ML022900730
| ML022900730 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 01/14/2002 |
| From: | Ernstes M Division of Reactor Safety II |
| To: | Christian D Virginia Electric & Power Co (VEPCO) |
| References | |
| 50-338/02-301, 50-339/02-301 | |
| Download: ML022900730 (202) | |
See also: IR 05000338/2002301
Text
North Anna
Final Admin
ES-301 Administrative Topics Outline Form ES-301-1 (R8, $1)
Facility: North Anna Power Station Date of Examination: 6/10-14/2002
Examination Level: SRO Operating Test Number: 1A
Administrative Describe method of evaluation:
Topic/Subject 1. ONE Administrative JPM, OR
Description 2. TWO Administrative Questions
A.1 Plant parameters JPM Determine the Quadrant Power Tilt Ratio by Hand
verification Calculation (1-PT-23)
(Both) Bank- R709; 015-A1.04, 3.5/3.7
Knowledge of JPM Respond to a loss of source-range nuclear instrumentation
Fuel Handling. during refueling (1-AP-4.1)
(Both) Bank - R714 (modified); G-2.2.30, 3.5/3.3
A.2 Tagging and JPM Review the expanded boundaries of a tagging order
Clearance New; G-2.2.13, 3.6/3.8
Procedures
(SRO)
A.3 Radiation JPM Determine Dose Rates with Airborne Activity Present.
Control New; G-2.3.1, 2.6/3.0
(Both)
A.4 Emergency JPM Given a set of plant conditions, determine applicable EPIP
Action Levels classification, including any required PAR's
and New; G-2.4.41, 2.3/4.1
Classifications
(SRO)
ES-301 Administrative Topics Outline Form ES-301-1 (R8, Si)
Facility: North Anna Power Station Date of Examination: 6/10-14/2002
Examination Level RO Operating Test Number: 1A
Administrative Describe method of evaluation:
Topic/Subject 1. ONE Administrative JPM, OR
Description 2. TWO Administrative Questions
A.1 Plant Parameters JPM Determine the Quadrant Power Tilt Ratio by Hand
Verification Calculation (1-PT-23)
(Both) Bank- R709; 015-A1.04, 3.5/3.7
Knowledge of JPM Respond to a loss of source-range nuclear instrumentation
fuel handling, during refueling (1-AP-4.1)
(Both) Bank - R714 (modified); G-2.2.30, 3.5/3.3
A.2 Tagging and JPM Expand the boundaries of a tagging order.
Clearance New; G-2.2.13, 3.6/3.8
Procedures
(RO)
A.3 Radiation JPM Determine Dose Rates with Airborne Activity Present.
Control New; G-2.3.1, 2.6/3.0
(Both)
A.4 Emergency JPM Given a set of plant conditions, make proper notifications
Communications for an Emergency Condition.
(RO) New; G-2.4.39, 3.3/3.1
NORTH ANNA POWER STATION
INITIAL LICENSE EXAMINATION
ADMINISTRATIVE
Classify an emergency event (SRO)
CANDIDATE
EXAMINER
Page 1 of 57 Rev. 0
NORTH ANNA POWER STATION
INITIAL LICENSE EXAMINATION
ADMINISTRATIVE
Task:
Classify an emergency event. (EPIP-1.01)
References:
EPIP-1.01, "Emergency Manager Controlling Procedure," Rev. 35
EPIP-1.05, "Response to General Emergency," Rev. 16
EPIP-1.06, "Protective Action Recommendations," Rev. 4
Validation Time: 13 min. Time Critical: Yes
Candidate:
NAME
Performance Rating: SAT UNSAT
Examiner: /
NAME SIGNATURE DATE
COMMENTS
Page 2 of 57 Rev. 0
Tools/Equipment/Procedures Needed:
EPIP-1.01, "Emergency Manager Controlling Procedure," Rev. 35
EPIP-1.05, "Response to General Emergency," Rev. 16
EPIP-1.06, "Protective Action Recommendations," Rev. 4
READ TO OPERATOR
DIRECTION TO TRAINEE:
I will explain the initial conditions, and state the task to be performed. All steps shall be performed
for this JPM, with the exception of any required communications, which shall be simulated.
Under no circumstances are you to operate any plant equipment. Ensure you indicate to me
when you understand your assigned task. To indicate that you have completed your assigned task
return the handout sheet I provided you.
INITIAL CONDITIONS:
Security reports that armed intruders entered the unit-2 main steam valve house.
Explosions were heard in the unit-2 main steam valve house and steam is issuing from within the building.
Narrow-range level on all three steam generators began rapidly decreasing immediately after the explosions
occurred.
Unit-2 tripped due to steam generator low level with steam flow-feed flow mismatch.
All three steam generators are depressurizing.
There is no steam reported in the Mechanical Equipment Room or the unit-2 Turbine Building.
Containment pressure and temperature are normal.
Security reports that the intruders have now been apprehended and the threat has been neutralized.
Operations shift "B"is designated for coverage.
INITIATING CUES:
You are requested to classify an emergency event in accordance with EPIP-1.01. Continue until you
have determined if an emergency action level has been exceeded, including the determination of any
applicable PAR. If a PAR is applicable, fill out a PAR form.
The time is now (After applicant understands the task, examiner to provide current time)
Page 3 of 57 Rev. 0
STEP 1: Obtain a copy of the appropriate procedure.
STANDARD: Operator obtains a copy of EPIP-1.01.
COMMENTS:
UNSAT
STEP 2: Determine the event category using the emergency action level table index.
(Step 1 .a) SAT
STANDARD: Operator determines that it is a Fuel Failure or Fuel Handling Accident (Tab C)
COMMENTS: UNSAT
STEP 3: Review the emergency action level tab associated with the event category.
(Step 1.b) SAT
STANDARD: Operator reviews the emergency action level tab.
COMMENTS: UNSAT
STEP 4: Use available resources to obtain indications of emergency conditions. (step
1 .c) SAT
STANDARD: Operator analyzes the initial conditions and compares them to the emergency
action level tab.
UNSAT
COMMENTS:
Page 4 of 12 Rev. 0
STEP 5: Verify emergency action level exceeded. (step 1 .d) CRITICAL.
STEP
STANDARD: Operator classifies the event as a General Emergency in accordance with tab
C-2. SAT
COMMENTS:
UNSAT
STEP 6: Record procedure initiation. (step 1.e)
STANDARD: Operator signs and dates the procedure.
COMMENTS:
UNSAT
STEP 7: Initiate a chronological log of events. (step 1.0
STANDARD: Operator states that he/she would initiate a chronological log of events.
COMMENTS:
UNSAT
STEP 8: Declare position of SEM. (step 1.g)
STANDARD: Operator declares the position of SEM.
COMMENTS:
UNSAT
STEP 9: Check conditions allow for normal implementation of emergency response
actions. (step 2) SAT
STANDARD: Operator states that he/she would initiate a chronological log of events.
COMMENTS: UNSAT
Page 5 of 12 Rev. 0
ISTEP 10: Check classification alert or higher. (step 3.a)II
STANDARD: Operator determines emergency classification is alert or higher.
COMMENTS:
UNSAT
STEP 11: Check if emergency assembly and accountability previously conducted. (step
3.b) SAT
STANDARD: Operator determines emergency assembly and accountability was not
previously conducted.
UNSAT
EXAMINER'S CUE: Emergency assembly and accountability have NOT yet been
performed.
COMMENTS:
STEP 12: Announce the emergency. (step 3.b RNO)
STANDARD: Operator simulates announcing the emergency.
COMMENTS:
UNSAT
STEP 13: Direct emergency communicators to initiate the applicable procedures. (step
4.a) SAT
STANDARD: Operator simulates contacting the emergency communicators to initiate EPIP
2.01 and EPIP-2.02.
UNSAT
EXAMINER'S CUE: The emergency communicators acknowledge your directions.
COMMENTS:
Page 6 of 12 Rev. 0
ISTEP 14: Direct Health Physics to initiate EPIP-4.01. (step 4.b)I
STANDARD: Operator simulates contacting Health Physics to initiate EPIP-4.01.
EXAMINER'S CUE: Health Physics acknowledges your direction.
UNSAT
COMMENTS:
STEP 15: Establish communications with the Security Shift Supervisor. (step 4.c)
STANDARD: Operator simulates contacting the Security Shift Supervisor and providing
current classification, coverage shift, and to initiate EPIP-5.09.
EXAMINER'S CUE: Security Shift Supervisor acknowledges your directions. UNSAT
COMMENTS:
STEP 16: Check TSC activated. (step 5)
STANDARD: Operator simulates contacting the TSC.
EXAMINER'S CUE: The TSC is activated.
UNSAT
COMMENTS:
STEP 17: Implement EPIP for emergency classification in effect. (step 6)
STANDARD: Operator obtains a copy of EPIP-1.05.
COMMENTS:
UNSAT
Page 7 of 12 Rev. 0
STEP 18: Record procedure initiation. (step 1)
STANDARD: Operator signs and dates the procedure.
COMMENTS:
UNSAT
STEP 19: Note time general emergency EAL was met. (step 2) CRITICAL
STEP
STANDARD: Operator records the time EAL was met in EPIP-1.05.
NOTE TO EXAMINER: The time recorded in procedure step 2 must be < 15 minutes
from the time stated in the initial conditions.
COMMENTS: UNSAT
STEP 20: Check if event announcement required. (step 3.a)
STANDARD: Operator determines announcement was previously done.
COMMENTS:
UNSAT
STEP 21: Initiate EPIP-1.06. (step 4)
STANDARD: Operator obtains a copy of EPIP-1.06.
COMMENTS:
UNSAT
STEP 22: Record procedure initiation. (step 1)
STANDARD: Operator signs and dates the procedure.
COMMENTS:
UNSAT
Page 8 of 12 Rev. 0
STEP 23: Use attachment 2 to determine initial PAR. (step 2)
STANDARD: Operator refers to attachment 2.
EXAMINER'S CUE: Offsite monitoring teams report that the projected dose at 5 miles is
2.5 Rem TEDE. The Radiological Assessment Coordinator has UNSAT
recommended an expanded PAR using EPIP-4.07 (examiner to provide
data sheet to applicant.)
COMMENTS:
STEP 24: Determine windspeed and three downwind sectors. (step 3.a)
STANDARD: Operator determines downwind sectors are Romeo, Alpha and Bravo.
COMMENTS:
UNSAT
STEP 25: Mark the appropriate PAR box in item 2. (step 3.b) CRITICAL
STEP
STANDARD: Operator performs the following:
"* Marks the Expanded PAR box and the Evacuate sectors box
"* Enters Romeo, Alpha and Bravo in the affected sector blanks SAT
- Enters 0 to 5 miles in the distance blanks
- Marks the Shelter sectors box
- Enters Romeo, Alpha and Bravo in the affected sector blanks
UNSAT
COMMENTS:
STEP 26: Sign and date form. (step 3.c)
STANDARD: Operator records signs and dates attachment 3.
COMMENTS:
UNSAT
Page 9 of 12 Rev. 0
ISTEP 27: Direct emergency communicators to notify offsite authorities of PAR. (step 4) 1
STANDARD: Operator states that he/she has completed the task.
EXAMINER'S CUE: Assume that another operator will complete the procedure.
UNSAT
COMMENTS:
END OF TASK
Page 10 of 12 Rev. 0
APPLICANT CUE SHEET
(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
Security reports that armed intruders have entered the unit-2 main steam valve house.
Explosions were heard in the unit-2 main steam valve house and steam is issuing from within the building.
Unit-2 tripped due to steam generator low level with steam flow-feed flow mismatch.
All three steam generators are depressurizing.
There is no steam reported in the Mechanical Equipment Room or the unit-2 Turbine Building.
Containment pressure and temperature are normal.
Narrow-range level on all three steam generators began rapidly decreasing immediately after the explosions
occurred.
Operations shift "B"is designated for coverage.
INITIATING CUES:
You are requested to classify an emergency event in accordance with EPIP-1.01. Continue until you have
determined if an emergency action level has been exceeded, including the determination of any applicable
PAR. If a PAR is applicable, fill out a PAR form.
The time is now (examiner to provide current time)
Page 11 of 12 Rev. 0
APPLICANT CUE SHEET
(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
The RAC recommends an expanded PAR as follows:
"* Evacuate downwind sectors from 0 - 5 miles
"* Shelter downwind sectors from 5 - 10 miles
The following meteorological conditions exist:
"* Wind speed is 12 mph
"* Wind direction is 180 degrees
Developed for the North Anna, June 2002, Initial Examination
U. S. Nuclear Regulatory Commission
Region II
A-3 Administrative Section
Page 12 of 12 Rev. 0
Title:
Determine Dose Rates with Airborne Activity Present
Page 13 of 12 Rev. 0
NRC-ADMIN-JPM-03
Page 1 of 4
JPM TITLE: Determine Dose Rates with Airborne Activity Present
JPM NUMBER: NRC-ADMIN-JPM-03
JPM REV. DATE: 03/14/02
TIME VALIDATION: MINUTES
AN 'X' BELOW INDICATES THE APPLICABLE METHOD(S) OF
TESTING WHICH MAY BE USED:
PERFORM: X SIMULATE: DISCUSS:
INSTRUCTOR'S INFORMATION
Task: Determine Dose Rates with Airborne Activity Present
Applicability Est Completion Time Actual Time
NUREG-1122 Importance Ratinas
GEN 2.3.1 Knowledge of 10 CFR: 20 and related facility radiation control requirements. (RO 2.6/SRO
3.0).
GEN 2.3.4 Knowledge of facility ALARA program. (RO 2.5/SRO2.9)
Conditions
- Task is to be PERFORMED in an area that has adequate reference material.
Standards
- Dose is correctly calculated with a respirator and without a respirator.
Page 1 of 12 Rev. 0
NRC-ADMIN-JPM-03
Page 2 of 4
READ TO THE TRAINEE
I will explain the initial conditions, and state the task to be performed. All steps shall be
performedlsimulated for this JPM. Ensure you indicate to me when you understand your assigned task.
To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
An NLO has been assigned the task of performing a valve lineup in the Auxiliary Building. The area
where the valves are located has a dose rate of 24 mR/Hr. and also has some airborne activity. From
experience the NLO knows that it will take 45 minutes to perform the valve lineup without a respirator,
or 75 minutes to complete the job with a respirator. If the job is done without a respirator the NLO will
receive 2 DAC-hours of internal exposure.
INITIATING CUES:
You have been directed to: Determine the dose the NLO will receive if he doesn't wear a respirator
while performing the valve lineup and the dose he will receive if he wears a respirator. Report to the Shift
Supervisor which method will be the lowest dose and keep exposure ALARA.
Page 2 of 12 Rev. 0
NRC-ADMIN-JPM-03
Page 3 of 4
. START TIME:
"*1. Calculates NLO dose without a respirator.
Standards
Calculates the dose to the NLO without a respirator.
0.75 hours8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br /> X 24 mR/hour = 18.0 mRem
2 DAC hours X 2.5 mRem/DAC-hour = 5
Total = 18.0 + 5 mRem = 23 mRem
Evaluator's Comments
- 2. Calculates NLO dose with a respirator.
Standards
Calculates the dose to the NLO with a respirator
1.25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> X 24 mRem/hour = 30 mRem.
Evaluator's Comments
- 3. Determines that the job should be performed without a respirator and reports findings to Shift
Supervisor.
Standards
Reports to Shift Supervisor that performance of work should be performed without a respirator
to achieve a dose that is ALARA. Calculates the dose to the NLO without a respirator ALARA.
