ML031840248

From kanterella
Jump to navigation Jump to search
Draft - Section a Operating
ML031840248
Person / Time
Site: Seabrook NextEra Energy icon.png
Issue date: 06/05/2003
From: Roy D
Florida Power & Light Energy Seabrook
To: Conte R
NRC/RGN-I/DRS/OSB
Conte R
References
50-443/03-301 50-443/03-301
Download: ML031840248 (88)


Text

JOB PERFORMANCE MEASURE WORKSHEET RO Administrative JPM #I Section A.1 PERFORM A QPTR CALCULATION Examinee:

NRC Examiner:

Facility Evaluator:

Date:

Method of Testing Simulated Performance:

Actual Performance:

Classroom:

Simulator:

Plant:

WA reference: 2.1 23 Ability to perform specific system and integrated plant procedures during all modes of plant oDeration.

USNRC Initial Licensing Examination Seabrook Station June 2003 RO Section A.l JPM #I Page 1 of 8

JOB PERFORMANCE MEASURE WORKSHEET VERIFICATION OF COMPLETION Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of attempts:

Time to complete:

Question documentation Responses to questions Result: SAT or UNSAT (circle one)

Examiners signature and date:

USNRC Initial Licensing Examination Seabrook Station June 2003 RO Section A.l JPM #I Page 2 of 8

~ _ _

JOB PERFORMANCE MEASURE WORKSHEET SYS KA Description 01 5 A I.04 Ability to monitor changes in QPTR.

01 5 K5.12 Knowledge of QPTR.

015 K5.16 Definition and calculation of QPTR.

I.o 2.0 3.0 4.0 0

0 0

5.0 6.0 Value RO/SRO 333.7 3.2/3.6 2.9/3.4 Task Number and

Description:

Position:

RO 0150200501 Perform A Manual QPTR Calculation Conditions:

A Plant is now at 100%.

B. The main plant computer has been inoperable since yesterday C. The seven-day QPTR surveillance is scheduled to be done this shift.

D. Incore/Excore calibration was performed yesterday.

Standards:

Perform the manual QPTR surveillance per RXI 703, QPTR Surveillance.

Final answers for QPTR should be within +/- 0.01 of the key. Deviations from this should be further examined.

Student Materials:

Copy of the Tear-Off Sheet Calculator RX1703, QPTR Surveillance, Rev. 6, Chg.3.

Limitations on performance:

Simulate/Perform all steps. Verbalize all actions to the evaluator.

Even if requested, no Peer Checks will be provided during the JPM.

References:

Procedures RX1703, QPTR Surveillance 0

OSlOOO.05, Power Increase 0

ON1251.01, Loss Of Plant Computer USNRC Initial Licensing Examination Seabrook Station June 2003 RO Section A. 1 JPM #I Page 3 of 8

JOB PERFORMANCE MEASURE WORKSHEET

7.0 Setting

Classroom 0

Give the student a copy of 100% power NI cabinet values.

0 Examiner must prepare a completed RX1703A in advance. It shall reflect the JPM values for NI cabinet detector currents and the RE-17 100% power, 0%

AFD values.

Use values listed in RE-17 rev 01-08-15.

0 8.0 Safety Considerations:

None 9.0 Approximate Completion Time:

20 minutes 10.0 Initiating Cue:

Initial Conditions:

0 Plant is now at 100% power.

0 The main plant computer has been inoperable since yesterday.

0 The QPTR surveillance is scheduled to be done this shift.

0 Incore/Excore calibration was performed yesterday.

You are the Primary Operator. You are going to perform the QPTR surveillance.

US to Primary Operator, Primary Operator (or students name), perform the QPTR Surveillance per RX1703. Discuss the results with me.

USNRC Initial Licensing Examination Seabrook Station June 2003 RO Section A.l JPM #I Page 4 of 8

PERFORMANCE CHECKLIST D=Discuss ELEMENTISTEP STANDARD EVALUATION IN ITIALS/DATE P=Perform

  • denotes a
  • denotes critical S=Simulate critical step standard SAT UNSAT I.

P Start time:-

NOTE: After the correct procedure is located, give the student the copy from the JPM. When the correct form is referenced, give the student a blank form from the JPM.

CUE:

If student asks: The QPTR alarm surveillance has been entered and the RTS is being generated. Continue with the QPTR calculation.

CUE:

peer check your actions. Please continue with the task.

If the student requests a Peer Check at any time during the JPM, respond: NO one is available to NOTE: Provide detector current data for upper & lower detectors.

2.

P Refers to section 4.1, Surveillance With QPTR Alarm I no per able:

a. RECORD the current output a.

Records detectors from the top (A) and bottom output:

(B) detector of each channel on Form A, Quadrant Power Tilt Calculation Sheet.

N41 top detector 0

N42 top detector --

0 N43 top detector --

0 N44 top detector 0

N41 bottom detector USNRC Initial Licensing Examination Seabrook Station June 2003 RO Section A.l JPM #I 0

N42 bottom detector --

0 N43 bottom detector --

0 N44 bottom detector Page 5 of 8

PERFORMANCE CHECKLIST D=Discuss ELEMENTETEP STANDARD EVALUATION INITIAL S/DATE P=Perform

  • denotes a
  • denotes critical S=Simulate critical step standard SAT UNSAT NOTE:

Provide the student with a copy of RE17 if asked.

3.

P

4.

P

5.

P

6.

P Using data from Technical Data From TDB fig RE-17, Book Figure RE-17, RECORD Records 100% power, 0%

the 100% power, 0% AFD AFD values:

detector current, for the top (A) 0 4 Top Detectors and bottom (B) detector of each channel on Form A, 4 Bottom Detectors Quadrant Power Tilt Calculation Sheet.

CALCULATE the normalized detector current by dividing each detector current by its 100% power, 0% AFD current.

0 4 Top Detectors RECORD the results on Form A, Quadrant Power Tilt 4 Bottom Detectors Calculation Sheet.

Calculates and records Normalized Detector Currents:

CALCULATE the average Calculates and records normalized detector current for average normalized the top detectors and for the detector currents:

bottom detectors. RECORD 0

Top the results on Form A, Quadrant Power Tilt Bottom Calculation Sheet.

CALCULATE the Quadrant Power Tilt Ratio for each detector by dividing each 4Top normalized detector current by its associated average 4 Bottom normalized detector current.

COMPLETE Form A, Quadrant Power Tilt Calculation Sheet.

Calculates and records QPTR for each detector:

NOTE: If the student expresses a rounded off value, then that value shall be compared against the standard.

The only value that is critical is the out of tolerance (asterisked ) QPTR value.

CUE:

If the student inquires about the RTS provide the following cue: The RTS is being printed out, please circle the maximum power tilt ratio on your calculation sheet, and continue with the procedure.

USNRC Initial Licensing Examination Seabrook Station June 2003 RO Section A.1 JPM #1 Page 6 of 8

D=Discuss ELEMENTETEP P=Perform

  • denotes a S=Simulate critical step PERFORMANCE CHECKLIST STANDARD EVALUATION I NITIALWDATE
  • denotes critical standard SAT UNSAT
  • 7.

P RECORD the maximum power

  • Identifies (circles) the tilt ratio on applicable RTS.

maximum power tilt ratio consistent with the answer key.

CUE:

If the student does not report TS compliance/noncompliance, provide the cue: Is QPTR within Tech.

Spec. Limits?

  • 8.

P If the Quadrant Power Tilt Ratio

  • Determines and reports is determined to be greater that QPTR is within TS than 1.02, immediately NOTIFY limits.

the SS/US.

CUE:

The JPM is complete.

9.

Stop time Start - Stop time is I 20 minutes.

Evaluator calculates the time to complete the task.

USNRC Initial Licensing Examination Seabrook Station June 2003 RO Section A.l JPM #i Page 7 of 8

Tear-Off Sheet for Applicant N42 TOP:

N42 BOTTOM:

Initial Conditions:

183 224 0

0 0

0 Plant is now at 100% power.

The main plant computer has been inoperable since yesterday.

The QPTR surveillance is scheduled to be done this shift.

Incore/Excore calibration was performed yesterday.

N43 TOP:

N43 BOTTOM:

N44 TOP:

N44 BOTTOM:

You are the Primary Operator. You are going to perform the QPTR surveillance.

200 222 195 209 US to Primary Operator, Primary Operator (or students name), perform the QPTR Surveillance per RX1703. Discuss the results with me.

USNRC Initial Licensing Examination Seabrook Station June 2003 RO Section A.l JPM #I Page 8 of 8

JOB PERFORMANCE MEASURE WORKSHEET RO Administrative JPM #2 Section A.l PERFORM A SHUTDOWN MARGIN CALCULATION Examinee:

NRC Examiner:

Facility Evaluator:

Date:

Method of Testing Simulated Performance:

Actual Performance:

Classroom:

Simulator:

Plant:

K/A reference: 2.1.25 Ability to obtain and interpret station reference materials such as graphs, monographs, and tables which contain performance data.

USNRC Initial Licensing Examination Seabrook Station June 2003 RO Section A.l JPM #2 Page 1 of 7

JOB PERFORMANCE MEASURE WORKSHEET VERIFICATION OF COMPLETION Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:

Number of attempts:

Time to complete:

Question documentation Responses to questions Result: SAT or UNSAT (circle one)

Examiner's signature and date:

USNRC Initial Licensing Examination Seabrook Station June 2003 RO Section A.l JPM #2 Page 2 of 7

I.o 2.0 3.0 4.0 5.0 6.0 JOB PERFORMANCE MEASURE WORKSHEET Task Number and

Description:

Position:

RO 001 01 00401 Perform Shutdown Margin Calculation Conditions:

The unit has just completed a natural circulation cooldown to 160F after a trip from full power that occurred 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> ago.

