ML031830315
| ML031830315 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| 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: ML031830315 (90) | |
Text
ES-301 Administrative Topics Outline Form ES-301-1 Facility: Seabrook Station Date of Examination: 6/02/03-6/05/03 Examination Level (circle one): RO Operating Test Number:
1 Administrative TopidSu bject escrbtion A. 1 A.2 A.3 A.4 QPTR Calculation JPM SDM Calculation JPM Tagout JPM High Radiation Area Question Contamination Control Question ROs Responsibilities During Emergency Plan implementation Describe method of evaluation:
- 2. TWO Administrative Questions 2.1.23 Ability to perform specific system and integrated plant procedures during all modes of plant operation. RO: 3.9.
JPM: Perform required QPTR due to PRNl failure.
2.1.25 Ability to obtain and interpret station reference materials such as graphs, monographs, and tables which contain performance data. R O 2.8.
JPM: Perform a SDM calculation for Natural Circulation Cooldown.
2.2.13 Knowledge of tagging and clearance procedures. RO: 3.6.
JPM: Generate a danger tagout 2.3.4 Knowledge of radiation exposure limits and contamination control, including permissible levels in excess of those authorized. RO: 2.5.
Question: Given the plant is in a Site Area Emergency, what is the highest dose a worker is allowed to receive in a nonsmergency operation.
2.3.1 Knowledge of IOCFR20 and related facility radiation control requirements. RO: 2.6.
Question: Requirements for a Locked High Rad Area.
2.4.39 Knowledge of the ROs responsibilities in emergency plan implementation. RO: 3.3.
Question: E Plan reporting requirements during training (off watch).
2.4.39 Knowledge of the ROs responsibilities in emergency plan implementation. RO: 3.3.
Question: Operator responsibilities during SGTR event.
JOB PERFORMANCE MEASURE WORKSHEET RO Administrative JPM #I Section A.l 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 operation.
USNRC Initial Licensing Examination Seabrook Station June 2003 RO Section A.l JPM #1 Page I 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 #1 Page 2 of 8
JOB PERFORMANCE MEASURE WORKSHEET KA Description SYS I.o 2.0 3.0 4.0 0
0 0
5.0 6.0 Value RO/SRO Task Number and
Description:
01 5 01 5 01 5 Position:
RO A I.04 Ability to monitor changes in QPTR.
3.5/3.7 K5.12 Knowledge of QPTR.
3.2/3.6 K5.16 Definition and calculation of QPTR.
2.9/3.4 01 50200501 Perform A Manual QPTR Calculation Conditions:
A Plant is now at 100%.
B. The main plant computer has been inoperable since yesterday C. The sevenday QPTR surveillance is scheduled to be done this shift.
D. Incore/Excore calibration was performed yesterday.
Standards:
Perform the manual QPTR surveillance per MI 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
OS1 000.05, Power Increase 0
ON1251.01, Loss Of Plant Computer*
USNRC Initial Licensing Examination Seabrook Station June 2003 RO Section A.l JPM #I Page 3 of 8
JOB PERFORMANCE MEASURE WORKSHEET 7.0 8.0 9.0 10.0 Setting:
Classroom Give the student a copy of 100% power NI cabinet values.
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-I 7 rev 01 1 5.
Safety Considerations:
None Approximate Completion Time:
20 minutes Initiating Cue:
Initial Conditions:
0 Plant is now at 100% power.
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 ELEMENT/STEP STANDARD EVALUATION INITIAL S/DATE P=Perform
- denotes a
- denotes critical S=Simulate critical step standard SAT UNSAT
- 1.
P Start time:
Initiating cue read.
0 Obtains a copy of RX1703.
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 sunreitlance 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 Inoperable:
- a. RECORD the current output a.
Records detectors from the top (A) and bottom (B) detector of each channel on Form A, Quadrant Power Tilt Calculation Sheet.
output:
0 N41 topdetector --
0 N42 top detector 0
N43 top detector --
0 N44 top detector --
0 N41 bottom detector --
0 N42 bottom detector --
N43 bottom detector --
0 N44 bottom detector USNRC Initial Licensing Examination Seabrook Station June 2003 RO Section A.l JPM #1 Page 5 of 8
D=Discuss ELEMENTISTEP P=Perform
- denotes a S=Simulate critical step PERFORMANCE CHECKLIST STANDARD
- denotes critical standard NOTE:
Provide the student with a copy of RE47 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 (8) detector of each channel on Form A, 0
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 0
4 Bottom Detectors Calculation Sheet.
Calculates and records Normatized 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 Top the results on Form A, Quadrant Power Tilt 0
Bottom Calculation Sheet.
