Text

2014-04 Final Operating Test
	ML14140A153
Person / Time
Site:	Waterford
Issue date:	04/07/2014
From:	Chris Steely; Operations Branch IV
To:	; Entergy Operations
	laura hurley
References
	50-382/14-004
	Download: ML14140A153 (247)
	v • d • e

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Waterford 3 Date of Examination: 4/07/2014 Examination Level: RO SRO Operating Test Number: 1 Administrative Topic Type Describe activity to be performed (see Note) Code*

A1 2.1.25, Ability to interpret reference materials, such as graphs, curves, tables, etc.

Conduct of Operations Calculate required and available Feedwater to place the M,R plant on Shutdown Cooling and determine the time K/A Importance: requirement to be on Shutdown Cooling.

3.9 A2 2.1.23, Ability to perform specific system and integrated plant procedures during all modes of plant operation.

Conduct of Operations Complete a calculation for determining the amount of pure water that may be added to the Refuel Cavity without D,P,R K/A Importance: dilution to below shutdown margin requirements in accordance with OP-010-006, Outage Operations, section 4.3 9.24, Refueling Cavity Boron Concentration.

(Used on 2012 NRC Exam)

A3 2.2.12, Knowledge of surveillance procedures Equipment Control Complete surveillance OP-903-008, Reactor Coolant N,R System Isolation Leakage Test, Attachment 10.9 RC Loop 2 Hot Leg Injection Inside Containment Check SI-510B Leak K/A Importance:

Rate Data.

3.7 A4 2.3.11, Ability to control radiation releases.

Radiation Control Evaluate Meteorological conditions for gaseous release M,R from the Gaseous Waste Management System in accordance with OP-007-003, Gaseous Waste K/A Importance:

Management.

3.8 Emergency Plan Not Selected NOTE: All items (5 total are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.

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

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

(P)revious 2 exams ( 1; randomly selected) 2014 NRC Revision 1

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Waterford 3 Date of Examination: 4/07/2014 Examination Level: RO SRO Operating Test Number: 1 Administrative Topic Type Describe activity to be performed (see Note) Code*

A5 2.1.25, Ability to interpret reference materials, such as Conduct of Operations graphs, curves, tables, etc.

N,R Review and approve a completed calculation for required and available Feedwater to place the plant on Shutdown K/A Importance: Cooling and review recommendation for the maximum time 4.2 requirement to be on Shutdown Cooling.

A6 2.1.23, Ability to perform specific system and integrated plant procedures during all modes of plant operation.

Conduct of Operations Review and approve a completed calculation for determining the amount of pure water that may be added to K/A Importance: D,P,R the Refuel Cavity without dilution to below shutdown margin 4.4 requirements in accordance with OP-010-006, Outage Operations, section 9.24, Refueling Cavity Boron Concentration.

(Used on 2012 NRC Exam)

A7 2.2.40, Ability to apply Technical Specifications for a Equipment Control system.

N,R Review and approve surveillance OP-903-008, Reactor K/A Importance: Coolant System Isolation Leakage Test, Attachment 10.9 4.7 RC Loop 2 Hot Leg Injection Inside Containment Check SI-510B Leak Rate Data.

A8 2.3.4, Knowledge of radiation exposure limits under normal Radiation Control or emergency conditions.

Calculate dose and assign non-licensed operators to vent D,R Safety Injection piping in Safeguards Room A. Given dose K/A Importance: rate with and without shielding installed, time to install 3.7 shielding, and job completion time using 1 operator or using 2 operators, determine proper job assignment.

A9 2.4.41, Knowledge of the emergency action level thresholds Emergency Plan and classifications.

M,R Determine appropriate Emergency Plan EAL.

K/A Importance:

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

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

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

(P)revious 2 exams ( 1; randomly selected) 2014 NRC Revision 0

Waterford 3 2014 NRC Exam JOB PERFORMANCE MEASURE A1 Determine Time to Shutdown Cooling Applicant:

Examiner:

JOB PERFORMANCE MEASURE DATA PAGE Task: Determine time to place plant on Shutdown cooling Task Standard: Applicant calculates time to place plant on Shutdown Cooling in accordance with key.

References:

OP-902-009, Standard Appendices, Rev 309, Appendix 2 OP-902-006, Loss of Main Feedwater Recovery, Rev 15 Alternate Path: No Time Critical: No Validation Time: 9 mins.

2.1.25 Ability to interpret reference K/A materials, such as graphs, curves, tables, Importance Rating 3.9 etc.

Level RO/SRO Applicant:

Time Start: Time Finish:

Performance Time: minutes Critical Time: N/A minutes Performance Rating: SAT UNSAT Comments:

Examiner: Date:

Signature Revision 0 Page 2 of 6 2014 NRC Exam

EXAMINER COPY ONLY Tools/Equipment/Procedures Needed:

Standard Appendices, Rev 309, Appendix 2-G through 2-J (Handout 1)

Straight Edge or Ruler Calculator

==

Description:==

The applicant will be required to perform a calculation and use graphs to determine available Feedwater for cooldown to Shutdown Cooling (SDC) conditions, required Feedwater for cooldown to SDC conditions, and the time required to place SDC in service in accordance with OP-902-009, Standard Appendices, Appendix 2.

The Applicant should determine the time to place SDC in service at no later than 14.75 to 15.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months .

READ TO APPLICANT DIRECTION TO APPLICANT:

Each administrative JPM has a cue sheet with the instructions for that JPM. Each administrative JPM stands alone, and conditions from 1 JPM do not carry over to any other JPM. If you have any questions, raise your hand and I will come to your desk.

Provide all answers on the sheets provided.

(Read the Initial Condition and Cues from the Applicant Cue sheet, and then give the cue sheet and student handout to the applicant.)

Revision 0 Page 3 of 6 2014 NRC Exam

TASK ELEMENT 1 STANDARD Directions for calculating available feed water, apply to Graphs 2-G thru 2 -J :

Calculated 212,000 gal DWST Volume = 5,000 gal/% x _ _ _ _ _ % - 58,000 gal. = _ _ _ _ _ gal.

Comment: Critical EXAMINER NOTE: Applicant should use 54% from initial conditions SAT / UNSAT TASK ELEMENT 2 STANDARD CSP Volume = 2,106 gal/% x _ _ _ _ _ % - 53,000 gal. = _ _ _ _ _ _ gal. Calculated 85,996 gal Comment: Critical EXAMINER NOTE: Applicant should use 66% from initial conditions SAT / UNSAT TASK ELEMENT 3 STANDARD Total Feedwater = DWST Volume + CSP Volume = _ _ _ _ _ _ _ _ gal. Calculated 297,996 gal Comment: Critical SAT / UNSAT TASK ELEMENT 4 STANDARD Determined 36,500 gal -

Determine required Feedwater from Attachment 2-G 37,500 gal Comment: Critical SAT / UNSAT EXAMINER NOTE: Refer to A1 key. Acceptable range based on graph interpolation Revision 0 Page 4 of 6 2014 NRC Exam

TASK ELEMENT 5 STANDARD Total Feedwater - Feedwater Required from Att. 2 -G = Available Feed water Calculated 260,496 gal -

Total _ _ _ _ _ _ _ _ - Required _ _ _ _ _ _ _ _ = Available _ _ _ _ _ _ _ 261,496 gal for Available.

Comment: Critical EXAMINER NOTE: Refer to A1 key. Acceptable range of answer depends on acceptable range of Required Feedwater from Task Element SAT / UNSAT 4.

TASK ELEMENT 6 STANDARD Calculate the maximum time remaining to place Shutdown Cooling in Determined 14.75 - 15.5 service. hours Comment: Critical EXAMINER NOTE: Applicant should use Figure 2-I, 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months curve. Refer to A1 key. Acceptable range of answer depends on acceptable range of SAT / UNSAT Available Feedwater from Task Element 5 based on graph interpolation END OF TASK Revision 0 Page 5 of 6 2014 NRC Exam

APPLICANT CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

Plant tripped 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ago due to a loss of Main Feedwater Plant Conditions as follows:

o RCS THOT = 550 F o DWST level = 54%

o CSP level = 66%

o 2 RCPs have been stopped OP-902-006, Loss of Main Feedwater has been completed up to the step to commence a plant cooldown.

INITIATING CUES:

The CRS directs you to calculate the maximum time remaining to place Shutdown Cooling in service at 350 F based upon Condensate inventory in accordance with OP-902-009, Appendix 2. Complete all work on attachment provided and write your answer on this sheet.

Maximum time remaining to place SDC in service ____________

Revision 0 Page 6 of 6 2014 NRC Exam

Waterford 3 2014 NRC Exam JOB PERFORMANCE MEASURE A2 Calculation for Determining the Amount of Pure Water That May Be Added to the Refuel Cavity Applicant:

Examiner:

JOB PERFORMANCE MEASURE DATA PAGE Task: Calculation for determining the amount of pure water that may be added to the Refuel Cavity Task Standard: Applicant calculates the amount of pure water that can be added to the refueling cavity in accordance with OP-010-006, Outage operations. The results must conform to the answer key.

References:

OP-010-006, Outage Operations Rev 322 TS 3.9.1 COLR Alternate Path: No Time Critical: No Validation Time: 11 mins.

2.1.23 Ability to perform specific system and K/A integrated plant procedures during all Importance Rating 4.3 modes of plant operation.

Level RO/SRO Applicant:

Time Start: Time Finish:

Performance Time: minutes Critical Time: N/A minutes Performance Rating: SAT UNSAT Comments:

Examiner: Date:

Signature Revision 2 Page 2 of 6 2014 NRC Exam

EXAMINER COPY ONLY Tools/Equipment/Procedures Needed:

OP-010-006, Outage Operations (Handout 1)

Calculator

==

Description:==

The applicant will be required to calculate the amount of pure water that can be added to the refueling cavity in accordance with OP-010-006, Outage Operations. To perform this calculation the applicant will need to determine what the Refueling Minimum Boron concentration is from Tech Specs. The results will indicate that 1413 gallons of CMU may be added to the refuel cavity.

READ TO APPLICANT DIRECTION TO APPLICANT:

Each administrative JPM has a cue sheet with the instructions for that JPM. Each administrative JPM stands alone, and conditions from 1 JPM do not carry over to any other JPM. If you have any questions, raise your hand and I will come to your desk.

Provide all answers on the sheets provided.

(Read the Initial Condition and Cues from the Applicant Cue Sheet, and then give the cue sheet to the applicant.)

Revision 2 Page 3 of 6 2014 NRC Exam

TASK ELEMENT 1 STANDARD Note:

(1) This attachment provides guidance for calculating the amount of pure water that may be added to the Refuel Cavity without dilution to below shutdown margin requirements. This is typically used while Radiation Protection is using CMU to wash down the Refuel Cavity walls to mitigate airborne radioactivity while performing Note reviewed.

Refuel Cavity drain down.

(2) This calculation is only valid for water additions while the Refuel Cavity Water Level is > 20 MSL.

(3) This calculation includes a 50% margin.

SAT / UNSAT 9.24.1 Record the following:

TASK ELEMENT 2 STANDARD Final Refuel Cavity Water Level (Lf): 22 ft Comment:

Refer to A2 Key.

SAT / UNSAT TASK ELEMENT 3 STANDARD Initial Refuel Cavity Boron Concentration (Ci) 2090 ppm Comment:

Refer to A2 Key.

SAT / UNSAT TASK ELEMENT 4 STANDARD Refueling Minimum Boron Concentration (Cf) 2050 ppm Comment: Critical Refer to A2 Key.

SAT / UNSAT The applicant will determine that 2050 ppm is the most restrictive requirement per TS 3.9.1.

Revision 2 Page 4 of 6 2014 NRC Exam

TASK ELEMENT 5 STANDARD 9.24.2 Calculate the amount of pure water that may be added to the Refuel Cavity (Vw) using the following formula:

Vw = (6954 gal/ft x Lf - 79,161 gal) x (1- Cf/Ci) 1402 to 1476 gallons Vw = [( 6954x___ ft) - 79,161]x [1-(___ppm/___ppm)]

Vw=____gallons Comment: Critical EXAMINER NOTE: (Cf/Ci) 2050ppm/2090ppm = .98086124 SAT / UNSAT Rounding up to .981 would yield Vw = 1402.7 gal. Rounding down to .98 would yield Vw = 1476.5 gal.

73,827 x .01913876 = 1413 gallons TASK ELEMENT 6 STANDARD 9.24.3 Select the lower of Vw calculated in Step 9.24.2 or 1500 gallons: 1402 to 1476 gallons Comment: Critical Refer to A2 Key.

SAT / UNSAT END OF TASK Revision 2 Page 5 of 6 2014 NRC Exam

APPLICANT CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

Waterford 3 is in a refueling outage.

Reactor engineering has determined that a boron concentration of 1985 ppm is required to maintain the refuel cavity at a Keff of < .95.

Refueling Cavity Water Level is 24 ft. and will be drained to 22 ft.

Refueling Cavity boron concentration is 2090 ppm.

INITIATING CUES:

RP has requested that the refuel cavity walls be washed down with CMU as level in the refueling cavity is lowered to 22 ft.

The CRS directs you to determine refueling minimum boron concentration per Technical Specifications and perform OP-010-006, Attachment 9.24 Refueling Cavity Boron concentration, through step 9.24.3.

Revision 2 Page 6 of 6 2014 NRC Exam

Waterford 3 2014 NRC Exam JOB PERFORMANCE MEASURE A3 Calculate Leak Rate for SI-510B Applicant:

Examiner:

JOB PERFORMANCE MEASURE DATA PAGE Task: Calculation for determining the leak rate of RC Loop 2 Hot Leg Injection Inside Containment Check SI-510B Task Standard: Applicant calculates the corrected leak rate of SI-510B and determines leakage is not acceptable in accordance with OP-903-008, Reactor Coolant System Isolation Leakage Test.

References:

OP-903-008, Reactor Coolant System Isolation Leakage Test Rev 13 Alternate Path: No Time Critical: No Validation Time: 17 mins.

2.2.12 Knowledge of Surveillance K/A Importance Rating 3.7 Procedures.

Level RO/SRO Applicant:

Time Start: Time Finish:

Performance Time: minutes Critical Time: N/A minutes Performance Rating: SAT UNSAT Comments:

Examiner: Date:

Signature Revision 1 Page 2 of 6 2014 NRC Exam

EXAMINER COPY ONLY Tools/Equipment/Procedures Needed:

OP-903-008, Reactor Coolant System Isolation Leakage Test (Handout 1)

Calculator with capability to raise to the 1/2 power (yx)

==

Description:==

The applicant will be required to calculate the leak rate based on data provided on Attachment 10.9. The Applicant will first calculate gross leak rate, the extrapolation ratio coefficient, and the corrected leak rate for valve SI-510B. The leakage will exceed acceptance criteria of 1 GPM and will be 1.18 GPM.

READ TO APPLICANT DIRECTION TO APPLICANT:

Each administrative JPM has a cue sheet with the instructions for that JPM. Each administrative JPM stands alone, and conditions from 1 JPM do not carry over to any other JPM. If you have any questions, raise your hand and I will come to your desk.

Provide all answers on the sheets provided.

(Read the Initial Condition and Cues from the Applicant Cue Sheet, and then give the cue sheet to the applicant.)

Revision 1 Page 3 of 6 2014 NRC Exam

TASK ELEMENT 1 STANDARD 7.9.5.16 / 7.9.6.13 Corrected Leak Rate Calculation for SI-510B:

GROSS LEAK RATE (RG):

RG = 2.64E-4 X VC / TE .95 to .951 GPM RG = 2.64E-4 X _________ ml / _________ min RG = _________ GPM Comment: Critical EXAMINER NOTE: RG = 2.64E-4 X 7200 ml / 2 min SAT / UNSAT Rounding down [(2.64E-4 X 7200) / 2] to 1.9/2 would yield RG = .95 GPM.

Rounding up [(2.64E-4 X 7200) / 2] to 1.901/2 would yield RG = .9505 (Then rounded up to .951) GPM.

Refer to A3 Key TASK ELEMENT 2 STANDARD EXTRAPOLATION RATIO COEFFICIENT (CE): (N/A if RG = 0) 0.5 CE = [2235 PSIG / P2]

0.5 CE = [2235 PSIG / _________ PSIG] 1.24 to 1.242 0.5 CE = [ _________ ]

CE = _________

Comment: Critical 0.5 EXAMINER NOTE: CE = [2235 PSIG / _________ PSIG]

0.5 SAT / UNSAT Rounding down (2235/1450) to 1.54 would yield CE = (1.54) = 1.2409 (Then rounded down to 1.24). Rounding up (2235/1450) to 1.5414 would 0.5 yield CE = (1.5414) = 1.2415 (Then rounded up to 1.242) GPM.

Refer to A3 Key TASK ELEMENT 3 STANDARD CORRECTED LEAK RATE (RC):

RC = RG X CE RC = _________ GPM X _________ 1.17 to 1.2 GPM RC = _________ GPM Comment: Critical EXAMINER NOTE: RC = _________ GPM X _________

Rounding down including min ranges of previous task elements (1.24 X SAT / UNSAT

.95) would yield RC = 1.178 GPM (Then stopped at 2 decimal places =

1.17 GPM). Rounding up including max ranges of previous task elements (1.242 X .951) would yield RC = 1.181 GPM (Then rounded up = 1.2 GPM)

Refer to A3 Key Revision 1 Page 4 of 6 2014 NRC Exam

TASK ELEMENT 4 STANDARD Note: Refer to attachment 10.16, Acceptance Criteria and Test Referred to Attachment Acceptance, for acceptance criteria. 10.16 Comment:

Refer to A3 Key.

SAT / UNSAT TASK ELEMENT 5 STANDARD 10.16.1 SI-4052A(B) leakage limit is less than or equal to 0.375 gpm. Determined step is N/A Comment:

SAT / UNSAT TASK ELEMENT 6 STANDARD 10.16.2 For all check valves tested, test is acceptable if leakage is less Determined leakage is not than or equal to 1 GPM. acceptable Comment: Critical EXAMINER NOTE: This may be satisfied by either annotating on 0.12, Attachment 10.9, Attachment 10.16, or on Cue sheet. SAT / UNSAT END OF TASK Revision 1 Page 5 of 6 2014 NRC Exam

APPLICANT CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

OP-903-008, Reactor Coolant Leakage System Isolation Test is in progress.

RC Loop 2 Hot Leg Injection inside Containment Check SI-510B Leak rate using HPSI Train A is in progress Data has been collected for valve SI-510B (RC LOOP 2 HOT LEG INJECTION INSIDE CONTAINMENT) and recorded on Attachment 10.9 Step 7.9.5.16 has been reached for calculating corrected leak rate on Attachment 10.9 INITIATING CUES:

The CRS directs you to resume with step 7.9.5.16 of OP-903-008 to Calculate Corrected Leak Rate for RC Loop 2 Hot Leg Injection Inside Containment Check, SI-510B, on Attachment 10.9, record test results for SI-510B, and evaluate against acceptance criteria on Attachment 10.12, Results Summary Table.

Revision 1 Page 6 of 6 2014 NRC Exam

Waterford 3 2014 NRC Exam JOB PERFORMANCE MEASURE A4 Gaseous Release Evaluation Applicant:

Examiner:

JOB PERFORMANCE MEASURE DATA PAGE Task: Meteorological conditions are evaluated for gaseous release from the GWM System.

Task Standard: Applicant concluded that a release is not permitted. The conclusion included the correct evaluation of wind speed, wind direction, and stability class.

References:

OP-007-003, Gaseous Waste Management, Rev 304 Alternate Path: No Time Critical: No Validation Time: 7 mins.

K/A 2.3.11, Ability to control radiation releases Importance Rating 3.8 Level RO/SRO Applicant:

Time Start: Time Finish:

Performance Time: minutes Critical Time: N/A minutes Performance Rating: SAT UNSAT Comments:

Examiner: Date:

Signature Revision 0 Page 2 of 5 2014 NRC Exam

EXAMINER COPY ONLY Tools/Equipment/Procedures Needed:

Attachment 11.5 of OP-007-003, Gaseous Waste Management (Handout 1)

MET data (Handout 2)

==

Description:==

The setting will be in the classroom for this JPM. The applicant will be provided information from the PMC for the applicable meteorological conditions. The data will be used to evaluate the flow chart in OP-007-003, Attachment 11.5.

READ TO APPLICANT DIRECTION TO APPLICANT:

Each administrative JPM has a cue sheet with the instructions for that JPM. Each administrative JPM stands alone, and conditions from 1 JPM do not carry over to any other JPM. If you have any questions, raise your hand and I will come to your desk.

Provide all answers on the sheets provided.

(Read the Initial Condition and Cues from the Applicant Cue Sheet, and then give the cue sheet to the applicant.)

Revision 0 Page 3 of 5 2014 NRC Exam

TASK ELEMENT 1 STANDARD Concluded wind speed is 2.68 (primary met tower)or Evaluate 10 meter (33 foot) wind speed.

2.75 (backup met tower) m/s.

Comment: Critical EXAMINER NOTE: Note 2 on attachment 11.5 directs the use of 33 foot parameters. Note 1 on attachment 11.5 directs all parameters to be SAT / UNSAT obtained from 15 minute average values.

EXAMINER NOTE: The 199 foot reading (3.62 m/s) will conclude that there are no restrictions on the release without using the rest of the flowchart TASK ELEMENT 2 STANDARD Concluded wind direction is 331.1(or 330.7 from the B/U Evaluate 10 meter (33 foot) wind direction. met tower) deg and continued right through the flow chart.

Comment: Critical EXAMINER NOTE: The 199 foot reading (314.5 deg) will also continue right through the flow chart. The procedure directs using the 33 foot SAT / UNSAT parameters.

TASK ELEMENT 3 STANDARD Concluded T is .77 °C or 0.76 °C, stability class F, Evaluate Pasquill Stability Class.

and that the release is not permitted.

Comment: Critical EXAMINER NOTE: Note 3 on attachment 11.5 directs the T/50m to be obtained from the primary or backup tower 199-33 Delta T reading. SAT / UNSAT EXAMINER NOTE: Use of instantaneous values (.72,.73 T/50m) would result in a Stability class E END OF TASK Revision 0 Page 4 of 5 2014 NRC Exam

APPLICANT CUE SHEET (TO BE RETURNED TO EXAMINER TO UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

The plant is in Mode 1 Chemistry has requested a release of all 3 Gas Decay Tanks for planned maintenance Environmental conditions are as displayed on the METDATA handout INITIATING CUES:

The CRS directs you to complete an evaluation of meteorological conditions for the release in accordance with OP-007-003, Gaseous Waste Management Document all information used and conclusions on OP-007-003, Attachment 11.5.

Revision 0 Page 5 of 5 2014 NRC Exam

Waterford 3 2014 NRC Exam JOB PERFORMANCE MEASURE A5 Verify Time to Shutdown Cooling Applicant:

Examiner:

JOB PERFORMANCE MEASURE DATA PAGE Task: Verify time to place plant on Shutdown cooling Task Standard: Applicant identifies error in Condensate Storage Pool (CSP) volume calculation and then recalculates CSP volume, recalculates the Total Feedwater. Identifies error in Required Feedwater and determines the Required Feedwater and recalculates the Available Feedwater. Applicant recalculates time to place plant on Shutdown Cooling at 14.75 to 15.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months .

References:

OP-902-009, Standard Appendices, Rev 309, Appendix 2 OP-902-006, Loss of Main Feedwater Recovery, Rev 15 Alternate Path: No Time Critical: No Validation Time: 16 mins.

2.1.25 Ability to interpret reference K/A materials, such as graphs, curves, tables, Importance Rating 3.9 etc.

Level SRO Applicant:

Time Start: Time Finish:

Performance Time: minutes Critical Time: N/A minutes Performance Rating: SAT UNSAT Comments:

Examiner: Date:

Signature Revision 1 Page 2 of 7 2014 NRC Exam

Revision 1 Page 3 of 7 2014 NRC Exam EXAMINER COPY ONLY Tools/Equipment/Procedures Needed:

Standard Appendices, Rev 309, Appendix 2-G through 2-J (Handout 1)

Straight Edge or Ruler Calculator

==

Description:==

The applicant will be required to verify a calculation and use graphs to determine available Feedwater for cooldown to Shutdown Cooling (SDC) conditions, required Feedwater for cooldown to SDC conditions, and the time required to place SDC in service in accordance with OP-902-009, Standard Appendices, Appendix 2. The Applicant should identify an error in determining Condensate Storage Pool volume and Required Feedwater. There is an additional error in that the RO used the wrong curve to identify that 29 hours3.356481e-4 days 0.00806 hours 4.794974e-5 weeks 1.10345e-5 months is the maximum time allowed to get on SDC. The SRO must use the correct curves to determine the time to place SDC in service at no later than 14.75 to 15.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months .

READ TO APPLICANT DIRECTION TO APPLICANT:

Each administrative JPM has a cue sheet with the instructions for that JPM. Each administrative JPM stands alone, and conditions from 1 JPM do not carry over to any other JPM. If you have any questions, raise your hand and I will come to your desk.

Provide all answers on the sheets provided.

(Read the Initial Condition and Cues from the Applicant Cue sheet, and then give the cue sheet and student handout to the applicant.)

Revision 1 Page 4 of 7 2014 NRC Exam

TASK ELEMENT 1 STANDARD Directions for calculating available feed water, apply to Graphs 2-G thru 2 -J :

Verified 212,000 gal DWST Volume = 5,000 gal/% x _ _ _ _ _ % - 58,000 gal. = _ _ _ _ _ gal.

Comment: Critical EXAMINER NOTE: Only Critical if the applicant changes the answer from the correct value which is given to an incorrect value and this value SAT / UNSAT changes the Final time to place SDC in service outside of the band given in Task element 6.

TASK ELEMENT 2 STANDARD Identified error and CSP Volume = 2,106 gal/% x _ _ _ _ _ % - 53,000 gal. = _ _ _ _ _ _ gal.

calculated 85,996 gal Comment: Critical EXAMINER NOTE: Error is that the RO supplying the information did not subtract 53,000 gal from the amount that is indicated SAT / UNSAT TASK ELEMENT 3 STANDARD Total Feedwater = DWST Volume + CSP Volume = _ _ _ _ _ _ _ _ gal. Recalculated 297,996 gal Comment: Critical EXAMINER NOTE: If previous value was used this would be reflected as an error carried forward from incorrect calculation of CSP volume. SAT / UNSAT TASK ELEMENT 4 STANDARD Identified error and Determine required Feedwater from Attachment 2-G determined 36,500 gal -

37,500 gal Comment: Critical EXAMINER NOTE: Error is that the RO supplying the information used a curve to reduce temperature to 400 F and not the required 350 F. SAT / UNSAT Refer to A5 key. Acceptable range based on graph interpolation Revision 1 Page 5 of 7 2014 NRC Exam

TASK ELEMENT 5 STANDARD Identified error and Inserted Total Feedwater - Feedwater Required from Att. 2 -G = Available Feed 297,996 gal for Total, water 36,500 gal - 37,500 gal for Total _ _ _ _ _ _ _ _ - Required _ _ _ _ _ _ _ _ = Available _ _ _ _ _ _ _ Required and Calculated 260,496 gal - 261,496 gal for Available.

Comment: Critical EXAMINER NOTE: Total Feedwater and Required Feedwater values given on handout are incorrect and should be corrected based on Task SAT / UNSAT Elements 2-4. Refer to A5 key. Acceptable range of answer depends on acceptable range of Required Feedwater from Task Element 4.

If previous value was used this would be reflected as an error carried forward from incorrect calculation of CSP volume and/or Required Feedwater calculation.

TASK ELEMENT 6 STANDARD Rejected recommendation Calculate the maximum time remaining to place Shutdown Cooling in of RO and used Figure 2-I, service. 2 RCP curve, determined 14.75 - 15.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months Comment: Critical EXAMINER NOTE: Refer to A5 key. Acceptable range of answer depends on acceptable range of Available Feedwater from Task Element SAT / UNSAT 5 based on graph interpolation END OF TASK Revision 1 Page 6 of 7 2014 NRC Exam

APPLICANT CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

Plant tripped 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ago due to a loss of Main Feedwater Plant Conditions as follows:

o RCS THOT = 550 F o DWST level = 54%

o CSP level = 66%

o 2 RCPs have been stopped OP-902-006, Loss of Main Feedwater has been completed up to the step to commence a plant cooldown.

A calculation was performed by the BOP operator to determine the maximum time remaining to place Shutdown Cooling in service at 350 °F based upon Condensate inventory in accordance with OP-902-009, Appendix 2. The BOP operator reports to you, the CRS, that SDC must be placed in service no later than 29 hours3.356481e-4 days 0.00806 hours 4.794974e-5 weeks 1.10345e-5 months from now.

INITIATING CUES:

You are directed to verify the BOP operators calculations and if necessary make any corrections to ensure the calculated time is correct based upon available Condensate Inventory in accordance with OP-902-009.

Revision 1 Page 7 of 7 2014 NRC Exam

Waterford 3 2014 NRC Exam JOB PERFORMANCE MEASURE A6 Review and Approve a Calculation for Determining the Amount of Pure Water That May Be Added to the Refuel Cavity Applicant:

Examiner:

JOB PERFORMANCE MEASURE DATA PAGE Task: Review and approve a calculation for determining the amount of pure water that may be added to the Refuel Cavity.

Task Standard: Applicant reviews a calculation for determining the amount of pure water that can be added to the refueling cavity in accordance with OP-010-006, Outage operations. The results must conform to the answer key.

References:

OP-010-006, Outage Operations Rev 322 TS 3.9.1 COLR Alternate Path: No Time Critical: No Validation Time: 16 mins.

2.1.23 Ability to perform specific system and K/A integrated plant procedures during all Importance Rating 4.4 modes of plant operation.

Level SRO Applicant:

Time Start: Time Finish:

Performance Time: minutes Critical Time: N/A minutes Performance Rating: SAT UNSAT Comments:

Examiner: Date:

Signature Revision 1 Page 2 of 7 2014 NRC Exam

EXAMINER COPY ONLY Tools/Equipment/Procedures Needed:

OP-010-006, Outage Operations Rev 322 (Handout 1)

==

Description:==

The applicant will be directed to review and approve a calculation for the amount of pure water that can be added to the refueling cavity in accordance with OP-010-006, Outage Operations. To perform this calculation the applicant will need to determine what the Refueling Minimum Boron concentration is from Tech Specs. The results will indicate that 1413 gallons of CMU may be added to the refuel cavity instead of the 1500 gallons indicated on the reviewed attachment.

READ TO APPLICANT DIRECTION TO APPLICANT:

Each administrative JPM has a cue sheet with the instructions for that JPM. Each administrative JPM stands alone, and conditions from 1 JPM do not carry over to any other JPM. If you have any questions, raise your hand and I will come to your desk.

Provide all answers on the sheets provided.

(Read the Initial Condition and Cues from the Applicant Cue sheet, and then give the cue sheet and student handout to the applicant.)

Revision 1 Page 3 of 7 2014 NRC Exam

TASK ELEMENT 1 STANDARD Note:

(1) This attachment provides guidance for calculating the amount of pure water that may be added to the Refuel Cavity without dilution to below shutdown margin requirements. This is typically used while Radiation Protection is using CMU to wash down the Refuel Cavity walls to mitigate airborne radioactivity while performing Note reviewed.

Refuel Cavity drain down.

(2) This calculation is only valid for water additions while the Refuel Cavity Water Level is > 20 MSL.

(3) This calculation includes a 50% margin.

SAT / UNSAT 9.24.1 Record the following:

TASK ELEMENT 2 STANDARD Final Refuel Cavity Water Level (Lf): value input verified Comment:

Refer to A6 Key.

SAT / UNSAT TASK ELEMENT 3 STANDARD Initial Refuel Cavity Boron Concentration (Ci) value input verified Comment:

Refer to A6 Key.

SAT / UNSAT Revision 1 Page 4 of 7 2014 NRC Exam

TASK ELEMENT 4 STANDARD Refueling Minimum Boron Concentration (Cf) 2050 ppm Comment: Critical Refer to A6 Key.

SAT / UNSAT The applicant will determine that 2050 ppm is the most restrictive requirement per TS 3.9.1.

The attachment being reviewed has 1985 ppm entered as the refueling minimum boron concentration. 1985 ppm is the reactor engineering boron concentration to maintain Keff < .95. TS 3.9.1 requires the most restrictive of 2050 ppm or the boron concentration to maintain Keff < .95 as the refueling minimum boron concentration. In this case, the most restrictive boron concentration is 2050 ppm.

TASK ELEMENT 5 STANDARD 9.24.2 Calculate the amount of pure water that may be added to the Refuel Cavity (Vw) using the following formula:

Vw = (6954 gal/ft x Lf-79,161 gal) x (1- Cf/Ci) 1402 to 1476 gallons Vw = [( 6954x___ ft) - 79,161]x [1-(___ppm/___ppm)]

Vw=____gallons Comment: Critical EXAMINER NOTE: (Cf/Ci) 2050ppm/2090ppm = .98086124 SAT / UNSAT Rounding up to .981 would yield Vw = 1402.7 gal. Rounding down to .98 would yield Vw = 1476.5 gal.

73,827 x .01913876 = 1413 gallons The attachment being reviewed would have an error carried forward if 1985 ppm is used as the minimum required boron concentration.

TASK ELEMENT 6 STANDARD 9.24.3 Select the lower of Vw calculated in Step 9.24.2 or 1500 gallons: 1402 to 1476 gallons Comment: Critical Refer to A6 Key.

SAT / UNSAT The attachment being reviewed would have an error carried forward if 1985 ppm is used as the minimum required boron concentration.

Revision 1 Page 5 of 7 2014 NRC Exam

TASK ELEMENT 7 STANDARD 9.24.4 SM/CRS designate the allowable amount of pure water to add to the Refuel Cavity by specifying an amount that is < amount specified in Less than or equal to the Step 9.24.3. number calculated in step 9.24.3 SM/CRS designated allowable pure water limit to add to cavity:

Comment: Critical Refer to A6 Key.

SAT / UNSAT The CRS may desire to limit the amount specified in step 9.24.3.

END OF TASK Revision 1 Page 6 of 7 2014 NRC Exam

APPLICANT CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

Waterford 3 is in a refueling outage.

Reactor engineering has determined that a boron concentration of 1985 ppm is required to maintain the refuel cavity at a Keff of < .95.

Refueling Cavity Water Level is 24 ft. and will be drained to 22 ft.

Refueling Cavity boron concentration is 2090 ppm.

INITIATING CUES:

RP has requested that the refuel cavity walls be washed down with CMU as level in the refueling cavity is lowered to 22 ft.

