at 70% power. NI-42 has a failed detector and is declared inoperable.

I&C has reported that the AFD monitor alarm ALB10-F06 is inoperable.

Task Standard: Inoperable AFD monitor alarm ALB10-F06 is evaluated and applicable actions taken (AFD calculated and LCO evaluated).

Required Materials: 14915-1, Data Sheet 6 Unit 1 Plant Technical Data Book Tab 6.0 17010-C Annunciator Response procedure for window ALB10F06 Tech Specs Calculator Initiating Cue: You are the SS. Determine the required actions and perform any necessary surveillances for the AFD monitor alarm inoperability using the data supplied.

Time Critical Task: No Validation Time: 15 minutes 1

Performance Information Critical steps denoted with an asterisk

• Determine surveillance required to be performed.

CUE: If asked: Provide the ARP 17010-C copy for window ALB10F06 Standard: Candidate determines AFD must be determined for each OPERABLE excore channel within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> using 14915-1 Data Sheet 6.

Comment:

• Step 1 Determine upper and lower limits of AFD from PTDB-1 Tab 6.0.

Standard: Candidate fills in date and power level 70% and records the value of the doghouse limit at 70% Upper limit +19.6% +/- 0.5% Lower limit -24% +/- 0.5%.

Comment:

• Step 2 Record indicated Axial Flux Difference for each operable Excore Channel.

Standard: Candidate records Delta Flux values for all channels, except N42 which is marked N/A with note stating channel is inoperable or blank with note stating channel is inoperable.

Comment:

2

• Step 3 Verify the Axial Flux Difference is within limits of PTDB-1 Tab 6.0.

Standard: Candidate verifies that two are not within limits and does not initial or sign Verified block to complete the surveillance signify it is unsatisfactory.

Comment:

• Step 4 Determine required action.

With the indicated AFD outside of the above required limits on 2 or more channels and with THERMAL POWER greater than or equal to 50% of RATED THERMAL POWER, reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within 30 minutes.

Standard: Candidate should report the above action must be done.

Comment:

Terminating cue: Student returns initiating cue sheet.

3

DATA SHEET 6 (ANSWER KEY)

DATA SHEET 6 Sheet 2 of 4 AXIAL FLUX DIFFERENCE WITH AFD MONITOR ALARM INOPERABLE Date Todays date Power 70%

Upper Limit = +19.6% +/- 0.5% (from PTDB Tab 6.0)

Lower Limit = -24% +/- 0.5%

TIME 1-NI-41C 1-NI-42C 1-NI-43C 1-NI-44C VERIFIED Current -25 N/A -22 -25 Note 2 time Note 1 Note 1 N42 inoperable Note 2 AFD unsat 4

Verification of Completion Job Performance Measure No:

Examinees Name:

Examiners Name:

Date Performed:

Number of Attempts:

Time to Complete:

Question Documentation:

Question: __________________________________________________________________

Response: _________________________________________________________________

Result: Satisfactory/Unsatisfactory Examiners signature and date: _______________________________ ________

5

Initial Conditions: Unit 1 has recently recovered from a load rejection. The unit is at 70% power. NI-42 has a failed detector I&C has reported that the AFD monitor alarm ALB10-F06 is inoperable.

Initiating Cue: You are the SS. Determine the required actions and perform any necessary surveillances for the AFD monitor alarm inoperability using the data supplied.

NI Channel Reading N41 70%

N42 67%

N43 70%

N44 70%

Delta Flux Channel N41C -25 N42C -20 N43C -22 N44C -25

17010-1 Ver. 49.0 WINDOW F06 ORIGIN SETPOINT DELTA FLUX YC-1140 Plant Technical DEVIATION Data Book, Tab 6 1.0 PROBABLE CAUSE

1. Xenon transient

2. Control rod motion

3. Thermal power transient

4. Loss of Power Range Detector voltage.

5. IPC Failure 2.0 AUTOMATIC ACTIONS NONE 3.0 INITIAL OPERATOR ACTIONS NOTE The Delta Flux Deviation Program satisfies the requirement for Verify AFD within limits for each OPERABLE excore channel in Technical Specifications SR 3.2.3.1.

