ML13336A424

301 Final Administrative JPMs

ML13336A424
Person / Time
Site:	Catawba
Issue date:	11/26/2013
From:	Duke Energy Carolinas
To:	NRC/RGN-II
References
50-413/13-301, 50-414/13-301
Download: ML13336A424 (58)

Text

Catawba Nuclear Station RO/SRO JPM A.1

-1 Sep. 2013 NRC Exam PAGE 1 OF 18

JPM A.1-1 RO / SRO

Catawba Nuclear Station RO/SRO JPM A.1

-1 Sep. 2013 NRC Exam PAGE 2 OF 18 DATA SHEET Task: Perform a manual shutdown margin calculation (Unit at Power) per OP/0/A/6100/006 (Reactivity Balance Calculation)

Alternate Path:

N/A Facility JPM #:

RB-121 - Modified Safety Function:

N/A K/A G 2.1.2 5 Ability to interpret reference materials, such as graphs, curves, tables, etc.

. Importance:

3.9 / 4.2 CFR: 41.10 / 43.5 / 45 1.2 Preferred Evaluation Location:

Preferred Evaluation Method:

Simulator In-Plant Perform X Simulate References

OP/0/A/6100/006 (Reactivity Balance Calculation), Rev. 83 Unit 1 Reactor Operating Data Book (R.O.D.)

Task Standard:

Applicant determines that required shutdown margin is 1300 pcm and current shutdown margin is 1 3 2 1 pcm, and concludes that adequate shutdown margin does exist per the Unit 1 Core Operating Limits Report.

Validation Time:

25 minutes Time Critical:

Yes No X Applicant:

Time Start: ______

____ NAME___________________________

Docket #_______________

Time Finish: ________

__ Performance Rating:

SAT ____ UNSAT ____

Performance Time ___

__ Examiner: _____________________________

_____________________________/________

NAME SIGNATURE DATE ===========================================================================

COMMENTS PAGE 3 0F 18 Catawba Nuclear Station RO/SRO JPM A.1

-1 Sep. 2013 NRC Exam PAGE 3 OF 18 READ TO APPLICANT DIRECTION 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. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

You are the Unit 1 OATC. The Reactivity Computer (REACT) is out of

-service. Current plant conditions are:

Power level = 85%

NC Tavg = 581°F Boron concentration = 959 ppm Core burnup = 300 EFPD Shutdown rod bank position: 226 steps Control rod bank A is at 226 steps.

Control rod bank B is at 226 steps.

Control rod bank C is at 226 steps.

Control rod bank D is at 200 steps.

INITIATING CUES:

You have been informed by the Control Room SRO that the following rods are untrippable:

H-4 K-2 Perform a Shutdown Margin Calculation in accordance with OP/0/A/6100/006 (Reactivity Balance Calculation) and determine if Core Operating Limits Report requirement for shutdown margin is satisfied. Calculation verification is waived.

EXAMINER NOTE

Provide applicant a copy of OP/0/A/6100/006.

Catawba Nuclear Station RO/SRO JPM A.1

-1 Sep. 2013 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 4 0F 18 START TIME: _______

STEP 1: Applicant obtains a copy of OP/0/A/6100/006 (Reactivity Balance Calculation) and from initiating cue determines that Enclosure 4.3 is applicable

. STANDARD: Applicant obtains a copy of OP/0/A/6100/006 (Reactivity Balance Calculation

). EXAMINER NOTE

COMMENTS:

___ SAT

___ UNSAT STEP 2: Review Limits and Precautions of OP/0/A/6100/006

. STANDARD: Limits and Precautions have been reviewed.

EXAMINER NOTE

Applicant should determine from initial conditions that Tavg is within 1°F based on power level and Tref program.

COMMENTS:

___ SAT

___UNSAT

Catawba Nuclear Station RO/SRO JPM A.1

-1 Sep. 2013 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 5 0F 18 STEP 3: OP/0/A/6100/006 Encl. 3 Step 3.1 Determine the following information

STANDARD: Applicant records the following data using the initial conditions:

Unit: 1 ____ Date/Time: Current Date/Time

____ Present Power:

85% ____ NC System Boron Concentration 959 ppm ____ Current Burnup: 300 EFPD ____ Present control bank position: 200 SWD, Control Bank D ____ Present shutdown bank position: ALL @ 226 ____ Quantity of misaligned rods:

0 ____ Number of untrippable RCCA(s):

2 ____ Untrippable RCCA(s) core location(s):

H-4, K-2 ____ Critical Step to accurately record required data for subsequent critical calculation

s. EXAMINER NOTE

Examiner may also refer to KEY at end of this document.

COMMENTS:

CRITICAL STEP

___ SAT ___ UNSAT STEP 4: Encl. 4.3

- Step 3.3 (Step 3.2 is N/A due to REACT program being unavailable.)

IF performing the calculation manually, perform the following:

STANDARD: COMMENTS: ___ SAT ___ UNSAT

Catawba Nuclear Station RO/SRO JPM A.1

-1 Sep. 2013 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 6 0F 18 STEP 5: Encl. 4.3

- Step 3.3.1 Determine available reactivity worth of trippable RCCAs for conditions in Step 3.1:

NOTE: Interpolation is NOT required in Step 3.3.1.1. Reactivity worth may be determined by choosing the lowest reactivity worth from Section 5.7 of the R.O.D. Manual associated with cycle burnups that bound the present cycle burnup recorded in Step 3.1. (R.M.)

STANDARD: COMMENTS: ___ SAT ___ UNSAT STEP 6: Encl. 4.3

- Step 3.3.1.1 Determine Total Available Rod Worth:

__5086__ pcm (Section 5.7 of R.O.D. Manual)

STANDARD: Applicant records 5086 pcm bin Step 3.3.1.1 blank provided. Critical Step to determine Total Available Rod Worth

, which is a required value for a subsequent critical calculation for determining present shutdown margin.

COMMENTS:

CRITICAL STEP ___ SAT ___ UNSAT

Catawba Nuclear Station RO/SRO JPM A.1

-1 Sep. 2013 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 7 0F 18 STEP 7: Encl. 4.3

- Step 3.3.1.2 IF only one RCCA is untrippable, determine reactivity worth penalty for untrippable RCCA core location of Step 3.1.10.

STANDARD: Applicant determine s that Step 3.3.1.2 is N/A, based on more than one untrippable RCCA.

