ML20217E502
| ML20217E502 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 10/02/1997 |
| From: | Curley V NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9710070053 | |
| Download: ML20217E502 (916) | |
Text
i October 2, 1997 -
NOTE T0: NRC Document Control Desk Mail Stop 0-5 D 24 FROM:- $ctl boa fen .L Opera';1ng Licensirp" Branch. -R pnsing Assistant '
SUBJECT:
OPERATOR LICENSING EXAMINATION ADMINISTERED ON
_lolv 7.11_ 1997 . AT Millstone Unit 3 .
DOCKET #50 .323 On Julv 7-11. 1997 Operator Licensing Examinations were administered at the referenced facility. Attached, you will find the following information for processing through NUDOCS and distribution to the NRC staff, including the NRC POR:
Item #1 - a) Facility submitted outline and initial exam submittal, designated for distribution under RIOS Code A070.
b)' As given operating examination, designated for distribution under RIOS Code A070.
Item #2 - Examination Report with the as given written examination attached, designated for distribution under RIOS Code IE42.
k
-t
- f 1 iV n 188 s M a88?aa PDR b!, !! ,
L
Administrative Topics Outline (Rev 11 Facility: Millstone Unit 3 Date of Examination: Week of 7/7/97 Examination f.evel: RQ Operating test Number:
Administrative Tonic / Subject Descrintion Method of Evaluation:
A.1 Conduct of Onerations
- 1. Given a set of conditions, be able to use JPM the applicable procedure and graphs to calculate the time to core boiling.
(K/A 2.1.20, RO: 4.3)
- 2. Responsibilities as the oncoming operator 2 Questions conceming the shift turnover process.
(K/A 2.1.3, RO:~ 3.0)
A.2 Ecuinnient Control N
- 1. Given a se: of P&lDs, he able to complete JPM i the requested information concerning s
\
components and nomenclature.
A.3 Radiation Control
- 1. At the RCA access point, be able to explain 2 Questions radiation hazards in the area entering, radiation work permit information and radiation control. (K/A 2.3.4, RO: 2.5)
A.4 Emergency Plan
- 1. Knowledge oof the RO's responsibilities 2 Questions in emergency plan implementation (K/A 2.4.39. RO: 3.3) 0 I
1b
JOB PERFORMANCE MEASURE WORKSHEET
- l. JPM
Title:
DETERMINE TIME Tb CORE BOILING ID Number: NRC-NEW3 Revision: 0 it. Initiated:
, R.L. Lueneburg 5/29/97 l Developer Date Ill. Reviewed:
Technical Reviewer Date i
instructional Reviewcr Date IV. Approved:
Operations Manager Date Nuclear Training Supervisor Date 1
_m >
JOB PERFORMANCE MEASURE WORKSHEET Facility: - Millstone Unit 3 Examinee: .
JPM Tracking Number:- NRC-NEW3 Validation Time:
minutes 1 Task
Title:
__CA.'..CULATE TIME TO CORE BOILING Time Critical Tast : ( )YES ( X ) NO Task Number: 119*047*03*02 K/A Number: 2.1.25 K/A Ratiy, 23/3.1 Acolicable Methods of Testing:
Simulate Performance - Actual Performance X Classroom Simulator X Plant X Task Standards: Satisfactorily complete the determination of time to core boiling for a given set of conditions.
Reauired Materials: None General
References:
OP 3260A Rev.10 READ TO THE EXAMINEE l will explain the initial conditions, which step (s) to simulate or discuss, and provide initiating -
cues, When you complete the task successfully, the objectives for this JPM will be satisfied.
You may use any approved reference materials normally available in the Control Room, including logs. Make all written reports, oral reports and log entries as if the evolution was -
actually being performed.
Initial Conditions: The plant is in MODE 5, shutdown 160 days for an extended non-refueling outage, RCS pressure is being maintained at 45 psia on a N2, RCS temperature is 105'F, and none of the RCS loops has been drained or isolated.
Initiating Cues: Given the plant conditions above, the US has directed you to calculate
time to core boiling".
2
- ~ _ - - _ _ _ _. _ _ _ . - _ _ _ - - - - .
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: GOP
-JPM Number: NRC-NEW3 Task
Title:
Determine Time to Core Boilina i_
Denote Critical Steps with an "X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade Start Time: I l
STEP 1 Performance Step: Obtain a copy of the appropriate procedure and select the appropriate section to determine time to core boiling. j GRADE Standards: Obtains a copy of OP3260A, Conduct
, of Outages, and selects section 1.1.4.a as the proper guidance for determining the time to core boiling.
Comments: If the examinee questions " update the plant " STATUS BOARD", provide the folbwing cue:
! Cue:: The' US will ensuie that th'e5
~ ~
Lappropriate updates'.are made. J l STEP 2 Performance Step: DETERMINE the time to core boiling and UPDATE the plant " status board" daily as follows:
IE the plant is in MODE 5 AND the RCS is vented to atmosphere QB with pressure between 45 psia and 170 psia, Perform the following:
1)lE RCS temperature is s 110'F, Refer to A_ttachment 5.