The CRS is to review the calculation for determining refueling minimum boron concentration per Technical Specifications and the performance OP-010-006, .24 Refueling Cavity Boron concentration. IF necessary, correct any problems found on Attachment 9.24.

Revision 1 Page 7 of 7 2014 NRC Exam

Waterford 3 2014 NRC Exam JOB PERFORMANCE MEASURE A7 Review Calculation of Leak Rate for SI-510B Applicant:

Examiner:

JOB PERFORMANCE MEASURE DATA PAGE Task: Review and approval of a calculation for determining the leak rate of RC Loop 2 Hot Leg Injection Inside Containment Check SI-510B.

Task Standard: Applicant identifies error in gross leak rate calculation and then recalculates the gross leak rate, recalculates the corrected leak rate of SI-510B and determines leakage is not acceptable in accordance with OP-903-008, Reactor Coolant System Isolation Leakage Test.

Applicant determines Technical Specification 3.4.5.2 condition e is applicable.

References:

OP-903-008, Reactor Coolant System Isolation Leakage Test Rev 13 Technical Specification 3.4.5.2 Alternate Path: No Time Critical: No Validation Time: 16 mins.

2.2.40 Ability to apply Technical K/A Importance Rating 4.7 Specifications for a System.

Level SRO Applicant:

Time Start: Time Finish:

Performance Time: minutes Critical Time: N/A minutes Performance Rating: SAT UNSAT Comments:

Examiner: Date:

Signature Revision 1 Page 2 of 6 2014 NRC Exam

EXAMINER COPY ONLY Tools/Equipment/Procedures Needed:

OP-903-008, Reactor Coolant System Isolation Leakage Test (Handout 1)

Calculator with capability to raise to the 1/2 power (yx)

==

Description:==

The applicant will be directed to review and accept the calculation of the leak rate of SI-510B based on data provided on Attachment 10.9. The Applicant should first notice an error was made calculating the gross leak rate, the extrapolation ratio coefficient is correct, and the corrected leak rate for valve SI-510B must be re-performed. The corrected leakage will exceed acceptance criteria of 1 GPM and will be 1.18 GPM. This will exceed Technical Specification leakage of 1 GPM and Technical Specification 3.4.5.2 for Reactor Coolant System Operational Leakage will be applicable.

READ TO APPLICANT DIRECTION TO APPLICANT:

Each administrative JPM has a cue sheet with the instructions for that JPM. Each administrative JPM stands alone, and conditions from 1 JPM do not carry over to any other JPM. If you have any questions, raise your hand and I will come to your desk.

Provide all answers on the sheets provided.

(Read the Initial Condition and Cues from the Applicant Cue Sheet, and then give the cue sheet to the applicant.)

Revision 1 Page 3 of 6 2014 NRC Exam

TASK ELEMENT 1 STANDARD 7.9.5.16 / 7.9.6.13 Corrected Leak Rate Calculation for SI-510B:

GROSS LEAK RATE (RG):

RG = 2.64E-4 X VC / TE Calculation corrected to .95 RG = 2.64E-4 X _________ ml / _________ min to .951 GPM RG = _________ GPM Comment: Critical EXAMINER NOTE: Instead of 2.64E-4 the calculation was performed using 2.64E-5 SAT / UNSAT RG = 2.64E-4 X 7200 ml / 2 min Rounding down [(2.64E-4 X 7200) / 2] to 1.9/2 would yield RG = .95 GPM.

Rounding up [(2.64E-4 X 7200) / 2] to 1.901/2 would yield RG = .9505 (Then rounded up to .951) GPM.

Refer to A7 Key TASK ELEMENT 2 STANDARD EXTRAPOLATION RATIO COEFFICIENT (CE): (N/A if RG = 0) 0.5 CE = [2235 PSIG / P2]

0.5 CE = [2235 PSIG / _________ PSIG] 1.24 to 1.242 0.5 CE = [ _________ ]

CE = _________

Comment: Critical 0.5 EXAMINER NOTE: CE = [2235 PSIG / _________ PSIG]

0.5 SAT / UNSAT Rounding down (2235/1450) to 1.54 would yield CE = (1.54) = 1.2409 (Then rounded down to 1.24). Rounding up (2235/1450) to 1.5414 would 0.5 yield CE = (1.5414) = 1.2415 (Then rounded up to 1.242) GPM.

Only Critical if the applicant changes the answer from the correct value which is given to an incorrect value outside of the given range Refer to A7 Key TASK ELEMENT 3 STANDARD CORRECTED LEAK RATE (RC):

RC = RG X CE Calculation corrected to RC = _________ GPM X _________ 1.17 to 1.2 GPM RC = _________ GPM Comment: Critical EXAMINER NOTE: Error carried forward from Gross Leakage Error SAT / UNSAT RC = _________ GPM X _________

Rounding down including min ranges of previous task elements (1.24 X

.95) would yield RC = 1.178 GPM (Then stopped at 2 decimal places =

1.17 GPM). Rounding up including max ranges of previous task elements (1.242 X .951) would yield RC = 1.181 GPM (Then rounded up = 1.2 GPM)

Refer to A7 Key Revision 1 Page 4 of 6 2014 NRC Exam

TASK ELEMENT 4 STANDARD Note: Refer to attachment 10.16, Acceptance Criteria and Test Referred to Attachment Acceptance, for acceptance criteria. 10.16 Comment:

Refer to A7 Key.

SAT / UNSAT TASK ELEMENT 5 STANDARD 10.16.1 SI-4052A(B) leakage limit is less than or equal to 0.375 gpm. Determined step is N/A Comment:

SAT / UNSAT TASK ELEMENT 6 STANDARD 10.16.2 For all check valves tested, test is acceptable if leakage is less Determined leakage is not than or equal to 1 GPM. acceptable Comment: Critical EXAMINER NOTE: This may be satisfied by either annotating on 0.12, Attachment 10.9, Attachment 10.16, or on Cue sheet. SAT / UNSAT TASK ELEMENT 7 STANDARD Determined T.S. 3.4.5.2 Recognize impact of unacceptable check valve leakage Action C is applicable Comment: Critical EXAMINER NOTE: This may be satisfied by either annotating on 0.12, Attachment 10.9, Attachment 10.16, or on Cue sheet. SAT / UNSAT END OF TASK Revision 1 Page 5 of 6 2014 NRC Exam

APPLICANT CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

Plant is in Mode 4 OP-903-008, Reactor Coolant Leakage System Isolation Test is in progress.

RC Loop 2 Hot Leg Injection inside Containment Check SI-510B Leak rate using HPSI Train A has been completed Data has been collected and leak rate calculated for valve SI-510B (RC LOOP 2 HOT LEG INJECTION INSIDE CONTAINMENT) and recorded on Attachment 10.9 INITIATING CUES:

The CRS is to review the calculation for leak rate of SI-510B. IF necessary, correct any problems found on Attachment 10.9 and identify any applicable actions per Technical Specifications. Document any comments/actions on Attachment 10.16 Revision 1 Page 6 of 6 2014 NRC Exam

Waterford 3 2014 NRC Exam JOB PERFORMANCE MEASURE A8 Plan Work and Assign Workers Based on Dose Rates and Shielding Applicant:

Examiner:

JOB PERFORMANCE MEASURE DATA PAGE Task: Plan Work and Assign Workers Based on Dose Rates and Shielding Task Standard: Applicant calculates dose with and without shielding, and calculates 2 workers are required, and directs job to two workers with shielding installed.

References:

N/A Alternate Path: No Time Critical: No Validation Time: 11 mins.

2.3.14 Knowledge of radiation or contamination hazards that may arise K/A Importance Rating 3.8 during normal, abnormal, or emergency conditions or activities.

Level SRO Applicant:

Time Start: Time Finish:

Performance Time: minutes Critical Time: N/A minutes Performance Rating: SAT UNSAT Comments:

Examiner: Date:

Signature Revision 1 Page 2 of 7 2014 NRC Exam

Revision 1 Page 3 of 7 2014 NRC Exam EXAMINER COPY ONLY Tools/Equipment/Procedures Needed:

None READ TO APPLICANT Each administrative JPM has a cue sheet with the instructions for that JPM. Each administrative JPM stands alone, and conditions from 1 JPM do not carry over to any other JPM. If you have any questions, raise your hand and I will come to your desk.

Provide all answers on the sheets provided.

(Read the Initial Condition and Cues from the Applicant Cue sheet, and then give the cue sheet and student handout to the applicant.)

Revision 1 Page 4 of 7 2014 NRC Exam

TASK ELEMENT 1 STANDARD Applicant calculated 600 mrem total Calculate dose for 1 worker with no shielding installed.

dose.

Comment:

EXAMINER NOTE: Applicant may calculate that 1 worker is SAT / UNSAT 90 work minutes and 2 workers are 72 work minutes, and therefore not calculate 1 person dose.

TASK ELEMENT 2 STANDARD Applicant calculated 480 mrem total Calculate dose for 2 workers with no shielding installed.

dose.

Comment: Critical SAT / UNSAT TASK ELEMENT 3 STANDARD Applicant calculated 498 mrem total Calculate dose for 1 worker with shielding installed.

dose.

Comment:

Installing the shielding results in 333 mrem total dose.

SAT / UNSAT Performing the work with 1 worker will result in 165 mrem +

333 mrem = total dose of 498 mrem EXAMINER NOTE: Applicant may calculate that 1 worker is 90 work minutes and 2 workers are 72 work minutes, and therefore not calculate 1 person dose.

TASK ELEMENT 4 STANDARD Applicant calculated 465 mrem total Calculate dose for 2 workers with shielding installed.

dose.

Revision 1 Page 5 of 7 2014 NRC Exam

Comment: Critical Installing the shielding results in 333 mrem total dose.

SAT / UNSAT Performing the job with 2 workers will result in 132 mrem +

333 mrem = total dose of 465 mrem TASK ELEMENT 5 STANDARD Job assigned to 2 workers with shielding Applicant assigns job.

installed.

Comment: Critical Installing the shielding results in 333 mrem total dose.

SAT / UNSAT Performing the job with 2 workers will result in 132 mrem +

333 mrem = total dose of 465 mrem END OF TASK Revision 1 Page 6 of 7 2014 NRC Exam

APPLICANT CUE SHEET (TO BE RETURNED TO EXAMINER TO UPON COMPLETION OF TASK)

Refuel is in progress and Safety Injection Train A is being aligned from its Shutdown Cooling alignment to its Safety Injection alignment. You are the Work Management Center SRO and have been assigned to coordinate the venting of Safety Injection Train A.

The dose rates in Safeguards Room A are 400 mrem/hour unshielded.

Installing shielding will reduce the dose rate to 110 mrem/hour.

It will take 2 workers a total of 25 minutes to install and remove the shielding (25 minutes each worker).

It will take 1 person 90 minutes to complete the venting if he works alone.

It will take 2 people 36 minutes to complete the venting (36 minutes each worker).

How will you direct the execution of the Safety Injection System venting to allow the least amount of total worker dose? Show all calculations to support your answer.

Revision 1 Page 7 of 7 2014 NRC Exam

Waterford 3 2014 NRC Exam JOB PERFORMANCE MEASURE A9 Classify an Emergency Event Applicant:

Examiner:

JOB PERFORMANCE MEASURE DATA PAGE Task: Classify an Emergency event Task Standard: Event classified correctly and declared within 15 minutes of JPM start.

References:

EP-001-001, Recognition and Classification of Emergency Conditions Rev 30 Alternate Path: No Time Critical: Yes Validation Time: 13 mins.

2.4.41, Knowledge of the emergency action K/A Importance Rating 4.6 level thresholds and classifications Level SRO Applicant:

Time Start: Time Finish:

Performance Time: minutes Critical Time: 15 minutes Performance Rating: SAT UNSAT Comments:

Examiner: Date:

Signature Revision 1 Page 2 of 6 2014 NRC Exam

EXAMINER COPY ONLY Tools/Equipment/Procedures Needed:

EP-001-001, Recognition and Classification of Emergency Conditions

==

Description:==

This JPM requires the applicant to determine the emergency action level from the initial conditions within 15 minutes IAW EP-001-001. The declaration will be CA3 Inability to maintain the plant in Cold Shutdown EAL 2 an UNPLANNED event results in RCS pressure increase > 10 psi due to a loss of RCS cooling. The JPM will be performed in the classroom using given data obtained from the Initial Conditions.

READ TO APPLICANT DIRECTION TO APPLICANT:

This is a Time Critical Task Each administrative JPM has a cue sheet with the instructions for that JPM. Each administrative JPM stands alone, and conditions from 1 JPM do not carry over to any other JPM. If you have any questions, raise your hand and I will come to your desk.

Provide all answers on the sheets provided.

(Read the Initial Condition and Cues from the Applicant cue Sheet, and then give the cue sheet and a copy of EP-001-001 to applicant)

Revision 1 Page 3 of 6 2014 NRC Exam

EXAMINER NOTE This JPM will be performed in the classroom using data obtained from the cue sheet provided. Ensure that the applicant turns in all paperwork prior to releasing.

Time Start:

TASK ELEMENT 1 STANDARD 5.2 Classification Determined Event is Real 5.2.1 Verify the off-normal event to ensure that the event is real. by initial conditions Comment:

SAT / UNSAT TASK ELEMENT 2 STANDARD 5.2.2 Match the off-normal event with one of the following six emergency categories:

5.2.2.1 Abnormal Radiation Levels/Radiological Effluents TAB A 5.2.2.2 Cold Shutdown/Refueling System Malfunction TAB C Determined Tab C is 5.2.2.3 ISFSI Malfunction TAB E applicable 5.2.2.4 Fission Product Barrier Degradation TAB F 5.2.2.5 Hazards and Other Conditions Affecting Plant Safety TAB H 5.2.2.6 System Malfunction TAB S Comment:

SAT / UNSAT TASK ELEMENT 3 STANDARD 5.2.3 Refer to Attachment 7.1 Emergency Categories, under the category Determined CA3, EAL #2 is TAB selected in step 5.2.2 above; match the off-normal condition with the applicable appropriate IC to determine the emergency classification.

Critical EXAMINER NOTE: CU5, EAL 1 is also applicable but is an Unusual Event.

SAT / UNSAT Revision 1 Page 4 of 6 2014 NRC Exam

TASK ELEMENT 4 STANDARD 5.2.4 If an event or condition existed which met or exceeded an IC but no emergency was declared the basis for the emergency classification no longer exists at the time of the discovery (rapidly concluded event, missed classification or misclassified event), then do not classify the emergency Determined step is N/A or make offsite notifications.

5.2.4.1 Notify the NRC within one hour of the discovery of the undeclared or misclassified event in accordance with UNT-006-010.

Comment:

SAT / UNSAT TASK ELEMENT 5 STANDARD Procedure Note:

The effects of combinations of initiating conditions that individually Note reviewed constitute a lower classification may be considered as a possibly higher emergency classification.

Comment:

SAT / UNSAT TASK ELEMENT 6 STANDARD Declared CA3, EAL #2 5.2.5 Declare the highest emergency classification for which an IC has within 15 minutes of JPM been met or exceeded start Comment: Critical SAT / UNSAT Time Complete:

Examiner Note: TIME CRITICAL STEP END OF TASK Revision 1 Page 5 of 6 2014 NRC Exam

APPLICANT CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

Plant has just performed a plant cooldown to Mode 5 using SDC train A Plant conditions:

o RCS Temperature = 192 F o RCS Pressure = 360 PSIA o PZR level = 35%

A trip of Low Pressure Safety Injection Pump A occurs At 1000 a loss of offsite power occurs The A Emergency Diesel Generator starts and loads on bus 3A The B Emergency Diesel Generator overspeeds and cannot be reset No Charging pumps are running At 1010 as a result of the above events the following plant conditions exist:

o RCS temperature = 197 F o RCS Pressure = 380 PSIA o PZR level = 38%

INITIATING CUES:

You are directed to classify and declare this event in accordance with EP-001-001, Recognition and Classification of Emergency Conditions This is a time critical task Write your declaration on this sheet Declaration ______________

Revision 1 Page 6 of 6 2014 NRC Exam

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Waterford 3 Date of Examination: 4/07/14 Exam Level RO SRO-I SRO-U Operating Test No.: NRC Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code* Safety Function S1 004 Chemical and Volume Control System Secure Emergency Boration in accordance with OP-901-103, Emergency Boration. (Used on 2012 NRC Exam) D,L,P,S 1 A4.07 Boration/Dilution RO - 3.9, SRO - 3.7 S2 006 Emergency Core Cooling System Mitigate the release of radioactivity through RWSP following RAS Actuation in accordance with OP-902-002, Loss of Coolant accident Recovery.

Fault: LPSI pump continues to run after RAS actuates, requiring the A,D,EN,L,S 2 applicant to manually stop the running LPSI pump after additional valve manipulations.

011 EA1.12 Long term containment of RO - 4.1, SRO - 4.4 radioactivity S3 003 Reactor Coolant Pump System Perform a Reactor Coolant Pump Shutdown in accordance with OP-001-002, Reactor Coolant Pump Operation.

Fault: Reactor Coolant pump reverse rotates requiring stopping of A,D,L,S 4P remaining Reactor Coolant Pumps.

A2.02 Conditions which exist for an abnormal shutdown of an RCP in comparison to a RO - 3.7, SRO - 3.9 normal shutdown of an RCP S4 076 Service Water System Perform a manual start of the Auxiliary Component Cooling water System in accordance with OP-002-001, Auxiliary Component Cooling D,L,S 4S Water.

A4.01 SWS pumps RO - 2.9, SRO - 2.9 S5 026 Containment Spray System Realign Containment Spray for auto initiation following a Containment Spray actuation signal in accordance with OP-902-009, Standard D,EN,L,S 5 Appendices (Appendix 5-E).

A4.01 CSS Controls RO - 4.5, SRO - 4.3 S6 064 Emergency Diesel Generators Restore Power to Safety Bus 3B in accordance with OP-902-000, Standard Post Trip Actions. A,EN,N,S 6 Fault: Tie breaker fails to open automatically. (WF3 OE)

A3.03 Indicating lights, meters, and recorders RO - 3.4, SRO - 3.3 S7 008 Component Cooling Water System Start Component Cooling Water Pump in accordance with OP-901-311, Loss of Train B Safety Bus. D,S 8 A4.01 CCW indications and Controls RO - 3.3, SRO - 3.1 1 2014 NRC Revision 1

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 S8 068 Liquid Radwaste System Discharge Waste Condensate Tank A to the Circulating water System in accordance with OP-007-004, Liquid Waste Management System.

Fault: Upon initiation of flow, LWM flow controller output fails high, A,D,L,S 9 raising flow beyond what is permitted by the release permit.

A4.03 Stoppage of releases if limits RO - 3.9, SRO - 3.8 exceeded In-Plant Systems@ (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)

P1 061 Auxiliary/Emergency Feedwater (AFW) System Establish Local Manual Control of EFW Flow in accordance with OP-009-003, Emergency Feedwater. (PRA Top Operator Action List) D,E,L 4S K1.01 S/G System RO - 4.1, SRO - 4.1 P2 062 A.C. Electrical Distribution Transfer SUPS 014AB from Alternate to Normal AC Power in accordance with OP-006-005, Inverters and Distribution.

A,D,P 6 Fault: After alignment, voltage will not be indicated on SUPS 014 AB inverter. (Used on 2012 NRC Exam)

A3.04 Operation of inverter RO - 2.7, SRO - 2.9 P3 033 Spent Fuel pool Cooling System Restore Spent Fuel Cooling Pump to Operation via the Emergency Diesel Generators in accordance with OP-901-513, Spent Fuel pool E,N,R 8 Cooling Malfunction.

K3.03 Spent fuel temperature RO - 3.0, SRO - 3.3

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

Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 5 (C)ontrol room (D)irect from bank 9/ 8/ 4 9 (E)mergency or abnormal in-plant 1/ 1/ 1 2 (EN)gineered safety feature - / - / 1 (control room system) 3 (L)ow-Power / Shutdown 1/ 1/ 1 7 (N)ew or (M)odified from bank including 1(A) 2/ 2/ 1 2 (P)revious 2 exams 3/ 3/ 2 (randomly selected) 2 (R)CA 1/ 1/ 1 1 (S)imulator 2 2014 NRC Revision 1

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Waterford 3 Date of Examination: 4/07/14 Exam Level RO SRO-I SRO-U Operating Test No.: NRC Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code* Safety Function S1 004 Chemical and Volume Control System Secure Emergency Boration in accordance with OP-901-103, Emergency Boration. (Used on 2012 NRC Exam) D,L,P,S 1 A4.07 Boration/Dilution RO - 3.9, SRO - 3.7 S2 006 Emergency Core Cooling System Mitigate the release of radioactivity through RWSP following RAS Actuation in accordance with OP-902-002, Loss of Coolant accident Recovery.

Fault: LPSI pump continues to run after RAS actuates, requiring the A,D,EN,L,S 2 applicant to manually stop the running LPSI pump after additional valve manipulations.

011 EA1.12 Long term containment of RO - 4.1, SRO - 4.4 radioactivity S3 003 Reactor Coolant Pump System Perform a Reactor Coolant Pump Shutdown in accordance with OP-001-002, Reactor Coolant Pump Operation.

Fault: Reactor Coolant pump reverse rotates requiring stopping of A,D,L,S 4P remaining Reactor Coolant Pumps.

A2.02 Conditions which exist for an abnormal shutdown of an RCP in comparison to a RO - 3.7, SRO - 3.9 normal shutdown of an RCP S4 076 Service Water System Perform a manual start of the Auxiliary Component Cooling water System in accordance with OP-002-001, Auxiliary Component Cooling D,L,S 4S Water.

A4.01 SWS pumps RO - 2.9, SRO - 2.9 S5 S6 064 Emergency Diesel Generators Restore Power to Safety Bus 3B in accordance with OP-902-000, Standard Post Trip Actions. A,EN,N,S 6 Fault: Tie breaker fails to open automatically. (WF3 OE)

A3.03 Indicating lights, meters, and recorders RO - 3.4, SRO - 3.3 S7 008 Component Cooling Water System Start Component Cooling Water Pump in accordance with OP-901-311, Loss of Train B Safety Bus. D,S 8 A4.01 CCW indications and Controls RO - 3.3, SRO - 3.1 3 2014 NRC Revision 1

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 S8 068 Liquid Radwaste System Discharge Waste Condensate Tank A to the Circulating water System in accordance with OP-007-004, Liquid Waste Management System.

Fault: Upon initiation of flow, LWM flow controller output fails high, A,D,L,S 9 raising flow beyond what is permitted by the release permit.

A4.03 Stoppage of releases if limits RO - 3.9, SRO - 3.8 exceeded In-Plant Systems@ (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)

P1 061 Auxiliary/Emergency Feedwater (AFW) System Establish Local Manual Control of EFW Flow in accordance with OP-009-003, Emergency Feedwater. (PRA Top Operator Action List) D,E,L 4S K1.01 S/G System RO - 4.1, SRO - 4.1 P2 062 A.C. Electrical Distribution Transfer SUPS 014AB from Alternate to Normal AC Power in accordance with OP-006-005, Inverters and Distribution.

A,D,P 6 Fault: After alignment, voltage will not be indicated on SUPS 014 AB inverter. (Used on 2012 NRC Exam)

A3.04 Operation of inverter RO - 2.7, SRO - 2.9 P3 033 Spent Fuel pool Cooling System Restore Spent Fuel Cooling Pump to Operation via the Emergency Diesel Generators in accordance with OP-901-513, Spent Fuel pool E,N,R 8 Cooling Malfunction.

K3.03 Spent fuel temperature RO - 3.0, SRO - 3.3

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

Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 5 (C)ontrol room (D)irect from bank 9/ 8/ 4 8 (E)mergency or abnormal in-plant 1/ 1/ 1 2 (EN)gineered safety feature - / - / 1 (control room system) 2 (L)ow-Power / Shutdown 1/ 1/ 1 6 (N)ew or (M)odified from bank including 1(A) 2/ 2/ 1 2 (P)revious 2 exams 3/ 3/ 2 (randomly selected) 2 (R)CA 1/ 1/ 1 1 (S)imulator 4 2014 NRC Revision 1

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Waterford 3 Date of Examination: 4/07/14 Exam Level RO SRO-I SRO-U Operating Test No.: NRC Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code* Safety Function S1 S2 006 Emergency Core Cooling System Mitigate the release of radioactivity through RWSP following RAS Actuation in accordance with OP-902-002, Loss of Coolant accident Recovery.

Fault: LPSI pump continues to run after RAS actuates, requiring the A,D,EN,L,S 2 applicant to manually stop the running LPSI pump after additional valve manipulations.

011 EA1.12 Long term containment of RO - 4.1, SRO - 4.4 radioactivity S3 003 Reactor Coolant Pump System Perform a Reactor Coolant Pump Shutdown in accordance with OP-001-002, Reactor Coolant Pump Operation.

Fault: Reactor Coolant pump reverse rotates requiring stopping of A,D,L,S 4P remaining Reactor Coolant Pumps.

A2.02 Conditions which exist for an abnormal shutdown of an RCP in comparison to a RO - 3.7, SRO - 3.9 normal shutdown of an RCP S4 S5 S6 064 Emergency Diesel Generators Restore Power to Safety Bus 3B in accordance with OP-902-000, Standard Post Trip Actions. A,EN,N,S 6 Fault: Tie breaker fails to open automatically. (WF3 OE)

A3.03 Indicating lights, meters, and recorders RO - 3.4, SRO - 3.3 S7 S8 5 2014 NRC Revision 1

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 In-Plant Systems@ (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)

P1 061 Auxiliary/Emergency Feedwater (AFW) System Establish Local Manual Control of EFW Flow in accordance with OP-009-003, Emergency Feedwater. (PRA Top Operator Action List) D,E,L 4S K1.01 S/G System RO - 4.1, SRO - 4.1 P2 P3 033 Spent Fuel pool Cooling System Restore Spent Fuel Cooling Pump to Operation via the Emergency Diesel Generators in accordance with OP-901-513, Spent Fuel pool E,N,R 8 Cooling Malfunction.

K3.03 Spent fuel temperature RO - 3.0, SRO - 3.3

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

Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 3 (C)ontrol room (D)irect from bank 9/ 8/ 4 3 (E)mergency or abnormal in-plant 1/ 1/ 1 2 (EN)gineered safety feature - / - / 1 (control room system) 2 (L)ow-Power / Shutdown 1/ 1/ 1 3 (N)ew or (M)odified from bank including 1(A) 2/ 2/ 1 2 (P)revious 2 exams 3/ 3/ 2 (randomly selected) 0 (R)CA 1/ 1/ 1 1 (S)imulator 6 2014 NRC Revision 1

Waterford 3 2014 NRC Exam JOB PERFORMANCE MEASURE S1 Securing Emergency Boration Applicant:

Examiner:

JOB PERFORMANCE MEASURE DATA PAGE Task: Secure Emergency Boration in accordance with OP-901-103, Emergency Boration.

Task Standard: Applicant secured Emergency Boration in accordance with step 7 of OP-901-103 without tripping the running Charging Pump.

References:

OP-901-103, Emergency Boration, Rev. 2 OP-002-005, Chemical and Volume Control, Rev. 043 Alternate Path: No Time Critical: No Validation Time: 12 min.

Importance Rating K/A 004 A4.07 Boration/Dilution 3.9/3.7 RO / SRO Level RO/SRO Applicant:

Time Start: Time Finish:

Performance Time: minutes Critical Time: N/A minutes Performance Rating: SAT UNSAT Comments:

Examiner: Date:

Signature Revision 2 Page 2 of 10 2014 NRC Exam

EXAMINER COPY ONLY Tools/Equipment/Procedures Needed:

OP-901-103, Emergency Boration (Handout 1)

OP-002-005, Chemical and Volume Control (Handout 2)

==

Description:==

This task occurs at CP-4. The applicant will perform step 7 of OP-901-103, Emergency Boration. This task secures Emergency Boration and aligns the suction source of the Charging Pumps to the Volume Control Tank. If an applicant does not follow the procedure sequence properly and trips the running Charging Pump, then that applicant would fail this task.

The plant will be emergency borating using the Boric Acid Make-up Pumps.

DIRECTIONS TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Indicate to me when you understand your assigned task.

Read the Initial Condition and Cues from the Applicant Cue Sheet, and then give the cue sheet to the applicant.

Revision 2 Page 3 of 10 2014 NRC Exam

EXAMINER NOTE Cue the Simulator Operator to place the Simulator in RUN.

TASK ELEMENT 1 STANDARD

7. When Emergency Boration termination criteria (Step 6) are met, then Applicant continued on with secure Emergency Boration by performing the following: the procedure.

Comment:

EXAMINER NOTE: Termination criteria is met as given in the initial conditions. SAT / UNSAT TASK ELEMENT 2 STANDARD 7.1 Place VCT Disch Valve, CVC-183, control switch to AUTO and verify CVC-183 is opened.

valve opens Comment: Critical SAT / UNSAT TASK ELEMENT 3 STANDARD Boric Acid Pumps are 7.2 Stop both Boric Acid Pumps.

stopped.

Comment: Critical EXAMINER NOTE: BAM Pump B is the critical element because it is the only Boric Acid pump currently operating. Taking the control switch to SAT / UNSAT either OFF or AUTO will stop the pump.

TASK ELEMENT 4 STANDARD 7.3 Verify the following valves closed:

CVC-507 RWSP to Charging Pumps All valves in step are BAM-133 Emergency Boration Valve closed.

BAM-113A Boric Acid Makeup Gravity Feed Valve A BAM-113B Boric Acid Makeup Gravity Feed Valve B Comment: Critical EXAMINER NOTE: BAM-133, BAM-113A, & BAM-113B will need to be closed. CVC-507 is not critical because it is already in the correct SAT / UNSAT position.

Revision 2 Page 4 of 10 2014 NRC Exam

TASK ELEMENT 5 STANDARD 7.4 Open the following valves:

BAM-126A Boric Acid Makeup Pump A Recirc Valve BAM-126A and B opened.

BAM-126B Boric Acid Makeup Pump B Recirc Valve Comment: Critical EXAMINER NOTE: BAM-126B is the Critical valve because it is the only one that is closed. SAT / UNSAT EXAMINER CUE After the above step has been performed, inform applicant 5 minutes has elapsed for the B Charging Pump. Inform the applicant that the CRS directs him to start Charging Pump A to flush boric acid out of the pump.

TASK ELEMENT 6 STANDARD 7.5 Operate each Charging Pump for at least 5 minutes to flush At least one standby concentrated boric acid out of pump. Charging Pump is operated.

Comment: Critical EXAMINER NOTE: The applicant may use OP-002-005 to swap charging pumps. Task elements 7 through 12 are the steps in OP-002-005, SAT / UNSAT Charging and Letdown System, for swapping charging pumps.

EXAMINER NOTE The JPM is complete after the applicant has started the A Charging pump. The applicant is not required to start the AB Charging pump. If applicant decides to start the A Charging pump in accordance with OP-002-005, Charging and Letdown System, provide the handout to the applicant.

TASK ELEMENT 7 STANDARD Procedure Note:

The Charging Pump Seal System should be operated for at least 30 Reviewed the Note minutes prior to starting the Charging Pump.

Comment:

EXAMINER NOTE: The seal package has been running for 30 minutes as indicated in the initial conditions. SAT / UNSAT EXAMINER CUE: If the applicant calls the RCA watch to verify the seal package running for 30 minutes, then inform him that all seal water pumps have been running for at least 30 minutes.

Revision 2 Page 5 of 10 2014 NRC Exam

TASK ELEMENT 8 STANDARD 6.2.1 At SM/CRS discretion, verify readiness for operation of each Charging Pump to be started as follows:

Verify crankcase oil level 1/2 in bulls eye.

Verify gear reducer oil level between low and high marks on dipstick.

Flush debris and fines from packing seal water system as follows:

A. Place Seal Water Pump A(B)(AB) control switch to ON.

B. Open Charging Pump A (B, AB) Packing Cooling Sump Drain, CVC-704A (B, AB). Applicant communicated with the RCA watch to verify C. If packing cooling tank level continues to lower Charging Pump AB ready after makeup begins, then prior to tank level for a start.

lowering below the bottom of the sight glass, Throttle Closed Charging Pump A(B, AB) Packing Cooling Sump Drain, CVC-704A(B, AB), as necessary to maintain packing cooling tank level visible but 1/2 in sightglass.

D. After flushing the packing cooling tank for at least three minutes, then Close Charging Pump A(B, AB) Packing Cooling Sump Drain, CVC-704A(B, AB).

E. Verify packing cooling tank water level 1/2 in sightglass.

Comment:

EXAMINER CUE: When the applicant calls the RCA watch to perform step 6.2.1, inform the applicant that all pre-start checks are SAT / UNSAT complete. Including:

Proper oil level Suction and discharge valves are open Motor vents unobstructed All personnel clear of the pump Revision 2 Page 6 of 10 2014 NRC Exam

TASK ELEMENT 9 STANDARD Procedure Note:

The purpose of securing the Pressurizer Backup Heater Bank is to minimize the impact of the Charging Pump start on Pressurizer pressure. Note reviewed If the first pump is secured shortly (within approximately one minute) after starting the second pump or PZR boron equalization is in progress, then this step is not necessary when swapping Charging pumps.

Comment:

SAT / UNSAT TASK ELEMENT 10 STANDARD 6.2.2 At SM/CRS discretion, if a Pressurizer Backup Heater Bank is operating, then secure the Pressurizer Backup Heater Bank by Step communicated with placing control switch in AUTO. the CRS.

Comment:

EXAMINER NOTE: No PZR heaters are currently operating EXAMINER CUE: If asked as SM/CRS, inform the applicant that SAT / UNSAT securing a pressurizer backup heater bank is not desired.

TASK ELEMENT 11 STANDARD Procedure Caution:

(1) TO MINIMIZE THERMAL SHOCK OF CHARGING NOZZLES, ONLY ONE CHARGING PUMP SHOULD BE STARTED AT A TIME. Caution reviewed (2) EXTREME CAUTION SHALL BE USED WHEN STARTING ADDITIONAL CHARGING PUMPS WITH THE PRESSURIZER SOLID. EXCESSIVE RCS PRESSURIZATION COULD RESULT.

Comment:

SAT / UNSAT Revision 2 Page 7 of 10 2014 NRC Exam

TASK ELEMENT 12 STANDARD 6.2.3 Start desired Charging Pump A by placing control switch(es) to ON and do not cause a trip of the A or B Charging Pump The A Charging Pump is due to valve misalignments. operated.