NONE

WINDOW F06 (Continued) 4.0 SUBSEQUENT OPERATOR ACTIONS NOTE This annunciator comes in immediately upon exceeding the limits for acceptable operation.

1. With Reactor Power greater than 50% check differential flux indications and if two or more are outside the limits, perform the following:

a. Restore the indicated AFD to within the limits, or

b. Reduce Thermal Power to less than 50% of Rated Thermal Power within 30 minutes.

2. Thermal Power shall not be increased above 50% of Rated Thermal Power until the indicated AFD is within the limits specified by the COLR.

3. IF loss of Power Range Detector voltage is determined, Go To 18002-C, "Nuclear Instrumentation System Malfunction".

4. Refer To Technical Specification LCO 3.2.3.

5. IF alarm is inoperable, begin recording differential flux in accordance with 14915-1, "Special Condition Surveillance Logs" (Technical Specifications SR 3.2.3.1).

6. Refer To Plant Computer alarm summary display for additional information relating to this alarm.

5.0 COMPENSATORY OPERATOR ACTIONS Initiate Data Sheet 6 of 14915-1, "Special Condition Surveillance Logs" END OF SUB-PROCEDURE

REFERENCES:

Technical Specification Section LCO 3.2.3

RO Job Performance Measure C Facility: Vogtle Task No: V-LO-TA-63013 Task

Title:

Determine Mode Change Requirements JPM No: V-NRC-JP-10008-20 K/A: G2.2.38 (3.6 / 4.5)

Examinee: __________________________ NRC Examiner: _____________________

Facility Evaluator: ____________________ Date: ______________________________

Method of testing:

Simulated Performance ________________ Actual Performance ___________________

Classroom ______________ Simulator ______________ Plant _____________

Read to the examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues.

When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions: Unit 1 is currently in Mode 5, loops filled, preparing for a post-refueling start up with the following conditions:

o RCS temperature 190°F, loops filled.

o RCPs 1 & 4 running.

o PZR level 25%, steam bubble established.

o RHR Train A in service.

o RHR Train B in standby.

o S/Gs NR level 65%.

o Ambient wet bulb temperature is 66ºF.

Equipment OOS:

o CCP-1A o Train A NSCW Tower Fan #2 o MDAFWP 1A o SG ARV loop 2 o Both SI pumps in PTL o PZR level channel 461 failed low - B/S tripped o 1-RE-2562A, CNMT Atmosphere Air Particulate monitor o 1ABA MCC RM ESF CLR cooling coil 1

Task Standard: Appropriate mode 4 restraints, if any, identified.

Required Materials: Technical Specifications and Bases Technical Requirements Manual Initiating Cue: The SS directs you to determine if Technical Specification requirements for Mode 4 entry are satisfied or identify ALL restraints for Mode 4 entry.

Time Critical Task: No Validation Time: 30 minutes 2

Performance Information Critical steps denoted with an asterisk CCP - 1A inoperable:

LCO 3.5.3 ECCS - One ECCS train shall be operable.

TR 13.1.3 Reactivity Controls - Boration Flow Paths Operating TR 13.1.5 Reactivity Controls - Charging Pumps Operating Standard: LCO applicable and MET.

Comment:

• Train A NSCW Tower Fan #2 inoperable:

LCO 3.7.9 Ultimate Heat Sink (UHS)

The UHS shall be OPERABLE. With ambient wet-bulb temperature > 63 ºF, four fans and four spray cells per train shall be OPERABLE. With ambient wet-bulb temperature 63 ºF, three fans and four spray cells per train shall be OPERABLE.

Condition B: One NSCW cooling tower with one or more required fans and/or spray cells inoperable.

Standard: Applies in MODE 4, therefore is a restraint.

Comment:

MDAFW Pump 1A should lead to referencing:

LCO 3.7.5 Auxiliary Feedwater (AFW)

Applicability: MODES 1, 2, and 3.

Standard: Only applies to Modes 1, 2, and 3; therefore not a restraint.

Comment:

3

SG ARV Loop 2 should lead to referencing:

LCO 3.7.4 Atmospheric Relief Valves (ARVs)

Applicability: MODES 1, 2, and 3.

Standard: Only applies to Modes 1, 2, and 3; therefore not a restraint.