Evaluator's Comments
- TERMINATE JPM AT THIS POINT ***
& STOP TIME:
Page 3 of 12 Rev. 0
NRC-ADMIN-JPM-03
Page 4 of 4
INITIAL CONDITIONS:
An NLO has been assigned the task of performing a valve lineup in the Auxiliary Building. The area
where the valves are located has a dose rate of 24 mR/Hr., and also has some airborne activity. From
experience the NLO knows that it will take 45 minutes to perform the valve lineup with out a
respirator, or 75 minutes to complete the job with a respirator. If the job is done without a respirator
the NLO will receive 2 DAC-hours of internal exposure.
INITIATING CUES:
You have been directed to: Determine the dose the NLO will receive if he doesn't wear a respirator
while performing the valve lineup and the dose he will receive if he wears a respirator. Report to the
Shift Supervisor which method will be the lowest dose and keep exposure ALARA
Page 4 of 12 Rev. 0
NRC-ADMIN-JPM-03
Page 5 of 4
NORTH ANNA POWER STATION
INITIAL LICENSE EXAMINATION
ADMINISTRATIVE
Prepare a follow-up report of emergency
to the state and local governments (RO)
CANDIDATE
EXAMINER
Page 5 of 57 Rev. 0
NRC-ADMIN-JPM-03
Page 6 of 4
NORTH ANNA POWER STATION
INITIAL LICENSE EXAMINATION
ADMINISTRATIVE
Task:
Prepare a follow-up report of emergency to the state and local governments. (EPIP-2.01)
References:
EPIP-2.01, "Notification of state and local governments," Rev. 24
Validation Time: 8 min. Time Critical: No
Candidate:
NAME
Performance Rating: SAT UNSAT
Examiner: /
NAME SIGNATURE DATE
COMMENTS
Page 6 of 57 Rev. 0
NRC-ADMIN-JPM-03
Page 7 of 4
Tools/Equipment/Procedures Needed:
EPIP-2.01, "Notification of state and local governments," Rev. 24
READ TO OPERATOR
DIRECTION TO TRAINEE:
Iwill explain the initial conditions, and state the task to be performed. All steps shall be performed
for this JPM. Ensure you indicate to me when you understand your assigned task. To indicate that
you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
A general emergency was declared 60 minutes ago.
A radioactive release is presently occurring.
The SEM describes the event as a "Loss of reactor coolant and loss of containment integrity."
Offsite assistance has NOT been requested.
Station monitoring teams have been dispatched offsite.
Station emergency personnel have been called in.
Onsite personnel have NOT been evacuated.
The prognosis of the situation is "worsening," according to the SEM.
All meteorological instrumentation is operable.
Main tower lower wind speed is 8 mph and average wind direction is 4100.
The recommended offsite protective actions are the expanded PAR, which is to evacuate 3600 from 0 to 5
miles and shelter downwind sectors from 5 to 10 miles.
The initial report of emergency to the state and local governments was transmitted from the control room.
You have taken turnover as the emergency communicator inthe LEOF.
INITIATING CUES:
You are requested to prepare the first follow-up report of emergency to the state and local
governments in accordance with EPIP-2.01, steps 5 - 18.
Page 7 of 57 Rev. 0
NRC-ADMIN-JPM-03
Page 8 of 4
STEP 1: Record message number (top of att. 2)
__SAT
blank.
STANDARD: Operator records "2" in the message #
COMMENTS:
UNSAT
STEP 2: Check off facility from which notification will be made (top of att. 2)
STANDARD: Operator checks LEOF blank.
COMMENTS:
UNSAT
STEP 3: Designate emergency classification. (item 1) CRITICAL
STEP
STANDARD: Operator checks the General Emergency box and enters today's date and the
time given in the initial conditions in item 1. SAT
EXAMINER'S CUE: Use the information provided in the Initial Conditions.
COMMENTS: UNSAT
STEP 4: Determine status of release of radioactive material. (item 2) CRITICAL
STEP
STANDARD: Operator checks the "Is presently occurring" box in item 2.
COMMENTS: SAT
UNSAT
Page 8 of 57 Rev. 0
NRC-ADMIN-JPM-03
Page 9 of 4
STEP 5: Record description of event. (item 3)
STANDARD: Operator enters "Loss of reactor coolant and loss of containment integrity" in
item 3.
COMMENTS: UNSAT
STEP 6: Determine assistance requested. (item 4)
STANDARD: Operator checks the "None" box in item 4.
COMMENTS:
UNSAT
STEP 7: Determine emergency response actions underway. (item 5)
STANDARD: Operator checks the "Station monitoring teams dispatched offsite" box and
"Station emergency personnel called in" box in item 5.
COMMENTS: UNSAT
STEP 8: Determine ifevacuation of onsite personnel is complete. (item 6)
STANDARD: Operator checks the "No" box in item 6.
COMMENTS:
UNSAT
STEP 9: Determine prognosis of situation. (item 7)
STANDARD: Operator checks the Worsening box in item 7.
COMMENTS:
UNSAT
Page 9 of 57 Rev. 0
NRC-ADMIN-JPM-03
Page 10 of 4
STEP 10: Determine status of meteorological instrumentation. (item 8)
STANDARD: Operator checks Based on onsite measurements box in item 8.
COMMENTS:
UNSAT
STEP 11: Record the meteorological data. (item 8)
STANDARD: Operator checks the Wind Direction box and enters NE or northeast, then
checks the Wind Speed box and enters 8 in item 8.
COMMENTS: UNSAT
STEP 12: Record your name. (item 9)
STANDARD: Operator enters his/her name in item 9.
COMMENTS:
UNSAT
STEP 13: Determine offsite protective actions recommended. (item 10) CRITICAL
STEP
STANDARD: Operator checks the Expanded box and the Evacuate 360 from 0 miles to 5
miles box in item 10.
COMMENTS:
UNSAT
Page 10 of 57 Rev. 0
NRC-ADMIN-JPM-03
Page 11 of 4
STEP 14: Record downwind sectors. (item 10) CRITICAL
STEP
STANDARD: Operator checks the Shelter sectors box and enters K, L, and M in the Shelter
sectors blanks, and enters 5 and 10 in the Shelter sectors blanks of item 10. __ SAT
COMMENTS:
UNSAT
STEP 15: Indicate that a report of radiological conditions will be sent. (item 11)
STANDARD: Operator checks the We will provide the report of radiological conditions to the
state representatives in the LEOF box in item 11.
UNSAT
COMMENTS:
STEP 16: Check emergency remains in effect. (step 4)
STANDARD: Operator initials step 4.
COMMENTS: UNSAT
STEP 17: Have SEM/RM approve and initial attachment. (step 5)
STANDARD: Operator states that he/she has completed the task.
EXAMINER'S CUE: Assume the SEM has initialed the attachment.
UNSAT
COMMENTS:
END OF TASK
Page 11 of 57 Rev. 0
NRC-ADMIN-JPM-03
Page 12 of 4
CANDIDATE CUE SHEET
(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
Ageneral emergency was declared 60 minutes ago.
Aradioactive release is presently occurring.
The SEM describes the event as a "Loss of reactor coolant and loss of containment integrity."
Offsite assistance has NOT been requested.
Station monitoring teams have been dispatched offsite.
Station emergency personnel have been called in.
Onsite personnel have NOT been evacuated.
The prognosis of the situation is "worsening," according to the SEM.
All meteorological instrumentation is operable.
Main tower lower wind speed is 8 mph and average wind direction is 4100.
The recommended offsite protective actions are the expanded PAR, which is to evacuate 3600 from 0 to 5
miles and shelter downwind sectors from 5 to 10 miles.
The initial report of emergency to the state and local governments was transmitted from the control room.
You have taken turnover as the emergency communicator in the LEOF.
INITIATING CUES:
You are requested to prepare the first follow-up report of emergency to the state and local
governments in accordance with EPIP-2.01, steps 5 - 18.
ES-301 Administrative Topics Outline Form ES-301-1 (R8, SI)
Facility: North Anna Power Station Date of Examination: 6/10-14/2002
Examination Level RO Operating Test Number: 1A
Administrative Describe method of evaluation:
Topic/Subject 1. ONE Administrative JPMV, OR
Page 12 of 57 Rev. 0
NRC-ADMIN-JPM-03
Page 13 of 4
Description 2. TWO Administrative Questions
A.1 Plant Parameters JPM Determine the Quadrant Power Tilt Ratio by Hand
Verification Calculation (1-PT-23)
(Both) Bank - R709; 015-A1.04, 3.5/3.7
Knowledge of JPM Respond to a loss of source-range nuclear instrumentation
fuel handling. during refueling (1-AP-4.1)
(Both) Bank - R714 (modified); G-2.2.30, 3.5/3.3
A.2 Tagging and JPM Expand the boundaries of a tagging order.
Clearance New; G-2.2.13, 3.6/3.8
Procedures
(RO)
A.3 Radiation JPM Determine Dose Rates with Airborne Activity Present.
Control New; G-2.3.1, 2.6/3.0
(Both)
A.4 Emergency JPM Given a set of plant conditions, make proper notifications
Communications for an Emergency Condition.
(RO) New; G-2.4.39, 3.3/3.1
ES-301 Administrative Topics Outline Form ES-301-1 (R8, Si)
Facility: North Anna Power Station Date of Examination: 6/10-14/2002
Examination Level: SRO Operating Test Number: 1A
Page 13 of 57 Rev. 0
NRC-ADMIN-JPM-03
Page 14 of 4
Administrative Describe method of evaluation:
Topic/Subject 1. ONE Administrative JPM, OR
Description 2. TWO Administrative Questions
A.1 Plant JPM Determine the Quadrant Power Tilt Ratio by Hand
parameters Calculation (1-PT-23)
verification Bank - R709; 015-Al.04, 3.5/3.7
(Both)
Knowledge of JPM Respond to a loss of source-range nuclear instrumentation
Fuel
Handling. during refueling (1-AP-4.1)
(Both) Bank - R714 (modified); G-2.2.30, 3.5/3.3
A.2 Tagging and JPM Review the expanded boundaries of a tagging order
Clearance New; G-2.2.13, 3.6/3.8
Procedures
(SRO)
A.3 Radiation JPM Determine Dose Rates with Airborne Activity Present.
Control New; G-2.3.1, 2.6/3.0
(Both)
A.4 Emergency JPM Given a set of plant conditions, determine applicable EPIP
Action Levels classification, including any required PAR's
and New; G-2.4.41, 2.3/4.1
Classifications
(SRO)
Page 14 of 57 Rev. 0
NRC-ADMIN-JPM-03
Page 15 of 4
Dominion
North Anna Power Station
JOB PERFORMANCE MEASURE EVALUATION
OPERATOR PROGRAM
INITIAL CONDITIONS
Prodac-250 computer has malfunctioned
Unit is stable at 100% power
All ex-core power-range channels are operable
The instrument technicians have obtained upper and lower detector currents and recorded them
on attachment 3 of 1-PT-23
INITIATING CUE
You are requested to calculate the maximum QPTR and determine the quadrant of the maximum
QPTR in accordance with 1-PT-23, attachment 3.
Page 15 of 57 Rev. 0
NRC-ADMIN-JPM-03
Page 16 of 4
Dominion
North Anna Power Station
JOB PERFORMANCE MEASURE EVALUATION
OPERATOR PROGRAM
R709
TASK
Determine the quadrant power tilt ratio by hand calculation (1-PT-23).
TASK STANDARDS
Normalized currents and QPTR are calculated to four decimal places and the quadrant of the
maximum QPTR is determined
K/A REFERENCE:
015-A1.04 (3.5/3.7)
ALTERNATE PATH:
N/A
TASK COMPLETION TIMES
Validation Time = 8 minutes Start Time =
Actual Time = minutes Stop Time =
Page 16 of 57 Rev. 0
NRC-ADMIN-JPM-03
Page 17 of 4
PERFORMANCE EVALUATION
Rating [ I SATISFACTORY [ I UNSATISFACTORY
Candidate (Print)
Evaluator (Print)
Evaluator's Signature /
Date
EVALUATOR'S COMMENTS
Page 17 of 57 Rev. 0
NRC-ADMIN-JPM-03
Page 18 of 4
Dominion
North Anna Power Station
(Evaluation)
OPERATOR PROGRAM
R709
READ THE APPLICABLE INSTRUCTIONS TO THE CANDIDATE
Instructions for Simulator JPMs
I will explain the initial conditions, and state the task to be performed. All control room steps
shall be performed for this JPM, including any required communications. I will provide initiating
cues and reports on other actions when directed by you. Ensure you indicate to me when you
understand your assigned task. To indicate that you have completed your assigned task return
the handout sheet I provided you.
Instructions for In-Plant JPMs
I will explain the initial conditions, and state the task to be performed. All steps, including any
required communications, shall be simulated for this JPM. Under no circumstances are you to
operate any plant equipment. I will provide initiating cues and reports on other actions when
directed by you. Ensure you indicate to me when you understand your assigned task. To
indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS
Prodac-250 computer has malfunctioned
Unit is stable at > 75% power
All ex-core power-range channels are operable
The instrument technicians have obtained upper and lower detector currents and recorded them
on attachment 3 of 1-PT-23
INITIATING CUE
Page 18 of 57 Rev. 0
NRC-ADMIN-JPM-03
Page 19 of 4
You are requested to calculate the maximum QPTR and determine the quadrant of the maximum
QPTR in accordance with 1-PT-23, attachment 3.
Page 19 of 57 Rev. 0
NRC-ADMIN-JPM-03
Page 20 of 4
TOOLS AND EQUIPMENT
Calculator
PERFORMANCE STEPS
START TIME
1 Record the expected 100% power current readings from the Procedure Step NA
Reactor Data Book.
ISAT[] UNSAT[]
STANDARDS currents
Operatorare calculated
obtains reactortodata decimal
four book andplaces
records detector
12 1Calculate the normalized detector currents. IProcedure Step NA I
ICRITICAL STEP JSAT[] UNSAT[] I
STANDARDS pNormalized detector currents are calculated to four decimal
placesI
Page 20 of 57 Rev. 0
NRC-ADMIN-JPM-03
Page 21 of 4
13 1Calculate the quadrant power tilt ratios. Procedure Step NA
CRITICAL STEP SAT[] UNSAT[ ]I
STANDARDS deUpper and lower quadrant power tilt ratios are calculated to four
decimals
4 Record theQPTR.
maximum maximum QPTR and the quadrant of the Procedure Step NA
CRITICAL STEP SAT[] UNSAT[ ]I
STANDARDS 1.0022 (+ .0002) is recorded as the maximum QPTR and N-42
lower is recorded as the quadrant of the maximum QPTR.
STOP TIME
Dominion
North Anna Power Station
JOB PERFORMANCE MEASURE EVALUATION
OPERATOR PROGRAM
INITIAL CONDITIONS
Page 21 of 57 Rev. 0
NRC-ADMIN-JPM-03
Page 22 of 4
Fuel movement is in progress
NIS SR LOSS OF DET VOLTAGE annunciator (1A-A1) has just alarmed
INITIATING CUE
You are requested to respond to a source-range nuclear instrumentation malfunction during
refueling using 1-AP-4.1.
Page 22 of 57 Rev. 0
NRC-ADMIN-JPM-03
Page 23 of 4
Dominion
North Anna Power Station
JOB PERFORMANCE MEASURE EVALUATION
OPERATOR PROGRAM
R714
TASK
Respond to a source-range nuclear instrumentation malfunction during refueling (1-AP-4.1).
