Text

GG-2020-02 Final Operating Test
	ML20058H621
Person / Time
Site:	Grand Gulf
Issue date:	02/10/2020
From:	Greg Werner; Operations Branch IV
To:	; Entergy Operations
References
	Download: ML20058H621 (321)
	v • d • e

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Grand Gulf Nuclear Station Date of Examination: 2/3/2020 Examination Level: RO SRO Operating Test Number: GGNS 2/2020 Administrative Topic (see Note) Type Describe activity to be performed Code*

Determine Core Flow, given plant parameters, system status or events determine actual Reactor Core Flow.

Conduct of Operations R, N GJPM-OPS-2/2020-AR1 2.1.7 (4.4)

Reactor Water Level Determination, The operator will evaluate plant conditions at the Remote Shutdown Panel to determine Narrow Conduct of Operations R, D Range reactor water level and the status of injection sources.

GJPM-OPS-2/2020-AR2 2.1.25 (3.9)

Emergency Exposure Limits, The operator will evaluate a condition involving abnormally high radiological conditions and determine Radiation Control R, D actions required to administratively control the dose received by determining who authorizes dose extensions in various situations.

GJPM-OPS-2/2020-AR3 2.3.4 (3.2)

Loss of Shutdown Cooling, Time to 200°F, given plant status and parameters determine the time to 200 on a loss of Shutdown Cooling.

Emergency Plan R, N GJPM-OPS-2/2020-AR4 2.4.11 (3.4/3.6)

NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics (which would require all five items).

Type Codes and Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs and RO retakes) (2)

(N)ew or (M)odified from bank ( 1) (2)

(P)revious 2 exams ( 1, randomly selected) (0)

Rev 0 8/6/2019

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Grand Gulf Nuclear Station Date of Examination: 2/3/2020 Examination Level: RO SRO Operating Test Number: GGNS 2/2020 Administrative Topic (see Note) Type Describe activity to be performed Code*

Determine Reportability, This task is to use corporate procedures and given plant conditions to determine the reportability and Conduct of Operations R, D complete applicable notification form GJPM-OPS-2/2020-AS1 2.1.20 (4.6)

Determine Penetration Isolation Requirements, given failure of penetration isolation valve failure, determine Tech Spec Conduct of Operations R, D action and requirements for isolating.

GJPM-OPS-2/2020-AS2 2.1.7 (4.7)

Tagout Removal Approval, given a protective tagging removal, verify restored positions and information.

Equipment Control R, D GJPM-OPS-2/2020-AS3 2.2.15 (4.3) - 2.2.15 (4.3) - 2.2.41 (3.9)

Authorize Emergency Exposure, given plant status and events in progress, determine appropriate radiation exposure limits.

Radiation Control R, N GJPM-OPS-2/2020-AS4 2.3.4 (3.7)

PAR Determination, given plant status and events in progress, determine correct PAR recommendations.

Emergency Plan R, N GJPM-OPS-2/2020-AS5 2.4.44 (4.4)

NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics (which would require all five items).

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

(N)ew or (M)odified from bank ( 1) (2)

(P)revious 2 exams ( 1, randomly selected) (0)

Rev 2 1/15/2019

Date of Examination: 2/03/2020 Operating Test Number: GGNS 2-2020 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2-2020AR1 2-2020 AR1 GGNS 2-2020 NRC Operating Test Job Performance Measure JPM Number: GJPM-OPS-2-2020AR1 JPM

Title:

Determine Core Flow Facility Number: N/A NEW (If Bank or Modified from Bank)

Prepared By: Steve Reeves 10/1/2019 Exam Developer Date Ops Review: Jonathan Smith 10/3/2019 1st Validation by Ops Rep or Ops Validation Crew Date Validated By: April Hargrave / Benny White 10/10/2019 2nd Validation by Ops Validation Crew Date Approved By: Tracy Tharp 10/24/2019 Project Lead or Exam Team Lead Date

GJPM-OPS-2-2020AR1 Determine Core Flow New Modified Direct from bank Time Critical Alternate Path Validation Time: 15 Min Setting: Classroom Type: RO Task: CRO-B33-10 K&A: 2.1.7, (4.4) 2.1.25, (3.9)

Safety Function: Reactivity Control (1) 10CFR 55.45(a) (5)

Performance: Perform Reference(s): 05-1-02-III-3, Rev 118 05-1-02-III-6, Rev 002 Handout(s) 05-1-02-III-3, 05-1-02-III-6

Manipulations: N/A

Critical Steps: 2 Simulator Setup/Required Plant Conditions:

NONE Safety Concerns:

NONE Reason For Revision:

Rev 1:

In step 3 & 4 change 05-1-02-III-3 to 05-1-02-III-6

In step 5 add actual values in standard for power and flow +/-2%

Modify task standard on pages 3 & 9 to be consistent with above

Add Feedwater temperature to Initiating Cue (normal for current plant conditions)

Revision 01 1/13/2020 Page 2 of 11

GJPM-OPS-2-2020AR1 Determine Core Flow Task Standard:

Calculates actual core flow to be 56.8 mlbm/hr

Performs plot on Power to Flow map

Using the given reactor power of 68.7% and the calculated core flow of 56.8 mlbm/hr the operator performs a plot on the Power to flow map Figure 1 and determines to be in the MELLLA + REGION. (+/- 2 mlbm/hour on either side and +/- 2%

power on either side.).

Revision 01 1/13/2020 Page 3 of 11

GJPM-OPS-2-2020AR1 Determine Core Flow Initial Condition(s):

The plant is operating at rated conditions when crew determines a Jet Pump #5 and #6 failure.

Current indications:

RECIRC PMP A/B DRIVING FLO o A - 29,700 gpm o B - 27,100 gpm

TOT JP FLO o 60 mlbm/hr

CAL JP FLO o A - 0.8 mlbm/hr o C - 2.0 mlbm/hr

CYCLOPS Jet Pump Flow indication:

o #5 - 0.8 mlbm/hr o #6 - 0.8 mlbm/hr

Reactor Power o 68.7%

Feedwater temperature is normal for the current conditions.

Initiating Cue(s):

CRS has directed you to determine actual core flow and plot on PF map.

Revision 01 1/13/2020 Page 4 of 11

GJPM-OPS-2-2020AR1 Determine Core Flow Notes to Evaluator:

Remember to record Start time on page 7.

Task Overview: (Detailed description of task)

Using procedures 05-1-02-III-3 and 05-1-02-III-6, the operator will use the provided indications to determine actual core flow.

Revision 01 1/13/2020 Page 5 of 11

GJPM-OPS-2-2020AR1 Determine Core Flow Critical tasks are underlined, italicized, and denoted by an (*)

NOTE: The sequence of the following steps is critical unless otherwise noted.

Remember to record Start time Step 1: 05-1-02-III-3, 5.9 IF cause is determined to be possible Jet Pump failure, THEN REFER to ONEP 05-1-02-III-6, Jet Pump Anomalies Standard: The operator Refers to 05-1-02-III-6, Jet Pump Anomalies Cue: None.

Notes:

SAT / UNSAT Step 2: 05-1-02-III-3, 3.5 VERIFY Thermal Limits are met. Accuracy of Total Core Flow indication May need evaluation.

Standard: The operator determines actual core flow by using information located in the NOTE above step 3.5 of 05-1-02-III-3.

Cue: None.

Notes:

SAT / UNSAT Revision 01 1/13/2020 Page 6 of 11

GJPM-OPS-2-2020AR1 Step 3: 05-1-02-III-6, 3.5 NOTE Core flow May be calculated by summing the indicated flow of the two affected Jet Pumps obtained from Cyclops computer AND subtracting this value twice from the total indicated Jet Pump flow.

Standard: The operator determines actual core flow by using information located in the NOTE above step 3.5 of 05-1-02-III-6.

Cue: None.

Notes:

SAT / UNSAT Step 4: 05-1-02-III-6, 3.5 NOTE Calculation

Calculates actual core flow.

Jet pump #5 flow 0.8 mlbm/hr + Jet pump #6 flow 0.8 mlbm/hr = 1.6 mlbm/hr TOT JP FLO 60 mlbm/hr - 1.6 mlbm/hr - 1.6 mlbm/hr = 56.8 mlbm/hr Standard: The operator determines actual core flow by using information located in the NOTE above step 3.5 of 05-1-02-III-6 to be 56.8 mlbm/hr Cue: None.

Notes:

SAT / UNSAT Revision 01 1/13/2020 Page 7 of 11

GJPM-OPS-2-2020AR1 Step 5: 05-1-02-III-3, Figure 1

Performs plot on Power to Flow map.

Standard: Using the given reactor power of 68.7% and the calculated core flow of 56.8 mlbm/hr the operator performs a plot on the Power to flow map Figure 1 and determines to be in the MELLLA + REGION. (+/- 2 mlbm/hour on either side and +/- 2% power on either side.)

Cue: None.

Notes: Attached is a Figure 1 KEY.

SAT / UNSAT Revision 01 1/13/2020 Page 8 of 11

GJPM-OPS-2-2020AR1 Determine Core Flow Time Critical Alternate Path Validation Time: 15 Min Operator: ____________________________________License: RO / SRO Date: __________

Evaluators Name: ______________________ Evaluators Signature:__________________________

Start Time:___________ Stop Time:____________

CRITICAL TIME FRAME: ________Required Time (min):________ Actual Time (min):_________

Task Standard(s):

Calculates actual core flow to be 56.8 mlbm/hr

Performs plot on Power to Flow map

Using the given reactor power of 68.7% and the calculated core flow of 56.8 mlbm/hr the operator performs a plot on the Power to flow map Figure 1 and determines to be in the MELLLA + REGION. (+/- 2 mlbm/hour on either side and +/- 2% power on either side.).

JPM Results (circle one): SAT UNSAT Follow-up Questions:

Follow-up Question Response:

Comments / Feedback:

Revision 01 1/13/2020 Page 9 of 11

GRAND GULF NUCLEAR STATION OFF-NORMAL EVENT PROCEDURE

Title:

Reduction in Recirculation No.: 05-1-02-III-3 Revision: 118 Page: 16 System Flow Rate Figure 1 KEY, DO NOT GIVE TO STUDENT GGNS C22 Power/Flow Map for Normal Feedwater Temperature This map is only valid for Normal Feedwater temperature which is defined as the value of Normal Feedwater temperature down to ten degrees F. below that value. For temperatures below that range refer to Figure 2 GGNS C22 Power/Flow Map for Reduced Feedwater Temperature.

CORE FLOW 56.8 Mlbm/hr POWER 68.7%

Revision 01 1/13/2020 Page 10 of 11

Give this page to the student Initial Condition(s):

The plant is operating at rated conditions when crew determines a Jet Pump #5 and #6 failure.

Current indications:

RECIRC PMP A/B DRIVING FLO o A - 29,700 gpm o B - 27,100 gpm

TOT JP FLO o 60 mlbm/hr

CAL JP FLO o A - 0.8 mlbm/hr o C - 2.0 mlbm/hr

CYCLOPS Jet Pump Flow indication:

o #5 - 0.8 mlbm/hr o #6 - 0.8 mlbm/hr

Reactor Power o 68.7%

Feedwater temperature is normal for the current conditions.

Initiating Cue(s):

CRS has directed you to determine actual core flow and plot on PF map.