CALCULATE the Quadrant Power Tilt Ratio for each detector by dividing each 4Top normalized detector current by its associated average 0
4Bottom normalized detector current.
COMPLETE Form A, Quadrant Power Tilt Calculation Sheet.
Calculates and records QPTR for each detector:
EVALUATION INITIALSIDATE SAT UNSAT 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.l JPM #I Page 6 of 8
PERFORMANCE CHECKLIST D=Discuss ELEM ENTISTEP STANDARD EVALUATION INITIAWDATE P=Perform
- denotes a
- denotes critical S=Simulate critical step standard SAT UNSAT
- 7.
CUE:
- 8.
CUE:
- 9.
P RECORD the maximum power
- Identifies (circles) the --
tilt ratio on applicable RTS.
maximum power tilt ratio consistent with the answer key.
If the student does not report TS compliancelnoncompliance, provide the cue: Is QPTR within Tech.
Spec. Limits?
P If the Quadrant Power Tilt Ratio is determined to be greater than 1.02, immediately NOTIFY the SS/US.
The JPM is complete.
Stop time Evaluator calculates the time to complete the task.
USNRC initial Licensing Examination Seabrook Station June 2003 RO Section A.l JPM #1 Determines and reports that QPTR is within TS limits.
Start - Stop time is 5 20 minutes.
Page 7 of 8
Tear-Off Sheet for Applicant N42 TOP:
N42 BOTTOM:
N43 TOP:
N43 BOTTOM:
Initial Conditions:
183 224 200 222 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.
N44 TOP:
N44 BOTTOM:
You are the Primary Operator. You are going to perform the QPTR surveillance.
1 95 209 US to Primary Operator, Primary Operator (or students name), perform the QPTR Surveillance per RX1703. Discuss the results with me.
Channel & Location Current (microAmps)
I N41 TOP:
I 187 I
1 N41 BOTTOM:
I 198 I
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.1 PERFORM 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 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 RO Section A.l JPM #2 Page 2 of 7
JOB PERFORMANCE MEASURE WORKSHEET 1.o 2.0 3.0 4.0 5.0 6.0 Task Number and
Description:
Position:
RO 001 01 00401 Perform Shutdown Margin Calculation 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.
Standards:
Calculate the boron concentration required to satisfy the SDM requirements for 160°F.
Use RX1707, Shutdown Margin Surveillance.
Student Materials:
0 0
Calculator Copy of the Tear-Off Sheet RX1707, Shutdown Margin Surveillance, Rev. 7, Chg.3.
Primary Tech Data Book, (BOL) - Curves RE-02 (rev 01-091 1) & RE-I8 (rev 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. I.
1, SDM greater than 200°F.
Manuals:
Primary Technical Data Book.
USNRC Initial Licensing Examination Seabrook Station June 2003 RO Section A1 JPM #2 Page 3 of 7
JOB PERFORMANCE MEASURE WORKSHEET KA Description SYS 192002 K I.I3 Calculate SDM using procedures and given plant parameters.
Value ROISRO 3.513.7 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 MI 707, determine if SDM is satisfactory.
The chemist will have the current RCS boron concentration shortly.
11.O Attachments RX1707, Shutdown Margin Surveillance Blank RX1707 Form A for applicant.
0 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.l JPM #2 Page 4 of 7
PERFORMANCE CHECKLIST D=Discuss ELEMENTSTEP STANDARD EVALUATION INITIALS/DATE 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 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:
0 Refers to figure RE-2. --
Records required boron concentration for existing RCS average temperature (MI 707A value A). (I 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,
& 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 JPM #2 Page 5 of 7
PERFORMANCE CHECKLIST D=Discuss ELEMENTSTEP STANDARD EVALUATION I NITIALS/DATE 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 Shutdown Boron Concentration (A).