Comment:

Both SI pumps in PTL:

LCO 3.4.12 Cold Overpressure Protection System (COPS)

A COPS shall be OPERABLE with all safety injection pumps incapable of injecting into the RCS and the accumulators isolated and either a or b below.

LCO 3.5.3 ECCS - Shutdown Standard: Applies in MODE 4 with any RCS cold leg temperature the COPS arming temperature specified in the PTLR, but MET.

Comment:

PZR level channel 461 failed low - B/S tripped should lead to referencing:

LCO 3.3.1 Reactor Trip System (RTS) Instrumentation Table 3.3.1-1 should that Pressurizer Level only applies in Mode 1 above P-7 and then only 3 channels are required.

Standard: LCO is not applicable until MODE 1.

Comments:

4

1RE-2562A, CNMT process particulate radiation monitor should lead to referencing:

LCO 3.4.15 RCS Leakage Detection Instrumentation The following RCS leakage detection instrumentation shall be OPERABLE:

a. The containment normal sumps level and reactor cavity sump monitors;

b. One containment atmosphere radioactivity monitor; AND

c. Either the containment air cooler condensate flow rate or a containment atmosphere gaseous or particulate radioactivity monitoring system not taken credit for in item b.

Standard: Applies in Mode 4 but MET.

Comments:

1ABA MCC RM ESF CLR cooling coil LCO 3.7.14 Engineered Safety Features (ESF) Room Cooler and Safety Related Chiller System Two Room Cooler and Safety Related Chiller trains shall be operable Condition A. One ESF Room Cooler and Safety Related Chiller Train Inoperable.

Standard: Applies in Mode 4 and NOT MET. This is a restraint on Mode 4.

Comments:

5

• Determine that Mode 4 entry is restrained.

Standard: Determines that LCO 3.7.9 Condition B and LCO 3.7.14 Condition A apply to Mode 4. LCO 3.0.4 is applicable and neither would allow continued operation of the unit in Mode 4 for an unlimited period of time. Therefore Train A NSCW Tower Fan #2 and 1ABA MCC RM ESF CLR cooling coil being out of service.

Comments:

Reports to SS that Mode 4 entry is restrained.

Standard: Reports to SS the restraints preventing entry into Mode 4.

Comments:

Terminating cue: Student returns initiating cue sheet and informs of the restraints on entry to Mode 4.

6

Verification of Completion Job Performance Measure No: V-NRC-JP-14915-001 Examinees Name:

Examiners Name:

Date Performed:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:__________________________________________________________________

Response:_________________________________________________________________

Result: Satisfactory/Unsatisfactory Examiners signature and date: _______________________________ ________

7

Initial Conditions: Unit 1 is currently in Mode 5, loops filled, preparing for a post-refueling start up with the following conditions:

o RCS temperature 190°F, loops filled.

o RCPs 1 & 4 running.

o PZR level 25%, steam bubble established.

o RHR Train A in service.

o RHR Train B in standby.

o S/Gs NR level 65%.

o Ambient wet bulb temperature is 66ºF.

Equipment OOS:

o CCP-1A o Train A NSCW Tower Fan #2 o MDAFWP 1A o SG ARV loop 2 o Both SI pumps in PTL o PZR level channel 461 failed low - B/S tripped o RE-2562A, CNMT Atmosphere Air Particulate monitor o 1ABA MCC RM ESF CLR cooling coil Initiating Cue: The SS directs you to determine if Technical Specification requirements for Mode 4 entry are satisfied or identify ALL restraints for Mode 4 entry.

SRO Job Performance Measure C Facility: Vogtle Task No: V-LO-TA-63013 Task

Title:

Determine Mode Change Requirements JPM No: V-NRC-JP-10008-21 K/A: G2.2.38 (3.6 / 4.5)

Examinee: __________________________ NRC Examiner: _____________________

Facility Evaluator: ____________________ Date: ______________________________

Method of testing:

Simulated Performance ________________ Actual Performance ___________________

Classroom ______________ Simulator ______________ Plant _____________

Read to the examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues.

When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions: Unit 1 is currently in Mode 5, loops filled, preparing for a post-refueling start up with the following conditions:

o RCS temperature 190°F, loops filled.

o RCPs 1 & 4 running.

o PZR level 25%, steam bubble established.

o RHR A in service.

o RHR B in standby.

o S/Gs NR level 65%.

o Ambient wet bulb temperature is 66ºF.