2)lE RCS temperature is s 140'F, Refer to Attachment 6.
3
PERFORMANCE INFORMATiON
, . Facility: Millstone Unit 3 System: GOP
'JPM Number: NRC-NEW3 Task
Title:
Determine Time to Core Boilina Denote Critical Steps with an T
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade
, GRADE Standards: Uses OP3260A, Step 1.1,4.a.1, and selects Attachment 5 as the correct attachment to use for the determination of time to core boiling.
STEP 2 Performance Step: Use Attachment 5 to determine time to core boiling.
4 GRADE Standards: Uses Attachment 5, column 1 Shutdown time (days), and reads
] dowa the column until he comes to 160,
. GRADE Standards: From 160 in column 1, goes across to i column 6, labeled 4 Loops and reads time to core boiling (hours) 5,6 l
STEP 3 Performance Step: Notify US that the time to core boiling has been determined
- GRADE _
Standards: Notifies the US that the time to core boiling has been determined as 5.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
Terminating Cue: The evaluation for this JPM is concluded, i Stop Time:
4 e ~
VERIFICATION OF COMPLETION'
-Job Performance Measure Number.; NRC NEW3- Revision: 0 Date Performed:
Examinee:
Evaluator:
.i Validated Time (min): Actual time to Complete (min);
t Result of JPMi (Denote by an S for satisfactory or a U for unsatisfactory)
Result of oral questions: Number of Questions:
Number of Correct Responses:
Score %
5
EXAMINEE HANDOUT INITIAL CONDITIONS AND INITIATING CUES JPM Tracking Number: NRC-NEW3 InitiaLC_onditions: The plant is in MODE 5, shutdown 160 days for an extended non refueling outage, RCS pressure is being maintained at 45 psla on a Na, RCS temperature is 105'F, and none of the RCS loops has been drained or isolated.
l l Initiating Cues: Given the plant conditions above, the US has directed you to l calculate " time to core boiling". '
6
Administrative Topic Outline for RO A.1 Conduct of Operations.
Responsibilities as the oncoming operator concerning the shift turnover -
process.
Question: The plant is in Mode 2 conducting a reactor startup. Bank D control rods are 60 steps from the ECP._ .You are the oncoming RO_ When would it be appropriate to relieve the shift? ,
l Cop 200.1 Section 1.20 states that "The SM/US shall ensure that the plant is in a controlled condition at the beginning of the shift relief process." A reactor start up is not a controlled situation. The RO should not relieve the shift until the reactor is critical and at a stable power level. ( Example would be stable in the IR below the POAH)
Administrative Topic Outline for RO A.1 Conduct of Operations Responsibilities as the oncoming operator concerning the shin turnover process.
Questiont As the oncoming RO what are examples of things that must be discussed and'or reviewed prior to assuming the watch? (list 5 examples) l COP 200.1 States that " The oncoming shift shall :
Ensure properly licensed or qualified to assume the assigned shift position Ensure physically and mental fitness to completely discharge assigned responsibilities Discuss important items affecting plant operations with counterpart Review pertainent information identified on the shift relief and tumover report generated in the last 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> e
Review logs and checklists applicable to assigned shift position e
Walkdown control boards and discuss the following:
e Unusual events that occurred during the last 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />
- Status of safety related equipment Inoperable equipment and ACTION statements, including surveillance -
requirements Reasons for annunciator alarms
- Tagged equipment, including any surveillance or equipment work in progress at time of shift relief and turnover Running equipment and train alignments e Read and Sign the turnover report"
JOB PERFORMANCE MEASURE WORKSHEET-
- 1. JPM
Title:
P & ID Reading and Identification of Comoonents/ Nomenclature ID Number: NRC NEW2 Revision: 0 l
- 11. Initiated:
l r
l R.L. Lueneburg 5/29/97 i
Developer Date a
111. Reviewed:
Technical Reviewer Date Instructional Reviewer Date IV. Approved:
Operations Manager Date Nuclear Training Supervisor Date 1
JOB PERFORMANCE MEASURE WORKSHEET
, Facility: Millstone Unit 3 Examinee:
JPM Tracking Number:
NRC-NEW2 Validation Time:
- minutes
' Task
Title:
P & lD Reading and Identification of Comoonents/ Nomenclature Time Critical Task: ( )YES ( X ) NO 1 Task Number: 119*046*01*01 K/A Number; Eauioment Control KIA Rating:
Acolicable Methods of Testina:
Simulate Performance Actual Performance X Classroom Simulator X Plant X Task Standards: Satisfactorily ask the provided questions using a set of P&lDs as the only reference.