RECORD this value (D) on Form A, Shutdown Margin Determination - MODES 3, 4 And 5, e.g., [D = A - (BE)].
If the number is negative, RECORD a zero.
boron concentration.
(MI 707A value f 20 ppm of key).
this value from the required (909 PPm)
CUE:
NOTE:
- 3.
CUE:
- 5.
When asked of current boron concentration: Chemistry reports that the RCS boron concentration is 980 pprn.
SDM is adequate (existing boron concentration is greater than that required at 160F).
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 Determinesthat existing boron concentration is adequate.
The JPM is complete.
Stop time Evaluator calculates the time to complete the task.
Start - Stop time is I 20 minutes.
USNRC Initial Licensing Examination Seabrook Station June 2003 RO Section A. 1 JPM #2 Page 6 of 7
Tear-Off Sheet for Applicant initial 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.
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.
USNRC Initial Licensing Examination Seabrook Station June 2003 RO Section A.l JPM #2 Page 7 of 7
RO/SRO KEY NRC EXAM (E)
EXISTING RCS BORON (PPW 980 TIMEIDATE RCS BORON GREAERTHAN REQUIRED
( Y E S n w YES Date:
06102-03/03 Time Performed by: 1 Date:
I
/
Time Verified1 Date:
Performed by:
I RCS TAVG (OF) 1 I Verified by:
160°F I
Date:
Time Date:
/
I Time Date:
Form A: Shutdown Margin Determination MODES 3,4 And 5
( 4
@I (C)
S W O N WORTH DIFFERENTIAL BORON (C0036)
BORON WORTH (From RE-2)
(From RE-18)
- 0)
SHUTDOWN BORON CONCENTRATION (XENON CREDIT)
( A - WC)) 0 909 4
Performed by:
Verified by: I Performed by:
Verified by:
Performed by:
Verified by:
Performed by:
Verified by:
US Review RX 1707 Rev. 07 Chg 03 Page llof 15
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 taminn 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 I.o 2.0 3.0 4.0 e
e e
e e
e 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, 1 -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 I-NHY-301016 SHCY3a Schematic I-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 I-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 '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.
4 1.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 ELEMENTETEP P=Perform
- denotes a S=Simulate critical step STANDARD
- denotes critical standard EVALUATION I NITIALSDATE SAT UNSAT
- 1.
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
P P
Place control switch tags on components prior to manipulating the supply breaker.
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.
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 he/she 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 6 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 WWlO-22-05 Clearance ONLINE CYCLE 9 Tag Place.
Place.
Reset TY Pe Config Seq.
Config.
Caution Required Required Danger or Off Not Not Danger Locked Not Not Open Required Required Danger Locked Not Not Closed Required Required Danger Locked Not Not Closed Required Required 6/2/03 0800 Page t o f.I Rest.
Notes Seq.
Not Not Required Required Not Not Required Required Not Not Required Required Not Not Required Required B CONTROL SWTCH AT MCB-FF 1 -CW-P-I 36-B-BKR
~
-~
C W L E E Not Required WATER PUMP B BREAKER AT MCC-273 <CY3>
1-CW-V-104-8 1 -CW-V-08-B CW-P-I 368 Not Required DISCHARGE ISOLATION CW-P-1368 SUCTION ISOLATION Tag Serial 0
Not Required 0
0 0
ADMINISTRATIVE QUESTION WORKSHEET 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 Knowledae 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
ADMINISTRATIVE 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
ADMINISTRATIVE QU ESTlON WORKSHEET 1.o 2.0 3.0 4.0 0
0 0
0 5.0 6.0 7.0 Task Number and
Description:
Position:
RO/SRO Task Number: N/A Conditions:
The site has declared a Site Area Emergency due to a LOCA.
You are directed to manipulate a valve in the RHR vault.
Standards:
The applicant must provide the correct answers in accordance with SSER 4.3, "Radiation Protection During Emergency Conditions
Student Materials:
Copy of the Tear-Off Sheet.
SSER, "Emergency Response Manual" SSREP, "Seabrook Station Radiological Emergency Plan" SSRP, "Radiation Protection Manual" Limitations on performance:
None.
References:
SSER 4.3, "Radiation Protection During Emergency Conditions" Setting:
Classroom/Simulator USNRC Initial Licensing Examination Seabrook Station June 2003 RO Section A.3 Question Page 3 of 6
ADMlN ISTRATIVE 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.