Equipment OOS:

o CCP-1A o Train A NSCW Tower Fan #2 o 1AD1M o SG ARV loop 2 o Both SI pumps in PTL o PZR level channel 461 failed low - B/S tripped o RE-2562A, CNMT Atmosphere Air Particulate monitor o 1ABA MCC RM ESF CLR cooling coil 1

Task Standard: Appropriate mode 4 restraints, if any, identified.

Required Materials: Technical Specifications and Bases Technical Requirements Manual Initiating Cue: The SS directs you to determine if Technical Specification requirements for Mode 4 entry are satisfied or identify ALL restraints for Mode 4 entry.

---

AND----

State ALL actions that could be taken to allow Mode change.

Time Critical Task: No Validation Time: 30 minutes 2

Performance Information Critical steps denoted with an asterisk CCP - 1A inoperable:

LCO 3.5.3 ECCS - One ECCS train shall be operable.

TR 13.1.3 Reactivity Controls - Boration Flow Paths Operating TR 13.1.5 Reactivity Controls - Charging Pumps Operating Standard: LCO applicable and MET.

Comment:

• Train A NSCW Tower Fan #2 inoperable:

LCO 3.7.9 Ultimate Heat Sink (UHS)

The UHS shall be OPERABLE. With ambient wet-bulb temperature > 63 ºF, four fans and four spray cells per train shall be OPERABLE. With ambient wet-bulb temperature 63 ºF, three fans and four spray cells per train shall be OPERABLE.

Condition B: One NSCW cooling tower with one or more required fans and/or spray cells inoperable.

Standard: Applies in MODE 4, therefore is a restraint.

Comment:

3

1AD1M LCO 3.8.9 Distribution Systems - Operating Bases should be referenced. The table has a footnote, Operability of 125 V Motor Control Centers 1/2AD1M and 1/2BD1M is addressed by LCOs 3.4.11, 3.4.12, and 3.7.5.

LCO 3.7.5 Auxiliary Feedwater (AFW) and 3.4.11 PORVs Applicability: MODES 1, 2, and 3.

3.4.12 COPS applies but is met by PORV train A and RHR train A or B suction reliefs Standard: LCOs do not apply or are met, therefore not a restraint.

Comment:

SG ARV Loop 2 should lead to referencing:

LCO 3.7.4 Atmospheric Relief Valves (ARVs)

Applicability: MODES 1, 2, and 3.

Standard: Only applies to Modes 1, 2, and 3; therefore not a restraint.

Comment:

Both SI pumps in PTL:

LCO 3.4.12 Cold Overpressure Protection System (COPS)

A COPS shall be OPERABLE with all safety injection pumps incapable of injecting into the RCS and the accumulators isolated and either a or b below.

LCO 3.5.3 ECCS - Shutdown Standard: Applies in MODE 4 with any RCS cold leg temperature the COPS arming temperature specified in the PTLR, but MET.

Comment:

4

PZR level channel 461 failed low - B/S tripped should lead to referencing:

LCO 3.3.1 Reactor Trip System (RTS) Instrumentation Table 3.3.1-1 should that Pressurizer Level only applies in Mode 1 above P-7 and then only 3 channels are required.

Standard: LCO is not applicable until MODE 1.

Comments:

1RE-2562A, CNMT process particulate radiation monitor should lead to referencing:

LCO 3.4.15 RCS Leakage Detection Instrumentation The following RCS leakage detection instrumentation shall be OPERABLE:

a. The containment normal sumps level and reactor cavity sump monitors;

b. One containment atmosphere radioactivity monitor; AND

c. Either the containment air cooler condensate flow rate or a containment atmosphere gaseous or particulate radioactivity monitoring system not taken credit for in item b.

Standard: Applies in Mode 4 but MET.

Comments:

5

1ABA MCC RM ESF CLR cooling coil LCO 3.7.14 Engineered Safety Features (ESF) Room Cooler and Safety Related Chiller System Two Room Cooler and Safety Related Chiller trains shall be operable Condition A. One ESF Room Cooler and Safety Related Chiller Train Inoperable.