Reauired Materials: Set of P&lDs
- General
References:
P&lDs i
READ TO THE EXAMINEE l will explain the initial conditions, which step (s) to simulate or discuss, and provide initiating
. cues. When you complete the task successfully, the objectives for this JPM w !! be satisfied.
You may use any approved reference materials normally available in the Control Room, including logs. Make all written reports, oral reports and log entries as if the evolution was actually being performed.
initial Conditions: You have been asked to answer a series of questions using a set of P&lDs as your only reference.
Initiating Cues: Answer t.1e following questions:
If it became necessary to drain the " Neutron Shield Tank Surge Tank", to which plant system wobid it be drained?
What automatic functions are associated with 3OSS-TE387 List the 9 sig[1als that would res;lt in an SBO diesel shutdown.
2
PERFORMANCE INFORMATION Facility: Villstone Unit 3 System: Admin LJPM Number: NRC-NEW2 Task
Title:
P & ID Reading and identification of Comoonents/ Nomenclature Denote Critical Steps with an "X"
- NOTE
- Critical Steps must be cumpleted correctly to achieve a satisfactory grade Start Time:
Comments: The examinee may answer the questions in any order.
STEP- 1 X Performance Step: Ifit became necessary to drain the
" Neutron Shield Tank Surge Tank", to which plant system would it be drained?
GRADE X Standards: Looks at the P&lD index and determines that EM-114A is the appropriate one for Neutron Shield Tank Cooling. Locatet. the Surga tank and its associated drain line. Reads the nomenclature concerning where the drain line goes. Answer:
Radioactive Liquid Waste and Aerated Drains, STEP 2 X Performance Step: What automatic functions are associated with 30SS-TE38?
GRADE '
Standards: Looks at the P&lD index and determines that EM-115A is the appropriate one for the QSS system.
locates instrument 3OSS-TE38 as a temperature element on the RWST (1-3). Determines that there are 2 automatic functions associated with this element:
- Auto starts 30SS-1 A/B on Hi Temp.
3
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: Admin
_JPM Number: NRC-NEW2 Task
Title:
P & ID Reading and Identification of Comoonents/ Nomenclature Denote Critical Steps with an T
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade (requires going to location B-4 on the same P&lD and analyzing the pump start circuit).
- Follows the lines that go to EM-122A , Reactor Plant Chilled Water System. Determines that 30SS-TE-l 38 crovides an open signal to 3CDS-SOV26 to provide cooling water to the Refueling Water Coolers.
STEP 3 X Performance Step: List the 9 signais that would result in an SBO diesel shutdown.
GRADE X Standards: Looks at the P&lD index and determines that the EM-158 series is
' the right series for the SBO Diesel.
After locating that series, determines that EM-158B is the correct page.
Locates the engine shutdown symbol (6-2 at J-11) and traces the 9 input lines:
- Primary Protective Relay
- Backup Protective Relay
- Emergency Stops
- Crankcase Hi Pressure
- Low Lube Oil Pressure
- High Lube Oil Temp.
- High Coolant Temp.
- Low Water Pressure w/ Low Water Level 4
PERFnRMANCE INFORMATION
- Facility: Millstone Unit 3 . System: Admin JPM Number: NRC-NEW2 -
Task Title; P & ID Reading and Identification of Comoonents/ Nomenclature Denote Critical Steps with an "X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade STEP 4- Performance Step: Indicate that all of the questions have been answered, I ' GRADE Standards: Informs the examiner that he har completely answered the 3 questions.
Tnrminating Cue: The evaluation for this JPM is concluded.
Stop Time:
5
. 1
VERIFICATION OF COMPLETION
- Job Performance Measure Number: NRC-NEW2 Revision: 0-Date Performed: ---
Examinee:
Evaluator: _ - - -
l l
l Validated Tiine (min): Actual time to Complete (min):
t i
Result of JPM: (Denote by an S for satisfactory or a U for unsatisfactory)
Result of oral questions: Number of Questions:
Number of Correct Responses:
Score %
9 6
EXAMINEE HANDOUT INITIAL CONDITIONS AND INITIATING CUES JPM Tracking Number: NRC-NEW2 initial Condi1[ons: You have been asked to answer a series of questions using a set of P&lDs as your only reference, initiating Cues: Answer the following questions:
i If it became necessary to drain the " Neutron Shield Tank Surge Tank", to which plant system would it be drained?
- i. -
What automatic functions are associated with 3QSS-
[ TE38?
List the 9 signals that would recult in an SBO diesel '
shutdown, 7
A.3 Radiation Control Knowledge of radiation exposure limits and contamination control, including permissible levels in excess of those authorized.
Applicable references available at the RCA may be used to answer this question.
