ML12214A358

Initial Exam 2012-301 Draft Administrative Jpms

ML12214A358
Person / Time
Site:	Farley
Issue date:	07/23/2012
From:	NRC/RGN-II
To:	Southern Nuclear Operating Co
Shared Package
ML12214A278	List: ML12214A258 ML12214A297 ML12214A317 ML12214A335 ML12214A347 ML12214A358 ML12214A458 ML12214A461 ML12214A470 ML12214A480 ML12214A487
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Download: ML12214A358 (71)

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FNP ILT-35 ADMIN Page 1 of 6 A.1.a Admin a ROISRO Conduct of Operations TITLE: Determine maximum RHR flowrate and time to saturation for a loss of RHR event.

EVALUATION LOCATION: SIMULATOR CONTROL ROOM X CLASSROOM PROJECTED TIME: 20 MIN SIMULATOR IC NUMBER: N/A ALTERNATE PATH TIME CRITICAL PRA_____

JPM DIRECTIONS:

1. Initiation of task may be in group setting, evaluation performed individually upon completion.

2. Requiring the exarninee to acquire the required materials may or may not be included as part of the JPM.

TASK STANDARD: Upon successful completion of this JPM, the examinee will:

• Correctly assess and determine the maximum RHR flowrate for the current RCS level.

• Correctly assess and determine the time to core boiling for the current core conditions.

Examinee:

Overall JPM Performance: Satisfactory Unsatisfactory D Evaluator Comments (attach additional sheets if necessary)

EXAMINER:

Developer BR Thornton Date: 2/10/12 NRC Approval SEE NUREG 1021 FORM ES-301-3

FNP-1-AOP-12.0 4-28-2010 Revision 24 FARLEY NUCLEAR PLANT ABNORMAL OPERATING PROCEDURE FNP-1-AOP-12 .0 RESIDUAL HEAT REMOVAL SYSTEM MALFUNCTION S

A F

PROCEDURE USAGE REQUIREMENTS-per FNP-O-AP-6 SECTIONS E T

Continuous Use ALL Y Reference Use R E

Information Use L A

T E

D Approved:

Operations Manager Date Issued:_____________

FNP ILT-35 ADMIN A.1 .a ROISRO Page 2 of 6 CONDITIONS When I tell you to begin, you are to DETERMINE MAXIMUM RHR FLOWRATE AND TIME TO SATURATION FOR A LOSS OF RHR EVENT. The conditions under which this task is to be performed are:

a. The Reactor has been shutdown for 350 hours0.00405 days <br />0.0972 hours <br />5.787037e-4 weeks <br />1.33175e-4 months <br />.

b. Refueling is complete, with 53 new fuel assemblies loaded into the core.

c. An RCS leak had occurred, but it has now been isolated.

d. The 1 A RHR pump started cavitating and RHR flow has been lowered to stop the cavitation per FNP-1-AOP-12.0, Residual Heat Removal Malfunction.

e. Current RCS level is 122 8.5 and stable.

f. Current RCS temperature is 120°F.

g. Perform the following per AOP-12.0:

1) Determine the maximum allowable RHR flowrate.

2) Determine the time to core saturation for a loss of RHR.

INITIATING CUE: IF you have no questions, you may begin.

EVALUATION CHECKLIST RESULTS:

ELEMENTS: STANDARDS: (CIRCLE)

START TIME

• 1. Evaluate Figure 1, RCS HOT LEG LEVEL vs 1) Step 7 of AOP-12.0, Maintain S / U RHR INTAKE FLOW To Minimize Vortexing to RCS level to within the determine maximum allowable RHR flowrate. Acceptable Operating Region of Figure 1, RCS HOT LEG LEVEL vs RHR INTAKE FLOW To Minimize Vortexing for the existing RHR flow.

RCS level is 122 8.5.

Determines that maximum RHR flow is < 1800 gprn.

Allowable tolerance: 1600 -1800 gpm.

FNP LT-35 ADMIN A.1.a RO/SRO Page3of6 EVALUATION CHECKLIST RESULTS:

ELEMENTS: STANDARDS: (CIRCLE)

2. Determine time to core saturation, determine 2) ATTACHMENT 3, step 1.1. S/U appropriate table of ATTACHMENT 3, TABLE A or TABLE B. Determines that Attachment 3, TABLE B is required per ATTACHMENT 3, step 1.1.2, Time to saturation with one third of the spent fuel replaced with new fuel.

3. Determine time to core saturation, determine 3) ATTACHMENT 3, step 1.3. S/U appropriate table of ATTACHMENT 3 based on initial RCS temperature: Determines that page from Table for 100°F Attachment 3, TABLE B for Table for 120°F ASSUMED INITIAL Table for 140°F TEMPERATURE = 120°F is required.

4. Determine time to core saturation, determine 4) ATTACHMENT 3, step 1.2. S/U appropriate column of ATTACHMENT 3, TABLE B ASSUMED INITIAL

, Determines that page from TEMPERATURE 120°F: Attachment 3, TABLE B for ASSUMED INITIAL Time to Saturation at midloop (mins) TEMPERATURE = 120°F, Time to Saturation 3 below flange (mins) column for Time to Saturation at Time to Saturation full Rx cavity (hours) midloop (mins) is required.

FNP ILT-35ADMIN A.1.a ROISRO Page 4 of 6 EVALUATION CHECKLIST RESULTS:

ELEMENTS: STANDARDS: (CIRCLE)

5. Determine time to core saturation. 5) Determines that Time After S / U Shutdown (hours) is 350 hours0.00405 days <br />0.0972 hours <br />5.787037e-4 weeks <br />1.33175e-4 months <br /> and minutes to boiling is calculated to be 21.35 minutes.

300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> = 20.2 minutes 400 hours0.00463 days <br />0.111 hours <br />6.613757e-4 weeks <br />1.522e-4 months <br /> 22.5 minutes 20.2 + 22.5 42.7 42.7/2 = 21.35 minutes After rounding, 21.4 minutes is acceptable.

Since the Time After Shutdown chart oniy shows 300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> and 400 hours0.00463 days <br />0.111 hours <br />6.613757e-4 weeks <br />1.522e-4 months <br />, the candidate may conservatively take the 300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> after shutdown for time to boil of 20.2 minutes.

Allowable tolerance: 20.2 -21.4 minutes.

STOP TIME Terminate when all elements of the task have been completed.

CRITICAL ELEMENTS: Critical Elements are denoted with an asterisk (*) before the element number.

FNP ILT-35 ADMIN A.1.a ROISRO Page 5 of 6 GENERAL

REFERENCES:

1. FNP-1-AOP-12.0, v24 2.KA:G2.1.25 RO (3.9) SRO (4.2)

GENERAL TOOLS AND EOUIPMENT:

1. FNP-1-AOP-12.0,v24

2. Calculator Critical ELEMENT justification:

STEP Evaluation

1. Critical: Task completion: requiri to properly determine Mdmum RHR flowrate.

2-5 Critical: Task completion: ruired to properly determinetimeto coresaturation.

COMMENTS:

KEY AOP-12 RCS level is 122 8.5. Determines that Maximum allowable RHR flowrate maximum RHR flow is < 1800 gprn.

Allowable range: 1600 -1800 gpm 300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> = 20.2 minutes 400 hours0.00463 days <br />0.111 hours <br />6.613757e-4 weeks <br />1.522e-4 months <br /> = 22.5 minutes 20.2 + 22.5 = 42.7 42.7/2 = 21.35 minutes After rounding, 21.4 minutes is acceptable.

Since the Time After Shutdown chart only Time to Core Saturation shows 300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> and 400 hours0.00463 days <br />0.111 hours <br />6.613757e-4 weeks <br />1.522e-4 months <br />, the candidate may conservatively take the 300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> after shutdown for time to boil of 20.2 minutes.

Allowable tolerance: 20.2 -21.4 minutes.

A.1.a ROISRO HANDOUT Pgl of 1 CONDITIONS When I tell you to begin, you are to DETERMINE MAXIMUM RHR FLOWRATE AND TIME TO SATURATION FOR A LOSS OF RHR EVENT. The conditions under which this task is to be performed are:

a The Reactor has been shutdown for 350 hours0.00405 days <br />0.0972 hours <br />5.787037e-4 weeks <br />1.33175e-4 months <br />

b. Refueling is complete, with 53 new fuel ssemblies loaded into the core.

c. An RCS leak had occurred, but it has now been isolated.

d. The IA RHR pump started cavitating and RHR flow has been lowered totop the cavitation per

e. Current RCS level is 122 8.5 and stable.

N f Current RCS temperature is 120°F

g. Perform the fo1lowingpeAQP+20

1) Determine the maximum allowable RHR flowrate.

2) Determine the time to core saturation for a loss of RHR.

AOP-12 Maximum allowable RHR flowrate Time to Core Saturation

FNP-l-AOP-12.O RESIDUAL HEAT REMOVAL SYSTEM MALFUNCTION Revision 24 TABLE OF CONTENTS Procedure Contains Number of Pages Body 24 Figure 1 1 Attachment 1 9 Attachment 2 4 Attachment 3 7 Attachment 4 1 Page 1 of 1

FNP-1-AOP-12.0 RESIDUAL HEAT REMOVAL SYSTEM MALFUNCTION Revision 24 A. Purpose This procedure provides actions for response to a malfunction of the RHR system.

Actions in this procedure for restoring RHR PUMPs assume electrical power is available. During loss of electrical power conditions, FNP-l-AOP-5.0, LOSS OF A OR B TRAIN ELECTRICAL POWER, provides actions for restoration of electrical power which should be performed in addition to continuing with this procedure.

The first part of this procedure deals with the protection of any running RHR pump and isolation of any leakage. If a running train is maintained the procedure is exited. The next portion deals with restoring a train of RHR while monitoring core temperatures. If a train cannot be restored actions are take for protection of personnel, establishing containment closure, and provides alternate methods of decay heat removal while trying to restore a train of RHR. Alternate cooling methods include: establishing a secondary heat sink if steam generators are available; feed and bleed cooling and feed and spill cooling.

The intent of feed and bleed cooling is to regain pressurizer level and allow steaming through a bleed path to provide core cooling. This requires that the RCS be in a configuration that will allow a level in the pressurizer.

The intent of feed and spill cooling is to allow spillage from the RCS and locally throttle injection flow to provide core cooling. This method is used when the reactor vessel head is blocked or RCS loop openings exist.

This procedure is applicable in modes 4, 5 and 6.

Containment closure is required to be completed within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of the initiating event unless an operable RHR pump is placed in service cooling the RCS the RCS temperature is below 180° F.

Page 1 of 24

FNP-1-AOP-12.O RESIDUAL HEAT REMOVAL SYSTEM MALFUNCTION Revision 24 B. Symptoms or Entry Conditions This procedure is entered when a malfunction of the R}IR system is indicated by any of the following:

1.1 Trip of any operating RUR pump 1.2 Excessive RHR system leakage 1.3 Evidence of running RHR pump cavitation 1.4 Closure of loop suction valve 1.5 High RCS or core exit T/C temperature 1.6 Procedure could be entered from various annunciator response procedures.