Comment: Critical SAT / UNSAT EXAMINER NOTE The JPM is complete after the applicant has started the A Charging pump.

END OF TASK Revision 2 Page 8 of 10 2014 NRC Exam

SIMULATOR OPERATOR INSTRUCTIONS

1. Reset to IC-181

2. Verify Emergency Boration aligned per OP-901-103 using Boric Acid Pumps

3. For 2014 NRC Exam, ensure setup of JPM S5 is performed concurrently

4. There are no malfunctions associated with this JPM Setup with specific IC unavailable or for non NRC exams:

1. Reset the simulator to an IC in Mode 3

2. Establish Emergency Boration IAW OP-901-103 specifically:

a. Place Makeup Mode switch to Manual

b. Open BAM-133

c. Start BAM pump B

d. Close BAM-126B

e. Close CVC-183

f. Open BAM-113A

g. Open BAM-113B

h. Verify Charging Pump A not the charging pump running

3. Place simulator in freeze and save IC Revision 2 Page 9 of 10 2014 NRC Exam

APPLICANT CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

An Excess Steam Demand Event is in progress The crew is responding in accordance with OP-902-004, Excess Steam Demand Recovery Safety Injection has initiated and has been reset The plant is Emergency Borating due to an uncontrolled cooldown The plant cooldown has been stopped by the crews actions Emergency Boration Termination criteria has been met The Standby Charging Pump Seal Packages have been running for 30 minutes, all pump start prerequisites are complete, and an AO is standing by INITIATING CUE:

The CRS directs you to secure Emergency Boration in accordance with OP-901-103, Emergency Boration, step 7 Revision 2 Page 10 of 10 2014 NRC Exam

Waterford 3 2014 NRC Exam JOB PERFORMANCE MEASURE S2 Mitigate Release of Radioactivity through RWSP following RAS Actuation Applicant:

Examiner:

JOB PERFORMANCE MEASURE DATA PAGE Task: Mitigate the release of radioactivity through RWSP following RAS Actuation Task Standard: Applicant completes actions for RAS in accordance with OP-902-002, step 43. Step 43.d must be complete within 2 minutes of RAS.

Step 43.f (2) must be complete within 5 minutes of SI Pump Recirc Isol valve closing.

References:

OP-902-002, Loss of Coolant Accident Recovery Rev 18 Alternate Path: Yes Time Critical: Yes Validation Time: 8 min.

011 EA1.12 Long term containment of Importance Rating K/A 4.1/4.4 radioactivity RO / SRO Level RO/SRO Applicant:

Time Start: Time Finish:

Performance Time: minutes Element 5 - (2)

Critical Time: minutes Element 9 - (5)

Performance Rating: SAT UNSAT Comments:

Examiner: Date:

Signature Revision 2 Page 2 of 10 2014 NRC Exam

EXAMINER COPY ONLY Tools/Equipment/Procedures Needed:

OP-902-002, Loss of Coolant Accident Recovery Procedure (Handout 1)

==

Description:==

This task is performed at CP-8 and CP-4. The operator performs required manipulations after Recirculation Actuation is initiated. After the simulator is taken out of freeze, the RAS will initiate in < 3 minutes.

This JPM has time critical elements. SI-120 A and B and SI-121 A and B must be closed within two minutes of RAS initiation to prevent recirculating SI sump water to the RWSP.

After all SI Recirc Isolation valves are closed, Steps 43.f.1 through 43.f.2 must be completed within five minutes to prevent SI Sump Screen clogging and LPSI Pump A damage.

DIRECTIONS TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Indicate to me when you understand your assigned task.

Read the Initial Condition and Cues from the Applicant Cue Sheet, and then give the cue sheet to the applicant.

Revision 2 Page 3 of 10 2014 NRC Exam

EXAMINER NOTE Cue the Simulator Operator to place the Simulator in RUN. RAS will actuate in < 2 minutes.

TASK ELEMENT 1 STANDARD Verified RAS by either ROM

43. IF the break is inside containment, AND RWSP level is less than indication at CP-7 or RAS 10%,THEN:

Train A and B Logic Initiated a: Verify the RAS is initiated.

annunciator on Panel K.

Comment:

SAT / UNSAT Time RAS actuated:

TASK ELEMENT 2 STANDARD Determined LPSI A continued to run and 43.b: Verify that BOTH LPSI pumps are stopped.

proceeded to contingency step Comment:

Examiner Note: Alternate Path Begins Here SAT / UNSAT EXAMINER NOTE: Applicant should attempt to stop LPSI pump A using the control switch.

TASK ELEMENT 3 STANDARD 43.b.1: IF LPSI pump continues to run THEN continue with Instruction Continued to perform step Step 43.c. 43 Comment:

SAT / UNSAT Revision 2 Page 4 of 10 2014 NRC Exam

TASK ELEMENT 4 STANDARD 43.c: Verify that ESF PUMPS SUCTION SI SUMP valves are open:

SI-602 A and B at CP-8 are

SI 602A open.

SI 602B Comment:

SAT / UNSAT TASK ELEMENT 5 STANDARD 43.d: Close the SI PUMPS RECIRC ISOL VALVES within two minutes of receipt of RAS:

SI-120 A & B and SI-121 A

SI 120A

& B at CP-8 closed within 2

SI 120B minutes of RAS actuation.

SI 121A

SI 121B Comment: Critical SAT / UNSAT Time Last Recirc valve closed:

Examiner Note: TIME CRITICAL STEP TASK ELEMENT 6 STANDARD 43.e: Close the ESF PUMPS SUCTION RWSP:

SI-106 A & B at CP-8

SI 106A closed.

SI 106B Comment: Critical SAT / UNSAT TASK ELEMENT 7 STANDARD Procedure Note: If a LPSI Pump does not trip, perform step 43.f.1-2 actions within five minutes. Time starts at SI Pumps Recirc Isol Valves Note reviewed closed and ends at SI FCVs closed.

Comment:

SAT / UNSAT Revision 2 Page 5 of 10 2014 NRC Exam

TASK ELEMENT 8 STANDARD 43.f: IF any LPSI pump operating, THEN perform the following:

SI-135A throttled open for

1) Throttle Open SI-135A(B) RC LOOP 2(1) SHDN COOLING approximately 10 seconds.

WARM-UP approximately 10 seconds.

Comment: Critical EXAMINER NOTE: SI-135A is a large gate valve that will be adjusted SAT / UNSAT again in Task Element 10.

TASK ELEMENT 9 STANDARD 43.f: IF any LPSI pump operating, THEN perform the following:

2) Reset Open then Close LPSI HEADER TO RC LOOP FLOW CONTROL:

SI-138A & SI-139A Closed.

SI-138A SI-139A Comment: Critical SAT / UNSAT Time Last SI FCV valve closed:

Examiner Note: TIME CRITICAL STEP TASK ELEMENT 10 STANDARD 43.f: IF any LPSI pump operating, THEN perform the following: SI-135A throttled Open to

3) Throttle Open SI-135A to establish approximately 4000 gpm. achieve 3700 - 4300 gpm LPSI flow.

Comment: Critical SAT / UNSAT Revision 2 Page 6 of 10 2014 NRC Exam

TASK ELEMENT 11 STANDARD 43.f: IF any LPSI pump operating, THEN perform the following: Directed field operator to

4) Stop operating LPSI Pump A(B). open breaker for LPSI Pump A.

Comment: Critical EXAMINER NOTE: Applicant should continue on with task performance.

SAT / UNSAT EXAMINER CUE: If informed as CRS that the LPSI pump A failed to stop, ask for a recommendation.

EXAMINER CUE: If applicant asks for permission to continue on while the NAO is opening the breaker for LPSI pump A, provide concurrence as CRS to continue in procedure.

EXAMINER CUE: If applicant directs an NAO to open the breaker for LPSI Pump A, acknowledge request and wait 1 minute and have BOOTH Operator initiate Event Trigger 1.

TASK ELEMENT 12 STANDARD Charging Pump A, B, & AB 43.g: Place ALL charging pumps in "OFF." control switches at CP-4 are OFF.

Comment: Critical SAT / UNSAT TASK ELEMENT 13 STANDARD 43.h: Close CVC 209, CHARGING HEADER ISOLATION. CVC-209 at CP-4 closed.

Comment: Critical EXAMINER NOTE: Key 203 is necessary for this manipulation and is SAT / UNSAT already located in the valve.

Revision 2 Page 7 of 10 2014 NRC Exam

TASK ELEMENT 14 STANDARD 43.i: Verify CVC-507, RWSP TO CHARGING PUMPS SUCTION CVC-507 checked closed ISOLATION closed.

Comment:

SAT / UNSAT END OF TASK The following table may be filled out for evaluating performance of time critical steps:

Time recorded Time recorded Task Element 1 Required Time Task element 1 Task Element 5 to Task Element 5 Completion Time Performance

< 2 minutes SAT / UNSAT Time recorded Time recorded Task Element 5 Required Time Task element 5 Task Element 9 to Task Element 9 Completion Time Performance

< 5 minutes SAT / UNSAT Revision 2 Page 8 of 10 2014 NRC Exam

SIMULATOR OPERATOR INSTRUCTIONS

1. Reset to IC-182

2. Verify the following is inserted:

a. RC01 LOSS OF ALL RCPS

b. RC23A RCS COLD LEG 1A RUPTURE with a severity of 100%

c. RP08M RELAY K104 FAILED, RAS TRAIN A (LPSI) is inserted (LPSI pump A fails to trip on RAS)

d. DI-08A05S02-1 LPSI Pump A is set to START (C/S overridden to start)

e. SIR32 LPSI PUMP A is set to RACKOUT on Event Trigger 1

3. Place key 203 in CVC-209 control switch)

TO PREVENT EXAM COMPROMISE, REMOVE ANY KEYS FROM THE RTGB BETWEEN RUNS OF THIS JPM AND VERIFY THEY ARE RETURNED TO THEIR PROPER LOCATION.

Do not place the Simulator in Run until the operator is ready to perform the task and cued by lead examiner. RAS occurs within 2 minutes of going to run.

Once the Applicant reaches Step 43.f.4), and informs the NAO to open LPSI Pump A breaker, THEN initiate Event Trigger 1 Setup with specific IC unavailable or for non NRC exams:

1. Reset the simulator to an IC at any power level

2. Insert commands listed above

3. Allow simulator to run until RAS actuates

4. Backtrack simulator for approximately 2 minutes

5. Place simulator in Run and acknowledge annunciators

6. Place simulator in freeze and save IC Revision 2 Page 9 of 10 2014 NRC Exam

APPLICANT CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

A Loss of Coolant Accident is in progress The crew is responding in accordance with OP-902-002, Loss of Coolant Accident Recovery RAS initiation is imminent This is a time critical task INITIATING CUE:

The CRS has directed you to perform step 43 of OP-902-002, after RAS initiates.

Revision 2 Page 10 of 10 2014 NRC Exam

Waterford 3 2014 NRC Exam JOB PERFORMANCE MEASURE S3 Perform a Reactor Coolant Pump Shutdown Applicant:

Examiner:

JOB PERFORMANCE MEASURE DATA PAGE Task: Perform A Reactor Coolant Pump Shutdown (With Reverse Rotation)

Task Standard: Reactor Coolant Pump 2A secured in accordance with OP-001-002 section 6.2., reverse rotation is recognized and RCPs 1A, 1B, & 2B are secured in accordance with OP-901-130.

References:

OP-001-002, Reactor Coolant Pump Operation Rev 021 OP-901-130, Reactor Coolant Pump Malfunction Rev 007 Alternate Path: Y Time Critical: N Validation Time: 18 min.

003 A2.02 Conditions which exist for an abnormal shutdown of an RCP in Importance Rating K/A 3.7/3.9 comparison to a normal shutdown of an RO / SRO RCP Level RO/SRO Applicant:

Time Start: Time Finish:

Performance Time: minutes Critical Time: N/A minutes Performance Rating: SAT UNSAT Comments:

Examiner: Date:

Revision 1 Page 2 of 10 2014 NRC Exam

Signature Revision 1 Page 3 of 10 2014 NRC Exam

EXAMINER COPY ONLY Tools/Equipment/Procedures Needed:

OP-001-002, Reactor Coolant Pump Operation, Section 6.2 (Handout 1)

OP-901-130, Reactor Coolant Pump Malfunction, Section E0 & E5 (Handout 2)

==

Description:==

This task is performed at CP-2. The examinee will perform a Reactor Coolant Pump Shutdown for Reactor Coolant Pump 2A. After the Reactor Coolant Pump is shutdown it will come to a stop and then start rotating in the reverse direction. Reverse rotation is indicated on the PMC. OP-002-001, Reactor Coolant Pump Operation directs implementation of OP-901-130, Reactor Coolant Pump Malfunction.

The task is complete after the examinee secures the remaining three Reactor Coolant Pumps.

DIRECTIONS TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Indicate to me when you understand your assigned task.

Read the Initial Condition and Cues from the Applicant Cue Sheet, and then give the cue sheet to the applicant.

Revision 1 Page 4 of 10 2014 NRC Exam

EXAMINER NOTE Cue the Simulator Operator to place the Simulator in RUN.

TASK ELEMENT 1 STANDARD Procedure Caution:

ALL CLOSED REACTOR TRIP BREAKERS WILL OPEN ON FIRST RCP Caution reviewed TRIP UNLESS REACTOR COOLANT LOW FLOW BYPASSES ARE ENABLED.

Comment:

SAT / UNSAT TASK ELEMENT 2 STANDARD 6.2.1 For RCP to be secured (1A, 1B, 2A, or 2B), Place associated RCP One Lift Oil Pump for RCP (1A, 1B, 2A, 2B) Oil Lift Pump A or B control switch to ON and verify 2A started lift pump Starts.

Comment:

SAT / UNSAT TASK ELEMENT 3 STANDARD 6.2.1.1 Verify remaining RCP 1A (1B, 2A, 2B) Oil Lift Pump B or A control Checked remaining Lift Oil switch in AUTO. Pumps in AUTO.

Comment:

SAT / UNSAT TASK ELEMENT 4 STANDARD Procedure Caution:

CBO AND CCW FLOW TO SEAL COOLERS SHOULD BE MAINTAINED Caution reviewed AFTER RCP HAS BEEN SECURED UNTIL RCS TEMPERATURE HAS BEEN REDUCED TO <140°F.

Comment:

SAT / UNSAT Revision 1 Page 5 of 10 2014 NRC Exam

EXAMINER NOTE RCP reverse rotation fault occurs at the following step. Approximately 45 seconds after the RCP 2A C/S is is placed to STOP, the RCP speed will reduce to approximately 0 RPM and quickly rotate in the reverse direction to a speed of approximately 540 RPM and stabilize. This indication is on the Plant Monitoring Computer and should be viewed by the applicant as part of the task.

TASK ELEMENT 5 STANDARD 6.2.2 Stop desired RCP 1A (1B, 2A, 2B) by placing its associated control RCP 2A is secured switch at CP-2 to Stop.

Comment: Critical SAT / UNSAT TASK ELEMENT 6 STANDARD 6.2.3 When RCP 1A (1B, 2A, 2B) speed indicates rotor is at rest, as indicated by PMC PID (PIDs are listed on Attachment 11.2), or with Recognized RCP is not at SM/CRS authorization, then secure operating RCP 1A (1B, 2A, 2B) rest Oil Lift Pumps by placing their control switches to OFF.

Comment:

Examiner Note: Alternate Path Begins Here SAT / UNSAT TASK ELEMENT 7 STANDARD 6.2.3.1 After RCP 1A (1B, 2A, 2B) has been secured for approximately 5 Determined RCP 2A is minutes, then verify all secured RCPs are not rotating in the rotating in the reverse reverse direction by observing zero speed indicated on the direction.

computer points listed in Attachment 11.2.

Comment: Critical SAT / UNSAT EXAMINER NOTE: ~45 seconds after the RCP 2A C/S is manipulated, the RCP speed will reduce to approximately 0 RPM and quickly rotate in the reverse direction to a speed of ~540 RPM and stabilize.

This is when it is time to provide cue below.

EXAMINER CUE: 5 minutes have elapsed.

Revision 1 Page 6 of 10 2014 NRC Exam

TASK ELEMENT 8 STANDARD 6.2.3.2 If PMC points indicate any RCP is rotating in the reverse direction, then refer to OP-901-130, Reactor Coolant Pump Malfunction Entered OP-901-130 and notify SM/CRS.

Comment:

EXAMINER CUE: If the applicant informs the SM/CRS of the need to perform OP-901-130, acknowledge applicants statement. If asked as SAT / UNSAT the CRS how to proceed, ask the applicant for a recommendation.

EXAMINER NOTE The following steps are from subsection E5 of OP-901-130.

TASK ELEMENT 9 STANDARD NOTE Indicated speed will not go negative when an RCP rotates in the reverse Note reviewed direction, it will be an absolute number. Speed will indicate approximately 600 rpm for the affected RCP when the other three RCPs are running.

Comment:

SAT / UNSAT TASK ELEMENT 10 STANDARD

1. Monitor Reactor Coolant Pump after shutdown for reverse rotation with the following methods:

IF conditions permit, THEN verify reverse rotation by local Re-verified reverse rotation observation. of RCP 2A using PID PMC PIDs D13214 (RCP 1A), D13614 (RCP 1B), D13414 (RCP 2A) D13414 and D13814 (RCP 2B).

Associated RCP PMC mimic Comment:

SAT / UNSAT Revision 1 Page 7 of 10 2014 NRC Exam

TASK ELEMENT 11 STANDARD check one Lift Oil Pump for

2. Start an oil lift pump on affected RCP.

RCP 2A running Comment:

SAT / UNSAT TASK ELEMENT 13 STANDARD

3. Remove ALL Reactor Coolant Pumps from service. RCP 1A, 1B, 2B secured Comment: Critical SAT / UNSAT END OF TASK Revision 1 Page 8 of 10 2014 NRC Exam

SIMULATOR OPERATOR INSTRUCTIONS

1. Reset to IC-183

2. Verify RC33C RCP2A ARRDFAILURE WITH ARRD TEMP SEVERITY set to a value of 172.229

3. Take simulator to RUN

4. Acknowledge PMC Alarms Setup with specific IC unavailable or for non NRC exams:

1. Reset the simulator to an IC in Mode 3

2. Ensure all Reactor Trip Breakers are open

3. Insert Malfunction listed above

4. Place simulator in freeze and save IC Revision 1 Page 9 of 10 2014 NRC Exam

APPLICANT CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

The Reactor is in MODE 3 with all Reactor Trip Breakers open The plant is preparing to perform an RCS cooldown to MODE 5 INITIATING CUE:

The CRS directs you to secure Reactor Coolant Pump 2A in accordance with OP-001-002, Reactor Coolant Pump Operation, section 6.2.

Revision 1 Page 10 of 10 2014 NRC Exam

Waterford 3 2014 NRC Exam JOB PERFORMANCE MEASURE S4 Perform a Manual Startup of ACCW Pump Applicant:

Examiner:

JOB PERFORMANCE MEASURE DATA PAGE Task: Perform manual startup of ACCW pump Task Standard: ACCW Pump started, temperature setpoint adjusted and controller placed in Auto

References:

OP-002-001, Auxiliary Component Cooling water Rev 305 Alternate Path: No Time Critical: No Validation Time: 12 min.

Importance Rating K/A 076 A4.01 SWS pumps 2.9/2.9 RO / SRO Level RO/SRO Applicant:

Time Start: Time Finish:

Performance Time: minutes Critical Time: N/A minutes Performance Rating: SAT UNSAT Comments:

Examiner: Date:

Signature Revision 2 Page 2 of 10 2014 NRC Exam

EXAMINER COPY ONLY Tools/Equipment/Procedures Needed:

OP-002-001, Auxiliary Component Cooling water (Handout 1)

==

Description:==

This task is performed at CP-33. The applicant will be directed to place the A train of ACCW in service in manual mode and adjust the temperature setpoint to 84 F in accordance with OP-002-001, Auxiliary Component Cooling water System. There are no faults selected for this JPM.

DIRECTIONS TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Indicate to me when you understand your assigned task.

Read the Initial Condition and Cues from the Applicant Cue Sheet, and then give the cue sheet to the applicant.

Revision 2 Page 3 of 10 2014 NRC Exam

EXAMINER NOTE Cue the Simulator Operator to place the Simulator in RUN.

TASK ELEMENT 1 STANDARD 6.2.1 Verify system has been filled and vented, in accordance with Step reviewed Section 5.1, Fill and Vent.

Comment:

EXAMINER CUE: If asked, inform applicant that section 5.1 has SAT / UNSAT previously been completed TASK ELEMENT 2 STANDARD 6.2.2 Prior to starting the selected ACC Pump, verify a visible clearance NAO dispatched exists between piping and jack stand.

Comment:

EXAMINER CUE: Respond as NAO and inform applicant that a SAT / UNSAT visible clearance between the piping and jack stand has been verified.

TASK ELEMENT 3 STANDARD 6.2.3 Verify following ACC Wet Cooling Tower Fan groups are in Auto:

Verified fans are in Auto ACC Wet Cooling Tower A(B) Fans 1A(B) through 4A(B)

ACC Wet Cooling Tower A(B) Fans 5A(B) through 8A(B)

Comment:

SAT / UNSAT TASK ELEMENT 4 STANDARD 6.2.4 Verify ACC Pump A(B) Discharge Line Isolation, ACC-110A(B), in ACC-110A verified in AUTO AUTO.

Comment:

SAT / UNSAT Revision 2 Page 4 of 10 2014 NRC Exam

TASK ELEMENT 5 STANDARD 6.2.5 Verify Locked Open ACC Pump A(B) Recirc Line Isolation, ACC-Dispatched NAO to verify 107A(B).

Comment:

EXAMINER CUE: Respond as NAO and inform applicant that ACC- SAT / UNSAT 107A is locked open.

TASK ELEMENT 6 STANDARD 6.2.6 Close ACC Header A(B) CCW HX Outlet Temp Control Valve, Closes ACC-126A using ACC-126A(B), using Component Cooling Water Header A(B)

CC-ITIC-7070A in manual Temperature Indicating Controller, CC-ITIC-7070A(B), in Manual.

Comment:

SAT / UNSAT TASK ELEMENT 7 STANDARD 6.2.7 Verify ACCW Pump A(B) bearing oil level is between the OFF Dispatched NAO to verify level marks Comment:

EXAMINER CUE: Respond as NAO and inform applicant that oil level SAT / UNSAT is between the OFF level marks and is ready for a start.

Revision 2 Page 5 of 10 2014 NRC Exam

TASK ELEMENT 8 STANDARD Caution - (1) REACTIVITY SHOULD BE MONITORED FOR CHANGES, WHEN CHANGING CCW TEMPERATURE CAUSES LETDOWN TEMPERATURE CHANGES. LOWERING LETDOWN TEMPERATURE MAY REMOVE BORON FROM ION EXCHANGER EFFLUENT AND RAISING LETDOWN TEMPERATURE MAY RELEASE BORON INTO ION Caution reviewed EXCHANGER EFFLUENT.

(2) CHANGING CCW TEMPERATURE WILL CAUSE CHANGES IN CONTAINMENT PRESSURE. LOWERING CONTAINMENT PRESSURE WILL CAUSE INDICATED CONTAINMENT SPRAY RISER LEVEL TO LOWER.

Comment:

SAT / UNSAT EXAMINER CUE: If asked about Containment Spray Riser level, report that level is not close to the Technical Specification limit.

TASK ELEMENT 9 STANDARD Start ACC Pump A(B).. ACC Pump A started using 6.2.8 control switch Comment: Critical SAT / UNSAT EXAMINER CUE: 1 minute after applicant starts ACCW Pump A, report as NAO that the ACCW.pump looks good on start.

TASK ELEMENT 10 STANDARD 6.2.9 Verify ACC Jockey Pump A(B) Stops Verified jockey pump stops Comment:

SAT / UNSAT Revision 2 Page 6 of 10 2014 NRC Exam

TASK ELEMENT 11 STANDARD Caution - IT MAY BE NECESSARY TO THROTTLE COOLING WATER TO ACC PUMP OIL COOLER IF THRUST BEARING TEMPERATURE IS Caution reviewed LESS THAN 70°F AFTER 15 MINUTES OF OPERATION.

Comment:

SAT / UNSAT TASK ELEMENT 12 STANDARD 6.2.10 Verify Open ACC Pump A(B) Discharge Line Isolation, ACC-Verified ACC-110A opened 110A(B).

Comment:

SAT / UNSAT TASK ELEMENT 13 STANDARD 6.2.11 Verify ACCW Pump A(B) bearing oil level is between the RUN Dispatched NAO to verify mark and the HIGH mark and flow exists through the sightglass.

Comment:

EXAMINER CUE: Respond as NAO and inform applicant that oil level SAT / UNSAT is between the run mark and the high mark and the sightglass shows flow.

TASK ELEMENT 14 STANDARD Note - Recommend 1000 gpm flow through ACC-126A(B) to minimize Note reviewed pump vibration.

Comment:

SAT / UNSAT EXAMINER NOTE: Applicant may raise flow to > 1000 GPM in manual.

Revision 2 Page 7 of 10 2014 NRC Exam

TASK ELEMENT 15 STANDARD 6.2.12 Restore Component Cooling Water Header A(B) Temperature Setpoint is set > 82 F and <

Indicating Controller, CC-ITIC-7070A(B), setpoint to 95 F or as 86 F otherwise directed by the SM/CRS.

Comment: Critical EXAMINER NOTE: The temperature setpoint is contained on the cue SAT / UNSAT sheet TASK ELEMENT 16 STANDARD 6.2.13 Verify Component Cooling Water Header A(B) Temperature Controller is placed in Auto Indicating Controller, CC-ITIC-7070A(B), is in AUTO.

Comment: Critical SAT / UNSAT END OF TASK Revision 2 Page 8 of 10 2014 NRC Exam

SIMULATOR OPERATOR INSTRUCTIONS

1. Reset to IC-184

2. For 2014 NRC Exam, ensure setup of JPM S8 is performed concurrently

3. There are no malfunctions associated with this JPM Setup with specific IC unavailable or for non NRC exams:

1. Reset the simulator to an IC in Mode 3

2. Ensure no ACCW pumps are operating initially

3. Set ACC-126A(B) setpoint to > 90 F < 95 F

4. Place simulator in freeze and save IC Revision 2 Page 9 of 10 2014 NRC Exam

APPLICANT CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

The plant is in MODE 3 Auxiliary Component Cooling Water System has been filled and vented in accordance with Section 5.1 of OP-002-001.

ATC is monitoring activity INITIATING CUE:

The CRS directs you to manually start up the A train of ACCW and set the temperature setpoint to 84 F in accordance with OP-002-001 section 6.2.

Revision 2 Page 10 of 10 2014 NRC Exam

Waterford 3 2014 NRC Exam JOB PERFORMANCE MEASURE S5 Realign Containment Spray for Auto Initiation following CSAS Applicant:

Examiner:

JOB PERFORMANCE MEASURE DATA PAGE Task: Realign Containment Spray for Auto Initiation Following CSAS Task Standard: Reset initiation and actuation relays, stopped CS Pumps, and realigned discharge valves

References:

OP-902-009, Standard Appendices Rev 309 Alternate Path: No Time Critical: No Validation Time: 13 min.

Importance Rating K/A 026A4.01 CSS controls 4.5/4.3 RO / SRO Level RO/SRO Applicant:

Time Start: Time Finish:

Performance Time: minutes Critical Time: N/A minutes Performance Rating: SAT UNSAT Comments:

Examiner: Date:

Signature Revision 2 Page 2 of 8 2014 NRC Exam

EXAMINER COPY ONLY Tools/Equipment/Procedures Needed:

OP-902-004, Excess Steam Demand Recovery OP-902-009, Standard Appendices (Handout 1)

==

Description:==

This task will be performed at CP-8, CP-10, and CP-33 during an excess steam demand accident that resulted in a CSAS. Containment pressure has since reduced below 16.4 PSIA and conditions have been met to reset Containment Spray. The operator will realign containment spray for automatic initiation IAW OP-902-009 Appendix 5 Attachment 5-E. There are no faults associated with this JPM.

DIRECTIONS TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Indicate to me when you understand your assigned task.

Read the Initial Condition and Cues from the Applicant Cue Sheet, and then give the cue sheet to the applicant.

Revision 2 Page 3 of 8 2014 NRC Exam

EXAMINER NOTE Cue the Simulator Operator to place the Simulator in RUN.

TASK ELEMENT 1 STANDARD 1.1 Place control switches for the following valves to "CLOSE:"

Control switches for CC-

CC 641, CCW RCP INLET OUTSIDE ISOL 641, CC-710, CC-713 in

CC 710, CCW RCP OUTLET INSIDE ISOL CLOSE

CC 713, CCW RCP OUTLET OUTSIDE ISOL Comment:

SAT / UNSAT TASK ELEMENT 2 STANDARD 1.2 Reset CSAS Initiation relays on ALL four channels as follows: Trains A, B, C, D reset

a. Place the Reset Permissive switch to "UNLK" position. (CP-10) permissive switch unlocked,

b. Press CSAS Reset pushbutton. CSAS reset pushbuttons

c. Verify the initiation relay indicator lit on the ENGINNERED SAFETY depressed for each train, FEATURES SYSTEM mimic. trains A, B, C, D reset

d. Place the Reset permissive switch to "LK" position. permissive switch to LK Comment: Critical SAT / UNSAT TASK ELEMENT 3 STANDARD 1.3 Reset CSAS actuation logic on BOTH trains as follows: Train A and B CSAS reset

a. Press the CSAS Reset pushbuttons. (CP-33) pushbuttons depressed Comment: Critical SAT / UNSAT Revision 2 Page 4 of 8 2014 NRC Exam

TASK ELEMENT 4 STANDARD 1.3 Reset CSAS actuation logic on BOTH trains as follows:

b. Verify the actuation relay indicator lit on the ENGINEERED SAFETY Verified relay indicators lit FEATURES SYSTEM mimic. (CP-10)

Comment:

SAT / UNSAT TASK ELEMENT 5 STANDARD 1.4 Stop ONE CS pump at a time. Either A or B CS pump switch placed to stop Comment: Critical SAT / UNSAT TASK ELEMENT 6 STANDARD CS pump that was not 1.5 IF a CS pump is operating, THEN stop the remaining CS pump. stopped previously is stopped Comment: Critical SAT / UNSAT TASK ELEMENT 7 STANDARD 1.6 Close the following Containment Spray valves:

CS 125A, CNTMT SPRAY HEADER A ISOL CS-125A and CS-125B

CS 125B, CNTMT SPRAY HEADER B ISOL closed Comment: Critical SAT / UNSAT EXAMINER NOTE: These valves will be closed by placing the control switch to open and then to close.

Revision 2 Page 5 of 8 2014 NRC Exam

TASK ELEMENT 8 STANDARD 1.7 Place BOTH Containment Spray pump control switches to normal Both CS pump control position. switches to normal Comment: Critical SAT / UNSAT EXAMINER NOTE: Normal position is the mid position.

END OF TASK Revision 2 Page 6 of 8 2014 NRC Exam

SIMULATOR OPERATOR INSTRUCTIONS

1. Reset to IC-181

2. Verify containment pressure < 16.4 PSIA

3. For 2014 NRC Exam, ensure setup of JPM S1 is performed concurrently IF POTENTIAL FOR EXAM COMPROMISE EXISTS THEN REMOVE ANY KEYS FROM THE RTGB BETWEEN RUNS OF THIS JPM AND VERIFY THEY ARE RETURNED TO THEIR PROPER LOCATION.

Setup with specific IC unavailable or for non NRC exams:

1. Reset the simulator to an IC at any power level in Mode 1

2. Insert a main steam line break inside Containment

3. When Containment Spray Actuates, delete the malfunction and insert the main steam line break on the same Steam Generator outside Containment (This is to empty the Steam Generator without raising Containment pressure too high)

4. Stop all RCPs

5. Once Steam Generator Blowdown is complete, delete the malfunction

6. Allow Containment pressure to reduce below 16.4 PSIA

7. Allow conditions to stabilize

8. Place simulator in freeze and save IC Revision 2 Page 7 of 8 2014 NRC Exam

APPLICANT CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

An Excess Steam Demand Event is in progress The crew is responding in accordance with OP-902-004, Excess Steam Demand Recovery Containment pressure has reduced to <16.4 PSIA and is stable INITIATING CUES:

The CRS has directed you reset Containment Spray Actuation Signal in accordance with OP-902-009 Appendix 5E.

Revision 2 Page 8 of 8 2014 NRC Exam

Waterford 3 2014 NRC Exam JOB PERFORMANCE MEASURE S6 Restore Power to Bus 3B Applicant:

Examiner:

JOB PERFORMANCE MEASURE DATA PAGE Task: Restore Power to Safety Bus 3B IAW OP-902-000, Standard Post Trip Actions.

Task Standard: Applicant attempts to transfer auxiliaries to the UAT and when Reactor trips, performs Standard Post Trip Actions from memory to restore power to Safety Bus 3B by tripping breaker 3-2.

References:

OP-006-001, Plant Distribution (7KV, 4KV, and SSD) System Rev 314 OP-902-000, Standard Post Trip Actions Rev 15 Alternate Path: Yes Time Critical: No Validation Time: 9 min.

064 A3.03 Indicating lights, meters, and Importance Rating K/A 3.4/3.3 recorders RO / SRO Level RO/SRO Applicant:

Time Start: Time Finish:

Performance Time: minutes Critical Time: N/A minutes Performance Rating: SAT UNSAT Comments:

Examiner: Date:

Signature Revision 1 Page 2 of 11 2014 NRC Exam

Revision 1 Page 3 of 11 2014 NRC Exam EXAMINER COPY ONLY Tools/Equipment/Procedures Needed:

OP-006-001, Plant Distribution (7KV, 4KV, and SSD) System (Handout 1)

OP-902-000, Standard Post Trip Actions

==

Description:==

This task takes place at CP-1. The applicant will assume the shift as the BOP operator during a plant startup at the step to transfer auxiliaries to the Unit Auxiliary Transformers. The applicant will align the A train busses and when the B train is aligned, the B UAT will fail. The failure will result in a Reactor Trip due to a loss of flow to the RCS. The B generator output breaker will fail to open resulting in a loss of offsite power to the B electrical busses. The applicant will perform the maintenance of vital auxiliaries section of OP-902-000 from memory. The applicant will trip the main generator using the trip pushbuttons, trip the generator output breaker, and recognize that the EDG started but did not supply its respective bus. The applicant will perform immediate action to open breaker 3-2 tie allowing the EDG to provide power to bus 3B.