Date of Examination: 2/03/2020 Operating Test Number: GGNS 2-2020 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2-2020AR2 2-2020 AR2 GGNS 2-2020 NRC Operating Test Job Performance Measure JPM Number: GJPM-OPS-2-2020AR2 JPM

Title:

Reactor Water Level Determination Facility Number: GJPM-OPS-AON05 (If Bank or Modified from Bank)

Prepared By: Steve Reeves 10/1/2019 Exam Developer Date Ops Review: Jonathan Smith 10/3/2019 1st Validation by Ops Rep or Ops Validation Crew Date Validated By: April Hargrave / Benny White 10/10/2019 2nd Validation by Ops Validation Crew Date Approved By: Tracy Tharp 10/24/2019 Project Lead or Exam Team Lead Date

GJPM-OPS-2-2020AR2 Reactor Water Level Determination New Modified Direct from bank Time Critical Alternate Path Validation Time: 15 Min Setting: Classroom Type: RO Task: CRO-C61-OFFNORM-5 K&A: 2.1.25 (3.9/4.2); 2.4.34 - (4.2/4.1)

Safety Function: NA 10CFR 55.45(a) (5)

Performance: Perform Reference(s): 05-1-02-II-1 (Shutdown from the Remote Shutdown Panel)

Handout(s): 05-1-02-II-1 (Shutdown from the Remote Shutdown Panel)

Rev 051 Photo of RSP level and pressure indication (attached)

Manipulations: N/A

Critical Steps: 3 Low Power: No Emergency/Abnormal: YES RCA entry: No Engineered Safety Function: No Simulator Setup/Required Plant Conditions:

None Safety Concerns:

None Revision 01 1/13/2020 Page 2 of 11

GJPM-OPS-2-2020AR2 Reactor Water Level Determination Reason For Revision:

Rev 1:

Change number of critical task to 3 in summary

Deleted last bullet in Task Standard due to redundant information.

Added Attachment 1 as a Key

Added Per Attachement 1 in step 1

Added RCIC is not injecting and not running due to Narrow range being >53.5 in step 2

Added Determines the status of RCIC by marking status blocks on turnover sheetto step 2.

Added Determines the HPCS pump is RUNNING but is NOT injecting due to Wide Range level being >53.5 by marking status blocks on turnover sheet. To step 3

Added boxes for the applicant to check if HPCS and RCIC is Running/NOT running, and Injecting/NOT Injecting to turnover sheet.

Task Standard(s):

Per Attachment 1 of 05-1-02-II-1, Determines Narrow Range reactor water level is 59.0.

KEY ATTACHED

Determines the status of RCIC by marking status blocks on turnover sheet, RCIC is not running and not injecting water to the reactor

Determines the status of HPCS by marking status blocks on turnover sheet, HPCS is Running and not injecting water to the reactor Revision 01 1/13/2020 Page 3 of 11

GJPM-OPS-2-2020AR2 Reactor Water Level Determination Initial Condition(s):

The Control Room has been evacuated per 05-1-02-II-1 (Shutdown from the remote Shutdown Panel).

An Alert has been declared for the Control Room Evactuation.

The Condensate/Feedwater system is not available for inventory control.

All actions for Control Room Evacuation has been completed.

o Reactor Mode Switch is in SHUTDOWN o All control rods are inserted o MSIVs are closed o RCIC is initiated o HPCS is initiated

NO 05-1-02-II-1 attatchments are installed.

All SRVs are currently CLOSED and reactor pressure is stable.

You report to the Remote Shutdown Panel to establish reactor water level.

Initiating Cue(s):

The CRS directs you to determine Narrow Range reactor water level and the status of HPCS and RCIC

Use the attached image for current plant conditions.

Consider only the given plant conditions.

HPCS RCIC Running NOT Running Injecting NOT Injecting Revision 01 1/13/2020 Page 4 of 11

GJPM-OPS-2-2020AR2 Reactor Water Level Determination Notes:

None Task Overview:

The operator will evaluate plant conditions at the Remote Shutdown Panel to determine Narrow Range reactor water level and the status of injection sources.

Revision 01 1/13/2020 Page 5 of 11

GJPM-OPS-2-2020AR2 Reactor Water Level Determination Critical tasks are underlined, italicized, and denoted by an (*)

NOTE: The sequence of the following steps is critical unless otherwise noted.

Remember to record Start time Step 1: 05-1-02-II-1 Attachment 1

Determine Narrow Range reactor water level is 59.0 Standard: Per Attachment 1 of 05-1-02-II-1, Determines Narrow Range reactor water level is 59.0. KEY ATTACHED.

Cue: None.

Notes: Narrow Range level between 57 and 60 is acceptable.

SAT / UNSAT Step 2: 05-1-02-II-1 Attachment 1

Determines the status of RCIC Standard: Determines the status of RCIC is NOT running and NOT Injecting due to Reactor water level being >53.5 Narrow range, by marking status blocks on turnover sheet RCIC Running NOT Running Injecting NOT Injecting Cue: None.

Notes:

SAT / UNSAT Revision 01 1/13/2020 Page 6 of 11

GJPM-OPS-2-2020AR2 Step 3:

Determines the status of HPCS Standard: Determines the HPCS pump is RUNNING but is NOT injecting to the reactor since the E22-F004 (HPCS injection valve) closed on Wide Range reactor water Level 8 (53.5) by marking status blocks on turnover sheet.

HPCS Running NOT Running Injecting NOT Injecting Cue: None.

Notes: HPCS is not monitored or controllable from the RSP. If reactor water level fails to Wide Range reactor Level 2 (-41.6), E22-F004 will open and HPCS will begin to inject to the reactor. The operator will need to determine this from memory of system operation as there are no references at the RSP to determine the status of HPCS.

To meet the critical task, the operator need only state that HPCS and RCIC is not injecting to the reactor.

SAT / UNSAT Revision 01 1/13/2020 Page 7 of 11

GJPM-OPS-2-2020AR2 Reactor Water Level Determination Time Critical Alternate Path Validation Time: 15 Min Operator: ____________________________________License: RO / SRO Date: __________

Evaluators Name: ______________________ Evaluators Signature:__________________________

Start Time:___________ Stop Time:____________

CRITICAL TIME FRAME: ________Required Time (min):________ Actual Time (min):_________

Task Standard(s):

Per Attachment 1 of 05-1-02-II-1, Determines Narrow Range reactor water level is 59.0. KEY ATTACHED

Determines the status of RCIC by marking status blocks on turnover sheet, RCIC is not running and not injecting water to the reactor

Determines the status of HPCS by marking status blocks on turnover sheet, HPCS is Running and not injecting water to the reactor JPM Results (circle one): SAT UNSAT Follow-up Questions:

Follow-up Question Response:

Comments / Feedback:

Revision 01 1/13/2020 Page 8 of 11

GJPM-OPS-2-2020AR2 KEY DO NOT GIVE TO STUDENT SHUTDOWN FROM THE REMOTE SHUTDOWN PANEL WIDE RANGE vs NARROW RANGE LEVEL Intersecting point of 70 Wide Range and 600 psig as indicated. 59 Narrow Range level Indicated level of 70 Wide Range Revision 01 1/13/2020 Page 9 of 11

Give this page to the student Initial Condition(s):

The Control Room has been evacuated per 05-1-02-II-1 (Shutdown from the remote Shutdown Panel).

An Alert has been declared for the Control Room Evactuation.

The Condensate/Feedwater system is not available for inventory control.

All actions for Control Room Evacuation has been completed.

o Reactor Mode Switch is in SHUTDOWN o All control rods are inserted o MSIVs are closed o RCIC is initiated o HPCS is initiated

NO 05-1-02-II-1 attatchments are installed.

All SRVs are currently CLOSED and reactor pressure is stable.

You report to the Remote Shutdown Panel to establish reactor water level.

Initiating Cue(s):

The CRS directs you to determine Narrow Range reactor water level and the status of HPCS and RCIC

Use the attached image for current plant conditions.

Consider only the given plant conditions.

HPCS RCIC Running NOT Running Injecting NOT Injecting

Date of Examination: 2/03/2020 Operating Test Number: GGNS 2-2020 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2-2020AR3 2-2020 AR3 GGNS 2-2020 NRC Operating Test Job Performance Measure JPM Number: GJPM-OPS-2-2020AR3 JPM

Title:

Emergency Exposure Limits Facility Number: GJPM-OPS-AEM11 (If Bank or Modified from Bank)

Prepared By: Steve Reeves 10/1/2019 Exam Developer Date Ops Review: Jonathan Smith 10/3/2019 1st Validation by Ops Rep or Ops Validation Crew Date Validated By: April Hargrave / Benny White 10/10/2019 2nd Validation by Ops Validation Crew Date Approved By: Tracy Tharp 10/24/2019 Project Lead or Exam Team Lead Date

GJPM-OPS-2-2020AR3 Emergency Exposure Limits New Modified Direct from bank Time Critical Alternate Path Validation Time: 15 Min Setting: Classroom Type: RO Task: CRO-ADMIN-15 K&A: Generic 2.3.4: 3.2/3.7 Safety Function: N/A 10CFR 55.45(a) (5)

Performance: Perform Reference(s): EN-RP-201 Dosimetry Administration, Rev 5 Handout(s) EN-RP-201 Dosimetry Administration

Manipulations: N/A

Critical Steps: 3 Simulator Setup/Required Plant Conditions:

None Safety Concerns:

None Reason For Revision:

Rev 1:

Added actual value to standard on step 2.

Added values to first two bullets of task standard

Deleted parts of remaining task standard Revision 01 1/13/2020 Page 2 of 9

GJPM-OPS-2-2020AR3 Emergency Exposure Limits Task Standard:

Determine total dose to limit of 750 mrem

Determine total stay time prior to exceeding limit of 3.75 hours8.680556e-4 days 0.0208 hours 1.240079e-4 weeks 2.85375e-5 months

Determine that per EN-RP-201, the Radiation Protection Manager Approves Revision 01 1/13/2020 Page 3 of 9

GJPM-OPS-2-2020AR3 Initial Condition(s):

Max expected dose rate for 166 elevation containment area where the job will be conducted is 200 mrem/hr.

Your current year-to-date exposure TEDE is 1250 mrem and you have no undocumented quarters in the current year.

Initiating Cue(s):

The CRS directs you to enter containment to vent the RHR A system using E12-F107A and E12-F108A and remain there until completely vented.

No authorization has been granted to exceed the current limit.

Considering only TEDE, calculate the maximum stay time before the current Administrative exposure limit is exceeded.

Who must authorize exceeding the exposure limit for this task up to 3000 mrem per year?

Revision 01 1/13/2020 Page 4 of 9

GJPM-OPS-2-2020AR3 Emergency Exposure Limits Notes to the Evaluator:

Remember to record Start time on page 8.

Task Overview:

The operator will evaluate a condition involving radiological conditions and determine actions required to administratively control the dose received by determining total stay time with current exposure.

Determines approval requirements for exceeding the limit.

Revision 01 1/13/2020 Page 5 of 9

GJPM-OPS-2-2020AR3 Emergency Exposure Limits Critical tasks are underlined, italicized, and denoted by an (*)

NOTE: The sequence of the following steps is critical unless otherwise noted.

Remember to record Start time Step 1: Calculation, EN-RP-201 5.3 [3]

Determine total dose to limit.

2,000 mrem (exposure limit) - 1250 mrem (ytd exposure) = 750 mrem Standard: Determines the correct does limit for normal operations with no emergency declared and correct dose to be received before the exposure limit is exceeded is 750 mrem.