CF3 1A lB RHR PUMP OVERLOAD TRIP CF4 1A RHR HX OUTLET FLOW LO CF5 lB RHR HX OUTLET FLOW LO CG3 1A lB RHR HX CCW DISCH FLOW HI EA5 1A OR lB RHR PUMP CAVITATION EB5 MID-LOOP CORE EXIT TEMP HI EC5 RCS LVL HI-LO Page 2 of 24

FNP-1-AOP-12.0 RESIDUAL HEAT REMOVAL SYSTEM MALFUNCTION Revision 24 Step Action/Expected Response Response NOT Obtained I I I CAUTION: Containment closure is required to be completed within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of the initiating event unless an operable RHR pump is placed in service cooling the RCS the RCS temperature is below 180° F.

CAUTION: Filling the pressurizer to 100% will cause a loss of nozzle dams due to the head of water.

NOTE: RCS to RHR loop suction valves will be deenergized if RCS TAVG is less than 180°F.

1 Check R}W loop suction valves - 1 Stop any RHR PUMP with closed OPEN, loop suction valve(s).

1.1 j required, RHR PUMP 1A lB THEN adjust charging flow to maintain RCS level.

1C(1A) RCS LOOP TO 1A(1B) RHR PUMP Q1E11MOV [1 8701A [1 8702A

[1 8701B [1 8702B 1C(1A) RCS LOOP TO 1A(1B) RHR PUMP [1 FU-T5 [] FU-G2 LOOP SUCTION POWER [1 FV-V2 [] FV-V3 SUPPLY BREAKERS CLOSED (IF REQUIRED) 2 IF the cause of the RHR malfunction is known AND does not affect the standby RHR train, THEN place the standby RHR train in service per FNP-1-SOP-7.O, RESIDUAL HEAT REMOVAL SYSTEM.

Page 3 of 24

FNP-l-AOP-12.O RESIDUAL HEAT REMOVAL SYSTEM MALFUNCTION Revision 24 Step Action/Expected Response Response NOT Obtained I I I I NOTE: Rapid flow adjustments may cause more severe pump cavitation.

3 Check RRR PUMPs - NOT 3 Perform the following:

CAVITATING.

3.1 Slowly reduce RHR flow rate to The following parameters should eliminate cavitation.

be stable and within normal ranges. 3.2 IF cavitation CANNOT be

[1 RHR flow rate within the eliminated, Acceptable Operating Region of THEN stop the affected RHR FIGURE 1, RCS HOT LEG LEVEL vs pump(s).

RHR INTAKE FLOW To Minimize Vortexing.

[1 Discharge pressure

[1 Suction pressure

[1 RHR motor ammeter readings

[1 No unusual pump noise 4 Check any RHR PUMP - RUNNING 4 Proceed to step 13.

5 Verify RRR flow > 3000 gpiu. 5 Refer to Technical Specifications 3.9.4 and 3.9.5 1A(1B) for applicability.

RHR HDR FLOW

[1 Fl 605A

[1 Fl 6053 Page 4 of 24

FNP-l-AOP-l2.0 RESIDUAL HEAT REMOVAL SYSTEM MALFUNCTION Revision 24 Step Action/Expected Response Response NOT Obtained I I I CAUTION: Indicated RCS level will rise approximately 1 ft for every 0.5 psi rise in RCS pressure if the indication is not pressure compensated.

CAUTION: Only borated water should be added to the RCS to maintain adequate shutdown margin.

6 Check RCS level ADEQUATE 6.1 Compare any available level indications.

[1 LT 2965A&B/level hose

[1 LI-2384 lB LOOP RCS NR LVL

[1 LI-2385 lC LOOP RCS NR LVL

[1 Temporary remote level indicator off of a RCS FT on A or C loop 6.2 Check RCS level within the 6.2 Raise RCS level.

Acceptable Operating Region of FIGURE 1. RCS HOT LEG LEVEL vs 6.2.1 Notify personnel in RHR INTAKE FLOW To Minimize containment that RCS level Vortexing. will be raised.

6.2.2 Align Technical Requirements Manual boration flow path.

6.2.3 Raise RCS level to within the Acceptable Operating Region of FIGURE 1, RCS HOT LEG LEVEL vs RHR INTAKE FLOW To Minimize Vortexing for the existing RHR flow.

Page 5 of 24

FNP-1-AOP-12.O RESIDUAL HEAT REMOVAL SYSTEM MALFUNCTION Revision 24 Step Action/Expected Response Response NOT Obtained I I I 7 Naintain RCS level within the 7 Verify RHR PUMP(s) stopped following limits: proceed to step 13.

[1 Maintain RCS level to within the Acceptable Operating Region of FIGURE 1, RCS HOT LEG LEVEL vs RHR INTAKE FLOW To Minimize Here the candidate will have to Vortexing for the existing RHR determine the max RHR flow flow.

Li Maintain RCS level less than 123 ft 4 in if personnel are in the channel heads without nozzle dams installed.

[j Maintain RCS level less than 123 ft 9 in if primary manways are removed without nozzle dams installed.

H Maintain RCS level less than 123 ft 9 in if seal injection is not established and RCPs are not backseated.

[] Maintain RCS level less than 124 ft if safety injection check valves are disassembled.

Page 6 of 24

FNP-1-AOP-12.O RESIDUAL HEAT REMOVAL SYSTEM MALFUNCTION Revision 24 FIGURE 1 RCS HOT LEG LEVEL vs RHR INTAKE FLOW To Minimize Vortexing RCS HOT LEG LEVEL vs RHR INTAKE FLOW To Minimize Vortexing 1221 T 12211W I ACCEPTABLE OPERATING_REGIOE

-J 1221O Lii

/

Ui I

1229 7/

12218n 1227 1 226 1000 1500 2000 2500 3000 RHR INTAKE FLOW (GALJMIN)

Page 1 of 1

FNP-1-A0P12.O RESIDUAL HEAT REMOVAL SYSTEM MALFUNCTION Revision 24 ATTACHMENT 3 Time to Core Saturation TABLE B---POWER UPRATED UNIT TIME TO SATURATION:IONE THIRD NEW FUEL I ASSUMED INITIAL TEMPERATURfr1200F Time After ime to Saturation Time to Saturation Time to Saturation 3t Shutdown (hours) t midloop (mins) below flange full Rx cavity (mins) (hours) 17.5 9.2 23.4 12.4 27.6 14.6 30.8 16.3 500 25.4 34.8 18.4 600 28.3 38.7 20.5 700 30.5 41.7 22.1 800 33.0 45.2 23.9 VOLUME REFERENCE TABLE MIDLOOP VOLUME (FT

)

3 VOLUME 3FT BELOW FLANGE(FT

)

3 VOLUME FULL REACTOR CAVITY(FT

)

3 Page 6 of 7

FNP ILT-35 ADMIN Page 1 of 7 A.Lb RO Conduct of Operations G2. 1.5 TITLE: IDENTIFY THE TECHNICAL SPECIFICATION AND EMERGENCY ORGANIZATION ON-SHIFT MANNING REQUIREMENTS FOR THE CONDITIONS PROVIDED.

EVALUATION LOCATION: D SIMULATOR D CONTROL ROOM I CLASSROOM PROJECTED TIME: 20 MIN SIMULATOR IC NUMBER: N/A D ALTERNATE PATH D TIME CRITICAL D PRA JPM DIRECTIONS:

1. Initiation of task may be in group setting, evaluation performed individually upon completion.

2. Requiring the examinee to acquire the required materials may or may not be included as part of the JPM.

TASK STANDARD: Upon successful completion of this JPM, the examinee will:

• Correctly determine if an oncoming Operations crew satisfies the minimum Operations shift staffing requirements of EIP-0.0

• Correctly state the minimum required Reactor Operators per FNP-0-SOP-0.0 (TS 5.2.2(a))

• Correctly identifi the required actions if minimum shift staffing requirements are not satisfied per EIP-0.0 step 4.8.2 AND/OR TS 5.2.2.C.

Examinee:

Overall JPM Performance: Satisfactory Unsatisfactory E1 Evaluator Comments (attach additional sheets if necessary)

EXAMINER:

Developer Howard Fitzwater Date: 2/10/20 12 NRC Approval SEE NUREG 1021 FORM ES-301-3

FNP ILT-35 ADMIN A.1.b RO Page 2 of 7 CONDITIONS When I tell you to begin, you are to IDENTIFY THE TECHNICAL SPECIFICATION AND EMERGENCY ORGANIZATION ON-SHIFT MANNING REQUIREMENTS FOR THE CONDITIONS PROVIDED. The conditions under which this task is to be performed are:

a. Both Units are at 100% power.

b. It is Night shift on a holiday, and the Operations Manager has authorized maximizing time off.

c. The table below represents the Operations shift complement that has arrived to receive turnover and their license level/status.

PERSON LICENSE status/qual ACTIVE Adam Dual Unit- SRO SM ACTIVE Bob Dual Unit- SRO Charlie Doug ACTIVE Eugene Dual Unit Frank RO INACTIVE Gary Dual Unit- SRO SSS-STA INACTIVE Harry Dual Unit- SRO SSS-Fire Jack Kelly Lisa

. Not licensed Mike 5Q Nick Oscar Pam Not Licensed Roger Fire Protection Administrator Qualified_Shift_Communicator

d. PROVIDE a written response to the following in accordance with SOP-O.O, General Instruction to Operations Personnel, and EIP-O.O, Emergency Organization:

o IDENTIFY whether or not the operations crew shown in the table above satisfies the requirements to take the shift without any additional action or personnel?

o STATE the minimum number of on-shift Reactor Operators required by Technical Specifications.

o Identify the required actions anytime the requirements for minimum on-shift staffing are NOT met.

FNPILT-35ADMIN A.1.bRO Page3of7 iNITIATING CUE: You may begin.

EVALUATION CHECKLIST RESULTS:

ELEMENTS: STANDARDS: (CIRCLE)

START TIME:

• 1. REVIEW shift Staffing levels per SOP-O.O & *IDENTIFY the MINIMUM S / U EIP-O.O. shift staffing is satisfied by circling: YES

• 2. REVIEW shift Staffing levels per SOP-O.O. *IDENTIFY the MINIMUM S / U number of Reactor Operators necessary to satisfy TS by writing: THREE (3)

• 3. REVIEW required actions for falling below

• S / U IDENTIFY that the required minimum shift Staffing levels per EIP-O.O AND action is to:

OR TS 5.2.2.c.

IMMEDIATELY INITIATE action to fill the vacant position within two HOURS.

OR LISTS the TS requirement 5.2.2.(c)

AND/OR the procedural step EIP-O.O paragraph 4.8.2.