TASK STANDARDS
Core alterations were stopped and the amplifier select switch was selected to an operable channel
K/A REFERENCE:
015-A2.02 (3.1/3.5)
TASK COMPLETION TIMES
Validation Time = 4 minutes Start Time =
Actual Time = minutes Stop Time =
Page 23 of 57 Rev. 0
NRC-ADMIN-JPM-03
Page 24 of 4
PERFORMANCE EVALUATION
Rating []SATISFACTORY [ I UNSATISFACTORY
Candidate (Print)
Evaluator (Print)
Evaluator's Signature /
Date
EVALUATOR'S COMMENTS
Page 24 of 57 Rev. 0
NRC-ADMIN-JPM-03
Page 25 of 4
Dominion
North Anna Power Station
(Evaluation)
OPERATOR PROGRAM
R714
READ THE APPLICABLE INSTRUCTIONS TO THE CANDIDATE
Instructions for Simulator JPMs
I will explain the initial conditions, and state the task to be performed. All control room steps
shall be performed for this JPM, including any required communications. I will provide initiating
cues and reports on other actions when directed by you. Ensure you indicate to me when you
understand your assigned task. To indicate that you have completed your assigned task return
the handout sheet I provided you.
Instructions for In-Plant JPMs
I will explain the initial conditions, and state the task to be performed. All steps, including any
required communications, shall be simulated for this JPM. Under no circumstances are you to
operate any plant equipment. I will provide initiating cues and reports on other actions when
directed by you. Ensure you indicate to me when you understand your assigned task. To
indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS
Fuel movement is in progress
NIS SR LOSS OF DET VOLTAGE annunciator (1A-Al) has just alarmed
INITIATING CUE
Page 25 of 57 Rev. 0
NRC-ADMIN-JPM-03
Page 26 of 4
You are requested to respond to a source-range nuclear instrumentation malfunction during
refueling using 1-AP-4.1.
Page 26 of 57 Rev. 0
NRC-ADMIN-JPM-03
Page 27 of 4
TOOLS AND EQUIPMENT
None
PERFORMANCE STEPS
START TIME
11 I Stop power increase. IProcedure Step 1 I
ISAT[] UNSAT[]I
NOTE TO THE You may now provide the requested procedure to the trainee
STANDARDS Since step is NA and there is no RNO the operator will proceed
Page 27 of 57 Rev. 0
NRC-ADMIN-JPM-03
Page 28 of 4
12 1Check if the unit is in mode 6. 1Procedure Step 2
ISAT[] UNSAT[]I
[fSTANDARDS ISince unit is in mode 6 the operator will proceed to the next step.
13 1Stop core alterations. IProcedure Step 3
1CRITICAL STEP ISAT[] UNSAT[]I
STANDARDS aNotification is made for personnel in containment to stop core
Page 28 of 57 Rev. 0
NRC-ADMIN-JPM-03
Page 29 of 4
14 1Stop all positive reactivity additions. IProcedure Step 4
ISAT[] UNSAT[]
STANDARDS to the step
ISince next step.
is NA and there is no RNO the operator will proceed
15 1Verify that only one source-range instrument has failed. IProcedure Step 5
ISAT[] UNSAT[]
Dead simulator Only one source-range instrument (NI-31) has failed
cue
STANDARDS Since only source range instrument has failed the operator will
proceed to the next step.I
Page 29 of 57 Rev. 0
NRC-ADMIN-JPM-03
Page 30 of 4
6 Verify that audible source-range indication in containment is Procedure Step 6
available.
ISAT[] UNSAT[]I
Examiner cue The source-range audible count rate speaker in containment is
Isilent
7 Select the operable channel on the audible count rate Procedure Step 6
drawer. RNO
ISAT[] UNSAT[] ]
FSTANDARDS IThe operator will select N32 on the audible count rate drawer.
Page 30 of 57 Rev. 0
NRC-ADMIN-JPM-03
Page 31 of 4
8 Verify audible source-range counts in containment. RNO
Procedure Step 6
ISAT[] UNSAT[]
EXAMINER The source-range audible count rate speaker in containment is
CUES silent
I
9 Place the amplifier select switch in the Al or A2 position. RNO
Procedure Step 6
CRITICAL STEP SAT[] UNSAT[J]
[STANDARDS Operator places amplifier selector switch in other position
EXAMINER The source-range audible count rate speaker in containment is
CUES now beeping
Page 31 of 57 Rev. 0
NRC-ADMIN-JPM-03
Page 32 of 4
110 1Enter action statement in accordance with tech specs. Procedure Step 7
SAT[] UNSAT[]
EXAMINER Assume that another operator will complete the procedure
CUESI
>>>>> END OF EVALUATION <<<<<
STOP TIME
Page 32 of 57 Rev. 0
NRC-ADMIN-JPM-03
Page 33 of 4
SIMULATOR, LABORATORY, IN--PLANT SETUP
(If Required)
SIMULATOR SETUP
R714
TASK
Respond to a source-range nuclear instrumentation malfunction during refueling (1-AP-4.1).
CHECKLIST
Recall the IC for mode 5
___ Pressurizer level = approximately 15%
___ Enter malfunction MNI1001, time delay = 10, ramp = 0, stop = 0, TRGR = NA
___ Alarm override V1AA1_W, 10 seconds, override = ON
___ Switch override AUDIOMULTOFF, 10 seconds, override = ON
Place the simulator in FREEZE
NORTH ANNA POWER STATION
INITIAL LICENSE EXAMINATION
ADMINISTRATIVE
Review and approve a
tagging record (SRO)
Page 33 of 57 Rev. 0
NRC-ADMIN-JPM-03
Page 34 of 4
CANDIDATE
EXAMINER
Page 34 of 57 Rev. 0
NRC-ADMIN-JPM-03
Page 35 of 4
NORTH ANNA POWER STATION
INITIAL LICENSE EXAMINATION
ADMINISTRATIVE
Task:
Review and approve a tagging record. (OPAP-0010)
References:
OPAP-0010, "Tag-Outs," Rev. 15
Validation Time: 6 min. Time Critical: No
Candidate:
NAME
Performance Rating: SAT UNSAT
Examiner: I
NAME SIGNATURE DATE
COMMENTS
Page 35 of 57 Rev. 0
NRC-ADMIN-JPM-03
Page 36 of 4
Tools/Ecuinment/Procedures Needed:
Tagging record package.
READ TO OPERATOR
DIRECTION TO TRAINEE:
I will explain the initial conditions, and state the task to be performed. All steps shall be performed
for this JPM. Ensure you indicate to me when you understand your assigned task. To indicate that
you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
1-BD-6, "A'SG blowdown piping penetration LMC/drain valve, leaks by and is scheduled to be replaced.
1-BD-7, "A"SG biowdown header isolation valve is difficult to operate and is scheduled to be replaced.
INITIATING CUES:
You are requested to review the tagging record package for 1-BD-6/7 for accuracy and completeness
and inform the Shift Supervisor of the results of your review.
Page 36 of 57 Rev. 0
STEP 1: Verify the tag-out is adequate for the tasks and hazards involved. (6.3.3.a)
STANDARD: Operator reviews the tagging record and reference material.
COMMENTS:
UNSAT
STEP 2: Identify that an inadequate boundary exists. (6.3.3.a) CRITICAL
STEP
STANDARD: Operator determines that 1-GN-1 09, N2 to "A"SG, was excluded as a
boundary valve. SAT
COMMENTS:
UNSAT
STEP 3: Identify that an inadequate vent/drain flow path exists. (6.3.3.a) CRITICAL
STEP
STANDARD: Operator determines that 1-BD-7, "A"SG blowdown header isolation, should
be tagged OPEN, and that the item should be a "maintenance" item instead of __ SAT
a yellow tag.
COMMENTS: Determining the tagged position as OPEN vs. CLOSED satisfies the critical
step. UNSAT
STEP 4: Identify that the order to hang tags is incorrect. (6.3.3.a) CRITICAL
STEP
STANDARD: Operator determines the following tagging order errors:
"* Tag number 6 (1-BD-95) should be ordered "4" SAT
"* Tag number 8 (1-BD-7) should be ordered "5"
"* Tag number 9 (1-BD-6) should be ordered "6"
"* (new) tag number 10 (1-GN-109) should be ordered "4"
UNSAT
COMMENTS: Determining that tag number 9 (1-BD-6) should be ordered "6" satisfies the
critical step.
ev.I
Page37o 57
Page 37 of 57 Rev. 0
STEP 5: If the review indicates a deficiency, notify the preparer and resolve the problem
or return it to the preparer. (6.3.4) SAT
STANDARD: Operator states that he/she would notify the tagging office of the deficiency
and resolve the problem or return the tagging record to the preparer.
UNSAT
EXAMINER'S CUE: The tagging office acknowledges, the evaluation is complete.
COMMENTS:
Page 38 of 57 Rev. 0
CANDIDATE CUE SHEET
(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
1-BD-6, "A"SG blowdown piping penetration LMC/drain valve, leaks by and is scheduled to be replaced.
1-BD-7, "A"SG blowdown header isolation valve is difficult to operate and is scheduled to be replaced.
INITIATING CUES:
You are requested to review the tagging record package for 1-BD-6/7 for accuracy and completeness and
inform the Shift Supervisor of the results of your review.
NORTH ANNA POWER STATION
INITIAL LICENSE EXAMINATION
ADMINISTRATIVE
Determine expanded tagging boundaries (RO)
CANDIDATE
EXAMINER
Page 39 of 57 Rev. 0
NORTH ANNA POWER STATION
INITIAL LICENSE EXAMINATION
ADMINISTRATIVE
Task:
Determine tagging boundaries (1-OPAP-0010)
References:
1-OPAP-0010, Rev. 15
Validation Time: 30 min. Time Critical: No
Candidate:
NAME
Performance Rating: SAT UNSAT
Examiner:
NAME SIGNATURE DATE
COMMENTS
Page 40 of 57 Rev. 0
Tools/Eauinment/Procedures Needed:
1-OPAP-0010, "Tagouts," Rev. 15
Mind computer or FM prints
READ TO OPERATOR
DIRECTION TO TRAINEE:
I will explain the initial conditions, and state the task to be performed. All steps shall be performed
for this JPM. Ensure you indicate to me when you understand your assigned task. To indicate that
you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
Blowdown is in service on "B" and "C" steam generators.
1-BD-6, "A" SG blowdown piping penetration LMC/drain valve, leaks by.
Maintenance has scheduled 1-BD-6 to be replaced.
When the tagout was hung for 1-BD-6 replacementit was discovered that 1-BD-7, "A" SG blowdown header isolation
valve leaks by.
INITIATING CUES:
You are requested to determine the necessary danger tags to expand the boundary to allow
maintenance to work 1 -BD-7 and to replace I -BD-6. Use the space below to identify the item(s) to be
tagged and the tagged position(s).
Page 41 of 57 Rev. 0
STEP 1: Determine the expanded mechanical boundaries. CRITICAL
STEP
STANDARD: Operator determines the additional boundary valves that need to be tagged in
accordance with the attached key.
NOTE TO EXAMINER: JPM steps need NOT be performed in sequence.
COMMENTS: UNSAT
STEP 2: Determine the expanded vent/drain flow paths. CRITICAL
STEP
STANDARD: Operator determines the additional vent/drain valves that need to be tagged in
accordance with the attached key.
EXAMINER'S CUE: If applicant asks whether the tag on 1-BD-7 has been cleared, state
that the tag has been cleared.
UNSAT
COMMENTS:
STEP3: Enter data into the computer tagging system.r
STANDARD: Operator states that he/she has completed the task.
EXAMINER'S CUE: Another operator will enter the data into the tagging system.
UNSAT
COMMENTS:
END OF TASK
END OF TASK
Page 42 of 12 Rev. 0
CANDIDATE CUE SHEET
(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
Blowdown is in service on "B"and "C" steam generators.
1-BD-6, "A"SG blowdown piping penetration LMC/drain valve, leaks by.
Maintenance has scheduled 1-BD-6 to be replaced.
When the tagout was hung for 1-BD-6 replacement, it was discovered that 1-BD-7, "A"SG blowdown header isolation
valve leaks by.
INITIATING CUES:
You are requested to determine the necessary danger tags to expand the boundary to allow
maintenance to work 1-BD-7 and to replace 1-BD-6. Use the space below to identify the item(s) to be
tagged and the tagged position(s).
Page 43 of 12 Rev. 0
Page 44 of 12 Rev. 0
North Anna
Final JPMs
ES-301 Control Room Systems Form ES-301-2 (R8, Si)
and Facility Walk-Through Test Outline
Facility: North Anna Date of Examination: 6/10-14/2002
Exam Level (circle one): RO / SRO(I) / SRO(U) Operating Test No.:
B.1 Control Room Systems
System / JPM Title Type Safety
Code* Function
a. Perform the Immediate Operator Actions in Response to a M,S,A 1
continuous uncontrolled rod motion. (R475MOD).
001AA1.01
b. Respond to a Shutdown LOCA in Mode 4. (R693). D,A,S,L 2
002A2.01
c. Initiate RCS bleed and feed in response to a loss of D,S,A 4S
secondary heat sink (1-FR-H.1) (R223). E05-EA1.1
d. Start A Reactor Coolant Pump. (1-OP-5.2) (R1 64MOD). M,S,A 4P
003A4.01
e. Reduce Containment Pressure to Subatmospheric D,S 5
(1-FR-Z.4) (R765) 022A4.04
f. Establish Safety Injection flow during a loss of all AC power D,S 6
recovery with safety Injection required. (R208). 056AA1.06
g. Respond to a Leak in the Component Cooling Water D,S 8
System (1-AP-15) (R707). 008A2.02
B.2 Facility Walk-Through
a. Align a charging flow path locally. (N907) 004-A2.07 D,R 2
b. Prepare the SBO Diesel Generator for Loading Following D 6
an automatic start (N1671). 055EA2.03
c. Transfer the Remote Monitoring ex-core neutron flux D 9
detector to its Dedicated Power Source (N963). 067AA2.16
- Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol
room, (S)imulator, (L)ow-Power, (R)CA
ES-301 Control Room Systems Form ES-301-2 (R8, SI)
and Facility Walk-Through Test Outline
Facility: North Anna Date of Examination: 6/10-14/2002
Exam Level (circle one): RO SRO(I) / SRO(U) Operating Test No.:
B.1 Control Room Systems
System I JPM Title Type Safety
Code* Function
a. Perform the Immediate Operator Actions in Response M,S,A I
to a continuous uncontrolled rod motion. (R475MOD).
001AA1.01
b. Respond to a Shutdown LOCA in Mode 4. (R693). D,A,S,L 2
002A2.01
c. Initiate RCS bleed and feed in response to a loss of D,S,A 4S
secondary heat sink (1-FR-H.1) (R223). E05-EA1.1
d. Start A Reactor Coolant Pump. (1-OP-5.2) (R164MOD). M,S,A 4P
003A4.01
e. Reduce Containment Pressure to Subatmospheric D,S 5
(1-FR-Z.4) (R765) 022A4.04
f. Establish Safety Injection flow during a loss of all AC power D,S 6
recovery with safety Injection required. (R208). 056AA1.06
g. Respond to a Leak in the Component Cooling Water D,S 8
System (1-AP-15) (R707). 008A2.02
B.2 Facility Walk-Through
a. Align a charging flow path locally. (N907) 04-A2.07 D,R 2
b. Prepare the SBO Diesel Generator for Loading D 6
Following an automatic start (N1671). 055EA2.03
c. Transfer the Remote Monitoring ex-core neutron flux D 9
detector to its Dedicated Power Source (N963). 067AA2.16
- Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol
room, (S)imulator, (L)ow-Power, (R)CA
Dominion
North Anna Power Station
JOB PERFORMANCE MEASURE EVALUATION
OPERATOR PROGRAM
INITIAL CONDITIONS
Station blackout conditions exist
The SBO EDG started ten minutes ago and is running at 900 RPM
There are no entries in the equipment status system that preclude performance of
this task
INITIATING CUE
You are requested to align the SBO diesel generator to supply the "F" transfer bus
following an automatic start in accordance with 0-OP-6.4.
Dominion
North Anna Power Station
JOB PERFORMANCE MEASURE EVALUATION
OPERATOR PROGRAM
N1671
TASK
Prepare the station blackout diesel generator for loading following an automatic
start (O-OP-6.4).