Cue: None Notes:

SAT / UNSAT Step 2: Calculation

Determine total stay time prior to exceeding limit.

750 mrem = 3.75 hours8.680556e-4 days 0.0208 hours 1.240079e-4 weeks 2.85375e-5 months 200 mrem Standard: Determines the correct stay time of 3.75 hours8.680556e-4 days 0.0208 hours 1.240079e-4 weeks 2.85375e-5 months before the exposure limit is exceeded.

Cue:

Notes:

SAT / UNSAT Revision 01 1/13/2020 Page 6 of 9

GJPM-OPS-2-2020AR3 Step 3: EN-RP-201 section 5.4

Determine that per EN-RP-201, the Radiation Protection Manager Approves Standard: Determines Radiation Protection Manager Approves up to 3000 mrem per year.

Cue:

Notes:

SAT / UNSAT Revision 01 1/13/2020 Page 7 of 9

GJPM-OPS-2-2020AR3 Emergency Exposure Limits Time Critical Alternate Path Validation Time: 15 Min Operator: ____________________________________License: RO / SRO Date: __________

Evaluators Name: ______________________ Evaluators Signature:__________________________

Start Time:___________ Stop Time:____________

CRITICAL TIME FRAME: ________Required Time (min):________ Actual Time (min):_________

Task Standard(s):

Determine total dose to limit of 750 mrem

Determine total stay time prior to exceeding limit of 3.75 hours8.680556e-4 days 0.0208 hours 1.240079e-4 weeks 2.85375e-5 months

Determine that per EN-RP-201, the Radiation Protection Manager Approves JPM Results (circle one): SAT UNSAT Follow-up Questions:

Follow-up Question Response:

Comments / Feedback:

Revision 01 1/13/2020 Page 8 of 9

Give this page to the student Initial Condition(s):

Max expected dose rate for 166 elevation containment area where the job will be conducted is 200 mrem/hr.

Your current year-to-date exposure TEDE is 1250 mrem.

Initiating Cue(s):

The CRS directs you to enter containment to vent the RHR A system using E12-F107A and E12-F108A and remain there until completely vented.

No authorization has been granted to exceed the current limit.

Considering only TEDE, calculate the maximum stay time before the current Administrative exposure limit is exceeded.

Who must authorize exceeding the exposure limit for this task up to 3000 mrem per year?

Date of Examination: 2/03/2020 Operating Test Number: GGNS 2-2020 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2-2020AR4 2-2020 AR4 GGNS 2-2020 NRC Operating Test Job Performance Measure JPM Number: GJPM-OPS-2-2020AR4 JPM

Title:

Loss of Shutdown Cooling, Time to 200°F Determination Facility Number: N/A NEW (If Bank or Modified from Bank)

Prepared By: Steve Reeves 10/1/2019 Exam Developer Date Ops Review: Jonathan Smith 10/3/2019 1st Validation by Ops Rep or Ops Validation Crew Date Validated By: April Hargrave / Benny White 10/10/2019 2nd Validation by Ops Validation Crew Date Approved By: Tracy Tharp 10/24/2019 Project Lead or Exam Team Lead Date

GJPM-OPS-2-2020AR4 Loss of Shutdown Cooling, Time to 200°F Determination New Modified Direct from bank Time Critical Alternate Path Validation Time: 15 Min Setting: Classroom Type: RO Task: CRO-E12-11 K&A: 2.4.11 (3.4/3.6)

Safety Function: Heat Removal from the Core 10CFR 55.45(a) (5)

Performance: Perform Reference(s): 05-1-02-III-1, Rev 48 Handout(s) 05-1-02-III-1

Manipulations: N/A

Critical Steps: 6 Simulator Setup/Required Plant Conditions:

NONE Safety Concerns:

NONE Reason For Revision:

Rev 1:

Change summary to 6 critical steps

Change Time to boil to Time to 200°F

Changed last bullet on Task standard, deleted approximately to +/- 1.0 hrs Revision 01 1/13/2020 Page 2 of 12

GJPM-OPS-2-2020AR4 Loss of Shutdown Cooling, Time to 200°F Determination Task Standard:

Determines figure 4 is to be used to determine time to 200°F.

Determines Pre-Shuffle 150°F line is to be used.

Using given information, determines time to boil is approximately 0.4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Determines figure 7 is to be used to determine time to TAF.

Determines Pre-Shuffle lines are to be used.

Using given information, determines time to TAF is 9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months (+/- 1.0 hrs.)

Revision 01 1/13/2020 Page 3 of 12

GJPM-OPS-2-2020AR4 Loss of Shutdown Cooling, Time to 200°F Determination Initial Condition(s):

On day 5 of a refueling outage the following conditions exist:

Reactor Cavity Pool is being drained for Drywell Head Removal.

Reactor water level is being maintained 95 to 100 Upset Range.

Reactor coolant temperature is 140°F.

RHR A is lined up and providing shutdown cooling through the E12-F053A (RHR A SHUTDN CLG RTN TO FW).

RHR B and ADHR are unavailable.

RWCU is available.

Initiating Cue(s):

RHR pump A trips on overcurrent

Determine the time available before reactor coolant temperature reaches 200°F.

Determine the time to for reactor water level to reach TAF.

Revision 01 1/13/2020 Page 4 of 12

GJPM-OPS-2-2020AR4 Loss of Shutdown Cooling, Time to 200°F Determination Notes to Evaluator:

Remember to record Start time on page 5.

Task Overview: (Detailed description of task)

This task has the student to estimate time to reach 200°F following loss of shutdown cooling and determine time to TAF.

Critical tasks are underlined, italicized, and denoted by an (*)

NOTE: The sequence of the following steps is critical unless otherwise noted.

Remember to record Start time Step 1: 05-1-02-III-1, Attachment 1

Determines figure 4 is to be used to determine time to 200°F.

Standard: The operator determines using procedure 05-1-02-III-1 Attachment I, Figure 4 due to current water level is 85 to 90 on Upset Range. The bottom of the Main Steam lines are located at 101 vessel level. Therefore, Figure 4 should be used at 12 inches below Main Steam Lines.

Cue: None.

Notes:

SAT / UNSAT Revision 01 1/13/2020 Page 5 of 12

GJPM-OPS-2-2020AR4 Step 2: 05-1-02-III-1, Attachment 1

Determines Pre-Shuffle 150°F line is to be used.

Standard: The operator determines using procedure 05-1-02-III-1 Attachment I, Figure 4 Pre-Shuffle line is to be used due to current conditions states that Reactor Cavity drain down is in progress for drywell head removal. Therefore no fuel has been moved and pre-shuffle lines must be used. The 150°F lines are to be used due to current temp is 140°F and the student should use the most conservative line.

Cue: None.

Notes:

SAT / UNSAT Step 3: 05-1-02-III-1, Attachment 1

Using given information, determines time to 200°F is approximately 0.4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Standard: The operator determines using procedure 05-1-02-III-1 Attachment I, Figure 4 that there are 0.4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or 24 minutes (+/- 0.08 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or 5 minutes) to 200°F.

Cue: None.

Notes:

SAT / UNSAT Revision 01 1/13/2020 Page 6 of 12

GJPM-OPS-2-2020AR4 Step 4: 05-1-02-III-1, Attachment 1

Determines figure 7 is to be used to determine time to TAF.

Standard: The operator determines using procedure 05-1-02-III-1 Attachment I, Figure 7 due to current water level is 85 to 90 on Upset Range. The bottom of the Main Steam lines are located at 101 vessel level. Therefore, Figure 7 should be used at 12 inches below Main Steam Lines.

Cue: None.

Notes:

SAT / UNSAT Step 5: 05-1-02-III-1, Attachment 1

Determines Pre-Shuffle lines are to be used.

Standard: The operator determines using procedure 05-1-02-III-1 Attachment I, Figure 7 Pre-Shuffle lines are to be used due to current conditions states that Reactor Cavity drain down is in progress for drywell head removal. Therefore no fuel has been moved and pre-shuffle lines must be used.

Cue: None.

Notes:

SAT / UNSAT Revision 01 1/13/2020 Page 7 of 12

GJPM-OPS-2-2020AR4 Step 6: 05-1-02-III-1, Attachment 1

Using given information, determines time to TAF is 9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months .

Standard: The operator determines using procedure 05-1-02-III-1 Attachment I, Figure 7 that there 9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months (+/- 1.0 hours0 days 0 hours 0 weeks 0 months ) to TAF.

Cue: None.

Notes:

SAT / UNSAT Revision 01 1/13/2020 Page 8 of 12

GJPM-OPS-2-2020AR4 Loss of Shutdown Cooling, Time to 200°F Determination Time Critical Alternate Path Validation Time: 15 Min Operator: ____________________________________License: RO / SRO Date: __________

Evaluators Name: ______________________ Evaluators Signature:__________________________

Start Time:___________ Stop Time:____________

CRITICAL TIME FRAME: ________Required Time (min):________ Actual Time (min):_________

Task Standard(s):

Determines figure 4 is to be used to determine time to 200°F.

Determines Pre-Shuffle 150°F line is to be used.

Using given information, determines time to boil is approximately 0.4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Determines figure 7 is to be used to determine time to TAF.

Determines Pre-Shuffle lines are to be used.

Using given information, determines time to TAF is 9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months (+/- 1.0 hrs.)

JPM Results (circle one): SAT UNSAT Follow-up Questions:

Follow-up Question Response:

Comments / Feedback:

Revision 01 1/13/2020 Page 9 of 12

GJPM-OPS-2-2020AR4 KEY DO NOT GIVE TO STUDENT GRAND GULF NUCLEAR STATION OFF-NORMAL EVENT PROCEDURE 05-1-02-III-1 Revision: 047 Attachment I Page 10 of 8 0.5 0.4 0.25 Figure 4: Time for Reactor Vessel to reach 200°F for Initial Water Level 12 in Below Main Steam Line Revision 01 1/13/2020 Page 10 of 12

GJPM-OPS-2-2020AR4 KEY DO NOT GIVE TO STUDENT GRAND GULF NUCLEAR STATION OFF-NORMAL EVENT PROCEDURE 05-1-02-III-1 Revision: 047 Attachment I Page 11 of 8 9 hrs Figure 7: Time to TAF from 12 in Below Main Steam Line Revision 01 1/13/2020 Page 11 of 12

Give this page to the student Initial Condition(s):

On day 5 of a refueling outage the following conditions exist:

Reactor Cavity Pool is being drained for Drywell Head Removal.

Reactor water level is being maintained 95 to 100 Upset Range.

Reactor coolant temperature is 140°F.

RHR A is lined up and providing shutdown cooling through the E12-F053A (RHR A SHUTDN CLG RTN TO FW).

RHR B and ADHR are unavailable.

RWCU is available.

Initiating Cue(s):

RHR pump A trips on overcurrent

Determine the time available before reactor coolant temperature reaches 200°F.

Determine the time to for reactor water level to reach TAF.