Question #1 You have been sent to the auxiliary building to complete some tagging. One of the tags that you must hang requires you to enter a Tech Spec Locked liigh Radiation Area. What requirements must be met for you to make this entry? Assume the radiation levels and the time to complete the job will are low enough that you will not exceed any personnel exposure limits.
Answer:
i Check Radiation Work Permit #5, job step 2 of 4.
Must contact 11P for a PRE-JOB Brief and latest survey data The llP briefing shall include:
Digidose alerm setpoint and Stay Time Control / Return ofIIR-2 Key
't Survey meter, alarming dosimeter or continuous HP coverage required for entry into Tech Spec Locked liigh Radiation Areas.
4 e
A.3 Radiation Control Knowledge of radiation exposure limits and contamination control, including permissible levels in excess of those authorized.
Question #2 If you were sent to the Auxiliary Building to replace a filter that was in a housing that had a contact dose rate of 450 mrem /hr and you expected to receive a dose to your extremity of 125 mrem and a whole body dose of 20 mrem, what spet.al instructions must be met.
Answer:
1 Check Radiation Work Permit 5, job step 1, Operations Blanket l
Under the Special Instructions Section notes the following for Filter change Evolutions:
Any filter housing with a contact dose rate of 500 mrem 41r or greater will be worked on RWP 10. Since the contact reading is 450 mrem /hr, can perform the task under RWP 5 Hp to survey filter housing prior to filter removal and survey filter (s) upon removal Because filter changes are rapid evolutions, finger rings are required when dose to the extremity 5 times the whole body dose and dose to the extremity >100 mrem is expected. Based on the given conditions, the expected dose to the extremity is greater than 5 times the expected whole body dose and is greater than 100 mrem. A finger ring is required.
HP to survey all tools and work area
A.4 Emergency Plan -
Knowledge of ROs responsibilities in emergency plan implementation.
Question #1 You are the on shif1 Reactor Operator when a significant plant event occurs and a Site Area Emergency classification has been declared. You find yourselfin a situation where you know you must take action to protect the public health and safety. Ilowever, the action you must take is not covered by any plant procedure nor is it in the plant's Technical Specification. What should you do?
Answer #1 10CFR 50.54(X) allows the licensee to take reasonable actions that depart froma license condition or Technical Specification under an emergency situation when the action must be taken to immediately protect the puiblic health and safety.10CFR 50.54(Y) further states that actions taken under 50.54(X) must be approved by a licensed senior operator prior to taking the action.
Consequently, the RO should state that he would take the required action aher having the SM or US or another licensed senior operator app ove the action.
A.4 Emergency Plan ,
Knowledge of ROs responsibilities in emergency plan implementation.
Question #2 You are at home when you receive a call from the plant stating that a Site Area Emergency has been declared and you are required to report to the plant and augment the operations shift.
Describe your responsibility for reporting to work.
Where do you report?
(No references are allowed)
Answer #2 First, must determine if fit for duty and advise the person calling of that situation.
If fit, report to the site. Upon arriving at the site, if access is restricted, report to the manager of resources in the EOF. If access is not restricted report to the Contol Room.
Reference:
SERO Handbook and annual SERO training 4
A.4 Emergency Plan Knowledge of ROs responsibilities in emergency plan implementation.
Question #2 Based on a significant plant transient a General Emergency classification was declared 90 minutes ago. You are the Reactor Operator and you have taken several calls from the Plant Equipment Operators (PEOs).
How often are the PEOs required to report to the control room and what type of information should they report?
Answer #2 1
The PEOs should call into the control room every 15-30 minutes and report the status of equipment in their area.
l
/
0 V
\
Individual Walk Throuch Test Outline
- Millsone Unit 3 Exam Date: Week of 7/7/97 -
SRO-U SgLL JPM # and Title Safety Function Ss s Code In Plant 113 RPCCW Swing Pump Alignment Due to Loss of RPCCW 8 008 Train (D) 083 Local Containment Isolation Phase B (D) 5- 103 Simulator
. New3 Placing Excess UD in Service (N) 2 004 050 Pressurizer Pressure Control Following a Trip (A) 3 010
'025 Stop EDG "B" and Place in Standby (D) 6 064 l
l l
i
- --- ---- o
ORIG JOB PERFORMANCE MEASURE WORKSHEET
- l. JPM
Title:
ALIGN *C" RPCCW PUMP AND HEAT EXCHANGER TO THE "A" TRAIN ID Number: 113 Revision: 3 II. Initiated:
, A. Oxgrth 3/20/97 l Developer Date Ill. Reviewed:
t c. he%w e6 en.J C)))h7 .
Chfh Technical Reviewer Date y
(d
" 41(struhtiondeYie s~Y s/h1 Date IV. Approved:
/
/ -
\- _
t
[N 5[' ( 'l /
i OpDtions Manager Da'te i ' i f v -
cos?