FNP ILT-35 ADMIN A.1 .b RO Page 4 of 7 EVALUATION CHECKLIST RESULTS:

ELEMENTS: STANDARDS: (CIRCLE)

ANSWER KEY:

1. Does the crew shown in the table satisfy the MINIMUM shift staffing requirements of SOP-O.O and EIP-O.O. YES NO

2. The Technical Specification minimum required number of Plant/Reactor Operators required on-shift is ONE OATC FOR EACH UNIT AND ONE UO SHARED BETWEEN THE UNITS for a total of THREE (3):

it is EQUALLY acceptable simply state: THREE (3)

3. ANYTIME the minimum on-shift staffing requirements are NOT met the actions required are:

IMMEDIATELY INITIATE ACTION TO FILL THE VACANT POSITION(s) within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. it is EQUALLY acceptable simply state: EIP-O.O, v27 para 4.8.2 or TS 5.2.2.c EIP-O. 0 v2 7 paragraph 4.8.2 states:

The shift crew composition may be one less than the table 1 requirenlents for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence ofon-duty shift crew members [...]provided immediate action is taken to restore the shift crew composition to within the Table 1 requirements TS 5.2.2.c states:

Shift crew composition may be less than the minimum requirement of 10 CFR

,)(V and 5.2.2. a and 5.2. 2.gfor a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order

50. 54m,.)(

2 to accommodate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements.

STOP TIME Terminate when all elements of the task have been completed.

CRITICAL ELEMENTS: Critical Elements are denoted with an asterisk (*) before the element number.

FNPILT-35ADMIN A.1.bRO Page5of7 GENERAL

REFERENCES:

1. FNP-O-EIP-O.O, V 27

2. FNP-O-SOP-O.O, V 149.1

2. KA: G2.1.5 RO 2.9 SRO 3.9 GENERAL TOOLS AND EOUIPMENT:

Provide/Acquire:

1. FNP-O-EIP-O.O, V 27

2. FNP-O-SOP-O.O, V 149.1 Critical ELEMENT justification:

STEP Evaluation

1. CRITICAL: TASK objective

2. CRITICAL: TASK objective

3. CRITICAL: TASK objective COMMENTS:

FNPILT-35ADMIN A.1.bRO HANDOUT Page 1 of2 CONDITIONS When I tell you to begin, you are to IDENTIFY THE TECHNICAL SPECIFICATION AND EMERGENCY ORGANIZATION ON-SHIFT MANNING REQUIREMENTS FOR THE CONDITIONS PROVIDED. The conditions under which this task is to be performed are:

a. Both Units are at 100% power.

b. It is Night shift on a holiday, and the Operations Manager has authorized maximizing time off.

c. The table below represents the Operations shift complement that has arrived to receive turnover and their license level/status.

PERSON LICENSE status/gual ACTIVE Adam Dual Unit- SRO SM ACTIVE Bob Dual Unit- SRO Charlie SS Doug ACTIVE Eugene Dual Unit Frank RO INACTIVE Gary Dual Unit- SRO SSS-STA INACTIVE Harry Dual Unit- SRO SSS-Fire Jack Kelly Lisa Not licensed Mike SO Nick Oscar Pam Not Licensed Roger Fire Protection Administrator Qualified_Shift_Communicator

d. PROVIDE a written response to the following in accordance with SOP-O.O, General Instruction to Operations Personnel, and EIP-O.O, Emergency Organization:

o IDENTIFY whether or not the operations crew shown in the table above satisfies the requirements to take the shift without any additional action or personnel?

o STATE the minimum number of on-shift Reactor Operators required by Technical Specifications.

o Identify the required actions anytime the requirements for minimum on-shift staffing are NOT met.

FNPILT-35ADMIN A.1.bRO HANDOUT Page 2 of 2

1. Does the crew shown in the table satisi the MiNIMUM Operations shift staffing requirements of SOP-O.O and EIP-O.O? YES I NO

2. The Technical Specification minimum required number of Reactor Operators required on-shift is:

3. ANYTIME the minimum on-shift staffing requirements are NOT met the actions required are:

FNP ILT-35 ADMIN Page 1 of 7 A.1.b SRO-only Conduct of Operations G2. 1.5 TITLE: IDENTIFY THE TECHNICAL SPECIFICATION AND EMERGENCY ORGANIZATION ON-SHTFT MANNING REQUIREMENTS FOR THE CONDITIONS PROVIDED.

EVALUATION LOCATION: D SIMULATOR D CONTROL ROOM l CLASSROOM PROJECTED TIME: 20 MIN SIMULATOR IC NUMBER: N/A D ALTERNATE PATH D TIME CRITICAL D PRA JPM DIRECTIONS:

1. Initiation of task may be in group setting, evaluation performed individually upon completion.

2. Requiring the examinee to acquire the required materials may or may not be included as part of the JPM; it is intended that the examinees be logged into a computer using the EXAM LOGIN and accessing the EXAM REFERENCE DISK to obtain/review the required references.

TASK STANDARD: Upon successful completion of this JPM, the examinee will:

• Correctly identify whether or not a shift compliment satisfies the minimum operations shift staffing requirements per EIP-0.0 (TS 5.2.2(a))

• Correctly assess that EIP-0.0 does NOT permit voluntarily reducing minimum shift staffing any further than one (1) below minimum.

• Correctly identify the Actions required by FNP-0-EIP-0.0 step 4.8.2 AND/OR TS 5.2.2.C if Operations shift staffing falls below minimum.

Examinee:

Overall JPM Performance: Satisfactory Unsatisfactory 1J Evaluator Comments (attach additional sheets if necessary)

EXAMINER:

Developer Howard Fitzwater Date: 2/10/20 12 NRC Approval SEE NUREG 1021 FORM ES-301-3

FNP ILT-35 ADMIN Al .b SRO Page 2 of 7 CONDITIONS When I tell you to begin, you are to IDENTIFY THE TECHNICAL SPECIFICATION AND EMERGENCY ORGANIZATION ON-SHIFT MANNING REQUIREMENTS FOR THE CONDITIONS PROVIDED. The conditions under which this task is to be performed are:

a. Both Units are at 100% power.

b. It is Night shift on a holiday, and The Operations Manager has authorized maximizing time off.

c. The table below represents the Operations shift complement that has arrived to receive turnover and their license level/status.

PERSON LICENSE status/gual ACTIVE Adam Dual Unit- SRO SM ACTIVE Bob Dual Unit- SRO Charlie Doug ACTIVE Eugene Dual Unit Frank RO INACTIVE Gary Dual Unit- SRO SSS-STA INACTIVE Harry Dual Unit- SRO SSS-Fire Jack Kelly Lisa

. Not licensed Mike SO Nick Oscar Pam Not Licensed Roger Fire Protection Administrator Qualified_Shift_Communicator

d. PROVIDE a written response to the following in accordance with SOP-O.O, General Instruction to Operations Personnel, and EIP-O.O, Emergency Organization:

o IDENTIFY whether or not the crew shown in the table above satisfies the requirements to take the shift without any additional action or personnel, o Consider a minimally staffed crew, and a Reactor Operator experiences chest pains requiring him/her to be transported to the hospital. Determine if the SSS-Fire is permitted to escort the Reactor Operator to the hospital per EIP-0.0, and o Identify the required actions anytime the requirements for minimum on-shift staffing are NOT met.

FNPLT-35ADMtN A.1.bSRO Page3of7 INITIATING CUE: You may begin.

EVALUATION CHECKLIST RESULTS:

ELEMENTS: STANDARDS: (CIRCLE)

START TIME:

• 1. REVIEW shift Staffing levels per SOP-O.O & *IDENTIFY the MINIMUM S / U EIP-O.O. shift staffing is satisfied by circling: YES

2. REVIEW shift Staffing levels per EIP-O.O. *IDENTIFY the requirements S / U of EIP-O.O, v27 paragraph 4.8.2 would not allow the crew to fall below ONE below voluntarily by circling: IS NOT

• 3. REVIEW required actions for falling below

• IDENTIFY that the required S / U minimum shift Staffing levels per EIP-O.O AND action is to:

OR TS 5.2.2.c.

IMMEDIATELY INITIATE action to the vacant position within two HOURS.

OR LISTS the TS requirement 5.2.2.(c)

AND/OR the procedural step EIP-O.O paragraph 4.8.2.

FNP ILT-35 ADMIN Al .b SRO Page 4 of 7 EVALUATION CHECKLIST RESULTS:

ELEMENTS: STANDARDS: (CIRCLE)

ANSWER KEY:

1. Does the crew shown in the table satisfy the MINIMUM shift staffing requirements of SOP-O.O and EIP-O.O() NO

2. IF a Reactor Operator experiences chest pains and is required to be transported to the hospital, the SSS-FIRE IS / permitted to escort the Reactor Operator to the hospital while a crew is at minimum shift staffing per EIP-O.O. (SEE paragraph 4.8.2 below; This wouldput staffing Two (2,) less than TABLE 1 requirements)

3. ANYTIME the minimum on-shift staffing requirements are NOT met the actions required are:

IMMEDIATELY INITIATE ACTION TO FILL THE VACANT POSITION(s) within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. it is EQUALLYacceytable simply state: EIP-O.O. v27 para 4.8.2 or TS 5.2.2.c EIP-O.O, v27 paragraph 4.8.2 states.

The shfi crew composition may be one less than the table 1 requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of on-duty shfl crew members [...]provided immediate action is taken to restore the shift crew composition to within the Table 1 requirements TS 5.2.2.c states:

Shift crew composition may be less than the minimum requirement of 10 CFR

.gfor a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order 50.54(m) (2) (i) and 5.2.2.a and 5.2.

2 to accommodate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements.

STOP TIME Terminate when all elements of the task have been completed.

CRITICAL ELEMENTS: Critical Elements are denoted with an asterisk (*) before the element number.

FNP ILT-35 ADMIN A.1 .b SRO Page 5 of 7 GENERAL

REFERENCES:

1. FNP-O-EW-O.O, V 27

2. FNP-O-SOP.-O.O, V 149.1

2. KA: G2.1.5 RO 2.9 SRO 3.9 GENERAL TOOLS AND EOUIPMENT:

Provide/Acquire:

1. FNP-O-EIP-O.O, V 27

2. FNP-O-SOP-O.O,V 149.1 Critical ELEMENT justification:

STEP Evaluation

1. CRITICAL: TASK objective

2. CRITICAL: TASK objective

3. CRITICAL: TASK objective COMMENTS:

FNPILT-35ADMIN A.1.bSRO HANDOUT Page 1 of2 CONDITIONS When I tell you to begin, you are to IDENTIFY THE TECHNICAL SPECIFICATION AND EMERGENCY ORGANIZATION ON-SHIFT MANNING REQUIREMENTS FOR THE CONDITIONS PROVIDED. The conditions under which this task is to be performed are:

a. Both Units are at 100% power.

b. It is Night shift on a holiday, and The Operations Manager has authorized maximizing time off.

c. The table below represents the Operations shift complement that has arrived to receive turnover and their license level/status.

PERSON LICENSE status/gual ACTIVE Adam Dual Unit- SRO SM ACTIVE Bob Dual Unit- SRO Charlie SS Doug ACTIVE Eugene Dual Unit Frank RO INACTIVE Gary Dual Unit- SRO S SS-STA INACTIVE Harry Dual Unit- SRO SSS-Fire Jack Kelly Lisa

. Not licensed Mike SO Nick Oscar Pam Not Licensed Roger Fire Protection Administrator Qualified_Shift_Communicator

d. PROVIDE a written response to the following in accordance with SOP-O.O, General Instruction to Operations Personnel, and EIP-O.O, Emergency Organization:

o IDENTIFY whether or not the crew shown in the table above satisfies the requirements to take the shift without any additional action or personnel, o Consider a minimally staffed crew, and a Reactor Operator experiences chest pains requiring him/her to be transported to the hospital. Determine if the SSS-Fire is permitted to escort the Reactor Operator to the hospital per EIP-0.0, and o Identify the required actions anytime the requirements for minimum on-shift staffing are NOT met.