Date of Examination: 2/03/2020 Operating Test Number: GGNS 2-2020 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2-2020AS1 2-2020 AS1 GGNS 2-2020 NRC Operating Test Job Performance Measure JPM Number: GJPM-OPS-2-2020AS1 JPM

Title:

Determine Reportability Facility Number: GJPM-OPS-AAD07 (If Bank or Modified from Bank)

Prepared By: Steve Reeves 10/1/2019 Exam Developer Date Ops Review: Jonathan Smith 10/3/2019 1st Validation by Ops Rep or Ops Validation Crew Date Validated By: Ronnie Walters / Brandon Meyer 10/10/2019 2nd Validation by Ops Validation Crew Date Approved By: Tracy Tharp 10/24/2019 Project Lead or Exam Team Lead Date

GJPM-OPS-2-2020AS1 Determine Reportability New Modified Direct from bank Time Critical Alternate Path Validation Time: 15 Min Setting: Classroom Type: SRO Task: SRO-M&S-011 K&A: 2.1.20 4.6, 2.1.1 4.2 Safety Function: N/A PRA Applicability: HPCS is listed as #16 on System Importance to CDF 10CFR 55.45(a) (5)

Performance: Actual Reference(s): EN-LI-108, Event Notification and Reporting, Rev 18 EN-OP-133, Operations Notifications, Rev 00 EN-OP-133-02, GGNS Operations Notifications, Rev 00 Handout(s) EN-LI-108, Event Notification and Reporting EN-OP-133, Operations Notifications EN-OP-133-02, GGNS Operations Notifications

Manipulations: N/A

Critical Steps: 2 Simulator Setup/Required Plant Conditions:

NONE Safety Concerns:

NONE Reason For Revision:

Rev 1:

Added 10CFR reference to the task standard list to match steps Revision 01 1/13/2020 Page 2 of 9

GJPM-OPS-2-2020AS1 Determine Reportability Task Standard:

Candidate determines the initiation of HPCS to mitigate an event and resulting injection to the RPV is a 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months reportable event reportable to the NRC Operations Center in accordance with EN-OP-133-02 Attachment 2 item II.2 per 10 CFR 50.72(b)(2)(iv)(A)..

Completes Attachment 1 of EN-OP-133-02 IAW with attached key.

Revision 01 1/13/2020 Page 3 of 9

GJPM-OPS-2-2020AS1 Determine Reportability Initial Condition(s):

The plant is in Mode 3.

RCIC is OOSVC and isolated.

Shutdown Cooling A was being aligned for operation.

While aligning Shutdown Cooling A, an error caused flow to be diverted to the Suppression Pool via the minimum flow valve.

As reactor water level decreased, RHR isolations and a reactor scram signal initiated at Reactor Level 3.

Reactor water level dropped to -45 inches Wide Range before the inventory reduction was terminated by the successful RHR isolation.

High Pressure Core Spray initiated during the event and restored level to the normal band.

Current reactor parameters:

o water level is +30 inches and stable o Reactor pressure 30 psig o Core Flow 0 Mlbm/hr o Reactor Temp 259°F Initiating Cue(s):

You are the Shift Manager.

Determine the MOST limiting reportability of this incident

Complete Attachment 1 of EN-OP-133-02

Another SRO will complete the On-Shift Evaluation.

Revision 01 1/13/2020 Page 4 of 9

GJPM-OPS-2-2020AS1 Determine Reportability Notes to Evaluator:

Remember to record Start time on page 6 Task Overview: (Detailed description of task)

This task is to corporate procedures and given plant conditions to determine the reportability and complete applicable notification form.

Critical tasks are underlined, italicized, and denoted by an (*)

NOTE: The sequence of the following steps is critical unless otherwise noted.

Remember to record Start time Step 1: EN-OP-133-02 & EN-LI-108 Reviews EN-OP-133-02 and EN-LI-108 for notification criteria and determines the relationship of plant conditions to conditions listed as reportable; the associated time frames and who is notified.

Standard: Candidate reviews EN-OP-133-02 and EN-LI-108 for notification criteria and determines the relationship of plant conditions to conditions listed as reportable, the associated time frames and who is notified.

Cue: None Notes:

SAT / UNSAT Revision 01 1/13/2020 Page 5 of 9

GJPM-OPS-2-2020AS1 Step 2: EN-OP-133-02 & EN-LI-108

Determines the ECCS (HPCS) injection due to a valid signal is a 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months reportable event reportable to the NRC Operations Center.

Standard: Candidate determines the initiation of HPCS to mitigate an event and resulting injection to the RPV is a 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months reportable event reportable to the NRC Operations Center in accordance with EN-OP-133-02 Attachment 2 item II.2 per 10 CFR 50.72(b)(2)(iv)(A).

The candidate should also recognize that a RPS actuation with the reactor NOT critical and also a CTMT isolation signal in more than one system due to a level 2 signal is an 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months reportable event.

Cue: None Notes: The candidate may use the Quick Reference Table.

SAT / UNSAT Step 3: EN-OP-133-02 Attachment 1

Completes Attachment 1 of EN-OP-133-02.

Standard: Candidate completes Attachment 1 IAW attached KEY Cue: If asked inform student that the CR number is CR-GGN-2019-0000 Another SRO will perform LCO requirements and ON-Shift Evaluation.

Notes: Highlighted areas are required on Attached Key.

SAT / UNSAT Revision 01 1/13/2020 Page 6 of 9

GJPM-OPS-2-2020AS1 Determine Reportability Time Critical Alternate Path Validation Time: 15 Min Operator: ____________________________________License: RO / SRO Date: __________

Evaluators Name: ______________________ Evaluators Signature:__________________________

Start Time:___________ Stop Time:____________

CRITICAL TIME FRAME: ________Required Time (min):________ Actual Time (min):_________

Task Standard(s):

Determines the ECCS (HPCS) injection due to a valid signal is a 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months reportable event reportable to the NRC Operations Center.

Completes Attachment 1 of EN-OP-133-02 IAW with attached key.

JPM Results (circle one): SAT UNSAT Follow-up Questions:

Follow-up Question Response:

Comments / Feedback:

Revision 01 1/13/2020 Page 7 of 9

EN-OP-133-02 Rev. 0 Page 20 of 55 Grand Gulf Nuclear Station Operations Notifications Attachment 1 KEY DO NOT GIVE TO Page 1 of 1 STUDENT Operational Event (Typical)

CR# _________________________________ Date: _________________________

Brief Description of Condition: Automatic initiation of HPCS to restore level. Actual or required ECCS injection due to a valid signal ______________________________________________________________________________

LCO Required: Yes: ______ No: ______ LCO Number: ________________________________

Rx Power: __0___ MWt __0___ MWe Average. Power Range Monitor (APRM) Flux: ____0_____%

Rx Mode (circle) 1 2 3 4 5 Rx Level: ___30____ Core Flow: ___0_____% Rx Pressure: ___30____ Rx Temperature: __259°F__

Duty Manager Notified: __________________________ Date / Time: _______________________

On-duty Shift Manager: __________________________ On-shift Evaluation Required: Yes ____ No ____

(Required for all operational type occurrences such as scrams, inadvertent actuations, safety/relief valve (SRV) lifts, ECCS injections, etc.)

On-Shift Evaluation LIST equipment / systems which were automatically or manually started: ________________________________

LIST ANY safety system components which should have activated but did not: ___________________________

Systems injecting: ___________________________________________________________________________

Rx Pressure at time of injection: _______________ Flow Rate: _____________________ GPM Source Water Temperature: _________________ Duration of injection: __________________

If SRVs lifted, LIST EACH SRV and RECORD the number of times EACH lifted: ________________________

LIST other equipment / systems that were available and could have performed the same function as the ones that were inoperable at the start of the event or that failed during the event. _____________________________

Effect of the event on safety or operating parameters: RECORD changes in pertinent parameters. GETARS or SENTINEL can be used to document data. (Example - Record changes in reactor coolant temperature if SDC is lost.) ____________________________________________________________________________________

If any safety related equipment was operated beyond its design specifications, LIST components effected.

Parameters exceeded or value operated at: ______________________________________________________

Length of time operated above design limits: ____________________________________

Date / Time conditions restored to normal: ______________________________________

Revision 01 1/13/2020 Page 8 of 9

Give this page to the student Initial Condition(s):

The plant is in Mode 3.

RCIC is OOSVC and isolated.

Shutdown Cooling A was being aligned for operation.

While aligning Shutdown Cooling A, an error caused flow to be diverted to the Suppression Pool via the minimum flow valve.

As reactor water level decreased, RHR isolations and a reactor scram signal initiated at Reactor Level 3.

Reactor water level dropped to -45 inches Wide Range before the inventory reduction was terminated by the successful RHR isolation.

High Pressure Core Spray initiated during the event and restored level to the normal band.

Current reactor parameters:

o water level is +30 inches and stable o Reactor pressure 30 psig o Core Flow 0 Mlbm/hr o Reactor Temp 259°F Initiating Cue(s):

You are the Shift Manager.

Determine the MOST limiting reportability of this incident

Complete Attachment 1 of EN-OP-133-02

Another SRO will complete the On-Shift Evaluation.

Date of Examination: 2/03/2020 Operating Test Number: GGNS 2-2020 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2-2020AS2 2-2020 AS2 GGNS 2-2020 NRC Operating Test Job Performance Measure JPM Number: GJPM-OPS-2-2020AS2 JPM

Title:

Determine Penetration Isolation Requirements Facility Number: GJPM-OPS-AAD16 (If Bank or Modified from Bank)

Prepared By: Steve Reeves 10/1/2019 Exam Developer Date Ops Review: Jonathan Smith 10/3/2019 1st Validation by Ops Rep or Ops Validation Crew Date Validated By: Ronnie Walters / Brandon Meyer 10/10/2019 2nd Validation by Ops Validation Crew Date Approved By: Tracy Tharp 10/24/2019 Project Lead or Exam Team Lead Date

GJPM-OPS-2-2020AS2 Determine Penetration Isolation Requirements New Modified Direct from bank Time Critical Alternate Path Validation Time: 15 Min Setting: Classroom Type: SRO Task: SRO-ADMIN-48, SRO-M&S-5, SRO-NO-16 K&A: 2.2.15 (3.9/4.3), 2.2.40 (3.4/4.7), 2.2.41 (3.5/3.9)

Safety Function: N/A 10CFR 55.45(a) (5)

Performance: Actual Reference(s): EN-OP-102 (Protective and Caution Tagging), Rev 023 02-S-01-17 (Control of Limiting Conditions for Operation), Rev 134 UFSAR Table 6.2-49 (Attached)

E1240-03 (SPCU Isolation Valve Electrical Schematic)

E0300 (Fuse Tabulation)

M-1099 (SPCU P&ID)

Technical Specification 3.6.1.3 Handout(s): EN-OP-102 02-S-01-17 (Control of Limiting Conditions for Operation)

E1240-03 (SPCU Isolation Valve Electrical Schematic)

E0300 page 91 (Fuse Tabulation, P60, Attached)

M1099 (SPCU P&ID) 04-1-01-P60-1 (SPCU SOI, Rev 35)

UFSAR Table 6.2-49 sheet 8 of 17 (Attached)

Technical Specifications

Manipulations: N/A

Critical Steps: 2 Revision 01 1/13/2020 Page 2 of 15

GJPM-OPS-2-2020AS2 Determine Penetration Isolation Requirements Simulator Setup/Required Plant Conditions:

None Safety Concerns:

None Task Standard(s):

The operator identifies valves 1P60F009, 1P60F011, and 1P60F034 must be closed.

The operator identifies 1P60F009 must be deactivated by removing fuse 1P60F016.

Reason For Revision:

Rev 1:

Changed validation time to 15 minutes

Changed summary to 2 critical steps

Added to the cue in step 3 Notify that the air isolation valve for the 1P60-F009 is INOPERABLE Revision 01 1/13/2020 Page 3 of 15

GJPM-OPS-2-2020AS2 Determine Penetration Isolation Requirements Initial Condition(s):

The plant is in Mode 1.