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 4 of 6
ADMl N ISTRATIVE QUESTION WORKSHEET QU EST1 ON:
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 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 Directu.
USNRC Initial Licensing Examination Seabrook Station June 2003 RO Section A.3 Question Page 5 of 6
ADMINISTRATIVE QU EST1 ON WORKSHEET 8.0 Safety Considerations:
None 9.0 Approximate Completion Time:
10 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:
Danger - High Radiation Area 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.
There is a barricade in front of the door with a motion-actuated strobe.
0 The door is unlocked but closed.
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
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.
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 hamination Seabrook Station June 2003 RO Section A.3 Question Page 6 of 6
ADMINISTRATIVE QUEST1 ON 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: 2.3.1 Knowledge of 10CFR20 and related facilitv radiation control requirements.
USNRC Initial Licensing Examination Seabrook Station June 2003 RO Section A.3 Question Page I of 6
ADMINISTRATIVE QUESTION WORKSH EET 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 1.0 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.
Complete set of Technical Specifications 0
SSRP 5.0 Limitations on performance:
None.
6.0
References:
7.0 Setting
Classroom/Simulator USNRC Initial Licensing Examination Seabrook Station June 2003 RO Section A.3 Question Page 3 of 6
~
~~
~~
AD MI NlSTRATlVE 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 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 Enter" 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:
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.
e The door is unlocked but closed.
There is no one in the VCT room.
e 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:
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
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.4 Question Page 2 of 6
ADMl N ISTFWTIVE QU EST1 ON WORKSHEET I
.o 2.0 3.0 4.0 5.0 6.0 7.0 8.0 9.0 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:
L 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:
10 minutes.
USNRC Initial Licensing Examination Seabrook Station June 2003 RO Section A.4 Question Page 3 of 6
ADMINISTRATIVE QU EST1 ON 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 Sectiin A.4 Question Page 4 of 6
ADMINISTRATIVE QUESTION WORKSHEET Question:
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 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:
You are just about to attend training in the simulator as a licensed reactor operator.
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
ASMlNlSTRATlVE QUESTION 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
ASMl N ISTRATIVE QU EST1 ON 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.4 Question Page 2 of 6
ASMl N ISTRATIVE QUESTION WORKSHEET 1.0 Task Number and
Description:
Position:
RO Task Number: N/A
2.0 Conditions
0 The applicant is the secondary control room operator (balance of plant operator).
0 A SGTR is in progess.
0 Main Steam Line Monitor is in high alarm.
3.0 Standards
The applicant must provide the correct response in accordance with ER 1.1, "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
ASMl Nl STRAT IVE QU EST1 ON WORKSHEET 8.0 Safety Considerations:
None 9.0 Approximate Completion Time:
I O 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.
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 4 of 6
AS M I N I STRAT IVE QUESTION WORKSHEET QUESTION:
A STGR is in progress. 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?
ANSWER:
- 1) This is a potential radiological release.
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.
- 1) why is it important to notify the SM if the ruptured steam generator ASDV is lifting?
USNRC Initial Licensing Examination Seabrook Station June 2003 RO Section A.4 Question
- 2) How will the SM use this information?
Page 6 of 6
ES-301 Administrative Topics Outline Form ES-301-1 Facility: Seabrook Station Examination Level: SRO Date of Examination: 6/02/03-6/05/0:
Operating Test Number:
1 Administrative Topidsubject Descridion Describe method of evaluation:
- 2. TWO Administrative Questions SDM Calculation Review A.2 Tagouts A.3 Radiation control A.4 Emergency Classification, Notifications, and PAR.
JPM 2.1.25 Ability to obtain and interpret station reference materials such as as graphs, monographs, and tables which contain performance data. SRO: 3.1.
JPM: Evaluate loss of cooling conditions and determine time to boiling from chart.
2.1.25 Ability to obtain and interpret station reference materials such as as graphs, monographs, and tables which contain performance data. SRO: 3.1.
JPM: Review a SDM calculation for Natural Circulation Cooldown.
2.2.13 Knowledge of tagging and clearance procedures. SRO:
3.0.
JPM: Review a tagout request.