Standards:

Student Materials:

Copy of the Tear-Off Sheet Calculator RXI707, "Shutdown Margin Surveillance", Rev. 7, Chg.3.

Primary Tech Data Book, (BOL) - Curves RE-02 (rev 01-091 1) & RE-18 (rev Calculate the boron concentration required to satisfy the SDM requirements for 160°F.

Use RX1707, "Shutdown Margin Surveillance".

01-09-01).

Limitations on performance:

Simulate/Perform all steps. Verbalize all actions to the evaluator.

Even if requested, no Peer Checks will be provided during the JPM.

References:

Procedures:

RX1707, Shutdown Margin Surveillance.

Technical Specifications:

3.1 i1.1, SDM greater than 200°F.

Manuals:

Primary Technical Data Book.

USNRC Initial Licensing Examination Seabrook Station June 2003 RO Section A. 1 JPM #I2 Page 3 of 7

JOB PERFORMANCE MEASURE WORKSHEET SYS KA Description Value RO/SRO 1

I I

I 192002 I K1.13 I Calculate SDM using procedures and given plant I 3.33.7 1

7.0 8.0 9.0 10.0 Setting:

Classroom. The Primary Technical Data Book containing COLR RE 21 Cycle 9 was used to generate the key and must be given to the applicants to complete this JPM.

Safety Considerations:

None Approximate Completion Time:

20 minutes Initiating Cue:

Initial conditions:

0 The unit has just completed a natural circulation cooldown to 160F after a trip from full power that occurred 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> ago.

US to Primary Operator, Primary Operator (or students name), determine the required boron concentration to satisfy SDM requirements for 160F, taking credit for xenon. Using RX1707, determine if SDM is satisfactory.

The chemist will have the current RCS boron concentration shortly.

I I

.O Attachments 0

RX1707, Shutdown Margin Surveillance 0

Blank RX1707 Form A for applicant.

Completed RX1707 Form A as answer key.

0 Primary Technical Data Book (COLR RE 21 Cycle 9)

USNRC Initial Licensing Examination Seabrook Station June 2003 RO Section A. 1 J PM #2 Page 4 of 7

D=Discuss ELEMENTETEP P=Perform

  • denotes a S=Simulate critical step PERFORMANCE CHECKLIST STANDARD EVALUATION IN ITIALS/DATE
  • denotes critical standard SAT UNSAT P

Start time:

Initiating cue read.

CUE:

peer check your actions. Please continue with the task.

If the student requests a Peer Check at any time during the JPM, respond: NO one is available to

1.

P For the RCS average temperature of 160F, OBTAIN the required shutdown boron concentration from Primary Technical Data Book Figure RE-2. RECORD this value (A) on Form A, Shutdown Margin Determination - MODEs 3, 4 and 5.

Determines required RE-2 concentration:

e Refers to figure RE-2. --

e Records required boron concentration for existing RCS average temperature (RX1707A value A). (1 135 ppm)

CUE:

When student asks about Xenon worth, provide the cue: Xenon worth is 3177 pcm.

  • 2.

P To take credit for xenon, Performs the following:

PERFORM the following:

a. OBTAIN the xenon worth
a. Obtains and records from the calculated point COO36 or from Reactor C0036.

Engineering. RECORD this (3177 pcm) value (B) on Form A, Shutdown Margin Determination - MODEs 3,4 and 5.

xenon worth from RE or

b. OBTAIN differential boron
b. Obtains and records worth (DBW) from TDB Figure RE-18. USE the
18.

value corresponding to the appropriate RCS temperature range. The value corresponding to RCS temperature below 530°F is the most conservative for this application and shall be used for RCS temperatures below 530°F. RECORD the value used (C) on Form A, Shutdown Margin Determination - Modes 3,4, 23 5.

DBW from Figure RE-(14.063 pcm/ppm)

c. DETERMINE the Shutdown *c. Calculates and records USNRC Initial Licensing Examination Seabrook Station June 2003 RO Section A. 1 J PM #2 Page 5 of 7

PERFORMANCE CHECKLIST D=Discuss ELEMENTISTEP STANDARD EVALUATION INITIALSIDATE P=Perform

  • denotes a
  • denotes critical S=Simulate critical step standard SAT UNSAT Boron Concentration, required shutdown including xenon, (D) by dividing the xenon worth (B) by the DBW (C). Subtract this value from the required Shutdown Boron Concentration (A).

RECORD this value (D) on Form A, Shutdown Margin Determination - MODEs 3,4 And 5, e.g., [D = A - (BIC)].

If the number is negative, RECORD a zero.

boron concentration.

(RX1707A value f 20 ppm of key).

(909 PPm)

CUE:

When asked of current boron concentration: Chemistry reports that the RCS boron concentration is 980 ppm.

NOTE: SDM is adequate (existing boron concentration is greater than that required at 160F).

  • 3.

P RECORD the Existing RCS Determines if current boron Boron Concentration (E) on concentration is adequate Form A, Shutdown Margin as follows:

Determination - MODEs 3,4 0

Records existing boron And 5. COMPARE it to the concentration.

Required Boron Concentration:

a. If taking credit for xenon, COMPARE the Existing Boron Concentration (E) to the Shutdown Boron Concentration including xenon (D). NOTIFY the SS/US if the existing Boron Concentration is less than the required Boron Concentration.
a.

Performs the following:

0 Compares existing boron concentration to required boron concentration.

  • 0 Determines that existing boron concentration is adequate.

CUE:

The JPM is complete.

5.

Stop time Start - Stop time is I 20 minutes.

Evaluator calculates the time to complete the task.

USNRC Initial Licensing Examination Seabrook Station June 2003 RO Section A.l JPM #2 Page 6 of 7

~~

Tear-Off Sheet for Applicant Initial conditions:

0 The unit has just completed a natural circulation cooldown to 160F after a trip from full power that occurred 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> ago.

US to Primary Operator, Primary Operator (or students name), detennine the required boron concentration to satisfy SDM requirements for 160F, taking credit for xenon. Using Rx1707, determine if SDM is satisfactory.

The chemist will have the current RCS boron concentration shortly.

USNRC Initial Licensing Examination Seabrook Station June 2003 RO Section A.l JPM #2 Page 7 of 7

Form A: Shutdown Margin Determination MODES (A)

(B)

(D)

(C)

SHUTDOWN BORON DIFFERENTIAL T I W A T E RCS SHUTDOWN XENON WORTH TAVG (OF)

BORON (C0036)

BORON WORTH CONCENTRATION (From RE-2)

(PCM)

(From RE-1 8)

(XENON CREDIT)

( A - (B/C)) (PPM)

(PPM)

(PCWPPM)

Date:

160°F 1135 3177 14.063 909 06102-03/03 Time Date:

/

I Time Date:

/

I Time Date:

/

I Time Date:

/

I Time Date:

/

I Time RCS BORON GREATER THAN REQUIRED C(ESN0)

YES 3,4 And 5 (E)

(PPW 980 EXISTING RCS BORON US Review Performed by: 1 RX 1707 Rev. 07 Chg 03 Page 1 lof 15 Verified by: 1 INITIALS Performed by: 7 Verified by: 7 Verified by:

Verified by:

~

JOB PERFORMANCE MEASURE WORKSHEET RO Administrative JPM #3 Section A.2 CIRCULATING WATER LUBE WATER PUMP TAGOUT Examinee:

NRC Examiner:

Facility Evaluator:

Date:

Method of Testing Simulated Performance:

Actual Performance:

Classroom:

Simulator:

Plant:

WA reference: 2.2.13 Knowledge of tagging and clearance procedures.

USNRC Initial Licensing Examination Seabrook Station June 2003 RO Section A.2 JPM #3 Page 1 of 6

JOB PERFORMANCE MEASURE WORKSHEET VERIFICATION OF COMPLETION Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of attempts:

Time to complete:

Question documentation Responses to questions Result: SAT or UNSAT (circle one)

Examiners signature and date:

USNRC Initial Licensing Examination Seabrook Station June 2003 RO Section A.2 JPM #3 Page 2 of 6

JOB PERFORMANCE MEASURE WORKSHEET 1.o 2.0 3.0 4.0 0

0 0

0 0

0 5.0 6.0 7.0 Task Number and

Description:

Position:

RO Task Number: N/A Conditions:

The applicant will receive a work package to tagout the CW Lube Water Pump B. The applicant is expected to provide the component ID, component noun name, type of tag needed, and tagged position. The selectionand sequence of the components must conform to MA 4.2, Equipment Tagging and Isolation.

You will provide the applicant with the following references if asked: PID I-CW-B20675, I

-NHY-301016 SHCY3a, and 1 -NHY-301016 SHCY3b. MA 4.2 will NOT be available to the applicant.

Standards:

The applicant must provide the minimum isolation required by the answer key.

More conservative configurations are acceptable as long as the tagout aligns the system in accordance with MA 4.2.

Student Materials:

Copy of the Tear-Off Sheet.

Work Package for Circ Water Lube Water pump B with the tagout section incomplete. The SOMS cover sheet should also be removed to prevent giving away tagging strategies.

Schematic 1-NHY-301016 SHCY3a Schematic 1-NHY-301016 SHCY3b Blank Tag List sheet to record answers.

Limitations on performance:

None.

References:

MA 4.2, Equipment Tagging and Isolation Setting:

Classroom/Simulator PID 1 -CW-B20675 USNRC Initial Licensing Examination Seabrook Station June 2003 RO Section A.2 JPM #3 Page 3 of 6

JOB PERFORMANCE MEASURE WORKSHEET 8.0 Safety Considerations:

None 9.0 Approximate Completion Time:

20 minutes.