COMMENTS: ___ SAT ___ UNSAT STEP 8: Encl. 4.3

- Step 3.3.1.3 Item A IF there are multiple untrippable RCCAs, perform the following:

A. Determine untrippable RCCA of Step 3.1.10 with the highest reactivity worth penalty. (Section 5.8 of R.O.D. Manual)

STANDARD: Refers to Section 5.8 of the R.O.D. Manual. Determines RCCA H-4 rod worth is 343 pcm, and is the highest reactivity worth penalty.

Critical Step to determine rod with the highest reactivity worth , which is used in a subsequent critical calculation for determining present shutdown margin.

COMMENTS:

CRITICAL STEP ___ SAT ___ UNSAT

Catawba Nuclear Station RO/SRO JPM A.1

-1 Sep. 2013 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 8 0F 18 STEP 9: Encl. 4.3

- Step 3.3.1.3 Item B Record reactivity worth of the untrippable RCCA of Step 3.3.1.3.A. (Section 5.8 of R.O.D. Manual)

______ pcm STANDARD: Applicant determines value and records 343 p cm in Step 3.3.1.3.B blank provided. Critical Step to determine Highest Worth Penalty

, which is used in a subsequent critical calculation for determining present shutdown margin. COMMENTS: CRITICAL STEP ___ SAT ___ UNSAT STEP 1 0: Encl. 4.3

- Step 3.3.1.3 Item C Determine maximum stuck rod worth during cycle (Section 5.7 of the R.O

.D. Manual).

STANDARD: Applicant determines required value and records 1046 pcm in Step 3.3.1.3.C blank provided.

Critical Step to determine Maximum Stuck Rod Worth, which is used in a subsequent critical calculation for determining present shutdown margin.

COMMENTS:

CRITICAL STEP ___ SAT ___ UNSAT

Catawba Nuclear Station RO/SRO JPM A.1

-1 Sep. 2013 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 9 0F 18 STEP 1 1: Encl. 4.3 - Step 3.3.1.3 Item D Calculate total untrippable RCCA reactivity worth penalty below: STANDARD: Applicant records the following data in appropriate table locations. Refer to EXAM KEY, if desired.

Number of Untrippable RCCAs

2 ____ Highest Worth Penalty

343 pcm ____ Max Stuck Rod

1046 pcm ____ Total untrippable RCCA Worth Penalty for Multiple RCCAs:

1389 p c m ____

Critical Step to determine Total untrippable RCCA Worth Penalty for Multiple RCCAs, which is used in a subsequent critical calculation for determining present shutdown margin.

COMMENTS:

CRITICAL STEP ___ SAT ___ UNSAT

Catawba Nuclear Station RO/SRO JPM A.1

-1 Sep. 2013 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 10 0F 18 STEP 1 2: Encl. 4.3

- Step 3.3.1.4 Record Total Untrippable RCCA Penalty from Step 3.3.1.2 or Step 3.3.1.3.D, whichever is applicable.

STANDARD: Applicant records Total Untrippable RCCA Penalty as 1 389 pcm.

Examiner NOTE:

This step, although important, is not critical, since the value has been previously determined in Step 11 this JPM.

COMMENTS: ___ SAT ___ UNSAT

Catawba Nuclear Station RO/SRO JPM A.1

-1 Sep. 2013 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 11 0F 18 STEP 1 3: Encl. 4.3

- Step 3.3.1.5 Determine Inserted Rod Worth for present bank positions:

STANDARD: Applicant determines the required values from the table and records the following:

Item A.: 58 pcm ____ Item B.: SD E 0 pcm ____ SD D 0 pcm ____ SD C 0 pcm ____ SD B 0 pcm ____ SD A 0 pcm ____ Inserted Worth of Present Position:

58 pcm ____ Critical Step to determine Inserted Worth of Present Position, which is used in a subsequent critical calculation for determining present shutdown margin.

COMMENTS:

CRITICAL STEP ___ SAT ___ UNSAT

Catawba Nuclear Station RO/SRO JPM A.1

-1 Sep. 2013 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 12 0F 18 STEP 1 4: Encl. 4.3

- Step 3.3.1.6 Calculate available reactivity worth of trippable RCCAs

. STANDARD: Applicant determines the required values from the table and records the following:

Total Available Rod Worth

5086 pcm ____ Untrippable RCCAs Penalty 1389 pcm ____ Inerted Worth of Present Position 58 pcm ____ Available Reactivity Worth of Trippable RCCAs

3639 pcm ____

Critical Step to determine Available Reactivity Worth of Trippable RCCAs, which is used in a subsequent critical calculation for determining present shutdown margin.

COMMENTS:

CRITICAL STEP ___ SAT ___ UNSAT

Catawba Nuclear Station RO/SRO JPM A.1

-1 Sep. 2013 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 13 0F 18 STEP 1 5: Encl. 4.3

- Step 3.3.1.7 Calculate total misaligned RCCA reactivity worth below:

STANDARD: Applicant determines the required values from the table and records the following:

Quantity of Misaligned Rods

0 ____ Maximum Dropped or Misaligned Rod Worth 200 pcm ____ Total misaligned RCCA Reactivity Worth 0 pcm ____

Critical Step to determine Total Misaligned RCCA Reactivity Worth, which is used in a subsequent critical calculation for determining present shutdown margin.

COMMENTS:

CRITICAL STEP ___ SAT ___ UNSAT

Catawba Nuclear Station RO/SRO JPM A.1

-1 Sep. 2013 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 14 0F 18 STEP 1 6: Encl. 4.3

- Step 3.3.2 Calculate SDM for present conditions:

STANDARD: Applicant determines the required values from the table and records the following:

Available reactivity worth of Trippable RCCAs 3639 pcm ____ Total misaligned RCCA reactivity Worth 0 pcm ____ Total Power Defect at present thermal power (Step 3.1.3) and current cycle burnup (Step 3.1.5) 1808 pcm ____ Transient Flux Redistribution Allowance 510 ____ Present SDM 1321 pcm ____ Critical Step to determine Present Shutdown Margin. This value is used to compare with the COLR requirement to detemine if present shutdown margin meets the requirements of the COLR.

COMMENTS:

CRITICAL STEP ___ SAT ___ UNSAT

Catawba Nuclear Station RO/SRO JPM A.1

-1 Sep. 2013 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 15 0F 18 STEP 1 7: Encl. 4.3

- Step 3.3.3 Sign below to document performance:

Performed by ________________________ Date/Time _____ / _____

STANDARD: Applicant signs applicable line to document performance.