Suppression Pool Cleanup System is shut down.

1P60F010, SPCU RTN FM CNDS PC FLTRS has failed in the open position.

Initiating Cue(s):

As CRS you are tasked to determine the action necessary to satisfy the Tech Spec requirements in accordance with plant procedures.

Revision 01 1/13/2020 Page 4 of 15

GJPM-OPS-2-2020AS2 Determine Penetration Isolation Requirements Notes to Evaluator:

None Task Overview: (Detailed description of task)

The operator will determine the proper tagout to meet Tech Spec Action requirements for INOP valve P60-F010.

Critical tasks are underlined, italicized, and denoted by an (*)

NOTE: The sequence of the following steps is critical unless otherwise noted.

Remember to record Start time Step 1: Technical Specification 3.6.1.3 Action A The operator must determine the required Tech Spec Action is to isolate the affected penetration flow path in accordance with TS 3.6.1.3 Action A.1.

Standard: Determines the required action is TS 3.6.1.3 Action A.1.

Cue: None Notes:

SAT / UNSAT Revision 01 1/13/2020 Page 5 of 15

GJPM-OPS-2-2020AS2 Step 2: 02-S-01-17 step 6.11.1

The operator determines valves 1P60F009, F011, and F034 must be closed.

Standard: The operator must determine the failed valve is the inboard boundary for the affected penetration and the penetration must be isolated using the outboard valve boundaries for the penetration. Determines the appropriate isolation valves for the penetration using UFSAR Table 6.2-49. P&ID M1099 may also be used. Determines 1P60F010, the failed valve, is the inboard isolation valve; therefore, outboard isolation valves 1P60F009, F011, and F034 must be closed.

Cue: None Notes:

SAT / UNSAT Revision 01 1/13/2020 Page 6 of 15

GJPM-OPS-2-2020AS2 Step 3: 02-S-01-17 step 6.11.4

The operator determines fuse 1P60F016 must be removed to electrically deactivate 1P60F009.

Standard: The operator, using E1240-03, determines fuse 1P60F016 must be removed to deactivate 1P60F009. The operator, then using E300, determines Fuse 1P60F016 is the fuse labeled fuse #34 located in 1H13P871 bay G.

Cue: If the operator states he would deactivate 1P60F009 only by closing the local air supply isolation valve, notify that the air isolation valve for the 1P60-F009 is INOPERABLE.

Notes: 02-S-01-17 step 6.11.4 states:

WHEN isolating Primary Containment, Secondary Containment, OR Drywell penetrations to meet action statements of LCOs 3.6.1.3, 3.6.4.2 and 3.6.5.3, USE the following guidance to de-activate automatic valves:

For air-operated valves, PULL the associated fuse OR CLOSE actuator air isolation valve.

SAT / UNSAT Revision 01 1/13/2020 Page 7 of 15

GJPM-OPS-2-2020AS2 Determine Penetration Isolation Requirements Time Critical Alternate Path Validation Time: 15 Min Operator: ____________________________________License: RO / SRO Date: __________

Evaluators Name: ______________________ Evaluators Signature:__________________________

Start Time:___________ Stop Time:____________

CRITICAL TIME FRAME: ________Required Time (min):________ Actual Time (min):_________

Task Standard(s):

The operator identifies valves 1P60F009, 1P60F011, and 1P60F034 must be closed.

The operator identifies 1P60F009 must be deactivated by removing fuse 1P60F016.

JPM Results (circle one): SAT UNSAT Follow-up Questions:

Follow-up Question Response:

Comments / Feedback:

Revision 01 1/13/2020 Page 8 of 15

Give this page to the student Initial Condition(s):

The plant is in Mode 1.

Suppression Pool Clean Up System is shut down.

1P60F010, SPCU RTN FM CNDS PC FLTRS has failed in the open position.

Initiating Cue(s):

As CRS you are tasked to determine the action necessary to satisfy the Tech Spec requirements in accordance with plant procedures.

Date of Examination: 2/03/2020 Operating Test Number: GGNS 2-2020 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2-2020AS3 2-2020 AS3 GGNS 2-2020 NRC Operating Test Job Performance Measure JPM Number: GJPM-OPS-2-2020AS3 JPM

Title:

Tagout Removal Approval Facility Number: GJPM-OPS-AAD09 (If Bank or Modified from Bank)

Prepared By: Steve Reeves 10/1/2019 Exam Developer Date Ops Review: Jonathan Smith 10/3/2019 1st Validation by Ops Rep or Ops Validation Crew Date Validated By: Ronnie Walters / Brandon Meyer 10/10/2019 2nd Validation by Ops Validation Crew Date Approved By: Tracy Tharp 10/24/2019 Project Lead or Exam Team Lead Date

GJPM-OPS-2-2020AS3 Tagout Removal Approval New Modified Direct from bank Time Critical Alternate Path Validation Time: 15 Min Setting: Classroom Type: SRO Task: SRO-ADMIN-48, SRO-M&S-5 K&A: 2.2.13 (4.1/4.3), 2.2.15 (3.9/4.3), 2.2.41 (3.5/3.9) 10CFR 55.45(a) (5)

Safety Function: Equipment Control Performance: Actual Reference(s): EN-OP-102 (Protective and Caution Tagging, Rev 023) 04-1-01-E51-1 (Reactor Core Isolation Cooling System (RCIC) SOI, Rev 142)

E-1185- 9, 10, 14 (RCIC Electrical Schematics)

M-1083B (RCIC P&ID)

Handout(s): EN-OP-102 04-1-01-E51-1 E-1185- 9, 10, 14 M-1083B Tagout Tags Sheet (Attached)

Manipulations: N/A

Critical Steps: 2 Simulator Setup/Required Plant Conditions:

None Safety Concerns:

None Reason For Revision:

Rev 1:

Changed summary to 2 critical steps

Changed completion time to 15 minutes

Added answer key handout.

Changed task standard to state IAW with answer key Revision 01 1/13/2020 Page 2 of 13

GJPM-OPS-2-2020AS3 Tagout Removal Approval Task Standard(s):

In Accordance With the attached KEY:

o The operator identifies restoration sequence for electrical breakers for MOVs should precede restoration of MOV handswitch tags.

o The operator identifies the tagout incorrectly restores RCIC steam supply isolation valves 1E51F063 and F064 OPEN, without slowly warming the steam supply lines per EN-OP-102.

Revision 01 1/13/2020 Page 3 of 13

GJPM-OPS-2-2020AS3 Tagout Removal Approval Initial Condition(s):

The plant is at rated power.

RCIC steam supply was tagged out of service 18 hours2.083333e-4 days 0.005 hours 2.97619e-5 weeks 6.849e-6 months ago for diagnostic (VIPER) testing of 1E51F064.

RCIC steam supply line pressure is now 0 psig on 1H13P601 indicator 1E51R602.

Work has been completed.

1E51F064 has been fully and satisfactorily retested, and the LCO for TS 3.6.1.3 for 1E51F064 has been cleared. An LCO for TS 3.5.3 for RCIC steam supply being isolated remains active.

The clearance has been released by the tagout holder.

Initiating Cue(s):

As CRS you are tasked to:

Ensure appropriate restoration positions and instructions are determined in accordance with procedures and/or plant drawings, and

Ensure appropriate restoration sequences are entered on the tagout.

Document any identified errors for restored positions and/or removal sequences by marking up the tagging forms provided.

Revision 01 1/13/2020 Page 4 of 13

GJPM-OPS-2-2020AS3 Tagout Removal Approval Notes to Evaluator:

Remember to record Start time on page 8.

Task Overview: (Detailed description of task)

The operator will determine the proper tagout restoration positions and sequence for the associated RCIC components.

Critical tasks are underlined, italicized, and denoted by an (*)

NOTE: The sequence of the following steps is critical unless otherwise noted.

Remember to record Start time Step 1: EN-OP-102 step 5.18[1], third bullet The candidate must determine the correct tag restored position for each tagged component (refer to tagout tag listing).

Standard: Determines the appropriate restored position.

Cue: NONE Notes: In general, RCIC must be warmed at a rate of 90°F per hour to limit thermal stress on piping and components. Also, steam supply valves must be opened slowly to limit steam flow below the RCIC steam line flow isolation setpoint, unless the trip function has been defeated. RCIC steam supply valves 1E51F063, F064, and F076 should be restored as CLOSED before beginning warming per SOI 04-1-01-E51-1 section 4.1.

If the candidate elects to leave the restored positions for 1E51F063 and 1E51F064 as OPEN with explicit restoration instructions to warm RCIC per 04-1-01-E51-1 section 4.1 as the method of restoring the valves OPEN, this is acceptable.

SAT / UNSAT Revision 01 1/13/2020 Page 5 of 13

GJPM-OPS-2-2020AS3 Step 2: EN-OP-102 step 5.18[1], fourth bullet The operator must determine the correct tag removal sequence for each tagged component (refer to tagout tag listing).

Standard: Determines the appropriate removal sequence.

Cue: NONE Notes: In general, electrical power for valves will be restored and tags removed from breakers and fuses, then handswitches will be aligned and handswitch tags removed last. Also, it would be typical to remove the local tag on a MOV before restoring the valves breaker, but in this case there are no local handwheel tags, since 1E51F063 and F076 are inaccessible in the drywell and VIPER testing 1E51F064 is prohibitive of a handwheel tag.

SAT / UNSAT Revision 01 1/13/2020 Page 6 of 13

GJPM-OPS-2-2020AS3 Step 3: EN-OP-102 step 5.18[1], third and fourth bullets

The Operator documents the following:

Tags must be removed from valve electrical supply breakers and restored before removing tags from handswitches.

Standard: Documents corrections.

Cue:

Notes: Corrections listed are the minimum required to prevent adverse plant effects. Any corrections that demonstrate an equivalent understanding is acceptable.

Electrical power for a MOV must be restored before its respective handswitch is restored to enable remote position indication and control function for the handswitch.

SAT / UNSAT Revision 01 1/13/2020 Page 7 of 13

GJPM-OPS-2-2020AS3 Step 4: EN-OP-102 step 5.18[1], third and fourth bullets

The Operator documents the following:

Restored positions for 1E51F063 AND/OR 1E51F076 and 1E51F064 must be closed, OR adequate removal instructions are added to warm RCIC per 04 01-E51-1 section 4.1 as the method for restoring 1E51F063 and 1E51F064 open.

Standard: Documents corrections.

Cue: NONE Notes: Corrections listed are the minimum required to prevent adverse plant effects. Any corrections that demonstrate an equivalent understanding is acceptable.

RCIC steam lines must be warmed per section 4.1 of SOI 04-1-01-E51-1 to prevent excessive thermal stress on piping and components and to prevent RCIC steam flow high isolation actuation, unless bypassed. For RCIC steam line warming, initial SOI position of 1E51F063, F064, and F076 is fully closed. As such, if the candidate specifies restored positions for these valves as CLOSED, before RCIC is warmed, this is acceptable.

Similarly, if the candidate elects to leave the listed restored positions for 1E51F063 and 1E51F064 as OPEN with explicit restoration instructions to warm RCIC per 04-1-01-E51-1 section 4.1 as the method of restoring the valves OPEN, this is acceptable.

The task is complete when the operator determines the adequacy for this Tagout.