2.3.4 Knowledge of radiation exposure limits and contamination control, including permissible levels in excess of those authorized. SRO: 3.1 JPM: Contaminated injured man actions.
2.4.38 Ability to take actions called for in the facility emergency pian, including (if required) supporting or acting as emergency coordinator. SRO: 4.0 JPM: Given a set of conditions, the applicant will make an EAL determination, PAR, and make required notifications.
JOB PERFORMANCE MEASURE WORKSHEET e
SRO Administrative JPM # I Section A.1 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 Abilitv 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 #1 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 #1 Page 2 of 6
JOB PERFORMANCE MEASURE WORKSHEET 1.o 2.0 3.0 I
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:
The plant is in mode 6.
0 Reactor vessel is being drained to install nozzle dams.
0 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 />.
Standards:
Use the appropriate attachment of OS1213.02, 'Loss of RHR While Operating at Reduced Inventory or MicCLoop Conditions".
Student Materials:
When the applicant finds AOP OS1213.02, give the applicant a copy of OS1213.02 to mark-up.
Limitations on performance:
None.
References:
OS1213.02, "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 #l 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 #1 Page 4 of 6
PERFORMANCE CHECKLIST D=Discuss ELEMENTSTEP STANDARD EVALUATION INITIALS/DATE P=Perform
- denotes a
- denotes critical S=Simulate critical step standard SAT UNSAT I.
P Start time Initiating cue read.
- 2.
P References Figure OS1 213.02-Locates and uses 5, Time to Boiling vs Time After Shutdown for RCS Water Level at Reduced Inventory (below minus 36 inches)
Figure OS1 21 3.02-5.
- 3.
P Determines time to boiling.
Determines time to boiling to be approximately 13 +I/-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.l JPM #1 Page 5 of 6
Tear-Off Sheet for Applicant 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.
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 />.
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.l 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, monoqraphs, 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.l JPM #2 Page 2 of 8
JOB PERFORMANCE MEASURE WORKSHEET I.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 160°F.
0 Determine that the shutdown boron concentration needed (column D of Form A) is incorrect.
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 01-0911) & RE-I8 (rev Completed copy of M I 7 0 7 Form A with error.
01 0 1 ).
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.l JPM #2 Page 3 of 8
JOB PERFORMANCE MEASURE WORKSHEET SYS KA Description 192002 KI.I3 Calculate SDM using procedures and given plant Value RO/SRO 3.513.7
7.0 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.
8.0 Safety Considerations:
None 9.0 Approximate Completion Time:
20 minutes 10.0 Initiating Cue:
Initial conditions:
0 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.
I I
.O Attachments 0
RX1707, Shutdown Margin Surveillance 0
Completed M I 7 0 7 Form A, with error, for applicant.
0 Completed M I 7 0 7 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 JPM #2 Page 4 of 8
PERFORMANCE CHECKLIST D=Discuss ELEMENTISTEP STANDARD EVALUATION INITIALS/DATE P=Perform
- denotes a
- denotes critical S=Simulate critical step 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 CUE:
peer check your actions. Please continue with the task.
I.
P For the RCS average Determines required RE-2 temperature of 160F, OBTAIN concentration:
concentration from Primary RE-2. RECORD this value (A) on Form A, Shutdown Margin Determination - MODEs 3, 4 and 5.
the required shutdown boron 0
Refers to figure RE-2. --
Technical Data Book Figure Verifies required boron --
concentration for RCS average temperature of 160F (MI 707A value A). (1 135 ppm)
CUE:
- 2.
P To take credit for xenon, Performs the following:
If the applicant asks what current Xenon is, respond: Xenon is worth 3177 ppm PERFORM the following:
- a.
t
- b.
C.
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.
OBTAIN differential boron worth (DBW) from TDB Figure RE-18. USE the value corresponding to the appropriate RCS temperature range. The value corresponding to RCS temperature below 53OOF 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.
DETERMINE the Shutdown
- a. Verifies Xenon is included in the calculation and is recorded in column B.
(3177 pcm)
- b. Verifies DBW from Figure RE-1 8.
(14.063 pcm/ppm)
- c. Calculates required USNRC Initial Licensing Examination Seabrook Station June 2003 RO Section A.1 JPM #2 Page 5 of 8
PERFORMANCE CHECKLIST D=Discuss ELEMENTISTEP STANDARD P=Perform
- denotes a
- denotes critical S=Simulate critical step standard 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 - (BE)].