Standard: Applies in Mode 4 and NOT MET. This is a restraint on Mode 4.

Comments:

6

• Determine that Mode 4 entry is restrained.

Standard: Determines that LCO 3.7.9 Condition B and LCO 3.7.14 Condition A apply to Mode 4. LCO 3.0.4 is applicable and neither would allow continued operation of the unit in Mode 4 for an unlimited period of time. Therefore Train A NSCW Tower Fan #2 and 1ABA MCC RM ESF CLR cooling coil being out of service.

Comments:

• Determine actions that would allow Mode 4 entry.

Standard: Determines that for LCO 3.7.9 Condition B Train A NSCW Tower Fan # 2 :

Restore the component to operable status -or-Verify SR 3.7.9.5 is performed and sat -or-Obtain an acceptable risk assessment per LCO 3.0.4b Determines that for LCO 3.7.14 Condition A 1ABA MCC RM ESF CLR cooling coil:

Restore the component to operable status or Obtain an acceptable risk assessment per LCO 3.0.4b Comments:

Terminating cue: Student returns initiating cue sheet and informs of the restraints on entry to Mode 4.

7

Verification of Completion Job Performance Measure No: V-NRC-JP-14915-001 Examinees Name:

Examiners Name:

Date Performed:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:__________________________________________________________________

Response:_________________________________________________________________

Result: Satisfactory/Unsatisfactory Examiners signature and date: _______________________________ ________

8

Initial Conditions: Unit 1 is currently in Mode 5, loops filled, preparing for a post-refueling start up with the following conditions:

o RCS temperature 190°F, loops filled.

o RCPs 1 & 4 running.

o PZR level 25%, steam bubble established.

o RHR A in service.

o RHR B in standby.

o S/Gs NR level 65%.

o Ambient wet bulb temperature is 66ºF.

Equipment OOS:

o CCP-1A o Train A NSCW Tower Fan #2 o 1AD1M o SG ARV loop 2 o Both SI pumps in PTL o PZR level channel 461 failed low - B/S tripped o RE-2562A, CNMT Atmosphere Air Particulate monitor o 1ABA MCC RM ESF CLR cooling coil Initiating Cue: The SS directs you to determine if Technical Specification requirements for Mode 4 entry are satisfied or identify ALL restraints for Mode 4 entry.

---

AND----

State ALL actions that could be taken to allow Mode change.

RO Job Performance Measure D Facility: Vogtle Task No: N/A Task

Title:

Calculate Stay Time for Emergency Exposure JPM No: V-NRC-JP-91301-20 K/A

Reference:

K/A: G2.3.7 (3.5 / 3.6)

Examinee: __________________________ NRC Examiner: _____________________

Facility Evaluator: ____________________ Date: ______________________________

Method of testing:

Simulated Performance ________________ Actual Performance ___________________

Classroom ______________ Simulator ______________ Plant _____________

Read to the examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues.

When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions: An Alert Emergency has been declared. Cold Leg Recirculation has been established CCP A motor and Lube oil temperatures are rising and CCP B is out of service.

You have been authorized by the Emergency Director to receive an Emergency Exposure to protect CCP pump A motor from damage by venting 1-1202-X4-419, 1-1202-U4-420, 1-1202-X4-421, 1-1202-U4-422 NSCW cooling water vents.

You are to be briefed by Health Physics on the anticipated dose for the areas to traverse to CCP A cooling water vents and RC113 where the valves are located.

You have been authorized by the Emergency Director to receive an Emergency Exposure of 10 REM.

Your current TEDE dose for this quarter is 500 mrem.

Task Standard: Maximum Stay time calculated that does not exceed Emergency exposure limit.

Required Materials: 1. HP briefing maps C level SE corner and C-113 1

General

References:

None Initiating Cue: Calculate your maximum stay time so as not to exceed your Emergency Exposure Limit.

Time Critical Task: No Validation Time: 10 minutes 2

Performance Information Critical steps denoted with an asterisk HP briefing CUE HP BRIEFING No dose on transit into Aux Bldg down the stairwell to Level C landing where your tools have been staged by another team.

General area dose rates in RC121 and RC122 are 4 REM per hour.