COMMENTS: ___ SAT ___ UNSAT STEP 1 8: Encl. 4.3

- Step 3.3.4 Ensure that an independent calculation per this enclosure has been separately performed.

STANDARD: Applicant ensures an independent calculation has been separately performed.

EXAMINER CUE: "An independent calculation per this enclosure has been performed."

COMMENTS:

___ SAT ___ UNSAT

Catawba Nuclear Station RO/SRO JPM A.1

-1 Sep. 2013 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 16 0F 18 STEP 1 9: Encl. 4.3

- Step 3.3.5 Verify that both performances of this enclosure yield equivalent results. STANDARD: Applicant verifies that both performances of this enclosure have yielded equivalent results.

EXAMINER CUE: "Both performances of this enclosure have yielded equivalent results

."

COMMENTS:

___ SAT ___ UNSAT

Catawba Nuclear Station RO/SRO JPM A.1

-1 Sep. 2013 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 17 0F 18 STEP 20: Encl. 4.3

- Step 3.3.6 STANDARD: Applicant determines that adequate shutdown DOES exist since actual is 1321 pcm and the COLR requirement is 1300 pcm. EXAMINER CUE: "Another operator will take actions and complete the procedure." This step is critical to in order to meet the Task Standard: determine that present shutdown margin DOES exist.

COMMENTS: END OF TASK CRITICAL STEP ___ SAT ___ UNSAT

STOP TIME ________

APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

Catawba 2013 NRC Exam

- RO/SRO JPM A.1

-1 READ TO APPLICANT DIRECTION 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. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you. INITIAL CONDITIONS:

You are the Unit 1 OATC. The Reactivity Computer (REACT) is out of

-service. Current plant conditions are:

Power level = 85%

NC Tavg = 581°F Boron concentration = 959 ppm Core burnup = 300 EFPD Shutdown rod bank position: 226 steps Control rod bank A is at 226 steps.

Control rod bank B is at 226 steps.

Control rod bank C is at 226 steps.

Control rod bank D is at 200 steps.

INITIATING CUES:

You have been informed by the Control Room SRO that the following rods are untrippable:

H-4 K-2 Perform a Shutdown Margin Calculation in accordance with OP/0/A/6100/006 (Reactivity Balance Calculation) and determine if Core Operating Limits Report requirement for shutdown margin is satisfied. Calculation verification is waived

.

Catawba Nuclear Station RO/SRO JPM A

.1-2 Sep. 2013 NRC Exam PAGE 1 OF 11

JPM A.1-2 RO / SRO

Catawba Nuclear Station RO/SRO JPM A

.1-2 Sep. 2013 NRC Exam PAGE 2 OF 11 DATA SHEET Task: Calculate Unit Vent flow manually per PT/1/A/4450/017 (Unit Vent Flow Manual Calculation).

Alternate Path: N/A Facility JPM #:

WG-002 Safety Function:

N/A K/A G 2.1.2 3 Ability to perform specific system and integrated plant procedures during all modes of plant operation.

Importance:

4.3 / 4.4 CFR: 41.10 / 43.5 / 45.2 / 45.6 Preferred Evaluation Location:

Preferred Evaluation Method:

Simulator X In-Plant Perform X Simulate References

PT/1/A/4450/017 (Unit Vent Flow Manual Calculation) Rev 013 SLC 16.11-7 (Radioactive Gaseous Effluent Monitoring Instrumentation

) Task Standard: Unit Vent flow is calculated to be 117450 scfm +/

- 1000. Validation Time:

15 minutes Time Critical:

Yes No X Applicant:

Time Start: ______

____ NAME___________________________

Docket #_______________

Time Finish: ________

__ Performance Rating:

SAT ____ UNSAT ____

Performance Time ___

__ Examiner: _____________________________

_____________________________/________

NAME SIGNATURE DATE ===========================================================================

COMMENTS Catawba Nuclear Station RO/SRO JPM A

.1-2 Sep. 2013 NRC Exam PAGE 3 OF 11 SIMULATOR OPERATOR INSTRUCTIONS:

1. ENSURE NRC Examination Security has been established.

2. Reset to IC

1. 168 3. Enter the password.

4. Select "Yes" on the INITIAL CONDITION RESET pop

-up window.

5. Ensure simulator setup per table below.

6. Place simulator in RUN and acknowledge any alarms.

7. ENSURE "Extra Operator" is present in the simulator.

8. Place simulator in FREEZE and maintain in FREEZE unless instructed by NRC Examiner to place in RUN

. 9. May need a footstool for applicants to access and read VA system flow indicator.

Instructor Action Final Delay Ramp Delete In Event XMT-VA001 (FVA_5280 ABFXU

-1 AIR FLOW MTR) 56000 XMT-VA002 (FVF_5310 OUTLET AIRFLOW TRN A MTR) 0 Place OOS sticker on 1VFP5310 (VF OTLT AIR FLOW TRN A)

PAGE 4 0F 11 Catawba Nuclear Station RO/SRO JPM A

.1-2 Sep. 2013 NRC Exam PAGE 4 OF 11 READ TO APPLICANT DIRECTION 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. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

Both Units are at 100% power.

No VQ release is in progress.

No GWRs are in progress.

The Waste Evaporator and Recycle Evaporator are secured.

The Unit Vent Stack Flow Rate Meter is INOPERABLE

. Auxiliary Building NLO has called the control room to report 1ABUXF Discharge Air Flow (1ABUX-AFMD-1) is reading 27000 scfm.

INITIATING CUES:

Calculate Unit Vent flow per PT/1/A/4450/017 (Unit Vent Flow Manual Calculation) Enclosure 13.1.

EXAMINER NOTE

Provide the applicant with a copy of PT/1/A/4450/017

.

Catawba Nuclear Station RO/SRO JPM A

.1-2 Sep. 2013 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 5 0F 11 START TIME: _______

STEP 1: Applicant locates and records VA (Auxiliary Building Ventilation)

System flow.

STANDARD: Applicant locates 1VAP5280 on 1MC

-3 and records 56, 500 scfm. Critical Step to obtain VA (Auxiliary Building Ventilation) flow required to complete the calculation.

EXAMINER NOTE: Range of 55000 to 57000 scfm is acceptable.