If the number is negative, RECORD a zero.
EVALUATION IN ITIALSIDATE SAT UNSAT shutdown boron concentration.
(RXl707A value f 20 ppm of key).
(909 ppm; applicants copy says 1037ppm due to xenon being entered into the calculation as 1377 vice 3177)
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 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:
boron concentration to required boron concentration.
0 Compares existing --
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 5 20 USNRC Initial Licensing Examination Seabrook Station June 2003 RO Section A.1 JPM #2 Page 6 of 8
D=Discuss ELEMENTETEP P=Perform
- denotes a S=Simulate critical step PERFORMANCE CHECKLIST STANDARD EVALUATION INITIALSDATE
- 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.l JPM #2 Page 7 of 8
Tear-Off Sheet for Applicant Initial conditions:
0 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
RO/SRO KEY NRC EXAM (B)
XENON WORTH (C0036)
(PCW 3177 Form A: Shutdown Margin Determination MODES 3,4 And 5 (C)
@)
DIFFERENTIAL SHUTDOWN BORON BORON WORTH CONCENTRATTON (From RE-18)
(XENON CREDIT)
(PcM/ppM)
( A - PO PPM) 14.063 909 Date:
06102-03/03 Time Date:
Time Date:
I
/
Time Date:
/
I Time Date:
Time Date:
Time RCS TAVG ("F) 160°F BORON (From RE-2)
(PPW 1135 (E)
EXISTING RCS BORON (PPM) 980 RCS BORON GREATERTHAN REQUIRED WSMO)
YES US Review Rx 1707 Rev. 07 Chg 03 Page llof 15 Performed by:
Verified by:
Performed by:
Verified by:
Performed by:
Verified by:
Performed by:
Verified by:
Performed by:
Verified by:
Performed by:
Verified by:
(4 TIMEfllATE RCS S"
TAVG (OF)
BORON (From RE-2)
(Ppw Date:
160°F 1135 06/02-03/03 Time Date:
I
/
Time Date:
1 1
Time Date:
/
I Time Date:
I
/
Time Date:
/
/
Time I
USReview XENON WORTH (C0036) v w 3177 RX 1707 Rev. 07 Chg 03 Page llof 15
JOB PERFORMANCE MEASURE WORKSHEET SRO Administrative JPM #3 Section A.2 REVIRN 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 taggina 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 'B' 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 I-CW-B20675,1-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 'B, 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. 1 would sign it as satisfactory". Conversely, if you find problems with the tagout, state: "I would not sign this as satisfactory because a#
Ask the examiner for any references you may need.
11.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 DsDiscuss ELEMENTISTEP STANDARD P=Perform
- denotes a
- denotes critical SsSimulate critical step standard EVALUATION IN ITIALSIDATE 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 Informs 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-I 36-B-CS Should
- 3.
P To prevent suction line over Informs examiner that the CW lube water pump discharge valve should be shut and tagged before the suction valve.
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 Informs examiner that heishe would NOT sign this tagout as "approved" due to the two flaws identified.
Verification as "Approved" 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 of0
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
Tag List for WWIO-22-05 Clearance ONLINE CYCLE 9 Noun Name Location Tag Tag Place.
Place.
Reset Serial Type Config Seq.
Config.
CW LUBE Not Required 0
Danger Locked Not Not WATER PUMP B Open Required Required BREAKER AT CW LUBE PUMP Not Required 0
Danger Off Not Not B CONTROL Required Required SWiTCH AT MCC-273 <CY3>
MCB-FF CW-P-1368 Not Required 0
Danger Locked Not Not SUCTION Closed Required Required iSOLATlON CW-P-1368 Not Required 0
Danger Locked Not Not DISCHARGE Closed Required Required ISOLATION Tag ID Rest.
Notes Seq.
Not Not Required Required Not Not Required Required Not Not Required Required Not Not Required Required 1 -CW-P-136 BKR 1 -CW-P-136-B-CS 1 -CW-V-88-B I
-CW-V-104-B I
I DO NOT US FOR TAG PLACEMENT OR REMOVAL 6/2/03 0800 Page I of I
Tag ID Noun Name Location Not Required Not Not Required Required 1 -CW-V-104-B CW-P-1368 DISCHARGE ISOLATION 6/2/03 0800 Page 1 of1 Tag List for WWIO-22-05 Clearance ONLINE CYCLE 9 Reset Rest.