Transit time through RC121 and RC122 is 6 minutes.

General area dose rates in RC113 are 14.5 REM per hour.

Valves 7 and 8 on C-113 room drawing are the cooler isolation valves. Vent valves are above them toward the middle of the room.

Standard: N/A Comment:

• Calculate Transit Time to and from work location.

4 Rem/Hr (General Area Dose-RC 121 & 122) ÷ 60 min per hour = 0.0667 REM per min (66.67 mrem/min) 0.0667 REM per min x 12 Min = 0.8004 REM (800.4 mrem)

Standard: Transit time calculated Comment:

3

• Calculate Stay Time 10 REM (Emergency Exposure limit) - 0.8004 REM (Actual Exposure) = 9.1996 REM (9199.6 mrem) 9.1996 REM ÷ 14.5 REM/hr (General Area Dose-RC 113) = 0.6345 hr (38.07 minutes) 0.6345 hr x 60 Min/hr = 38.07 minutes OR 38 minutes and 4 seconds.

Standard: Stay time calculated at 38.07 minutes OR 38 minutes and 4 seconds + 0 minutes to - 1 minute (38.07 minutes to 37.07 minutes OR 38 minutes and 4 seconds to 37 minutes and 4 seconds).

Comment:

Terminating cue: Student returns initiating cue sheet 4

Verification of Completion Job Performance Measure No. V-NRC-JP-91301-20 Examinees Name:

Examiners Name:

Date Performed:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:__________________________________________________________________

Response:_________________________________________________________________

Result: Satisfactory/Unsatisfactory Examiners signature and date: _______________________________ ________

5

Initial Conditions: An Alert Emergency has been declared. Cold Leg Recirculation has been established CCP A motor and Lube oil temperatures are rising and CCP B is out of service.

You have been authorized by the Emergency Director to receive an Emergency Exposure to protect CCP pump A motor from damage by venting 1-1202-X4-419, 1-1202-U4-420, 1-1202-X4-421, 1-1202-U4-422 NSCW cooling water vents.

You are to be briefed by Health Physics on the anticipated dose for the areas to traverse to CCP A cooling water vents and RC113 where the valves are located.

You have been authorized by the Emergency Director to receive an Emergency Exposure of 10 REM.

Your current TEDE dose for this quarter is 500 mrem.

Initiating Cue: Calculate your maximum stay time so as not to exceed your Emergency Exposure Limit.

6

SRO Job Performance Measure D Facility: Vogtle Task No: N/A Task

Title:

Lifesaving In Emergency Conditions JPM No: V-NRC-JP-91301-20 K/A

Reference:

G 2.3.4 (3.2/3.7)

Examinee: __________________________ NRC Examiner: _____________________

Facility Evaluator: ____________________ Date: ______________________________

Method of testing:

Simulated Performance ________________ Actual Performance ___________________

Classroom ______________ Simulator ______________ Plant _____________

Read to the examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues.

When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions: You are the Emergency Director.

An ALERT emergency has been declared.

ECCS has been placed in cold leg recirculation.

A missing person has been located in FHB Level B penetration room.

He is unconscious and HP measures the general area dose at 300 Rem/hr.

This person must be moved outside the room in order to survive.

The estimated time for a rescuer to remove this injured person is 8 minutes.

Data: EMERGENCY EXPOSURE # 1 HP SUPERVISOR: J. SMITH RESCUER NAME: JOHN DOE SSN: 123-45-6789 OSLD # 12345 Page 1 of 6

Task Standard: Dose calculated.

Emergency exposure permits properly completed per 91301-C.

State the requirements the rescuer must satisfy for this exposure.

Required Materials: 91301-C, Emergency Exposure Guidelines General

References:

None Initiating Cue:

Perform the following:

1. Calculate the projected dose to the rescuer.

2. Given 91301-C, Complete data sheet 1 for this exposure.

3. State requirements the rescuer must satisfy for this exposure.

Time Critical Task: No Validation Time: 10 minutes Page 2 of 6

Performance Information Critical steps denoted with an asterisk

• Calculate Projected Dose Dose projection = 300 Rem/hr x 8 min x (1 hr / 60 min) = 40 Rem Standard: 40 Rem calculated Comment:

• Completes Data sheet 1 per procedure 91301-C.