10.0 Initial Cue:

You are tasked with tagging out the Circulating Water Lube Water Pump By for maintenance on a TRlCO oiler.

This work package explains the details of the work to be performed.

You are to supply the following minimal information to the examiner on the answer sheet provided to you: the component ID, the component noun name, type of tag used (danger, caution, directional, etc.), and the tagged position of the component.

Inform the examiner when you are complete.

You may choose to explain your logic to the examiner while you are performing this JPM.

11.O Attachments 0

Tag List answer key.

0 Work package.

0 Blank Tag List sheet USNRC Initial Licensing Examination Seabrook Station June 2003 RO Section A.2 JPM #3 Page 4 of 6

PERFORMANCE CHECKLIST D=Discuss ELEMENTKTEP STANDARD EVALUATION I NITIALWDATE P=Perform

  • denotes a
  • denotes critical S=Simulate critical step standard SAT UNSAT I.

P Read applicant initial cue and Time started:

begin JPM.

CUE: Give applicant the work package.

NOTE: The applicant should use the rules for tagging in MA 4.2, Equipment Tagging and Isolation, Figure 5.2 CUE: Give the applicant the appropriate drawing when they attempt to use the PID stick.

2.

P Fill out blank Tag List sheet.

Student should fill in the blank Tag List sheet provided to him/her.

NOTE: The tagout should be graded in accordance with the criteria listed below.

  • 2.
  • 3.
  • 4 P

Place control switch tags on components prior to manipulating the supply breaker.

P To prevent suction line over pressurization, close the pump discharge valve prior to closing the suction valve and monitor suction pressure to ensure leakage past the valve is NOT excessive.

P Place a locking device over the breaker switch and attach the tag to the locking device.

Informs the examiner that control switch 1-be danger tagged in the OFF position.

CW-P-136-B-CS should Informs examiner that the CW lube water pump discharge valve should be shut and tagged before the suction valve.

Informs examiner that all breakers are LOCKED open.

CUE: When applicant is finished, collect hidher answer sheet and schematics for comparison to the key. Look at the applicants answer to determine if helshe understood the task. If the JPM is complete, inform the applicant: The JPM is complete USNRC Initial Licensing Examination Seabrook Station June 2003 RO Section A.2 JPM #3 Page 5 of 6

Tear-Off Sheet for Applicant You are tasked with tagging out the Circulating Water Lube Water Pump B for maintenance on a TRICO oiler.

This work package explains the details of the work to be performed.

You are to supply the following minimal information to the examiner on the answer sheet provided to you: the component ID, the component noun name, type of tag used (danger, caution, directional, etc.), and the tagged position of the component.

Inform the examiner when you are complete.

You may choose to explain your logic to the examiner while you are performing this JPM.

USNRC Initial Licensing Examination Seabrook Station June 2003 RO Section A.2 JPM #3 Page 6 of 6

Tag List for WIO-22-05 Clearance ONLINE CYCLE 9 Location Not Required Tag ID Tag Tag Place.

Place.

Serial TY Pe Config Seq.

0 Danger or Off Not Caution Required 1-CW-P-136-B-CS Not Required l-CW-P-136-B-BKR 0

Danger Locked Not Open Required 1-CW-V-104-B Not Required 1 -CW-V-88-B Not Required Noun Name CW LUBE PUMP B CONTROL SWITCH AT MCB-FF CW LUBE WATER PUMP B BREAKER AT MCC-273 CY3>

CW-P-I 36B DISCHARGE ISOLATION CW-P-136B SUCTION ISOLATION DO NOT USE FOR TAG PLACEMENT OR REMOVAL Not Required 0

Danger Locked Not I

1 1

Closed 1

Required Not Required 0

Danger Locked Not I

I 1

Closed 1

Required Reset Config.

Not Required Not Required Not Required Not Required 6/2/03 0800 Page I of I Required Required Not I Not Required Required Not I Not

ADMINISTRATIVE QUESTION WORKSH EET RO Administrative Question Section A.3.1 EMERGENCY DOSE LIMITS QUESTION Examinee:

NRC Examiner:

Facility Evaluator:

Date:

Method of Testing Simulated Performance:

Actual Performance:

Classroom:

Simulator:

Plant:

WA reference: 2.3.4 Knowledge of radiation exposure limits and contamination control, including permissible levels in excess of those authorized.

USNRC Initial Licensing Examination Seabrook Station June 2003 RO Section A.3 Question Page 1 of 6

~

ADMl N ISTRATIVE QUESTION WORKSHEET VERIFICATION OF COMPLETION Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of attempts:

Time to complete:

Question documentation Responses to questions Result: SAT or UNSAT (circle one)

Examiners signature and date:

USNRC initial Licensing Examination Seabrook Station June 2003 RO Section A.3 Question Page 2 of 6

ADM I N I STRATIVE QU EST1 0 N WORKS H E ET 1.O Task Number and

Description:

Position:

RO/SRO Task Number: N/A

2.0 Conditions

0 0

The site has declared a Site Area Emergency due to a LOCA.

You are directed to manipulate a valve in the RHR vault.

3.0 Standards

The applicant must provide the correct answers in accordance with SSER 4.3, Radiation Protection During Emergency Conditions 4.0 Student Materials:

0 0

SSER, Emergency Response Manual 0

0 SSRP, Radiation Protection Manual Copy of the Tear-Off Sheet.

SSREP, Seabrook Station Radiological Emergency Plan 5.0 Limitations on performance:

None.

6.0

References:

SSER 4.3, Radiation Protection During Emergency Conditions

7.0 Setting

Classroom/Simulator USNRC Initial Licensing Examination Seabrook Station June 2003 RO Section A.3 Question Page 3 of 6

~-

ADM I N I STRAT IVE QUEST10 N WORKSHEET 8.0 Safety Considerations:

None 9.0 Approximate Completion Time:

10 minutes.

10.0 Initial Cue:

This is an open reference question.

This is a three-part question.

Initial Conditions:

0 The site has declared a Site Area Emergency due to a LOCA.

You are directed to manipulate a valve in the RHR vault.

Part I: What is your whole body dose limit for this activity?

Part 2: Given the current situation, under what circumstances can dose limits be raised above the non-emergency, federal annual limit and what are the limits?

Part 3: Whose permission is required to increase dose limits beyond the normal federal limits in an emergency?

Write you answers below and verbally explain to the examiner USNRC Initial Licensing Examination Seabrook Station June 2003 RO Section A.3 Question Page 4 of 6

ADMl N ISTRATIVE QUESTION WORKSHEET QUESTION:

This is a three-part question.

Initial Conditions:

0 0

The site has declared a Site Area Emergency due to a LOCA.

You are directed to manipulate a valve in the RHR vault.

Part 1: What is your whole body dose limit for this activity?

Part 2: Given the current situation, under what circumstances can dose limits be raised above the non-emergency, federal annual limit and what are the limits?

Part 3: Whose permission is required to increase dose limits beyond the normal federal limits in an emergency?

ANSWER:

Student may find answers in SSER Section 4.3, Figure 2.

Part 1: 5 rem.

Part 2:

10 rem to protect valuable equipment.

25 rem for lifesaving or protection of large populations.

>25 rem for lifesaving or protection of large populations (voluntary basis only)

Part 3: The Station Emergency Director or Short Term Emergency Directa-USNRC Initial Licensing Examination Seabrook Station June 2003 RO Section A.3 Question Page 5 of 6

~

TEAR-OFF SHEET FOR APPLICANT QUESTION:

This is an open reference question.

This is a three-part question.

Initial Conditions:

0 The site has declared a Site Area Emergency due to a LOCA.

0 You are directed to manipulate a valve in the RHR vault.

Part 1: What is your whole body dose limit for this activity?

Part 2: Given the current situation, under what circumstances can dose limits be raised above the non-emergency, federal annual limit and what are the limits?

Part 3: Whose permission is required to increase dose limits beyond the normal federal limits in an emergency?

Write you answers below and verbally explain to the examiner.

USNRC Initial Licensing Examination Seabrook Station June 2003 RO Section A.3 Question Page 6 of 6

ADMINISTRATIVE QUESTION WORKSHEET RO Administrative Question Section A.3.2 REQUIREMENTS OF A LOCKED HIGH RADIATION AREA QUESTION Examinee:

NRC Examiner:

Facility Evaluator:

Date:

Method of Testing Simulated Performance:

Actual Performance:

Classroom:

Simulator:

Plant:

WA reference: 23.1 Knowledge of 1 OCFR20 and related facility radiation control requirements.

USNRC Initial Licensing Examination Seabrook Station June 2003 RO Section A.3 Question Page 1 of 6

~

~

ADMINISTRATIVE QUESTION WORKSHEET VERIFICATION OF COMPLETION Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:

Number of attempts:

Time to complete:

Question documentation Responses to questions Result: SAT or UNSAT (circle one)

Examiner's signature and date:

USNRC Initial Licensing Examination Seabrook Station June 2003 RO Section A.3 Question Page 2 of 6

ADMINISTRATIVE QUESTION WORKSHEET 1.O Task Number and

Description:

Position:

RO/SRO Task Number: N/A

2.0 Conditions

No specific plant condition necessary.

3.0 Standards

The applicant must provide the correct answers in accordance with Technical Specification 6.1 1.

4.0 Student Materials:

0 Copy of the Tear-Off Sheet.

0 Complete set of Technical Specifications SSRP 5.0 Limitations on performance:

None.

6.0

References:

Technical Specification 6.1 I

7.0 Setting

Classroom/Simulator USNRC Initial Licensing Examination Seabrook Station June 2003 RO Section A.3 Question Page 3 of 6

ADMINISTRATIVE QUESTION WORKSHEET 8.0 Safety Considerations:

None 9.0 Approximate Completion Time:

I O minutes.