DIRECTIONS TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Indicate to me when you understand your assigned task.

Read the Initial Condition and Cues from the Applicant Cue Sheet, and then give the cue sheet to the applicant.

Revision 1 Page 4 of 11 2014 NRC Exam

EXAMINER NOTE Cue the Simulator Operator to place the Simulator in RUN.

TASK ELEMENT 1 STANDARD 6.3.1 Transfer from Startup Transformer (SUT) A to Unit Auxiliary Transformer (UAT) A as follows: Verified with initial 6.3.1.1 Verify Unit Auxiliary Transformer A in service in accordance with conditions OP-006-008, Transformer Operation.

Comment:

SAT / UNSAT EXAMINER CUE: If asked, provide cue that the both UAT are in service in accordance with OP-006-008, Transformer Operation TASK ELEMENT 2 STANDARD 6.3.1.2 Verify all fault relays Reset on CP-15 for Unit Auxiliary Fault Relays verified reset Transformer A.

Comment:

SAT / UNSAT TASK ELEMENT 3 STANDARD Bus A transfer switch in 6.3.1.3 Place Bus A Transfer switch to UAT.

UAT Comment: Critical SAT / UNSAT TASK ELEMENT 4 STANDARD 6.3.1.3.1 Verify the following Startup Transformer A breakers Open:

7KV-EBKR-1A-4 and 4KV-7KV-EBKR-1A-4 Startup Transformer A 7KV Isolation EBKR-2A-4 checked open 4KV-EBKR-2A-4 Startup Transformer A 4KV Isolation Comment:

SAT / UNSAT Revision 1 Page 5 of 11 2014 NRC Exam

TASK ELEMENT 5 STANDARD 6.3.1.3.2 Verify the following Unit Auxiliary Transformer A breakers Closed: Verified with initial 7KV-EBKR-1A-1 Unit Auxiliary Transformer A 7KV Isolation conditions 4KV-EBKR-2A-1 Unit Auxiliary Transformer A 4KV Isolation Comment:

SAT / UNSAT TASK ELEMENT 6 STANDARD 6.3.2 Transfer from Startup Transformer (SUT) B to Unit Auxiliary Transformer (UAT) B as follows: Verified with initial 6.3.2.1 Verify Unit Auxiliary Transformer B in service in accordance with conditions OP-006-008, Transformer Operation.

Comment:

SAT / UNSAT TASK ELEMENT 7 STANDARD 6.3.2.2 Verify all fault relays Reset on CP-15 for Unit Auxiliary Fault Relays verified reset Transformer B.

Comment:

SAT / UNSAT EXAMINER NOTE The fault is inserted at the following step and these steps should be performed from memory.

TASK ELEMENT 8 STANDARD Bus B transfer switch in 6.3.2.3 Place Bus B Transfer switch to UAT.

UAT Comment: Critical SAT / UNSAT Revision 1 Page 6 of 11 2014 NRC Exam

TASK ELEMENT 9 STANDARD Immediate actions Recognize Turbine and Reactor Trip, proceed to SPTAs commenced Comment:

EXAMINER NOTE: Alternate Path Begins Here SAT / UNSAT EXAMINER CUE: Provide cue to applicant to perform Standard Post Trip Actions as the Balance of Plant Operator TASK ELEMENT 10 STANDARD

2. Determine that Maintenance of Vital Auxiliaries acceptance criteria are met:

a. Check the Main Turbine is tripped: Governor valves and throttle

Governor valves closed valves checked closed

Throttle valves closed Comment:

SAT / UNSAT TASK ELEMENT 11 STANDARD

b. Check the Main Generator is tripped:

Determined Generator

GENERATOR BREAKER A tripped Breaker B is closed and

GENERATOR BREAKER B tripped proceeded to contingency

EXCITER FIELD BREAKER tripped Comment:

SAT / UNSAT Revision 1 Page 7 of 11 2014 NRC Exam

TASK ELEMENT 12 STANDARD b.1 Perform ANY of the following:

1) Manually trip the Main Generator using BOTH GENERATOR EMERG TRIP pushbuttons.

Pushed Both Generator

2) Manually trip the Main Generator by performing ALL of the following:

emergency Trip

a. Transfer BOTH electrical buses from UAT to SUT.

pushbuttons or opened

b. Open the following breakers:

Generator Breaker B

GENERATOR BREAKER A

GENERATOR BREAKER B

EXCITER FIELD BREAKER Comment:

SAT / UNSAT EXAMINER NOTE: Applicant will be successful either by pushing both Generator Emergency pushbuttons or manually tripping the Generator output breaker. Preferred order would be using the Generator Pushbuttons as they are numbered steps.

The motoring of the Generator isolated offsite power due to the breaker failure to open scheme so the Generator is no longer motoring after offsite power was lost to the B busses.

TASK ELEMENT 13 STANDARD

c. Check station loads are energized from offsite electrical power as follows:

Train A

A1, 6.9 KV non safety bus

A2, 4.16 KV non safety bus

A3, 4.16 KV safety bus

A-DC electrical bus Recognized bus B3

A or C vital AC Instrument Channel deenergized and proceeded Train B to contingency

B1, 6.9 KV non safety bus

B2, 4.16 KV non safety bus

B3, 4.16 KV safety bus

B-DC electrical bus

B or D vital AC Instrument Channel Comment:

SAT / UNSAT Revision 1 Page 8 of 11 2014 NRC Exam

TASK ELEMENT 14 STANDARD c.1 IF ANY 4.16 KV safety bus is NOT powered from offsite, THEN:

1) Verify associated EDG has started AND EDG output breaker closed. Determined EDG output

2) IF EDG output breaker is NOT closed Breaker not closed, EDG THEN: Voltage checked, tripped

Verify stable EDG Voltage 3920 - 4350 AC Volts. breaker 3-2 tie, checked

Verify 3-2 Breaker open. sequencer lockout not

Check Sequencer LOCKOUT NOT illuminated. illuminated, and checked

3) IF EDG output breaker is NOT closed AND Step c.1.2) is met THEN CCW pump running for B locally close EDG output breaker. EDG.

4) Verify CCW cooling available to EDG.

Comment: Critical EXAMINER NOTE: Only tripping the 3-2 breaker is critical for task SAT / UNSAT completion.

END OF TASK Revision 1 Page 9 of 11 2014 NRC Exam

SIMULATOR OPERATOR INSTRUCTIONS

1. Reset to IC-190

2. RESET ANY FAULT RELAYS ON CP-15 BETWEEN EACH RESET FOR THIS JPM

3. RESET SIMULATOR LIGHTING BETWEEN EACH RESET FOR THIS JPM

4. Verify the following (Should be loaded in IC):

a. EG04B MAIN GENERATOR B OUTPUT BREAKER FAILS TO OPEN (Active)

b. EG04B is set to delete in 1 second on Event Trigger 2

c. ED23B 3BS TO B2 BUS BREAKER FAILS TO TRIP ON UV tied to Event Trigger 1 (Inactive)

d. ED02F LOSS OF UAT-B TRANSFORMER tied to Event Trigger 1 (Inactive)

5. Ensure Event Trigger 1 is inserted as follows (Should be loaded in IC)

a. Event - UAT/SUT B SWITCH in UAT

b. Code is ZDIEDSTECS2235(1) == 1

6. Ensure Event Trigger 2 is inserted as follows: (Should be loaded in IC)

a. Event - Generator Trip - Both Required

b. Code is ZDIEGGENECS2201(1) == 1 & ZDIEGGENECS2205(1) ==

1 Setup with specific IC unavailable or for non NRC exams:

1. Reset the simulator to an IC with the turbine ready to sync to the Grid

2. Sync the turbine to the grid in accordance with OP-010-004

3. Adjust Generator load to obtain approximately 60 MWe

4. Stabilize plant conditions

5. Enter malfunctions and Triggers listed above

6. Place simulator in freeze and save IC Revision 1 Page 10 of 11 2014 NRC Exam

APPLICANT CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

The plant is performing a startup S/G levels are being maintained by an additional operator ATC watch is controlling RCS parameters You are the BOP operator Both Startup Transformers are in service Both Unit Auxiliary Transformers are ready to be placed in service INITIATING CUE:

The CRS directs you to transfer auxiliaries from the Startup Transformers to the Unit Auxiliary Transformers in accordance with OP-006-001, section 6.3.

Revision 1 Page 11 of 11 2014 NRC Exam

Waterford 3 2014 NRC Exam JOB PERFORMANCE MEASURE S7 Start Component Cooling Water Pump AB Applicant:

Examiner:

JOB PERFORMANCE MEASURE DATA PAGE Task: Start Component Cooling Water Pump AB as the second CCW Pump.

Task Standard: Transfer 3AB Bus to the A train and start Component Cooling Water Pump AB in accordance with OP-901-311, Loss of Train B Safety Bus.

References:

OP-901-311, Loss of Train B Safety Bus Rev 309 Alternate Path: No Time Critical: No Validation Time: 7 min.

Importance Rating K/A 008 A4.01 CCW indications and controls 3.3/3.1 RO / SRO Level RO/SRO Applicant:

Time Start: Time Finish:

Performance Time: minutes Critical Time: N/A minutes Performance Rating: SAT UNSAT Comments:

Examiner: Date:

Signature Revision 1 Page 2 of 8 2014 NRC Exam

Revision 1 Page 3 of 8 2014 NRC Exam EXAMINER COPY ONLY Tools/Equipment/Procedures Needed:

OP-901-311, Loss of Train B Safety Bus (Handout 1)

==

Description:==

This task takes place at CP-1 and CP-8. Plant conditions start after a Loss of B Safety bus. Emergency Diesel Generator B tripped on overspeed; the 3B Safety Bus is not energized. Component Cooling Water Pump A is running. The applicant will be directed to start CCW Pump AB as the second CCW Pump. The 3AB Bus will be aligned to Train B, requiring an AB Bus transfer prior to starting CCW Pump AB.

DIRECTIONS TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Indicate to me when you understand your assigned task.

Read the Initial Condition and Cues from the Applicant Cue Sheet, and then give the cue sheet to the applicant.

Revision 1 Page 4 of 8 2014 NRC Exam

EXAMINER NOTE Cue the Simulator Operator to place the Simulator in RUN.

TASK ELEMENT 1 STANDARD

2. If BUS AB3 is not energized, then align BUS AB3 to BUS A3 as follows: BUS TIE B TO AB 2.1 BUS TIE B TO AB to TRIP keyswitch is in TRIP Comment: Critical SAT / UNSAT TASK ELEMENT 2 STANDARD BUS AB STATUS 2.2 BUS AB STATUS SELECTOR to A SELECTOR switch is in A Comment: Critical SAT / UNSAT TASK ELEMENT 3 STANDARD BUS TIE A TO AB 2.3 BUS TIE A TO AB to CLOSE keyswitch is in CLOSE Comment: Critical SAT / UNSAT TASK ELEMENT 4 STANDARD

3. Verify two Component Cooling Water Pumps operating and supplying both A and B loops.

CCW Assignment Switch is 3.1 If CCW Pump AB is the standby pump and it is desired to align this in position B pump for service, then perform the following:

3.1.1 Place CCW Assignment Switch to position B.

Comment: Critical SAT / UNSAT Revision 1 Page 5 of 8 2014 NRC Exam

TASK ELEMENT 5 STANDARD 3.1.2 Verify Open the following valves: CC-126B, CC-114B, CC-CC-126B/CC-114B CCW Suct & Disch Header Tie Valves AB to B 127B, and CC-115B are CC-127B/CC-115B CCW Suct & Disch Header Tie Valves AB to B verified open Comment:

SAT / UNSAT TASK ELEMENT 6 STANDARD 3.1.3 Start CCW Pump AB. CCW Pump AB is running Comment: Critical SAT / UNSAT END OF TASK Revision 1 Page 6 of 8 2014 NRC Exam

SIMULATOR OPERATOR INSTRUCTIONS

1. Reset to IC-186

2. Verify the following (Should be loaded in IC):

a. EG10B DG OVERSPEED TRIP (Active)

b. DI-01A07S16-1 B2 TO B3 TIE BKR is set to TRIP

3. Ensure Bus AB is aligned to the B train Setup with specific IC unavailable or for non NRC exams:

1. Reset to an IC in Mode 1

2. Insert commands listed above

3. Ensure bus AB is aligned to the B train

4. Place simulator in freeze and save IC Revision 1 Page 7 of 8 2014 NRC Exam

APPLICANT CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

A Loss of Bus 3B has occurred.

Emergency Diesel Generator B tripped on Overspeed.

INITIATING CUE:

The CRS directs you to align the 3AB bus to the A bus and start Component Cooling Water Pump AB using OP-901-311, Loss of Train B Safety Bus, section E0 step 2 and 3.

Revision 1 Page 8 of 8 2014 NRC Exam

Waterford 3 2014 NRC Exam JOB PERFORMANCE MEASURE S8 Waste Condensate Tank Discharge Applicant:

Examiner:

JOB PERFORMANCE MEASURE DATA PAGE Task: Discharge Waste Condensate Tank in accordance with OP-007-004, Liquid Waste Management System Task Standard: Applicant reset LWM integrator, recorded initial data, and initiated Waste Condensate Tank release by opening LWM-441 and LWM-442. Applicant recognized controller failed to maximum output and stops release by closing valves LWM-441 and LWM-442 on CP-4.

References:

OP-007-004, Liquid Waste Management System Rev 306 CE-003-514, Liquid Radioactive Waste Release Permit (Computer)

Rev 301 Alternate Path: Yes Time Critical: No Validation Time: 9 min.

068 A4.03 Stoppage of releases if limits Importance Rating K/A 3.9/3.8 exceeded RO / SRO Level RO/SRO Applicant:

Time Start: Time Finish:

Performance Time: minutes Critical Time: N/A minutes Performance Rating: SAT UNSAT Comments:

Examiner: Date:

Signature Revision 2 Page 2 of 8 2014 NRC Exam

EXAMINER COPY ONLY Tools/Equipment/Procedures Needed:

OP-007-004, Liquid Waste Management System (Handout 1)

Discharge Permit for Waste Condensate Tank A (Handout 2)

Release request form (Handout 3)

==

Description:==

This task is performed at CP-4. The applicant will be tasked with initiating a discharge of Waste Condensate Tank A. The cue will indicate that the operator in the field has completed all required lineups and is standing by. When the applicant initiates flow, the controller output will fail to maximum. The applicant will stop discharge flow by closing the discharge isolation valve(s).

DIRECTIONS TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Indicate to me when you understand your assigned task.

Read the Initial Condition and Cues from the Applicant Cue Sheet, and then give the cue sheet to the applicant.

Revision 2 Page 3 of 8 2014 NRC Exam

EXAMINER NOTE Cue the Simulator Operator to place the Simulator in RUN.

TASK ELEMENT 1 STANDARD 6.10.8 On CP-4, Reset Liquid Waste Discharge Flow Integrator to zero. Integrator is reset to zero Comment: Critical SAT / UNSAT TASK ELEMENT 2 STANDARD 6.10.9 Record WCT level and Liquid Waste Discharge Integrator reading Reading is recorded on the on Liquid Release Permit. Release Permit Comment:

SAT / UNSAT TASK ELEMENT 3 STANDARD 6.10.10 Verify Liquid Waste Discharge Flow Controller, LWM-IFIC-0647, Verification complete in Manual with 0% output.

Comment:

SAT / UNSAT TASK ELEMENT 4 STANDARD Procedure Caution: If Circulating Water flow is reduced to less than that required by the discharge permit, then discharge shall be secured Caution reviewed immediately.

Comment:

SAT / UNSAT Revision 2 Page 4 of 8 2014 NRC Exam

EXAMINER NOTE The combined control switch on CP-4 will open LWM-441 and give an open permissive to LWM-442.

LWM-442 is operated using controller LWM-IFIC-0647, also on CP-4.

TASK ELEMENT 5 STANDARD 6.10.11 To start discharging WCT, perform the following:

6.10.11.1 Momentarily position Liquid Waste Condensate Flow Control LWM-441 is opened using hand switch, LWM-441 and LWM-442, to Open until LWM-441 control switch indicates Open.

Comment: Critical SAT / UNSAT EXAMINER NOTE When flow rises above the trigger setpoint, the controller output will fail to maximum output. The applicant will be required to secure flow by closing LWM-441 and LWM-442 on CP-4.

TASK ELEMENT 6 STANDARD 6.10.11.2 Adjust flow using Liquid Waste Condensate Flow Controller, LWM-442 is throttled open LWM-IFIC-0647, not to exceed value specified on Liquid using controller to a flow > 0 Release Permit. gpm Comment: Critical SAT / UNSAT EXAMINER NOTE: Alternate Path Begins Here EXAMINER CUE: Direct the applicant to achieve a flow rate of 40 gpm.

EXAMINER NOTE: The controller failure is set to occur when indicated flow exceeds 10 gpm. If applicant does not exceed 10 gpm then cue the booth operator to manually initiate Event Trigger 1.

Revision 2 Page 5 of 8 2014 NRC Exam

TASK ELEMENT 7 STANDARD Recognize discharge flow rate is greater than release permit and stop the LWM-441 and LWM-442 release closed Comment: Critical EXAMINER NOTE: The applicant may proceed to step 6.10.17 to perform this action. SAT / UNSAT EXAMINER: If directed as NAO to stop WCT Pump A, then use remote function WDR21 to stop the WCT pump and report that the pump has been stopped after 1 minute.

END OF TASK Revision 2 Page 6 of 8 2014 NRC Exam

SIMULATOR OPERATOR INSTRUCTIONS

1. IF there are no gallons indicated on the LWM Flow totalizer, THEN reset to IC-184, discharge greater than 100 gallons of water and proceed to step 2.

2. Reset to IC-184

3. For 2014 NRC Exam, ensure setup of JPM S4 is performed concurrently

4. Verify the following (Should be loaded in IC):

a. DI-04A3A12C-3 LWM-IFIC-0647 DISCHARGE VALVES LIQUID WASTE CONDEN is tied to Event Trigger 1 (Inactive) with a final value of PUSH.

b. DI-04A3A12D-4 LWM-IFIC-0647 DISCHARGE VALVES LIQUID WASTE CONDEN is tied to Event Trigger 1 (Inactive) with a final value of RELEASE.

c. DI-04A3A12A-1 LWM-IFIC-0647 DISCHARGE VALVES LIQUID WASTE CONDEN is tied to Event Trigger 1 (Inactive) with a final value of RELEASE.

5. Ensure Event Trigger 1 is inserted as follows (Should be loaded in IC)

a. Event - LWM Flow > 10 gpm

b. Code is ZAOWDLWMIFRR0647(1) > 0.1 Setup with specific IC unavailable or for non NRC exams:

1. Prepare a discharge release permit

2. Reset to an IC in Mode 3

3. discharge greater than 100 gallons of water

4. Enter malfunctions and Triggers listed above

5. Insert Remote WDR21 WASTE COND PUMP A LWM-MPMP-005A set to START. (This will not appear in the Director Summary in a snapped IC)

6. Place simulator in freeze and save IC Revision 2 Page 7 of 8 2014 NRC Exam

APPLICANT CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

The plant is in Mode 3 Waste Condensate Tank A has been prepared for discharge.

The RCA Watch reports that he has completed step 6.10.6 in OP-007-004, Liquid Waste Management System, and that Attachment 11.4, Waste Condensate Tank Discharge Checklist, is complete up to step 20.

INITIATING CUE:

The Control Room Supervisor directs you to commence discharging Waste Condensate Tank A, starting at step 6.10.8 of OP-007-004, Liquid Waste Management System.

Revision 2 Page 8 of 8 2014 NRC Exam

Appendix D Scenario Outline Form ES-D-1 Facility: Waterford 3 Scenario No.: 1 Op Test No.:

Examiners: Operators:

Initial Conditions: Reactor power is 100%, MOC Turnover:

Protected Train is B, AB Busses are aligned to Train B, Nothing is OOS, maintain 100%

power Event Malf. Event Event No. No. Type* Description (A) VCT level instrument CVC-ILT-0227 Fails high diverting I - ATC letdown to the Boron Management system. OP-901-113, 1 CVC12A1 I - SRO Volume Control Tank Makeup Control Malfunction C - BOP (A) Atmospheric Dump Valve on Steam Generator #1 C - SRO spuriously opens requiring closing in accordance with OP-2 MS23A TS - SRO 901-221, Secondary System Transient. (TS 3.7.1.7)

R - ATC N - BOP (A) Control Element Assembly CEA #9 drops into the core N - SRO requiring a rapid plant down power to 70%.

3 RD02 A09 TS - SRO OP-901-102, CEA or CEDMCs Malfunction. (TS 3.1.3.1)

Main Feedwater Pump B loss of oil pressure trip results in a Reactor Power Cutback and unanalyzed rod configuration 4 FW32 B M - ALL and reactor trip. OP-902-000, Standard Post Trip Actions.

3 Control Element Assemblies fail to insert into the core RD11 A07 following the reactor trip, Emergency Boration (Critical Task RD11 A37 1, commence emergency boration prior to exiting step 1 5 RD11 A39 C - ATC of OP-902-000)

Main Turbine fails to trip automatically requiring manual action. OP-902-000, Standard Post Trip Actions. (Critical Task 2, trip the main turbine prior to TCOLD lowering to 6 RP03 C - BOP 443 F)

Main Feedwater Pump A overspeed trip resulting in a loss of C - ATC Main Feedwater requiring stopping of 2 RCPs. OP-902-006, 7 FW03 A C - SRO Loss of Main Feedwater Recovery Procedure RP05 A6/A7 Emergency Feedwater fails to actuate requiring manual RP05 B6/B7 action to initiate Emergency Feedwater. (Critical Task 3, RP05 C6/C7 manually actuate EFW prior to SG level lowering to <

8 RP05 D6/D7 I - BOP 20% WR) (#2 Dominant Accident Sequence)

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor 2014 NRC Exam Scenario 1 D-1 Rev 2

Scenario Event Description NRC Scenario 1 The crew assumes the shift at 100% power with instructions to maintain 100% power.

After taking the shift, Volume Control Tank level instrument CVC-ILT-0227 fails high resulting in valve CVC-169 diverting letdown to the Boron Management System. The ATC should recognize this through indications on the Plant Monitoring Computer. The SRO should enter into procedure OP-901-113, Volume Control Tank Makeup Control Malfunction, and direct the ATC to place valve CVC-169 to the VCT position.

After the procedure has been reviewed and a brief has occurred, the setpoint for #1 Steam Generator Atmospheric Dump Valve (ADV) fails low and the controller MS-IPIC-0303-A1 demands the ADV fully open. The SRO should enter into procedure OP-901-221, Secondary System Transient and direct the BOP to manually close the valve by placing controller MS-IPIC-0303-A1 in manual control and lowering the output to minimum. The SRO should review Technical Specification 3.7.1.7 and determine that the ADV will need to be restored to operable status in automatic within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be below 70% Rated Thermal Power within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

After the SRO addresses Technical Specifications of the above event, Control Element Assembly #9 (Regulating group 4) drops into the core. The SRO should enter into procedure OP-901-102, CEA or CEDMCS Malfunction and proceed to section E1, CEA Misalignment Greater than 7 inches. The SRO will direct the BOP to adjust turbine load to match T AVG to TREF initially and then perform a rapid plant downpower (commence direct boration to the RCS) within 15 minutes of the dropped CEA to comply with Technical Specification 3.1.3.1 and the COLR. The SRO should evaluate and enter Technical Specifications 3.1.3.1 action c.

After the crew has performed a significant portion of the downpower and at lead Examiner discretion, Main Feedwater Pump B will develop an oil leak that will lead to a loss of oil pressure and a trip of the pump. The BOP will note the tripped pump and a Reactor Power Cutback will occur as expected. The Reactor Power cutback combined with a previous dropped CEA will result in an unanalyzed rod configuration and the ATC will conduct a manual Reactor Trip. During the trip 3 CEAs remain fully withdrawn and the ATC will commence emergency boration to the RCS in accordance with OP-902-000, Standard Post Trip Actions (Critical Task 1). While the ATC is emergency borating the RCS, the turbine will fail to automatically trip and MSIS will fail to actuate requiring the BOP to manually trip the turbine or close the Main Steam Isolation Valves in accordance with OP-902-000, Standard Post Trip Actions (Critical Task 2).

While the crew is progressing through the action steps of OP-902-000, Standard Post Trip Actions, Main Feedwater Pump A will trip on an overspeed condition resulting in a complete loss of Main Feedwater.

The crew will complete Standard Post Trip Actions and enter diagnostics. The crew will enter Appendix 1 of OP-902-009, Standard Appendices and diagnose into OP-902-006, Loss of Main Feedwater Recovery Procedure. The SRO will direct the BOP to ensure that Emergency Feedwater is available to the Steam Generators. At this point, or earlier depending on when the narrow range level in the Steam Generators reaches 27.4% and lowering, Emergency Feedwater actuation failed to occur. The BOP must take action to ensure that a heat sink exists by manually actuating Emergency Feedwater Actuation Signal, establishing Auxiliary Feedwater flow, or depressurizing the Steam Generators and injecting with Condensate pumps (Critical Task 3). In Waterford 3 Probalistic Risk Analysis, the #2 Dominant Accident Sequence that would lead to core damage is a Loss of Main Feedwater with an EFW failure. This accident would (statistically speaking) constitute 20.86% of all core damage events at WF3. This is mitigated by performing Critical Task 3. The crew will continue on in OP-902-006 and stop 1 RCP in each loop.

The scenario may be terminated once all critical tasks have been completed or performance standards exceeded and when the crew stops 2 RCPs in accordance with OP-902-006, Loss of Main Feedwater Recovery or at the discretion of the lead examiner.

2014 NRC Exam Scenario 1 D-1 Rev 2

NRC Scenario 1 CRITICAL TASKS

1. ESTABLISH REACTIVITY CONTROL This task is satisfied by commencing Emergency Boration flow by either Boric Acid makeup pumps or Gravity Feed valves in accordance with OP-902-000, Standard Post Trip Actions step 1 prior to exiting the step to verify Reactivity Control. This task becomes applicable following the initiation of a Reactor Trip.

2. ESTABLISH REACTIVITY CONTROL This task is satisfied by stopping the steam flow to the Main Turbine by either tripping the Main Turbine manually or by closing the Main Steam Isolation valves before TCOLD lowers to below 443 F. This task becomes applicable following the initiation of the Reactor Trip signal.

3. ESTABLISH RCS HEAT REMOVAL This task is satisfied by manually actuating Emergency Feedwater Actuation System, manually starting at least 1 Emergency Feedwater pump, aligning and starting the Auxiliary Feedwater pump, or depressurizing at least 1 Steam Generator and injecting the Steam Generator with Condensate flow prior to Steam Generator levels reducing below 20% Wide Range in both Steam Generators. This task becomes applicable once Steam Generator water level reduces below 27.4% Narrow Range in one or both Steam Generators.

Scenario Quantitative Attributes

1. Total malfunctions (5-8) 8

2. Malfunctions after EOP entry (1-2) 4

3. Abnormal events (2-4) 3

4. Major transients (1-2) 1

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

6. EOP contingencies requiring substantive actions (0-2) 0

7. Critical tasks (2-3) 3 2014 NRC Exam Scenario 1 D-1 Rev 2

NRC Scenario 1 SCENARIO SETUP A. Reset Simulator to IC-187.

B. Verify Scenario Malfunctions, Remotes, and overrides are loaded, as listed in the Scenario Timeline.

C. Ensure Protected Train B sign is placed in SM office window.

D. Verify EOOS is 10.0 Green with nothing out of service E. Complete the simulator setup checklist.

F. Start Insight, open file Crew Performance.tis.

2014 NRC Exam Scenario 1 D-1 Rev 2

NRC Scenario 1 SIMULATOR BOOTH INSTRUCTIONS Event 1 VCT level instrument, CVC-ILT-0227, Fails High

1. On Lead Examiner's cue, initiate Event Trigger 1.

2. If Work Week Manager or PMI are called, inform the caller that a work package will be assembled and a team will be sent to the Control Room.

Event 2 ADV #1 Controller MS-IPIC-0303A SETPOINT FAILURE

1. On Lead Examiner's cue, initiate Event Trigger 2.

2. If Work Week Manager or PMI are called, inform the caller that a work package will be assembled and a team will be sent to the Control Room.

Event 3 CEA #9 Falls into the core

1. On Lead Examiner's cue, initiate Event Trigger 3.

2. If Work Week Manager or PMI are called, inform the caller that a work package will be assembled and a team will be sent to CEDMCS Alley.

3. If called as RAB and directed to CEDMCs Alley, respond in 3 minutes that you have arrived. If asked, report that there is no apparent cause for the dropped CEA.

4. If Chemistry is called to sample the RCS for Dose Equivalent Iodine due to the down power, acknowledge and report that samples will be taken 2-6 hours from notification time and if asked tell the caller your name is Joe Chemist.

5. If notified as Load Dispatcher (Woodlands) acknowledge the communications and inform the caller that the grid will remain stable with available backup generation.

6. If requested to monitor Polisher Vessel D/P and remove as necessary, acknowledge the report.

Event 4 Main Feedwater pump B Lube oil leak/trip

1. On Lead Examiner's cue, initiate Event Trigger 4.

2. After event is initiated, wait 2 minutes and report as NAO that a significant oil leak is coming from B Main Feedwater pump.

3. If directed as NAO to open the breakers from the oil pumps, wait 2 minutes and initiate Event Trigger 14.

Event 5-6 3 CEAs stuck out on Reactor Trip and Main Turbine Fails to Trip

1. No actions for these events.

Event 7 Main Feedwater Pump A overspeed trip

1. On lead examiner's cue, initiate Event Trigger 7.

2. If called as NAO to check status of Main Feedwater Pump A, wait 2 minutes and report that you are unable to determine why it has tripped.

Event 8 Emergency Feedwater Actuation System fails to actuate

1. No actions for this event.

2. At the end of the scenario, before resetting, end data collection and save the file as 2014 Scenario 1-(start-end time).tid. Export to .csv file. Save the file into the folder for the appropriate crew..

2014 NRC Exam Scenario 1 D-1 Rev 2

NRC Scenario 1 SCENARIO TIMELINE DELAY RAMP EVENT KEY DESCRIPTION TRIGGER FINAL HH:MM:SS HH:MM:SS EVENT DESCRIPTION 8 RP05B6 FAILS TO TRIP CH B LO S/G LEVEL #1(EFAS-1) N/A 00:00:00 00:00:00 ACTIVE EFAS FAILS TO ACTUATE ON LOW S/G LEVEL 8 RP05B7 FAILS TO TRIP CH B LO S/G LEVEL #2(EFAS-2) N/A 00:00:00 00:00:00 ACTIVE EFAS FAILS TO ACTUATE ON LOW S/G LEVEL 8 RP05C6 FAILS TO TRIP CH C LO S/G LEVEL #1(EFAS-1) N/A 00:00:00 00:00:00 ACTIVE EFAS FAILS TO ACTUATE ON LOW S/G LEVEL 8 RP05C7 FAILS TO TRIP CH C LO S/G LEVEL #2(EFAS-2) N/A 00:00:00 00:00:00 ACTIVE EFAS FAILS TO ACTUATE ON LOW S/G LEVEL 8 RP05D6 FAILS TO TRIP CH D LO S/G LEVEL #1(EFAS-1) N/A 00:00:00 00:00:00 ACTIVE EFAS FAILS TO ACTUATE ON LOW S/G LEVEL 8 RP05D7 FAILS TO TRIP CH D LO S/G LEVEL #2(EFAS-2) N/A 00:00:00 00:00:00 ACTIVE EFAS FAILS TO ACTUATE ON LOW S/G LEVEL 6 RP08G RELAY K305 FAILED, MSISTRAIN A (MS/FW) N/A 00:00:00 00:00:00 ACTIVE MAIN STEAM ISOLATION SIGNAL FAILS TO ACTUATE 2014 NRC Exam Scenario 1 D-1 Rev 2

NRC Scenario 1 DELAY RAMP EVENT KEY DESCRIPTION TRIGGER FINAL HH:MM:SS HH:MM:SS EVENT DESCRIPTION 6 RP09F RELAY K305 FAILED, MSISTRAIN B (MS/FW) N/A 00:00:00 00:00:00 ACTIVE MAIN STEAM ISOLATION SIGNAL FAILS TO ACTUATE 6 RP08H RELAY K313 FAILED, MSISTRAIN A (MS/FW) N/A 00:00:00 00:00:00 ACTIVE MAIN STEAM ISOLATION SIGNAL FAILS TO ACTUATE 6 RP09H RELAY K313 FAILED, MSISTRAIN B (MS/FW) N/A 00:00:00 00:00:00 ACTIVE MAIN STEAM ISOLATION SIGNAL FAILS TO ACTUATE 5 RD11A07 CEA 07 MECHANICALLY STUCK N/A 00:00:00 00:00:00 ACTIVE CEA 07 FAILS TO INSERT 5 RD11A37 CEA 37 MECHANICALLY STUCK N/A 00:00:00 00:00:00 ACTIVE CEA 37 FAILS TO INSERT 5 RD11A39 CEA 39 MECHANICALLY STUCK N/A 00:00:00 00:00:00 ACTIVE CEA 39 FAILS TO INSERT 6 RP03 REACTOR TRIP WITH NO AUTO TURBINE TRIP N/A 00:00:00 00:00:00 ACTIVE TURBINE FAILS TO TRIP AUTOMATICALLY 1 CV12A1 VCT LEVEL XMTR CVC-ILIC-0227 FAILS HI 1 00:00:00 00:00:00 ACTIVE VCT LEVEL TRANSMITTER FAILS HIGH 2 MS23A ADV 1 CNTRLR MS-IPIC-0303A SETPT FAILURE (0-1200 PSIG) 2 00:00:00 00:00:00 0 ATMOSPHERIC DUMP VALVE CONTROLLER FAILURE 2014 NRC Exam Scenario 1 D-1 Rev 2

NRC Scenario 1 DELAY RAMP EVENT KEY DESCRIPTION TRIGGER FINAL HH:MM:SS HH:MM:SS EVENT DESCRIPTION 3 RD02A09 DROPPED CEA 09 3 00:00:00 00:00:00 ACTIVE DROPPED CEA 09 4 FW32B MFW PUMP B LUBE OIL PIPE BREAK 4 00:00:00 00:00:00 65 MFW PUMP B LUBE OIL PIPE BREAK 7 FW03A MFW PUMP A OVERSPEED TRIP 7 00:00:00 00:00:00 ACTIVE MFW PUMP A OVERSPEED TRIP 8 RP05A6 FAILS TO TRIP CH A LO S/G LEVEL #1(EFAS-1) N/A 00:00:00 00:00:00 ACTIVE EFAS FAILS TO ACTUATE ON LOW S/G LEVEL 8 RP05A7 FAILS TO TRIP CH A LO S/G LEVEL #2(EFAS-2) N/A 00:00:00 00:00:00 ACTIVE EFAS FAILS TO ACTUATE ON LOW S/G LEVEL 4 FWR67 SGFP B MOP-1 BREAKER 14 00:00:00 00:00:00 OPEN OIL PUMP BREAKER REMOTE FUNCTION 4 FWR68 SGFP B MOP-2 BREAKER 14 00:00:00 00:00:00 OPEN OIL PUMP BREAKER REMOTE FUNCTION 4 FWR69 SGFP B EOP BREAKER 14 00:00:00 00:00:00 OPEN OIL PUMP BREAKER REMOTE FUNCTION 2014 NRC Exam Scenario 1 D-1 Rev 2

NRC Scenario 1 REFERENCES Event Procedures 1 OP-901-113, Volume Control Tank Makeup Control Malfunction, Rev. 301 2 OP-901-221, Secondary System Transient, Rev. 0 Technical Specification 3.7.1.7 3 OP-901-102, CEA or CEDMCS Malfunction, Rev. 301 OP-901-212, Rapid Plant Power Reduction, Rev. 6 OP-901-501, PMC or Core Operating Limit Supervisory System Malfunction, Rev. 13 Technical Specification 3.1.3.1 4 OP-901-101, Reactor Power Cutback, Rev. 8 5 OP-902-000, Standard Post Trip Actions, Rev. 15 OP-901-103, Emergency boration, Rev. 2 6 OP-902-000, Standard Post Trip Actions, Rev. 15 7 OP-902-009, Standard Appendices, Rev. 309, Appendix 1, Diagnostic Flow Chart OP-902-006, Loss of Main Feedwater Recovery Procedure, Rev. 15 8 OP-902-006, Loss of Main Feedwater Recovery Procedure, Rev. 15 2014 NRC Exam Scenario 1 D-1 Rev 2

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 1 Page 1 of 30 Event

Description:

VCT level instrument CVC-ILT-0227 Fails high.