Standard: 1. Data sheet 1 completed as shown on key

2. John Doe signs in signature block CUE: When candidate indicates J. Doe must sign, state J. Doe has read and signed the data sheet"

3. Candidate signs, dates and time after J. Doe as the Emergency Director to approve.

Comment:

• State requirements the rescuer must satisfy for this exposure.

Standard: Candidate indicates he is a volunteer and is fully aware of the risks as the acknowledgement states.

Comment:

Terminating cue: Student returns initiating cue sheet Page 3 of 6

Verification of Completion Job Performance Measure No. V-NRC-JP-91310-20 Examinees Name:

Examiners Name:

Date Performed:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:__________________________________________________________________

Response:_________________________________________________________________

Result: Satisfactory/Unsatisfactory Examiners signature and date: _______________________________ ________

Page 4 of 6

Sheet 1 of 1 DATA SHEET 1 PERMIT FOR EMERGENCY RADIATION EXPOSURE #__1___

Prepared by: Candidate name Date: Todays Date Time: Current time Task Type: (circle one) Protecting Valuable Property Lifesaving or protection of large population Task

Description:

Lifesaving unconscious person in FHB Level B penetration room. (or similar)

DOSE LIMITS: _______>25_______ REM TEDE ACKNOWLEDGMENT For doses greater than 25 REM TEDE

1. I am a volunteer to receive a dose of greater than 25 REM TEDE.

2. I am fully aware of the risks involved in receiving the estimated dose of 40 REM TEDE.

NAME SSN SIGNATURE OSLD (last 4 digits) NUMBER JOHN DOE 6789 12345

• N/A_ or blank N/A N/A Health Physics Supervisor Date Time Authorization to exceed 10CFR20 exposure limits is granted. (1985304696)

• __Name _____________ __ ______Date___ _______Time_____

Emergency Director Date Time

• Verbal authorization shall be noted by initials of person receiving verbal authorization from HP Supervisor or Emergency Director. Emergency Director signature to be obtained when time permits.

Page 5 of 6

Initial Conditions: Initial Conditions: You are the Emergency Director.

An ALERT emergency has been declared.

ECCS has been placed in cold leg recirculation.

A missing person has been located in FHB Level B penetration room.

He is unconscious and HP measures the general area dose at 300 Rem/hr.

This person must be moved outside the room in order to survive.

The estimated time for a rescuer to remove this injured person is 8 minutes.

Data: EMERGENCY EXPOSURE # 1 HP SUPERVISOR: J. SMITH RESCUER NAME: JOHN DOE SSN: 123-45-6789 OSLD # 12345 Initiating Cue: Perform the following:

1. Calculate the projected dose to the rescuer.

2. Given 91301-C Complete data sheet 1 for this exposure.

3. State requirements the rescuer must satisfy for this exposure.

Page 6 of 6

SRO Job Performance Measure E Facility: Vogtle Task No: V-LO-TA-40001 Task

Title:

Classify an Emergency Event JPM No: V-NRC-JP-NMP-EP-110-20 K/A

Reference:

G2.4.38 Examinee: __________________________ NRC Examiner: _____________________

Facility Evaluator: ____________________ Date: ______________________________

Method of testing:

Simulated Performance ________________ Actual Performance ___________________

Classroom ______________ Simulator ______________ Plant _____________

Read to the examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues.

When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions: Unit 1 is at 100% power Unit 2 is in Mode 5, 105 ºF at 50% PRZR Level (Cold Cal) preparing for Vacuum refill.

Unit 2 time to boil is 75 minutes.

The following occurs:

- A fault in the High voltage switchyard trips power to all RATs.

UNIT ONE STATUS

- Unit 1 tripped due to the switchyard fault.

- Both Unit 1 Diesel Generators start and are powering their emergency buses.

- 15 minutes has elapsed since the fault.

- Unit 1 is stable at 557 ºF and 2235 psig.

1

UNIT TWO STATUS

- D/G-2A starts but does not energize 2AA02. The crew has emergency stopped D/G-2A.

- D/G-2B starts but trips on overspeed.

- 15 minutes has elapsed since the fault.

- Power restoration to 2AA02 expected in 45 minutes.