FNPILT-35ADMN Ai.bSRO HANDOUT Page 2 of 2

1. Does the crew shown in the table satisf the MINIMUM Operations shift staffing requirements of SOP-O.O and EIP-O.O? YES / NO

2. IF a Reactor Operator experiences chest pains and is required to be transported to the hospital, the SSS-FIRE IS / IS NOT permitted to escort the Reactor Operator to the hospital while a crew is at minimum shift staffing per EIP-O.O.

3. ANYTIME the minimum on-shift staffing requirements are NOT met the actions required are:

FNP HLT-35 ADMIN Page 1 of 8 A.2 RO Conduct of Operations ADMIN G2.2.12 Modified CRO-035 TITLE: Perform STP-9.0, RCS Leakage Test EVALUATION LOCATION: SIMULATOR CONTROL ROOM X CLASSROOM PROJECTED TIME: 20 MN SIMULATOR IC NUMBER: N/A ALTERNATE PATH TIME CRITICAL PRA____

JPM DIRECTIONS:

1. Initiation of task may be in group setting, evaluation performed individually upon completion.

2. Requiring the examinee to acquire the required materials may or may not be included as part of the JPM.

TASK STANDARD: Upon successful completion of this JPM, the exarninee will:

• Correctly assess and determine RCS leakrate.

• Correctly assess and determine if STP-9.0 Acceptance Criteria is met.

Examinee:

Overall JPM Performance: Satisfactory Unsatisfactory C Evaluator Comments (attach additional sheets if necessary)

EXAMINER:

Developer Billy Thornton Date: 2R0/2012 NRC Approval SEE NUREG 1021 FORM ES-301-3

FNP HLT-35 ADMIN A.2 RD Page 2 of 8 CONDITIONS When I tell you to begin, you are to PERFORM STP-9.0, RCS LEAKAGE TEST. The conditions under which this task is to be performed are:

a. Unit 1 is stable at 100% power.

b. The RCS leakrate program is unavailable.

c. The plant computer data has been provided on the HANDOUT.

d. Previous RCS leakrate has been 0.00 gpm.

e. You are directed by the Shift Supervisor to

1) Determine RCS leakage per STP-9.0, APPENDIX A

- When APPENDIX A is complete, another operator will perform the remainder of the steps in STP-9.0.

2) Determine whether or not RCS leakage Acceptance Criteria is met.

TNITIATING CUE: IF you have no questions, you may begin.

EVALUATION CHECKLIST RESULTS:

ELEMENTS: STANDARDS: (CIRCLE)

START TIME

1. Appendix A, step 2.1 Read and record initial

- 1) Records initial readings on data S / U readings on data sheet 1. sheet 1.

2. Appendix A, step 2.2 Read and record final

- 2) Records final values on data S / U values on data sheet 1. sheet 1.

CUE IF REQUESTED: Other leakage is 0 gpm.

NOTE: [IF applicant inquires about any other leakage it is 0 gpm. This is information that is obtainable in the plant from turnover, and since there is no other known leakage provided, it may be assumed to be 0 gpm OR it may be requested. Either is acceptablel.

FNP HLT-35 ADMIN A.2 RO Page 3 of 8 EVALUATION CHECKLIST RESULTS:

ELEMENTS: STANDARDS: (CIRCLE)

3. Appendix A, step 2.4 Calculate identified and

- 3) Calculation shows: S / U unidentified leakages using the formulas on STP- Identified RCS leakage 9.0 data sheet 1. 0.05 gpm Unidentified RCS leakage =

Acceptable range 1.16 1.17 gpm

• 4. Compares actual Leak rates with the Acceptance 4) Determines that: S / U Criteria, and determines that the Unidentified Identified RCS leakage =

Leakage does not meet Acceptance Criteria. 0.05 gpm Acceptance Criteria is

<10 gpm and is met.

Unidentified RCS leakage =

Acceptable range 1.16 1.17 gpm Acceptance Criteria is

<1 gpm and is NOT met.

STOP TIME Terminate when all elements of the task have been completed.

CRITICAL ELEMENTS: Critical Elements are denoted with an asterisk (*) before the element number.

FNP HLT-35 ADMIN A.2 RO Page 4 of 8 GENERAL

REFERENCES:

1. FNP-l-STP-9.0, v50.0

2. Plant tank curves 27A, 27B, 27C, 28A, & 28B

3. KA: G2.2. 12 Knowledge of surveillance procedures.

(CFR: 41.10 /45.13)

IMPORTANCE RO 3.7 SRO 4.1 GENERAL TOOLS AND EOUIPMENT:

1. Copy of FNP-1-STP-9.0, v50.0 that is signed off, up to the step required.

2. Plant tank curves 27A, 27B, 27C, 28A, & 28B

3. Calculator

4. Plant Conditions at 10:00 & 12:00 Critical ELEMENT justification:

STEP Evaluation 1-2 Not Critical: thistask will beperformed to document thedata on Data Sheet 1, but is not cr1 ti cal to performing the RCS I eekrate cal cul ati on.

3 Critical: Task completion: required to properly determine Identified and Unidentified RCS leake rate.

4 Critical: Task completion: required to properly determine if Acceptance Criteria of STP-9.0 is met.

COMMENTS:

FNP HLT-35 ADMIN A.2 RO Page 5 of 8 KEY: STP-9.0, DATA SHEET 1, RCS Leakage All tolerances based on differences in rounding. One caic was performed rounding to the least significant digits at each step of the calculation, and one was performed using all digits in the calculator until the end of each step of the calculations to round to the least significant digits.

INSTRUMENT NAME INITIAL FINAL FINAL - INITIAL Computer TIME 1000 1200 A = 120 Minutes (MCB)

NC1 100A No significant change (N-41B,N-42B, PRAVGFLUX 100.0% 100.0%

(<0.1%)

N-43B, N-44B)

TE0453 (T10453)

LIQ PRZR TEMP 650. 8 °F 650. 8 °F No significant change (1 °F)

PC0482, PT0455, PT0456 or PT0457 PRZR PRESS 2239. 4 2239. 4 No significant change (P1 455, P1 456 (Note 1) psig psig (5 psig) orPI457)

TC0484 (preferred),

OR AT= 0 °F TYO412K, OR RCS TAVG TY0422K, OR Maximum change of 0.3°F (Note 1) 571. 9 °F 571. 9 °F TY0432K (Note 7) allowed if TAVG is 545°F or greater, 0.1°F if TAVG is less (Average of TI 412D, than 545°F.

422D & 432D)

RCS Temperature 99. 7 CF (NoteS) N/A B = AT x CF = 0 Gal.

Correction Factor OR NA LC 1600 OR Average of LT0459, PRZR LVL 47.8 % 47. 8 % C = 56.3 x 0 % = 0 Gal.

LT0460 & LT0461 (LI-459, 460, 461)

LTO115 D= 14.18 x ()10.3%=

VCT LVL 51.0 % 40. 7 %

(L1115) ()146.0 to 146.1 Gal.

LI 1003 Waste Pnl or 36. 4 % 38,_i % E = 6.01 to 6.02 Gal.

RCDTLVL BOP LS261 Pos 6 (127.69 *Gal 133.71 *Gal Enter 0 if negative)

LT0470 PRT LVL 697% 69.7°7o F = 0 Gal.

(LI 470) (Note 2) NA *Gal NA *Gal (Enter 0 if negative)

TOTAL FLOW 3489 Gal. 3489 Gal. G = 0 Gal. Dilution and FIS 168 BATCH INTEG NA Gal. NA Gal. Blended Makeup

• From Tank Curve Book

FNP HLT-35 ADMIN A.2 RO Page 6 of 8 KEY (continued): STP-9.0, DATA SHEET 1, RCS Leakage Total Leakage BC-D+G( o)( 0 )( (-)146.Oto(-)146.1)+( o)

= (+1.21)to(+1.22)GPM A

( 120 )

Identified Leakage =

E+F (6.OOto6.03)+( 0 ) +

0

= 0.O5GPM A

( 120 ) Other leakage Other Leakage: Source Rate (GPM) 0 0 Total Other 0.0 gpm Unidentified Leakage 1.21 to 1.22 Total Leakage 0.050 no tolerance Identified Leakage

=1.16 to 1.17 GPM ACCEPTANCE CRITERIA:

• Identified Leakage 10 gprn Unidentified Leakage 1 gpm Identified RCS Leakage is M50 gpm.

Unidentified RCS Leakage is 1.16 to 1.17 gprn.

STP-9.0 Acceptance Criteria IS NOT met.

A.2R0 HANDOUT Pg 1 of2 CONDITIONS When I tell you to begin, you are to PERFORM STP-9.0, RCS LEAKAGE TEST. The conditions under which this task is to be performed are:

a. The unit is in Mode 1 at 100% power.

b. The RCS leakrate program is unavailable.

c. The plant computer data has been provided on the HANDOUT.

d. Previous RCS leakrate has been 0.00 gpm.

e. You are directed by the Shift Supervisor to

1) Determine RCS leakage per STP-9.0, APPENDIX A

- When APPENDIX A is complete, another operator will perform the remainder of the steps in STP-9.0.

2) Determine whether or not RCS leakage Acceptance Criteria is met.

Identified RCS Leakage is gpm.

Unidentified RCS Leakage is gpm.

STP-9.0 Acceptance Criteria IS met / IS NOT met.

A.2 RO HANDOUT Pg 2 of 2 Plant Conditions at 1000:

INSTRUMENT NAME Computer Points N/A TIME 10:00 NC1100A PR AVG FLUX 100.0  %

TE0453 LIQ PRZR TEMP 650.8 °F PC0482 PRZR PRESS 2239.4 psig TC0484 RCS TAVG 571.9 °F LC 1600 PRZR LVL 47.8  %

LTO115 VCT LVL 51.0  %

36.4  %

BOP L5261 Pos 6 RCDT LVL LT0470 PRT LVL 69.7  %

TOTAL FLOW 3489 Gal.

FIS 168 BATCH INTEG Plant Conditions at 1200:

INSTRUMENT NAME Computer Points N/A TIME 12:00 NC1100A PR AVG FLUX 100.0  %

TE0453 LIQ PRZR TEMP 650.8 PC0482 PRZR PRESS 2239.4 Psig TC0484 RCS TAVG 571.9 °F LC 1600 PRZR LVL 47.8  %

LTO115 VCT LVL 40.7  %

RCDT LVL 38.1  %

BOP LS261 Pos 6 LT0470 PRT LVL 69.7  %

TOTAL FLOW FIS 168 3489 Gal.