TASK STANDARDS
The SBO diesel is aligned to supply the "F" transfer bus
K/A REFERENCE:
055-EA2.03 (3.9/4.7)
ALTERNATE PATH:
N/A
TASK COMPLETION TIMES
Validation Time 10 minutes Start Time =
Actual Time = minutes Stop Time =
PERFORMANCE EVALUATION
Rating [ I SATISFACTORY f[UNSATISFACTORY
Candidate (Print)
Evaluator (Print)
Evaluator's Signature
/ Date
EVALUATOR'S COMMENTS
Dominion
North Anna Power Station
(Evaluation)
OPERATOR PROGRAM
N1671
READ THE APPLICABLE INSTRUCTIONS TO THE CANDIDATE
Instructions for In-Plant JPMs
I will explain the initial conditions, and state the task to be performed. All steps,
including any required communications, shall be simulated for this JPM. Under
no circumstances are you to operate any plant equipment. I will provide initiating
cues and reports on other actions when directed by you. Ensure you indicate to
me when you understand your assigned task. To indicate that you have
completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS
Station blackout conditions exist
The SBO EDG started ten minutes ago and is running at 900 RPM
There are no entries in the equipment status system that preclude performance of
this task
INITIATING CUE
You are requested to align the SBO diesel generator to supply the "F" transfer bus
following an automatic start in accordance with O-OP-6.4.
TOOLS AND EQUIPMENT
SBO Sync key
PERFORMANCE STEPS
START TIME
1 Verify initial conditions are satisfied. Procedure Step
ISTANDARDS IInitial conditions are verified satisfied.
ISAT[] UNSAT[]
2 Review precautions and limitations. Procedure Step
15.1.2
Sý-TANDARDS IPrecautions and limitations are reviewed.
ISAT[] UNSAT[]
3 Determine the SBO diesel status. Procedure Step
5.1.3
FSTANDARDS IEDG speed is verified approximately 900 rpm. I
ISAT[] UNSAT[]
Examiner's cue IReview the JPM initial conditions.
Notes/Comments: Ifcandidate requests status of EDG speed, read the above
cue. Candidate proceeds to step 5.1.5 (step 5.1.4 is N/A)
4 Place the SBO diesel fuel oil transfer pump Procedure Step
HAND/OFF/AUTO switch in the AUTO position. 5.1.5
CRITICAL STEP SAT[] UNSAT[]
STANDARDS Station blackout diesel generator fuel oil transfer pump is
placed in AUTO
5 Verify breaker 05M1 is closed. Procedure Step
5.1.6.a, 1"bullet
STANDARDS IBreaker 05M1 is verified closed.
[SAT[] UNSAT[]
VERBAL- Breaker 05M1 red light is lit and green light is NOT lit.
VISUAL CUES
6 Verify breaker 05M5 is closed. 5.1.6.a,
Procedure bullet
2n' Step
FSTANDARDS IBreaker 05M5 is verified closed.
ISAT[] UNSAT7[]
VERBAL- Breaker 05M5 red light is lit and green light is NOT lit.
VISUAL CUES
7 Verify breaker 04M1-1 is open. 5.1.6.a,
Procedure 3rd bullet
Step
FSTANDARDS IBreaker 04M1-1 is verified open.
[SAT[] UNSAT[]j
VERBAL- Breaker 04M1-1 green light is lit and red light is NOT lit.
VISUAL CUES
8 Verify breaker 04M1-2 is closed. Procedure Step
5.1.6.a, 4t" bullet
STANDARDS IBreaker 04M1-2 is verified closed.
[SAT[] UNSAT[]
VERBAL- Breaker 04M1-2 red light is lit and green light is NOT lit.
VISUAL CUES
9 Match the breaker control switch flags for those Procedure Step
breakers that are in the correct positions. 5.1.6.b
ISTANDARDS IControl switch flags are matched with the indications.
rSAT[] UNSAT[]U
Notes/Comments: Candidate proceeds to step 5.1.8 (step 5.1.7 is N/A)
10 Have the SRO determine which transfer bus will be
Procedure Step
supplied by the SBO EDG. 5.1.8
ISTANDARDS IF transfer bus is recorded in the procedure blank.
ISAT[] UNSAT[]j
Examiner's cue IReview the JPM initial conditions.
Notes/Comments: Ifcandidate requests SRO guidance, read the above cue.
Candidate proceeds to step 5.1.11 (steps 5.1.9 and 5.1.10 are N/A)
11 Ensure breaker 05L3 is open. Procedure Step
5.1.11.a
STANDARDS IBreaker 05L3 is verified open.
ISAT[] UNSAT[]j
VERBAL- Breaker 05L3 green light is lit and red light is NOT lit
VISUAL CUES
12 Ensure breaker 05L2 is open. Procedure Step
15.1.11. b
FSTANDARDS IBreaker 05L2 is verified open.
ISAT[] UNSAT[]
VERBAL- Breaker 05L2 green light is lit and red light is NOT lit
VISUAL CUES
13 Ensure breaker 05M3 is open. Procedure Step
15. 1.1 1.c
FSTANDARDS IBreaker 05M3 is verified open.
ISAT[] UNSAT[]
VERBAL- Breaker 05M3 green light is lit and red light is NOT lit
VISUAL CUES
14 Ensure breaker 05L1 is open. Procedure Step
5.1.1 1.d
STANDARDS IBreaker 05L1 is verified open.
[SAT[] UNSAT[]
VERBAL- Breaker 05L1 green light is lit and red light is NOT lit
VISUAL CUES
15 Close breaker 05M2. Procedure Step
5.1.11I.e
CRITICAL STEP JSAT[] UNSAT[]
FSTANDARDS IBreaker 05M2 control switch is placed in CLOSE
VERBAL- Breaker 05M2 red light is now lit and green light is NOT lit
VISUAL CUES
16 Insert synch key in breaker 15F5 synch switch and turn Procedure Step
synch switch ON. 5.1.11.f
CRITICAL STEP JSAT[] UNSAT[]l
STANDARDS Synch key is inserted in breaker 15F5 synch switch, which
is then rotated to the ON position
VERBAL- Incoming and running voltage is now indicated
VISUAL CUES
17 Have the unit-1 OATC ensure breaker 15F1 is open. Procedure Step
5.1.I.g. I
FSTANDARDS IUnit-1 OATC is requested to verify breaker 15F1 is open.
ISAT[] UNSAT[]l
VERBAL- Unit-I QATC confirms breaker 15F1 is open.
VISUAL CUESI
18 Have the backboards operator ensure breakers 15F3, Procedure Step
15F4, 15H11 and 25J11 are open. 5.1.11.g.2
STANDARDS Backboards operator is requested to verify breakers 15F3,
15F4, 15Hl1 and 25JI1 are open.
ISAT[] UNSAT[]
VERBAL- Backboards operator confirms breakers 15F3, 15F4, 15H1I
VISUAL CUES and 25J1I are all open.
19 Close breaker 15F5. Procedure Step
I ý5.1.1 1.h
CRITICAL STEP SAT[] UNSAT[]
SSTANDARDS IBreaker 15F5 control switch is placed in CLOSE
VERBAL- Breaker 15F5 red light is now lit and green light is NOT lit
VISUAL CUES
20 Place synch key in OFF. Procedure Step
I ý5.1.11.iI
STANDARDS Synch switch for breaker 15F5 is rotated to the OFF
position
SSAT[] UNSAT[]
VERBAL- Incoming and running voltmeters now indicate zero
VISUAL CUES
21 Record the time the station blackout diesel generator Procedure Step
started. 5.1.12
STANDARDS start time is recorded in the procedure
JSAT[] UNSAT[]
FExaminer's cue IReview the JPM initial conditions.
Notes/Comments: Ifcandidate requests EDG start time, read the above cue.
22 Adjust the generator voltage. Procedure Step
I ý5.1.13
STANDARDS IGenerator voltage is verified between 4250 and 4350 volts
[SAT[] UNSAT[]
VERBAL- Generator voltage is 4300 volts
VISUAL CUES
23 Adjust the generator frequency. Procedure Step
5.1.14
STANDARDS Generator frequency is verified between 59.5 and 60.5
volts
ISAT[] UNSAT[]
VERBAL- Generator frequency is 60 Hz
VISUAL CUES
I
I
>>>>> END OF EVALUATION <<<<<
STOP TIME
SIMULATOR, LABORATORY, IN--PLANT SETUP
(If Required)
O-OP-6.4 - Initial conditions, precautions and limitations, and section 5.1.
Dominion
North Anna Power Station
JOB PERFORMANCE MEASURE EVALUATION
OPERATOR PROGRAM
N907
INITIAL CONDITIONS
There is a fire in unit one emergency switchgear
Unit one's normal charging has been lost
Normal charging valves 1-CH-MOV-1289A and 1289B are closed
1-CH-FCV-1122 is not available
INITIATING CUE
You are requested to manually align a charging flow path and establish 25 gpm charging flow in
accordance with attachment 11 of 1-FCA-2.
Dominion
North Anna Power Station
JOB PERFORMANCE MEASURE EVALUATION
OPERATOR PROGRAM
N907
TASK
Establish normal charging flow locally (1-FCA-2).
TASK STANDARDS
Charging MOVs 1289A and 1289B are opened, 1-CH-289 is throttled open, 1-CH
287 is closed.
K/A REFERENCE:
004-A2.07 (3.4/3.7)
ALTERNATE PATH:
TN/AC
TASK COMPLETION TIMES
Validation Time 10 minutes Start Time =
Actual Time = minutes Stop Time =
PERFORMANCE EVALUATION
Rating [ ] SATISFACTORY [ I UNSATISFACTORY
Candidate (Print)
Evaluator (Print)
Evaluator's Signature
/ Date
EVALUATOR'S COMMENTS
Dominion
North Anna Power Station
(Evaluation)
OPERATOR PROGRAM
N907
READ THE APPLICABLE INSTRUCTIONS TO THE CANDIDATE
Instructions for In-Plant JPMs
I will explain the initial conditions, and state the task to be performed. All steps,
including any required communications, shall be simulated for this JPM. Under
no circumstances are you to operate any plant equipment. I will provide initiating
cues and reports on other actions when directed by you. Ensure you indicate to
me when you understand your assigned task. To indicate that you have
completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS
There is a fire in unit one emergency switchgear
Unit one's normal charging has been lost
Normal charging valves 1-CH-MOV-1289A and 1289B are closed
1-CH-FCV-1 122 is not available
INITIATING CUE
You are requested to manually align a charging flow path and establish 25 gpm charging flow in
accordance with attachment 11 of 1-FCA-2.
TOOLS AND EQUIPMENT
Appendix-R lantern
Appendix-R radio
Emergency dosimeter
PERFORMANCE STEPS
START TIME
I Obtain a radio and emergency lantern from the Procedure Step 1
Appendix-R locker.
ISTANDARDS IRadio and lantern are obtained from Appendix-R locker.
ISAT[] UNSAT[]
12 1Obtain Emergency Dosimeter from HP IProcedure Step 2
STANDARDS Dosimeter is obtained from the DAD check-out area. ]
ISAT[] UNSAT[][
Notes/Comments: Emergency dosimeters are located on the wall outside the
HP office.
3 1Locally ensure normal charging isolations are open. Procedure Step 4
CRITICAL STEP ISAT[] UNSAT[]l
STANDARDS 1-CH-MOV-1289A is declutched and handwheel is turned
in the CCW direction until the valve is fully open.
1-CH-MOV-1289B is declutched and handwheel is turned
in the CCW direction until the valve is fully open.
VERBAL- 1-CH-MOV-1289A and 1289B stem indicators are at the
VISUAL CUES top red line.
14 1Establish communications with the control room. Procedure Step 5a]
CRITICAL STEP ISAT[] UNSAT[]
FSTANDARDS OATC is contacted.
5 establish the required
Throttle open flow. flow control bypass valve to
the charging Procedure Step 5c
CRITICAL STEP ISAT[] UNSAT[]
STANDARDS 1-CH-289 handwheel is turned in the CCW direction until
the valve is throttled open.
VuLVERBAL- The OATC reports that charging flow is now 25 gpm.
IVISUAL CUESI
16 1Close inlet isolation for FCV-1 122. Procedure Step 5c
CRITICAL STEP SAT [] UNSAT []
STANDARDS 1-CH-287 handwheel is turned in the CW direction until the
valve is fully closed.
17 1Control charging flow as directed by OATC. IProcedure Step 5d
ISAT[] UNSAT[]
VERBAL- Assume another operator will continue this task.
VISUAL CUES
STOP TIME
SIMULATOR, LABORATORY, IN--PLANT SETUP
(If Required)
Attachment 11 of 1-FCA-2.
Dominion
North Anna Power Station
JOB PERFORMANCE MEASURE EVALUATION
OPERATOR PROGRAM
INITIAL CONDITIONS
Fire in the control room has been reported
INITIATING CUE
You are requested to transfer both the unit-1 and the unit-2 channel I ex-core flux
detectors to their backup power source in accordance with 0-FCA-1, attachment
11.
Dominion
North Anna Power Station
JOB PERFORMANCE MEASURE EVALUATION
OPERATOR PROGRAM
N963
TASK
Transfer the remote monitoring ex-core neutron flux detector to its dedicated power
source (0-FCA-1, 1-FCA-2, 1-FCA-3, 1-FCA-5).
TASK STANDARDS
The unit 1 and unit 2 channel I ex-core flux detectors are on their backup power
sources
K/A REFERENCE:
067-AA2.16 (3.3/4.0)
ALTERNATE PATH:
N/A
TASK COMPLETION TIMES
Validation Time 15 minutes Start Time =
Actual Time minutes Stop Time =
PERFORMANCE EVALUATION
Rating [ ] SATISFACTORY [ J UNSATISFACTORY
Candidate (Print)
Evaluator (Print)
Evaluator's Signature
/ Date
EVALUATOR'S COMMENTS
Dominion
North Anna Power Station
(Evaluation)
OPERATOR PROGRAM
N963
READ THE APPLICABLE INSTRUCTIONS TO THE CANDIDATE
Instructions for In-Plant JPMs
I will explain the initial conditions, and state the task to be performed. All steps,
including any required communications, shall be simulated for this JPM. Under
no circumstances are you to operate any plant equipment. I will provide initiating
cues and reports on other actions when directed by you. Ensure you indicate to
me when you understand your assigned task. To indicate that you have
completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS-
Fire in the control room has been reported
INITIATING CUE
You are requested to transfer both the unit-1 and the unit-2 channel I ex-core flux
detectors to their backup power source in accordance with 0-FCA-1, attachment
11.
TOOLS AND EQUIPMENT
Administrative lock key
Unit-1 remote flux monitor power source transfer switch key
Unit-2 remote flux monitor power source transfer switch key
PERFORMANCE STEPS
START TIME
1 Obtain keys from Appendix R key locker or admin key Procedure Step 1
locker.
STANDARDS Admin key, unit-1 and unit-2 remote flux monitor power
source keys are obtained.
ISAT[] UNSAT[]
12 1Place disconnect switch on 2-EP-CB-001 to OFF. Procedure Step 2a
ICRITICAL STEP SAT[] UNSAT[]
FSTANDARDS 12-EP-CB-001 disconnect switch is placed in OFF
13 1Verify inverter 2-1 AC output breaker is closed. Procedure Step 2b
FSTANDARDS Inverter 2-1 AC output breaker is verified closed.
[SAT[] UNSAT[]
VERBAL- 2-1 inverter output breaker handle is up.
VISUAL CUES
4 Place the ex-core flux monitor power supply transfer Procedure Step 2c
switch 1-XFR-SW-202 to the BACKUP position.