Notes Config.
Place.
Place.
Config Locked Tag Serial Not Required 0
l-CW-P-136-B-BKR CW LUBE WATER PUMP B BREAKER AT CW LUBE PUMP B CONTROL SWITCH AT MCC-273 CY3>
MCB-FF 1-CW-P-I 36-B-CS Not Required 0
Danger 1-CW-V-88-B CW-P-1368 SUCTION ISOLATION Not Required 0
Danger Locked Closed Closed 3
(4)
(3) 4 Not Required 0
Danger Required Required Required Not I
Not I Not I
I 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 #M 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 SRO Section A.3 JPM #4 Page 2 of 7
JOB PERFORMANCE MEASURE WORKSHEET 1.o 2.0 0
0 0
0 0
0 0
0 0
3.0 4.0 5.0 Task Number and
Description:
Position:
SRO Task Number: N/A Applicant must respond to a contarninz..2d, 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 resin/water 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 OD1.32, Medical Emergency Response Student Materials:
0 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:
0 ODl.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:
I 5 minutes.
10.0 Initial Cue:
This is an open reference question.
Initial 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 resin/water 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 ELEMENT/STEP STANDARD P=Perform
- denotes a
- denotes critical S=Simulate critical step standard EVALUATION IN ITIALWDATE SAT UNSAT P
Start time:
Initiating cue read.
CUE:
When the applicant locates the master copy of OD1.32, hand them OD1.32.
- I P
Locate OD1.32 Applicant locates OD1.32. Examiner provides a copy for mark-up.
- 2.
S Notify Station EMTs, and Simulates notifying the --
activate the 91 I pager for site EMTs to respond.
EMTs and activating the 91 I pager for site EMTs to respond (uses direct dial pushbutton on US desk or uses 62-91 I).
- 3.
P Initiate medical emergency data sheet.
- a.
P Completes data in section 1 Completes section I Fills in date, time, callers name, phone ext, and injured personnels name.
-conscious: no
-breathing: yes
-type of injury: head injurybleeding
-location: PAB
-hazards: contaminated
- b.
S Makes/verifies 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 A.3 JPM #I4 Page 5 of 7
PERFORMANCE CHECKLIST D=Discuss ELEMENTKTEP P=Perform
- denotes a S=Simulate critical step STANDARD EVALUATION I NITIALWDATE
- denotes critical 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:
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 resinlwater 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 W Page 7 of 7
JOB PERFORMANCE MEASURE WORKSHEET SRO Administrative JPM #5 Section A.4 GENERAL EMERGENCY CLASSIFICATION, PAR DETERMINATION, AND NOTIFICATIONS Examinee:
NRC Examiner:
Facility Evaluator:
Date:
Method of Testing Simulated Performance:
Actual Performance:
Classroom:
Simulator:
Plant:
WA reference: 2.4.38 Abilitv to take actions called for in the facility emergency plan, including (if required) supporting or acting as emerqency 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 NIA.
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 RCS pressure is approx. 40 psig, 0
Containment pressure is 26 psig and decreasing.
0 RCS sub-cooling is OOF.
0 Pzr Level is zero.
0 0
0 No RDMS alarms present.
0 Containment Sump Level indicates 3 feet.
Containment Post-LOCA monitor indicates 15 Whr.
Upper and lower wind direction indicates 210O.
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-1.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 KA Description 2.4 2.4.38 Ability to take actions called for in the facility E-Plan.
4.0 Student Materials:
Value RO/SRO 224.0 Copy of tear-off sheet.
0 ER-1.I, Classification Of Emergencies, Rev. 34.
ER-1.IA, Emergency Classification Flow Chart, Rev. 30.
ER-1.2, Emergency Plan Activation, Rev. 42.
5.0 Limitations on performance:
Simulate all required communications.
6.0
References:
ER-I.I, 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:
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.