Time Position Applicants Actions or Behavior Examiner Note Cue the Simulator Operator when ready for Event 1 ATC Recognizes and reports indications of failed channel.

Alarms:

PMC PID D39302 NT VCT PMC PID D39303 FLASH TK Indications:

Valve CVC-169, VCT Inlet/Bypass To Holdup Tanks indicates BMS VCT level indication CVC-ILT-0226 slowly lowering VCT level indication PMC-IUR-0001 Green Pen (Flashing)

Note The SRO may direct the ATC to take manual control of CVC-169, VCT Inlet/Bypass To Holdup Tanks and direct valve to the VCT position prior to entering procedure.

SRO Enter and direct the implementation of OP-901-113, Volume Control Tank Makeup Control Malfunction OP-901-113, Volume Control Tank Makeup Control Malfunction NOTE Failure low of VCT level instrument CVC-ILT-0227(PID A39401) will cause RWSP TO CHARGING PUMPS (CVC 507) to open and VCT DISCH VALVE (CVC 183) to close. Failure of VCT level instrument CVC-ILT-0226 (PID A39400) affects CP-4 level indication and Auto makeup to the VCT.

SRO 1. IF a VCT level instrument fails, THEN perform the following:

N/A a. IF level instrument CVC-ILT-0227 fails low causing Charging Pump suction source to swap to RWSP, THEN perform the following:

2014 NRC Exam Scenario 1 D-2 Rev 2

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 1 Page 2 of 30 Event

Description:

VCT level instrument CVC-ILT-0227 Fails high.

Time Position Applicants Actions or Behavior ATC b. IF level instrument CVC-ILT-0227 fails high causing the VCT INLET/BYPASS VALVE (CVC 169) to divert to BMS, THEN perform the following:

1) Align VCT INLET/BYPASS VALVE (CVC 169) to VCT.

2) Makeup to VCT as required to restore level in accordance with OP-002-005, CHEMICAL AND VOLUME CONTROL.

3) Initiate corrective action to repair level instrument.

5) WHEN level instrument CVC-ILT-0227 is repaired, THEN restore VCT INLET/BYPASS VALVE (CVC 169) to AUTO.

N/A c. IF level instrument CVC-ILT-0226 fails, THEN secure auto makeup to the VCT in accordance with OP-002-005, CHEMICAL AND VOLUME CONTROL, and monitor VCT level using PMC PID A39401, CVCS VOL CONT TK LVL 1.

CAUTION DIRECT LOCAL DILUTION/BORATION OPERATIONS MUST BE DIRECTED FROM THE CONTROL ROOM. THIS REQUIRES THAT CONTINUOUS COMMUNICATIONS BE ESTABLISHED AND MAINTAINED BETWEEN THE CONTROL ROOM AND THE OPERATOR STATIONED IN BAMT ROOM A. IF COMMUNICATION IS LOST AT ANY TIME, THEN THE LOCAL OPERATOR SHALL IMMEDIATELY SECURE DILUTION/BORATION BY CLOSING MANUAL DIRECT BORATION ISOLATION(BAM 138) AND PMU TO CHG PMP SUCT HDR ISOL (PMU 140).

N/A 2. IF boric acid OR primary water flow can NOT be established to VCT, THEN makeup directly to Charging Pump suction as follows:

Examiner Note This event is complete after the ATC places CVC-169 to the VCT position or At Lead Examiners Discretion Examiner Note Cue the Simulator Operator when ready for Event 2 2014 NRC Exam Scenario 1 D-2 Rev 2

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 2 Page 3 of 30 Event

Description:

Atmospheric Dump Valve #1 spuriously opens Time Position Applicants Actions or Behavior BOP Recognize and report indications of ADV open.

Alarms:

SG 1 ATMOSPHERIC DUMP VLV OPEN (Cabinet M, G-1)

COLSS MASTER (Cabinet L, A-6)

LETDOWN FLOW HI/LO (Cabinet G, C-1)

Indications RCS temperature dropping ADV 1 setpoint indicates 0 ADV 1 output is 100%

Reactor Power Rising above 100%

Note The SRO may direct the BOP to take manual control and close ADV 1 upon the initial report, prior to entering the off normal.

SRO Enter and direct the implementation of OP-901-221, Secondary System Transient.

OP-901-221, Secondary System Transient, E0 - General NOTE (1) Some steps of this procedure may not be applicable due to plant conditions. In these cases SM/CRS may NA the step.

(2) Steps within this procedure may be performed concurrently or out of sequence with SM/CRS concurrence.

N/A 1. If Reactor trip occurs, then go to OP-902-000, Standard Post Trip Actions.

N/A 2. If Reactor Power Cutback occurs, then perform OP-901-101, Reactor Power Cutback, concurrently with this procedure.

BOP 3. If an Atmospheric Dump Valve fails or begins to fail Open, then place the respective controller to MANUAL with minimum output.

N/A 4. If a Steam Bypass Valve fails or begins to fail Open, then perform any of the following (in preferred order) to close the valve.

N/A 5. If an uncontrollable RCS cooldown exists, then perform the following:

2014 NRC Exam Scenario 1 D-2 Rev 2

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 2 Page 4 of 30 Event

Description:

Atmospheric Dump Valve #1 spuriously opens Time Position Applicants Actions or Behavior NOTE (1) The following are initial turbine load reductions to be considered depending on the current power level, time in core life, and equipment malfunction.

Transient Initial Load Reduction Rate Two or more Heater Drain Pumps Tripping FW Heater #1 or #2 Extraction Steam 100 MW 40 MW/min Valve Closure Atmospheric Dump Valve Fails Open Steam Bypass Valve Fails Open (2) With COLSS in service, utilize the following to observe instantaneous power changes for power levels 40%. Reference Attachment 3, COLSS Maneuvering Power Indications, for all other power levels.

Reactor Power UFM in service UFM not in service MSBSRAW 95% (PMC PID C24631)

USBSRAW FWBSRAW

< 95% and 40% (PMC PID C24629) (PMC PID C24630)

BOP 6. If Main Turbine is available, then adjust Turbine load as necessary to maintain the following:

Reactor Power 100%

Match Tavg with Tref FWPT Suction Pressure > 300 PSIG (monitored on CP-1 via CD IPI1280, IP Htrs Outlet Hdr)

RCS Tcold 536F - 549F 2014 NRC Exam Scenario 1 D-2 Rev 2

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 2 Page 5 of 30 Event

Description:

Atmospheric Dump Valve #1 spuriously opens Time Position Applicants Actions or Behavior OP-005-007, Main Turbine and Generator CAUTION THE FOLLOWING SECTION HAS THE POTENTIAL TO AFFECT CORE REACTIVITY. REACTOR POWER, RCS TEMPERATURE, AND MAIN GENERATOR MW LOAD SHOULD BE CLOSELY MONITORED DURING PERFORMANCE OF THIS SECTION.

BOP 6.2.1 To change Load/Rate perform the following:

6.2.1.1 Depress LOAD/RATE MW/MIN pushbutton.

6.2.1.2 Depress appropriate numerical pushbuttons for desired load rate.

6.2.1.3 Depress ENTER pushbutton.

NOTE Prior to changing Reference Demand, Main Turbine load must not be changing.

BOP 6.2.2 To change Main Turbine load, perform the following:

6.2.2.1 Depress REF pushbutton.

6.2.2.2 Depress appropriate numerical pushbuttons for desired MW load.

6.2.2.3 Depress ENTER pushbutton.

6.2.2.4 Depress GO pushbutton.

6.2.2.5 Verify Turbine load change stops at the desired MW load.

N/A 7. If needed, then concurrently perform OP-901-212, Rapid Plant Down Power, until a power level is reached in which the plant can be stabilized.

N/A 8. If a loss of Feedwater preheating occurs, then go to E1, Loss of Feedwater Preheating.

SRO 9. If a loss of secondary inventory occurs (Condensate, Feedwater or Steam leak), then go to E2, Loss of Secondary Inventory.

2014 NRC Exam Scenario 1 D-2 Rev 2

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 2 Page 6 of 30 Event

Description:

Atmospheric Dump Valve #1 spuriously opens Time Position Applicants Actions or Behavior OP-901-221, Secondary System Transient, E2 - Loss of Secondary Inventory ATC/BOP

1. Verify the following:

1.1 Pressurizer Pressure Control System maintaining or restoring Pressurizer pressure to 2250 PSIA.

1.2 Pressurizer Level Control System maintaining or restoring Pressurizer level to program level.

1.3 Steam Generator levels being maintained or restored to 50% to 70% Narrow Range level.

1.4 Steam Bypass Control System responding to maintain Steam Generator pressure.

N/A 2. Dispatch an operator and determine leak severity and location.

SRO 3. Attempt to safely isolate the leak.

3.1 If a Atmospheric Dump Valve is isolated or associated controller placed in manual, then refer to the Technical Specification 3.7.1.7, Atmospheric Dump Valves.

SRO Reviews the following Technical Specifications and determines applicable actions:

3.7.1.7 action a Examiner Note This event is complete after the BOP places controller MS-IPIC-0303-A1 in manual and closes ADV #1 and the SRO has evaluated Technical Specifications or At Lead Examiners Discretion Examiner Note Cue the Simulator Operator when ready for Event 3 2014 NRC Exam Scenario 1 D-2 Rev 2

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 3 Page 7 of 30 Event

Description:

Control Element Assembly #9 drops into the core Time Position Applicants Actions or Behavior ATC / BOP Recognize and report indications of dropped CEA Alarms RPS CHANNEL TRIP LOCAL PWR DENSITY HI (Cabinet K, A-11)

RPS CHANNEL TRIP DNBR LO (Cabinet K, A-12)

LOCAL PWR DENSITY HI PRETRIP B/D (Cabinet K, C-11)

DNBR LO PRETRIP B/D (Cabinet K, C-12)

CEA CHANNEL B DEVIATION (Cabinet K, H-12)

CEA CHANNEL C DEVIATION (Cabinet K, K-13)

CEA CALCULATOR CHNL B TROUBLE (Cabinet K, K-15)

CEA CALCULATOR CHNL C TROUBLE (Cabinet K, K-16)

RPS CHANNEL D TROUBLE (Cabinet K, H-18)

Indications Rod bottom light for CEA 9 TCOLD dropping LPD and DNBR trips on Channel D (targeted channel)

Examiner Note The CRS may direct a Main Turbine load reduction before entering the off normal procedure to raise T COLD. It is not required to do this before entering OP-901-102. This is not a deficiency if the CRS does not perform this step at this time. If the CRS performs this step, the guidance is located on page 8.

CRS Enter and direct the implementation of OP-901-102, CEA or CEDMCS Malfunction.

OP-901-102, CEA or CEDMCS Malfunction, Immediate Operator Actions Examiner Note This is the immediate action for this procedure. This is not applicable to this scenario.

N/A 1. If in Mode 1 and two or more Control Element Assemblies drop or are misaligned by >19 inches, then manually trip the Reactor and go to OP-902-000, Standard Post Trip Actions.

OP-901-102, CEA or CEDMS Malfunction, E0, General N/A 2. If any of the following occur, then manually trip the Reactor and go to OP-902-000, Standard Post Trip Actions:

SRO 3. If Control Element Assembly is misaligned >7 inches, then go to section E1, CEA Misalignment Greater Than 7 Inches.

2014 NRC Exam Scenario 1 D-2 Rev 2

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 3 Page 8 of 30 Event

Description:

Control Element Assembly #9 drops into the core Time Position Applicants Actions or Behavior OP-901-102, CEA or CEDMS Malfunction, E1, CEA Misalignment Greater than 7 inches SRO 1. Match Tavg and Tref by performing the following:

Adjust Turbine load in accordance with OP-010-004, Power Operations.

Adjust RCS boron concentration in accordance with OP-002-005, Chemical and Volume Control.

OP-005-007, Main Turbine and Generator CAUTION THE FOLLOWING SECTION HAS THE POTENTIAL TO AFFECT CORE REACTIVITY. REACTOR POWER, RCS TEMPERATURE, AND MAIN GENERATOR MW LOAD SHOULD BE CLOSELY MONITORED DURING PERFORMANCE OF THIS SECTION.

BOP 6.2.1 To change Load/Rate perform the following:

6.2.1.1 Depress LOAD/RATE MW/MIN pushbutton.

6.2.1.2 Depress appropriate numerical pushbuttons for desired load rate.

6.2.1.3 Depress ENTER pushbutton.

NOTE Prior to changing Reference Demand, Main Turbine load must not be changing.

BOP 6.2.2 To change Main Turbine load, perform the following:

6.2.2.1 Depress REF pushbutton.

6.2.2.2 Depress appropriate numerical pushbuttons for desired MW load.

6.2.2.3 Depress ENTER pushbutton.

6.2.2.4 Depress GO pushbutton.

6.2.2.5 Verify Turbine load change stops at the desired MW load.

OP-901-102, CEA or CEDMS Malfunction, E1, CEA Misalignment Greater than 7 inches SRO 2. Notify Duty Plant Manager and Duty Engineering.

SRO 3. Record time of CEA misalignment >7 inches in Station Log.

SRO 4. If CEA misalignment >19 inches, then go to step 8.

2014 NRC Exam Scenario 1 D-2 Rev 2

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 3 Page 9 of 30 Event

Description:

Control Element Assembly #9 drops into the core Time Position Applicants Actions or Behavior CAUTION A POWER REDUCTION MUST BE STARTED WITHIN 15 MINUTES OF CEA MISALIGNMENT

>7 INCHES TO COMPLY WITH TECH SPEC 3.1.3.1.

Examiner Note The SRO should determine that a power reduction is required within 60 minutes.

NOTE (1) Complete the required down-power prior to withdrawal of the affected CEA.

(2) If a Shutdown Bank CEA has dropped or is misaligned and is <145 inches withdrawn, then CEA Group Out of Sequence annunciator (A-7 on Cabinet L) is an expected annunciator when performing ASI Control using Regulating Group CEAs.

SRO 8. If misalignment >19 inches or affected CEA is not aligned to within 7 inches of all other CEAs in the same group within 15 minutes, then perform the following:

Reduce power in accordance with OP-901-212, Rapid Plant Power Reduction to comply with Technical Specification 3.1.3.1.

Maintain Tavg at Tref by adjusting turbine load If PMC is Operable, then verify CEA Pulse Counter indication is correct or enter the correct CEA position in the PMC database.

Declare COLSS Inoperable and enter OP-901-501, PMC or COLSS Inoperable and perform concurrently with this procedure due to COLSS being Inoperable.

Use SEC CAL PWR (C24230), CBTFSP (C24102), BDELT (C24104), CBDELT (C24103), or TURB PWR (C24101) for indication during power reduction.

Examiner Note When a full crew complement is present, OP-901-501, PMC or COLSS inoperable would be performed by the STA.

2014 NRC Exam Scenario 1 D-2 Rev 2

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 3 Page 10 of 30 Event

Description:

Control Element Assembly #9 drops into the core Time Position Applicants Actions or Behavior OP-901-212, Rapid Plant Power Reduction, E0, General Actions Examiner Note A Rapid downpower does not have to be started at 30MW/min, but should attempt to eventually reach that value. The crew will likely not start the load reduction at that high of a rate.

NOTE (1) A rapid power reduction is defined as approximately 30 MW/minute load reduction on the main turbine.

(2) Power Reduction may be stopped at any point.

(3) Some Steps of this procedure may not be applicable due to plant conditions. In these cases SM/CRS may NA the step.

(4) Steps within this procedure may be performed concurrently or out of sequence with SM/CRS concurrence.

(5) During power reduction PMC PID C24650, COLSS DESCENDING PWR TRACK (DUMOUT19),

will automatically select and display the correct power indication.

OP-010-003, Plant Startup, provides greater detail on which power indications are displayed by PID C24650 based on power level and whether or not the UFM is in service.

(6) Volume Control Tank (VCT) level may lower during the down power. Charging pump suction swaps to the RWSP at 8% VCT level. Makeup to the VCT in accordance with OP-002-005, Chemical and Volume Control, may be necessary if boration from the RWSP is not desired.

ATC 1. Begin RCS Boration by one of the following methods:

1.1 Direct Boration or 1.2 Borate from the RWSP using one or two Charging Pump as follows:

1.2.1 Open RWSP to Charging Pumps Suction Isolation, CVC-507.

1.2.2 Close Volume Control Tank Outlet Isolation, CVC-183.

1.2.3 If necessary, then start another Charging pump 2014 NRC Exam Scenario 1 D-2 Rev 2

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 3 Page 11 of 30 Event

Description:

Control Element Assembly #9 drops into the core Time Position Applicants Actions or Behavior OP-005-005, Chemical and Volume Control CAUTION (1) THIS SECTION AFFECTS REACTIVITY. THIS EVOLUTION SHOULD BE CROSS-CHECKED AND COMPLETED PRIOR TO LEAVING CP-4.

(2) AT LEAST ONE REACTOR COOLANT PUMP IN EACH LOOP SHOULD BE OPERATING PRIOR TO PERFORMING DIRECT BORATION OPERATIONS TO ENSURE PROPER CHEMICAL MIXING.

ATC 6.7.1 Inform SM/CRS that this Section is being performed.

NOTE When performing a Plant down power where final RCS Boron Concentration needs to be determined, the following Plant Data Book figure(s) will assist the Operator in determining the required RCS Boron PPM change.

1.2.1.1 Power Defect Vs Power Level 1.4.3.1 Inverse Boron Worth Vs. Tmod at BOC (<30 EFPD) 1.4.4.1 Inverse Boron Worth Vs. Tmod at Peak Boron (30 EFPD up to 170 EFPD) 1.4.5.1 Inverse Boron Worth Vs. Tmod at MOC (170 EFPD up to 340 EFPD) 1.4.6.1 Inverse Boron Worth Vs. Tmod at EOC ( 340 EFPD)

ATC 6.7.2 At SM/CRS discretion, calculate volume of Boric Acid to be added on Attachment 11.6, Calculation of Boric Acid Volume for Direct Boration or VCT Borate Makeup Mode.

ATC 6.7.3 Set Boric Acid Makeup Batch Counter to volume of Boric Acid desired.

ATC 6.7.4 Verify Boric Acid Makeup Pumps selector switch aligned to desired Boric Acid Makeup Pump A(B).

ATC 6.7.5 Place Direct Boration Valve, BAM-143, control switch to AUTO.

ATC 6.7.6 Place Makeup Mode selector switch to BORATE.

ATC 6.7.7 Verify selected Boric Acid Makeup Pump A(B) Starts.

ATC 6.7.8 Verify Direct Boration Valve, BAM-143, Opens.

2014 NRC Exam Scenario 1 D-2 Rev 2

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 3 Page 12 of 30 Event

Description:

Control Element Assembly #9 drops into the core Time Position Applicants Actions or Behavior NOTE The Boric Acid Flow Totalizer will not register below 3 GPM. The Boric Acid Flow Totalizer is most accurate in the range of 10 - 25 GPM.

ATC 6.7.9 If manual control of Boric Acid flow is desired, then perform the following:

6.7.9.1 Verify Boric Acid Flow controller, BAM-IFIC-0210Y, in Manual.

6.7.9.2 Adjust Boric Acid Flow controller, BAM-IFIC-0210Y, output to >3 GPM flow rate.

N/A 6.7.10 If automatic control of Boric Acid flow is desired, then perform the following:

6.7.10.1 Place Boric Acid Flow controller, BAM-IFIC-0210Y, in Auto.

6.7.10.2 Adjust Boric Acid Flow controller, BAM-IFIC-0210Y, setpoint potentiometer to >3 GPM flow rate.

ATC 6.7.11 Verify Boric Acid Makeup Control Valve, BAM-141, Intermediate or Open.

ATC 6.7.12 Observe Boric Acid flow rate for proper indication.

ATC 6.7.13 When Boric Acid Makeup Batch Counter has counted down to desired value, then verify Boric Acid Makeup Control Valve, BAM-141, Closed.

2014 NRC Exam Scenario 1 D-2 Rev 2

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 3 Page 13 of 30 Event

Description:

Control Element Assembly #9 drops into the core Time Position Applicants Actions or Behavior Examiner Note The step below is only applicable if the ATC adds acid in small batches.

NOTE Step 6.7.14 may be repeated as necessary to achieve desired total boron addition for plant conditions.

ATC 6.7.14 If additional boric acid addition is required and with SM/CRS permission, then perform the following:

6.7.14.1 Reset Boric Acid Makeup Batch Counter.

6.7.14.2 Verify Boric Acid Makeup Control Valve, BAM-141, Intermediate or Open.

6.7.14.3 Observe Boric Acid flow rate for proper indication.

6.7.14.4 When Boric Acid Makeup Batch Counter has counted down to desired value, then verify Boric Acid Makeup Control Valve, BAM-141, Closed.

ATC 6.7.15 Verify Boric Acid Flow controller, BAM-IFIC-0210Y, in Manual.

ATC 6.7.16 Verify both Boric Acid Flow controller, BAM-IFIC-0210Y, output and setpoint potentiometer set to zero.

ATC 6.7.17 Place Makeup Mode selector switch to MANUAL.

ATC 6.7.18 Verify Selected Boric Acid Makeup Pump A (B) Stops.

ATC 6.7.19 Verify Direct Boration Valve, BAM-143, Closed.

ATC 6.7.20 Place Direct Boration Valve, BAM-143, control switch to CLOSE.

2014 NRC Exam Scenario 1 D-2 Rev 2

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 3 Page 14 of 30 Event

Description:

Control Element Assembly #9 drops into the core Time Position Applicants Actions or Behavior OP-901-212, Rapid Plant Power Reduction, E0, General Actions NOTE To prevent Pressurizer heater cutout, avoid operating with Pressurizer pressure near the heater cutout pressure of 2270 PSIA while on Boron Equalization.

ATC 2. Perform Boron Equalization as follows:

2.1 Place available Pressurizer Pressure Backup Heater Control Switches to ON.

2.2 Reduce Pressurizer Spray Valve Controller (RC-IHIC-0100) setpoint potentiometer to establish spray flow and maintain RCS pressure 2250 PSIA (2175 - 2265).

CAUTION REFER TO TECHNICAL SPECIFICATION 3.1.3.6 FOR TRANSIENT INSERTION LIMITS.

ATC 3. Operate CEAs in accordance with OP-004-004, Control Element Drive, to maintain ASI using CEA Reg. Group 5, 6 or Group P Control Element Assemblies in accordance with OP-010-005, Plant Shutdown, Attachment 9.10, Axial Shape Control Guidelines.

SRO 4. Notify the Woodlands System Load Dispatcher that a rapid power reduction is in progress.

BOP 5. Announce to Station Personnel over the Plant Paging System that a rapid plant power reduction is in progress.

ATC 6. Maintain RCS Cold Leg Temperature 536 F to 549 F.

BOP 7. Commence Turbine load reduction by performing the following:

7.1 Depress LOAD RATE MW/MIN pushbutton.

7.2 Set selected rate in Display Demand Window.

7.3 Depress ENTER pushbutton.

7.4 Depress REFERENCE pushbutton.

7.5 Set desired load in Reference Demand Window.

7.6 Depress ENTER pushbutton.

7.7 Depress GO pushbutton.

2014 NRC Exam Scenario 1 D-2 Rev 2

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 3 Page 15 of 30 Event

Description:

Control Element Assembly #9 drops into the core Time Position Applicants Actions or Behavior NOTE If USBSCAL is not in service, the COLSS Steam Calorimetric will be automatically disabled when MSBSCAL, PMC PID C24246, drops below 95% Power, and will revert back to FWBSCAL, PMC PID C24235. This may result in a step change in COLSS indicated Plant Power (BSCAL) of up to 1.0% when this occurs.

ATC 8. When Reactor Power consistently indicates less than 98% power, as indicated on PMC PID C24631 [MAIN STEAM RAW POWER (MSBSRAW)], or an alternate point provided by Reactor Engineering, then verify the value of C24648 [BSCAL SMOOTHING VAL. APPLD (DUMOUT17)] automatically changes to 1.

N/A 9. If C24648 does not automatically change to 1, then inform Reactor Engineering and set the value of 1 for COLSS power smoothing constant K24250, [ADDRSSBL SMOOTHING FOR BSCAL (ALPHA)] in accordance with OP-004-005, Core Operating Limits Supervisory System.

BOP 10. Following a Reactor Power change of >15% within a one hour period, direct Chemistry Department to sample Reactor Coolant System (RCS) for an isotopic iodine analysis two to six hours later.

BOP 11. When Condensate flow is <18,000 gpm, verify Gland Steam Condenser Bypass, CD-154, Closed (PMC PID D02404).

BOP 12. Monitor Condensate Polisher differential pressure and remove Polishers from service to maintain system pressure in accordance with OP-003-031, Condensate Polisher/Backwash Treatment.

N/A 13. When Reactor Power is approximately 70% or Heater Drain Pump flow is unstable, then remove Heater Drain Pumps from service by taking pump control switches to Stop.

OP-901-102, CEA or CEDMS Malfunction, E1, CEA Misalignment Greater than 7 inches SRO 9. If either of the following occur, then within one hour declare CEA Inoperable and verify acceptable Shutdown Margin in accordance with OP-903-090, Shutdown Margin:

Misaligned CEA is in Shutdown Bank and cannot be withdrawn to 145 inches [T.S. 3.1.3.5]

or Any CEA is misaligned from its group by >7 inches and cannot be aligned [T.S. 3.1.3.1]

2014 NRC Exam Scenario 1 D-2 Rev 2

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 3 Page 16 of 30 Event

Description:

Control Element Assembly #9 drops into the core Time Position Applicants Actions or Behavior SRO Reviews the following Technical Specifications and determines applicable actions:

3.1.3.1 action c ATC 10. Monitor the following for compliance with Technical Specifications:

Linear Heat Rate (LPD) [T.S. 3.2.1]

Departure from Nucleate Boiling Ratio [T.S. 3.2.4]

Azimuthal Power Tilt [T.S. 3.2.3]

ASI [T.S. 3.2.7]

ATC 11. Perform the following to verify compliance with Technical Specification 3.2.3:

Verify COLSS is detecting Azimuthal Power Tilt as influenced by the misaligned CEA.

If measured Azimuthal Power Tilt exceeds 0.03, then verify Azimuthal Power Tilt within limits of Technical Specification 3.2.3 If measured Azimuthal Power Tilt exceeds CPC Power Tilt Allowance, then adjust CPC Power Tilt allowance to the measured value in accordance with OP-004-006, Core Protection Calculator System.

NOTE If the CEA misalignment is due to a dropped rod then the ACTM card for the dropped rod may need to be reset if the CEA is not responding to a withdrawal demand.

ATC 12. Maintain ASI within 0.05 of target ESI to limit potential impact of transient Xenon on core peaking using Manual Group or Manual Sequential.

N/A 13. Correct cause of CEA misalignment.

BOP 14. If initial Reactor power is 75 %, then notify Chemistry Department to sample Reactor Coolant System for an isotopic iodine analysis within two to six hours due to a power reduction of 15 % in one hour.

Examiner Note This event is complete after the Reactivity Manipulation is satisfied and the SRO has evaluated Technical Specifications OR At Lead Examiners Discretion 2014 NRC Exam Scenario 1 D-2 Rev 2

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 3 Page 17 of 30 Event

Description:

Control Element Assembly #9 drops into the core Time Position Applicants Actions or Behavior Examiner Note Cue the Simulator Operator when ready for Event 4 Examiner Note Event 5 and 6 will occur automatically after the crew takes action responding to Event 4.

2014 NRC Exam Scenario 1 D-2 Rev 2

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 4 Page 18 of 30 Event

Description:

Main Feedwater Pump Trip / Reactor Cutback leads to Reactor Trip Time Position Applicants Actions or Behavior ATC / BOP Recognize and report indications of MFP Trip and Reactor Cutback Alarms FWPT B OIL PUMP TROUBLE (Cabinet F, R-18)

REACTOR PWR CUTBACK ACTUATION (Cabinet H, K-5)

FWPT B FLOW LO (Cabinet F, M-20)

FWPT B FLOW LO-LO (Cabinet F, N-20)

FWPT B DISCH PRESS/FLOW MONITOR FAIL (Cabinet F, P-20)

SG 2 LEVEL HI/LO (Cabinet F, U-18)

SG1 LEVEL HI/LO (Cabinet F, U-14)

HTR DRAIN PUMP A(B)(C) TRIP/TROUBLE [Cabinet F, P-11(12)(13)]

HTR DRAIN PUMP A(B)(C) SUCTION PRESS LO [Cabinet F, Q-11(12)(13)]

HTR DRAIN PUMP A FLOW LO (Cabinet F, R-11(12)(13)

Indications Rod bottom lights for CEAs 44, 21, 45, 22, 46, 23, 47, 20 TCOLD dropping Reactor Power Dropping CRS Enter and direct the implementation of OP-901-101, Reactor Power Cutback.

Examiner Note The SRO should direct a manual Reactor Trip due to incorrect rod configuration following the Reactor Power Cutback ATC Trip the Reactor and enter OP-902-000, Standard Post Trip Actions Examiner Note The subsequent actions contained in Event 4 will be contained after events 5 and 6 which occur in order of how they will be performed during the scenario.

2014 NRC Exam Scenario 1 D-2 Rev 2

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 5 Page 19 of 30 Event

Description:

3 CEAs fail to insert on the Reactor Trip Time Position Applicants Actions or Behavior ATC Recognize and report indications of 3CEAs fail to insert Alarms N/A Indications Rod bottom lights for CEAs 7, 37, 39 extinguished CEA position for CEA 7, 37, 39 showing withdrawn OP-902-000, Standard Post Trip Actions ATC 1. Determine Reactivity Control acceptance criteria are met:

a. Check reactor power is dropping.

b. Check startup rate is negative.

c. Check less than TWO CEAs are NOT fully inserted.

ATC c.1 Commence emergency boration.

CRITICAL TASK ESTABLISH REACTIVITY CONTROL This task is satisfied by commencing Emergency Boration flow by either Boric Acid makeup pumps or Gravity Feed valves in accordance with OP-902-000, Standard Post Trip Actions step 1 prior to exiting the step to verify Reactivity Control.

This task becomes applicable following the initiation of a Reactor Trip.

Examiner Note The steps below are contained on an Operator Aid on the RTGB ATC 1. Place Makeup Mode selector switch to MANUAL. (CRITICAL)

ATC 2. Align borated water source by performing one of the following (a. or b.):

(CRITICAL)

a. Initiate Emergency Boration using Boric Acid Pump as follows:

Open Emergency Boration Valve, BAM-133.

Start one Boric Acid Pump.

Close recirc valve for Boric Acid Pump started:

BAM-126A Boric Acid Makeup Pump Recirc Valve A or BAM-126B Boric Acid Makeup Pump Recirc Valve B 2014 NRC Exam Scenario 1 D-2 Rev 2

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 5 Page 20 of 30 Event

Description:

3 CEAs fail to insert on the Reactor Trip Time Position Applicants Actions or Behavior ATC b. Initiate Emergency Boration using Gravity Feed as follows:

Open the following Boric Acid Makeup Gravity Feed valves:

BAM-113A Boric Acid Makeup Gravity Feed Valve A BAM-113B Boric Acid Makeup Gravity Feed Valve B ATC 3. Close VCT Disch Valve, CVC-183. (CRITICAL)

ATC 4. Verify at least one Charging Pump operating and Charging Header flow

>40 GPM.

Examiner Note This event is complete after the ATC has established emergency boration OR At Lead Examiners Discretion 2014 NRC Exam Scenario 1 D-2 Rev 2

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 6 Page 21 of 30 Event

Description:

Turbine Fails to Automatically Trip Time Position Applicants Actions or Behavior BOP Recognize indications of Main Turbine failing to trip Alarms N/A Indications Main Turbine Governor and Throttle valves indicate open TCOLD lowering RCS pressure lowering OP-902-000, Standard Post Trip Actions BOP 2. Determine Maintenance of Vital Auxiliaries acceptance criteria are met:

a. Check the Main Turbine is tripped:

Governor valves closed Throttle valves closed CRITICAL TASK ESTABLISH REACTIVITY CONTROL This task is satisfied by stopping the steam flow to the Main Turbine by either tripping the Main Turbine manually or by closing the Main Steam Isolation valves before TCOLD lowers to below 443 F.

This task becomes applicable following the initiation of the Reactor Trip signal.

BOP a.1 Perform ANY of the following: (CRITICAL)

1) Manually trip the Main Turbine using TURBINE TRIP and THINK pushbuttons.