CRITICAL STEP ISAT[] UNSAT[]
FaSTANDARDS ITransfer switch 1-XFR-SW-202 in placed in BACKUP
15 1Place disconnect switch on 1-EP-CB-001 to OFF. IProcedure Step 3a
CRITICAL STEP ISAT[] UNSAT[]
ISTANDARDS 11-EP-CB-001 disconnect switch is placed in OFF I
16 1Verify inverter 1-1 AC output breaker is closed. IProcedure Step 3b
ISTANDARDS IInverter 1-1 AC output breaker is verified closed.
[SAT[] UNSAT[]
VERBAL- 1-1 inverter AC output breaker handle is up.
VISUAL CUES
7 switch 2-XFR-SW-202
Place the to the BACKUP
ex-core flux monitor position.
power supply transfer Procedure Step 3c
CRITICAL STEP SAT [] UNSAT []
FSTANDARDS ITransfer switch 2-XFR-SW-202 in placed in BACKUP
8 Obtain vital area key for Fuel Building, Remote Monitor Procedure Step 4
and Aux Monitor.
Examiner's cue Assume another operator will complete this attachment.
Show me where the source-range amplifier selector switch
is located (Admin-A.1 JPM R714). NOTE: Applicant is
allowed to refer to 1-AP-4.1
>>>>> END OF EVALUATION <<<<
STOP TIME
Dominion
North Anna Power Station
JOB PERFORMANCE MEASURE EVALUATION
OPERATOR PROGRAM
INITIAL CONDITIONS
Unit startup from mode 5 to mode 4 is in progress
Reactor coolant pumps "A"and "C" are in operation
Hot-leg and cold-leg loop "B" stop valves are open
Conditions have been established for starting the "B" reactor coolant pump
Reactor Coolant System pressure is 350 psig
Reactor Coolant System temperature is 190 0 F
"B" station service bus is not being supplied from reserve station service
Pressurizer bubble is being used for Reactor Coolant System pressure control
Reactor coolant filters and a mixed-bed ion exchanger are in service
1-OP-5.2 has been completed through verifying RCP #1 seal delta-P is in spec
INITIATING CUE
You are requested to start the "B" reactor coolant pump in accordance with 1-OP
5.2.
Dominion
North Anna Power Station
JOB PERFORMANCE MEASURE EVALUATION
OPERATOR PROGRAM
R164 (MOD)
TASK
Start a reactor coolant pump (1-OP-5.2).
TASK STANDARDS
"B" RCP was started, then tripped when vibrations exceeded the limit
K/A REFERENCE:
003-A4.01 (3.3/3.2)
ALTERNATE PATH:
Following RCP start, vibrations increase above the value requiring the operator to
trip the RCP.
TASK COMPLETION TIMES
Validation Time 10 minutes Start Time =
Actual Time = minutes Stop Time =
PERFORMANCE EVALUATION
Rating [ ] SATISFACTORY [ I UNSATISFACTORY
Candidate (Print)
Evaluator (Print)
Evaluator's Signature
/ Date
EVALUATOR'S COMMENTS
Dominion
North Anna Power Station
(Evaluation)
OPERATOR PROGRAM
R1 64
READ THE APPLICABLE INSTRUCTIONS TO THE CANDIDATE
Instructions for Simulator JPMs
I will explain the initial conditions, and state the task to be performed. All control
room steps shall be performed for this JPM, including any required
communications. I will provide initiating cues and reports on other actions when
directed by you. Ensure you indicate to me when you understand your assigned
task. To indicate that you have completed your assigned task return the handout
sheet I provided you.
INITIAL CONDITIONS
Unit startup from mode 5 to mode 4 is in progress
Reactor coolant pumps "A" and "C" are in operation
Hot-leg and cold-leg loop "B"stop valves are open
Conditions have been established for starting the "B" reactor coolant pump
Reactor Coolant System pressure is 350 psig
Reactor Coolant System temperature is 190°F
"B" station service bus is not being supplied from reserve station service
Pressurizer bubble is being used for Reactor Coolant System pressure control
Reactor coolant filters and a mixed-bed ion exchanger are in service
1-OP-5.2 has been completed through verifying RCP #1 seal delta-P is in spec
INITIATING CUE
You are requested to start the "B" reactor coolant pump in accordance with 1-OP
5.2.
TOOLS AND EQUIPMENT
None
PERFORMANCE STEPS
START TIME
1 Start the "B" reactor coolant pump bearing lift pump I- Procedure Step
RC-P-1 BI. 5.2.10
CRITICAL STEP SAT[] UNSAT[]
STANDARDS Control switch for 1-RC-P-1B1 is placed in START
Dead simulator "B" RCP bearing lift pump red light is lit and green light is
cue NOT lit.
2 Verify that the "B" reactor coolant pump oil pressure Procedure Step
start permissive indicating light is lit. 5.2.11
STANDARDS Oil pressure start permissive white indicating light is verified
lit.
[SAT[] UNSAT[]
Dead simulator Oil pressure start permissive indicating light is lit
cue
3 Verify that the "B" reactor coolant pump annunciators Procedure Step
are not lit. 5.2.12
FSTANDARDS IRCP annunciators are verified NOT lit.
ISAT[] UNSAT[]
Dead simulator Annunciators C-C2, C-E2, C-F2, C-G2, and C-H2 are NOT
cue lit
4 Ensure that the Chemical and Volume Control System Procedure Step
parameters are within specifications. 5.2.14
SSTANDARDS ICVCS parameters are verified within specifications.
[SAT[] UNSAT[]
Dead simulator Seal injection flow rate for "B" RCP is 8 gpm
cue VCT temperature is 100°F
VCT pressure is 38 psig
I
5 Ensure that the Component Cooling Water System Procedure Step
parameters are within specifications. 5.2.15
STANDARDS ICCW parameters are verified within specifications. =
ISAT[] UNSAT[]
Dead simulator Upper oil cooler flow is 160 gpm
cue Stator cooler flow is 120 gpm
Lower oil cooler flow is 7 gpm
Thermal barrier flow is 50 gpm
CCHX outlet temperature is 100°F
6 Ensure that RCS pressure is above the required value. Procedure Step
S5.2.16
ISTANDARDS CRS pressure is verified above 280 psig.
ISAT[] UNSAT[]
Dead simulator RCS pressure is 350 psig.
cue
7 Verify that the bearing lift pump has operated for at Procedure Step
least two minutes. 5.2.17
STANDARDS RCP "B" bearing lift pump is verified running at least two
minutes.
ISAT[] UNSAT[]]
Examiner's cue Assume two minutes have passed since the bearing lift
pump was started.
Notes/Comments: The next procedure step is N/A.
8 Ensure that all personnel are clear of the reactor Procedure Step
coolant pump to be started. 5.2.19
[STANDARDS IRCP start is announced on the plant paging system.
ISAT[] UNSAT[]
9 Start the "B" reactor coolant pump I -RC-P-1 B. S5.2.20
Procedure Step
CRITICAL STEP ISAT[] UNSATI[]
STANDARDS Control switch for 1-RC-P-1B is placed in AUTO-AFTER
START
At least two minutes have elapsed since the bearing lift
pump for "B" RCP was started.
Dead simulator "B"RCP motor ammeter pegged high, then decreased to
cue 920.
10 Verify that reactor coolant flow is increasing. Procedure Step
15.2.2
FSTANDARDS Flow in "B" reactor coolant loop is verified increasing.
JSAT[] UNSAT[]
Dead simulator Flow is increasing on all "B" loop reactor coolant flow
cue indicators
Notes/Comments: 20 seconds after RCP is started, annunciator A-E6, RCP
1B VIBRATION ALERT/DANGER, will illuminate.
11 Verify that annunciator IA-E6, RCP 1B VIBRATION Procedure Step
ALERT/DANGER, is not lit. 5.2.22
FSTANDARDS Annunciator is observed lit.
[SAT[] UNSAT[]
Dead simulator Annunciator A-E6 is illuminated.
cue
Notes/Comments: Transitions to annunciator response for A-E6
12 Check seismic vibration less than 5 mils. AR procedure step
2.1
FSTANDARDS ISeismic vibration indication for "B" is observed.
ISAT[] UNSAT[]
Dead simulator "B"RCP seismic vibration is 3 mils.
cue
Notes/Comments
13 Check proximity vibration less than 20 mils. AR procedure step
2.2
FSTANDARDS Proximity vibration indication for "B" is observed. 7
SSAT[] UNSAT[]
Dead simulator "B" RCP proximity vibration is 25 mils.
cue
14 Stop "B" RCP. AR procedure step
2.2 (RNO)
ICRITICAL STEP JSAT[] UNSAT[]
ISTANDARDS Control switch for 1-RC-P-1B is placed in STOP
Dead simulator "B" RCP motor ammeter has decreased to zero.
cue
Examiner cue Assume another operator will continue with the annunciator
response actions.
>>>>> END OF EVALUATION <<<<<
STOP TIME
SIMULATOR, LABORATORY, IN--PLANT SETUP
(If Required)
SIMULATOR SETUP
R1 64
TASK
Start a reactor coolant pump (1-OP-5.2).
CHECKLIST
Recall the IC for mode 5, 350 psig, 180 0 F, bubble in the pressurizer
Enter the following initial conditions
- "A" and "C" reactor coolant pumps are in operation
- "B" Reactor Coolant System loop stop valves are open
- Conditions have been established to start "B" reactor coolant pump
- "B" station service is not being supplied from the reserve station service
transformer
- Place RCPs on digital trend
Enter malfunction RC3902, delay time = 5, severity value = 75, trigger = 1.
Sign-off a copy of 1-OP-5.2, section 5.2 for starting "B" RCP through
verifying #1 seal delta-P in spec.
Implement the malfunction 20 seconds after the "B" RCP is started.
Dominion
North Anna Power Station
JOB PERFORMANCE MEASURE EVALUATION
OPERATOR PROGRAM
INITIAL CONDITIONS
1-ECA-0.0 has directed a transition to 1-ECA-0.2
Power to the "H" emergency bus has been restored
Seal injection and seal cooling have been isolated in accordance with 1-ECA-0.0
INITIATING CUE
You are requested to establish safety injection flow in accordance with 1-ECA-0.2,
"Loss of All AC Power Recovery With SI Required." Continue to the point of
checking intact steam generator levels.
Dominion
North Anna Power Station
JOB PERFORMANCE MEASURE EVALUATION
OPERATOR PROGRAM
R208
TASK
Establish safety injection flow during a loss of all AC power recovery with safety
injection required (1-ECA-0.2).
TASK STANDARDS
Safety Injection flow has been established via cold leg injection flowpath
KJA REFERENCE:
006-A4.08 (4.2/4.3)
ALTERNATE PATH:
N/A
TASK COMPLETION TIMES
Validation Time 8 minutes Start Time =
Actual Time = minutes Stop Time =
PERFORMANCE EVALUATION
Rating [ I SATISFACTORY [ ] UNSATISFACTORY
Candidate (Print)
Evaluator (Print)
Evaluator's Signature
/ Date
EVALUATOR'S COMMENTS
Dominion
North Anna Power Station
(Evaluation)
OPERATOR PROGRAM
R208
READ THE APPLICABLE INSTRUCTIONS TO THE CANDIDATE
Instructions for Simulator JPMs
I will explain the initial conditions, and state the task to be performed. All control
room steps shall be performed for this JPM, including any required
communications. I will provide initiating cues and reports on other actions when
directed by you. Ensure you indicate to me when you understand your assigned
task. To indicate that you have completed your assigned task return the handout
sheet I provided you.
INITIAL CONDITIONS
1-ECA-0.0 has directed a transition to 1-ECA-0.2
Power to the "H" emergency bus has been restored
Seal injection and seal cooling have been isolated in accordance with 1-ECA-0.0
INITIATING CUE
You are requested to establish safety injection flow in accordance with 1-ECA-0.2,
"Loss of All AC Power Recovery With SI Required." Continue to the point of
checking intact steam generator levels.
TOOLS AND EQUIPMENT
None
PERFORMANCE STEPS
START TIME
1I Verify that both trains of safety injection are reset. IProcedure Step 1
STANDARDS Permissive status light P-H1 is verified NOT lit.
ISAT[] UNSAT[]
Dead simulator Permissive status light P-H1 is NOT lit.
cue
12 1Check RWST level greater than 23%. 1Procedure Step 2
ISTANDARDS IRWST level is verified >23%.
ISAT[] UNSAT[]j
Dead simulator
cue RWST level is 97%.
3 Open charging pump suction from the RWST. Procedure Step 3a]
CRITICAL STEP ISAT[] UNSAT[]l
STANDARDS 1-CH-MOV-1115D control switch is placed in the OPEN
position.
Dead simulator 1-CH-MOV-1115D red light is lit and green light is NOT lit.
cue
14 1Close charging pump suction from the VCT. Procedure Step 3b
CRITICAL STEP SAT[] UNSAT[]
STANDARDS 1-CH-MOV-1115C control switch is placed in the CLOSE
position.
Dead simulator 1-CH-MOV-1115C green light is lit and red light is NOT lit.
cue
15 1Close normal charging isolation valve. Procedure Step 3c
CRITICAL STEP SAT[] UNSAT[]
STANDARDS 1-CH-MOV-1289A control switch is placed in the CLOSE
position.
Dead simulator 1-CH-MOV-1289A green light is lit and red light is NOT lit.
cue
16 1Close the BIT recirc valves. IProcedure Step 3d
CRITICAL STEP ISAT[] UNSAT[]j
STANDARDS 1-SI-TV-1 884A, 1884B, and 1884C CLOSE pushbuttons
are depressed.
Dead simulator 1-SI-TV-1884A, 1884B, and 1884C green lights are all lit
cue and red lights are NOT lit.
Notes/Comments: Closing either TV-1 884A or 1884C is sufficient to satisfy
the critical step.
17 1Open BIT outlet valve. Procedure Step 3e
ICRITICAL STEP SAT[] UNSAT[]
FSTANDARDS OPEN pushbutton for 1-SI-MOV-1867C is depressed.
Dead simulator 1-SI-MOV-1867C red light is lit and green light is NOT lit.
cue
18 1Open BIT inlet valve. Procedure Step 3f
CRITICAL STEP ISAT[] UNSAT[]
FSTANDARDS IOPEN pushbutton for 1-SI-MOV-1867A is depressed.
Dead simulator 1-SI-MOV-1867A red light is lit and green light is NOT lit.
cue
19 1Open LHSI pump suction valve from RWST. Procedure Step 4a
FSTANDARDS 11-SI-MOV-1862A is verified open.
SAT[] UNSAT[]
Dead simulator 1-SI-MOV-1862A red light is lit and green light is NOT lit.
cue
10 Open LHSI pump discharge valve. Procedure Step
14b1
FSTANDARDS I1-SI-MOV-1864A is verified open
ISAT[] UNSAT[]
Dead simulator 1-SI-MOV-1864A red light is lit and green light is NOT lit.
cue
11 Open LHSI pump cold-leg injection valve. Procedure Step
4b2
ISTANDARDS 11-SI-MOV-1890C is verified open
[SAT[] UNSAT[]
Dead simulator 1-SI-MOV-1890C red light is lit and green light is NOT lit.
Icue
112 1Verify SW spray valves open. IProcedure Step 5a
ISTANDARDS Pressure is verified on in-service SW spray headers.
ISAT[] UNSAT[]
Dead simulator Pressure is indicated on the in-service SW spray headers.
cue
113 1Verify SW spray bypass valves closed. IProcedure Step 5b
STANDARDS ISW spray bypass pressure is verified zero.
ISAT[] UNSAT[]
Dead simulator SW spray bypass pressure is zero.
cue
114 1Manually start the low-head safety injection pump. IProcedure Step 6a
ICRITICAL STEP ISAT[] UNSAT[]
ISTANDARDS IControl switch for 1-SI-P-lA is placed in AUTO
Dead simulator "A" LHSI pump motor ammeter pegged high, then
cue decreased to 28.