COMMENTS:

CRITICAL STEP

___ SAT

___ UNSAT STEP 2: Applicant locates and records VE (Annulus Ventilation) 1A flow to stack. STANDARD: Applicant locates 1VEP5180, notes VE (Annulus Ventilation) train 1A is shutdown and records 0 scfm. Critical Step to obtain 1A Train Annulus Ventilation Flow required to complete the calculation.

COMMENTS:

CRITICAL STEP ___ SAT

___UNSAT

Catawba Nuclear Station RO/SRO JPM A

.1-2 Sep. 2013 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 6 0F 11 STEP 3: Applicant locates and records VE (Annulus Ventilation) 1B flow to stack. STANDARD: Applicant locates 1VEP5200, notes VE (Annulus Ventilation) train 1B is shutdown and records 0 scfm. Critical Step to obtain 1B Train Annulus Ventilation Flow required to complete the calculation.

COMMENTS:

CRITICAL STEP

___ SAT ___ UNSAT STEP 4: Applicant locates and records VF (Fuel Pool Ventilation) 1A flow to stack. STANDARD: Applicant locates 1VFP5310, notes VF (Fuel Pool Ventilation) reading is OOS and uses 33130 scfm from enclosure 13.2.

This step is critical to ensure the correct value is included in the calculation.

COMMENTS:

CRITICAL STEP ___ SAT ___ UNSAT

Catawba Nuclear Station RO/SRO JPM A

.1-2 Sep. 2013 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 7 0F 11 STEP 5: Applicant locates and records VF (Fuel Pool Ventilation) 1B flow to stack. STANDARD: Applicant locates 1VFP5340, notes VF (Fuel Pool Ventilation) train 1B is shutdown and records 0 scfm. Critical Step to obtain 1B Train Fuel Pool Ventilation Flow required to complete the calculation.

COMMENTS: CRITICAL STEP ___ SAT ___ UNSAT STEP 6: Applicant records 1ABUX

-AFMD-1 flow. STANDARD: Applicant records 27000 scfm based on initial cue.

Critical Step to ensure the value is used in the calculation.

COMMENTS: CRITICAL STEP ___ SAT ___ UNSAT

Catawba Nuclear Station RO/SRO JPM A

.1-2 Sep. 2013 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 8 0F 11 STEP 7: Applicant records VP (Containment Purge) flows. STANDARD: Based on initial cues VP (Containment Purge) is secured. Applicant records flow as 0 scfm or N/A

. Critical Step to obtain Containment Purge Flows required to complete the calculation.

COMMENTS: CRITICAL STEP ___ SAT ___ UNSAT STEP 8: Applicant records WG (Waste Gas) flow and VQ (Containment Air Release and Addition) flow. STANDARD: Based on initial cues, applicant records flow as 0 scfm or N/A

. Critical Step to obtain Waste Gas Flow and Containment Air Release Flow required to complete the calculation.

COMMENTS: CRITICAL STEP ___ SAT ___ UNSAT STEP 9: Applicant records TL (Main Turbine Seals) flow STANDARD: Based on initial cue and procedure notes, applicant records 1260 scfm. Critical Step to obtain Main Turbine Seals flow required to complete the calculation.

COMMENTS:

CRITICAL STEP ___ SAT ___ UNSAT

Catawba Nuclear Station RO/SRO JPM A

.1-2 Sep. 2013 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 9 0F 11 STEP 1 0: Applicant records NB (Reactor Makeup) and WL (Liquid Waste) flows. STANDARD: Based on initial cues, applicant records flow as 0 scfm or N/A.

Critical Step to obtain Reactor Makeup and Liquid Waste flows required to complete the calculation.

COMMENTS: CRITICAL STEP

___ SAT ___ UNSAT STEP 1 1: Applicant records ZJ (Condensate Steam Air Ejectors) flow to stack. STANDARD: Based on initial cue and procedure notes, applicant records 60 scfm. Critical Step obtain Condensate Steam Air Ejectors flow required to complete the calculation.

COMMENTS:

CRITICAL STEP ___ SAT ___ UNSAT

Catawba Nuclear Station RO/SRO JPM A

.1-2 Sep. 2013 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 10 0F 11 STEP 1 2: Calculate total vent flow.

STANDARD: Applicant calculates total vent flow to stack as 117450 scfm.

EXAMINER NOTE

Due to reading instruments, 116450 -118450 scfm is considered acceptable.

This step is critical to calculate total vent flow.

EXAMINER CUE:

"Another operator will continue with the PT." COMMENTS: END OF TASK CRITICAL STEP ___ SAT ___ UNSAT STOP TIME ________

APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

Catawba 2013 NRC Exam

- RO/SRO JPM A

.1-2 READ TO APPLICANT DIRECTION 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. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you. INITIAL CONDITIONS:

Both Units are at 100% power.

No VQ release is in progress.

No GWRs are in progress.

The Waste Evaporator and Recycle Evaporator are secured.

The Unit Vent Stack Flow Rate Meter is INOPERABLE

. Auxiliary Building NLO has called the control room to report 1ABUXF Discharge Air Flow (1ABUX

-AFMD-1) is reading 27000 scfm.

INITIATING CUES:

Provide the applicant with a copy of PT/1/A/4450/017

.

Catawba Nuclear Station RO-SRO JPM A.2 Sep. 2013 NRC Exam PAGE 1 OF 7 JPM A.2 RO-SRO

Catawba Nuclear Station RO-SRO JPM A.2 Sep. 2013 NRC Exam PAGE 2 OF 7 DATA SHEET Task: Classify a D/G Start and Complete a Logbook Entry Alternate Path:

N/A Facility JPM #:

DG3-010 Safety Function:

N/A K/A 2.2.12 Knowledge of surveillance procedures.

Importance:

3.7 / 4.1 CFR: 41.10 / 45.13 Preferred Evaluation Location:

Preferred Evaluation Method:

Simulator Classroom X Perform X Simulate References

OMP 2-28 (Diesel Generator Logbook) rev 026 PT/2/A/4350/002 B, (Diesel Generator 2B Operability Test), Rev. 101 Task Standard:

Classify the D/G start as a VALID FAILURE and correctly enter data into the logbook. Validation Time:

14 minutes Time Critical: Yes No X Applicant:

Time Start: ______

____ NAME___________________________

Docket #_______________

Time Finish: ________

__ Performance Rating:

SAT ____ UNSAT ____

Performance Time ___

__ Examiner: _____________________________

_____________________________/________

NAME SIGNATURE DATE ===========================================================================

COMMENTS PAGE 3 0F 7 Catawba Nuclear Station RO-SRO JPM A.2 Sep. 2013 NRC Exam PAGE 3 OF 7 READ TO APPLICANT DIRECTION 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. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

Unit 2 is in Mode 1.