2) Close BOTH MSIVs.

Examiner Note This event is complete after the BOP has stopped steam flow to the Main Turbine OR At Lead Examiners Discretion 2014 NRC Exam Scenario 1 D-2 Rev 2

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 4 Page 22 of 30 Event

Description:

Main Feedwater Pump Trip / Reactor Cutback leads to Reactor Trip Time Position Applicants Actions or Behavior BOP b. Check the Main Generator is tripped:

GENERATOR BREAKER A tripped GENERATOR BREAKER B tripped EXCITER FIELD BREAKER tripped BOP c. Check station loads are energized from offsite electrical power as follows:

Train A A1, 6.9 KV non safety bus A2, 4.16 KV non safety bus A3, 4.16 KV safety bus A-DC electrical bus A or C vital AC Instrument Channel Train B B1, 6.9 KV non safety bus B2, 4.16 KV non safety bus B3, 4.16 KV safety bus B-DC electrical bus B or D vital AC Instrument Channel ATC 3. Determine RCS Inventory Control acceptance criteria are met:

a. Check that BOTH the following conditions exist:

Pressurizer level is 7% to 60%

Pressurizer level is trending to 33% to 60%

b. Check RCS subcooling is greater than or equal to 28ºF.

Examiner Note If the Main Turbine manual trip is delayed in Event 6, this may have an effect on RCS Pressure and Temperature and PZR level which will make some of the following steps applicable. It is possible that a Safety Injection and Containment isolation could occur, but this will not impact the flow of the scenario unless a subsequent misdiagnosis is made by the crew.

ATC 4. Determine RCS Pressure Control acceptance criteria are met by checking that BOTH of the following conditions exist:

Pressurizer pressure is 1750 psia to 2300 psia Pressurizer pressure is trending to 2125 psia to 2275 psia 2014 NRC Exam Scenario 1 D-2 Rev 2

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 4 Page 23 of 30 Event

Description:

Main Feedwater Pump Trip / Reactor Cutback leads to Reactor Trip Time Position Applicants Actions or Behavior ATC 5. Determine Core Heat Removal acceptance criteria are met:

a. Check at least one RCP is operating.

b. Check operating loop T is less than 13ºF.

c. Check RCS subcooling is greater than or equal to 28ºF.

Examiner Note At any point prior to event 8, the crew may notice that Steam Generator levels have reduced below 27% NR and an Emergency Feedwater Actuation Signal failed to occur. If the operator manually initiates EFAS at this time, it will satisfy the critical task in Event 8. This is not required to be performed at this time but only prior to lowering level to below 20% WR.

BOP 6. Determine RCS Heat Removal acceptance criteria are met:

a. Check that at least one steam generator has BOTH of the following:

Steam generator level is 10% to 76% NR Main Feedwater is available to restore level within 55%-70%

NR.[60% to 80% NR]

ATC b. Check RCS TC is 530 ºF to 550 ºF BOP c. Check steam generator pressure is 885 psia to 1040 psia.

BOP d. Check Feedwater Control in Reactor Trip Override:

MAIN FW REG valves are closed STARTUP FW REG valves are 13% to 21% open Operating main Feedwater pumps are 3800 rpm to 4000 rpm BOP e. Reset moisture separator reheaters, and check the temperature control valves closed.

ATC 7. Determine Containment Isolation acceptance criteria are met:

a. Check containment pressure is less than 16.4 psia.

b. Check NO containment area radiation monitor alarms OR unexplained rise in activity.

c. Check NO steam plant activity monitor alarms OR unexplained rise in activity.

BOP 8 Determine Containment Temperature and Pressure Control acceptance criteria are met:

a. Check containment temperature is less than or equal to 120ºF.

b. Check containment pressure is less than 16.4 psia.

2014 NRC Exam Scenario 1 D-2 Rev 2

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 4 Page 24 of 30 Event

Description:

Main Feedwater Pump Trip / Reactor Cutback leads to Reactor Trip Time Position Applicants Actions or Behavior N/A 9. IF ALL safety function acceptance criteria are met, AND NO contingency actions were performed, THEN GO TO OP-902-001, "Reactor Trip Recovery" procedure.

SRO 10. IF ANY safety function acceptance criteria are NOT met, OR ANY contingency action was taken, THEN GO TO Appendix 1, "Diagnostic Flowchart.

Examiner Note Cue the Simulator Operator when ready for Event 7 Examiner Note This event is complete after the SRO has commenced diagnosis in OP-902-009, Standard Appendices OR At Lead Examiners Discretion 2014 NRC Exam Scenario 1 D-2 Rev 2

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 7 Page 25 of 30 Event

Description:

Feedwater Pump A overspeed trip / Loss of Main Feedwater Time Position Applicants Actions or Behavior BOP Recognize and report indications of Feedwater Pump A trip Alarms FWPT A TRIP OVERSPEED (Cabinet F, K-15)

FWPT A FLOW LO (Cabinet F, M-16)

FWPT A FLOW LO-LO (Cabinet F, N-16)

Indications Steam Generator levels lowering Feedwater flow lowering Feedwater Pump speed lowering OP-902-009, Standard Appendices, Appendix 1 Examiner Note Appendix 1 is a flow chart used to diagnose to the correct recovery procedure for the event in progress. The steps below will be followed by a YES or NO to indicate proper flow path.

ATC Rx Pwr dropping, SUR negative, and < two CEAs NOT fully inserted or Emergency Boration in progress (YES)

ATC Pressurizer pressure dropping rapidly and Pressurizer level changing (NO)

SRO Page 2 BOP At least one 7 KV non safety bus and one 4 KV safety bus powered from offsite (same train) (YES)

BOP MFW restoring or maintaining at least one SG level 55% to 70% NR (NO)

SRO GO TO OP-902-006 Loss of Main Feedwater Recovery OP-902-006, Loss of Main Feedwater Recovery SRO Confirm Diagnosis

1. Confirm diagnosis of a Loss of Main Feedwater by checking Safety Function Status Check Acceptance Criteria are satisfied.

BOP Announce the Event

2. Announce the Loss of Main Feedwater in progress using the plant page.

2014 NRC Exam Scenario 1 D-2 Rev 2

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 7 Page 26 of 30 Event

Description:

Feedwater Pump A overspeed trip / Loss of Main Feedwater Time Position Applicants Actions or Behavior N/A Classify the Event

3. Advise the Shift Manager to REFER TO EP-001-001, "Recognition &

Classification of Emergency Condition", and implement the Emergency Plan.

N/A Restore Operation of DCT Sump Pumps

4. IF power has been interrupted to either 3A or 3B safety buses, THEN perform Appendix 20, "Operation of DCT Sump Pumps".

SRO Implement Placekeeping

5. REFER TO Section 6.0, "Placekeeper", and record the time of the reactor trip.

ATC Verify ONE RCP In Each Loop Secured

6. Verify no more than two RCPs are operating.

N/A Stop ALL RCPs

7. IF ANY of the following conditions exist, THEN perform the following:

a. IF ALL feedwater is lost, THEN stop ALL RCPs.

b. IF MFW is lost AND the only feedwater available is ONE motor driven EFW Pump, THEN within the following 30 minutes stop ALL RCPs.

BOP Verify Proper CCW Operation

8. Check a CCW pump is operating for each energized 4.16 KV safety bus.

BOP Conserve Steam Generator Inventory

9. Conserve steam generator inventory:

a. Verify the following steam generator blowdown isolation valves are closed:

BD 102A, SG BLOWDOWN ISOL STM GEN 1 (IN)

BD 102B, SG BLOWDOWN ISOL STM GEN 2 (IN)

BD 103A, SG BLOWDOWN ISOL STM GEN 1 (OUT)

BD 103B, SG BLOWDOWN ISOL STM GEN 2 (OUT) 2014 NRC Exam Scenario 1 D-2 Rev 2

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 7 Page 27 of 30 Event

Description:

Feedwater Pump A overspeed trip / Loss of Main Feedwater Time Position Applicants Actions or Behavior BOP b. Verify the following steam generator sampling valves are closed:

SSL 8006A, SAMPLING ISOLATION SG 1

SSL 8006B, SAMPLING ISOLATION SG 2

SSL 301A, SAMPLING ISOLATION MAIN STM LINE 1

SSL 8004A, SAMPLING ISOLATION SG 1

SSL 8004B, SAMPLING ISOLATION SG 2

SSL 301B, SAMPLING ISOLATION MAIN STM LINE 2 N/A Reset MSIS

10. IF MSIS has actuated AND opening the MSIVs or MFIVs will aid in the restoration of feedwater, THEN REFER TO Appendix 5-B, "MSIS Main Steam Pressure Reset Procedure", and reset the MSIS.

Examiner Note The Loss of Feedwater event is complete after the crew has stopped 2 Reactor Coolant Pumps and has completed Event 8 OR At Lead Examiners Discretion 2014 NRC Exam Scenario 1 D-2 Rev 2

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 8 Page 28 of 30 Event

Description:

Emergency Feedwater Fails to Actuate Time Position Applicants Actions or Behavior BOP Recognize and report indications of EFAS fail to actuate Alarms Absence of Alarms:

EFAS-1 TRAIN A LOGIC INITIATED (Cabinet K, M-19)

EFAS-2 TRAIN A LOGIC INITIATED (Cabinet K, N-19)

EFAS-1 TRAIN B LOGIC INITIATED (Cabinet K, M-20)

EFAS-2 TRAIN B LOGIC INITIATED (Cabinet K, N-20)

Indications Steam Generator levels <27.4% NR EFW Pump A, B, AB not operating CRITICAL TASK ESTABLISH RCS HEAT REMOVAL This task is satisfied by manually actuating Emergency Feedwater Actuation System, manually starting and aligning at least 1 Emergency Feedwater pump, aligning and starting the Auxiliary Feedwater pump, or depressurizing at least 1 Steam Generator and injecting the Steam Generator with Condensate flow prior to Steam Generator levels reducing below 20% Wide Range in both Steam Generators.

This task becomes applicable once Steam Generator water level reduces below 27.4% Narrow Range in one or both Steam Generators.

BOP Restore Steam Generator Inventory

11. Replenish inventory in at least one steam generator by performing ANY of the following:

a. Check emergency Feedwater available to at least one steam generator.

b. REFER TO Appendix 32, "Establishing Main Feedwater" and restore main feedwater flow to at least one steam generator.

BOP Actuate EFAS - 1 and EFAS - 2. (CRITICAL)

Examiner Note The following steps are added as a reference if the crew continues on in OP-902-006 and has not yet actuated Emergency Feedwater. These steps describe alternative methods to establishing RCS heat removal. (Appendix 32 A & B) 2014 NRC Exam Scenario 1 D-2 Rev 2

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 8 Page 29 of 30 Event

Description:

Emergency Feedwater Fails to Actuate Time Position Applicants Actions or Behavior OP-902-009, Standard Appendices, Appendix 32A Starting Auxiliary Feedwater Pump NOTE When AFW is being used to feed the steam generators, consideration should be given to aligning the condenser to the CST.

BOP 1. Verify MAIN FW ISOL VALVES open:

FW-184A FW-184B BOP 2. Place the following controllers to "MAN" and set to minimum:

FW-IFIC-8202, AUX FEEDWATER FLOW FW-IHIC-1105, SG 1 STARTUP FW REG FW-IHIC-1106, SG 2 STARTUP FW REG BOP 3. Verify the following valves closed:

FW-170A, SG 1 MAIN FW REG ISOLATION FW-170B, SG 2 MAIN FW REG ISOLATION BOP 4. Verify the following valves open:

FW-163A, SG 1 STARTUP FW REG ISOLATION FW-163B, SG 2 STARTUP FW REG ISOLATION BOP 5. Start Auxiliary Feedwater Pump.

BOP 6. Adjust the following controllers to 5% output:

FW-IHIC-1105, SG 1 STARTUP FW REG FW-IHIC-1106, SG 2 STARTUP FW REG NOTE AFW pump discharge pressure should be monitored closely while adjusting flow.

BOP 7. Adjust the following controllers and valve to achieve desired flow rates:

FW-IHIC-1105, SG 1 STARTUP FW REG

FW-IHIC-1106, SG 2 STARTUP FW REG

FW-IFIC-8202, AUX FEEDWATER FLOW AFW-125, AUXILIARY FEEDWATER PRESSURE RELIEF OP-902-009, Standard Appendices, Appendix 32B Aligning Condensate to Feed the Steam Generators BOP 1. Verify MFW pumps are tripped.

BOP 2. Verify AFW pump secured.

2014 NRC Exam Scenario 1 D-2 Rev 2

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 8 Page 30 of 30 Event

Description:

Emergency Feedwater Fails to Actuate Time Position Applicants Actions or Behavior BOP 3. Verify at least one Condensate Pump operating.

BOP 4. Open FW 125, FW PUMPS BYPASS valve.

N/A 5. IF MSIS has initiated, THEN REFER TO Appendix 5-B, "MSIS Main Steam Pressure Reset Procedure" and reset MSIS.

BOP 6. Verify MFIV open for selected steam generator.

BOP 7. Maintain SG level 55%-70% NR [60-80% NR] by adjusting the following controllers:

FW-IHIC-1105, SG 1 STARTUP FW REG FW-IHIC-1106, SG 2 STARTUP FW REG Examiner Note This event is complete after the crew has actuated EFAS OR At Lead Examiners Discretion 2014 NRC Exam Scenario 1 D-2 Rev 2

Appendix D Scenario Outline Form ES-D-1 Facility: Waterford 3 Scenario No.: 3 Op Test No.:

Examiners: Operators:

Initial Conditions: Reactor power is ~1%, MOC Turnover:

Protected Train is B, AB Bus is aligned to Train B, Raise power to 5%.

Event Malf. Event Event No. No. Type* Description R - ATC Secure the Auxiliary Feedwater Pump and raise power N - BOP to 5% in accordance with OP-003-035, Auxiliary 1 N/A N - SRO Feedwater and OP-010-003, Plant Startup.

Steam generator 1 Pressure Instrument SG-IPT-I - BOP 1013C, fails low requiring Technical Specification I - SRO entry and bypass of multiple PPS bistables. (TS 3.3.1, 2 SG04G TS - SRO 3.3.2)

C - BOP (A) Reactor Coolant Pump 1A lower seal fails. OP-3 RC08A C - SRO 901-130, Reactor Coolant Pump Malfunction I - ATC (A) PZR level instrument, RC-ILI-0110X, fails low I - SRO affecting letdown and heaters. OP-901-110, 4 RC15A2 TS - SRO Pressurizer Level Control Malfunction. (TS 3.3.3.5)

RP02A RP02B RCP 1A sustains a locked rotor and an automatic RP02C reactor trip does not occur. Manual action is needed RP02D C - ATC to trip the reactor (Critical Task 1, manually trip 5 RC03A M - ALL reactor prior to exiting step 1 of OP-902-000)

Loss of Coolant Accident occurs inside containment RC23A and valve CS-125A (Containment Spray Hdr A 6 CS04A M - ALL Isolation) fails closed Containment Spray Pump B trips and cannot be restarted requiring entry into OP-902-008, Functional Recovery and action taken to align Low Pressure Safety Injection pump to provide Containment Spray DI-08A04S22-1 C - BOP (Critical Task 2, align LPSI pump to replace CS 7 CS01B C - SRO pump prior to exiting Appendix 28 of OP-902-009)

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor 2014 NRC Exam Scenario 3 D-1 Rev 3

Scenario Event Description NRC Scenario 3 The crew assumes the shift at ~ 1% power with instructions to stop the running Auxiliary Feedwater Pump and raise power to 5%. All requirements have been met to change modes from MODE 2 to MODE 1.

The Shift Manager has given permission to change modes. The SRO should direct raising power using Control Element Assemblies in accordance with OP-010-003, Plant Startup.

After conducting the required reactivity manipulation, Steam Generator 1 Pressure Instrument, SG-IPT-1013C, fails low. The SRO should review and enter Technical Specifications 3.3.1 action 2 and 3.3.2 action 13 and direct the BOP to bypass the Steam Generator 1 Pressure Lo, Steam Generator 1 P, and Steam Generator 2 P trip bistables in Plant Protection System Channel C within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , in accordance with OP-009-007, Plant Protection System. The SRO should review Technical Specifications 3.3.3.5 and 3.3.3.6 and OP-903-013, Monthly Channel Checks, and determine that Technical Specification entry for 3.3.3.5 and 3.3.3.6 is not required.

After Technical Specifications are addressed, Reactor Coolant Pump 1A lower seal fails requiring entry into OP-901-130, Reactor Coolant Pump Malfunction and implement Section E1, Seal Failure. The SRO should direct the BOP to lower Controlled Bleed off temperature by lowering Component Cooling Water temperature.

After the crew is in Section E1 of OP-901-130 AND the BOP has adjusted Component Cooling Water Temperature, PZR level instrument, RC-ILI-0110X, fails low. The crew will implement OP-901-110, Pressurizer Level Control malfunction and select the non-faulted channel and reenergize Pressurizer heaters. The SRO should review Technical Specifications 3.3.3.5 and 3.3.3.6 and OP-903-013, Monthly Channel Checks, and determine that Technical Specification 3.3.3.5 action a is applicable and the channel needs to be restored within 7 days. The SRO should determine that Technical Specification 3.3.3.6 is not applicable as long as QSPDS channel for Pressurizer level is credited in accordance with OP-903-013, Monthly Channel Checks.

Once the SRO has addressed Technical Specifications, Reactor Coolant Pump 1A sustains a locked rotor and low Reactor Coolant flow bistables actuate. The Reactor Protection System fails to open the required Reactor Trip Breakers and an ATWS condition exists. The ATC should recognize that an automatic protection system has failed to occur and manually trip the reactor by depressing both Reactor Trip pushbuttons (A and D) on CP-2 (CRITICAL TASK 1). The Reactor will be successfully tripped from the RTGB and the crew will enter OP-902-000, Standard Post Trip Actions.

While the crew is performing Standard Post Trip Actions (RCS Heat Removal checks), a Loss of Coolant Accident will occur inside Containment. Safety Injection, Containment Isolation, and Containment Spray will all actuate. The ATC should secure all running Reactor Coolant Pumps when Containment Spray Actuates. When Containment Spray actuates, CS-125A (Containment Spray Hdr A Isolation) fails to open and cannot be opened from the RTGB or locally as it is mechanically stuck. This will result in Containment Spray Pump B as the only source of Containment Spray. The crew should enter OP-902-009, Standard Appendices Appendix 1, Diagnostic Flowchart and diagnose to OP-902-002, Loss of Coolant Accident Recovery.

Once the crew has entered OP-902-002, Containment Spray Pump B will trip and will not be able to be restarted. The crew should determine that Containment isolation and Containment Pressure and Temperature Control Safety Functions are not being met and diagnose into OP-902-008, Functional Recovery. The SRO should prioritize Containment Isolation first due to CS-125B being open and Containment Pressure and Temperature Control second. The crew will perform steps in OP-902-008, Functional Recovery and align the LPSI pump B to replace CS Pump B to establish Containment Temperature and Pressure Control (CRITICAL TASK 2).

The scenario can be terminated after the established Containment Spray flow from the Low Pressure Safety Injection Pump or at the lead examiners discretion.

2014 NRC Exam Scenario 3 D-1 Rev 3

NRC Scenario 3 CRITICAL TASKS

1. ESTABLISH REACTIVITY CONTROL This task is satisfied by shutting down the Reactor by either depressing both Reactor Trip pushbuttons on CP-2 or CP-8, initiating Diverse Reactor Trip Pushbuttons on CP-2, or by deenergizing the rod drive MG sets by deenergizing busses 32A and 32B on CP-1 prior to exiting the step to Verify Reactivity Control (Step 1) of OP-902-000, Standard Post Trip Actions. This task becomes applicable following the tripped Reactor Coolant Pump 1A.

2. ESTABLISH CONTAINMENT TEMPERATURE AND PRESSURE CONTROL This task is satisfied by aligning Low Pressure Safety Injection Pump B to replace Containment Spray Pump B in accordance with Appendix 28 of OP-902-009, Standard Appendices prior to exiting OP-902-009 Appendix 28. This task becomes applicable following the initiation of a Containment Spray Actuation Signal.

Scenario Quantitative Attributes

1. Total malfunctions (5-8) 6

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

3. Abnormal events (2-4) 2

4. Major transients (1-2) 2

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

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

7. Critical tasks (2-3) 2 2014 NRC Exam Scenario 3 D-1 Rev 3

NRC Scenario 3 SCENARIO SETUP A. Reset Simulator to IC-189.

B. Verify Scenario Malfunctions, Remotes, and overrides are loaded, as listed in the Scenario Timeline.

C. Ensure Protected Train B sign is placed in SM office window.

D. Verify PMC is set to MODE 2.

E. Verify EOOS is 10.0 Green F. Complete the simulator setup checklist.

G. Start Insight, open file Crew Performance.tis.

H. If scenario is allowed to run for 10 minutes, the last alarm should be HTR 4B Alt drain valve open (K-

6) on CP-13. Approximately 10 minutes later, another alarm will occur for HTR 6C (H-10) on CP-13 followed by SG level HI/LO. Allow simulator to run as long as desired and then place the simulator in freeze prior to starting the scenario.

2014 NRC Exam Scenario 3 D-1 Rev 3

NRC Scenario 3 SIMULATOR BOOTH INSTRUCTIONS Event 1 Secure AFW Pump and Raise power to 5%

1. No actions for this event.

Event 2 Steam Generator 1 Pressure Instrument SG-IPT-1013C, fails low

1. On Lead Examiner's cue, initiate Event Trigger 2.

2. If Work Week Manager or PMI are called, inform the caller that a work package will be assembled and a team will be sent to the Control Room.

Event 3 RCP 1A Lower Seal Fails

1. On Lead Examiner's cue, initiate Event Trigger 3.

2. If the Duty Engineering or RCP Engineer is called inform the caller that you will monitor RCP 1A for further degradation.

3. If the Work Week Manager or PMM are called, inform the caller that a work package will be assembled for the next forced outage.

Event 4 PZR level instrument, RC-ILI-0110X, fails low

1. On Lead Examiner's cue, initiate Event Trigger 4.

2. If called as NAO to check LCP-43, wait 3 minutes and report RC-ILI-0110-X1 is failed downscale.

3. If directed to check a started Charging pump for proper operation following start, wait 3 minutes and report the following:

a. Suction and discharge valves are open

b. Proper oil levels exist

c. No abnormal vibrations or noises present

4. If Work Week Manager, Computer Technician, or PMI are called, inform the caller that a work package will be assembled and a team will be sent to the Control Room.

Event 5 Reactor Coolant Pump 1A locked rotor

1. On Lead Examiner's cue, initiate Event Trigger 5.

Event 6 Loss of Coolant Accident and valve CS-125A fails closed

1. On Lead Examiner's cue, initiate Event Trigger 6

2. If directed to override CS-125A, wait 3 minutes and initiate Event Trigger 16 and report that the keyswitch for CS-125A is in override.

3. If directed to place the keyswitch for CS-125A in NORMAL, wait 1 minute and initiate Event Trigger 26 and report that the keyswitch for CS-125B is in NORMAL

4. If called as NAO to verify proper operation of unloaded Emergency Diesel Generators, then wait 2 minutes and manually initiate Event Trigger 10. Wait an additional minute and manually initiate Event Trigger 11 to acknowledge local EDG panels. Report that both A and B EDGs are running properly unloaded.

2014 NRC Exam Scenario 3 D-1 Rev 3

NRC Scenario 3 Event 7 Containment Spray Pump B Trip

1. After the crew enters OP-902-002 and on Lead Examiner's cue, initiate Event Trigger 7.

2. If directed to override CS-125B, wait 3 minutes (1 minute if already in the area) and initiate Event Trigger 17 and report that the keyswitch for CS-125B is in OVERRIDE

3. If directed to place the keyswitch for CS-125B in NORMAL, wait 1 minute and initiate Event Trigger 27 and report that the keyswitch for CS-125B is in NORMAL

4. At the end of the scenario, before resetting, end data collection and save the file as 2012 Scenario 1-(start-end time).tid. Export to .csv file. Save the file into the folder for the appropriate crew 2014 NRC Exam Scenario 3 D-1 Rev 3

NRC Scenario 3 SCENARIO TIMELINE DELAY RAMP EVENT KEY DESCRIPTION TRIGGER FINAL HH:MM:SS HH:MM:SS EVENT DESCRIPTION 5 RP02A RPS CH A AUTO TRIP FAILURE N/A 00:00:00 00:00:00 ACTIVE NO AUTOMATIC REACTOR TRIP 5 RP02B RPS CH B AUTO TRIP FAILURE N/A 00:00:00 00:00:00 ACTIVE NO AUTOMATIC REACTOR TRIP 5 RP02C RPS CH C AUTO TRIP FAILURE N/A 00:00:00 00:00:00 ACTIVE NO AUTOMATIC REACTOR TRIP 5 RP02D RPS CH D AUTO TRIP FAILURE N/A 00:00:00 00:00:00 ACTIVE NO AUTOMATIC REACTOR TRIP 6 CS04A CS TRAIN A CS-125A FAILS TO AUTO OPEN N/A 00:00:00 00:00:00 ACTIVE CS-125A FAILS SHUT 2 SG04G MS LINE IPT-1013C FAIL (0-100%) 2 00:00:00 00:00:00 0 SG-IPT-1013C FAILS LOW 3 RC08A RCP 1A LOWER SEAL FAILURE (0-100%) 3 00:00:00 00:00:00 100 PRESSURIZER CODE SAFETY, RC-317A, FAILS OPEN, 4 RC15A2 PZR CONTROL LT 0110X FAILS LO 4 00:00:00 00:00:00 ACTIVE PZR LT 0110X FAILS LOW 5 RC03A RCP RC-MPMP-0001A SHAFT SEIZURE 5 00:00:00 00:00:00 ACTIVE RCP 1A SHAFT SEIZURE 2014 NRC Exam Scenario 3 D-1 Rev 3

NRC Scenario 3 DELAY RAMP EVENT KEY DESCRIPTION TRIGGER FINAL HH:MM:SS HH:MM:SS EVENT DESCRIPTION 6 RC23A RCS COLD LEG 1A RUPTURE 6 00:00:00 00:00:00 3 COLD LEG LOSS OF COOLANT ACCIDENT 7 CS01B LOSS OF CNTMT SPRAY PUMP B 7 00:00:00 00:00:00 ACTIVE CS PUMP B TRIP 6 CSR13A CS-125A REMOTE KEY SW TO CLOSE VALVE 16 00:00:00 00:00:00 OVERRIDE CS-125A KEY SWITCH 6 CSR13A CS-125A REMOTE KEY SW TO CLOSE VALVE 26 00:00:00 00:00:00 NORMAL CS-125A KEY SWITCH 7 CSR13B CS-125B REMOTE KEY SW TO CLOSE VALVE 17 00:00:00 00:00:00 OVERRIDE CS-125B KEY SWITCH 7 CSR13B CS-125B REMOTE KEY SW TO CLOSE VALVE 27 00:00:00 00:00:00 NORMAL CS-125B KEY SWITCH 6 EGR26 EDG A LOCAL ANNUN ACK 10 00:00:00 00:00:00 ACKN LOCAL EDG ANNUNCIATOR ACKNOWLEDGE 6 EGR27 EDG B LOCAL ANNUN ACK 11 00:00:00 00:00:00 ACKN LOCAL EDG ANNUNCIATOR ACKNOWLEDGE 7 DI-08A04S22-1 CC-125A CNTMT SPRAY HEADER A ISOL N/A 00:00:00 00:00:00 CLOSE OVERRIDE CS-125A CONTROL SWITCH TO CLOSE 2014 NRC Exam Scenario 3 D-1 Rev 3

NRC Scenario 3 REFERENCES Event Procedures 1 OP-003-035, Auxiliary Feedwater, Rev. 304 OP-010-003, Plant Startup, Rev. 332 (Copy marked up through Step 9.4.54) 2 OP-009-007, Plant Protection System, Rev. 15 OP-903-013, Monthly Channel Checks, Rev. 16 Technical Specification 3.3.1 Technical Specification 3.3.2 3 OP-901-130, Reactor Coolant Pump Malfunction, Rev. 7 4 OP-901-110, Pressurizer Level Control Malfunction, Rev. 5 Technical Specification 3.3.3.5 OP-903-013, Monthly Channel Checks, Rev. 16 5 OP-902-000, Standard Post Trip Actions, Rev. 13 6 OP-902-009, Standard Appendices, Rev. 309, Appendix 1, Diagnostic Flow Chart OP-902-002, Loss of Coolant Accident Recovery Procedure, Rev. 18 OP-902-009, Standard Appendices, Rev. 309, Appendix 2, Figures 7 OP-902-008, Functional Recovery, Rev. 22 OP-902-009, Standard Appendices, Rev. 309, Appendix 28, Aligning LPSI Pump to Replace CS Pump 2014 NRC Exam Scenario 3 D-1 Rev 3

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 1 Page 1 of 32 Event

Description:

Secure AFW Pump and raise power to 5%

Time Position Applicants Actions or Behavior OP-010-003, Plant Startup, Section, 9.4 SRO 9.4.52.2 Secure Auxiliary Feedwater Pump in accordance with OP-003-035, Auxiliary Feedwater.

OP-003-035, Auxiliary Feedwater, Section, 7.0 N/A 7.1 Shutdown of Auxiliary Feedwater Pump 7.1.1 If recircing Steam Generators, then re-align Blowdown to Condenser A by performing the following:

BOP 7.1.2 Secure Auxiliary Feedwater Pump.

BOP 7.1.3 Place Auxiliary Feedwater Controller, FW-IFIC-8202, in Manual (MAN).

BOP 7.1.3.1 Set controller to minimum setting.

BOP 7.1.4 Open Auxiliary Feedwater Pump Discharge Pressure Cntrl, AFW-125.

OP-010-003, Plant Startup, Section, 9.4 BOP 9.4.52.3 Maintain Steam Generator levels 50 to 70% NR.

N/A 9.4.53 Adjust Steam Generator Blowdown flow as recommended by Chemistry Department.

ATC 9.4.54 Begin raising Reactor power by CEA withdrawal or boron dilution to 5% full power.

ATC Commences raising power per Reactivity plan and per OP-004-004, Control Element Drive OP-004-004, Control Element drive, Section, 6.7 N/A 6.7 Operation of CEAs in Manual Group (MG) Mode (c) 2014 NRC Exam Scenario 3 D-2 Rev 1

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 1 Page 2 of 32 Event

Description:

Secure AFW Pump and raise power to 5%

Time Position Applicants Actions or Behavior CAUTION (1) CRITICALITY SHALL BE ANTICIPATED ANY TIME CEAS ARE WITHDRAWN AND THE REACTOR IS NOT CRITICAL.

(2) OBSERVE APPLICABLE GROUP INSERTION LIMITS IN ACCORDANCE WITH TECHNICAL SPECIFICATION 3.1.3.6 (REG GROUP), AND TECHNICAL SPECIFICATION 3.1.3.5 (SHUTDOWN BANKS).

(3) IMPROPER OPERATION OF CEAS IN MANUAL GROUP MODE MAY CAUSE A REACTOR TRIP BASED ON AN OUT-OF-SEQUENCE CONDITION.

(4) CEA INITIALIZATION PROGRAM MUST BE RUNNING IN THE PLANT MONITORING COMPUTER TO HAVE GROUP STOPS AND SEQUENTIAL PERMISSIVES AVAILABLE.

ATC 6.7.1 Verify Plant Monitoring Computer operable in accordance with OP-004-012, Plant Monitoring Computer.

ATC 6.7.2 Position Group Select switch to desired group (Group P).

ATC 6.7.3 Place Mode Select switch to MG and verify the following:

White lights Illuminated on Group Selection Matrix for selected group MG light Illuminates ATC 6.7.4 Operate CEA Manual Shim switch to WITHDRAW or INSERT group to desired height while monitoring the following:

CEA Position Indicator selected CEA group is moving in desired direction If Reactor is critical, then monitor the following:

o Reactor Power o Reactor Coolant System (RCS) temperature o Axial Shape Index (ASI)

NOTE The Operator should remain in the area in front of the CEA Drive Mechanism Control Panel when the Mode Select switch is not in OFF.

ATC 6.7.5 When desired set of moves have been completed, then place Mode Select switch to OFF.

OP-010-003, Plant Startup, Section, 9.4 ATC 9.4.55 Prior to exceeding 5% power, verify Linear Power Channels are on scale.

2014 NRC Exam Scenario 3 D-2 Rev 1

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 1 Page 3 of 32 Event

Description:

Secure AFW Pump and raise power to 5%

Time Position Applicants Actions or Behavior Examiner Note This event is complete when the AFW pump is stopped and Reactivity Manipulation is satisfied or At Lead Examiners Discretion Examiner Note Cue the Simulator Operator when ready for Event 2 2014 NRC Exam Scenario 3 D-2 Rev 1

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 2 Page 4 of 32 Event

Description:

Steam Generator Pressure Instrument SG-IPT-1013C fails low Time Position Applicants Actions or Behavior ATC Recognize and report indications of failed channel.

Alarms:

RPS CHANNEL TRIP SG 1 PRESSURE LO (Cabinet K, E-15)

SG 1 PRESSURE LO PRETRIP A/C (Cabinet K, F-15)

ESFAS CHANNEL TRIP PRESS SG 2 > SG 1 (Cabinet K, L-16)

PRESS SG 2 > SG 1 ESFAS PRETRIP A/C (Cabinet K, M-16)

RPS CHANNEL C TROUBLE (Cabinet K, G-18)

Indications:

SG #1 Pressure Safety Channel C fails downscale Pre-Trip indication Channel C LO SG-1 PRESS bistable Trip indication Channel C LO SG-1 PRESS bistable Pre-Trip indication Channel C HI SG-2 P bistable Trip indication Channel C HI SG-2 P bistable Examiner Note All BOP manipulations for OP-009-007 are located at CP-10 except as noted.

OP-009-007, Plant Protection System ,Section 6.2, Trip Channel Bypass Operation SRO 6.2.1 Refer to Attachment 11.11, PPS Bistable Bypass Chart to assist in determination of Trip Channels requiring placement in bypass.

Determines the following bistables are affected and need to be bypassed:

11 - LO SG-1 PRESS 19 - HI SG-1 P 20 - HI SG-2 P SRO Directs BOP to bypass the LO SG-1 PRESS, HI SG-1 P, and HI SG-2 P bistables in PPS Channel C within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months in accordance with OP-009-007, Plant Protection System.