15 Verify RCP seal injection and seal cooling has been Procedure Step
isolated. 6bl
STANDARDS IRCP seal injection and seal cooling is verified isolated.
ISAT[] UNSAT[]
Examiner's cue IReview the JPM initial conditions.
Notes/Comments: Ifcandidate requests status of RCP seal injection and seal
cooling, read the above cue.
I1
16 Start charging pump. Procedure Step
16b2
CRITICAL STEP ISAT[] UNSAT[]
ISTANDARDS 11-CH-P-1A or 1-CH-P-1C control switch is placed in AUTO.
Dead simulator Charging pump motor ammeter pegged high, then
cue decreased to 97.
I
I
>>>>> END OF EVALUATION <<<<<
STOP TIME
SIMULATOR, LABORATORY, IN--PLANT SETUP
(If Required)
EL0301,0302
Perform ECA-0.0 through step 10 and attachment 3, then reenergize 1H bus and
continue with step 27 - 31
Close the following per attachment 3
1-CH-318
1-CH-314
1-CH-310
1-CC-757
1-CH-MOV-1381
Align "C"charging pump to "H"bus
Dominion
North Anna Power Station
JOB PERFORMANCE MEASURE EVALUATION
OPERATOR PROGRAM
R223
INITIAL CONDITIONS
Loss of all main feedwater due to a piping rupture resulted in the unit's tripping from
100% power
All steam generator wide-range levels are less than 12%
All auxiliary feedwater pumps are unavailable
1-FR-H.1 has been completed through checking if a wide-range level in any two
steam generators is less than 12%
INITIATING CUE
You are requested to initiate Reactor Coolant System bleed and feed in
accordance with 1-FR-H.1.
Dominion
North Anna Power Station
JOB PERFORMANCE MEASURE EVALUATION
OPERATOR PROGRAM
R223
TASK
Initiate RCS bleed and feed in response to a loss of secondary heat sink
TASK STANDARDS
RCPs are stopped, SI is actuated, PCV-1455C is opened and reactor/PRZR vents
are opened
K/A REFERENCE:
E05-EAI.1 (4.1/4.0)
ALTERNATE PATH:
One PRZR PORV fails to open, requiring reactor head vents and PRZR vents to be
opened
TASK COMPLETION TIMES
Validation Time 6 minutes Start Time =
Actual Time = minutes Stop Time =
PERFORMANCE EVALUATION
Rating [ ] SATISFACTORY [ ] UNSATISFACTORY
Candidate (Print)
Evaluator (Print)
Evaluator's Signature
/ Date
EVALUATOR'S COMMENTS
Dominion
North Anna Power Station
(Evaluation)
OPERATOR PROGRAM
R223
READ THE APPLICABLE INSTRUCTIONS TO THE CANDIDATE
Instructions for Simulator JPMs
I will explain the initial conditions, and state the task to be performed. All control
room steps shall be performed for this JPM, including any required
communications. I will provide initiating cues and reports on other actions when
directed by you. Ensure you indicate to me when you understand your assigned
task. To indicate that you have completed your assigned task return the handout
sheet I provided you.
INITIAL CONDITIONS
Loss of all main feedwater due to a piping rupture resulted in the unit's tripping from
100% power
All steam generator wide-range levels are less than 12%
All auxiliary feedwater pumps are unavailable
1-FR-H.1 has been completed through checking if a wide-range level in any two
steam generators is less than 12%
INITIATING CUE
You are requested to initiate Reactor Coolant System bleed and feed in
accordance with 1-FR-H.1.
TOOLS AND EQUIPMENT
Copy of 1-FR-H.1 signed off through checking if a wide-range level in any two
steam generators is less than 12%
PERFORMANCE STEPS
START TIME
I Verify all reactor coolant pumps have been placed in Procedure Step 15
STOP.
CRITICAL STEP SAT[] UNSAT[]
STANDARDS Control switches for all reactor coolant pumps are placed in
STOP
cuDead simulator RCP motor ammeters all indicate zero.
c~ue
12 1Place all pressurizer heaters in PULL-TO-LOCK. Procedure Step 16
CRITICAL STEP ISAT[] UNSAT[]
STANDARDS All pressurizer heater control switches are placed in PULL
TO-LOCK
Dead simulator Red and green lights for all PRZR heaters are NOT lit.
cue
13 1Determine if safety injection has been actuated. IProcedure Step 17
ISTANDARDS I Permissive status lights P-H1 and P-H2 are verified NOT lit.
ISAT[] UNSAT[]
cuDead simulator Permissive status lights P-Hi and P-H2 are NOT lit
cýue
4 Manually actuate both trains of safety injection. Procedure Step
S17b RNO
CRITICAL STEP !SAT[] UNSAT[]
STANDARDS Either SAFETY INJECTION INITIATE control switch is
placed in INITIATE
5 Verify that at least one charging pump is running. I18a
Procedure Step
FSTANDARDS JA and B charging pumps are verified running.
ISAT[] UNSAT[]
Dead simulator A and B charging pump motor ammeters indicate 92 amps
cue
I
6 Verify charging pump suction valves from RWST are Procedure Step
open. 18b.1
FSTANDARDS I1-CH-MOV-1 115B and 1115D are verified open. :
ISAT[] UNSAT[]
Dead simulator 1-CH-MOV-1115B and 1115D red lights are both lit and
cue green lights are NOT lit
7 Verify charging pump suction valves from VCT are Procedure Step
closed. 18b.2
FSTANDARDS 11-CH-MOV-1115C and 1115E are verified closed.
ISAT[] UNSAT[]
Dead simulator 1-CH-MOV-1115C and 1115E green lights are both lit and
cue red lights are NOT lit
8 Verify BIT recirc valves are closed. Procedure Step
18b.3
FSTANDARDS 11-SI-TV-1884A, 1884B and 1884C are verified closed.
ISAT[] UNSAT[]
Dead simulator 1-SI-TV-1884A, 1884B, and 1884C green lights are lit and
cue red lights are NOT lit
9 Verify BIT outlet valves are open. Procedure Step
S18b.4
ISTANDARDS 11-SI-MOV-1867C and 1867D are verified open.
SAT[] UNSAT[]
Dead simulator 1-SI-MOV-1867C and 1867D red lights are both lit and
cue green lights are NOT lit
10 Verify BIT inlet valves are open. Procedure Step
118b.5
STANDARDS 1-SI-MOV-1867A and 1867B are verified open.
ISAT[] UNSAT[]
Dead simulator 1-SI-MOV-1867A and 1867B red lights are both lit and
cue green lights are NOT lit
11 Verify normal charging valves are closed. Procedure Step
18b.6
ISTANDARDS 1-CH-MOV-1289A and 1289B are verified closed.
JSAT[] UNSAT[]
Dead simulator 1-CH-MOV-1289A and 1289B green lights are both lit and
cue red lights are NOT lit
12 Verify that cold-leg safety injection flow is indicated. Procedure Step
I 18c
FSTANDARDS SI flow is verified.
ISAT[] UNSAT[]
Dead simulator 380 gpm flow is indicated on SI-Fl-1943 and 1943-1
cue
113 1Reset both trains of safety injection. IProcedure Step 19
FSTANDARDS ISI reset switches are both placed in RESET.
ISAT[] UNSAT[]
Dead simulator Permissive status light P-H1 is NOT lit, status light P-H2 is
cue lit
114 1Reset both trains of phase "A" isolation. IProcedure Step 20
FSTANDARDS Phase A reset switches are both placed in RESET.
ISAT[] UNSAT[]
Dead simulator Annunciator K-H7 is NOT lit
cue
115 1Reset both trains of phase "B" isolation, if necessary. Procedure Step 21
ISTANDARDS Phase B is verified not actuated.
ISAT[] UNSAT[]
Dead simulator Permissive status lights P-H1 and P-H2 are NOT lit
cue
116 1Establish instrument air to containment. IProcedure Step 22
STANDARDS 2-IA-C-1 is verified running and containment trip valves are
verified open.
ISAT[] UNSAT[]
Dead simulator 2-IA-C-1 red light is lit and green light is not lit, 1-IA-TV
cue 102A and 102B red lights are both lit and green lights are
NOT lit.
17 Verify that power is available to the pressurizer power- Procedure Step
operated relief valve block valves. 23a
FSTANDARDS IPRZR PORV block valves are verified energized.
ISAT[] UNSAT[]
Dead simulator 1-RC-MOV-1535 and 1536 red lights are both lit and green
/cue lights are NOT lit
18 Verify that both pressurizer power-operated relief valve Procedure Step
block valves are open. 23b
FSTANDARDS IPRZR PORV block valves are verified open.
ISAT[] UNSAT7[]
Dead simulator 1-RC-MOV-1535 and 1536 red lights are both lit and green
cue lights are NOT lit
19 Open both pressurizer power-operated relief valves. Procedure Step
123c
CRITICAL STEP ISAT [] UNSAT []]
STANDARDS Control switches for 1-RC-PCV-1455C and 1-RC-PCV
I ý1456 are placed in OPEN
Dead simulator 1-RC-PCV-1455C red light is lit and green light is NOT lit,
cue 1-RC-PCV-1456 green light is lit and red light is NOT lit
20 Try to open PORVs using NDT protection key switches. Procedure Step
123c RNO
CRITICAL STEP ISAT[] UNSAT[]j
STANDARDS lKeyswitch for 1-RC-PCV-1456 is placed in OPEN
Dead simulator 1-RC-PCV-1455C red light is lit and green light is NOT lit,
cue 1-RC-PCV-1 456 green light is lit and red light is NOT lit
21 Verify that the Reactor Coolant System bleed path is Procedure Step 24
adequate.
STANDARDS PRZR PORVs and block valves are checked and PCV
1456 is determined to be closed.
ISAT[] UNSAT[]
Dead simulator 1-RC-PCV-1455C red light is lit and green light is NOT lit,
cue 1-RC-PCV-1456 green light is lit and red light is NOT lit
22 Open the reactor head vent valves. Procedure Step
ý24a RNO
CRITICAL STEP ISAT[] UNSAT[]
STANDARDS Control switch for each of the following reactor vent valves
is placed in OPEN:
"* 1-RC-SOV-101A-1
"* 1-RC-SOV-10IB-1
"* 1-RC-SOV-101A-2
"* 1-RC-SOV-101B-2
Dead simulator 1-RC-SOV-101A-1, 101B-1, 101A-2, and 10IB-2 red lights
cue are all lit and green lights are NOT lit
22 Open the PRZR vent valves. Procedure Step
24b RNO
CRITICAL STEP SAT[] UNSAT[]
STANDARDS Control switch for each of the following PRZR vent valves is
placed in OPEN:
"* 1-RC-SOV-102A-1
"* 1-RC-SOV-102B-1
"* 1-RC-SOV-102A-2
"* 1-RC-SOV-102B-2
Dead simulator 1-RC-SOV-102A-1, 102B-1, 102A-2, and 102B-2 red lights
cue are all lit and green lights are NOT lit
23 Align low-pressure water source. Procedure Step
24c RNO
FSTANDARDS Auxiliary operator is requested to align low-pressure water
Isource.
IExaminer's cue IAssume that another operator will complete the procedure
III
>>>>> END OF EVALUATION <
STOP TIME
SIMULATOR, LABORATORY, IN--PLANT SETUP
(If Required)
SIMULATOR SETUP
R223
CHECKLIST
__ Recall 100% power IC (IC-1 72)
Enter switch overrides:
"* PCV456_OPEN, time delay = 0, override = OFF, trigger = none
"* PCV456_N2_OPEN, time delay = 0, override = OFF, trigger = none
___ Enter malfunction FW06, time delay = 0, trigger = none
___ Go to run, trip the reactor and the turbine, close the reheater FCVs, place CN pumps and HP
heater drain pumps in PTL
___ When at least 2 steam generators decrease to 12% wide-range level (i.e.,
when the second steam generator reaches 12%), place the simulator in
FREEZE
Dominion
North Anna Power Station
JOB PERFORMANCE MEASURE EVALUATION
OPERATOR PROGRAM
INITIAL CONDITIONS
Unit 1 is at 100% power.
The previous shift experienced problems with rod control.
I&C desires rod control to remain in AUTO during troubleshooting.
INITIATING CUE
Assist I&C as necessary in troubleshooting rod control system problems.
Dominion
North Anna Power Station
JOB PERFORMANCE MEASURE EVALUATION
OPERATOR PROGRAM
R475 (MOD)
TASK
Perform the immediate operator actions in response to a continuous uncontrolled
rod motion (1-AP-1.1).
TASKSTANDARDS
Immediate actions of 1-AP-1.1 were performed from memory
Immediate actions of 1-E-0, "Reactor Trip and Safety Injection" were performed
from memory.
K/A REFERENCE:
001-AA1.01 (3.5/3.2)
ALTERNATE PATH:
1-E-0, Reactor Trip or Safety Injection.
TASK COMPLETION TIMES
Validation Time 8 minutes Start Time =
Actual Time = minutes Stop Time =
PERFORMANCE EVALUATION
Rating [ ] SATISFACTORY [ ] UNSATISFACTORY
Candidate (Print)
Evaluator (Print)
Evaluator's Signature
/ Date
EVALUATOR'S COMMENTS
Dominion
North Anna Power Station
(Evaluation)
OPERATOR PROGRAM
R475 (MOD)
READ THE APPLICABLE INSTRUCTIONS TO THE CANDIDATE
Instructions for Simulator JPMs
I will explain the initial conditions, and state the task to be performed. All control
room steps shall be performed for this JPM, including any required
communications. I will provide initiating cues and reports on other actions when
directed by you. Ensure you indicate to me when you understand your assigned
task. To indicate that you have completed your assigned task return the handout
sheet I provided you.
INITIAL CONDITIONS
Unit is at 100% steady-state operation.
The previous shift experienced problems with rod control.
I&C desires rod control to remain in AUTO during troubleshooting.
INITIATING CUE
Assist I&C as necessary in troubleshooting rod control system problems.
TOOLS AND EQUIPMENT
None
PERFORMANCE STEPS
START TIME
1 Place the control rod BANK SELECTOR switch to AP-1.1, step 1
MANUAL.
CRITICAL STEP JSAT[] UNSAT[]j
FSTANDARDS IBANK SELECTOR switch is placed in MANUAL.
Notes/Comments: Malfunction will occur 10 seconds after simulator is placed
in RUN.
12 Verify that rod motion has stopped. AP-1.1, step 2
STANDARDS Rods are verified still moving.
ISAT[] UNSAT[]
Dead simulator Rods are still inserting.
cue
3 Go to 1-E-0, Reactor Trip or Safety Injection. AP-1 .1, step 2
RNO and E-O, step
1
CRITICAL STEP SATI[] UNSAT[]
FSTANDARDS Either reactor trip switch is placed in TRIP.
Dead simulator Red lights are NOT lit and green lights are lit for both
cue reactor trip breakers.
14 Manually trip turbine. E-0, step 2a
STANDARDS Both turbine trip pushbuttons are simultaneously
depressed.
ISAT[] UNSAT[]
15 1Verify all turbine stop valves are closed. E-0, step 2b
ISTANDARDS Turbine stop valves are verified still open.
ISAT[] UNSAT[]
Dead simulator Turbine stop valve red lights are lit and green lights are
cue NOT lit, turbine stop valve status lights are NOT lit.
16 1Place both EHC pumps in PTL. IE-0, step 2b RNO
FSTANDARDS Both EHC pumps are placed in Pull-To-Lock.
ISAT[] UNSAT[]
Dead simulator Turbine stop valve red lights are lit and green lights are
cue NOT lit, turbine stop valve status lights are NOT lit.