SAT / UNSAT Revision 01 1/13/2020 Page 8 of 13

GJPM-OPS-2-2020AS3 Tagout Removal Approval Time Critical Alternate Path Validation Time: 15 Min Operator: ____________________________________License: RO / SRO Date: __________

Evaluators Name: ______________________ Evaluators Signature:__________________________

Start Time:___________ Stop Time:____________

CRITICAL TIME FRAME: ________Required Time (min):________ Actual Time (min):_________

Task Standard(s):

In Accordance With the attached KEY:

o The operator identifies restoration sequence for electrical breakers for MOVs should precede restoration of MOV handswitch tags.

o The operator identifies the tagout incorrectly restores RCIC steam supply isolation valves 1E51F063 and F064 OPEN, without slowly warming the steam supply lines per EN-OP-102.

JPM Results (circle one): SAT UNSAT Follow-up Questions:

Follow-up Question Response:

Comments / Feedback:

Revision 01 1/13/2020 Page 9 of 13

GJPM-OPS-2-2020AS3 NUCLEAR NON-QUALITY RELATED EN-OP-102-01 REV.14 MANAGEMENT MANUAL MULTI-USE: INFORMATIONAL USE PAGE 7 OF 31 AND REFERENCE USE Protective and Caution Tagging Forms & Checklist KEY DO NOT GIVE TO APPLICANT ATTACHMENT 9.3 TAGOUT TAGS SHEET CLEARANCE: ____MANUAL________ TAGOUT: 1CXX-1 E51-001 - 1E51F064 Tag Tag Equipment Place. Place. Rest. 1st Rest. 2nd Placement/

Serial Type Equipment Description Place. Placement 1st Verif 2nd Verif Rest. Restoration Verif Verif Removal No. Equipment Location Seq. Configuration Date/Time Date/Time Seq. Configuration Date/Time Date/Time Tag Notes 1-E51 -IBISSW-1E51M620 Hoge, AUTO Knox, Tim

RCIC STM LINE WARMUP Tom AUTO AFTER 0001 Danger 1 AFTER 2/15/20XX 1 2 VLV 1E51F076 2/15/20XX CLOSED CLOSED 05:35

C0A-166 -0C503- 05:00 1-E51 -IBISSW-1E51M609 Hoge, Knox, Tim

RCIC STM SPLY DRWL Tom OPEN 0002 Danger 1 CLOSE 2/15/20XX 1 2 INBD ISOL 1E51F063 2/15/20XX CLOSED 05:40

C0A-166 -0C503- 05:05 1-E51 -IBISSW-1E51M610 Hoge, Knox, Tim

RCIC STM SPLY DRWL Tom OPEN 0003 Danger 1 CLOSE 2/15/20XX 1 2 OTBD ISOL 1E51F064 2/15/20XX CLOSED 05:45

C0A-166 -0C503- 05:10 1-E51 -CTKBRK- 52-163138 Bow, Bill Sims, Matt

RCIC STM LINE WARMUP 0009 Danger 2 OFF 2/15/20XX 2/15/20XX 2 1 CLOSED VLV 1E51F076 06:15 07:15

A08-119 -1A207-1-E51 -CTKBRK- 52-163134 Bow, Bill Sims, Matt

RCIC STM SPLY DRWL 0010 Danger 2 OFF 2/15/20XX 2/15/20XX 2 1 CLOSED INBD ISOL 1E51F063 06:20 07:20

A08-119 -1A207-1-E51 -CTKBRK- 52-153129 Test Bow, Bill Sims, Matt

RCIC STM SPLY DRWL 0011 and 2 OFF 2/15/20XX 2/15/20XX 2 1 CLOSED OTBD ISOL 1E51F064 Maint 06:25 07:25

A07-119 -1A208-Revision 01 1/13/2020 Page 10 of 13

Give this page to the student Initial Condition(s):

The plant is at rated power.

RCIC steam supply was tagged out of service 18 hours2.083333e-4 days 0.005 hours 2.97619e-5 weeks 6.849e-6 months ago for diagnostic (VIPER) testing of 1E51F064.

RCIC steam supply line pressure is now 0 psig on 1H13P601 indicator 1E51R602.

Work has been completed.

1E51F064 has been fully and satisfactorily retested, and the LCO for TS 3.6.1.3 for 1E51F064 has been cleared. An LCO for TS 3.5.3 for RCIC steam supply being isolated remains active.

The clearance has been released by the tagout holder.

Initiating Cue(s):

As CRS you are tasked to:

Ensure appropriate restoration positions and instructions are determined in accordance with procedures and/or plant drawings, and

Ensure appropriate restoration sequences are entered on the tagout.

Document any identified errors for restored positions and/or removal sequences by marking up the tagging forms provided.

NUCLEAR NON-QUALITY RELATED EN-OP-102-01 REV.14 MANAGEMENT MANUAL MULTI-USE:

INFORMATIONAL USE AND PAGE 6 OF 31 REFERENCE USE Protective and Caution Tagging Forms & Checklist ATTACHMENT 9.2 TAGOUT COVER SHEET Clearance: MANUAL_______ Tagout: 1CXX-1 E51-001 - 1E51F064 Component to be worked:

1E51F064 RCIC STM SPLY DRWL OTBD ISOL

==

Description:==

THIS TAGOUT WILL ISOLATE THE RCIC STEAM SUPPLY TO PERFORM VIPER TESTING ON 1E51F064 TEST AND MAINTENANCE TAGS ARE BEING USED FOR 1E51F064 SINCE IT WILL BE OPERATED FOR ELECTRICAL MAINTENANCE Placement Inst:

HANG TAGS IN SEQUENCE LISTED. 1E51F063 AND 1E51F076 HANDWHEELS ARE NOT BEING TAGGED LOCALLY DUE TO THEY ARE INACCESSIBLE (IN THE DRYWELL).

Hazards:

HIGH ENERGY SYSTEM.

RCIC STEAM PIPING WILL BE EXTREMELY HOT.

Restoration Inst:

CLEAR TAGOUT FIRST.

AFTER TAGOUT HAS BEEN CLEARED, THEN PLACE RCIC SYSTEM IN STANDBY MODE PER SOI 04-1-01-E51-1 SECTION 4.1.

Attribute Description Attribute Value HIGH ENERGY SYSTEM CONCERNS YES - SEE TAGOUT HAZARDS TECH SPEC IMPACT? LCO 1-TS-XX-0001 COMPENSATORY ACTIONS REQUIRED? NO SCAFFOLD REQUIRED NO WALKDOWN COMPLETE YES TAGOUT PREPARE ISSUES: NO Work Order Number Description XX357XX PERFORM DIAGNOSTIC TESTING (VIPER) FOR 1E51F064 Status Description User Verification Date Prepared Prepared Taw Jackson 2/1/20XX Technical Reviewed Reviewed John T. Chance 2/2/20XX Approved Approved George W. McLintock 2/3/20XX Tags Verified Hung Tags Verified Hung Tim Knox 2/15/20XX Removal Approved Removal Approved Tags Verified Removed Tags Verified Removed

NUCLEAR NON-QUALITY RELATED EN-OP-102-01 REV.14 MANAGEMENT MANUAL MULTI-USE: INFORMATIONAL USE PAGE 7 OF 31 AND REFERENCE USE Protective and Caution Tagging Forms & Checklist ATTACHMENT 9.3 TAGOUT TAGS SHEET CLEARANCE: ____MANUAL________ TAGOUT: 1CXX-1 E51-001 - 1E51F064 Tag Tag Equipment Place. Place. Rest. 1st Rest. 2nd Placement/

Serial Type Equipment Description Place. Placement 1st Verif 2nd Verif Rest. Restoration Verif Verif Removal No. Equipment Location Seq. Configuration Date/Time Date/Time Seq. Configuration Date/Time Date/Time Tag Notes 1-E51 -IBISSW-1E51M620 Hoge, AUTO Knox, Tim

RCIC STM LINE WARMUP Tom AUTO AFTER 0001 Danger 1 AFTER 2/15/20XX 1 VLV 1E51F076 2/15/20XX CLOSED CLOSED 05:35

C0A-166 -0C503- 05:00 1-E51 -IBISSW-1E51M609 Hoge, Knox, Tim

RCIC STM SPLY DRWL Tom 0002 Danger 1 CLOSE 2/15/20XX 1 OPEN INBD ISOL 1E51F063 2/15/20XX 05:40

C0A-166 -0C503- 05:05 1-E51 -IBISSW-1E51M610 Hoge, Knox, Tim

RCIC STM SPLY DRWL Tom 0003 Danger 1 CLOSE 2/15/20XX 1 OPEN OTBD ISOL 1E51F064 2/15/20XX 05:45

C0A-166 -0C503- 05:10 1-E51 -CTKBRK- 52-163138 Bow, Bill Sims, Matt

RCIC STM LINE WARMUP 0009 Danger 2 OFF 2/15/20XX 2/15/20XX 2 CLOSED VLV 1E51F076 06:15 07:15

A08-119 -1A207-1-E51 -CTKBRK- 52-163134 Bow, Bill Sims, Matt

RCIC STM SPLY DRWL 0010 Danger 2 OFF 2/15/20XX 2/15/20XX 2 CLOSED INBD ISOL 1E51F063 06:20 07:20

A08-119 -1A207-1-E51 -CTKBRK- 52-153129 Test Bow, Bill Sims, Matt

RCIC STM SPLY DRWL 0011 and 2 OFF 2/15/20XX 2/15/20XX 2 CLOSED OTBD ISOL 1E51F064 Maint 06:25 07:25

A07-119 -1A208-

Date of Examination: 2/03/2020 Operating Test Number: GGNS 2-2020 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2-2020AS4 2-2020 AS4 GGNS 2-2020 NRC Operating Test Job Performance Measure JPM Number: GJPM-OPS-2-2020AS4 JPM

Title:

Emergency Exposure Limits Facility Number: N/A NEW (If Bank or Modified from Bank)

Prepared By: Steve Reeves 1/14/2020 Exam Developer Date Ops Review: Jonathan Smith 1/15/2020 1st Validation by Ops Rep or Ops Validation Crew Date Validated By: Larry Bufkin 1/15/2020 2nd Validation by Ops Validation Crew Date Approved By: Tracy Tharp 1/20/2020 Project Lead or Exam Team Lead Date

GJPM-OPS-2-2020AS4 Emergency Exposure Limits New Modified Direct from bank Time Critical Alternate Path Validation Time: 15 Min Setting: Classroom Type: SRO Task: SRO-A&E-015 K&A: Generic 2.3.4 (3.7)

Safety Function: N/A 10CFR 55.45(a) (5)

Performance: Perform Reference(s): 10-S-01-1 (Activation of the Emergency plan) 10-S-01-17 (Emergency Personnel Exposure Control, Rev 19)

EN-RP-201 (Dosimetry Administration, Rev 5)

Handout(s) 10-S-01-1 (Activation of the Emergency plan) 10-S-01-17 (Emergency Personnel Exposure Control)

EN-RP-201 (Dosimetry Administration)

Manipulations: N/A

Critical Steps: 5 Simulator Setup/Required Plant Conditions:

NONE Safety Concerns:

NONE Revision 00 1/15/2020 Page 2 of 9

GJPM-OPS-2-2020AS4 Emergency Exposure Limits Task Standard:

Determines expected total exposure for the task.

Determines total exposure for each operator

Determines the administrative dose limits are in affect per EN-RP-201

Determines the extension process of EN-RP-201 (Dosimetry Administration) is applicable.