You were an extra operator on shift and assisting the Operation Test Group in a scheduled surveillance test of the 2B Emergency Diesel Generator.

The test was conducted using procedure PT/2/A/4350/002B (D/G Operability Test). Given the following timeline:

0830 2B D/G was started

. Time to reach required frequency was 7.0 seconds.

Time to reach required voltage was 6.7 seconds.

0845 2B D/G was fully loaded.

0905 Prior to completing the surveillance, 2B D/G tripped due to a malfunction of the low

-low lube oil pressure switch.

PT/2/A/4350/002B has been completed up to step 12.

7 5 for completing Diesel Generator Logbook entries per OMP 2

-28 (Diesel Generator Logbook)

. INITIATING CUES:

Using the information provided in Initial Conditions, classify the test and fill in all available Diesel Generator Logbook data (Items A through L) on Attachment 10.1 (Diesel Generator Log Sheet) and 10.2 (Index Sheet) of OMP 2-28 and submit to the CRS for revie

w. EXAMINER NOTE

Provide applicant with a copy of OMP 2

-28 (total of 11 pages). Attachment 10.2 will include one entry from the previous surveillance.

The applicant may ask for a name for the MCE Rotating Equipment Supervisor and a PIP # when completing the logbook entries.

If necessary, this may be done in another room to prevent possible compromise of the exam.

Catawba Nuclear Station RO-SRO JPM A.2 Sep. 2013 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 4 0F 7 START TIME: _______

STEP 1: Based on initial conditions, applicant refers to OMP Section 6 to determine the TEST CLASSIFICATION.

STANDARD: Applicant determines that the test is a VALID FAILURE based on criteria 6.4.A.

Critical Step step in order to meet the Task Standard: Determine the correct classification.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT

Catawba Nuclear Station RO-SRO JPM A.2 Sep. 2013 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 5 0F 7 STEP 2: Applicant enters appropriate information on Attachment 10.1 using information from the initial conditions.

STANDARD: Examiner NOTE:

See KEY provided with this document for required entries, including Critical Step aspects identified on the KEY.

Enters 2B D/G

. Enters start attempt as "2." Marks PT/1(2)/4350/002A(B) as procedure used

. Marks Scheduled Surveillance as Reason for D/G Operation

. Marks Turbo Prelube as Type of Diesel Start. Enters engine start time as 08 3 0. Enters engine shutdown time as 0905. Calculates and enters run time as 0.

58 hours6.712963e-4 days <br />0.0161 hours <br />9.589947e-5 weeks <br />2.2069e-5 months <br />. Enters Start Data:

Time for Frequency

> 57 Hz as 7.0 sec.

Time for Voltage

> 3950 volts as 6.7 sec.

Enters classification as VALID FAILURE

. Marks "Record Classification in Index" for Item L.

Applicant may continue past Step L and enter / inquire about the following:

Marks MCE Rotating Equipment supervisor or designee

. Enters reason D/G start was not a valid success: (2B D/G tripped on a malfunction of the LOLO Lube Oil Pressure switch prior to being loaded > 2875 KW for > 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />)

. EXAMINER CUE

"CRS will contact MCE Rotating Equipment supervisor.

" Marks PIP block since a PIP is required for this start

. EXAMINER CUE

PIP # C-1 3-02580 Th e steps in bold are critical because all other entries are required regardless of the classification

. COMMENTS: CRITICAL STEP

___ SAT ___UNSAT

Catawba Nuclear Station RO-SRO JPM A.2 Sep. 2013 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 6 0F 7 STEP 3: Logs the start into the Index Sheet (Enclosure 10.2)

STANDARD: Enters Start # as "2". Enters Date as today

's date. Enters Test Classification as "VALID FAILURE". Enters run time as 0.

58 hrs. Enters yearly run time as 2

.0 8 hrs. Indicates PIP # will be written in space provided

. The items in bold are critical based on OMP 2

-28 section 3 criteria.

COMMENTS: END OF TASK CRITICAL STEP ___ SAT ___ UNSAT STOP TIME ________

APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

Catawba 2013 NRC Exam

- RO-SRO JPM A.2 READ TO APPLICANT DIRECTION 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. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

Unit 2 is in Mode 1.

You were an extra operator on shift and assisting the Operation Test Group in a scheduled surveillance test of the 2B Emergency Diesel Generator.

The test was conducted using procedure PT/2/A/4350/002B (D/G Operability Test). Given the following timeline:

0830 2B D/G was started.

Time to reach required frequency was 7.0 seconds. Time to reach required voltage was 6.7 seconds.

0845 2B D/G was fully loaded.

0905 Prior to completing the surveillance, 2B D/G tripped due to a malfunction of the low

-low lube oil pressure switch.

PT/2/A/4350/002B has been completed up to step 12.

7 5 for completing Diesel Generator Logbook entries per OMP 2

-28 (Diesel Generator Logbook).

INITIATING CUES:

Using the information provided in Initial Conditions, classify the test and fill in all available Diesel Generator Logbook data (Items A through L) on Attachment 10.1 (Diesel Generator Log Sheet) and 10.2 (Index Sheet) of OMP 2-28 and submit to the CRS for review.

Catawba Nuclear Station RO-SRO JPM A.3 Sep. 2013 NRC Exam PAGE 1 OF 13

JPM A.3 RO - SRO

Catawba Nuclear Station RO-SRO JPM A.3 Sep. 2013 NRC Exam PAGE 2 OF 13 DATA SHEET Task: Calculate Low Pressure Service Water Discharge flow for a liquid radioactive release.

Alternate Path:

N/A Facility JPM #:

2010 NRC Initial License Exam SRO

-D Admin. Safety Function:

N/A K/A 2.3.11 Ability to control radiation releases Importance:

3.8 / 4.3 CFR: 41.11 / 43.4 / 45.10 Preferred Evaluation Location:

Preferred Evaluation Method: Simulator Classroom X Perform X Simulate References

PT/0/A/4250/011 (RL Temperature And Discharge Flow Determination) rev 050 Task Standard:

Applicant obtains needed data, correctly calculates total discharge flow, and determines that the liquid waste release can NOT continue.