Nuclear Training Supervisor Date 1
o
JOB PERFORMANCE MEASURE WORKSHEET l
Facility: M111sione Unit 3 Examinee:
1 JPM Tracking Number: 11?L_ Validation Time: 15 minutes t
Task
Title:
ALIGN *C" RPCCW PUMP AND HEAT EXCHANGER TO THE "A" TRAIN Time Critical Task: ( )YES ( X ) NO Task Number: 008*034*01*01 AND 334*056*04*01 K/A Number: 008-030-A4.05 K/A Rating: 3.1/ 3.1 c
Applicable Methqds of Testing:
Simulate Performance X Actual Performance Classroom Simulator Plant X Task Standards: Satisfactorily align the "C" RPCCW pump and heat exchanger to ihe "A" train of RPCCW using OP 3330A Section 7.5.
Reauired Materials: None.
General
References:
OP 3330A, Rev.13 READ TO THE EXAMINEE I will explain the initial conditions, which step (s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objectives for this JPM will be satisfied.
You may use any approved reference materials normally available in the Control Room, including logs. Make all written reports, oral reports and log entries as if the evolution was actually being performed.
Initial Conditions: Train "A" RPCCW pump has been lost and the Control Room team is carrying out the actions in AOP 3561 for a loss of RPCCW. The Ctmt headers have been cross-connected. Both RPCCW pump "C" control switches are in the PULL-TO-LOCK position. Another PEO has been dispatched to complete steps 7.5.11 through 7.5.15 in OP 3330A and will provide you with the appropriate Kirk key when he has completed his actions.
Initiatina Cues: The US has directed you to align the "C" RPCCW pump and heat exchanger to the "A" train of RPCCW using OP 3330A Section 7.5.
2
s PERFORMANCE INFORMATION 7
Facility: Millstone Unit 3 System: CCP i JPM Number: 113 Task
Title:
ALIGN 'C' RPCCW PUMP AND HEAT EXCHANGER TO THE *A* TRAIN Denote Critical Steps with an *X"
' NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade 4
Start Time:
Comments: The position indicators for several of the valves that are manipulated during this JPM cannot be observed without a ladder. For the purposes of inls JPM lt is not required that a ladder be obtained to check the position Indications. The examiner shall provide the appropriate cues as to valve positions, Comments: Location for Penormance Steps 1 through 4 is Aux. Bldg. 24'6", near HX and pumps.
STEP 1 X Performance Step: CLOSE 3SWP'V68 and 3SWP'V69, RPCCW heat exchanger C Train B service water supply.
GRADE X Standards: Rotates the handwheel for 3SWP*V68 in the clockwise direction to close the valve
' Cue: The valve handwheefrotees in the clockwise direction Eventually some
= resistance ~ls met and the valve comes to a hard stop The position indicator
- points to't_he " closed? position (not observable);
t 3
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: CCP JPM Number: 113 Task
Title:
AllGN *C" RPCCW PUMP AND HEAT EXCHANGER TO THE 'A" TRAlh:
Denote Critical Steps with an *X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade GRADE X Standards: Rotates the handwheel for 3SWP'VGD in the clockwise direction to close the valve.
! Cue: The valve handwheel rotates in the
. clockwise direction. Eventually some resistance is met and the valve comes to a hard stop. The position Indicator points to the
- closed
- position (not
< observable).
STEP 2 X Performance Step: CLOSE 3SWP*V70 and 3SWP*V71, RPCCW heat exchanger C Train B service water returns.
GRADE X Standards: Rotates the handwheel for 3SWP'V70 in the clockwise direction to close the valve.
' Cuei The valve handwheel rotates in the clockwise direction. ar.d the position 3~
- indicator starts moving toward tho
. close pr>sition ' Eventualtj some -
- Tresistance is rnet and the valve comes
- to'a hard stop. The position indicator points to;the:" closed", position, GRADE X Standards: Rotates the handwheel for 3SWP'V71 in the clockwise direction to close the valve.
4
PERFORMANCE INFORMATION Facility: Mllstone Unit 3 System: CCP JPM Number: 113 Task
Title:
ALIGN 'C" RPCCW PUMP AND HEAT EXCHANGER TO THE *A" TRAIN Denote Critical Steps with an *X"
- NOTE' Critical Steps must be completed correctly to achieve a satisfactory grade
= Cue:' ~ The' valve handwheel rotates in the clockwise direction and the position Indicator starts moving toward the close position Eventually some resistance is met and the valve comes to a hard stop. The position Indicator points to the " closed" position. -
STEP 3 X Performance Step: OPEN 3SWP'V36 and 3SWP'V37, RPCCW heat exchanger C Train A service water supplies.
GRADE X Standards: Rotates the handwheel for 3SWP'V36 in the counterclockwise direction to open the valve.
Cue: The valve handwheel rotates in the counterclockwise direction; Eventually some resistance is met and the valve -
comes to a hard stop. The position -
indicator points to the 'open" position (not observable)e .;.