Using table in section 5.4 of EN-RP-201.Determines the following for each operator:

o Operator #1 requires Radiation Protection Manager authorization o Operators #2 and #3 requires Radiation Protection Manager and Plant General Manager authorization Revision 00 1/15/2020 Page 3 of 9

GJPM-OPS-2-2020AS4 Emergency Exposure Limits Initial Condition(s):

The plant is at 55% power.

A job in the Containment is required.

There are high radiation levels in containment.

The task will take 15 minutes inside containment.

Max expected radiation exposure for containment is 10,000 mrem/hr.

An Unusual Event has been declared

Three qualified operators are available and required o Operator #1 current year-to-date exposure TEDE of 320 mrem o Operator #2 current year-to-date exposure TEDE of 560 mrem o Operator #3 current year-to-date exposure TEDE of 600 mrem Initiating Cue(s):

Shift Manager directs you to:

o Determine the current exposure limit o Determine expected exposure for Operator #1, Operator #2 and Operator #3 o Determine approval requirements for this task Revision 00 1/15/2020 Page 4 of 9

GJPM-OPS-2-2020AS4 Emergency Exposure Limits Notes to Evaluator:

Remember to record Start time on page 8.

Task Overview: (Detailed description of task)

The operator will evaluate a condition involving abnormally high radiological conditions and determine actions required to administratively control the dose received by determining who authorizes dose extensions in various situations.

Critical tasks are underlined, italicized, and denoted by an (*)

NOTE: The sequence of the following steps is critical unless otherwise noted.

Step 1: Calculation

Determines expected total exposure following the task.

10,000 mrem 1 hr 15 min = 2,500 mrem hr 60 min Standard: Determines expected total exposure of 2,500 mrem for the task.

Cue: None Notes:

SAT / UNSAT Revision 00 1/15/2020 Page 5 of 9

GJPM-OPS-2-2020AS4 Step 2: EN-RP-201 section 5.4

Determines total exposure for each operator Standard: Determines total exposure for each operator Operator #1 - 320 mrem + 2500 mrem = 2820 mrem Operator #2 - 560 mrem + 2500 mrem = 3060 mrem Operator #3 - 600 mrem + 2500 mrem = 3100 mrem Cue: None Notes:

SAT / UNSAT Step 3: 10-S-01-17 section 6.1.2

Determines the administrative dose limits are in affect per EN-RP-201 Standard: Determines the administrative dose limits are in affect per EN-RP-201.

Cue: None Notes: Even though the site has declared an Unusual Event, it requires an Alert or above to raise the dose limits to the federal limits.

SAT / UNSAT Revision 00 1/15/2020 Page 6 of 9

GJPM-OPS-2-2020AS4 Step 4: EN-RP-201 section 5.4

Determines the extension process of EN-RP-201 (Dosimetry Administration) is applicable.

Standard: Determines the extension process of EN-RP-201 (Dosimetry Administration) is applicable.

Cue: None Notes:

SAT / UNSAT Step 5: EN-RP-201 section 5.4

Determines correct approval requirements Standard: . Using table in section 5.4 of EN-RP-201.Determines the following for each operator:

Operator #1 requires Radiation Protection Manager authorization Operators #2 and #3 requires Radiation Protection Manager and Plant General Manager authorization Cue: None Notes:

Remember to record stop time SAT / UNSAT Revision 00 1/15/2020 Page 7 of 9

GJPM-OPS-2-2020AS4 Emergency Exposure Limits Time Critical Alternate Path Validation Time: 15 Min Operator: ____________________________________License: RO / SRO Date: __________

Evaluators Name: ______________________ Evaluators Signature:__________________________

Start Time:___________ Stop Time:____________

CRITICAL TIME FRAME: ________Required Time (min):________ Actual Time (min):_________

Task Standard(s):

Determines expected total exposure for the task.

Determines total exposure for each operator

Determines the administrative dose limits are in affect per EN-RP-201

Determines the extension process of EN-RP-201 (Dosimetry Administration) is applicable.

Using table in section 5.4 of EN-RP-201.Determines the following for each operator:

o Operator #1 requires Radiation Protection Manager authorization o Operators #2 and #3 requires Radiation Protection Manager and Plant General Manager authorization JPM Results (circle one): SAT UNSAT Follow-up Questions:

Follow-up Question Response:

Comments / Feedback:

Revision 00 1/15/2020 Page 8 of 9

Give this page to the student Initial Condition(s):

The plant is at 55% power.

A job in the Containment is required.

There are high radiation levels in containment.

The task will take 15 minutes inside containment.

Max expected radiation exposure for containment is 10,000 mrem/hr.

An Unusual Event has been declared

Three qualified operators are available and required o Operator #1 current year-to-date exposure TEDE of 320 mrem o Operator #2 current year-to-date exposure TEDE of 560 mrem o Operator #3 current year-to-date exposure TEDE of 600 mrem Initiating Cue(s):

Shift Manager directs you to:

o Determine the current exposure limit o Determine expected exposure for Operator #1, Operator #2 and Operator #3 o Determine approval requirements for this task

Date of Examination: 2/03/2020 Operating Test Number: GGNS 2-2020 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2-2020AS5 2-2020 AS5 GGNS 2-2020 NRC Operating Test Job Performance Measure JPM Number: GJPM-OPS-2-2020AS5 JPM

Title:

PAR Determination Facility Number: N/A NEW (If Bank or Modified from Bank)

Prepared By: Steve Reeves 12/4/2019 Exam Developer Date Ops Review: Jonathan Smith 12/5/2019 1st Validation by Ops Rep or Ops Validation Crew Date Validated By: Ryan Meyer 12/17/2019 2 Validation by Ops Validation Crew nd Date Approved By: Tracy Tharp 12//2019 Project Lead or Exam Team Lead Date

GJPM-OPS-2-2020AS5 PAR Determination New Modified Direct from bank Time Critical Alternate Path Validation Time: 15 Min Setting: Classroom Type: SRO Task: SRO-A&E-041 K&A: 2.4.44 - 2.4/4.4 Safety Function: Emergency Procedures/Plan 10CFR 55.45(a) (5)

Performance: Actual Reference(s): 10-S-01-12 (Radiological Assessment and Protective Action Recommendations, Rev 47) 10-S-01-1 (Activation of the Emergency Plan)

Handout(s): EAL flow charts from 10-S-01-1 10-S-01-1 (available) 10-S-01-12 (Radiological Assessment and Protective Action Recommendations)

Manipulations: N/A

Critical Steps: 4 Simulator Setup/Required Plant Conditions:

None Safety Concerns:

None Reason For Revision:

Rev 1:

Added only to task standard for determining sectors.

Revision 01 1/13/2020 Page 2 of 14

GJPM-OPS-2-2020AS5 PAR Determination Task Standard(s):

Within 15 minutes determine that an Extended PAR is warranted and only sectors C, D, and E should be evacuated to 10 miles.

Sections 5 and 8 of Emergency Notification Form completed correctly.

Revision 01 1/13/2020 Page 3 of 14

GJPM-OPS-2-2020AS5 PAR Determination Initial Condition(s):

The plant was shut down at 0245 this morning by inserting a manual scram.

The site Emergency Plan has been activated.

A site General Emergency was declared at 0718 due to a loss of two barriers and a potential loss of third barrier (FG1).

A Standard PAR was issued with the declaration of a General Emergency at 0718 to evacuate all sectors to 2 miles and sectors R, A, and B to 5 miles.

A new Emergency Notification form (EPP-06-01) has been completed except for items 5 (Recommended Protective Actions) and 8 (Meterological Data).

Containment venting has been in progress for 15 minutes.

Weather is clear.

Initiating Cue(s):

New dose projections and wind direction changes warrant a new notification and PAR recommendation.

The Shift Manager directs you to recommend a new PAR and complete items 5 and 8 of the Emergency Notification Form.

This Task is time critical.

Revision 01 1/13/2020 Page 4 of 14

GJPM-OPS-2-2020AS5 PAR Determination Notes to Evaluator:

Remember to record Start time on page 7 Task Overview: (Detailed description of task)

This task is to use GGNS procedure 10-S-01-12 (Radiological Assessment and Protective Action Recommendations) to determine appropriate PAR actions.

Critical tasks are underlined, italicized, and denoted by an (*)

Step 1: 10-S-01-12 Section 5.2

Using dose data from item 12 of Notification Form, determine that an extended PAR is warranted with evacuation of all sectors 2 miles and sectors C, D, and E to 10 miles.

Standard: Determines new PAR.

Cue:

Notes: This can be determined using only section 5.2.1 or can also reference section 5.2.5.

SAT / UNSAT Revision 01 1/13/2020 Page 5 of 14

GJPM-OPS-2-2020AS5 Step 2: 10-S-01-1 Section 6.1.6.a

Determine that sectors C, D, and E are the only sectors to be filled in on the Emergency Notification form.

Standard: From the given Met Data, determines evacuation for correct sectors.

Cue: None Notes:

SAT / UNSAT Step 3: Emergency Notification form

Check box 5C on the Emergency Notification form and list sectors C, D, and E as the sectors to evacuate to 10 miles.

Standard: Completes the form correctly per page 8.

Cue: None Notes:

SAT / UNSAT Revision 01 1/13/2020 Page 6 of 14

GJPM-OPS-2-2020AS5 Step 4: Emergency Notification form

Completes section 8 of the Emergency Notification Form:

WIND DIRECTION FROM 231 DEGREES At 6 MPH SECTOR(S) AFFECTED (A-R) C, D, AND E Standard: From the given Met Data, completes section 8 of the Emergency Notification form per page 8.

Cue: None Notes:

SAT / UNSAT Revision 01 1/13/2020 Page 7 of 14

GJPM-OPS-2-2020AS5 PAR Determination Time Critical Alternate Path Validation Time: 15 Min Operator: ____________________________________License: RO / SRO Date: __________

Evaluators Name: ______________________ Evaluators Signature:__________________________

Start Time:___________ Stop Time:____________

CRITICAL TIME FRAME: ________Required Time (min):________ Actual Time (min):_________

Task Standard(s):

Within 15 minutes determine that an Extended PAR is warranted and only sectors C, D, and E should be evacuated to 10 miles IAW with attached KEY.

Sections 5 and 8 of Emergency Notification Form completed correctly IAW with attached KEY.

JPM Results (circle one): SAT UNSAT Follow-up Questions:

Follow-up Question Response:

Comments / Feedback:

Revision 01 1/13/2020 Page 8 of 14

GJPM-OPS-2-2020AS5 KEY DO NOT GIVE TO APPLICANT EMERGENCY NOTIFICATION FORM KEY DO NOT GIVE TO APPLICANT

1. THIS IS GRAND GULF NUCLEAR STATION WITH MESSAGE NUMBER

2. A. TIME DATE B. COMMUNICATOR: C. TEL NO. 601-437-

3. EMERGENCY CLASSIFICATION:

A. NOTIFICATION OF UNUSUAL EVENT C. SITE AREA EMERGENCY E. TERMINATED B. ALERT D. GENERAL EMERGENCY

4. CURRENT EMERGENCY CLASSIFICATION DECLARATION TIME: 0718 DATE: Today TERMINATION TIME: DATE:

5. RECOMMENDED PROTECTIVE ACTIONS:

A. No Protective Actions Recommended At This Time (Go to item 6).

B. Consider use of Potassium Iodide in accordance with State Plans.

AND EVACUATE ALL sectors to 2 miles. EVACUATE sectors to 5 miles.