Wind direction is from 300 degrees at a speed of 5.8 mph.

Stability class - D, with no precipitation.

Task Standard: Event classified within 15 minutes per NMP-EP-110 and NMP-EP-110 Checklist1 completed.

Required Materials: 1. ED packet

2. NMP-EP-110, Emergency Classification Determination and Initial Action

3. NMP-EP-110-GL03, VEGP EALs - ICs, Threshold Values and Basis

4. NMP-EP-110-GL03, Figure 1 Fission Product Barrier Evaluation

5. Large copy NMP-EP-110-GL03, Figure 2 - Hot Initiating Condition Emergency Action Level Matrix

6. Large copy NMP-EP-110-GL03, Figure 3 - Cold Initiating Condition Emergency Action Level Matrix General

References:

None Initiating Cue: Classify the event. Complete Checklist 1 - Classification Determination.

Time Critical Task: YES Validation Time: 15 minutes to classify 2

Performance Information Critical steps denoted with an asterisk NMP-EP-110 Checklist 1 CLASSIFICATION DETERMINATION START TIME CRITICAL__________

1. Determine the appropriate Initiating Condition Matrix for classification of the event based on the current operating mode:

Standard: Both boxes checked by the ED.

Comment:

2. Evaluate the status of the fission product barrier using Figure 1, Fission Product Barrier Evaluation.

a. Select the condition of each fission product barrier:

Standard: All barriers marked INTACT. Step is initialed by the ED.

Comment:

2.

b. Determine the highest applicable fission product barrier Initiating Condition (IC):

Standard: None is marked by the ED. Step is initialed by the ED.

Comment:

3

3. Evaluate and determine the highest applicable IC/EAL using the Matrix Evaluation Chart identified in step.

NOTE to examiner: SU1 is the highest on the Hot Matrix. Per step 6.1.7, Events should be classified based on meeting the Initiating Condition (IC) and Threshold Value (TV) for an EAL considering each Unit independently. If both Units are in concurrent events, then the highest classification must be made and used for the Offsite notifications with the other Unit events noted on the Emergency Notification form.

Standard: EAL # CA3 (Loss of ALL Offsite Power AND Loss of All Onsite AC Power to Essential Busses) is filled in. Step is initialed by the ED.

Comment:

• 4. Check the highest emergency classification level identified from either step 2b or 3.

Standard: Alert is marked. CA3 is entered in the based on IC# line beside Alert. Step is initialed by the ED.

Remarks blank specific EAL not needed, it may be marked N/A. Candidate may place Unit one highest IC# here, but it is not required.

Comment:

• 5. Declare the event by approving the Emergency Classification.

Standard: Step is signed, with date and time completed. ED initials the step.

STOP TIME CRITICAL__________

Comment:

4

6. Obtain Meteorological Data.

Standard: 300°, 5.8 mph, D, and none, entered into blocks. ED initials step Comment:

5

Verification of Completion Job Performance Measure No. V-RQ-JP-91001-016 Examinees Name:

Examiners Name:

Date Performed:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:__________________________________________________________________

Response:_________________________________________________________________

Result: Satisfactory/Unsatisfactory Examiners signature and date: _______________________________ ________

6

THIS IS A TIME CRITICAL JPM Initial Conditions: Unit 1 is at 100% power Unit 2 is in Mode 5, 105 ºF at 50% PRZR Level (Cold Cal) preparing for Vacuum refill.

Unit 2 time to boil is 75 minutes.

The following occurs:

- A fault in the High voltage switchyard trips power to all RATs.

UNIT ONE STATUS

- Both Unit 1 diesels start and are powering their emergency buses.

- Unit 1 tripped due to the switchyard fault.

- 15 minutes has elapsed since the fault.

- Unit 1 is stable at 557 ºF and 2235 psig.

UNIT TWO STATUS

- D/G-2A starts but does not energize 2AA02. The crew has emergency stopped D/G-2A.

- D/G-2B starts but trips on overspeed.

- Power restoration to 2AA02 expected in 45 minutes.

Wind direction is from 300 degrees at a speed of 5.8 mph.

Stability class - D, with no precipitation.

Initiating Cue: Classify the event. Complete Checklist 1 - Classification Determination.

7