BATCH_INTEG

FNP HLT-35 ADMIN Page 1 of 9 A.2 SRO Conduct of Operations ADMIN G2.2.12 Modified CRO-035 TITLE: Perform STP-9.O, RCS Leakage Test EVALUATION LOCATION: SIMULATOR CONTROL ROOM X CLASSROOM PROJECTED TIME: 25 MIN SIMULATOR IC NUMBER: N/A ALTERNATE PATH TIME CRITICAL PRA JPM DIRECTIONS:

1. Initiation of task may be in group setting, evaluation performed individually upon completion.

2. Requiring the examinee to acquire the required materials may or may not be included as part of the JPM.

TASK STANDARD: Upon successful completion of this JPM, the examinee will:

• Correctly assess and determine RCS leakrate.

• Correctly assess and determine if STP9.O Acceptance Criteria is met.

Examinee:

Overall JPM Performance: Satisfactory Unsatisfactory 11 Evaluator Comments (attach additional sheets if necessary)

EXAMINER:

FNP HLT-35 ADMIN A.2 SRO Page 2 of 9 CONDITIONS When I tell you to begin, you are to PERFORM STP-9.0, RCS LEAKAGE TEST. The conditions under which this task is to be performed are:

a. Unit 1 is stable at 100% power.

b. The RCS leakrate program is unavailable.

c. The plant computer data has been provided on the HANDOUT.

d. Previous RCS leakrate has been 0.00 gpm.

e. You are directed by the Shift Supervisor to

1) Determine RCS leakage per STP-9.0, APPENDIX A

- When APPENDIX A is complete, another operator will perform the remainder of the steps in STP-9.0.

2) Determine whether or not RCS leakage Acceptance Criteria is met. /

3)EvaluateTech Specs A INITIATING CUE: IF you have no questions, you may begin.

EVALUATION CHECKLIST RESULTS:

ELEMENTS: STANDARDS: (CIRCLE)

START TIME

1. Appendix A, step 2.1 Read and record initial

- 1) Records initial readings on data S / U readings on data sheet 1. sheet 1.

2. Appendix A, step 2.2 Read and record final

- 2) Records final values on data S / U values on data sheet 1. sheet 1.

CUE IF REQUESTED: Other leakage is 0 gpm.

NOTE: [IF applicant inquires about any other leakage it is 0 gpm. This is information that is obtainable in the plant from turnover, and since there is no other known leakage provided, it may be assumed to be 0 gpm OR it may be requested. Either is acceptable].

FNP HLT-35 ADMIN A.2 SRO Page 3 of 9 EVALUATION CHECKLIST RESULTS:

ELEMENTS: STANDARDS: (CIRCLE)

3. Appendix A, step 2.4 Calculate identified and

- 3) Calculation shows: S / U unidentified leakages using the formulas on STP- Identified RCS leakage =

9.0 data sheet 1. 0.05 gpm Unidentified RCS leakage Acceptable range 1.16 1.17 gpm

4. Compares actual Leak rates with the Acceptance 4) Determines that: S / U Criteria, and determines that the Unidentified Identified RCS leakage =

Leakage does not meet Acceptance Criteria. 0.05 gprn Acceptance Criteria is

<10 gpm and is met.

Unidentified RCS leakage =

Acceptable range 1.161.17 gpm Acceptance Criteria is

<1 gprn and is NOT met.

FNP HLT-35 ADMIN A.2 SRO Page 4 of 9 EVALUATION CHECKLIST RESULTS:

ELEMENTS: STANDARDS: (CIRCLE)

5. Perform Tech Spec evaluation. 5) DetenTiines that Tech Spec 3.4.13 RAS is entered for unidentified LEAKAGE> 1 gpm.

CONDITION A is in effect for RCS operational LEAKAGE not within limits.

REOUIRED ACTION:

Reduce LEAKAGE to within limits in 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

If LEAKAGE is not within limits in 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, Then -

Be in MODE 3 in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> AND BE in MODE 5 in 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> is required.

STOP TIME Terminate when all elements of the task have been completed. I CRITICAL ELEMENTS: Critical Elements are denoted with an asterisk (*) before the element number.

FNP HLT-35 ADMIN A.2 SRO Page 5 of 9 GENERAL

REFERENCES:

1. FNP-1-STP-9.0, v50.0

2. Plant tank curves 27A, 27B, 27C, 28A, & 28B

3. Tech Specs and Bases, v186 / v53

4. KA: G2.2. 12 Knowledge of surveillance procedures.

(CFR: 41.10 /45.13)

IMPORTANCE RO 3.7 SRO 4.1 GENERAL TOOLS AND EOUIPMENT:

1. Copy of FNP-1-STP-9.0, v50.0 that is signed off, up to the step required.

2. Plant tank curves 27A, 27B, 27C, 28A, & 28B

3. Tech Specs and Bases

4. Calculator 5, Plant Conditions at 10:00 & 12:00 Critical ELEMENT justification:

STEP Evaluation 1-2 Not Critical: thistask will beperformedtodocumentthedataon Data Sheet 1, but is not critical to performing the RCS I eakrate cal cul ati on.

3 Critical: Task completion: required to properly determine Identified and Unidentified RCS leakage rate.

4 Critical: Task completion: required to properly determine if Acceptance Criteria of STP-9.0 is met.

5 Critical: Task completion: required to properly determineTech Spec requirements COMMENTS:

This Admin task was evaluated for performing notifications per EIP-8.0 for the SROs. The Corporate Duty Manager is required to be notified, but that is the only requirement. After discussion it was determined that there was little discriminatory value in the EIP-8.0 notification requirements. The Corporate DM is required to be notified, but Corporate DM notification is required for off normal occurrence: Step 20.9 Other events which are considered at the time of their occurrence to be of possible concern to upper management including but not limited to (A12008204673) basically any off normal event. In addition, it is a procedural requirement to make Corporate DM notifications, but it is open to interpretation as to what is required. If the Corporate DM is not notified, there is no significant consequence.

FNP HLT-35 ADMIN A.2 SRO Page 6 of 9 KEY: STP-9.0, DATA SHEET 1, RCS Leakage All tolerances based on differences in rounding. One caic was performed rounding to the least significant digits at each step of the calculation, and one was performed using all digits in the calculator until the end of each step of the calculations to round to the least significant digits.

INSTRUMENT NAME INITIAL FINAL FINAL - INITIAL Computer TIME 1000 1200 A = 120 Minutes (MCB)

NC 11 OOA No significant change (N-41B, N-42B, PR AVG FLUX 100. 0% 100. 0%

(<0.1%)

N-43B, N-44B)

TE0453 LIQ PRZR TEMP 650. 8 °F 650. 8 °F No significant change (1 °F)

(T10453)

PC0482, PT0455, PT0456 or PT0457 PRZR PRESS 2239. 4 2239. 4 No significant change (P1 455, P1 456 (Note 1) psig psig (5 psig) orP1457)

TC0484 (preferred),

OR AT= 0 °F TYO4I2K, OR RCS TAVG TY0422K, OR Maximum change of 0.3°F (Note 1) 571.9 °F 571.9 °F TY0432K (Note 7) allowed if TAVG is 545°F or greater, 0.1°F if TAVG is less (Average of TI 412D, than 545°F.

422D & 432D)

RCS Temperature 99. 7 CF (NoteS) N/A B = AT x CF = 0 Gal.

Correction Factor OR NA LC 1600 OR Average of LT0459, PRZRLVL 47.8 % 47.8 % C=56.3 x 0 %= 0 Gal.

LT0460 & LT0461 (LI-459, 460, 461)

LTO 115 D=14.18x()10.3%=

VCTLVL 51.0 % 40.7 %

(LI 115) ()146.0 to 146.1 Gal.

LI 1003 Waste Pnl or 36. 4 % 38. 1 % E = 6.01 to 6.02 Gal.

RCDT LVL BOP LS261 Pos 6 127.69 *Gal 133.71 *Gal (Enter 0 if negative)

LT0470 PRT LVL 69. 7 % 69. 7 % F 0 Gal.

(LI 470) (Note 2) NA *Gal NA *Gal (Enter 0 if negative)

TOTAL FLOW 3489 Gal. 3489 Gal. G = 0 Gal. Dilution and FIS 168 BATCH INTEG NA Gal. NA Gal. Blended Makeup

• From Tank Curve Book

FNP HLT-35 ADMIN A.2 SRO Page 7 of 9 KEY (continued): STP-9.0, DATA SHEET 1, RCS Leakage Total Leakage BC-D+G (o )( 0 )( (-)146.Oto(-)146.1)+( o) = (+1.21)to(+1.22)GPM A

( 120 )

=

E+F (6.OOto6.03)+( 0 ) +

0

= 0.05 GPM

( )

Identified Leakage A 120 Other leakage Other Leakage: Source Rate (GPM) 0 0 Total Other 0.0 gprn Unidentified Leakage =

1.21 to 1.22 Total Leakage Identified 0.050110 tolerance Leakage

=1.16 to 1.17 GPM ACCEPTANCE CRITERIA:

• Identified Leakage 10 gpm Unidentified Leakage 1 gprn Identified RCS Leakage is gprn.

Unidentified RCS Leakage is 1.16 to 1.17 gpm.

STP-9.0 Acceptance Criteria IS NOT met.

Tech Spec Evaluation TS 3.4.13 Cond A.

A.2 SRO HANDOUT Pg 1 of2 CONDITIONS When I tell you to begin, you are to PERFORM STP-9.0, RCS LEAKAGE TEST. The conditions under which this task is to be performed are:

a. Unit 1 is stable at 100% power.

b. The RCS leakrate program is unavailable.

c. The plant computer data has been provided on the HANDOUT.

d. Previous RCS leakrate has been 0.00 gprn.

e. You are directed by the Shift Supervisor to

1) Determine RCS leakage per STP-9.0, APPENDIX A

- When APPENDIX A is complete, another operator will perform the remainder of the steps in STP-9.0.

2) Deten-nine whether or not RCS leakage Acceptance Criteria is met.

3) Evaluate Tech Specs.

Identified RCS Leakage is gpm.

Unidentified RCS Leakage is gpm.

STP-9.0 Acceptance Criteria IS met / IS NOT met.

Tech Spec Evaluation

A.2SRO HANDOUT Pg 2 of 2 Plant Conditions at 1000:

INSTRUMENT NAME Computer Points N/A TIME 10:00 NC1100A PR AVG FLUX 100.0  %

TE0453 LIQ PRZR TEMP 650.8 °F P00482 PRZR PRESS 2239.4 psig TC0484 RCS TAVG 571.9 °F LC 1600 PRZR LVL 47.8  %

LTO115 VCT LVL 51.0  %

BOP L5261 Pos 6 RCDT LVL 36.4  %

LT0470 PRT LVL 69.7  %

TOTAL FLOW 3489 Gal.

FIS 168 BATCH INTEG Plant Conditions at 1200:

INSTRUMENT NAME Computer Points N/A TIME 12:00 NC1100A PR AVG FLUX 100.0  %

TE0453 LIQ PRZR TEMP 650.8 °F P00482 PRZR PRESS 2239.4 Psig TC0484 RCS TAVG 571.9 °F LC 1600 PRZR LVL 47.8  %

LTO115 VCT LVL 40.7  %

BOP L5261 Pos RCDT LVL 38.1  %

6 LT0470 PRT LVL 69.7  %

TOTAL FLOW FIS 168 3489 Gal.