Validation Time:

15 minutes Time Critical:

Yes No X Applicant:

Time Start: ______

____ NAME___________________________

Docket #_______________

Time Finish: ________

__ Performance Rating: SAT ____ UNSAT ____

Performance Time ___

__ Examiner: _____________________________

_____________________________/________

NAME SIGNATURE DATE ===========================================================================

COMMENTS PAGE 3 0F 13 Catawba Nuclear Station RO - SRO JPM A.3 Sep. 2013 NRC Exam PAGE 3 OF 13 READ TO APPLICANT DIRECTION 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. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

1. Unit 1 is currently performing a liquid waste release from the Monitor Tank Building. 2. Low Pressure Service Water (RL) Flow transmitter 0RLP5080 (RL Disch Flow) and OAC points C1P0903 and C2P0903 (RL Line A Disch Flow

-Hourly Average) are INOPERABLE and have been removed from service.

3. The RN system is aligned to the RL discharge header.

4. Units 1 and 2 are both at 100% power.

INITIATING CUES:

You are directed to calculate the total RL discharge flow using Enclosure 13.2 (Total Discharge Flow Calculation Sheet) of PT/0/A/4250/011 and determine if adequate flow exists to continue the release per the LWR currently in progress. Record your answer in the spaces below.

Total RL Discharge Flow GPM. Adequate Flow Exists

. Yes/No EXAMINER NOTE

After reading initiating cue, provide applicant with a copy of PT/0/A/4250/011 marked up as follows:

Step 12.1 signed off.

Enclosure 13.1 signed off up to Step 1.1.4.3 for performing Enclosure 13

.2 Also provide a copy of the LWR permit report.

Catawba Nuclear Station RO - SRO JPM A.3 Sep. 2013 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 4 0F 13 START TIME: _______

STEP 1: 1.1.2 Perform the following calculations to obtain Total Discharge Head: RL Disch Pressure = 0RLP5030 + 3.9 psi RL Disch Pressure = __6 6__ + 3.9 psi =

_69.9_ psig Lake Elevation = __569__ 0RNP7380 (Lake Wylie Level) or obtained from hydro central per Step 1.1.4.2 of Enclosure 13.1

(_69.9_ psig x 2.311ft/psig) + (571.7 5 - _569_ft) = _164.3_ft RL Disch Pressure Lake Elev Total Disch Head STANDARD: Applicant calculates RL Discharge pressure as 164.3 ft. (Acceptable range: 163

- 165 ft. based on accounting for rounding and truncation.)

This step is critical because improper entry affect s the calculation for Total RL Discharge Flow.

EXAMINER NOTE:

Step 1.1.1 is N/A because ORLP5030 indicator IS available.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT

Catawba Nuclear Station RO - SRO JPM A.3 Sep. 2013 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 5 0F 13 STEP 2: 1.1.3 Using Total Discharge Head from Step 1.1.

2 obtain the RL Pump Flow value using one of the following:

Enclosure 13.7 (RL Pumps Head / Capacity Table)

OR OAC Databook in "Secondary Systems Databook Calcs" using "RL Total Discharge Head vs. RL Pump Flow Rate" STANDARD: Applicant determines that RL Pump Flow per Enclosure 13.7 is 3 8 , 3 5 4 GPM. EXAMINER NOTE: Range of 37,405 - 39,219 GPM is acceptable.

This step is critical because improper entry affect s the calculation for Total RL Discharge Flow.

COMMENTS:

CRITICAL STEP ___ SAT ___UNSAT

Catawba Nuclear Station RO - SRO JPM A.3 Sep. 2013 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 6 0F 13 STEP 3: 1.1.4 Once RL Pump Flow value is obtained, calculate Total RL Supply based on number of RL pumps in operation:

___38354___ X __ __1_______ = _____38354_____ RL Pump Flow

1. of pumps in op. Total RL Supply (A)

STANDARD: Applicant calculates Total RL Supply to be 38,354 GPM. EXAMINER NOTE: Range carried forward is 37,405 to 39,219 GPM. This step is critical because improper entry affect s the calculation for Total RL Discharge Flow.

COMMENTS:

CRITICAL STEP ___ SAT ___ UNSAT STEP 4: 1.1.5 Enter Total RL supply (A) value in Step 1.4.

STANDARD: Applicant enters value calculated for Total RL Supply in blank (A) on page 3 of 3 of Enclosure 13.2

. EXAMINER NOTE: Steps 1.2.1 and 1.2.2 are not applicable per initiating cue.

This step is critical because improper entry affect s the calculation for Total RL Discharge Flow.

COMMENTS:

CRITICAL STEP ___ SAT ___ UNSAT

Catawba Nuclear Station RO - SRO JPM A.3 Sep. 2013 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 7 0F 13 STEP 5: 1.2.3 IF either C1P5854 (RN Train A Calculated Total Flow)

OR C1P5855 (RN Train B Calculated Total Flow) is NOT available, perform the following to obtain total RN flow:

1.2.3.1 Calculate RN Pump Train A flow:

____0_____

+ ____0_____

= _____0____

gpm 1RNP7520 + 2RNP7520

= RN Pump Train A flow 1.2.3.2 Calculate RN Pump Train B flow:

__17,000__

+ ___0____ = _ 17,000__

gpm 1RNP7510 + 2RNP7510 = RN Pump Train B flow STANDARD: Applicant calculates total RN flow to be 17,000 GPM.

This step is critical because improper entry affect s the calculation for Total RL Discharge Flow.

COMMENTS:

CRITICAL STEP ___ SAT ___ UNSAT STEP 6: 1.2.4 Perform the following calculations to obtain Total RN Flow:

_________0________

+ _____17,000_______ = _17,000_gpm (B) RN Pump Train A Flow + RN Pump Train B Flow = Total RN Flow STANDARD: Applicant calculates total RN flow to be 17,000 GPM.

This step is critical because improper entry affect s the calculation for Total RL Discharge Flow.

COMMENTS:

CRITICAL STEP ___ SAT ___ UNSAT

Catawba Nuclear Station RO - SRO JPM A.3 Sep. 2013 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 8 0F 13 STEP 7: 1.2.5 Enter Total RN Flow (B) in Step 1.4.

STANDARD: Applicant enters Total RN Flow calculated in previous step in blank (B) on page 3 of 3.