AND MONITOR AND PREPARE the remainder of the 10 mile EPZ with the exception of areas previously recommended for evacuation.

C. Consider use of Potassium Iodide in accordance with State Plans.

AND EVACUATE ALL sectors to 2 miles. EVACUATE sectors C, D, E to 10 miles.

AND MONITOR AND PREPARE the remainder of the 10 mile EPZ with the exception of areas previously recommended for evacuation.

D. Consider use of Potassium Iodide in accordance with State Plans and Shelter:

6.a EAL#: FG1 6.b INCIDENT DESCRIPTION/UPDATE/COMMENTS Loss of two fission product barriers with a potential loss of the third barrier

7. REACTOR SHUTDOWN? NO YES TIME: 0245 DATE: Today

8. METEROLOGICAL DATA: NOT AVAILABLE AT THIS TIME (Go to item 9)

NOTE: If not available is marked, Met Data should be provided as soon as possible on a follow-up Notification Form.

A. WIND DIRECTION FROM 231 Degrees at 6 MPH B. SECTORS AFFECTED (A-R) C, D, E C. STABILITY CLASS (A-G) B D. PRECIPITATION: None Rain Sleet Snow Hail Other

9. RELEASE INFORMATION:

A. NO RELEASE (Go to item 13)

B. A RELEASE is occurring BELOW federally approved operating limits. (Go to item 9E)

C. A RELEASE is occurring ABOVE federally approved operating limits. (Go to item 9E)

D. A RELEASE OCCURRED BUT STOPPED (Go to item Go to item 9E)

E. Release started at 0634 (time) Release stopped at N/A (time) Release Duration 2 hrs (Actual or Expected)

10. TYPE OF RELEASE:

A. Radioactive Gases B. Radioactive Airborne Particulates C. Radioactive Liquids (Go to item 13)

11. RELEASE RATE: A. NOBLE GASES 2.301 Ci/s B. IODINES 0.8743 Ci/s

12. ESTIMATE OF PROJECTED OFF-SITE DOSE: A. Projections for 2 hours based on: Field Data Plant Data B. TEDE - WB DOSE COMMITMENT(mRem) C. CDE - THYROID DOSE COMMITMENT (mRem)

Site Boundary 3422 5 miles 1153 Site Boundary 3953 5 miles 1187 2 miles 2738 10 miles 340 2 miles 3108 10 miles 424

13. MESSAGE APPROVED BY: EMERGENCY DIRECTOR Reviewed Return to communicator instructions line J Sections (3,4,6) Sections(5,7,8,9,10,11,12)

EOF Manager Init RAC Init PAR Change Time EPP 06-01, REV. 27 (10-17)

Revision 00 12/4/2019 Page 9 of 14

GJPM-OPS-2-2020AS5 EMERGENCY NOTIFICATION FORM DO NOT FAX (Only Read items in shaded areas over Operational Hotline) DO NOT FAX THIS SHEET!!

THIS SHEET!!

BEFORE SENDING THE MESSAGE:

BEFORE DIALING:

A. Check items 3 through 13 on the Notification Form to ensure all required items (including reviews) are filled in.

B. Enter message number, date of notification, your name, and telephone number on lines 1 and 2.

C. Check the appropriate boxes in Section M of this form.

DIALING INSTRUCTIONS:

D. Lift the receiver. Note that the new OHL phone do not have a push-to-talk button.

E. As agencies answer say: THIS IS GRAND GULF NUCLEAR STATION, PLEASE STANDBY FOR AN EMERGENCY NOTIFICATION.

F. When the ENF form is in hand at least one agency answers record the time on line 2. (see 10-S-01-6)

G. Allow approximately 30 seconds for agencies to answer. Repeat Line E (above) as necessary.

INITIAL ROLL-CALL: (All agencies are not required to be on-line before reading notification. The Corporate Emergency Center is not manned 24-7 and may not answer until activated.)

H. THIS IS GRAND GULFNUCLEAR STATION, THIS IS AN EMERGENCY NOTIFICATION, STANDBY FOR AN INITIAL ROLL CALL. PLEASE ACKNOWLEDGE AS YOUR NAME IS CALLED:

MS Emergency Management Agency (MEMA) (9-601-933-6362) MS Highway Patrol (MHP) (9-601-987-1530)

Governors Office of Homeland Security/EP (9-1-225-925-6536) LA Dept. of Environmental Quality (LDEQ) (9-1-225-765-0160)

Claiborne County Sheriff's Office (CCSO) (9-601-437-5161) Claiborne County Civil Defense (CCCD) (9-601-437-4684)

Tensas Parish Sheriff's Office (TPSO) (9-1-318-766-3376) Corporate Emergency Center (Entergy) (9-601- 368-5701)

MESSAGE:

I. Read items 1 - 9 and 13 from the Notification Form. Read slowly and deliberately. READ LINE NUMBERS AND LETTERS. Inform them items 10-12 will be sent via fax.

MESSAGE VERIFICATION AND FINAL ROLL-CALL:

J. At least one agency in each row must answer. If no answer, use listed phone numbers as necessary.

K. THIS IS GRAND GULF NUCLEAR STATION, ARE THERE ANY QUESTIONS? Re-read any information requested. If requested information is not on the form, record the request and inform the Emergency Director/Offsite Emergency Coordinator.

L. THIS IS GRAND GULF WITH THE FINAL ROLL-CALL. PLEASE ACKNOWLEDGE RECEIPT OF MESSAGE WHEN YOUR STATION IS CALLED MS Emergency Management Agency (MEMA) (9-601-933-6362) MS Highway Patrol (MHP) (9-601-987-1530)

Governors Office of Homeland Security/EP (9-1-225-925-6536) LA Dept. of Environmental Quality (LDEQ) (9-1-225-765-0160)

Claiborne County Sheriff's Office (CCSO) (9-601-437-5161) Claiborne County Civil Defense (CCCD) (9-601-437-4684)

Tensas Parish Sheriff's Office (TPSO) (9-1-318-766-3376) Corporate Emergency Center (Entergy) (9-601- 368-5701)

COMPLETING THE NOTIFICATION:

M. THIS NOTIFICATION IS COMPLETE, THIS IS THE FINAL MESSAGE.

THE NEXT MESSAGE IS EXPECTED TO BE ISSUED: 60 MINUTES FROM START OF THIS NOTIFICATION WHEN THE EVENT IS TERMINATED THIS IS GRAND GULF OUT.

N. FAX the Emergency Notification form (First page only, not this page) to the other Emergency Response Facilities and Offsite Agencies (ENF Group).

NRC NOTIFICATION: (Notify within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months of initial classification)

O. Nuclear Regulatory Commission (Use ENS Phone)

Name of person Contacted: Time:

P. NRC Resident Inspector (Office: 601-437-2387, Pager: 601-930-7900 or 1-877-400-9673) (Initial Notification Only.)

Caution Revisions to this EPP form should be assessed for their impact against the notification form accuracy requirements of NEI 99-02 and receive a 50.54Q screening.

EPP 06-01 REV. 27 (10-17)

Revision 00 12/4/2019 Page 10 of 14

Give this page to the student Initial Condition(s):

The plant was shut down at 0245 this morning by inserting a manual scram.

The site Emergency Plan has been activated.

A site General Emergency was declared at 0718 due to a loss of two barriers and a potential loss of third barrier (FG1).

A Standard PAR was issued with the declaration of a General Emergency at 0718 to evacuate all sectors to 2 miles and sectors R, A, and B to 5 miles.

A new Emergency Notification form (EPP-06-01) has been completed except for items 5 (Recommended Protective Actions) and 8 (Meterological Data).

Containment venting has been in progress for 15 minutes.

Weather is clear.

Initiating Cue(s):

New dose projections and wind direction changes warrant a new notification and PAR recommendation.

The Shift Manager directs you to recommend a new PAR and complete items 5 and 8 of the Emergency Notification Form.

This Task is time critical.

EMERGENCY NOTIFICATION FORM

1. THIS IS GRAND GULF NUCLEAR STATION WITH MESSAGE NUMBER

2. A. TIME DATE B. COMMUNICATOR: C. TEL NO. 601-437-

3. EMERGENCY CLASSIFICATION:

A. NOTIFICATION OF UNUSUAL EVENT C. SITE AREA EMERGENCY E. TERMINATED B. ALERT D. GENERAL EMERGENCY

4. CURRENT EMERGENCY CLASSIFICATION DECLARATION TIME: 0718 DATE: Today TERMINATION TIME: DATE:

5. RECOMMENDED PROTECTIVE ACTIONS:

A. No Protective Actions Recommended At This Time (Go to item 6).

B. Consider use of Potassium Iodide in accordance with State Plans.

AND EVACUATE ALL sectors to 2 miles. EVACUATE sectors to 5 miles.

AND MONITOR AND PREPARE the remainder of the 10 mile EPZ with the exception of areas previously recommended for evacuation.

C. Consider use of Potassium Iodide in accordance with State Plans.

AND EVACUATE ALL sectors to 2 miles. EVACUATE sectors to 10 miles.

AND MONITOR AND PREPARE the remainder of the 10 mile EPZ with the exception of areas previously recommended for evacuation.

D. Consider use of Potassium Iodide in accordance with State Plans and Shelter:

6.a EAL#: FG1 6.b INCIDENT DESCRIPTION/UPDATE/COMMENTS Loss of two fission product barriers with a potential loss of the third barrier

7. REACTOR SHUTDOWN? NO YES TIME: 0245 DATE: Today

8. METEROLOGICAL DATA: NOT AVAILABLE AT THIS TIME (Go to item 9)

NOTE: If not available is marked, Met Data should be provided as soon as possible on a follow-up Notification Form.

A. WIND DIRECTION FROM Degrees at MPH B. SECTORS AFFECTED (A-R) C. STABILITY CLASS (A-G) B D. PRECIPITATION: None Rain Sleet Snow Hail Other

9. RELEASE INFORMATION:

A. NO RELEASE (Go to item 13)

B. A RELEASE is occurring BELOW federally approved operating limits. (Go to item 9E)

C. A RELEASE is occurring ABOVE federally approved operating limits. (Go to item 9E)

D. A RELEASE OCCURRED BUT STOPPED (Go to item Go to item 9E)

E. Release started at 0634 (time) Release stopped at N/A (time) Release Duration 2 hrs (Actual or Expected)

10. TYPE OF RELEASE:

A. Radioactive Gases B. Radioactive Airborne Particulates C. Radioactive Liquids (Go to item 13)

11. RELEASE RATE: A. NOBLE GASES 2.301 Ci/s B. IODINES 0.8743 Ci/s

12. ESTIMATE OF PROJECTED OFF-SITE DOSE: A. Projections for 2 hours based on: Field Data Plant Data B. TEDE - WB DOSE COMMITMENT(mRem) C. CDE - THYROID DOSE COMMITMENT (mRem)

Site Boundary 3422 5 miles 1153 Site Boundary 3953 5 miles 1187 2 miles 2738 10 miles 340 2 miles 3108 10 miles 424

13. MESSAGE APPROVED BY: EMERGENCY DIRECTOR Reviewed Return to communicator instructions line J Sections (3,4,6) Sections(5,7,8,9,10,11,12)

EOF Manager Init RAC Init PAR Change Time EPP 06-01, REV. 27 (10-17)

EMERGENCY NOTIFICATION FORM DO NOT FAX (Only Read items in shaded areas over Operational Hotline) DO NOT FAX THIS SHEET!!