10.0 initial Cue:

This is an open reference question.

While you are walking in the PAB, you pass the VCT room.

The following radiological controls are posted on, or in front of, the door leading into the room:

0 Danger - High Radiation Area 0

A radiological survey map with a gamma dose rate marked at 1300 mremlhr @

45cm. The high dose area is accessible to anyone in the room.

0 There is a barricade in front of the door with a motion-actuated strobe.

0 The door is unlocked but closed.

0 There is no one in the VCT room.

0 There is a sign on the door that reads "HP Work Area - Do Not Enter" Are the controls and postings adequate for the radiological conditions inside this room?

USNRC initial Licensing Examination Seabrook Station June 2003 RO Section A.3 Question Page 4 of 6

ADMINISTRATIVE QUESTION WORKSHEET QUESTION:

While you are walking in the PAB, you pass the VCT room.

The following radiological controls are posted on, or in front of, the door leading into the room:

0 Danger - High Radiation Area 0

A radiological survey map with a gamma dose rate marked at 1300 mrem/hr @

45cm. The high dose area is accessible to anyone in the room.

0 There is a barricade in front of the door with a motion-actuated strobe.

0 The door is unlocked but closed.

0 There is no one in the VCT room.

There is a sign on the door that reads "HP Work Area - Do Not Entef Are the controls and postings adequate for the radiological conditions inside this room?

ANSWER:

No. This is a Technical Specification High Radiation Area. The door needs to be locked.

USNRC Initial Licensing Examination Seabrook Station June 2003 RO Section A.3 Question Page 5 of 6

TEAR-OFF SHEET FOR APPLICANT QUESTION:

This is an open reference question.

While you are walking in the PAB, you pass the VCT room.

The following radiological controls are posted on, or in front of, the door leading into the room:

0 Danger - High Radiation Area 0

A radiological survey map with a gamma dose rate marked at 1300 mremlhr @

45cm. The high dose area is accessible to anyone in the room.

0 There is a barricade in front of the door with a motion-actuated strobe.

0 The door is unlocked but closed.

0 There is no one in the VCT room.

There is a sign on the door that reads HP Work Area - Do Not Enter Are the controls and postings adequate for the radiological conditions inside this room?

USNRC Initial Licensing Examination Seabrook Station June 2003 RO Section A.3 Question Page 6 of 6

ADMINISTRATIVE QUESTION WORKSHEET RO Administrative Question Section A.4.1 OFF-WATCH E-PLAN REPORTING REQUIREMENTS Examinee:

NRC Examiner:

Facility Evaluator:

Date:

Method of Testing Simulated Performance:

Actual Performance:

Classroom:

Simulator:

Plant:

K/A reference: 2.4.39 Knowledge of the ROs responsibilities in emergency plan implementation.

USNRC Initial Licensing Examination Seabrook Station June 2003 RO Section A.4 Question Page 1 of 6

ADM I N ISTRATIVE Q U EST1 ON WORKSH EET VERIFICATION OF COMPLETION Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of attempts:

Time to complete:

Question documentation Responses to questions Result: SAT or UNSAT (circle one)

Examiners signature and date:

USNRC Initial Licensing Examination Seabrook Station June 2003 RO Section A.4 Question Page 2 of 6

1.o 2.0 3.0 4.0 5.0 6.0 7.0 8.0 9.0 ADM I N I STRATIVE QUEST1 ON WORKSHEET Task Number and

Description:

Position:

RO Task Number: N/A Conditions:

The applicant is in training on-site when the site declares an ALERT.

Standards:

The applicant must provide the correct response in accordance with the Radiological Emergency Plan (SSREP).

Student Materials:

None.

Limitations on performance:

None.

References:

SSREP, "Radiological Emergency Plan", appendix A, table 2 Setting:

Classroom/Simulator Safety Considerations:

None Approximate Completion Time:

I O minutes.

USNRC Initial Licensing Examination Seabrook Station June 2003 RO Section A.4 Question Page 3 of 6

ADMINISTRATIVE QUESTION WORKSHEET 10.0 Initial Cue:

Initial Conditions:

0 You are just about to attend training in the simulator as a licensed reactor operator.

0 The site declares an ALERT in response to an event in the plant.

Where are you to report?

Explain the location of this area.

USNRC Initial Licensing Examination Seabrook Station June 2003 RO Section A.4 Question Page 4 of 6

ADMINISTRATIVE Q U EST1 ON WORKSHEET Question:

Initial Conditions:

You are just about to attend training in the simulator as a licensed reactor operator.

0 The site declares an ALERT in response to an event in the plant.

Where are you to report and what are your duties?

Explain the location.

Answer:

The SSREP directs control room operators to report to the Operational Support Center (OSC).

The OSC is near the normal RCA entry point by the HP office.

USNRC Initial Licensing Examination Seabrook Station June 2003 RO Section A.4 Question Page 5 of 6

TEAR-OFF SHEET FOR APPLICANT This is a closed reference question.

The question has two parts.

Initial Conditions:

0 You are just about to attend training in the simulator as a licensed reactor operator.

0 The site declares an ALERT in response to an event in the plant.

Where are you to report?

Explain the location of this area.

Write your answers below and verbally explain them to the examiner.

USNRC Initial Licensing Examination Seabrook Station June 2003 RO Section A.4 Question Page 6 of 6

ASM I N I STRAT IVE QU EST10 N WORKSHEET RO Administrative Question Section A.4.2 ON-WATCH COMMUNICATIONS Examinee:

NRC Examiner:

Facility Evaluator:

Date:

Method of Testing Simulated Performance:

Actual Performance:

Classroom:

Simulator:

Plant:

WA reference: 2.4.39 Knowledge of the ROs responsibilities in emergency plan implementation.

USNRC Initial Licensing Examination Seabrook Station June 2003 RO Section A.4 Question Page 1 of 6

ASMlNlSTRATlVE QUESTION WORKSHEET VERIFICATION OF COMPLETION Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of attempts:

Time to complete:

Question documentation Responses to questions Result: SAT or UNSAT (circle one)

Examiners signature and date:

USNRC Initial Licensing Examination Seabrook Station June 2003 RO Section A.4 Question Page 2 of 6

ASM I N I STRAT IVE QU EST1 ON WORKSH EET 1.0 Task Number and

Description:

Position:

RO Task Number: N/A

2.0 Conditions

e The applicant is the secondary control room operator (balance of plant operator).

e A SGTR is in progess.

e Main Steam Line Monitor is in high alarm.

3.0 Standards

The applicant must provide the correct response in accordance with ER 1.I, Classification of Emergencies 4.0 Student materials None.

5.0 Limitations on performance:

None.

6.0

References:

SSER, Emergency Response Manual

7.0 Setting

Classroom/Simulator USNRC Initial Licensing Examination Seabrook Station June 2003 RO Section A.4 Question Page 3 of 6

ASMINISTRATWE QUESTION WORKSHEET 8.0 Safety Considerations:

None 9.0 Approximate Completion Time:

10 minutes.

10.0 Initial Cue:

This is a closed-reference question.

This is a two-part question.

A STGR is in progress. The Main Steam Line Monitor for the ruptured steam generator is in high alarm. You are the Balance Of Plant operator.

1) Why is it important to notify the SM if the ruptured steam generator ASDV is lifting?
2) How will the SM use this information?

USNRC Initial Licensing Examination Seabrook Station June 2003 RO Section A.4 Question Page 4 of 6

ASMINISTRATIVE QUESTION WORKSHEET QUESTION:

A STGR is in progress. You are the Balance Of Plant operator.

I) Why is it important to notify the SM if the ruptured steam generator ASDV is lifting?

2) How will the SM use this information?

ANSWER:

1) This is a potential radiological release.
2) The SM is required to make a dose assessment using ODPS for E-Plan classification.

USNRC Initial Licensing Examination Seabrook Station June 2003 RO Section A.4 Question Page 5 of 6

TEAR-OFF SHEET FOR APPLICANT This is a closed-reference question.

This is a two-part question.

A STGR is in progress. You are the Balance Of Plant operator.

I)

Why is it important to notify the SM if the ruptured steam generator ASDV is lifting?

2) How will the SM use this information?

USNRC Initial Licensing Examination Seabrook Station June 2003 RO Section A.4 Question Page 6 of 6

JOB PERFORMANCE MEASURE WORKSHEET SRO Administrative JPM #I Section A.l LOSS OF RHR COOLING TIME TO BOIL DETERMINATION Examinee:

NRC Examiner:

Facility Evaluator:

Date:

Method of Testing Simulated Performance:

Actual Performance:

Classroom:

Simulator:

Plant:

WA reference: 2.1.25 Ability to obtain and interpret station reference materials such as graphs, monographs, and tables which contain performance data.

USNRC Initial Licensing Examination Seabrook Station June 2003 SRO Section A.l JPM #I Page 1 of 6

JOB PERFORMANCE MEASURE WORKSHEET VERIFICATION OF COMPLETION Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of attempts:

Time to complete:

Question documentation Responses to questions Result: SAT or UNSAT (circle one)

Examiners signature and date:

USNRC Initial Licensing Examination Seabrook Station June 2003 SRO Section A.l JPM #I Page 2 of 6

-~

JOB PERFORMANCE MEASURE WORKSHEET 1.o 2.0 3.0 4.0 5.0 6.0 7.0 8.0 9.0 Task Number and

Description:

Position:

SRO Evaluate Loss of cooling conditions and determine time to boiling.

Conditions:

0 0

0 0

0 0

Standards:

Use the appropriate attachment of OS1213.02, Loss of RHR While Operating at Reduced Inventory or Mid-Loop Conditions.