EXAMINER NOTE: Steps 1.3.1 and 1.3.2 are not applicable per data sheet.

This step is critical because improper entry affect s the calculation for Total RL Discharge Flow.

COMMENTS:

CRITICAL STEP ___ SAT ___ UNSAT STEP 8: 1.3.3 Calculate Cooling Tower Total Evaporation as follows:

13,500 + 14,000 = 27,500 gpm (C) (C1P5853) (C2P5853) Tot al Evaporation STANDARD: Applicant calculates Total Cooling Tower Evaporation to be 27,500 GPM and enters this value in blank (C) of step 1.4.

This step is critical because improper entry affect s the calculation for Total RL Discharge Flow.

COMMENTS:

CRITICAL STEP ___ SAT ___ UNSAT

Catawba Nuclear Station RO - SRO JPM A.3 Sep. 2013 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 9 0F 13 STEP 9: 1.4 Perform the following calculation to obtain Total RL Disch Flow: 38354 + 17,000 - 27,500 = 27,854 gpm (A) (B) (C)

STANDARD: Applicant calculates Total RL discharge flow to be 27,854 gpm. EXAMINER NOTE: Calculation range carried forward would be 26,905 to 28, 7 19 GPM. This step is critical to ensure that enough RL flow exists to dilute the liquid waste release that is in progress.

COMMENTS:

CRITICAL STEP ___ SAT ___ UNSAT

Catawba Nuclear Station RO - SRO JPM A.3 Sep. 2013 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 10 0F 13 STEP 1 0: 1.5 Apply dilution safety factor to obtain Total RL Discharge flow from the Calculated Total RL Discharge Flow from Step 1.4 as follows:

(27,854 gpm)

X 0.65 = 18,105 gpm STANDARD: Applicant calculates Total RL Discharge flow to be 18,105 GPM. EXAMINER NOTE: Calculation range carried forward would be 17,488 to 18,667 GPM. This step is critical to ensure that enough RL flow exists to dilute the liquid waste release that is in progress.

COMMENTS:

CRITICAL STEP ___ SAT ___ UNSAT

Catawba Nuclear Station RO - SRO JPM A.3 Sep. 2013 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 11 0F 13 STEP 11 Determination of adequate RL flow.

STANDARD: Applicant determines that Total RL Discharge Flow is LESS than the "Minimum RL Flow interlock setpoint for radionuclides (gpm)" required by and listed on the Liquid Waste Release Permit Report, and that the release may NOT continue. This step is critical for ensuring termination of a release with inadequate dilution flow.

EXAMINER NOTE

The Liquid Waste release Permit Report requires at least 27,600 gpm RL flow in order for the release to continue. If the applicant does NOT apply the dilution safety factor (listed in STEP 10 of this JPM), it will appear that adequate RL flow DOES exist (27,854 gpm). But with the required dilution safety factor, RL flow can only be calculated as 18,105 gpm: inadequate for the release to continue

. COMMENTS:

END OF TASK CRIT ICAL STEP ___ SAT ___ UNSAT

STOP TIME ________

APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

Catawba 2013 NRC Exam

- RO - SRO JPM A.3 READ TO APPLICANT DIRECTION 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. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

1. Unit 1 is currently performing a liquid waste release from the Monitor Tank Building. 2. Low Pressure Service Water (RL) Flow transmitter 0RLP5080 (RL Disch Flow) and OAC points C1P0903 and C2P0903 (RL Line A Disch Flow

-Hourly Average) are INOPERABLE and have been removed from service.

3. The RN system is aligned to the RL discharge header.

4. Units 1 and 2 are both at 100% power.

INITIATING CUES:

You are directed to calculate the total RL discharge flow using Enclosure 13.2 (Total Discharge Flow Calculation Sheet) of PT/0/A/4250/011 and determine if adequate flow exists to continue the release per the LWR currently in progress. Record your answer in the spaces below.

Total RL Discharge Flow GPM. Adequate Flow Exists

. Yes/No

APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

Catawba 2013 NRC Exam

- RO - SRO JPM A.3 Unit 1 and Unit 2 Data Sheet for 1030 Unit 1 Cooling Tower Evaporation (PID C1P5853)

- 13,500 GPM Unit 2 Cooling Tower Evaporation (PID C2P5853)

- 14,000 GPM Low Pressure Service Water (RL) Status

RL pump A only is in service

. RL Header Pressure (0RLP5030)

- 6 6 PSIG Lake Wylie Level (0RNP7380)

- 569 Feet Nuclear Service Water (RN) Status

1B RN pump is in service OAC points C1P5854, C1P5855, and C1P5856 are removed from service

RN Pump Train A flow (1RNP7520)

- 0 GPM RN Pump Train A flow (2RNP7520)

- 0 GPM RN Pump Train B flow (1RNP7510)

- 17,000 GPM RN Pump Train B Flow (2RNP7510)

- 0 GPM Catawba Nuclear Station SRO JPM A.4 Sep. 2013 NRC Exam PAGE 1 OF 9 JPM A.4 SRO

Catawba Nuclear Station SRO JPM A.4 Sep. 2013 NRC Exam PAGE 2 OF 9 DATA SHEET Task: Make Emergency Classification and Complete the Initial Emergency Notification Form Alternate Path:

N/A Facility JPM #:

SEP-018 Safety Function:

N/A K/A 2.4.40 Knowledge of SRO responsibilities in emergency plan implementation.

Importance:

2.7 / 4.5 CFR: 41.10 / 43.5 / 45.11 Preferred Evaluation Location:

Preferred Evaluation Method:

Simulator Classroom X Perform X Simulate References

RP/0/A/5000/001 (Classification of Emergency), revision 029 Task Standard:

Event classified as a "Site Area Emergency" based on the criteria in 4.1.C.4 and 4.1.N.2 (or N.3) within 15 minutes of JPM start

. Obtain the preprinted Emergency Notification sheet or complete a blank one for 4.1.S.3. Fill out the sheet within 15 minutes from the time the classification is made. Validation Time:

22 minutes Time Critical:

Yes X No Applicant:

Time Start: ______

____ NAME___________________________

Docket #_______________

Time Finish: ________

__ Performance Rating:

SAT ____ UNSAT ____

Performance Time ___

__ Examiner: _____________________________

_____________________________/________

NAME SIGNATURE DATE ===========================================================================

COMMENTS PAGE 3 0F 9 Catawba Nuclear Station SRO JPM A.4 Sep. 2013 NRC Exam PAGE 3 OF 9 READ TO APPLICANT DIRECTION 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. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS: A Unit 1 transient initially caused an OP Delta T Reactor Trip signal

. The reactor failed to automatically trip. The crew successfully completed a manual reactor trip from the control room

. Almost immediately, the unit safety injected

. The crew entered EP/1/A/5000/E

-0 (Reactor Trip or Safety Injection).