BOP 6.2.2 To place a bistable in or remove a bistable from bypass, go to Attachment 11.10, Trip Channel Bypass Operation.

2014 NRC Exam Scenario 3 D-2 Rev 1

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 2 Page 5 of 32 Event

Description:

Steam Generator Pressure Instrument SG-IPT-1013C fails low Time Position Applicants Actions or Behavior OP-009-007, Plant Protection System ,Attachment 11.10, Trip Channel Bypass Operation CAUTION (1) ATTEMPTING TO PLACE MORE THAN ONE TRIP CHANNEL IN BYPASS REMOVES BOTH TRIP CHANNELS FROM BYPASS.

(2) PRIOR TO PLACING ANY TRIP CHANNEL IN BYPASS, VERIFY BYPASS PUSH BUTTONS ON DE-ENERGIZED PPS BAY NOT DEPRESSED.

BOP 11.10.1 To Bypass a Trip Channel, perform the following:

11.10.1.1 Circle the bistable numbers selected for bypass under Step 11.10.1.4. (Circles bistable numbers 11, 19 and 20 in Step 11.10.1.4 table)

BOP 11.10.1.2 Check desired Trip Channel is not Bypassed on another PPS Channel.

BOP 11.10.1.3 Open key-locked portion of BCP in desired PPS Channel.

BOP 11.10.1.4 Depress Bypass push buttons for the desired Trip Channels BOP 11.10.1.5 Check all selected bistable Bypass push buttons remain in a Depressed state.

BOP 11.10.1.6 Check all selected bistable Bypass lights Illuminate on BCP for the desired Trip Channels.

CREW 11.10.1.7 Check all selected bistable Bypass lights Illuminate on ROM for the desired Trip Channels. (Verifies correct bistables lit on CP-7 PPS Channel C Remote Operator Module)

SRO Reviews the following Technical Specifications and determines applicable actions:

3.3.1 - action 2 3.3.2 - action 13 3.3.3.5 - no actions required 3.3.3.6 - no actions required 2014 NRC Exam Scenario 3 D-2 Rev 1

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 2 Page 6 of 32 Event

Description:

Steam Generator Pressure Instrument SG-IPT-1013C fails low Time Position Applicants Actions or Behavior Examiner Note This event is complete when bistables are bypassed and Technical Specifications have been addressed or At Lead Examiners Discretion Examiner Note Cue the Simulator Operator when ready for Event 3 2014 NRC Exam Scenario 3 D-2 Rev 1

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 3 Page 7 of 32 Event

Description:

RCP 1A Lower Seal Failure Time Position Applicants Actions or Behavior ATC / BOP Recognize and report indications of RCP Seal failure Alarms PMC alarm RCP 1A CONTROLLED BLEEDOFF TEMP HI (Cabinet H, F-4) (if unattended)

Indications Middle Seal Pressure rising Upper Seal Pressure rising CCW return temperature rising Controlled bleed off temperature rising CRS Enter and direct the implementation of OP-901-130, Reactor Coolant Pump Malfunction.

OP-901-130, Reactor Coolant Pump Malfunction, E0, Subsequent Operator Actions N/A 1. IF Reactor Coolant Pump trips, THEN verify Reactor tripped AND GO TO OP-902-000, STANDARD POST TRIP ACTIONS.

N/A 2. IF loss of Component Cooling Water to Reactor Coolant Pumps occurs, THEN GO TO OP-901-510, COMPONENT COOLING WATER SYSTEM MALFUNCTION.

SRO 3. IF Reactor Coolant Pump Seal has failed, THEN GO TO section E1, Seal Failure.

OP-901-130, Reactor Coolant Pump Malfunction, E1, Seal Failure NOTE

1. RCP Seal pressure and Control Bleedoff temperature and flow are normally as follows (assuming normal operating RCS temperature and pressure):

Vapor Seal pressure: 25 to 45 PSIG Upper Seal pressure: 585 to 915 PSIG Middle Seal pressure: 1237 to 1815 PSIG CBO temperature: 135° to 190°F CBO flow: 1.2 to 1.8 GPM

2. (If only one Reactor Coolant Pump Seal has failed on a Reactor Coolant Pump, THEN pump operation may continue provided the seal package is monitored for further degradation.

BOP 1. Inform System Engineer of Reactor Coolant Pump Seal failure.

2014 NRC Exam Scenario 3 D-2 Rev 1

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 3 Page 8 of 32 Event

Description:

RCP 1A Lower Seal Failure Time Position Applicants Actions or Behavior CAUTION (1) CCW TEMPERATURES OF <75 F COULD LEAD TO ESSENTIAL CHILLER TRIPS ON EVAPORATOR LOW REFRIGERANT PRESSURE.

(2) CCW TEMPERATURE SHOULD BE CHANGED AT A RATE OF <10 F IN ONE HOUR TO PREVENT DEGREDATION OF THE REACTOR COOLANT PUMP SEALS.

BOP 2. IF Controlled Bleedoff temperature is rising, THEN lower Component Cooling Water temperature by ANY of the following:

Start Dry Cooling Tower Fans Start Auxiliary Component Cooling Water Pump(s) AND associated Wet Cooling Tower Fans.

Start Auxiliary Component Cooling Water Pump(s) AND lower ACC-126A(B) setpoint.

N/A 3. IF TWO OR MORE seals fail in rapid succession, (within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ) THEN perform the following:

3.1 Trip the Reactor.

3.2 Secure affected Reactor Coolant Pump.

3.3 GO TO OP-902-000, STANDARD POST TRIP ACTIONS N/A 4. IF a SECOND seal fails on the same Reactor Coolant Pump, THEN commence a controlled Plant shutdown in accordance with OP-010-005, Plant Shutdown.

N/A 5. IF during the controlled Plant shutdown Controlled Bleedoff temperature rises to >200 F OR a THIRD seal fails on the same Reactor Coolant Pump, THEN perform the following:

NOTE Manual override is accomplished by positioning control switch to CLOSED, then to OPEN. If after 100 seconds CCW Return temperature is <145 F, Seal Cooler isolations will remain open.

CAUTION IF COMPONENT COOLING WATER IS LOST TO REACTOR COOLANT PUMP SEALS FOR >10 MINUTES, THEN RESTORING COMPONENT COOLING WATER TO REACTOR COOLANT PUMPS MAY RESULT IN SEAL FAILURE.

N/A 6. IF Component Cooling Water to a Reactor Coolant Pump Seal Cooler isolates, THEN within 3 minutes restore Component Cooling Water flow to Reactor Coolant Pump by opening the Reactor Coolant Pump Component Cooling Water Isolation valves:

N/A 7. IF CCW flow is lost to a Reactor Coolant Pump Seal AND can NOT be restored within 3 minutes, THEN perform the following:

2014 NRC Exam Scenario 3 D-2 Rev 1

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 3 Page 9 of 32 Event

Description:

RCP 1A Lower Seal Failure Time Position Applicants Actions or Behavior Examiner Note This event is complete after the BOP takes action to lower Component Cooling Water temperature OR At Lead Examiners Discretion Examiner Note Cue the Simulator Operator when ready for Event 4 2014 NRC Exam Scenario 3 D-2 Rev 1

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 4 Page 10 of 32 Event

Description:

Pressurizer Level Channel RC-ILI-0110X fails low Time Position Applicants Actions or Behavior ATC / BOP Recognize and report indications of Channel Failure Alarms PRESSURIZER LEVEL HI/LO (Cabinet H, B-1)

PRESSURIZER LEVEL LO-LO (Cabinet H, C-1)

LETDOWN FLOW HI/LO (Cabinet G, C-1)

Indications PZR Level RC-ILR-0110-X fails downscale All PZR Heaters OFF All Charging Pumps running Letdown Flow lowering Actual PZR level RC-ILR-0110-X rising SRO Enter and direct the implementation of OP-901-110, Pressurizer Level Control Malfunction.

OP-901-110, Pressurizer Level Control Malfunction, E0, General Actions N/A 1. Stop Turbine load changes.

N/A 2. IF malfunction is due to failure of Letdown Flow Control valve, THEN GO TO OP-901-112, CHARGING/LETDOWN MALFUNCTION.

SRO 3. IF malfunction is due to failure of Pressurizer Level Control Channel (incorrect readings on EITHER RC-ILI-0110X OR RC-ILI-0110Y), THEN GO TO Subsection E1, Pressurizer Level Control Channel Malfunction.

OP-901-110, Pressurizer Level Control Malfunction, E1, Pressurizer Level Control Channel Malfunction NOTE Selecting the non-faulted channel may cause automatic actions to occur if actual level is not at program level.

ATC 1. Place Pressurizer Level Controller (RC-ILIC-0110) in MAN AND adjust OUTPUT to slowly adjust letdown flow to restore Pressurizer level.

2014 NRC Exam Scenario 3 D-2 Rev 1

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 4 Page 11 of 32 Event

Description:

Pressurizer Level Channel RC-ILI-0110X fails low Time Position Applicants Actions or Behavior ATC 2. Transfer Pressurizer Level Control CHANNEL SELECT switch to non-faulted channel.

ATC 3. Transfer Pressurizer CHANNEL SELECT LO LEVEL HEATER CUTOFF switch to non-faulted channel.

ATC 4. Verify desired backup Charging pumps in AUTO.

ATC 5. Verify ALL PROPORTIONAL AND BACKUP HEATER BANKS reset.

ATC 6. Place Pressurizer Level Controller (RC-ILIC-0110) in AUTO and verify Pressurizer Level is being restored to setpoint.

ATC 7. Verify Pressurizer level controlling at program setpoint in accordance with Attachment 1, Pressurizer Level Versus Tave Curve.

SRO 8. Refer to Technical Specifications 3.3.3.5 and 3.3.3.6 for Remote Shutdown and Accident Monitoring operability determination.

2014 NRC Exam Scenario 3 D-2 Rev 1

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 4 Page 12 of 32 Event

Description:

Pressurizer Level Channel RC-ILI-0110X fails low Time Position Applicants Actions or Behavior SRO Reviews the following Technical Specifications and determines applicable actions:

3.3.3.5 - action a 3.3.3.6 - no actions required Examiner Note This event is complete after the ATC has restored automatic Pressurizer level control and the SRO has evaluated Technical Specifications OR At Lead Examiners Discretion Examiner Note Cue the Simulator Operator when ready for Event 5 2014 NRC Exam Scenario 3 D-2 Rev 1

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 5 Page 13 of 32 Event

Description:

RCP 1A locked rotor no automatic Reactor Trip Time Position Applicants Actions or Behavior ATC Recognize and report indications of RCP trip and no Auto RX Trip Alarms:

RCP 1A TRIP/TROUBLE (Cabinet H, A-3)

RCP 1A LUBE OIL PRESSURE LO (Cabinet H, E-3)

RCP 1A VIBRATION HI (Cabinet H, A-4)

RCP 1A CCW FLOW LO (Cabinet H, H-4)

RCP 1A CCW FLOW LOST (Cabinet SA(SB), A-1(6)

RPS CHANNEL TRIP LOCAL PWR DENSITY HI (Cabinet K, A-11)

RPS CHANNEL TRIP DNBR LO (Cabinet K, A-12)

LOCAL PWR DENSITY HI PRETRIP A/C(B/D) (Cabinet K, B(C)-11)

DNBR LO PRETRIP A/C(B/D) (Cabinet K, B(C)-12)

RPS CHANNEL TRIP COOLANT FLOW LOST (Cabinet K, D-12)

RPS CHANNEL A(B)(C)(D) TROUBLE (Cabinet K, E(F)(G)(H)-18)

Indications:

RCP 1A STOP light and Yellow Trip indication RCP 1A Oil Lift Pumps running RCP 1A motor amps indicate 0amps RCP 1A P lowering Trip indication Channel A(B)(C)(D) HI LOCAL POWER bistables Pre-Trip indication Channel A(B)(C)(D) HI LOCAL POWER bistables Trip indication Channel A(B)(C)(D) LOW DNBR bistables Pre-Trip indication Channel A(B)(C)(D) LOW DNBR bistables Trip indication Channel A(B)(C)(D) SG LO FLOW bistables All Reactor Trip breakers remain closed All CEAs remain withdrawn CRITICAL TASK ESTABLISH REACTIVITY CONTROL This task is satisfied by shutting down the Reactor by either depressing both Reactor Trip pushbuttons on CP-2 or CP-8, initiating Diverse Reactor Trip Pushbuttons on CP-2, or by deenergizing the rod drive MG sets by deenergizing busses 32A and 32B on CP-1 prior to exiting the step to Verify Reactivity Control (Step 1) of OP-902-000, Standard Post Trip Actions.

This task becomes applicable following the tripped Reactor Coolant Pump 1A.

ATC Manually Trip the Reactor (CRITICAL) 2014 NRC Exam Scenario 3 D-2 Rev 1

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 5 Page 14 of 32 Event

Description:

RCP 1A locked rotor no automatic Reactor Trip Time Position Applicants Actions or Behavior OP-902-000, Standard Post Trip Actions ATC 1. Determine Reactivity Control acceptance criteria are met:

a. Check reactor power is dropping.

b. Check startup rate is negative.

c. Check less than TWO CEAs are NOT fully inserted.

BOP 2. Determine Maintenance of Vital Auxiliaries acceptance criteria are met:

a. Check the Main Turbine is tripped:

Governor valves closed Throttle valves closed BOP b. Check the Main Generator is tripped:

GENERATOR BREAKER A tripped GENERATOR BREAKER B tripped EXCITER FIELD BREAKER tripped BOP c. Check station loads are energized from offsite electrical power as follows:

Train A A1, 6.9 KV non safety bus A2, 4.16 KV non safety bus A3, 4.16 KV safety bus A-DC electrical bus A or C vital AC Instrument Channel Train B B1, 6.9 KV non safety bus B2, 4.16 KV non safety bus B3, 4.16 KV safety bus B-DC electrical bus B or D vital AC Instrument Channel ATC 3. Determine RCS Inventory Control acceptance criteria are met:

a. Check that BOTH the following conditions exist:

Pressurizer level is 7% to 60%

Pressurizer level is trending to 33% to 60%

b. Check RCS subcooling is greater than or equal to 28ºF.

2014 NRC Exam Scenario 3 D-2 Rev 1

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 5 Page 15 of 32 Event

Description:

RCP 1A locked rotor no automatic Reactor Trip Time Position Applicants Actions or Behavior ATC 4. Determine RCS Pressure Control acceptance criteria are met by checking that BOTH of the following conditions exist:

Pressurizer pressure is 1750 psia to 2300 psia Pressurizer pressure is trending to 2125 psia to 2275 psia ATC 5. Determine Core Heat Removal acceptance criteria are met:

a. Check at least one RCP is operating.

b. Check operating loop T is less than 13ºF.

c. Check RCS subcooling is greater than or equal to 28ºF.

Examiner Note This event is complete after the crew has reached the steps to check RCS Heat Removal OR At Lead Examiners Discretion Examiner Note Cue the Simulator Operator when ready for Event 6 2014 NRC Exam Scenario 3 D-2 Rev 1

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 6 Page 16 of 32 Event

Description:

Loss of Coolant Accident CS-125A fails closed Time Position Applicants Actions or Behavior BOP Recognize and report indications of LOCA Alarms CONTAINMENT WATER LEAKAGE HI (Cabinet N, L-20)

CONTAINMENT WATER LEAKAGE HI-HI (Cabinet N, K-20)

PRESSURIZER PRESSURE HI/LO (Cabinet H, E-1)

CIAS TRAIN A(B) LOGIC INITIATED [Cabinet K, E-19(20)]

SIAS TRAIN A(B) LOGIC INITIATED [Cabinet K, G-19(20)]

CSAS TRAIN A(B) LOGIC INITIATED [Cabinet K, H-19(20)]

MSIS TRAIN A(B) LOGIC INITIATED [Cabinet K, L-19(20)]

SUBCOOLED MARGIN LO [Cabinet M(N), M-7(17)]

RPS CHANNEL TRIP PZR PRESSURE LO (Cabinet K, A-16)

RPS CHANNEL TRIP CNTMT PRESSURE HI (Cabinet K, A-17)

ESFAS CHANNEL TRIP CNTMT PRESSURE HI (Cabinet K, L-17)

CNTMT SPRAY HDR A FLOW LO (Cabinet M, F-4)

Indications RCS pressure lowering PZR level lowering Containment Pressure and Temperature rising Containment activity rising Containment water level rising ESFAS components actuating CS-125A indicates in CLOSE (GREEN)

Examiner Note The crew should report indications but continue in OP-902-000, Standard Post Trip Actions BOP 6. Determine RCS Heat Removal acceptance criteria are met:

a. Check that at least one steam generator has BOTH of the following:

Steam generator level is 10% to 76% NR Main Feedwater is available to restore level within 55%-70%

NR.[60% to 80% NR]

ATC b. Check RCS TC is 530 ºF to 550 ºF BOP c. Check steam generator pressure is 885 psia to 1040 psia.

2014 NRC Exam Scenario 3 D-2 Rev 1

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 6 Page 17 of 32 Event

Description:

Loss of Coolant Accident CS-125A fails closed Time Position Applicants Actions or Behavior BOP d. Check Feedwater Control in Reactor Trip Override:

MAIN FW REG valves are closed STARTUP FW REG valves are 13% to 21% open Operating main Feedwater pumps are 3800 rpm to 4000 rpm BOP e. Reset moisture separator reheaters, and check the temperature control valves closed.

ATC 7. Determine Containment Isolation acceptance criteria are met:

a. Check containment pressure is less than 16.4 psia.

b. Check NO containment area radiation monitor alarms OR unexplained rise in activity.

c. Check NO steam plant activity monitor alarms OR unexplained rise in activity.

ATC a.1 IF containment pressure is greater than or equal to 17.1 psia, THEN verify the following:

CIAS is initiated

SIAS is initiated

MSIS is initiated BOP 8 Determine Containment Temperature and Pressure Control acceptance criteria are met:

a. Check containment temperature is less than or equal to 120ºF.

b. Check containment pressure is less than 16.4 psia.

BOP 8.1 Verify at least three containment fan coolers are operating.

BOP 8.2 IF containment pressure is greater than or equal to 17.1 psia, THEN verify ALL available containment fan coolers are operating in emergency mode.

BOP/ATC 8.3 IF containment pressure is greater than or equal to 17.7 psia, THEN verify ALL of the following:

CSAS is initiated

ALL available containment spray pumps are delivering flow greater than 1750 gpm

ALL RCPs are secured N/A 9. IF ALL safety function acceptance criteria are met, AND NO contingency actions were performed, THEN GO TO OP-902-001, "Reactor Trip Recovery" procedure.

2014 NRC Exam Scenario 3 D-2 Rev 1

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 6 Page 18 of 32 Event

Description:

Loss of Coolant Accident CS-125A fails closed Time Position Applicants Actions or Behavior SRO 10. IF ANY safety function acceptance criteria are NOT met, OR ANY contingency action was taken, THEN GO TO Appendix 1, "Diagnostic Flowchart.

OP-902-009, Standard Appendices, Appendix 1 Examiner Note Appendix 1 is a flow chart used to diagnose to the correct recovery procedure for the event in progress. The steps below will be followed by a YES or NO to indicate proper flow path.

ATC Rx Pwr dropping, SUR negative, and < two CEAs NOT fully inserted or Emergency Boration in progress (YES)

ATC Pressurizer pressure dropping rapidly and Pressurizer level changing (YES)

BOP Steam Generator Pressure Abnormally Low (NO)

N/A Primary Break ATC Containment Pressure and Temperature Abnormally High (YES)

ATC Activity in the Steam Plant (NO)

N/A LOCA inside Containment BOP At least one 4KV safety bus energized (YES)

SRO Go To OP-902-002, LOCA Recovery OP-902-002, Loss of Coolant accident Recovery NOTE The Shift Chemist should be notified if a SIAS or CIAS has occurred. The secondary sampling containment isolation valves should not be opened following an SIAS or CIAS until directed by the Shift Chemist.

BOP Confirm Diagnosis

1. Confirm diagnosis of a LOCA:

a. Check Safety Function Status Check acceptance criteria are satisfied.

b. IF steam generator sample path is available, THEN direct Chemistry to sample BOTH steam generators for activity.

2014 NRC Exam Scenario 3 D-2 Rev 1

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 6 Page 19 of 32 Event

Description:

Loss of Coolant Accident CS-125A fails closed Time Position Applicants Actions or Behavior BOP Announce the Event

2. Announce a Loss of Coolant Accident is in progress using the plant page.

N/A Classify the Event

3. Advise the Shift Manager to REFER TO EP-001-001, "Recognition &

Classification of Emergency Condition", and implement the Emergency Plan.

N/A Restore Operation of DCT Sump Pumps

4. IF power has been interrupted to either 3A or 3B safety buses, THEN perform Appendix 20, "Operation of DCT Sump Pumps".

SRO Implement Placekeeping

5. REFER TO Section 6.0, "Placekeeper", and record the time of the reactor trip.

ATC Verify SIAS Initiation

6. IF pressurizer pressure is less than 1684 psia, THEN check SIAS has initiated.

BOP *7. IF SIAS has initiated, THEN:

a. Verify safety injection pumps have started.

b. Check safety injection flow is within the following:

Appendix 2-E, "HPSI Flow Curve" Appendix 2-F, "LPSI Flow Curve" Examiner Note Appendix 2-E and Appendix 2-F are contained on the next 2 pages. Injection flow will be meeting all requirements.

2014 NRC Exam Scenario 3 D-2 Rev 1

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 6 Page 20 of 32 Event

Description:

Loss of Coolant Accident CS-125A fails closed Time Position Applicants Actions or Behavior 2014 NRC Exam Scenario 3 D-2 Rev 1

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 6 Page 21 of 32 Event

Description:

Loss of Coolant Accident CS-125A fails closed Time Position Applicants Actions or Behavior ATC c. Verify ALL available charging pumps are operating.

N/A RCP Trip Strategy

8. IF pressurizer pressure is less than 1621 psia, AND SIAS is actuated, THEN:

a. Verify no more than two RCPs are operating.

b. IF pressurizer pressure is less than the minimum RCP NPSH of Appendix 2A-D, "RCS Pressure and Temperature Limits", THEN stop ALL RCPs.

2014 NRC Exam Scenario 3 D-2 Rev 1

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 6 Page 22 of 32 Event

Description:

Loss of Coolant Accident CS-125A fails closed Time Position Applicants Actions or Behavior ATC Verify RCP Operating Limits

9. IF RCPs are operating, THEN:

a. Verify CCW available to RCPs.

b. IF a CSAS is initiated, THEN stop ALL RCPs.

c. IF RCS TC is less than 382ºF, THEN verify no more than two RCPs are operating.

BOP Verify Proper CCW Operation

10. Check a CCW pump is operating for each energized 4.16 KV safety bus.

ATC Isolate the LOCA

11. Isolate the LOCA:

a. Verify the following letdown containment isolation valves are closed:

CVC 101, LETDOWN STOP VALVE CVC 103, LETDOWN ISOL VALVE CVC 109, LETDOWN ISOL VALVE BOP b. Verify the following RCS sampling containment isolation valves are closed:

Train A PSL 107, HOT LEG PSL 204, PZR SURGE PSL 304, PZR STEAM Train B PSL 105, HOT LEG PSL 203, PZR SURGE PSL 303, PZR ISOL VLV Examiner Note This event is complete after the crew has entered OP-902-002, Loss of Coolant Accident Recovery and all RCPs are secured OR At Lead Examiners Discretion Examiner Note Cue the Simulator Operator when ready for Event 7 Examiner Note It takes approximately 30 seconds from when the simulator operator initiates Event 7 for the first indication to be present to the applicants.

2014 NRC Exam Scenario 3 D-2 Rev 1

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 7 Page 23 of 32 Event

Description:

Containment Spray Pump B Trips Time Position Applicants Actions or Behavior BOP Recognize and report indications of B Spray Pump Trip Alarms CNTMT SPRAY PUMP B TRIP/TROUBLE (Cabinet N, B-14)

Indications Containment Spray Pump B indicates OFF (GREEN)

Containment Spray flow indicates 0 GPM OP-902-002, Loss of Coolant accident Recovery SRO Confirm Diagnosis

1. Confirm diagnosis of a LOCA:

a. Check Safety Function Status Check acceptance criteria are satisfied.

b. IF steam generator sample path is available, THEN direct Chemistry to sample BOTH steam generators for activity.

SRO Evaluate Safety Functions SRO Determine Containment Pressure and Temperature Control Safety Function not met SRO SAFETY FUNCTION:

8. Containment Temperature and Pressure Control Condition 2

a. Containment fan coolers > 1 operating in emerg mode

b. Containment spray pump > 1 operating with flow > 1750 gpm

c. Containment pressure < 50 psia SRO a.1 GO TO ONE of the following:

Appendix 1, "Diagnostic Flowchart" OP-902-008, "Functional Recovery Procedure" Examiner Note Appendix 1 Diagnostic Flowchart will not provide guidance for this event. OP-902-008, Functional Recovery Procedure is the procedure to recover from this event.

OP-902-008, Functional Recovery BOP Announce the Event

1. Announce that the Functional Recovery Procedure is in progress using the plant page.

2014 NRC Exam Scenario 3 D-2 Rev 1

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 7 Page 24 of 32 Event

Description:

Containment Spray Pump B Trips Time Position Applicants Actions or Behavior N/A Classify the Event

2. Advise the Shift Manager to REFER TO EP-001-001, "Recognition &

Classification of Emergency Condition", and implement the Emergency Plan.

SRO Implement Placekeeping

3. REFER TO the "Placekeeper", and record the time of the reactor trip.

ATC RCP Trip Strategy

4. IF pressurizer pressure is less than 1621 psia, AND SIAS is actuated, THEN:

a. Verify no more than two RCPs are operating.

b. IF pressurizer pressure is less than the minimum RCP NPSH of Appendix 2A-D, "RCS Pressure and Temperature Limits", THEN stop ALL RCPs.

N/A Verify RCP Operating Limits

5. IF RCPs are operating, THEN:

a. IF a CSAS is initiated, THEN stop ALL RCPs.

b. Verify CCW available to RCPs. c. IF RCS TC is less than 382ºF

[384ºF], THEN verify no more than two RCPs are operating.

NOTE The Shift Chemist should be notified if a SIAS or CIAS has occurred. The secondary sampling containment isolation valves should not be opened following an SIAS or CIAS until directed by the Shift Chemist.

BOP Sample BOTH Steam Generators

6. Direct Chemistry to sample BOTH steam generators for activity and boron.

N/A Verify Equipment Ventilation

7. IF power is lost to both 3A and 3B safety buses and NOT expected to be restored within 30 minutes, THEN perform the following:

NOTE Portable emergency lighting is available in Appendix R lockers located at LCP-43, Remote Shutdown Panel and +35 RAB Relay Room.

N/A Reduce Battery Loads

8. IF power is lost to both 3A and 3B safety buses and NOT expected to be restored within 30 minutes, THEN perform the following to reduce unnecessary station loads:

2014 NRC Exam Scenario 3 D-2 Rev 1

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 7 Page 25 of 32 Event

Description:

Containment Spray Pump B Trips Time Position Applicants Actions or Behavior N/A Restore Operation of DCT Sump Pumps

9. IF power has been interrupted to either 3A or 3B safety buses, THEN perform Appendix 20, "Operation of DCT Sump Pumps".

BOP Place Hydrogen Analyzers in Service

10. Place Hydrogen Analyzers in service:

Train A

a. Place Train A H2 ANALYZER CNTMT ISOL VALVE keyswitch to "OPEN". (Key 216)

b. Place H2 ANALYZER A POWER to "ON".

c. Check H2 ANALYZER A PUMP indicates ON.

BOP Train B

a. Place Train B H2 ANALYZER CNTMT ISOL VALVE keyswitch to "OPEN". (Key 217)

b. Place H2 ANALYZER B POWER to "ON".

c. Check H2 ANALYZER B PUMP indicates ON.

SRO Identify Success Paths

11. Identify success paths to be used to satisfy each safety function using BOTH of the following:

Resource Assessment Trees Safety Function Tracking Sheet Note 1. Reactivity Control RC-1

2. Maintenance of Vital Auxiliaries (DC) MVA-DC-1

3. Maintenance of Vital Auxiliaries (AC) MVA-AC-1

4. RCS Inventory Control IC-2

5. RCS Pressure Control PC-2

6. RCS and Core Heat Removal HR-2

7. Containment Isolation CI-1

8. Containment Pressure and Temperature Control CPTC-2 SRO Perform Safety Function Status Checks

12. REFER TO Section 6.0, "Safety Function Status Check", and perform Safety Function Status Checks.

2014 NRC Exam Scenario 3 D-2 Rev 1

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 7 Page 26 of 32 Event

Description:

Containment Spray Pump B Trips Time Position Applicants Actions or Behavior Examiner Note

1. RC Met

2. MVA-DC Met

3. MVA-AC Met

4. IC Met

5. PC Met

6. HR Met

7. CI NOT Met

8. CPTC NOT Met SRO Maintain Success Paths

13. Prioritize Safety Functions based on ALL of the following:

a. Instructions for those Safety Functions which do NOT meet any success path.

b. Instructions for those Safety Functions for which success path one criteria is NOT met.

c. Instructions for Safety Functions for which success path one criteria is met.

Note 1. Containment Isolation CI-1

2. Containment Pressure and Temperature Control CPTC-2

3. RCS Inventory Control IC-2

4. RCS Pressure Control PC-2

5. RCS and Core Heat Removal HR-2

6. Reactivity Control RC-1

7. Maintenance of Vital Auxiliaries (DC) MVA-DC-1

8. Maintenance of Vital Auxiliaries (AC) MVA-AC-1 SRO Implement Success Paths

14. Implement success paths based on prioritization from previous step.

Examiner Note The SRO may decide that by establishing Containment Pressure and Temperature control, that this would satisfy the Containment Isolation Safety Function. The SRO may decide to implement CPTC-2 to restore both Safety Functions. However this guide contains CI-1 steps below followed by CPTC-2 steps.

2014 NRC Exam Scenario 3 D-2 Rev 1

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 7 Page 27 of 32 Event

Description:

Containment Spray Pump B Trips Time Position Applicants Actions or Behavior OP-902-008, Functional Recovery, CI-1 SRO Verify Containment Isolation

1. IF ANY of the following conditions exist:

Containment pressure is greater than 17.1 psia Pressurizer pressure is less than 1684 psia Containment area radiation monitors greater than the Hi Alarm setpoint THEN perform BOTH of the following:

a. Verify CIAS is initiated.

b. Verify that an isolation valve is closed for each containment penetration required to be closed.

N/A b.1 IF ANY containment fan cooler is NOT operating AND containment pressure is greater than 17.1 psia, THEN REFER TO Appendix 21-B, "CFC CCW Override" and close the associated Containment Fan Cooler CCW Isolation Valves.

SRO b.2 IF ANY CS-125, Containment Spray Header Isolation is open AND the associated CS pump is NOT operating, THEN REFER TO Appendix 21-A, "CS-125 Override," and close the valve.

OP-902-009, Standard Appendices, Appendix 21-A BOP 1.1 Place Containment Spray Pump A(B) control switch to "OFF."

Examiner Note CNTMT SPRAY HDR B ISOL VLV IN CSAS OVERRIDE (Cabinet N, K-14) will actuate upon the execution of the step below to place the keyswitch for CS-125B in OVERRIDE.

BOOTH 1.2 Place the keyswitch for CS-125A(B), Containment Spray Isolation Valve, located on the side of Auxiliary Panel 1(Auxiliary Panel 2) to "OVERRIDE."

BOP 1.3 Place CS-125A(B), CNTMT SPRAY HEADER A(B) ISOL valve to "OPEN" and then to "CLOSE."

SRO Transition back to OP-902-008, Functional Recovery 2014 NRC Exam Scenario 3 D-2 Rev 1

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 7 Page 28 of 32 Event

Description:

Containment Spray Pump B Trips Time Position Applicants Actions or Behavior OP-902-008, Functional Recovery, CI-1 (cont)

N/A Determine Most Affected SG

2. IF a SGTR is indicated by ANY of the following:

Steam generator activities Main Steam Line radiation levels Steam generator Blowdown radiation monitor readings Steam generator level rise when NOT feeding One steam generator level rising faster that the other with feed and steaming rates being essentially the same for both Feed flow mismatch between steam generators Steam flow verses feed flow mismatch in a steam generator prior to the reactor trip THEN REFER TO Heat Removal success path in use and isolate the most affected steam generator:

BOP CCW Leakage

3. Check the following CCW Radiation Monitor AB indications:

Hi Alarm clear No abnormal rise in radiation monitor reading SRO Check CI-1 Acceptance Criteria

4. Check CI-1, Automatic/Manual Isolation is satisfied by ANY of the following:

Condition 1

a. IF steam plant activity monitor alarms or an unexplained rise in steam plant activity exists, THEN ALL release paths from the most affected steam generator to the environment are closed.

b. Containment pressure is less than 17.1 psia.

c. NO Containment area radiation monitor alarms or unexplained rise.

d. IF SGTR diagnosed, THEN steam generator pressure less than 1000 psia

[960 psia] AND NOT steaming via ADV.

SRO Condition 2

a. IF steam plant activity monitor alarms or an unexplained rise in steam plant activity exists, THEN ALL release paths from the most affected steam generator to the environment are closed.

b. Each containment penetration required to be closed for current plant conditions has an isolation valve closed.

c. IF SGTR diagnosed, THEN steam generator pressure less than 1000 psia

[960 psia] AND NOT steaming via ADV.

2014 NRC Exam Scenario 3 D-2 Rev 1

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 7 Page 29 of 32 Event

Description:

Containment Spray Pump B Trips Time Position Applicants Actions or Behavior N/A Continue Efforts to Restore Safety Functions

1. IF the Containment Isolation safety function is still NOT met, THEN continue efforts to establish Containment Isolation by evaluating further actions based on ALL of the following:

The urgency of other safety functions that are NOT met The risk to plant personnel and the public of leaving certain containment penetrations unisolated The feasibility of isolating containment penetration(s) by alternate means OP-902-008, Functional Recovery, CPTC-2 BOP Verify Containment Spray Actuation

1. IF containment pressure is greater than 17.7 psia, THEN perform BOTH of the following:

a. Verify CSAS is initiated.

b. Verify ALL containment spray pumps are delivering flow greater than 1750 gpm.

BOP a.1 IF ANY CS-125, Containment Spray Header Isolation is open AND the associated CS pump is NOT operating, THEN REFER TO Appendix 21-A, "CS-125 Override," and close the valve.

OP-902-009, Standard Appendices, Appendix 21-A BOP 1.1 Place Containment Spray Pump A(B) control switch to "OFF."