GRADE Standards: Rotates the handwheel 1/4 turn in the clockwise (close) direction, Cue: The haridwheel has bee'n rotated 1/4 -
. turn ir' the clockwise direction.-
5 J
PERFORMANCE INFORMATION Facility: Millstona Unit ? System: CCP JPM Number: -113 Task
Title:
ALIGN *C" RPCCW PUMP AND HEAT EXCHANGER TO THE "A" TRAIN Denote Critical Steps with an *X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade l
l GRADE X Standards: Rotates the handwheel for 3SWP*V37 in the counterclockwise direction to open the valve.
Cue: The valve handwheel rotates in the counterclockwise direction. Eventually some resistance is met and the valve; comes tola hard stop. The position -
indicator points to the "open" position
. (not observable).3 GRADE Standards: Rotates the handwheel 1/4 turn in the clockwise (close) direction.
Cue:' ' Theiharidwheel hasLbeen rotated 1/4
' turn in the clockwise directionc
-STEP "
4 X Performance Step: OPEN 3SWP'V41 AND 3SWP*V40, RPCCW heat exchanger C Train A service water returns.
GRADE X~ Standards: Rotates the handwheel for 3SWP*V41 in the counterclockwise direction to -
open the valve.
Cue':( ,
T TheValverhand_ wheel rotates in the
, , " counterclocknise' direction and the
, position' indicator starts' moving toward t '- the open positio_n. Eventually some <
resistance is met'and the valve comes to a hard'stop. The position indicator t points.to the "open" position.
6
PERFORMANCE INFORMATION f Facility: Millstone Unit 3 System: CCP JPM Number: 113 Task
Title:
ALIGN *C" RPCCW PUMP AND HEAT EXCHANGER TO THE 'A* TRAIN Denote Critical Steps with an *X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade GRADE Standards: Rotates the handwheel 1/4 turn in the clockwise (close) direction.
Cue: The handwheel has been rotated 1/4 turn in the clockwise direction, GRADE X Standards: Rotates the handwheel for 3SWP*V40 in the counterclockwise direction to open the valve.
Cue: The valve handwheel rotates in the_
counterclockwise direction and the position indicator starts movint towerd the open position. Eventually some resistance is met and the valve comes to a.hard stop.The position indicator points to the *open" position.
GRADE Standards: Rotates the handwheel 1/4 turn in the clockwise (close) directior,.
. Cue: .The handwheel has been rotated 1/4.
.tum in the clockwise dire'ction, STEP 5 Performance Step: PLACE both RPCCW pump C control Switches in PULL TO LOCK.
GRADE Standards: No action required. Both control switches are in PULL-TO LOCK. This was given in the initial conditions.
Comments: If the examinee asks the status of these switches, inform him that both switches are in the PULL-TO-LOCK position.
7
Y
?&?$WN T
f PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: CCP
^
JPM Number: 113 Task
Title:
AllGN *C" RPCCW PUMP AND HEAT EXCHANGER TO THE *A* TRAIN Denote Critical Steps with an *X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade Comments: Location for Performance Steps 6 and 7 is Aux. Bldg.14' platform, h STEP 6 X Performance Step: CLOSE 3CCP*V94 and 3CCP*V95, Train B RPCCW suction cross-connects.
, GRADE X Standards: Rotates the handwheel for 3CCP*V94 i in the clockwise direction to close the k
valve.
Cue: The valve handwheel rotates in the clockwise direction and the position Indicator starts to move toward the close position. Eventually some resistance is met and the valve comes to a hard stop. The position indicator points to the " closed' position.
GRADE X Standards: Rotates the handwheel for 3CCP*V95 in the clockwise direction to close the valve.
Cue: The valve handwheel rotates in the clockwise direction and the position Indicator starts to move toward the close position. Eventually some resistance is met and the valve comes to a hard stop. The position indicator points to the " closed" position.
8
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System; _CCP JPM Number: 113 I Task
Title:
ALIGN?C" RPCCW PUMP AND HEAT EXCHANGER TO THE *A" TRAIN Denote Critical Steps with an *X*
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory g ade i
STEP 7 X Performance Step: OPEN 3CCP*V93 and 3CCP*V92, Train A RPCCW suction cross-connects.
i GPADE X Standards: Rotates the handwheel for 3CCP'V93 in the counterclockwise direction to open the valve.
Cue: The ~ valve handwheel rotates in the counterclockwise direction and the position indicator starts moving tov.ard. Eventually some resistance is met and the valve comes to a hard ~
stop. The position indicator points to
- . the "open" position.
GRADE ~ ~ ~ ~
Standards: Rotates the handwheel 1/4 turn in the clockwise (close) direction.
Cue:; The'h'anawheel has been rotated 1/4 turn'in the clockwise direction.-
GRADE X Standards: Rotates the handwheel for 3CCP'V92
, in the counterclockwise direction to open the valve.