Student Materials:

When the applicant finds AOP OSI213.02, give the applicant a copy of OS1213.02 to mark-up.

Limitations on performance:

None.

References:

The plant is in mode 6.

Reactor vessel is being drained to install nozzle dams.

Reactor vessel level is at minus (-)38 inches.

Both RHR pumps are lost and cannot be recovered.

RCS temperature was 162F prior to the loss of both RHR pumps.

The plant has been shutdown for 280 hours0.00324 days <br />0.0778 hours <br />4.62963e-4 weeks <br />1.0654e-4 months <br />.

0 081213.02, Loss of RHR While Operating at Reduced Inventory or Mid Loop Conditions.

Setting:

Simulator or classroom.

Safety Considerations:

None Approximate Completion Time:

10 minutes USNRC Initial Licensing Examination Seabrook Station June 2003 SRO Section A.l JPM #I Page 3 of 6

JOB PERFORMANCE MEASURE WORKSHEET 10.0 Initiating Cue:

Given the following conditions, determine the time until boiling in the RCS.

0 The plant is in mode 6.

0 Reactor vessel is being drained to install nozzle dams. The current level is at minus (-)38 inches.

0 Both RHR pumps are lost and cannot be recovered.

0 RCS temperature was 162F prior to the loss of both RHR pumps.

0 The plant has been shutdown for 280 hours0.00324 days <br />0.0778 hours <br />4.62963e-4 weeks <br />1.0654e-4 months <br />.

Write your answer below and verbally explain to the examiner.

USNRC Initial Licensing Examination Seabrook Station June 2003 SRO Section A.l JPM #I Page 4 of 6

PERFORMANCE CHECKLIST D=Discuss ELEMENTSTEP P=Perform

  • denotes a S=Simulate critical step STANDARD EVALUATION INITIALSDATE
  • denotes critical standard SAT UNSAT
1.

P Start time Initiating cue read.

  • 2.

P References Figure OS1213.02-Locates and uses 5, Time to Boiling vs Time After Shutdown for RCS Water Level at Reduced Inventory (below minus 36 inches)

Figure OS1213.02-5.

  • 3.

P Determines time to boiling.

Determines time to boiling to be approximately 13 +1/-2 minutes.

CUE: When applicant gives examiner answer, inform applicant The JPM is complete.

USNRC Initial Licensing Examination Seabrook Station June 2003 SRO Section A.1 JPM #1 Page 5 of 6

Tear-Off Sheet for Applicant Given the following conditions, determine the time until boiling in the RCS.

The plant is in mode 6.

0 Reactor vessel is being drained to install nozzle dams. The current level is at minus (-)38 inches.

0 Both RHR pumps are lost and cannot be recovered.

0 RCS temperature was 162F prior to the loss of both RHR pumps.

0 The plant has been shutdown for 280 hours0.00324 days <br />0.0778 hours <br />4.62963e-4 weeks <br />1.0654e-4 months <br />.

Write your answer below and verbally explain to the examiner.

USNRC Initial Licensing Examination Seabrook Station June 2003 SRO Section A.l JPM #I Page 6 of 6

JOB PERFORMANCE MEASURE WORKSHEET SRO Administrative JPM #2 Section A.1 REVIEW A SHUTDOWN MARGIN CALCULATION Examinee:

NRC Examiner:

Facility Evaluator:

Date:

Method of Testing Simulated Performance:

Actual Performance:

Classroom:

Simulator:

Plant:

WA reference: 2.1.25 Ability to obtain and interpret station reference materials such as graphs, monographs, and tables which contain performance data.

USNRC Initial Licensing Examination Seabrook Station June 2003 RO Section A.l JPM #2 Page 1 of 8

JOB PERFORMANCE MEASURE WORKSHEET VERIFICATION OF COMPLETION Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of attempts:

Time to complete:

Question documentation Responses to questions Result: SAT or UNSAT (circle one)

Examiners signature and date:

USNRC Initial Licensing Examination Seabrook Station June 2003 RO Section A. 1 JPM #2 Page 2 of 8

JOB PERFORMANCE MEASURE WORKSHEET 4.O 2.0 0

0 3.0 4.0 5.0 6.0 Task Number and

Description:

Position:

SRO 001 01 00401 Perform Shutdown Margin Calculation Conditions:

The unit has just completed a natural circulation cooldown to 160F after a reactor trip that occurred 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> ago.

The reactor operator has just given the US a shutdown margin calculation to review.

Standards:

0 Review a completed SDM calculation for 160OF.

Determine that the shutdown boron concentration needed (column D of Form A) is incorrect.

0 Use RXI 707, "Shutdown Margin Surveillance".

Student Materials:

0 Copy of the Tear-Off Sheet 0

Calculator 0

RX1707, Shutdown Margin Surveillance, Rev. 7, Chg.3.

0 Primary Tech Data Book, (BOL) - Curves RE-02 (rev 01-091 1) & RE-I8 (rev 01 01).

0 Completed copy of M I 7 0 7 Form A with error.

Limitations on performance:

Simulate/Perform all steps. Verbalize all actions to the evaluator.

Even if requested, no Peer Checks will be provided during the JPM.

References:

Procedures:

RX1707, Shutdown Margin Surveillance.

Manuals:

Primary Technical Data Book.

USNRC Initial Licensing Examination Seabrook Station June 2003 RO Section A. 1 JPM #2 Page 3 of 8

JOB PERFORMANCE MEASURE WORKSHEET KA Description Parameters.

SYS 192002 KI.13 Calculate SDM using procedures and given plant Value ROISRO 3.513.7 7.0 8.0 9.0 10.0 0

Setting:

Classroom. The Primary Technical Data Book containing COLR RE 21 Cycle 9 was used to generate the key and must be given to the applicants to complete this JPM.

Safety Considerations:

None Approximate Completion Time:

20 minutes Initiating Cue:

Initial conditions:

The unit has just completed a natural circulation cooldown to 160F after a reactor trip that occurred 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> ago.

You had ordered the primary operator to perform a SDM calculation for 160F with Xenon included. The operator has finished the task and has handed you Form A for review.

Your task is to perform a supervisory review of the shutdown margin determination to determine if it is satisfactory.

I1.O Attachments 0

RX1707, Shutdown Margin Surveillance e Completed RX1707 Form A, with error, for applicant.

Completed RX1707 Form A as answer key.

Primary Technical Data Book (COLR RE 21 Cycle 9)

USNRC Initial Licensing Examination Seabrook Station June 2003 RO Section A.1 JPM #2 Page 4 of 8

PERFORMANCE CHECKLIST D=Discuss ELEMENTISTEP STANDARD EVALUATION IN ITIALWDATE P=Perform

  • denotes a
  • denotes critical S=Simulate critical step standard SAT UNSAT P

Start time:

Initiating cue read.

CUE:

peer check your actions. Please continue with the task.

If the applicant requests a Peer Check at any time during the JPM, respond: NO one is available to

1.

P For the RCS average Determines required RE-2 temperature of 160F, OBTAIN concentration:

the required shutdown boron Refers to figure RE-2.

concentration from Primary Technical Data Book Figure Verifies required boron RE-2. RECORD this value (A) concentration for RCS on Form A, Shutdown Margin average temperature of Determination - MODEs 3, 4 160F (MI 707A value and 5.

A). (1 135 ppm)

CUE:

If the applicant asks what current Xenon is, respond: Xenon is worth 3177 ppm

2.

P To take credit for xenon, PERFORM the following:

a. OBTAIN the xenon worth from the calculated point COO36 or from Reactor Engineering. RECORD this value (B) on Form A, Shutdown Margin Determination - MODEs 3, 4 and 5.

Performs the following:

a. Verifies Xenon is included in the calculation and is recorded in column B.

(3177 pcm)

b. OBTAIN differential boron
b. Verifies DBW from Figure RE-18.

(1 4.063 pcm/ppm) worth (DBW) from TDB Figure RE-18. USE the value corresponding to the appropriate RCS temperature range. The value corresponding to RCS temperature below 530°F is the most conservative for this application and shall be used for RCS temperatures below 530°F. RECORD the value used (C) on Form A, Shutdown Margin Determination - Modes 3,4,

& 5.

c. DETERMINE the Shutdown *c. Calculates required USNRC Initial Licensing Examination Seabrook Station June 2003 RO Section A.l JPM #2 Page 5 of 8

PERFORMANCE CHECKLIST D=Discuss ELEMENTETEP P=Perform

  • denotes a S=Simulate critical step CUE:

NOTE:

  • 3.

Boron Concentration, including xenon, (D) by dividing the xenon worth (B) by the DBW (C). Subtract this value from the required Shutdown Boron Concentration (A).

RECORD this value (D) on Form A, Shutdown Margin Determination - MODES 3,4 And 5, e.g., [D = A - (BIG)].

If the number is negative, RECORD a zero.

STANDARD

  • denotes critical standard shutdown boron concentration.

(RXI 707A value k 20 ppm of key).

(909 ppm; applicants copy says 1037ppm due to xenon being entered into the calculation as 1377 vice 31 77)

EVALUATION IN ITIALWDATE SAT UNSAT When asked of current boron concentration: Chemistry reports that the RCS boron concentration is 980 ppm.

SDM is adequate (existing boron concentration is greater than that required at 160F).

P RECORD the Existing RCS Determines current boron concentration is adequate as follows:

Boron Concentration (E) on Form A, Shutdown Margin And 5. COMPARE it to the concentration.