1C Steam Generator has a stuck open S/G safety

. Coolant activity level is 30 Ci/cc Dose Equivalent Iodine (DEI) I

-131. The crew is transitioning to EP/1/A/5000/E

-2 (Faulted Steam Generator Isolation). The transition brief contained the following additional information:

NC pumps had to be tripped due to a loss of subcooling

. NC pressure is 600 psig and stable

. 1ETB has an unknown fault and is currently de

-energized. EMF Trip 2 alarms are in

1EMF-28 (Steam line 1C) 1EMF-33 (Condenser Air Ejector Exhaust) 1EMF-72 (S/G B Leakage) 1EMF-73 (S/G C Leakage)

Current meteorological data:

Clear conditions

. Wind speed is 5 mph. Wind direction is 270°

. INITIATING CUES:

Classify the event and fill out the initial Emergency Notification form through the date and time that you approve it.

This JPM is time critical.

PAGE 4 0F 9 Catawba Nuclear Station SRO JPM A.4 Sep. 2013 NRC Exam PAGE 4 OF 9 EXAMINER NOTE:

Provide applicant a copy of:

RP/0/A/5000/006 A (Notifications to States and Counties from the Control Room), Enclosure 4.1, "Emergency Notification Form Completion", 7 pages

Catawba Nuclear Station SRO JPM A.4 Sep. 2013 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 5 0F 9 START TIME: _______

STEP 1: Classify the event using RP/0/A/5000/001, Classification of Emergency.

STANDARD: Applicant classifies the event as a "Site Area Emergency" based on: Event # 4.1.C.4 and #4.1.N.2 or 3.

3 points 4.1.C.4 (SG Secondary Side Release With Primary to

Secondary Leakage)

.

AND 5 points 4.1.N.2 (Greater than available makeup capacity as indicated by a loss of NCS Subcooling)

. OR 5 points 4.1.N.3 (Indication that a SG is ruptured and has a Non

-

Isolable secondary side fault.)

The above conditions will result in a 4.1.S.3 Site Area Emergency

. EXAMINER NOTE

It is critical that the classification be made and the emergency be declared within 15 minutes of the recorded start time.

TIME EMERGENCY DECLARED __________________.

This step is critical to ensure the proper classification will be communicated.

COMMENTS: CRITICAL STEP ___ SAT ___ UNSAT

Catawba Nuclear Station SRO JPM A.4 Sep. 2013 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 6 0F 9 STEP 2: Obtain Emergency Notification form.

STANDARD: Applicant obtains a blank Emergency Notification form (provided by Examiner).

This step is critical to ensure that the proper form is transmitted

. COMMENTS:

CRITICAL STEP

___ SAT

___UNSAT

Catawba Nuclear Station SRO JPM A.4 Sep. 2013 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 7 0F 9 STEP 3: Complete the Emergency Notification Form.

EXAMINER NOTE:

Critical Steps are in BOLD below. Also see attached completed Emergency Notification Form KEY.

On the KEY, the Critical Steps are highlighted in YELLOW.

STANDARD: Line 1: "Drill" is marked.

Line 2: "Initial" is marked.

Line 3: Catawba Nuclear Site (pre-printed). Line 4: Per attached KEY.

Line 5: "None" is marked.

Line 6: Emergency release "is occurring" due to 1EMF

-33 indication of S/G tube leakage

. Line 7: "Under evaluation" marked EXAMINER CUE

"RP is determining release significance

." Line 8: "Stable " marked. Line 9: Not required for initial notifications, and NOT critical.

If entered, wind direction is 270° and wind speed 5 mph. Line 10: "Declaration" marked and enters current date and time. Line 11: Affected Unit(s) marked as "1". Line 12: Marks box "A" and 0% power

. EXAMINER CUE: "The reactor was tripped 10 minutes ago

." Enters time minus 10 minutes and enters today's date

. Line 13: Includes information on the loss of power and the ATWS.

Lines 14,15 and 16

- see Examiner Cue below.

IF ASKED, EXAMINER CUE: "RP has not determined any release data

." COMMENTS: CRITICAL STEP ___ SAT ___ UNSAT

Catawba Nuclear Station SRO JPM A.4 Sep. 2013 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 8 0F 9 STEP 3 (cont.) EXAMINER NOTE

These steps are not required for initial notifications.

Line 17: Signs as Emergency Coordin ator. Date and time on line 17 is based on time of approval

. See attached, completed, Emergency Notification sheet for a key.

Time Emergency Notification Form is completed:

_______________

It is critical that the total time from the declaration time recorded in Step 1 to completing the Emergency Notification Form is

< 15 minutes. COMMENTS:

STOP TIME ________

APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

Catawba 2013 NRC Exam

- SRO JPM A.4 READ TO APPLICANT DIRECTION 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. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you. INITIAL CONDITIONS:

A Unit 1 transient initially caused an OP Delta T Reactor Trip signal

. The reactor failed to automatically trip. The crew successfully completed a manual reactor trip from the control room

. Almost immediately, the unit safety injected. The crew entered EP/1/A/5000/E

-0 (Reactor Trip or Safety Injection).

1C Steam Generator has a stuck open S/G safety

. Coolant activity level is 30 Ci/cc Dose Equivalent Iodine (DEI) I

-131. The crew is transitioning to EP/1/A/5000/E

-2 (Faulted Steam Generator Isolation).

The transition brief contained the following additional information:

NC pumps had to be tripped due to a loss of subcooling

. NC pressure is 600 psig and stable

. 1ETB has an unknown fault and is currently de

-energized. EMF Trip 2 alarms are in

1EMF-28 (Steamline 1C) 1EMF-33 (Condenser Air Ejector Exhaust) 1EMF-72 (S/G B Leakage) 1EMF-73 (S/G C Leakage)

INITIATING CUES:

Classify the event and fill out the initial Emergency Notification form through the date and time that you approve it.

This JPM is time critical.