Cue:' The' vane handwheel rotates in the-counterclockwise direction and the ~
position indicator' starts to movei toward the open position. Eventually some resistance is met and the valve comes to a hard stop. The position
- indicator points to the "open" position.
9
1 PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: CCP JPM Number: 113 Task
Title:
ALIGN *C" RPCCW PUMP AND HEAT EXCHANGER TO THE *A" TRAIN Denote Critical Steps with an *X"
' NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade GRADE Standards: Rotates the handwheel 1/4 turn in the clockwise (close) direction.
~
- Cuei The handwheel has been rotated 1/4 turn in the clockwise direction. !
1 Comments: Location for Performance Steps 8 through 10 is Aux. Bldg. 24'6", near HX and pumps.
STEP 8 X Performance Step: CLOSE 3CCP*V8 and 3CCP*V10.
Train B RPCCW discharge cross-connects.
GRADE X Standards: Rotates the handwheel for 3CCP'V8 in the clockwise direction to close the valve.
! Cue: The valse h'andwheel rotates in the
~
l clockwise direction and the position p ,
Indicator starts moving toward the -
- close position. Eventually some resistance ls met and the valve comes to a hard stop.iThe position indicator'
- , points to the " closed" position.
GRADE StandarJr' Rotates the handwheel for 3CCP*V10 1 in the clockwise direction to close the valve.
l L
! 10
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: CCP JP.A Number: 113 Task
Title:
ALIGN "C" RPCCW PUMP AND HEAT EXCHANGER TO THE *A" TRAIN Denote Critical Steps with an *X"
- NOTE' Critical Steps must be completed correctly to achieve a satisfactory grade
! Cue: ' The' valve handwheel rotates in the -
" clockwise direction and the position indicator starts moving toward the close position, Eventually some -
resistance is met'and the valve com~es (to a hard stop. The position indicator l . , points to the
- closed". position.
L STEP 9 X Performance Step: OPEN 3CCP'V9 and 3CCP*V7, Train-A RPCCW discharge cross connects.
GRADE X Standards: Rotates the handwhee; for 3CCP*V9 in the counterclockwise direction to i- open the valve.
Cue: The valve' handwheel rotates in the counterclockwise direction and the position indicator starts to move -
toward the open position, Eventually :
some resistance is met and the valve comes to a hard stop. The position
- indicator polnts to the *open" position, GRADE Standards
- Rotates the handwheel 1/4 turn in the clockwise (close) direction.
i cuei The handwheel his beesi rotated 1/4
-turn in the clockwise direction, GRADE X Standards: Rotates the handwheel for 3CCP*V7 in the counterclockwise direction to open the valve.
11
PERFORMANCE INFORMATION Facility: Millstone Unit 2 System: _CCP JPM Number: 113 Task
Title:
ALIGN *C" RPCCW PUMP AND HEAT EXCHANGER TO THE "A" TRAIN Denote Critical Steps with an *X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade
~
' Cuei The valve handwheel rotates in the counterclockwise direction and the position indicator starts moving toward the open position. Eventually some resistance is met and the valve comes to a hard stop. The position Indicator
_ points to the ?open" position.
GRADE Standards: Rotates the handwheel 1/4 turn in the clockwise (close) direction.
Cue: ' The handwheel has been rotated 1/4 turn in the clockwise direction.
STEP 10 X Performance Step: OPEN 3CCP*VS, RPCCW pump C discharge valve.
GRADE X Standards: Rotates the handwheel for 3CCP*V5 in the counterclockwise direction to l open the valve.
Cue: ~'
The valve handwheel rotates in the counterclockwise direction l Eventually some resistance is met and the valve
.comes toLa hard stop. The position indicator points to the *open" position (notl observable);
GRADE Standards: Rotates the handwheel 1/4 turn in the clockwise (close) direction.
Cue: 4 The handwheel has been rotated 1/4
- turn in the' clockwise direction.
12
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: ._CCE_.
JPM Number: 113 Task
Title:
AllGN 'C' RPCCW PUMP AND HEAT EXCHANGER TO THE *A" TRAIN Denote Critical Steps with an T I
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade i cue l Steps 7.5.11 Thru 7.5.15 have been completed. Simulate handing Kirk Key
~ No. 3 to the examinee..
STEP 11 Performance Step: At 3CCP*TRS P1C (East MCC/RCA 46'), INSERT the Kirk key (No. 3) into the lower block at switch 2 and UNLOCK switch 2.
GRADE Standards: Inserts Kirk key No. 3 into the lower block and rotates the key to unlock switch 2.
Cue: The Kirk key has been Inserted, rotated, and switch 2 is unlocked.
STEP 12 Performance Step: OPEN switch 2 by pulling the lever arm down.