Required Boron Concentration:

Determination - MODES 3,4 0

Observes existing boron --

a. If taking credit for xenon, COMPARE the Existing Boron Concentration (E) to the Shutdown Boron Concentration including xenon (D). NOTIFY the SS/US if the existing Boron Concentration is less than the required Boron Concentration.
a.

Performs the following:

0 Compares existing boron concentration to required boron concentration.

  • 0 Determines that existing boron concentration is adequate.

NOTE: the applicant should note an error in the calculation of required shutdown boron concentration. It is not critical that they identify that xenon is incorrect, but they must realize the existing RCS boron concentration is adequate vice inadequate.

CUE:

The JPM is complete.

5.

Stop time Start - Stop time is I 20 USNRC Initial Licensing Examination Seabrook Station June 2003 RO Section A.l JPM #2 Page 6 of 8

D=Discuss ELEMENTETEP P=Perform

  • denotes a S=Simulate

, critical step PERFORMANCE CHECKLIST STANDARD EVALUATION INITIALWDATE

  • denotes critical standard SAT UNSAT minutes.

Evaluator calculates the time to complete the task.

USNRC Initial Licensing Examination Seabrook Station June 2003 RO Section A. 1 JPM #2 Page 7 of 8

Tear-Off Sheet for Applicant Initial conditions:

The unit has just completed a natural circulation cooldown to 160F after a reactor trip that occurred 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> ago.

You had ordered the primary operator to perform a SDM calculation for 160F, with Xenon included, in accordance with RX1707. The operator has finished the task and has handed you Rx1707 Form A for review.

Your task is to perform a supervisory review of the shutdown margin determination to determine if it is satisfactory.

Verbally explain your determination to the examiner.

USNRC Initial Licensing Examination Seabrook Station June 2003 RO Section A.l JPM #2 Page 8 of 8

SRO EXAM - APPLICANT HANDOUT

@I Q

RCS CONCENTRATION BORON GREATER THAN (XENON CREDIT)

PPM)

REQUIRED SHUTDOWN BORON EXISTING RCS BORON TIMEDATE NITIALS Date:

06102-03/03 Time Date:

/

/

Time RCS TAVG (OF) 160°F Date:

(4 SHUTDOWN BORON (From RE-2)

(PPM) 1135 Time

( A - (BE)) (PPM) 1037 Date:

/

I Time (YESMO) 980 NO Performed by:

Date:

I

/

Time Date:

/

I Time Form A: Shutdown Margin Determination MODES 3,4 And 5 (B)

(Pew XENON WORTH (C0036) 3177 (C)

DIFFERENTIAL BORON WORTH (From RE-1 8)

(PCMRPM) 14.063 Verified by: I Performed by:

Verified by: 1 Performed by:

Verified by: 1 Performed by:

Verified by: 1 Performed by:

Verified by:

I Performed by:

Verified by:

US Review RX 1707 Rev. 07 Chg 03 Page llof 15

ROISRO KEY NRC EXAM Form A: Shutdown Margin Determination MODES 3,4 And 5 (E)

EXISTING RCS BORON (PPM) 980 1

Date:

RCS BORON GREATERT REQUIRED OIESMO)

YES 06102-03/03 Time Date:

I 1

Time Date:

1 1

Time Verified by: 7 Date:

Time Date:

I 1

I 1

Time Performed1 Date:

1 Verified by:

I 1

i Time (A)

SHUTDOWN BORON (From RE-2)

PPM) 1135

03)

XENON WORTH (C0036)

W M )

3177 DIFFE-(PCM/ppM)

BORON WORTH (From RE-1 8) 14.063

@)

SHUTDOWN BORON CONCENTRATION (XENON CREDIT)

( A - 03/C)) W M )

909 INITIALS Performed by: i Verified by:

Performed by: 1 US Review RX 1707 Rev. 07 Chg 03 Page llof 15

JOB PERFORMANCE MEASURE WORKSHEET SRO Administrative JPM #3 Section A.2 REVIEW OF CIRCULATING WATER LUBE WATER PUMP TAGOUT Examinee:

NRC Examiner:

Facility Evaluator:

Date:

Method of Testing Simulated Performance:

Actual Performance:

Classroom:

Simulator:

Plant:

WA reference: 2.2.13 Knowledge of tanning and clearance procedures.

USNRC Initial Licensing Examination Seabrook Station June 2003 SRO Section A.2 JPM #3 Page 1 of 6

JOB PERFORMANCE MEASURE WORKSHEET VERIFICATION OF COMPLETION Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:

Number of attempts:

Time to complete:

Question documentation Responses to questions Result: SAT or UNSAT (circle one)

Examiner's signature and date:

USNRC Initial Licensing Examination Seabrook Station June 2003 SRO Section A.2 JPM #3 Page 2 of 6

JOB PERFORMANCE MEASURE WORKSHEET 1.o 2.0 3.0 4.0 5.0 6.0 7.0 8.0 Task Number and

Description:

Position:

SRO Task Number: N/A Conditions:

The applicant will receive a work package with a tagout for administrative review.

The tagout isolates Circulating Water Lube Water Pump '6 mechanically and electrically. The danger tag for the breaker switch is sequenced after the breaker. The pump suction valve is tagged before the discharge valve in the tagout.

You will provide the applicant with the following references if asked: PID 1CW-620675,1-NHY-301016 SHCY3a and 1 -NHY-301016 SHCY3b. MA 4.2 will NOT be available to the applicant.

Standards:

The applicant must identify that the breaker switch should be danger tagged prior to the breaker itself. The applicant should determine that the pump's discharge valve should be shut and tagged before the suction valve. The applicant must not sign the tagout as being satisfactory.

Student Materials:

0 Copy of the Tear-Off Sheet.

0 Work Package for Circ Water Lube Water pump 'By, including Tag List with errors.

0 PlDs and Electrical schematics.

Limitations on performance:

None.

References:

MA 4.2, "Equipment Tagging and Isolation" Setting:

Classroom/Simulator Safety Considerations:

None USNRC Initial Licensing Examination Seabrook Station June 2003 SRO Section A.2 JPM #3 Page 3 of 6

JOB PERFORMANCE MEASURE WORKSHEET 9.0 Approximate Completion Time:

15 minutes.

10.0 Initial Cue:

You are to review the tagout in this work package for technical adequacy.

Inform the examiner of the results of your review.

For example, if the tagout is satisfactory, state: "I have reviewed the tagout and it is satisfactory. I would sign it as satisfactory". Conversely, if you find problems with the tagout, state: "I would not sign this as satisfactory because Ask the examiner for any references you may need.

1 I

.O Attachments 0

Work package including tag list with errors.

0 Schematics 1-NHY-301016 SHCY3a and 1-NHY-301016 SHCY3b.

PID 1-CW-B20675.

USNRC Initial Licensing Examination Seabrook Station June 2003 SRO Section A.2 JPM #3 Page 4 of 6

PERFORMANCE CHECKLIST D=Discuss ELEMENTKTEP P=Perform

  • denotes a S=Simulate critical step STANDARD
  • denotes critical standard EVALUATION INITIALWDATE SAT UNSAT
1.

P Read applicant initial cue and Time started:

begin JPM.

CUE: Give applicant the work package containing the tagout to review.

NOTE: The applicant should use the rules for tagging in MA 4.2, "Equipment Tagging and Isolation", Figure 5.2 CUE: Give the applicant the appropriate drawings when they attempt to use the PID 'stick'.

  • 2.

P Place control switch tags on tnforms the examiner that control switch 1-be danger tagged in the OFF position prior to tagging the supply breaker.

components prior to breaker.

manipulating the supply CW-P-136-B-CS should

  • 3.

P To prevent suction line over pressurization, close the pump discharge valve prior to closing the suction valve and monitor suction pressure to ensure leakage past the valve is NOT excessive.

  • 4 P

"Sign On' Clearance Section Verification as "Approved" Informs examiner that the CW lube water pump discharge valve should be shut and tagged before the suction valve.

Informs examiner that he/she would NOT sign this tagout as "approved" due to the two flaws identified.

CUE: When applicant identifies both errors and informs examiner of approval status, inform the applicant "The JPM is over" USNRC Initial Licensing Examination Seabrook Station June 2003 SRO Section A.2 JPM #3 Page 5 of 6

Tear-Off Sheet for Applicant You are to review the tagout in this work package for technical adequacy.

MA 4.2 is not available for use.

Inform the examiner of the results of your review. For example, if the tagout is satisfactory, state: "I have reviewed the tagout and it is satisfactory. I would sign it as satisfactory". Conversely, if you find problems with the tagout, state: "I would not sign this as satisfactory because n

USNRC Initial Licensing Examination Seabrook Station June 2003 SRO Section A.2 JPM #3 Page 6 of 6

DO NOT USE FOR TAG PLACEMENT OR REMOVAL Tag List for WWIO-22-05 Clearance ONLINE CYCLE 9 Tag ID 6/2/03 0800 Page I of I Noun Name 1 -CW-P-136-B-BKR 1-CW-P-136-B-CS 1 -CW-V-88-B I-CW-V-104-8 CW LUBE WATER PUMP B BREAKER AT MCC-273 <CY3>

CW LUBE PUMP B CONTROL SWITCH AT MCB-FF CW-P-1368 S U CTI 0 N ISOLATION DISCHARGE ISOLATION CW-P-1368 I+-- -

Location Not Required Not Required Not Required Not Required Place.

Place.

Serial Config Danger Locked Open Required 0

Danger Off Not Required 0

Danger Locked Not 1

1 Closed 1

Required 0

Danger Locked Not 1

1 Closed I Required Not Not Not Required Required Required Not Not Not Required Required Required Not Not Not Required Required Required

Tag List for WWIO-22-05 Clearance ONLINE CYCLE 9 Not Required 6/2/03 0800 Page I of I Not Required I

I DO NOT USE FOR TAG PLACEMENT OR REMOVAL 1 -CW-V-I 04-B I SOLATI 0 N DISCHARGE ISOLATION CW-P-1368 Tag ID I

NounName Location Tag Serial 0

0 0

0 Place.

Seq.