Notes/Comments
17 Manually run back the turbine. IE-0, step 2b RNO
STANDARDS TURB MAN pushbutton is depressed, then GV FAST and
GV 11 pushbuttons are simultaneously depressed.
ISAT[] UNSAT[]]
Dead simulator Turbine stop valve red lights are lit and green lights are
cue NOT lit, turbine stop valve status lights are NOT lit.
Notes/Comments
18 1Close MSTV's and Bypass Valves. E-O, step 2b RNO
CRITICAL STEP ISAT[] UNSAT[]1
STANDARDS MSTV App-R fire emergency close pushbutton is rotated to
EMER position and depressed,
CLOSE pushbuttons for all three MSTVs are depressed.
Dead simulator Red lights are NOT lit and green lights are lit for all three
cue MSTVs.
I IAnnunciator F-GI is lit.
19 1Reset reheaters IE-0, step 2c 7
FSTANDARDS Reheater reset button is pressed.
[SAT[] UNSAT[]]
Dead simulator Red lights are NOT lit and green lights are lit for all reheater
cue FCVs.
110 1Verify generator output breaker open. IE-0, step 2d I
ISAT[] UNSAT7[]
FSTANDARDS IGenerator output breaker is verified NOT open.
Dead simulator G-12 red light is lit and green light is NOT lit.
cue
11 Manually open G-12 and exciter field breaker. IE-0, step 2d RNO
CRITICAL STEP JSAT[] UNSAT[]
STANDARDS G-12 control switch is placed in TRIP and exciter field
breaker control switch is placed in TRIP.
Notes/Comments: Inform candidate that the team will complete verification of
immediate actions.
>>>>> END OF EVALUATION <<<<<
STOP TIME
SIMULATOR, LABORATORY, IN--PLANT SETUP
(If Required)
SIMULATOR SETUP
R475 (MOD)
TASK
Perform the immediate operator actions in response to a continuous uncontrolled
rod motion (1-AP-1.1) along with failure of turbine to trip and G-12 to open
automatically.
CHECKLIST
Recall IC for 100% power (IC-1 65)
__ Enter malfunction RD07, delay time = 10, trigger = 1; Switch overrides: CNTRLRODMAN,
override = OFF, trigger = none, CNTRLRODAUTO, override = OFF, trigger = none.
Block reactor from automatically tripping:
"* Remote functions - rod control, RD32 & RD38, delay time = 0, trigger
= none
"* Remote function - SSPS, AMSACDEFEAT = true, delay time = 0,
trigger = none
Prevent turbine from tripping:
"* TU02, override = true, delay time = 0, trigger = none
"* TU03, override = true, delay time = 0, trigger = none
"* TMP3_STOP, override = OFF, delay time = 0, ramp = 0, trigger = none
"* TMP3_LOCK, override = OFF, delay time = 0, ramp = 0, trigger = none
"* TURBINE_MAN, override = OFF, delay time = 0, ramp = 0, trigger =
none
Prevent generator output breaker (and switchyard breakers) from opening:
- GMG12TRIPFAIL, remote value = trip, delay time = 0, trigger = none
Prevent MSTVs from auto-closure: MON button, then
msstmflow-kl (1)(2)(3)(4)(5)(6) = -10
Go to RUN and immediately implement malfunction RD07.
Dominion
North Anna Power Station
JOB PERFORMANCE MEASURE EVALUATION
OPERATOR PROGRAM
INITIAL CONDITIONS
Unit one is in mode 4 at 2850 F
Residual Heat Removal System is in service
Reactor coolant pumps "A" and "C" are in operation
Independent RCS level indicator 1-RC-LI-105 is tagged-out for maintenance.
PRZR level has just begun decreasing
INITIATING CUE
You are requested to respond to a shutdown LOCA.
Dominion
North Anna Power Station
JOB PERFORMANCE MEASURE EVALUATION
OPERATOR PROGRAM
R693
TASK
Respond to a shutdown LOCA in mode 4 (1-AP-1 7).
TASK STANDARDS
Letdown is isolated and SI flow is established.
K/A REFERENCE:
002-A2.01 (4.3/4.4)
ALTERNATE PATH:
Charging flow is not adequate to maintain PRZR level, SI flow must be aligned.
TASK COMPLETION TIMES
Validation Time 12 minutes Start Time =
Actual Time = minutes Stop Time =
PERFORMANCE EVALUATION
Rating [ I SATISFACTORY [ ] UNSATISFACTORY
Candidate (Print)
Evaluator (Print)
Evaluator's Signature
/ Date
EVALUATOR'S COMMENTS
Dominion
North Anna Power Station
(Evaluation)
OPERATOR PROGRAM
R693
READ THE APPLICABLE INSTRUCTIONS TO THE CANDIDATE
Instructions for Simulator JPMs
I will explain the initial conditions, and state the task to be performed. All control
room steps shall be performed for this JPM, including any required
communications. I will provide initiating cues and reports on other actions when
directed by you. Ensure you indicate to me when you understand your assigned
task. To indicate that you have completed your assigned task return the handout
sheet I provided you.
INITIAL CONDITIONS
Unit one is in mode 4 at 285 0 F
Residual Heat Removal System is in service
Reactor coolant pumps "A" and "C" are in operation
Independent RCS level indicator 1-RC-LI-105 is tagged-out for maintenance.
PRZR level has just begun decreasing
INITIATING CUE
You are requested to respond to a shutdown LOCA.
TOOLS AND EQUIPMENT
None
PERFORMANCE STEPS
START TIME
1I Check at least one charging pump running. Procedure Step Ia
rSTANDARDS I"A" charging pump is verified running.
ISAT[] UNSAT[]
Dead simulator "A" charging pump motor ammeter indicates 70, "B"and "C"
cue both indicate zero.
2 pressurizer level. flow as necessary to maintain
Adjust charging Procedure Step l b
CRITICAL STEP ISAT[] UNSAT[]
FSTANDARDS Normal charging FCV-1 122 controller output is raised
Dead simulator FCV-1122 output is now 100%.
cue
3 Check letdown valves closed. Procedure Step 2a
SRNO
CRITICAL STEP ISAT[] UNSAT[]
STANDARDS 1-CH-HCV-1200A, 1200B, and 1200C control switches are
placed in CLOSE
1-CH-LCV-1460A and 1460B control switches are placed in
CLOSE
Dead simulator 1-CH-HCV-1200A, 1200B, and 1200C green lights are lit
cue and red lights are NOT lit.
1-CH-LCV-1460A and 1460B green lights are lit and red
lights are NOT lit.
Notes/Comments: Closing HCV-1200A, 1200B, 1200C, and either 1460A or
1460B satisfies the critical step.
4 Check RHR to letdown valve closed. RNO
Procedure Step 2b
ICRITICAL STEP SAT[] UNSAT[]
FSTANDARDS 1-CH-HCV-1142 controller demand is lowered to zero
Dead simulator 1-CH-HCV-1142 controller demand is now zero.
cue
15 1Check loop drain valves closed. Procedure Step 2c
STANDARDS Loop drain valves 1-RC-HCV-1557A, 1557B and 1557C
are verified closed.
SAT[] UNSAT[]
Dead simulator 1-RC-HCV-1557A, 1557B, and 1557C green lights are
cue NOT lit and red lights are NOT lit.
16 1Verify 1-RH-36 and 1-RH-34 are locked closed. IProcedure Step 2d
STANDARDS 11-RH-36 and 1-RH-34 are verified locked closed.
ISAT[] UNSAT[]
FExaminer's cue IReview the JPM initial conditions.
Notes/Comments: If applicant requests status of 1-RH-36 and 1-RH-34, read
the above cue.
17 1Close any known RCS drain paths. IProcedure Step 2e
FSTANDARDS IAll known RCS drain paths are verified closed.
JSAT[] UNSAT[]
Examiner's cue IThere are no other known RCS drain paths.
18 1Evacuate all unnecessary personnel from containment. IProcedure Step 3
STANDARDS Containment evacuation alarm is sounded and plant
paging system is used to direct all unnecessary personnel
to evacuate containment.
ISAT[] UNSATI[]
9 indicator
Verify independentis Reactor
that1-RC-LI-105 energized.
Coolant System level Procedure Step 4
FSTANDARDS IRCS independent level indicator is verified de-energized.
JSAT[] UNSAT[]
Examiner's cue IReview the JPM initial conditions.
Notes/Comments: Ifcandidate requests status of 1-RC-LI-105, read the
above cue.
10 1Determine mode of operation at start of event - Mode 4 1Procedure Step 5
STANDARDS Unit is verified in mode 4.
[SAT[] UNSAT[]
FExaminer's cue IReview the JPM initial conditions.
Notes/Comments: Ifcandidate requests unit mode, read the above cue.
11 1Check if RHR pumps should be stopped IProcedure Step 6
ISTANDARDS RHR pump is verified running normally.
[SAT[] UNSAT[]
Dead simulator "A"RHR pump amps are stable at 42 and RHR flow is
cue stable at 3,500 gpm.
12 Check if charging flow is adequate Procedure Step 7
ISTANDARDS jPRZR level is verified less than 21% and decreasing.
ISAT[] UNSAT[]
Dead simulator Pressurizer level is 15% and decreasing
Icu e
Notes/Comments: This is the alternate path (RNO) step.
13 Verify only one charging pump running Procedure Step
11a
STANDARDS Charging pumps are observed and only one is verified
running.
ISAT[] UNSAT[]
Dead simulator "A" charging pump motor ammeter indicates 92, "B" and "C"
cue both indicate zero.
14 Open charging pump suction valves from RWST Procedure Step
11b
STANDARDS 11-CH-MOV-1115B and 1115D are verified open.
ISAT[] UNSAT[]
Dead simulator MOV-1115B and 1115D red lights are both lit and green
cue lights are NOT lit.
15 Close charging pump suction valves from VCT Procedure Step
11c
ISTANDARDS 1-CH-MOV-1115C and 1115E are verified closed.
ISAT[] UNSAT[]
Dead simulator MOV-1115B and 1115D green lights are both lit and red
cue lights are NOT lit.
16 Close BIT recirc valves Procedure Step
llid
CRITICAL STEP ISAT[] UNSAT[]
STANDARDS 1-SI-TV-1884A, 1884B and 1884C CLOSE pushbuttons
are depressed
Dead simulator TV-1 884A, 1884B, and 1884C green lights are all lit and
cue red lights are NOT lit.
Notes/Comments: Closing either TV-1 884A or 1884C satisfies the critical
step.
17 Open BIT outlet valves. Procedure Step
ille
CRITICAL STEP ISAT[] UNSAT[]
STANDARDS OPEN pushbuttons for 1-SI-MOV-1867C and 18670 are
depressed.
Dead simulator 1-SI-MOV-1867C and 1867D red lights are both lit and
cue green lights are NOT lit.
Notes/Comments: Opening either MOV-1867C or 1867D satisfies the critical
step.
18 Open BIT inlet valves. Procedure Step
CRITICAL STEP SAT[] UNSAT[]]
STANDARDS OPEN pushbuttons for 1-SI-MOV-1867A and 1867B are
depressed.
Dead simulator 1-SI-MOV-1867A and 1867B red lights are both lit and
cue green lights are NOT lit.
Notes/Comments: Opening either MOV-1867A or 1867B satisfies the critical
step.
19 Close normal charging line isolation valves. Procedure Step
11g
CRITICAL STEP JSAT[] UNSAT[]l
STANDARDS 1-CH-MOV-1289A and 1289B control switches are placed
Iin the CLOSE position.
Dead simulator 1-CH-MOV-1289A and 1289B green lights are both lit and
cue red lights are NOT lit.
Notes/Comments: Closing either MOV-1289A or 1289B satisfies the critical
step.
20 Close charging pump recirc valves. Procedure Step
11h
CRITICAL STEP SAT[] UNSAT[]
STANDARDS 1-CH-MOV-1275A, 1275B, and 1275C control switches are
placed in the CLOSE position.
Dead simulator 1-CH-MOV-1275A, 1275B, and 1275C green lights are all
cue lit and red lights are NOT lit.
121 Actuate phase A isolation Procedure Step 12]
CRITICAL STEP SAT[] UNSAT[]
STANDARDS Either control switch for phase A isolation is placed in
INITIATE
Dead simulator Annunciator K-H7 is lit.
cue
22 Evaluate the need to implement EPIP-1.01, "Emergency Procedure Step 13
Manager Controlling Procedure." i
[SAT[] UNSAT[]I
Examiner's cue IThe Station Emergency Manager has initiated EPIP-1.01.
23 Check if RCPs must be stopped Procedure Step
14a
STANDARDS IRCP #1 seal AP indications are verified less than 200 psid.
ISAT[] UNSAT[J
Dead simulator RCP seal AP is less than 200 psid on the running RCPs.
cue
24 Stop the affected RCPs. Procedure Step
14b
CRITICAL STEP SAT[] UNSAT[]
STANDARDS Control switches for the "A" and "C" reactor coolant pumps
are placed in AUTO-AFTER-STOP or PULL-TO-LOCK.
Dead simulator "A" and "C" RCP motor ammeters indicate zero.
cue
Notes/Comments: If RCP seal delta-P remains above 200 psid, this step is
NOT critical.
I
25 Verify the alignment of the low-head safety injection Procedure Step 15
pump
ISTANDARDS LHSI suction and discharge valves are verified open.
SAT[] UNSAT[]
Dead simulator 1-SI-MOV-1862A and 1864A red lights are both lit and
cue green lights are NOT lit.
126 1Check if low-head safety injection flow is required Procedure Step 161
FSTANDARDS IRCS subcooling is verified > 35 0 F.
[SAT[] UNSAT[]
Dead simulator RCS subcooling is 159TF.
cue
27 Verify adequate safety injection flow Procedure Step
17a
STANDARDS RVLIS dynamic indication is verified > 67% (2 RCPs
running) OR
RVLIS full-range indication is verified 51% (all RCPs
secured).
ISAT[] UNSAT[]
Dead simulator RVLIS dynamic indicates 59% (2 RCPs running) OR
cue RVLIS full-range indicates 104% (all RCPs secured).
28 Check if core exit temperatures are stable Procedure Step
17b
FSTANDARDS jCore-exit TCs are verified stable or decreasing.
[SATI[] UNSAT[]
Dead simulator Core-exit TCs are stable.
cue
29 Check if the Reactor Coolant System hot-leg Procedure Step 18
temperatures are stable
[SAT[] UNSAT[]
IExaminer's cue IAssume that another operator will complete the procedure
>>>>> END OF EVALUATION <<<<<
STOP TIME
SIMULATOR, LABORATORY, IN--PLANT SETUP
(If Required)
SIMULATOR SETUP
R693
TASK
Respond to a shutdown LOCA in mode 4 (1-AP-1 7).
CHECKLIST
___ Recall the IC for mode 4 with temperature = 2850 F (IC-170)
___ Ensure "A" charging pump is running with suction aligned to the volume
control tank
___ Ensure all three letdown orifice HCVs are open
Close CH-217 on PNID
___ Enter MRC0101_DEG = 0.1
Place simulator in RUN
Place the simulator in FREEZE
After applicant isolates letdown, increase the leak degradation to 0.13.
Dominion
North Anna Power Station
JOB PERFORMANCE MEASURE EVALUATION
OPERATOR PROGRAM
INITIAL CONDITIONS
"A" CC pump is running
"B" CC pump is in automatic
Component cooling water is split out between units for on-going engineering
evaluation.
Control room annunciator window G-AI, CC SURGE TK HI-LO LEVEL, is lit
INITIATING CUE
You are requested to respond to a decrease of component cooling water head tank
level in accordance with 1-AP-15. This is a time-critical task.
Dominion
North Anna Power Station
JOB PERFORMANCE MEASURE EVALUATION
OPERATOR PROGRAM
R707
TASK
Respond to a leak in the Component Cooling Water System (1-AP-1 5).