BATCH_INTEG

FNP ILT-35 ADMIN Page 1 of 10 A.3 ADMIN RO Radiation Control TITLE: Determine the Correct RWP, Total Projected Dose And Determine if an Oil Addition and venting can be Performed to the 2A RHR pump without exceeding limits defined.

EVALUATION LOCATION: D SIMULATOR LICONTROL ROOM LiCLASSROOM PROJECTED TIME: 20 M1N SIMULATOR IC NUMBER: N/A LI ALTERNATE PATH LI TIME CRITICAL LI PRA JPM DIRECTIONS:

1. Initiation of task may be in group setting, evaluation performed individually upon completion.

2. Requiring the examinee to acquire the required materials may or may not be included as part of the JPM.

TASK STANDARD: Upon successful completion of this JPM, the examinee will review an RWP, Radiological Survey Map and perform the following for adding oil to the 2A RHR pump and venting the suction:

• Identify the correct RWP.

• Calculate the total projected dose for the job.

• Determine if the task can or cannot be performed without exceeding Administrative Limits or RWP limits on a single entry, and if NOT then state the reason.

Examinee:

Overall JPM Performance: Satisfactory Unsatisfactory D Evaluator Comments (attach additional sheets if necessary)

EXAMINER:

Developer GT Ohmstede Date: 2/9/20 12 NRC Approval SEE NUREG 1021 FORM ES-301-3

FNP ILT-35 ADMIN A.3 RO Page 2 of 10 CONDITIONS When I tell you to begin, you are to Determine the Correct RWP, Total Projected Dose And Determine if an Oil Addition and venting can be Performed to the 2A RHR pump without exceeding limits defined.

The conditions under which this task is to be performed are:

1. You are a trainee on shift and will be accomplishing the following task under instruction.

2. You will be draining and adding oil to the 2A RHR Pump Motor upper and lower reservoirs and venting the suction of the RHR pump near the encapsulation.

3. All needed tools, oil, and equipment have been staged outside the 2A RHR Pump room.

4. All necessary briefings to perform the task have been completed.

5. Your accumulated dose for this year to date is 1260 mRem.

6. Contamination levels: All areas are less than ALPHA 3 levels and < 200 dpm/lOO cm .

2

7. The following tasks are required to be performed:

1. TASK TIME REQUIRED DOSE RATE I Drain and fill the RHR 5 mm 25 mR/hr pump motor (upper reservoir) 2 Drain and fill the RHR 15 mm 60 mR/hr pump motor (lower reservoir) 3 Remove pipe cap, attach 25 mm 120 mR/hr hose to vent valve and open the valve until air free water issues from the vent.

Note: Assume no dose received while traveling between tasks.

8. Using the attached RWPs, you are to DETERMINE and DOCUMENT your conclusions for yourself ONLY on the table below:

a. The correct RWP to use for this task.

b. Total projected dose for this task.

c. Whether you can or cannot perform the task without exceeding Administrative Dose Limits or RWP limits. If the task cannot be performed, then state the reason.

INITIATING CUE: IF you have no questions, you may begin.

FNP ILT-35 ADMIN A.3 RO Page 3 of 10 EVALUATION CHECKLIST RESULTS:

ELEMENTS: STANDARDS: (CIRCLE)

START TIME

1. Determines RWP to use. Reviews the dose rates and S / U identifies that the highest General Area dose rate for the jobs to be performed is 120 mR/hr.

Determines that the task will require a High Radiation Area entry.

References the RWPs and determines that RWP 12-0 101 is a Training RWP, but it cannot be used for a High Radiation Area entry.

Determines that RWP 12-0503 has allowance for OPS Training in High Radiation Areas, and is the correct RWP to use.

• 2. Calculates total projected dose. Calculates dose received while S / U performing the job.

Documents the total of 67 mRem Total dose from task calculation:

Dose-upper oil addition + Dose-lower oil addition + Dose-venting = Total dose for the task

1. 5 minutes

• 25 mRem/ hr

• 1 hr/60 minutes = 2.08 mRem (dose at jobsite) {2 2.1}

2. 15 minutes

• 60 mRem/ hr

• 1 hr/60 minutes = 15 mRem (dose at jobsite) { no range }

3. 25 minutes

• 120 mRem/ hr

• I hr/60 minutes = 50 mRem (dose at jobsite) { no range }

2.08 + 15 + 50 = Total Dose = 67 to 67.1 mRem total

FNP ILT-35 ADMIN A.3 RO Page 4 of 10 EVALUATION CHECKLIST RESULTS:

ELEMENTS: STANDARDS: (CIRCLE)

• 3. Determine if any dose limits will be exceeded by Determines if allowable dose limits S / U performing the task. will be exceed:

Admin dose limit Total dose 1260 + 67.1 =

1327.1 mR 1327.1 mR< Admin dose limit of 2000 mR.

RWP Task dose limit 67.1 mR < RWP 12-0503 Task dose limit of 90 mR RWP Task dose rate limit 120 mR/hr < RWP 12-0503 Task dose rate limit of 140 mR/hr.

Documents that dose limits will not be exceeded.

Total ANNUAL dose:

(1260 accumulated) + 67.1 1327.1 mR {1327 1327.1}

FNP Administrative Annual Dose limit from FNP-0-M-001, Southern Nuclear Company Joseph M. Farley Nuclear Plant Health Physics Manual, is 2000 mR for a Fully Documented Radiation worker.

• 4. States the task is permitted IDENTIFIES that the task actions S / U can be completed as assigned.

STOP TIME Terminate when all elements of the task have been completed.

CRITICAL ELEMENTS: Critical Elements are denoted with an asterisk (*) before the element number.

GENERAL

REFERENCES:

1. FNP-0-M-001, v18.0 2.KA: G2.3.14 RO 3.4 SRO 3.8

FNP LT-35 ADMIN A3 RO Page 5 of 10 GENERAL TOOLS AND EQUIPMENT:

Calculator RWP 12-0503 and 12-0101 (For Training USE ONLY)

Health Physics Manual, FNP-0-M-001, v18.0.

Critical ELEMENT justification:

STEP Evaluation

1. Critical: Task completion: required to determine proper Radiation Work Pennit for the task given.

2. Critical: Task completion: required to determine the total projected dose.

3. Critical: Task completion: required to determine if any dose limits will be exceeded.

4. Critical: Task completion: required to identify that the task can be done within limits permitting task completion.

FNP ILT-35 ADMIN A.3 RO Page 6 of 10 KEY Determination of Task Performance CORRECT RWP to use (CIRCLE the correct RWP) 12-0101

• 67 to 67.1 mRem Projected dose for this task

{range of 67-67.1 mRem}

[RCLE ONE)

Can you complete this task without exceeding limits?

• NO REASON, if applicable: NA

FNP ILT-35 ADMIN A.3 RO HANDOUT Pg 1 of2 CONDITIONS When I tell you to begin, you are to Determine the Correct RWP, Total Projected Dose And Determine if an Oil Addition and venting can be Performed to the 2A RBR pump without exceeding limits defined.

The conditions under which this task is to be performed are:

1. You are a trainee on shift and will be accomplishing the following task under instruction.

2. You will be draining and adding oil to the 2A RHR Pump Motor upper and lower reservoirs and venting the suction of the RHR pump near the encapsulation.

3. All needed tools, oil, and equipment have been staged outside the 2A RHR Pump room.

4. All necessary briefings to perform the task have been completed.

5. Your accumulated dose for this year to date is 1260 mRem.

6. Contamination levels: All areas are less than ALPHA 3 levels and < 200 dpm/l00 cm .

2

7. The following tasks are required to be performed:

1. TASK TIME REQUIRED DOSE RATE 1 Drain and fill the RHR 5 mm 25 mR/hr pump motor (upper reservoir) 2 Drain and fill the RHR 15 mm 60 mR/hr pump motor (lower reservoir) 3 Remove pipe cap, attach 25 mm 120 mR/hr hose to vent valve and open the valve until air free water issues from the vent.

Note: Assume no dose received while traveling between tasks.

8. Using the attached RWPs, you are to DETERMINE and DOCUMENT your conclusions for yourself ONLY on the table below:

d. The correct RWP to use for this task.

e. Total projected dose for this task.

f. Whether you can or cannot perform the task without exceeding Administrative Dose Limits or RWP limits. If the task cannot be performed, then state the reason.

FNPILT-35ADMIN A.3R0 HANDOUT Pg 2 of 2 Determination of Task Performance CORRECT RWP to use (CIRCLE the correct RWP) 120101 124503 Projected dose for this task (CIRCLE ONE)

Can you complete this task without exceeding limits?

YES NO REASON, if applicable:

Plant Farley UNIT Radiation 12-0101 Work Permit FOR TRAINING USE ONLY 99 Administration:This RWP is designated for administrative departments to include Executive & Senior Management. Security.

Job Information Technology, Fleet Oversight, Safety and Health, Training, Performance Improvement, and Work Control that involve Description radiological work categorized as Low Risk AND not specifically addressed by other RWPs. Caution: This RWP cannot be used for entries into Containment, work in High Radiation Areas, Airborne Areas, or posted Alpha Level 2 or Level 3 Contaminated Areas.

Location RADIATION CONTROL AREAS HP Coverage INTERMITTENT Authorization ALL Briefing ALL j Start Date 1/1/2012 12:00AM

[ End Date 12/3 1/20 12 11:59PM

/ 4 Job Supv. G. Ohmstede EXT 4758 Radiological Conditions ft TASKS AIRBORNE LEVELS: < 0.3 DAC PART AND IODINE, <1.0 If .

Description h DAD Alarms DAC NOBLE GAS/TRITIUM Rate(mrfh)

CONTAMINATION: < 200,000 DPMJ100CM2 BETA GAMMA, NRC, INPO, ETC. ACTIVITIES LESS THAN ALPHA LEVEL 1 10 50

RAD LEVELS: LESS < 100 MREM/HR FLEET OVERSIGHT ACTIVITIES 10 50 L Dosimetry TLDandDAD TRAINlNG AND EP ACTIVITIES WORKCONTROL ACTIVITIES 25 25 50 50 Protective Clothing DRESS REQUIRMENTS AS HP DIRECTS quirements r SECURITY ACTIVITIES 10 50

J Respirators Usage is Prohibited INSTRUCTIONS There are certain worker instructions that are applicable to ALL RWPs. These instructions are provided at the Main RCA entrance.

Worker MUST ensure they understand and comply with these instructions at all times while working in RCAs ENTRY iNTO AREAS WITH KNOWN RADIOLOGICAL CONDITIONS GREATER THAN THOSE SPECIFIED ABOVE IS PROHIBITED AND REQUIRES AUTHORIZATION AND BRIEFING ON THE APPROPRIATE RWP.

Contact Health Physics Prior to entering any Radiation Area posted as Neutron Monitoring Required.

Exposure limits for Neutron is as follows: 10 mrem per entry and 50 mrem/hour.

The following special instructions may be deviated from with SNC HP ANSI 3.1 or higher qualified individuals permission.