1 (2)

Notes Place.

Config Locked Open Danger Not Required l-CW-P-136-B-BKR CW LUBE WATER PUMP B BREAKER AT CW LUBE PUMP 8 CONTROL SWITCH AT MCC-273 <CY3>

MCB-FF CW-P-1368 SUCTION Not Required 1 -CW-P-I 36-B-CS Not Required Danger Off Not Required I

-CW-V-88-B I Danger Locked Closed 3

(4)

Not Required Not Required Not Required Not Required Locked Closed 4

(3)

Not Required Not Required Not Required Not Required Danger Two Errors present. Control switch should be tagged before breaker then the discharge valve should be tagged before the suction valve. Bold numbers in the Place Sequence denote required order of placement.

JOB PERFORMANCE MEASURE WORKSHEET SRO Administrative JPM #4 Section A.3 CONTAMINATED INJURED MAN PROCEDURE Examinee:

NRC Examiner:

Facility Evaluator:

Date:

Method of Testing Simulated Performance:

Actual Performance:

Classroom:

Simulator:

Plant:

WA reference: 2.3.4 Knowledge of radiation exposure limits and contamination control, including permissible levels in excess of those authorized.

USNRC Initial Licensing Examination Seabrook Station June 2003 SRO Section A.3 JPM #4 Page 1 of 7

JOB PERFORMANCE MEASURE WORKSHEET VERIFICATION OF COMPLETION Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of attempts:

Time to complete:

Question documentation Responses to questions Result: SAT or UNSAT (circle one)

Examiners signature and date:

USNRC Initial Licensing Examination Seabrook Station June 2003 SRO Section A.3 JPM #4 Page 2 of 7

JOB PERFORMANCE MEASURE WORKSHEET I.o 2.0 e

0 0

0 0

0 e

0 3.0 4.0 5.0 Task Number and

Description:

Position:

SRO Task Number: N/A Applicant must respond to a contaminated, injured worker in accordance with OD1.32. The applicant is required to execute a medical emergency data sheet up to and including step 7.

Conditions:

The plant is in mode 6. You are the US.

A resin sluice was in progress for the letdown ion exchangers.

During the sluice, water backed up to the funnel quickly, which startled the vendor at the funnel.

The vendor slipped and hit his head on the ground and is bleeding from a 6" cut on his head.

The resinhater mixture spilled over the funnel and spilled about 2 gallons on and around the vendor.

HP technicians report the man, John Doe, is highly contaminated and likely overexposed.

A spill has been called away and HP technicians are at the scene.

The spill has been isolated.

The injured man is unconscious and breathing heavy.

Standards:

The applicant must provide the correct response in accordance with 001.32, "Medical Emergency Response" Student Materials:

Copy of the Tear-Off Sheet.

After applicant identifies to proper procedure to use, give them a copy of OD1.32.

Limitations on performance:

None.

6.0

References:

OD1.32, "Medical Emergency Response" USNRC Initial Licensing Examination Seabrook Station June 2003 SRO Section A.3 JPM #4 Page 3 of 7