TASKSTANDARDS
U-1 CC pumps placed in PTL, charging and seal return isolated, seal injection
reduced, and CC pump restarted prior to exceeding RCP trip criteria.
K/A REFERENCE:
008-A2.02 (3.2/3.5)
ALTERNATE PATH:
N/A
TIME CRITICAL:
Yes - CC pump must be restarted prior to exceeding RCP trip criteria
TASK COMPLETION TIMES
Validation Time 15 minutes Start Time =
Actual Time minutes Stop Time =
PERFORMANCE EVALUATION
Rating [ ] SATISFACTORY [ I UNSATISFACTORY
Candidate (Print)
Evaluator (Print)
Evaluator's Signature
/ Date
EVALUATOR'S COMMENTS
Dominion
North Anna Power Station
(Evaluation)
OPERATOR PROGRAM
R707
READ THE APPLICABLE INSTRUCTIONS TO THE CANDIDATE
Instructions for Simulator JPMs
I will explain the initial conditions, and state the task to be performed. All control
room steps shall be performed for this JPM, including any required
communications. I will provide initiating cues and reports on other actions when
directed by you. Ensure you indicate to me when you understand your assigned
task. To indicate that you have completed your assigned task return the handout
sheet I provided you.
INITIAL CONDITIONS
"A" CC pump is running
"B"CC pump is in automatic
Component cooling water is split out between units for on-going engineering
evaluation.
Control room annunciator window G-AI, CC SURGE TK HI-LO LEVEL, is lit
INITIATING CUE
You are requested to respond to a decrease of component cooling water head tank
level in accordance with 1-AP-15. This is a time-critical task.
TOOLS AND EQUIPMENT
None
PERFORMANCE STEPS
START TIME
1I Verify CC head tank level is stable or increasing. Procedure Step I
FSTANDARDS ICC head tank level is verified off-scale low.
[SAT[] UNSAT[]
Dead simulator CC head tank level indicates off-scale low.
cue
2 Align to refill the component cooling water head tank. Procedure Step 1a
RNO
CRITICAL STEP SAT[] UNSAT[]
STANDARDS Auxiliary operators are requested to align to refill the CC
Ihead tank
Booth oDerator Condensate is being aligned to fill the CC head tank level.
cue
3 Procedure Step
CRITICAL STEP ISAT[] UNSAT[]I
STANDARDS Control switches for 1-CC-P-1A and 1-CC-P-1B are placed
in PTL
Dead simulator CC pump motor ammeters both indicate zero.
cue
I
4 Locally isolate the ruptured equipment supplied by the Procedure Step
Component Cooling Water System. 1b2 RNO
CRITICAL STEP ISAT[] UNSAT[f]
STANDARDS Auxiliary operator is requested to locate and isolate CC
leakage.
Booth operator Auxiliary operator acknowledges direction to locate and
cue isolate CC leak.
I
5 Determine if the unit-1 and unit-2 Component Cooling Procedure Step 8
Water Systems are cross-connected.
ISTANDARDS ICC systems are verified split-out.
ISAT[] UNSAT[f]
Examiner's cue IReview the JPM initial conditions.
Notes/Comments: If candidate requests the status of CC systems, read the
above cue.
16 1Monitor RCP temperatures. IProcedure Step 106]
ISTANDARDS IRCP temperatures are verified within limits.
ISAT[] UNSAT[]
Dead simulator RCP temperatures are increasing, but no maximum
cue temperature limits have been exceeded
17 Isolate normal letdown. Procedure Step 11
CRITICAL STEP ISAT[] UNSAT[f]
ISTANDARDS 1-CH-HCV-1200B control switch is placed in CLOSE
1-CH-LCV-1460A and 1460B control switches are placed in
CLOSE.
Dead simulator HCV-1200B, LCV-1460A and 1460B green lights are all lit
cue and red lights are NOT lit.
Notes/Comments: Closing HCV-1200B, and either 1460A or 1460B satisfies
the critical step.
18 1Check excess letdown secured. Procedure Step 12]
ISTANDARDS Excess letdown valves are verified closed.
ISAT[] UNSAT[]
Dead simulator HCV-1201 green light is lit and red light is NOT lit.
cue HCV-1 137 controller demand is zero.
19 1Isolate normal charging. IProcedure Step 13
ICRITICAL STEP ISAT[] UNSAT[]
FSTANDARDS 1z-CH-FCV-1 122 controller output is manually decreased to
zero.
Dead simulator FCV-1 122 controller output is now zero.
cue
110 Isolate seal water return. IProcedure Step 14
CRITICAL STEP ISAT[] UNSAT[]l
FSTANDARDS 1-CH-MOV-1380 CLOSE pushbutton is depressed.
Dead simulator MOV-1380 green light is lit and red light is NOT lit.
cue
111 IAdjust reactor coolant pump seal injection. IProcedure Step 15
STANDARDS 1-CH-HCV-1 186 controller output is decreased until each
RCP's seal injection flow indicates approximately 6 gpm
[SAT[] UNSAT[]
Dead simulator Seal injection to each RCP is approximately 6 gpm.
cue
112 1Verify that CC head tank level is stable or increasing. IProcedure Step 16
SSTANDARDS CC head tank level is verified off-scale low.
[SAT[] UNSAT[]
Dead simulator CC head tank level indicates off-scale low.
cue
13 Put CC pumps in PTL Procedure Step
I ý16a RNO
STANDARDS Control switches for 1-CC-P-IA and 1-CC-P-1B are verified
in PTL
ISAT[] UNSAT[]]
Dead simulator CC pump motor ammeters both indicate zero.
cue
14 Locally isolate the ruptured equipment supplied by the Procedure Step
Component Cooling Water System. 16b RNO
STANDARDS Auxiliary operators are verified dispatched to locate and
isolate CC leakage.
ISAT[] UNSAT[]]
Booth operator Auxiliary building operator reports discovering and isolating
cue a ruptured supply pipe to the gas stripper trim cooler.
15 Align to refill the component cooling water head tank. Procedure Step
116c RNO
STANDARDS Auxiliary operators are verified aligning to refill the CC head
tank.
ISAT[] UNSAT[]
Booth operator Condensate is aligned to fill the CC head tank level.
cue
16 When component cooling water head tank level is Procedure Step
restored, go to step 2. 16d RNO
JSTANDARDS I-CC head tank level is verified on-scale.
[SAT[] UNSAT[]
cuDead simulator CC head tank level indicates 10% and increasing.
cueI
117 1Verify that at least one unit-1 CC pump is running. IProcedure Step 2
STANDARDS Control switches for 1-CC-P-1A and 1-CC-P-1B are verified
in PTL
ISAT[] UNSAT[]
Dead simulator CC pump motor ammeters both indicate zero.
cue
18 Start a unit-1 CC pump. Procedure Step 2
RNO
CRITICAL STEP SAT[] UNSAT[]
STANDARDS Control switch for 1-CC-P-1A or 1B is placed in AUTO
I IAFTER-START
Dead simulator CC pump motor ammeter pegged high, then decreased to
cue 55 amps.
119 1Check running CC pump amps stable. IProcedure Step 3
ISTANDARDS ICC pump motor ammeter is verified stable
[SAT[] UNSAT[]
Dead simulator CC pump motor ammeter is stable at 55 amps.
cu__ge
120 1Verify CC flow is normal. PProcedure Step 4
FSTANDARDS ICC flow is verified stable.
[SAT[] UNSAT[]
Dead simulator CC flow is stable at approximately 3,500 gpm per heat
-Jcue exchanger.
21 Locally check service water to CC heat exchangers' Procedure Step 5
differential pressures are normal.
FSTANDARDS IAuxiliary operator is requested to check CCHX delta-Ps.
JSAT[] UNSAT[]
Booth operator Auxiliary building operator reports that the service water
cue differential pressure across the component cooling water
heat exchangers is 10 PSID
122 1Restore equipment to normal. Procedure Step 6
SSTANDARDS Attachment 2 is initiated.
ISAT[] UNSAT[]
FExaminer's cue IAssume that another operator will complete the procedure.
>>>>> END OF EVALUATION <<<<<
STOP TIME
SIMULATOR, LABORATORY, IN--PLANT SETUP
(If Required)
SIMULATOR SETUP
R707
CHECKLIST
Recall IC for 100% power (IC-164)
Enter malfunction CC01 01, delay time = 0, ramp = 0, severity value = .5
Shut component cooling cross-tie using PNID: CC-49 = 0
Run simulator until component cooling surge tank is 0%
Place the simulator in FREEZE; then delete the malfunction
When directed by procedure to fill the component cooling surge tank, slowly
open CN-41 to 0.2 on PNID (verify that CC-625 LCV bypass is open)
When requested to align to fill the CC head tank, read the following cue:
Booth operator Condensate is being aligned to fill the CC head tank level.
cue
When requested to locate CC leak, read the following cue:
Booth operator Auxiliary building operator acknowledges direction to locate
cue and isolate CC leak.
When contacted concerning status of CC leak, read the following cue:
Booth operator Auxiliary building operator reports discovering and isolating
cue a ruptured supply pipe to the gas stripper trim cooler.
When contacted concerning status of CC head tank fill, read the following cue:
Booth operator Condensate is aligned to fill the CC head tank level.
cue
When requested to check CCHX SW delta-Ps, read the following cue:
Booth operator Auxiliary building operator reports that the service water
cue differential pressure across the component cooling water
heat exchangers is 10 PSID
Dominion
North Anna Power Station
JOB PERFORMANCE MEASURE EVALUATION
OPERATOR PROGRAM
INITIAL CONDITIONS
CDA has NOT been actuated
The mechanical chiller is running
Containment pressure is approximately 18 psia and increasing due to a small main
steam piping break
1-FR-Z.4 has been completed through establishing instrument air to the
containment
INITIATING CUE
You are requested to reduce containment pressure to subatmospheric in
accordance with 1-FR-Z.4.
Dominion
North Anna Power Station
JOB PERFORMANCE MEASURE EVALUATION
OPERATOR PROGRAM
R765
TASK
Reduce containment pressure to subatmospheric (1-FR-Z.4).
TASK STANDARDS
Chilled water flow was aligned to CARFs, SW flow was aligned to "A" RSHX and 1
RS-P-1A was started.
K/A REFERENCE:
022-A4.04 (3.1/3.2)
ALTERNATE PATH:
N/A
TASK COMPLETION TIMES
Validation Time 10 minutes Start Time =
Actual Time = minutes Stop Time =
PERFORMANCE EVALUATION
Rating [ ] SATISFACTORY [ ] UNSATISFACTORY
Candidate (Print)
Evaluator (Print)
Evaluator's Signature
/ Date
EVALUATOR'S COMMENTS
Dominion
North Anna Power Station
(Evaluation)
OPERATOR PROGRAM
R765
READ THE APPLICABLE INSTRUCTIONS TO THE CANDIDATE
Instructions for Simulator JPMs
I will explain the initial conditions, and state the task to be performed. All control
room steps shall be performed for this JPM, including any required
communications. I will provide initiating cues and reports on other actions when
directed by you. Ensure you indicate to me when you understand your assigned
task. To indicate that you have completed your assigned task return the handout
sheet I provided you.
INITIAL CONDITIONS
CDA has NOT been actuated
The mechanical chiller is running
Containment pressure is approximately 18 psia and increasing due to a small main
steam piping break
1-FR-Z.4 has been completed through establishing instrument air to the
containment
INITIATING CUE
You are requested to reduce containment pressure to subatmospheric in
accordance with 1-FR-Z.4.
TOOLS AND EQUIPMENT
Copy of 1-FR-Z.4 signed off through establishing instrument air to the containment
PERFORMANCE STEPS
START TIME
1 Verify that the containment air recirculation fan chilled Procedure Step 3a
water supply valves are open.
CRITICAL STEP JSAT[] UNSAT[]
STANDARDS Control switch for 1-CC-TV-115A, 115B, and 115C is
placed in the CD position
Dead simulator 1-CC-TV-1 15A, 1155B, and 11 5C red lights are all lit and
cue green lights are NOT lit.
2 Verify return
water that thevalves are open.
containment air recirculation fan chilled Procedure Step 3b
STANDARDS 1-CC-TV-105A, 105B, 105C and 100A, 100B, 100C are
verified open.
SAT[] UNSAT[]
Dead simulator 1-CC-TV-105A, 105B, 105C and 100A, 100B, 100C red
cue lights are all lit and green lights are NOT lit.
3 Verify that the containment air recirculation fans are Procedure Step 3c
running.
FSTANDARDS 1-HV-F-1A, 1B, and 1C are verified running.
ISAT[] UNSAT[]
Dead simulator 1-HV-F-1A, 1B, and IC red lights are all lit and green lights
cue are NOT lit.
14 1Verify that the chilled water system is in service. Procedure Step 3d
STANDARDS IMechanical chiller is verified running.
{SAT[] UNSAT[]
Examiner's cue IReview the JPM initial conditions.
Notes/Comments: Ifcandidate requests the status of chilled water, read the
above cue.
I
5 Check that the control rod drive mechanism cooling fans Procedure Step 4
are running.
ISTANDARDS 11-HV-F-37C, 37D, and 37E are verified running.
[SAT[] UNSAT[]
Dead simulator 1-HV-F-37C, 37D, and 37E red lights are all lit and green
cue lights are NOT lit.
16 Check containment pressure stable or decreasing. Procedure Step 5
ISTANDARDS Containment pressure is verified increasing.
ISAT[] UNSAT[]
Dead simulator Containment pressure is 22 psia and slowly increasing
cue
17 1Check recirculation spray sump level. IProcedure Step 8
ISTANDARDS IRecirc spray sump level is verified greater than 1' 4".
ISAT[] UNSAT[]
Dead simulator Recirc spray sump level is 1' 8" and slowly increasing.
cue
18 1Check that 1-RS-P-1A is available. Procedure Step 9
FSTANDARDS lRecirc spray pump 1-RS-P-1A is verified available.
ISAT[] UNSAT[]
Dead simulator 1-RS-P-1A is in auto-after stop and 1H bus is energized.
cue
9 Align service water to 1-RS-E-1A. Procedure Step
CRITICAL STEP ISAT[] UNSAT[]
STANDARDS OPEN push-buttons for 1-SW-MOV-101A, 103A, 104A,
and 105C are depressed
Dead simulator 1-SW-MOV-101A, 103A, 104A and 105C red lights are all
cue lit and green lights are NOT lit.
10 Start inside recirculation spray pump 1-RS-P-1A. Procedure Step
10Gb
CRITICAL STEP SAT[] UNSATj[]]
STANDARDS Control switch for 1-RS-P-1A is placed in AUTO-AFTER
START
Dead simulator 1-RS-P-1A motor ammeter pegged high, then decreased to
cue 320 amps.
11 Operate 1-RS-P-1A to maintain containment pressure Procedure Step 11
between 10.5 psia and 13 psia.
ISTANDARDS IContainment pressure is verified decreasing.
ISAT[] UNSAT[]
FExaminer's cue IAssume that another operator will complete the procedure
Dead simulator Containment pressure is now 21 psia and decreasing
cue
>>>>> END OF EVALUATION <<<<<
STOP TIME
SIMULATOR, LABORATORY, IN--PLANT SETUP
(If Required)
SIMULATOR SETUP
R765
TASK
Reduce containment pressure to subatmospheric (1-FR-Z.4).
CHECKLIST
___ Recall IC for 100% power (IC-169)
Place the simulator in RUN
Enter the malfunction for a main steam break inside containment such that a safety injection is
received and containment pressure is 18 psia (MS0801)
Close 1-CC-TV-1 15A/B/C
___ Ensure that the sump level > 1 foot 4 inches
Place the simulator in FREEZE