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:
Sub-criticality: Green 0
Core Cooling: Yellow 0
Heat Sink: Green 0
Integrity: Red Containment: Orange 0
Inventory: Yellow
'B' RHR Pump is tagged out for maintenance work, 'A RHR Pump has tripped on over-current.
0 Crew has entered ECA-1.1 "Loss of Emergency Coolant Recirculation."
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 Page 5 of 10
PERFORMANCE CHECKLIST D=Discuss ELEMENTISTEP P=Perform
- denotes a S=Simulate critical step
- 1.
CUE:
- 1.
- a.
- b.
C.
CUE:
- 2.
CUE:
CUE:
STANDARD
- denotes critical standard P
Start time:
Initiating cue read.
EVALUATION i N IT1 ALS/DATE SAT UNSAT 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 --
level.
any CSFs are challenged.
miscellaneous emergency 15f General Emergency.
conditions.
applicable miscellaneous emergency conditions.
P Applicant determines all Applicant should circle EAL 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.
0 Is there a WRGM high 0
Chooses No path
/
alarm?
HP has determined Main Steamline radiation levels are normal. No alarm condition exists.
0 is there a main Steam line 0
Chooses No path monitor high alarm with an open ASDV or SRV on the affected line?
0 Select ER I
.2D step 3.
- Determines Schiller Station not activated and goes to step 3.
CUE:
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 ELEMENTKTEP P=Perform
- denotes a S=Simulate critical step STANDARD EVAL UATl 0 N I N I TI ALS/DATE
- denotes critical standard SAT UNSAT
- 5.
P NOTIFY Guard Island Security Notifies Guard Island:
- a. Contact the Guard Island
- a. Contacts the Guard --
Supervisor at x4006.
Island Supervisor.
NOTE: An evaluator must be present to act as Guard Island Security.
- b. Provide the following
- b. Provides the following:
information:
A General Emergency
- a GEhasbeen has been declared.
declared.
a Time of declaration.
- a Time of Gaitronics announcement.
0 The emergency initiating 15F condition designation.
a Schiller Station is/is not
- a Schiller Station not --
being activated (as activated.
determined above) a Direct implementation of
- a Directs GN1332.00 --
procedure GNI 332.00, be implemented.
Security Response to a Declared Radiological Emergency.
- c. Proceed to Step 7.
0 Goes to Step 7.
- 6.
P COMPLETE ER-2.0B, State Completes ER-2.0B:
Notification Fact Sheet.
- a. Block 1 - Leave Blank
- a. Block I
- leaves blank.
CUE:
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 ELEMENTKTEP P=Perform
- denotes a S=Simulate critical step CUE:
CUE:
NOTE:
STANDARD EVALUATION IN IT1 AL S/DATE
- denotes critical standard SAT UNSAT NO release is in progress from the plant vent. The lower wind direction is from 210°.
If a release is in progress from the plant vent, enter the current upper wind direction. For other conditions, enter the current lower wind direction -
FROM degrees.
Identify the appropriate PAR GROUP A column based on the above wind direction to determine the towns to be evacuated and she1 tered.
Check off the evacuated and sheltered towns on form ER-2.0BY Block 3.
All NH and MA beaches should be checked off as evacuated and closed, respectively.
Block 4 - Self-explanatory e Enters lower wind direction (210O) on ER-1.2D.
e Selects the column 168 - 281.4 0
Checks ERPAA Seabrook and Hampton Falls and ERPA D Hampton and North-Hampton EVACUATE. All other towns -
SHELTER.
e Checks EVACUATE NH Beaches and CLOSE MASS Beaches. --
- d. Block 4 - checks the emergency is continuing.
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.
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 ELEMENTETEP P=Perform
- denotes a S=Simulate critical step STANDARD
- denotes critical standard EVALUATION IN IT1 ALS/DATE SAT UNSAT
- f. Block 6 - Self-explanatory
- f.
Block 6 - STED authorizes by signing and filling in date/time.
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 "8
S Federal Notification Requirements CUE:
"The JPM is complete."
The states of New Hampshire and Massachusetts must be notified within 15 minutes after declaring an emergency. Use form ER 1.2E.
The NRC must be 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.
- 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 SRO Section A.4 JPM #5 Page 9 of 10
TEAR-OFF SHEET FOR APPLICANT I
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 0
Inventory: Yellow 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 10 Page 10 of