Dressout requirements for areas >50,000 dpm/I OOcm2 beta/gamma: Double coveralls, or 1 set of Ultra Orex or equivalent, two sets of booties, two sets rubber shoecovers, and two sets gloves.

FOR TRAINING USE ONLY 6/18/2012 12:00:00AM by NRC Prepared NRC EXAM TEAM APPROVED EXAM WRITER

Plant Farley TJNIT Radiation Rev Work Permit -

FOR TRAINING USE ONLY 99 Operations: This RWP is designated for Operations Activities involving work in High Radiation Areas and other work Job classified as Medium Radiological Risk not specifically addressed by other RWPs. CAUTION: This RWP cannot be Description used for entries into Containment, Locked High Radiation Areas, OR work in Alpha Level 3 Areas.

Location jRADIATION CONTROL AREAS HP Coverage INTERMITTENT Authorization INDIVIDUAL Briefing I Stan Date 1/1/20 12 End Date 12/31/2012 INDIVIDUAL 12:00 AM 11:59 PM Job_Supv.__G. Ohmstede EXT 4758 Radiological Conditions I TASKS AIRBORNE LEVELS: LESS THAN 4 DAC HOURS PER Description L DAD Alarms ENTRY [ Dose (nir) II Rate(mr/h)

CONTAMINATION: < 500,000 DPM/IOOCM2 BETA GAMMA, OPS ACTIVITIES (NON HIGH RAD LESS THAN ALPHA LEVEL 3 AREAS) 20 70 RAD LEVELS: LESS < 1000 MREMJHR OPS TRAINING & JPM ACTIVITIES (NON HIGH RAD AREAS) 20 70 Dosimetry OPS ACTIVITIES (HIGH RAD AREAS) 90 140 TLD and DAD OPS TRAINING & JPM ACTIVITIES (HIGH RED AREAS) 90 140 Protective Clothing Requirements I DRESS REQUIRMENTS AS HP DIRECTS

[ Respirators I Usage is Conditional per HP INSTRUCTIONS There are certain worker instructions that are applicable to ALL RWPs. These instructions are provided at the Main RCA entrance.

Worker MUST ensure they understand and comply with these instructions at all times while working in RCAs All workers must receive an Initial RWP Briefing prior to using this RWP for the FIRST time.

Prior to commencing work, individuals will receive a High Rad briefing for every posted High Radiation Area to be entered.

Prior to comnsencing any work in Neutror Radiation Areas, individuals will contact Health Physics to ensure appropriate Neutron monitoring is performed.

Exposure limits for Neutron is as follows: 10 mrem per entry and 50 mrem/hour.

Health Physics Technician must give approval before any tool or piece of equipment is raised such that the item comes out of the water.

Health Physics Technician must give approval before any activated or high dose object is brought near the surface of the water.

When there is extended work evolutions in the SFP Room, the Operations Refueling Supervisor should consider placing the SFP on recirc to the demin.

Notify HP prior to moving any fuel or irradiated components so that HP can ensure the movement will not cause any possible streaming from the light poles in the SFP Transfer canal.

Identified Irradiated FME must have a retrieval plan approved by the HP Supervisor and can not be vacuumed to a filter without approval of HP Radwaste DAD alarm values may be adjusted by a SNC HP ANSI 3.1 or higher qualified individual based on expected conditions but can not exceed the limits listed for this RWP.

The following special instructions maybe deviated from with a SNC HP ANSI 3.1 or higher qualified individuals pemsission.

Dressout requirements for areas >50,000 dpm/lOOcm2 beta/gamma: Double coveralls, or 1 set of Ultra Orex or equivalent, two sets of booties, two sets rubber shoecovers, and two sets gloves.

FOR TRAINING USE ONLY 6/18/2012 12:00:00 AM by NRC Prepared NRC EXAM TEAM APPROVED EXAM WRITER

FNP ILT-35 ADMIN Page 1 of 7 A.3 ADMIN SRO Radiation Control TITLE: Calculate the Maximum Dose an individual will receive to operate local equipment, if the individual will exceed Emergency Dose Limits, and then determine if the individual is required to receive a volunteer brief prior to performing the emergency actions.

EVALUATION LOCATION: El SIMULATOR EICONTROL ROOM CLASSROOM PROJECTED TIME: 20 MIN SIMULATOR IC NUMBER: N/A El ALTERNATE PATH El TIME CRITICAL El PRA JPM DIRECTIONS:

1. Initiation of task may be in group setting, evaluation performed individually upon completion.

TASK STANDARD: Upon successful completion of this JPM, the exarninee will calculate the Maximum dose an individual will receive to operate equipment for the Safety and Health of the public, then deterinine if the EDLs have been exceeded and if a volunteer brief is required.

Examinee:

Overall JPM Performance: Satisfactory Unsatisfactory 11 Evaluator Comments (attach additional sheets if necessary)

EXAMINER:

Developer GT Ohmstede Date: 2/9/20 12 NRC Approval SEE NUREG 1021 FORM ES-301-3

FNP ILT-35 ADMIN A.3 SRO Page 2 of 7 CONDITIONS When I tell you to begin, you are to Calculate the Maximum Dose an individual will receive to operate local equipment, if the individual will exceed Emergency Dose Limits, and then determine if the individual is required to receive a volunteer brief prior to performing the emergency actions.

The conditions under which this task is to be performed are:

1. lB Steam Generator (SG) has a SGTR, 1A and IC SGs have tube leaks and there is fuel failure indicated.

2. 1A, lB and 1C Atmospheric Relief Valves have failed open and are required to be closed to protect the Safety and Health of the Public.

3. Emergency Dose Limits are in effect and there is only one SO available to accomplish the task.

4. SO A has received 1.26 Rem TEDE this year.

5. The following tasks are required to be performed:

1. TASK TIME REQUIRED DOSE RATE 1 Close PCV-3371A 20mm 12.0 R/hr 2 Close PCV-3371B 24 mm 40.0 R/hr 3 Close PCV-3371C 21 mm 12.0 RIhr Note: Assume no dose received while traveling between tasks.

Refer to the above information and answer the questions below:

6. IF SO A completes ALL tasks in the time required:

• What will be the total dose for the actions performed?

• Will SO A exceed the Emergency Dose Limits in effect?

• Is this individual required to receive a volunteer brief?

INITIATING CUE: IF you have no questions, you may begin.

FNP ILT-35 ADMIN A.3 SRO Page 3 of 7 EVALUATION CHECKLIST RESULTS:

ELEMENTS: STANDARDS: (CIRCLE)

START TIME

1. Determine dose received while performing task 1 Determine dose received while S / U performing task 1 12.0 Rfhr X lhr/60 mm X 20 mm = 4.0 R 4.0 Rem

2. Determine dose received while performing task 2 Determine dose received while S / U performing task 2 40.0 RIhr X lhr/60 mm X 24 mill 16.0 R 16.0 Rem

3. Determine dose received while performing task 3 Determine dose received while performing task 3 12 R!hrX lhr/60 mm X 21 mm 4.2 R 4.2 Rem

• 4. Determine TOTAL dose received 24.2 Rem Total dose calculation: Dose-task 1 + Dose- task 2 + Dose- task 3 Total dose 4.0 + 16.0 + 4.2 = Total Dose = 24.2 Rem total

5. Determine if Emergency Dose Limits will be Determines if Emergency Dose S / U exceeded by performing the task per EIP-14.0 Limits will be exceeded.

step 7.12.

Emergency Dose Limits that can be 24.2 Rem projected < 25 Rem for REQUIRED (non volunteer) to be received is Protection of Large Populations up to 25 Rem TEDE for protection of large populations. Answer is NO.

EIP-14.O - Emergency doses received do not have to take into account the annual dose to date.

6. Is this individual required to receive a volunteer Checks volunteer requirements and brief? determines a volunteer brief is NOT required.

STOP TIME Terminate when all elements of the task have been completed.

FNP ILT-35 ADMIN A.3 SRO Page 4 of 7 CRITICAL ELEMENTS: Critical Elements are denoted with an asterisk (*) before the element number.

GENERAL

REFERENCES:

1. FNP-0-EJP-14.0, VER 26.0 2.KA: G2.3.14 RO 3.4 SRO 3.8 GENERAL TOOLS AND EOUIPMENT:

Calculator FNP-0-EIP-14.0, VER 26.0 Comments:

CAUTION EMERGENCY EXPOSURE LIMITS SHALL ONLY BE AUTHORIZED BY THE ED 7.12 Emergency situations may transcend the normal requirement of maintaining personnel exposures below 10CFR2O limits, as noted in step 7.10. Emergency exposures shall be minimized to every degree practicable. FNP personnel who have completed the onsite radiation protection training may be required to receive an exposure up to 25 Rem TEDE for the activity and conditions described below.

For those same personnel to receive in excess of 25 Rem, they must voluntarily agree to receive an emergency dose in excess of 25 Rem, but less than 100 Rem. Emergency doses received do not have to take into account the annual dose to date. Persons volunteering to receive in excess of 25 Rem must be made fully aware of the risks involved.

Emergency exposure limits are as follows:

TEDE Dose Activity Condition 10 Rem Protecting Valuable Property Lower Dose Not Practical 25 Rem Life Saving or Protection Lower Dose Not Practical of Large Populations

>25 Rem Life Saving or Protection Volunteers Only That Are

<100 Rem of Large Populations Fully Aware of The Risks Involved Critical ELEMENT justification: 1-3 are critical since if done incorrectly the answer could be correct for the wrong reason.

STEP Evaluation

1. Critical: calculation is required to calculate if EDLs will be exceeded and then to determine correctly if a volunteer will be required.

2. Critical: calculation is required to calculate if EDLs will be exceeded and then to determine correctly if a volunteer will be required.

3. Critical: calculation is required to calculate if EDLs will be exceeded and then to determine correctly if a volunteer will be required.

4. Critical: calculation is required to calculate if EDLs will be exceeded and then to determine correctly if a volunteer will be required.

5. Critical: EIP-l4.0 EDLs for this task are up to 25 Rem, not including dose received to date. If EDL of 10 Rem for Protecting Valuable Property is used then the person could NOT do the task since 24.2 Rem will be received.

6. Critical: EIP-14,0 requires a volunteer to be used if 25 Rem or greater doses are to be received. If the dose received to date is added in then the person would be required to be a volunteer and receive extra briefings per EJP-14.0.

FNP ILT-35 ADMIN A.3 SRO Page5of7 KEY EDLs What will be the total dose for the actions performed? 24.2 Rem

{No Range}

(CIRCLE ONE)

Will SO A exceed the Emergency Dose Limits in effect?

(CIRCLE Is this individual required to receive a volunteer brief?

YES

FNPILT-35ADMIN \A.3R0 HANDOUT Pglof2 CONDITIONS When I tell you to begin, you are to Calculate the Maximum Dose an individual will receive to operate local equipment, if the individual will exceed Emergency Dose Limits, and then determine if the individual is required to receive a volunteer brief prior to performing the emergency actions.

The conditions under which this task is to be performed are:

1. lB Steam Generator (SG) has a SGTR, 1A and 1C SGs have tube leaks and there is fuel failure indicated.

2. 1A, lB and IC Atmospheric Relief Valves have failed open and are required to be closed to protect the Safety and Health of the Public.