~

~~~~

JOB PERFORMANCE MEASURE WORKSHEET

7.0 Setting

Classroom/Simulator 8.0 Safety Considerations:

None 9.0 Approximate Completion Time:

15 minutes.

10.0 Initial Cue:

This is an open reference question.

I nit ial Conditions:

The plant is in mode 6. You are theUS.

A resin sluice was in progress for the letdown ion exchangers.

During the sluice, water backed up to the funnel quickly, which startled the vendor at the funnel.

The vendor slipped and hit his head on the ground and is bleeding from a 6 cut on his head.

The resinhater mixture spilled over the funnel and spilled about 2 gallons on and around the vendor.

HP technicians report the man, John Doe, is highly contaminated and likely overexposed.

A spill has been called away and HP technicians are at the scene.

The spill has been isolated.

The injured man is unconscious and breathing heavy.

What is the required medical response to this situation?

USNRC Initial Licensing Examination Seabrook Station June 2003 SRO Section A.3 JPM #4 Page 4 of 7

PERFORMANCE CHECKLIST D=Discuss EL EM ENTISTEP STANDARD P=Perform

  • denotes a
  • denotes critical S=Simulate critical step standard EVALUATION INITIALWDATE SAT UNSAT P

Start time:

Initiating cue read.

CUE:

When the applicant locates the master copy of OD1.32, hand them ODl.32.

  • I P

Locate 001.32 Applicant locates OD1.32. Examiner provides a copy for mark-up.

  • 2.

S Notify Station EMTs, and Simulates notifying the EMTs and activating the 91 I pager for site EMTs to respond (uses direct dial pushbutton on US desk or uses 62-91 I).

activate the 91 1 pager for site EMTs to respond.

  • 3.

P Initiate medical emergency data sheet.

a.

P Completes data in section 1 Completes section 1 Fills in date, time, callers name, phone ext, and injured personnels name.

-conscious: no

-breathing: yes

-type of injury: head injurylbleeding

-location: PAB

-hazards: contaminated --

b.

S Makeshrerifies notifications in Explains process of section 2 and records time.

notifications in section 2 and records time.

CUE: Examiner to applicant, The site ambulance is available.

C.

S Page site EMTs or call site Simulates contacting ambulance cell phone.

site ambulance.

d.

S Notify Security to which Simulates contacting ambulance is responding.

security to tell them the USNRC initial Licensing Examination Seabrook Station June 2003 SRO Section 14.3 JPM #4 Page 5 of 7

PERFORMANCE CHECKLIST D=Discuss ELEMENTKTEP STANDARD EVALUATION INITIALWDATE P=Perform

  • denotes a
  • denotes critical S=Simulate critical step standard SAT UNSAT site ambulance is responding (any site phone).

CUE: Examiner to applicant, From the EMTs at the scene: ALS is not necessary

e.

S Send a vendor supervisor to Simulates contacting the medical facility receiving the injured.

John Does supervisor and sending him to the medical facility.

CUE: Examiner to applicant: Exeter hospital is available.

f.

S If overexposed, initiate a I hour

  • Simulates initiating a 1-report and see figure 6.2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> report.

Figure 6.2 decision tree results: CONTACT MEDICAL TREATMENT PROVIDER (FIG 6.3)

AND INDICATE PATIENT IS OVEREXPOSED, CONTAMINATED AND INJURED.

Simulates calling Exeter Hospital(direct dial pushbutton on US desk phone).

CUE:

The JPM is complete.

4.

Stop time Start - Stop time is I 20 minutes.

Evaluator calculates the time to complete the task.

USNRC Initial Licensing Examination Seabrook Station June 2003 SRO Section A.3 JPM #4 Page 6 of 7

TEAR-OFF SHEET FOR APPLICANT This is an open reference question.

Initial Conditions:

e 0

0 e

e e

e 0

0 The plant is in mode 6. You are the US.

A resin sluice was in progress for the letdown ion exchangers.

During the sluice, water backed up to the funnel quickly, which startled the vendor employee at the funnel.

The vendor employee slipped and hit his head on the ground and is bleeding from a 6" cut on his head.

The resinhater mixture spilled over the funnel and spilled about 2 gallons on and around the vendor.

A spill has been called away and HP technicians are at the scene.

The spill has been isolated.

HP technicians report the man, John Doe, is highly contaminated and likely overexposed The injured man is unconscious and breathing heavy.

What is the required medical response to this situation?

USNRC initial Licensing Examination Seabrook Station June 2003 SRO Section A.3 JPM #4 Page 7 of 7

JOB PERFORMANCE MEASURE WORKSHEET SRO Administrative JPM #5 Section A.4 GENERAL EMERGENCY CLASSIFICATION, PAR DETERMINATION, AND NOTI FlCATlONS Examinee:

NRC Examiner:

Facility Evaluator:

Date:

Method of Testing Simulated Performance:

Actual Performance:

Classroom:

Simulator:

Plant:

WA reference: 2.4.38 Ability to take actions called for in the facility emergency plan, including (if required) supporting or acting as emergencv coordinator.

USNRC Initial Licensing Examination Seabrook Station June 2003 SRO Section A.4 JPM #5 Page 1 of 10

JOB PERFORMANCE MEASURE WORKSHEET VERIFICATION OF COMPLETION Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:

Number of attempts:

Time to complete:

Question documentation Responses to questions Result: SAT or UNSAT (circle one)

Examiner's signature and date:

USNRC Initial Licensing Examination Seabrook Station June 2003 SRO Section A.4 JPM #5 Page 2 of 10

JOB PERFORMANCE MEASURE WORKSHEET 1.0 Task Number and

Description:

Task number is N/A.

Applicant makes an EAL determination (General Emergency), PAR, and makes required notifications.

2.0 Conditions

The reactor tripped from 100%.

Safety Injection has automatically actuated due to a Large Break LOCA.

Plant conditions:

0 0

0 RCS sub-cooling is O O F.

0 Pzr Level is zero.

0 0

0 No RDMS alarms present.

0 RCS pressure is approx. 40 psig, Containment pressure is 26 psig and decreasing.

Containment Sump Level indicates 3 feet.

Containment Post-LOCA monitor indicates 15 Whr.

Upper and lower wind direction indicates 21 0.

The CSF status is as follows:

0 Sub-criticality: Green 0

Core Cooling: Yellow 0

Heat Sink: Green 0

Integrity: Red 0

Containment: Orange 0

Inventory: Yellow B RHR Pump is tagged out for maintenance work, A RHR Pump has tripped on over-current.

Crew has entered ECA-I.I Loss of Emergency Coolant Recirculation.

3.0 Standards

The applicant correctly identifies the event as a General Emergency and makes the correct PAR and notifications as described below.

USNRC Initial Licensing Examination Seabrook Station June 2003 SRO Section A.4 JPM #5 Page 3 of 10

JOB PERFORMANCE MEASURE WORKSHEET SYS 2.4 4.0 5.0 6.0 KA Description Value 2.4.38 Abilitv to take actions called for in the facilitv E-Plan.

RO/SRO 2.2/4.0 Student Materials:

Copy of tear-off sheet.

e ER-1.1, Classification Of Emergencies, Rev. 34.

ER-I.1A, Emergency Classification Flow Chart, Rev. 30.

ER-I.2, Emergency Plan Activation, Rev. 42.

Limitations on performance:

Simulate all required communications.

References:

ER-1.1, Classification of Emergencies.

ER-1.2, Emergency Plan Activation.

7.0 8.0 9.0 10.0 Setting:

Classroom setting.

Safety Considerations:

None Approximate Completion Time:

20 minutes.

Initial Cue:

You are the Work Center Supervisor (WCS).

Plant conditions:

0 e

e e

e e

0 0

0 0

The reactor tripped from 100%.

Safety Injection has automatically actuated due to a Large Break LOCA.

RCS pressure is approx. 40 psig, Containment pressure is 26 psig and decreasing.

RCS sub-cooling is OOF.

PZR level is zero.

Containment Sump Level indicates 3 feet.

Containment Post-LOCA monitor indicates 15 R/hr.

No RDMS alarms present.

Upper and lower wind direction indicates 210°.

USNRC Initial Licensing Examination Seabrook Station June 2003 SRO Section A.4 JPM #5 Page 4 of 10

JOB PERFORMANCE MEASURE WORKSHEET The CSF status is as follows:

0 Sub-criticality: Green 0

Core Cooling: Yellow 0

Heat Sink: Green 0

Integrity: Red 0

Containment: Orange 0

Inventory: Yellow 0

B RHR Pump is tagged out for maintenance work, A RHR Pump has tripped on over-current.

0 Crew has entered ECA-1.I Loss of Emergency Coolant Recirculation.

SM to WCS, WCS (or applicants name), evaluate present conditions and determine required emergency plan classification. Once condition is determined perform emergency plan activation and notification up to completion of state notification fact sheet.

Simulate the notifications to the examiner.

USNRC Initial Licensing Examination Seabrook Station June 2003 SRO Section A.4 JPM #5 Page 5 of 10

PERFORMANCE CHECKLIST D=Discuss ELEMENTETEP P=Perform

  • denotes a S=Simulate critical step I.

CUE:

I.

a.
  • b.
c.

CUE:

  • 2.

CUE:

CUE:

CUE:

STANDARD EVALUATION IN ITIALWDATE

  • denotes critical standard SAT UNSAT P

Start time:

Initiating cue read.

If the applicant requests a Peer Check at any time during the JPM, respond: NO one is available to peer check your actions. Please continue with the task.

P Determine emergency action Implements ER-I. I P

Applicant determines whether None should be circled.

P Applicant determines highest Applicant should circle EAL P

Applicant determines all Applicant should circle EAL level.

any CSFs are challenged.

miscellaneous emergency 15f General Emergency.

conditions.

applicable miscellaneous emergency conditions.

15d Site Area Emergency.

If applicant reports to SM results - direct applicant to perform emergency plan activation.

P DETERMINE Schiller Station Applicant implements ER Activation:

1.2D General Emergency Checklist and uses flow chart:

HP has determined WRGM radiation levels are normal. No alarm condition exists.

Is there a WRGM high 0

Chooses No path alarm?

HP has determined Main Steamline radiation levels are normal. No alarm condition exists.

Is there a main Steam line Chooses No path monitor high alarm with an open ASDV or SRV on the affected line?

0 Select ER 1.2D step 3.

0

  • Determines Schiller Station not activated and goes to step 3.

When the student inquires about performing step 3 Notify Station Personnel inform student to assume the announcement has been initiated at <present time> and to continue with step 3.f.

f. Proceed to Step 6.
f. Proceeds to Step 6.

USNRC Initial Licensing Examination Seabrook Station June 2003 SRO Section A.4 JPM #5 Page 6 of 10

PERFORMANCE CHECKLIST D=Discuss ELEMENT/STEP STANDARD EVALUATION INITIALSDATE P=Perform

  • denotes a
  • denotes critical S=Simulate critical step standard SAT UNSAT
  • 5.

NOTE:

  • 6.

CUE:

P NOTIFY Guard Island Security Notifies Guard Island:

a. Contact the Guard island
  • a. Contacts the Guard Supervisor at x4006.

Island Supervisor.

An evaluator must be present to act as Guard island Security.

b. Provide the following
b. Provides the following:

information:

A General Emergency

  • 0 GE hasbeen has been declared.

declared.

0 Time of declaration.

  • 0 Time of Gaitronics announcement.

The emergency initiating

  • 0 15F condition designation.

0 Schiller Station i s h not

  • 0 Schiller Station not being activated (as activated.

determined above) e Direct implementation of

  • 0 Directs GN1332.00 --

procedure GNI 332.00, be implemented.

Security Response to a Declared Radiological Emergency.

c. Proceed to Step 7.

Goes to Step 7.

P COMPLETE ER-2.OB, State Completes ER-2.0B:

Notification Fact Sheet.

a. Block 1 - Leave Blank
a. Block I - leaves blank.

If asked, STED to WCS, Time of declaration was <current time> based on your announcement

b. Block 2 - Check General
  • b. Block 2 - checks GE Emergency time declared.

and enters time declared.

c. Block 3 - Complete using
c. Block 3:

the following information:

USNRC Initial Licensing Examination Seabrook Station June 2003 SRO Section A.4 JPM #5 Page 7 of 10

PERFORMANCE CHECKLIST D=Discuss ELEMENTBTEP STANDARD EVALUATION INITIALSDATE P=Perform

  • denotes a
  • denotes critical S=Simulate critical step standard SAT UNSAT CUE:

NO release is in progress from the plant vent. The lower wind direction is from 210°.7 If a release is in progress from the plant vent, enter Enters lower wind direction (210O) on the current upper wind ER-1.2D.

direction. For other conditions, enter the current lower wind direction -

FROM degrees.

Identify the appropriate 0

Selects the PAR GROUP A column based on the above wind direction to determine the towns to be evacuated and sheltered.

column 168 - 281.4 Check off the evacuated Checks ERPAA and sheltered towns on form ER-2.0BI Block 3.

Seabrook and Hampton Falls and ERPA D Hampton and North-Hampton EVACUATE. All other towns -

SHELTER.

Checks All NH and MA beaches e

should be checked off as EVACUATE NH evacuated and closed, respectively.

MASS Beaches.

Beaches and CLOSE

d. Block 4 - Self-explanatory
d. Block 4 - checks the emergency is continuing.

CUE:

STED to WCS, There has been no release.

e. Block 5 - Use guidance to
  • e. Block 5 - checks a determine if a release has radiological release occurred.

has not occurred.

NOTE: When student presents form for authorization: Make no comments on the information recorded.

Sign and fill in date and time. Return the signed form to the student.

USNRC Initial Licensing Examination Seabrook Station June 2003 SRO Section A.4 JPM #5 Page 8 of 10

PERFORMANCE CHECKLIST D=Discuss ELEMENTSTEP STANDARD EVALUATION INITIALS/DATE P=Perform

  • denotes a
  • denotes critical S=Simulate critical step standard SAT UNSAT
f. Block 6 - Self-explanatory
f.

Block 6 - STED authorizes by signing and filling in datehime.

CUE: When the applicant gets to step 8, Notify the States, stop them from navigating the procedure and ask them: What agency notifications are required and what time limits are associated with them?

  • 7 S

State Notification Requirements The states of New Hampshire and Massachusetts must be notified within 15 minutes after declaring an emergency. Use form ER 1.2E.

S Federal Notification The NRC must be Requirements notified within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

The headquarters operation officers is reached at 301-816-51 00.

CUE:

The JPM is complete.

9.

Stop time Start - Stop time is 5 20 minutes.

Evaluator calculates the time to complete the task.

USNRC Initial Licensing Examination Seabrook Station June 2003 SRO Section A.4 JPM #5 Page 9 of 10

TEAR-OFF SHEET FOR APPLICANT You are the Work Center Supervisor (WCS).

Plant conditions:

The reactor tripped from 100%.

Safety Injection has automatically actuated due to a Large Break LOCA.

RCS pressure is approx. 40 psig, Containment pressure is 26 psig and decreasing.

RCS sub-cooling is OOF.

PZR level is zero.

Containment Sump Level indicates 3 feet.

Containment Post-LOCA monitor indicates 15 Whr.

No RDMS alarms present.

Upper and lower wind direction indicates 21 Oo.

'B RHR Pump is tagged out for maintenance work; 'A RHR Pump has tripped on over-current.

Crew has entered ECA-1.I "Loss of Emergency Coolant Recirculation."

The CSF status is as follows:

Sub-criticality: Green Core Cooling: Yellow Heat Sink: Green Integrity: Red Containment: Orange Inventory: Yellow SM to WCS, "WCS (or applicant's name), evaluate present conditions and determine required emergency plan classification. Once condition is determined perform emergency plan activation and notification up to completion of state notification fact sheet."

Simulate the notifications to the examiner.

USNRC Initial Licensing Examination Seabrook Station June 2003 SRO Section A.4 JPM #5 10 Page I O of