Examiner Note CNTMT SPRAY HDR B ISOL VLV IN CSAS OVERRIDE (Cabinet N, K-14) will actuate upon the execution of the step below to place the keyswitch for CS-125B in OVERRIDE.

BOOTH 1.2 Place the keyswitch for CS-125A(B), Containment Spray Isolation Valve, located on the side of Auxiliary Panel 1(Auxiliary Panel 2) to "OVERRIDE."

BOP 1.3 Place CS-125A(B), CNTMT SPRAY HEADER A(B) ISOL valve to "OPEN" and then to "CLOSE."

SRO Transition back to OP-902-008, Functional Recovery 2014 NRC Exam Scenario 3 D-2 Rev 1

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 7 Page 30 of 32 Event

Description:

Containment Spray Pump B Trips Time Position Applicants Actions or Behavior OP-902-008, Functional Recovery, CPTC-2 (cont)

N/A Containment Spray Termination

2. IF CS pumps are operating AND ALL of the following conditions are satisfied:

Containment pressure is less than 16.4 psia and stable or lowering RAS has NOT actuated Containment Spray is NOT required for iodine removal THEN REFER TO Appendix 5-E, "CSAS Reset Procedure",and reset CSAS actuation.

SRO Check CTPC-2 Acceptance Criteria

3. Check CTPC-2, Containment Spray is satisfied by ANY of the following:

Condition 1

a. BOTH containment spray pumps delivering flow greater than or equal to 1750 gpm.

b. Containment pressure is less than 50 psia.

Condition 2

a. At least one containment fan cooler is operating in the emergency mode.

b. At least one containment spray pump delivering flow greater than or equal to 1750 gpm.

c. Containment pressure is less than 50 psia.

SRO 3.1 IF the Containment Temperature and Pressure safety function is still NOT met, THEN REFER TO CTPC Continuing Actions.

OP-902-008, Functional Recovery, CPTC Continuing Actions SRO Continue Efforts to Restore Safety Functions

1. IF the Containment Temperature and Pressure safety function is still NOT met, THEN continue efforts to establish Containment Temperature and Pressure by evaluating further actions using ALL of the following:

a. The urgency of other safety functions that are NOT met.

b. The rate of change of containment temperature and pressure and potential for damage to the containment.

c. The feasibility of restoring a success path by restoring ALL of the following:

Vital auxiliaries necessary to operate systems or components in the success path Manual operation of valves

d. Use of alternate components to implement a success path:

Appendix 28, "Aligning LPSI to Replace CS" 2014 NRC Exam Scenario 3 D-2 Rev 1

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 7 Page 31 of 32 Event

Description:

Containment Spray Pump B Trips Time Position Applicants Actions or Behavior OP-902-009, Standard Appendices, Appendix 28-B CRITICAL TASK ESTABLISH CONTAINMENT TEMPERATURE AND PRESSURE CONTROL This task is satisfied by aligning Low Pressure Safety Injection Pump B to replace Containment Spray Pump B in accordance with Appendix 28 of OP-902-009, Standard Appendices prior to exiting OP-902-009 Appendix 28.

This task becomes applicable following the initiation of a Containment Spray Actuation Signal.

SRO 1.1 Obtain TSC concurrence prior to performing this evolution.

BOP 1.2 Verify LPSI Pump B control switch in "OFF." (CRITICAL)

BOP 1.3 Verify Containment Spray Pump B control switch in "OFF."

BOP 1.4 Place SI-129B, LPSI FLOW CONTROL VALVE to "AUTO." (Key 146)

(CRITICAL)

BOP 1.5 Place SI-IFIC-0306, LPSI FLOW CONTROLLERS HEADER 1A/1B in "MAN." (CRITICAL)

BOP 1.6 Adjust SI-IFIC-0306, LPSI FLOW CONTROLLERS HEADER 1A/1B to 0% output. (CRITICAL)

BOP 1.7 Verify the following valves Closed: (CRITICAL)

SI-415B, LPSI SHUTDOWN TEMP CONTROL valve (Key 147)

SI-138B, LPSI FLOW CONTROL COLD LEG 1B SI-139B, LPSI FLOWCONTROL COLD LEG 1A BOP 1.8 Open SI-125B/SI-412B, SHDN HX B ISOL valves. (Key 145)

(CRITICAL)

BOP 1.9 Verify CS-125B, CNTMT SPRAY HEADER B ISOL valve open.

(CRITICAL)

BOP 1.10 Start LPSI Pump B. (CRITICAL)

BOP 1.11 Verify Containment Spray Header B flow.

2014 NRC Exam Scenario 3 D-2 Rev 1

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 7 Page 32 of 32 Event

Description:

Containment Spray Pump B Trips Time Position Applicants Actions or Behavior Examiner Note This event is complete after the BOP has established Containment Spray flow in accordance with OP-902-009, Standard appendices, Appendix 28 OR At Lead Examiners Discretion 2014 NRC Exam Scenario 3 D-2 Rev 1

ES-301 Transient and Event Checklist Form ES-301-5 Facility: Waterford 3 Date of Exam: 4/07/2014 Operating Test No. 1 A E Scenarios p v 1 2 3 T M p E 0 I L N CREW CREW CREW CREW T N I T POSITION POSITION POSITION POSITION I

c s A B s A B s A B s A B A M

A T A T 0 A T 0 A T 0 A T 0 L u y

N T p 0 c p 0 c p 0 c p 0 c p M(*)

E A I u RX 3 3 1 3 1 1 0 NOR 3 3 3 3 1 1 3 1 1 1 1/C 1,2,7 1,5,7 2,6,8 1,2,4, 2,&,7 1,4,6 2,3,4, 4,5 2,3,7 16 4 4 2 7 7 MAJ 4 4 4 5 5 5 5,6 5,6 ~ 4 2 2 1 TS 2,3 1,2,3 2.4 7 0 2 2 RX 0 1 1 0 NOR 3 3 1 3 1 1 1 SRO 1/C 1,2,7 1,2,4, 2,3,4, 11 4 4 2 7 7 MAJ 4 5 5,6 4 2 2 1 TS 2,3 1,2,3 2,4 7 0 2 2 RX 3 3 1 3 1 1 0 NOR 0 1 1 1 ATC 1/C 1,5,7 2,6,7 4,5 8 4 4 2 MAJ 4 5 5,6 4 2 2 1 TS 0 0 2 2 RX 0 1 1 0 NOR 3 3 1 3 1 1 1 1/C 2,6,8 1,4,6 2,3,7 9 4 4 2 BOP MAJ 4 5 5,6 4 2 2 1 TS 0 0 2 2 Instructions:

1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the "at-the-controls (ATC)" and "balance-of-plant (BOP)" positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (1/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one 1/C malfunction can be credited toward the two 1/C malfunctions required for the ATC position.

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

3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicant's competence count toward the minimum requirements specified for the applicant's license level in the right-hand columns.

2014 NRC Revision 0

ES-301 Competencies Checklist Form ES-301-6 Facility: Waterford 3 Date of Exam: 4/07/2014 Operating Test No.: 1 APPLICANTS ATC BOP SRO Competencies SCENARIO SCENARIO SCENARIO 1 2 3 4 1 2 3 4 1 2 3 4 Interpret/Diagnose Events 1 ,3, 1 ,2, 1,3, 2,4, 3,4, 1 ,2, 1,2, 1 ,2, 1 ,2, and Conditions 4,5, 3,5, 4,5, 6,7, 6,7 3,6, 3,4, 3,4, 3,4, 7 6,7 6 8 7 7 5 6,7 Comply With and 1 ,3, 2,3, 1,4, 2,3, 1 ,3, 1 ,2, 1,2, 1 ,2, 1,2, Use Procedures (1) 4,5, 5,7 5,6 6,8 4,5 3,6, 3,4, 3,4, 3,4, 7 7 7 5,7 6,7 Operate Control 1 ,3, 2,3, 1,4, 2,3, 1 ,3, 1 ,2, Boards (2} 4,5, 5,6, 5,6 6,8 4,5, 3,6, N/A N/A N/A 7 7 6 7 Communicate and Interact ALL ALL ALL ALL ALL ALL ALL ALL ALL Demonstrate Supervisory 1 ,2, 1 ,2, 1 ,2, Ability (3) N/A N/A N/A N/A N/A N/A 3,4, 3,4, 3,4, 7 5,7 6,7 Comply With and 2,3 1 ,2, 2,4 Use Tech. Specs. (3} N/A N/A N/A N/A N/A N/A 3 Notes:

(1) Includes Technical Specification compliance for an RO.

(2) Optional for an SRO-U.

(3) Only applicable to SROs.

Instructions:

Check the applicants' license type and enter one or more event numbers that will allow the examiners to evaluate every applicable competency for every applicant.

Revision 0

Waterford 3 2014 NRC Exam Job Performance Measure P1 Establish Local Manual Control of EFW Flow Applicant:

Examiner:

JOB PERFORMANCE MEASURE DATA PAGE Task: Establish local manual control of EFW flow.

Task Standard: Local Manual control of EFW 223A, Emergency Feedwater HDR A to SG1 Backup Flow Cntrl established and valve closed.

References:

OP-009-003, Emergency Feedwater Rev. 305 Alternate Path: No Time Critical: No Validation Time: 14 min.

Importance Rating K/A 061 K1.01 AFW and S/G system 4.1/4.1 RO / SRO Level NAO/RO/SRO Applicant:

Time Start: Time Finish:

Performance Time: minutes Critical Time: N/A minutes Performance Rating: SAT UNSAT Comments:

Examiner: Date:

Signature Revision 1 Page 2 of 7 2014 NRC Exam

EXAMINER COPY ONLY Tools/Equipment/Procedures Needed:

OP-009-003, Emergency Feedwater (Handout 1)

==

Description:==

The task takes place during a simulated station blackout with depleting station batteries. This requires the applicant to simulate securing Emergency Feedwater flow manually. This JPM takes place in a location with numerous pipes and supports that are bump hazards, but no special PPE will be required for this task. There are no special radiological requirements to perform this task.

When performing JPM validation, actions are necessary to ensure exam security is maintained.

Prior to commencing in plant JPM validation, contact Health Physics and direct them to disable all cameras in the CAA in a manner that prevents anyone from viewing any of the CAA cameras.

After all in plant JPMs are complete, contact Health Physics to restore the disabled cameras.

DIRECTIONS TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. All steps for this JPM will be simulated; do not manipulate any plant components. Make all necessary communications to me. I will provide initiating cues and reports on other actions when directed by you. Indicate to me when you understand your assigned task.

Read the Initial Condition and Cues from the Applicant Cue Sheet, and then give the cue sheet and procedure to the applicant.

Revision 1 Page 3 of 7 2014 NRC Exam

TASK ELEMENT 1 STANDARD 8.5 LOCAL OPERATION OF EFW FLOW CONTROL VALVES 8.5.1 If local operation of an Emergency Feedwater (EFW) Flow Control Proceeded to Attachment Valve is required, then perform this operation in accordance with 11.4 1.4, Local Operation of EFW Flow Control Valves.

Comment:

SAT / UNSAT TASK ELEMENT 2 STANDARD CAUTION - THE FOLLOWING SECTION HAS THE POTENTIAL TO Caution acknowledged AFFECT CORE REACTIVITY Comment:

SAT / UNSAT EXAMINER NOTE The following table is located under step 11.4.6 of Attachment 11.4 and applies to TASK ELEMENT 3 PERFORMED IV BY COMPONENT REQUIRED BY COMPONENT DESCRIPTION LOCATION (INITIAL /

NUMBER POSITION (INITIAL /

DATE)

EMERGENCY CLOSED RB +46 COL FEEDWATER HDR A TO (HANDWHEEL EFW-223A 3 A&L EL SG1 BACKUP FLOW LOCKED IN

+56 CNTRL NEUTRAL)

EMERGENCY CLOSED RB +46 COL FEEDWATER HDR A TO (HANDWHEEL EFW-224A 3 A&N EL SG1 PRIMARY FLOW LOCKED IN

+48 CNTRL NEUTRAL)

EMERGENCY CLOSED RB +46 COL FEEDWATER HDR B TO (HANDWHEEL EFW-223B 11 A&N EL SG2 BACKUP FLOW LOCKED IN

+56 CNTRL NEUTRAL)

EMERGENCY CLOSED RB +46 COL FEEDWATER HDR B TO (HANDWHEEL EFW-224B 11 A&N EL SG2 PRIMARY FLOW LOCKED IN

+48 CNTRL NEUTRAL)

Revision 1 Page 4 of 7 2014 NRC Exam

TASK ELEMENT 3 STANDARD 11.4.1 Unlock the handwheel for the EFW Flow Control Valve selected Handwheel unlocked from below. EFW-223A Comment: Critical EXAMINER CUE: Provide indication that lock has been unlocked SAT / UNSAT EXAMINER NOTE The following table is located under step 11.4.8 of Attachment 11.4 and applies to TASK ELEMENT 4 PERFORMED IV BY COMPONENT REQUIRED BY COMPONENT DESCRIPTION LOCATION (INITIAL /

NUMBER POSITION (INITIAL /

DATE)

RAB +46 NG/IA ISOLATION TO COL 11 NG-927A OPEN EFW-224B AZ&M EL

+52 RAB +46 NG/IA ISOLATION TO COL 11 NG-928B OPEN EFW-223B AZ&M EL

+52 RAB +46 NG/IA ISOLATION TO COL 2 NG-827B OPEN EFW-223A AZ&M EL +52 RAB +46 NG/IS ISOLATION TO COL 2 NG-828B OPEN EFW-224A AZ&M EL +52 TASK ELEMENT 4 STANDARD 11.4.2 Close the Nitrogen/Instrument Air supply to the selected EFW NG-827B is closed Flow Control Valve.

Comment: Critical EXAMINER CUE: When Applicant simulates closing NG-827B by rotating handwheel in the clockwise direction, inform Applicant that SAT / UNSAT the handwheel will no longer rotate in the clockwise direction.

Revision 1 Page 5 of 7 2014 NRC Exam

TASK ELEMENT 5 STANDARD 11.4.3 Bleed off air supply line to the selected EFW Flow Control Valve Petcock opened using the air regulator petcock.

Comment: Critical EXAMINER CUE: When applicant has simulated opening the petcock by rotating the petcock in the counter-clockwise direction, inform SAT / UNSAT the applicant that a hissing sound was heard and now that sound has diminished and stopped. The regulator pressure gage reads 0 psig.

TASK ELEMENT 6 STANDARD 11.4.4 Manually operate the selected EFW Flow Control Valve EFW-223A is closed handwheel to achieve the desired EFW flowrate.

Comment: Critical EXAMINER CUE:

SAT / UNSAT If valve position is checked, Show initial indication that valve is currently at the top solid line. (corresponds to full open)

When applicant simulates closing valve by rotating handwheel in the clockwise direction, provide cue that the handwheel will no longer rotate in the clockwise direction.

If applicant states that he will look at the position indicator, provide a cue by showing valve position closed on valve position indicator (bottom solid line).

END OF TASK Revision 1 Page 6 of 7 2014 NRC Exam

APPLICANT CUE SHEET Do Not Manipulate Any Plant Components (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

The plant has experienced a Station Blackout The A & B Train Battery voltages are degrading rapidly Emergency Feedwater (EFW) Pump AB is operating The Control Room can no longer control EFW from CP-8 controllers You have a set of operations keys INITIATING CUES:

The CRS directs you to take manual control of EFW 223A, Emergency Feedwater HDR A to SG1 Backup Flow Cntrl and close the valve IAW OP-009-003 Section 8.5.

Revision 1 Page 7 of 7 2014 NRC Exam

Waterford 3 2014 NRC Exam Job Performance Measure P2 SUPS 014 AB Operation Applicant:

Examiner:

JOB PERFORMANCE MEASURE DATA PAGE Task: Transfer SUPS 014 AB from Alternate to Normal AC power Task Standard: SUPS 014 AB was transferred from Alternate to Normal AC alignment in accordance with OP-006-005, Inverters and Distribution.

References:

OP-006-005, Inverters and Distribution Rev. 308 Alternate Path: Yes Time Critical: No Validation Time: 18 min.

Importance Rating K/A 062 A3.04, Operation of inverter 2.7 / 2.9 RO / SRO Level: NAO/RO/SRO Applicant:

Time Start: Time Finish:

Performance Time: minutes Critical Time: N/A minutes Performance Rating: SAT UNSAT Comments:

Examiner: Date:

Signature Revision 2 Page 2 of 11 2014 NRC Exam

EXAMINER COPY ONLY Tools/Equipment/Procedures Needed:

OP-006-005, Inverters and Distribution (Handout 1)

==

Description:==

SUPS 014 AB will be simulated in the Alternate AC power alignment. Applicant will transfer SUPS 014 AB to the Normal AC alignment. All steps will be simulated in Switchgear Room A. No special PPE will be required for this task.

There is a summary of the initial breaker positions and the initial meter readings before the task elements.

DIRECTION TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. All steps for this JPM will be simulated; do not manipulate any plant components. Make all necessary communications to me. I will provide initiating cues and reports on other actions when directed by you. Indicate to me when you understand your assigned task.

Read the Initial Condition and Cues from the Applicant Cue Sheet, and then give the cue sheet and procedure to the applicant.

Revision 2 Page 3 of 11 2014 NRC Exam

Revision 2 Page 4 of 11 2014 NRC Exam Indications METERS Item Designation Comment M1 Inverter Input Voltage Voltage reads zero until AC power is (0-150 VDC) applied to the rectifier at step 6.5.3.1.1.

M2 Inverter Input Current Current reads zero until AC power is (0-400 DC Amps) applied to the rectifier at step 6.5.3.1.1.

M3 Battery Current (400 amps Reads as displayed throughout discharge to 400 amps evolution.

charge)

M4 Battery Recharge Timer Reads as displayed throughout (0-30 Hours) evolution.

M5 AC Voltage (0-250 VAC) In the Inverter position, Voltage reads zero until step 6.5.3.9.

In the UPS position, voltage reads zero until step 6.5.3.4.

M6 Frequency (57-63 Hz) Frequency reads 60 (center) until step 6.5.3.9.

M7 UPS Output Current System load current reads zero until step (0-150 Amps AC) 6.5.3.6.

INDICATOR LIGHTS Item Designation Indication I-1 Inverter Phase Locked Illuminates at step 6.5.3.9.

I-2 High-Low DC Voltage Illuminated at the start of the JPM, clears at step 6.5.3.1.

I-3 Inverter Output Overload Remains OFF during JPM.

I-4 Over temperature Remains OFF during JPM.

I-5 Static Switch Inhibited Illuminated at the start of the JPM, clears at step 6.5.3.3.

I-6 Static Switch On Reserve Clear at the start of the JPM, illuminates at step 6.5.3.4.

Revision 2 Page 5 of 11 2014 NRC Exam

TASK ELEMENT 1 STANDARD 6.5.3 Transfer SUPS 014AB from Alternate to Normal AC Power as follows:

Breaker ID-EBKR9335-1 is 6.5.3.1 If SUPS 014AB inverter has been isolated in accordance with step ON.

6.5.2.7,then perform the following:

6.5.3.1.1 Place Normal Feeder breaker, ID-EBKR9335-1 to ON.

Comment: Critical EXAMINER CUE: Breaker will be OFF on arrival, provide cue of breaker being moved from OFF to ON. SAT / UNSAT EXAMINER NOTE: Meters M1 (Inverter Input Voltage) move to read as is after this step is performed and M2 (Inverter Input Current) reads zero.

EXAMINER NOTE: Indicating light I-2 (High-Low DC Voltage) extinguishes after this step is performed TASK ELEMENT 2 STANDARD 6.5.3.1.2 Verify Inverter Input Voltage > 121 VDC, then place Emergency Breaker ID-EBKR9335-2 is Feeder breaker, ID-EBKR9335-2 to ON. ON.

Comment: Critical EXAMINER CUE: When meter checked Inverter Voltage reads as you see it. SAT / UNSAT EXAMINER CUE: Breaker will be OFF on arrival, provide cue of breaker being moved from OFF to ON.

TASK ELEMENT 3 STANDARD Pushbutton is pressed and 6.5.3.1.3 Depress and release Inverter Operate pushbutton.

released.

Comment: Critical EXAMINER CUE: Pushbutton moved in when depressed and popped out when released. SAT / UNSAT TASK ELEMENT 4 STANDARD 6.5.3.2 Verify SUPS 014AB Static Switch Retransfer toggle switch in Verification complete.

INHIBIT.

Comment:

EXAMINER CUE: The Static Switch Retransfer toggle switch will be in INHIBIT on arrival. SAT / UNSAT Revision 2 Page 6 of 11 2014 NRC Exam

TASK ELEMENT 5 STANDARD 6.5.3.3 Place SUPS 014AB Alternate Feeder breaker, ID-EBKR9335-3 to Breaker ID-EBKR9335-3 is ON. ON.

Comment: Critical EXAMINER CUE: Breaker will be OFF on arrival, provide cue of breaker being moved from OFF to ON. SAT / UNSAT EXAMINER NOTE: Indicating light I-5 (Static Switch Inhibited) light goes OFF after this step is performed.

TASK ELEMENT 6 STANDARD 6.5.3.4 Depress and release SUPS 014AB Static Switch Transfer Test Test pushbutton depressed pushbutton. and released.

Comment: Critical EXAMINER CUE: Pushbutton moved in when depressed and popped out when released. SAT / UNSAT EXAMINER NOTE: Indicating light I-6 (Static Switch On Reserve) light illuminates after this step is performed.

TASK ELEMENT 7 STANDARD 6.5.3.4.1 Verify Static Switch On Reserve light Illuminates. Verification complete.

Comment:

EXAMINER CUE: The Static Switch On Reserve light is illuminated.

SAT / UNSAT TASK ELEMENT 8 STANDARD Pushbutton depressed and 6.5.3.5 Depress and release SUPS 014AB Lamp Test/Reset pushbutton.

released.

Comment: Critical EXAMINER CUE: Pushbutton moved in when depressed and popped out when released. SAT / UNSAT Revision 2 Page 7 of 11 2014 NRC Exam

TASK ELEMENT 9 STANDARD 6.5.3.5.1 Verify Static Switch On Reserve light remains Illuminated. Verification complete.

Comment:

EXAMINER CUE: The Static Switch On Reserve light is illuminated.

SAT / UNSAT TASK ELEMENT 10 STANDARD 6.5.3.6 Place SUPS 014AB Output To PDP014AB, ID-EBKR9335-4 Breaker ID-EBKR9335-4 is breaker to ON. ON.

Comment: Critical EXAMINER CUE: Breaker will be OFF on arrival, provide cue of breaker being moved from OFF to ON. SAT / UNSAT TASK ELEMENT 11 STANDARD Breaker ID-EBKR9335-5 is 6.5.3.7 Place SUPS 014AB Bypass breaker, ID-EBKR9335-5 to OFF.

OFF.

Comment: Critical EXAMINER CUE: Breaker will be ON on arrival, provide cue of breaker being moved from ON to OFF. SAT / UNSAT TASK ELEMENT 12 STANDARD Select Switch is verified in 6.5.3.8 Place SUPS 014AB AC Voltage Select Switch to INVERTER.

INVERTER.

Comment:

EXAMINER CUE: AC Voltage Select Switch is in INVERTER SAT / UNSAT EXAMINER NOTE: The AC Voltage Select Switch could be in what ever position the last watch stander left it in.

Revision 2 Page 8 of 11 2014 NRC Exam

EXAMINER NOTE Step 6.5.3.9 has been broken up into 2 task elements (13, 14) for clarity with providing cues.

When applicant observes the SUPS Output Voltage meter, provide indication of zero volts.

If the applicant presses the Operate pushbutton, provide the indications provided in Task Element 14.

If the applicant does not press the Operate pushbutton, then provide the indication that the Static Switch On Reserve light is still illuminated at Task Element 17.

TASK ELEMENT 13 STANDARD 6.5.3.9 If no voltage is indicated, then depress and release SUPS 014AB Inverter Operate pushbutton, and verify the following:

Inverter Phase Locked light Illuminated Prior to pushing the operate Inverter Output voltage CN ~120 VAC (118.8 to 121.2 VAC) pushbutton, observed no Inverter Output voltage AN ~120 VAC (118.8 to 121.2 VAC) voltage in any Inverter Inverter Output voltage BN ~120 VAC (118.8 to 121.2 VAC) position Inverter Output frequency ~60 Hz (59.97 to 60.03 Hz)

Comment:

EXAMINER NOTE: Alternate Path Begins Here SAT / UNSAT EXAMINER NOTE: The applicant must use the multi-selector switch and move through these positions.

EXAMINER CUE: There is no voltage indicated in any Inverter position.

TASK ELEMENT 14 STANDARD 6.5.3.9 If no voltage is indicated, then depress and release SUPS 014AB Pressed and released the Inverter Operate pushbutton, and verify the following: Operate pushbutton.

Comment: Critical EXAMINER CUE: Pushbutton moved in when depressed and popped out when released. SAT / UNSAT EXAMINER CUE: If the applicant observes any UPS position, voltage will be 120 VAC.

Revision 2 Page 9 of 11 2014 NRC Exam

TASK ELEMENT 15 STANDARD 6.5.3.10 Place SUPS 014AB Static Switch Retransfer toggle switch to Toggle Switch is in Auto.

AUTO.

Comment: Critical EXAMINER CUE: Static Switch Retransfer toggle switch will be in INHIBIT at this point, cue that the switch is moved from INHIBIT to SAT / UNSAT AUTO.

TASK ELEMENT 16 STANDARD 6.5.3.11 After approximately 30 seconds, depress and release SUPS Pushbutton pressed and 014AB Lamp Test/Reset pushbutton. released.

Comment: Critical EXAMINER CUE: 30 seconds have elapsed. After this pushbutton is depressed, the Static Switch On Reserve light will extinguish. SAT / UNSAT TASK ELEMENT 17 STANDARD 6.5.3.11.1 Verify Static Switch On Reserve light Extinguished. Verification complete.

Comment:

EXAMINER CUE: Provide indication that the Static Switch On Reserve light is extinguished. SAT / UNSAT END OF TASK Revision 2 Page 10 of 11 2014 NRC Exam

APPLICANT CUE SHEET Do Not Manipulate Any Plant Components (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

SUPS 014 AB is in the Alternate AC alignment The inverter was isolated in accordance with OP-006-005, Inverters and Distribution, step 6.5.2.7.

INITIATING CUES:

The CRS directs you to place SUPS 014 AB in the Normal AC alignment in accordance with OP-006-005, Inverters and Distribution, section 6.5.3.

Revision 2 Page 11 of 11 2014 NRC Exam

Waterford 3 2014 NRC Exam Job Performance Measure P3 Restore SFP Cooling Pumps from EDG Applicant:

Examiner:

JOB PERFORMANCE MEASURE DATA PAGE Task: Restore Spent Fuel Cooling Pump to Operation via EDG.

Task Standard: Perform correct breaker and valve alignment and contact the control room to have the Spent Fuel Pool Cooling Pump started

References:

OP-901-513, Spent Fuel Pool Cooling Malfunction Rev. 009 OP-006-001, Plant Distribution (7KV, 4KV, SSD) System Rev. 313 Alternate Path: No Time Critical: No Validation Time: 14 min.

Importance Rating K/A 033 K3.03 Spent fuel temperature 3.0/3.3 RO / SRO Level NAO/RO/SRO Applicant:

Time Start: Time Finish:

Performance Time: minutes Critical Time: N/A minutes Performance Rating: SAT UNSAT Comments:

Examiner: Date:

Signature Revision 0 Page 2 of 8 2014 NRC Exam

EXAMINER COPY ONLY Tools/Equipment/Procedures Needed:

OP-901-513, Spent Fuel Pool Cooling Malfunction (Handout 1)

==

Description:==

The task takes place during a simulated loss of offsite power with both EDGs supplying their respective electrical busses. The applicant will be directed to restore Spent Fuel Pool Cooling flow via the EDG locally. This requires the applicant to simulate stripping loads from the non-safety related portion of MCC-314 and reenergize the bus. The applicant will then close the breaker for the Spent Fuel Pool Cooling Pump. The applicant will then throttle down on the discharge valve of the pump to be started and then contact the control room to start the Spent Fuel Pool Cooling Pump.

This JPM takes place in a location with numerous pipes and supports that are bump hazards, but no special PPE will be required for this task. This task will be performed inside the RCA and RWP requirements apply.

When performing JPM validation, actions are necessary to ensure exam security is maintained.

Prior to commencing in plant JPM validation, contact Health Physics and direct them to disable all cameras in the CAA in a manner that prevents anyone from viewing any of the CAA cameras.

After all in plant JPMs are complete, contact Health Physics to restore the disabled cameras.

DIRECTIONS TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. All steps for this JPM will be simulated; do not manipulate any plant components. Make all necessary communications to me. I will provide initiating cues and reports on other actions when directed by you. Indicate to me when you understand your assigned task.

Read the Initial Condition and Cues from the Applicant Cue Sheet, and then give the cue sheet and procedure to the applicant.

Revision 0 Page 3 of 8 2014 NRC Exam

TASK ELEMENT 1 STANDARD Procedure Note: If this attachment is being performed concurrently with OP-901-502, Evacuation of the Control Room & Subsequent Plant Shutdown, then assistance will be required from the Technical Support Note Reviewed Center (TSC) to install a jumper between terminals 5 & 6 to bypass the 42 contact for the Spent Fuel Pool Cooling Pump being started. Refer to CWD B424-634 (A Train) or B424-635 (B Train).

Comment:

SAT / UNSAT TASK ELEMENT 2 STANDARD 1.0 Restore SFP Cooling Pump A to service from EDG A as follows:

MCC-314A checked 1.1 If MCC-314A is energized and the MCC-314A Safety to energized and SSD-EBKR-Nonsafety Tie, SSD-EBKR-314A-2M, is Open, then perform the 314A-2M checked Open following:

Comment:

EXAMINER NOTE: MCC-314A is energized upon arrival and EBKR-314A-2M is open upon arrival SAT / UNSAT EXAMINER CUE: Provide indication that EBKR-314A-2M is open TASK ELEMENT 3 STANDARD Determined sequencer 1.1.1 Verify EDG A Sequencer has timed out.

timed out Comment:

EXAMINER CUE: If contacted as the control room, provide report that the EDG A sequencer has timed out SAT / UNSAT Revision 0 Page 4 of 8 2014 NRC Exam

EXAMINER NOTE The following table describes as found breaker positions and position required by applicant. This applies to task element 4. The applicant should not open any safety related breakers on this bus.

Component number Component Description As Found Required position LTN-EBKR-314A-3BL Lighting Panel 349 FHB +46 Fuel Pool ON OFF Underwater Ltg FHS-EBKR-314A-3BR New Fuel Elevator Supply Breaker OFF SSD-EBKR-314A-4BL Fhb Receptacles F1A To F4A ON OFF ACC-EBKR-314A-4BR Wet Cooling Tower A Basin Filtration ON OFF SP-EBKR-314A-4F West Dry Cooling Tower Sump Pump A ON OFF SP-EBKR-314A-4H Fuel Handling Building Sump Pump A ON OFF HVF-EBKR-314A-4M Fhb Normal Exhaust Fan A ON OFF FHS-EBKR-314A-5BL Spent Fuel Handling Supply Breaker LOCKED OFF FHS-EBKR-314A-5BR SFHM Upender OFF FS-EBKR-314A-5D Fuel Pool Purification Pump OFF SP-EBKR-314A-5F East Dry Cooling Tower Sump Pump A ON OFF HVF-EBKR-314A-5HL Fhb HVAC Room Heater ON OFF FS-EBKR-314A-5M Fuel Pool Pump A ON OFF CRN-EBKR-314A-6C Fuel Handling Building Crane ON OFF TASK ELEMENT 4 STANDARD 1.1.2 Open ALL MCC-314A Nonsafety load breakers. Listed breakers opened Comment: Critical EXAMINER CUE: When Applicant simulates placing selected breakers to OFF, provide cue that the breakers have been placed SAT / UNSAT from on to off.

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TASK ELEMENT 5 STANDARD SSD-EBKR-314A-2M is 1.1.3 Close SSD-EBKR-314A-2M, MCC314A Safety to Nonsafety Tie.

closed Comment: Critical EXAMINER NOTE: This breaker may be closed by either holding down the close pushbutton or by lifting up on the metal latch on the front of the SAT / UNSAT breaker cubicle.

EXAMINER CUE: If asked, provide indication that the spring status indicates charged EXAMINER CUE: When applicant has simulated closing breaker SSD-EBKR-314A-2M provide indication that breaker has gone from open to close.

TASK ELEMENT 6 STANDARD FS-EBKR-314A-5M is 1.2 Close FS-EBKR-314A-5M, Fuel Pool Pump A.

closed Comment: Critical EXAMINER CUE: When applicant has simulated closing breaker FS-EBKR-314A-5M provide indication that breaker has gone from OFF to SAT / UNSAT ON.

TASK ELEMENT 7 STANDARD 1.3 Throttle FS-106A, Fuel Pool Pump A Discharge Header Isol Valve, 12 Valve FS-106A throttled to turns open. 12 turns open Comment: Critical EXAMINER CUE: When applicant simulates turning valve FS-106A handwheel in the clockwise direction for several turns, provide cue SAT / UNSAT that the handwheel will no longer rotate.

When the applicant simulates turning valve FS-106A handwheel in the counter clockwise direction for 12 turns, provide cue that the valve handwheel has been turned 12 turns.

TASK ELEMENT 8 STANDARD 1.4 Start Spent Fuel Pool Cooling Pump A. Contacted Control Room Comment: Critical EXAMINER CUE: Respond as control room and report that the requested SFPC pump is running. SAT / UNSAT Revision 0 Page 6 of 8 2014 NRC Exam

TASK ELEMENT 6 STANDARD 1.5 Open FS-106A, Fuel Pool Pump A Discharge Header Isol Valve. Valve FS-106A opened Comment: Critical EXAMINER CUE: When the applicant simulates turning valve FS-106A handwheel in the counter clockwise direction for several turns, SAT / UNSAT provide cue that the valve handwheel will no longer rotate.

END OF TASK Revision 0 Page 7 of 8 2014 NRC Exam

APPLICANT CUE SHEET Do Not Manipulate Any Plant Components (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

The plant has experienced a loss of offsite power Both Emergency Diesel Generators are supplying their respective busses Both EDG sequencers have timed out INITIATING CUES:

The CRS directs you to restore Spent Fuel Pool Cooling Pump A to operation from the A EDG IAW OP-901-513 Attachment 5.

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