3. Emergency Dose Limits are in effect and there is only one SO available to accomplish the task.

4. 50 A has received 1.26 Rem TEDE this year.

5. The following tasks are required to be performed:

1. TASK TIME REQUIRED DOSE RATE 1 Close PCV.-3371A 20 mm 12.0 R/hr 2 Close PCV-3371B 24 mm 40.0 RIhr 3 ClosePCV-3371C 21mm 12.OR!hr Note: Assume no dose received while traveling between tasks.

Refer to the above information and answer the questions below:

6. IF SO A completes ALL tasks in the time required:

• What will be the total dose for the actions performed?

• Will SO A exceed the Emergency Dose Limits in effect?

• Is this individual required to receive a volunteer brief?

FNP ILT-35 ADMIN A.3 RO HANDOUT Pg2of2 EDLs What will be the total dose for the actions performed?

(CIRCLE ONE)

Will SO A exceed the Emergency Dose Limits in effect?

YES NO (CIRCLE ONE)

Is this individual required to receive a volunteer brief?

YES NO

(LT-35 ADMIN JPM A.4 SRO Page 1 of 7 A.4 Admin SRO only Emergency Plan TITLE: Classify an Emergency Event per NMP-EP- 110, Emergency Classification Determination and Initial Action, and complete Checklist 1, Classification Determination.

EVALUATION LOCATION: D SIMULATOR LICONTROL ROOM CLASSROOM PROJECTED TIME: 15 MIN SIMULATOR IC NUMBER: N/A D ALTERNATE PATH TIME CRITICAL D PRA JPM DIRECTIONS:

1. This task can be conducted individually or in a group setting in which all the necessary references are available.

2. Provide the candidate the HANDOUT page and a copy of Checklist 1, Classification Determination, to allow for familiarization with the task for the event in progress. Since this is a Time Critical task, allow the candidate time to review and understand the task.

3. When the candidate understands his task, provide the candidate a copy of the procedure NMP EP- 110 AND NMP-EP- 11 0-GLOO 1, and allow the candidate to begin. This starts the time critical time.

4. Ensure a clock is in the room in which this task will be conducted.

5. This task is TIME CRITICAL.

CAUTION: A KEY is included and precedes the student handout. CARE must be taken when providing the Student HANDOUT as to not also include the KEY.

TASK STANDARD: Upon successful completion of this JPM, the examinee will:

• Correctly assess the Classification and correctly fill out Checklist 1; which includes line 5; Name, Date and Time. The time is required to be within 15 minutes of the Start Time.

Examinee:

Overall JPM Performance: Satisfactory 1J Unsatisfactory D Evaluator Comments (attach additional sheets if necessary)

EXAMINER:

Developer GT Ohmstede Date: 2/6/20 12 NRC Approval SEE NUREG 1021 FORM ES-301-3

LT-35 ADMIN JPM A.4 SRO Page 2 of 7 CONDITIONS When I tell you to begin, you are to Classify an Emergency Event per NMP-EP-11O, Emergency Classification Determination and Initial Action, and complete Checklist 1, Classification Determination The conditions under which this task is to be performed are:

a. The Site Security Captain reports that there are thre 1 with guns in the Unit 2 Turbine

-Building and there is an on-going exchange of gunfireiith security officers 7

AOP-49 0, Irnmment Security Threat, has been entereN

c. Unit I was tripped from 1 0 deifrbrn the MCB Handswitches.

d. Unit 2 attempted to trip the reactor using the MCB trip switches unsuccessfully.

e. The OATC then successfully opened the CRDM MG set supply breakers and the rods fell into the core.

f Both units are currently in ESP-0 1, Reactor Trip Response

g. Subsequently, the following conditions are reported on Unit 2:

• An RCS leak of 150 gprn has developed.

• R-2 is reading 40 mr/hr and R-7 is reading 100 mr/hr and BOTH radiation monitors are rising.

h. As the extra SRO on shift, you have been assigned the task of classifying the event and completing NMP-EP-1 10, Checklist 1 for the Shift Manager per NMP-EP-1 10 step 6.2.

i. The current MET Tower data is as follows:

o Wind Direction 125 degrees.

o Wind Speed 4.5 mph o Precipitation none.

o Stability Class E

j. This task has TIME CRITICAL elements.

INITIATING CUE: IF you have no questions, you may begin.

Ensure the CANDIDATE understands the task and has no further questions, THEN have the CANDIDATE place the START TIME on the HANDOUT SHEET. Put that same time in the START CRITICAL TIME block below.

EVALUATION CHECKLIST RESULTS:

ELEMENTS: STANDARDS: (CIRCLE)

START CRITICAL TIME (step 1 of NMP-EP-l 10, Checklist 1) S / U

1. Determine the appropriate Initiating Candidate will use Figure 2, HOT Condition Matrix for classification of the event INITIATING CONDITION based on the current operating mode. MATRIX for evaluation.

Li (GO to Step 2)

ILT-35 ADMIN JPM A.4 SRO Page 3 of 7 EVALUATION CHECKLIST RESULTS:

ELEMENTS: STANDARDS: (CIRCLE)

(step 2a) S / U

2. Evaluate the status of the fission product Candidate will evaluate:

barrier using Figure 1 FPB Evaluation. RCS Leak Rate-Non-isolable RCS leak greater thanl20 GPM = potential loss EJ Containment Radiation Monitoring CTMT Rad Monitor RE-2 greater than 100 mRlhr OR CTMT Radiation Monitor RE-7 greater than 200 rnRihr = not a LOSS This meets FA1 criteria for ANY Loss or ANY Potential Loss of EITHER Fuel Clad OR RCS Line 2a should be filled out as below:

LOSS POTENTIAL LOSS INTACT Fuel Cladding Integrity LI LI liii Reactor Coolant System LI lI LI Containment Integrity LI LI El (step 2b) S / U

3. Determine the highest applicable fission El FA1 selected product barrier Initiating Condition (IC):

(step3) S / U

4. Evaluate and determine the highest Using the TOP down approach, the applicable IC/EAL using the Matrix security event will be evaluated as Evaluation Chart identified in step I THEN a Site Area emergency HS4 GO to step 4 The Rx trip issue should be evaluated and determined to be an ALERT classification- SA2 El Places HS4 in block 3 (step4) S / U

5. Check the highest emergency classification El Site-Area block checked level identified above: El HS4 placed in blank provided next to Site-Area

ILT-35ADMINJPM A.4SRO Page4of7 EVALUATION CHECKLIST RESULTS:

ELEMENTS: STANDARDS: (CIRCLE)

(step 5) S I U

6. Declare the event by approving the Name placed in blank Emergency declaration, provided for Emergency Director Date placed in blank provided Time placed in blank provided (step6) S / U

7. Obtain Meteorological Data (not required Wind Direction (from) 125° prior to event declaration): Wind Speed 4.5 Stability Class E LI Precipitation none STOP CRITICAL TIME (Stop Critical Time is the time from Block 5)

Terminate when all elements of the task have been completed.

CRITICAL ELEMENTS: Critical Elements are denoted with an asterisk (*) before the element number.

GENERAL

REFERENCES:

1. NMP-EP-1 10 Version 3.0

2. NMP-EP-1 lO-GLO1, Version 2.0

3. KA: G2.4.41 SRO (4.6)

GENERAL TOOLS AND EQUIPMENT:

NMP-EP-1 10 NMP-EP-1 lO-GLO1

ILT-35ADMINJPM A.4SRO Page5of7 Critical ELEMENT justification:

STEP Evaluation 1 Not critical: using the correct matrix is vital to get the correct answer but if the task was completed with the wrong matrix, the classification would still be correct.

2 Not critical: evaluating the FPB correctly is important but the correct classification is a SITE AREA so this being classified as an ALERT is not critical. The Critical Task will show up in block 5.

3 Not critical: filling out this block is important but the Critical Task will show up in block 5.

4 Not critical: filling out this block is important but the Critical Task will show up in block 5.

5 Critical: Task completion; information provided is essential for correct classification and Emergency Notification form being correctly filled out and transmitted.

6 Critical: The time and approval name is required to correctly fill out the Emergency Notification form and provide approval to allow transmitting the form.

COMMENTS:

NO I A N SW E R K EY Pagel2of23 Checklist I Classification Determination (page 1 of 1)

NOTE Key Parameters should be allowed to stabilize to accurately represent plant conditions prior to classifying an event.

Initial Actions Completed by

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

D HOT lC/EAL Matrix Evaluation Chart (GO to Step 2) to evaluate the Barriers)

D COLD IC/EAL Matrix Evaluation Chart (GO to Step 3)

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:

LOSS POTENTIAL LOSS INTACT Fuel Cladding Integrity D 0 x FA1 -ALERT Reactor Coolant System x classification for Containment Integrity D 0 x 150 gpm leak.

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

(select one) 0 FG1 0 FS1 X FA1 0 FU1 0 None SA2 - ALERT classification Evaluate and determine the highest applicable IC/EAL using the Matrix Evaluation on Unit 2 for Chart identified in step 1 THEN GO to step 4.

IHS4 Site Area emergency for BOTH Rx Trip issue lC#________ HS4 0 None lunits due to the security event.

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

Classification Based on lC# Classification Based on IC#

0 General 0 Alert X Site-Area HS4 0 NOUE 0 None N/A Remarks (Identify the specific EAL, as needed):_____________________

5. Dlrc th cvnt hv rnnrnving the Emergency Classification.

Name of candidate 6/19/2012 current time Time:

Emergency Director

6. Obtain Meteorological Data (not required prior to event declaration):

Wind Direction (from) 125 Wind Speed Stability ClassE Precipitation__none

7. Initiate Checklist 2, Emergency Plan Initiation.

ILT-35 ADMIN JPM A.4 SRO HANDOUT Page 1 of 1 CONDITIONS When I tell you to begin, you are to Classify an Emergency Event per NMP-EP-11O, Emergency Classification Determination and Initial Action, and complete Checklist 1, Classification Determination.

The conditions under which this task is to be performed are:

a. The Site Security Captain reports that there are three people with guns in the Unit 2 Turbine Building and there is an on-going exchange of gunfire with security officers.

b. AOP-49.0, Imminent Security Threat, has been entered.

c. Unit 1 was tripped from 100% power from the MCB Handswitches.

d. Unit 2 attempted to trip the reactor using the MCB trip switches unsuccessfully.

e. The OATC then successfully opened the CRDM MG set supply breakers and the rods fell into the core.

f. Both units are currently in ESP-0. 1, Reactor Trip Response.

g. Subsequently, the following conditions are reported on Unit 2:

• An RCS leak of 150 gpm has developed.

• R-2 is reading 40 mr/hr and R-7 is reading 100 mr/hr and BOTH radiation monitors are rising.

h. As the extra SRO on shift, you have been assigned the task of classifying the event and completing NMP-P-ii0, Checklist 1 for the Shift Manager per NMP-EP-1l0 step 6.2.

[i. The current MET Tower data is as follows o Wind Direction from 125 degrees.

o Wind Speed 4.5 mph.

o Precipitation none.

Stability Class E

j. ThisiskhaTIME CRITICAL elements.

START TIME