GRADE Standards: Pulls the lever arm down
~
Cueil The lever arm is in the down position e
13
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: CCP JPM Number: 113 .
Task
Title:
ALIGN *C" RPCCW PUMP AND HEAT EXCHANGER TO THE 'A" TRAIN Denote Critical Steps with an "X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade STEP 13 Performance Step: LOCK switch 2 open and REMOVE the upper Kirk key (No. 2).
GRADE ~
Standards: Rotates the Kirk key No. 2 to lock switch 2 and pulls the Kirk key out of the locking block.
Cue: The upper Kirk key (No. 2) has been rotated and you have the key in your hand.
STEP 14
~
Performance Step: INSERT Kirk key (No. 2)into the lower block at switch 1 and UNLOCK switch 1.
GRADE Standards: Inserts Kirk key No. 2 into the lower block and rotates the key to unlock switch 1.
Cue: The' Kirk key has been inserted,.
rotated,- and switch 1lls unlocked.
STEP ~~
15 Performance Step: CLOSE switch 1 by PUSHING the lever UP.
GRADE Standards: Pushes the lever up.
Cue: The lever is aligned to the up position.
14
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: CCP JPM Number; 113 Task
Title:
AllGN _*C" RPCCW PUMP AND HEAT EXCHANGER TO THE "A" TRAIN Denote Critical Steps with an T
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade STEP 16 Performance Step: LOCK switch 1 closed and REMOVE the upper Kirk key (No.1).
GRADE ~
Standards: Rotates the Kirk key No.1 to lock switch 1 and pulls the Kirk key out of the locking block.
Cue:' The upper Kirk key (Nol1) has been rotated and you have the key in your
'hande-Comment: For the next JPM step, the cabinet should not be opened. The examinee will have to simulate opening the door and explain his actions.
Comment: The examinee should explain during the next step that he would turn the key as far as it will go to ensure the electricat interlocks are also made up.
STEP 17 Performance Step: With Kirk key (No.1), UNLOCK the elevator mechanism at breaker 34C10 2.
GRADE Standards: Inserts Kirk key No.1 into the locking block and rotates the key to unlock the elevator mechanism.
Cue: iThe Kiik key is inserted and rotated..
~
Cue: 'For_ the purposes of this JPM assume that he has RACKED UP the "C" RPCCW pump circuit breaker into cubicle 34C10 2_
15.
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: CCP JPM Number: 113 Task
Title:
ALIGN "C" RPCCW PUMP AND HEAT EXCHANGER TO THE *A" TRAIN Denote Critical Steps with an T '
' NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade l
STEP 18 Performance Step: PLACE RPCCW pump C control switch, associated with the switchgear cubicle location 34C10 2 (Train A), to the AUTO position.
GRADE Standards: Requests that the control room-operators position the control switch associated with the switchgear cubicle location 34C10 2 for the "C" RPCCW pump to the " auto" position.
Cue: " Role play as an operator in the control room and_ report that te appropriate
' control switch for the *C"_ RPCCW pump has been placed in the
- auto" position.4 STEP 19 Performance Step: Notify the US that the "C" RPCCW pump and heat exchanger are aligned to the Train A RPCCW System.
GRADE Standards: Informs the US that Section 7.5 of OP 3330A has been completed and the
- C" RPCCW pump and heat exchanger are aligned to the Train A RPCCW System.
Terminating Cue: The evaluation for this JPM is concluded.
16 U
8 PERFORMANCE INFORMATION r Facility: Millstone. Unit 3 System:
j ._CC P . l 2
- JPM Number: 113 -
Task
Title:
AllGN "C" RPCCW PUMP AND HEAT EXCHANGER TO THE "A" TRAIN !
- Denote Critical Steps with an "X" j
- NOTE" Critical Steps must be completed correctly to achieve a satisfactory grade
[
1 t
i
- Stop Time: -
1-i b
4 3
4 t i
i i
17 L ,, n s
VERIFICATION OF COMPLETION Job Performance Measure Number: 113 Revision: 3_,
Date Performed:
Examinee:
l l
Evaluator:
Validated Time (min): 15 Actual time to Complete (min):
Result of JPM: (Denote by an S for satisfactory or a U for unsatisfactory)
Result of oral questions: Number of Questions:
Number of Correct Responses:
4 Score %
18
EXAMINEE HANDOUT INITIAL CONDITIONS ANO INITIATING CUES JPM Tracking Number: 113 initial Conditions: Train "A" RPCCW pun.p has been lost and the Control Room team is carrying out the actions in AOP 3561 for a loss of RPCCW. The Ctmt headers have been cross-connected. Both RPCCW pump "C" control switches are in the PULL TO. LOCK position. Another PEO has been dispatched to complete steps 7.5.11 thru 7.5.15 in OP 3330A and will provide you with the appropriate Kirk key when he has completed his actions.
initiating Cues: The US has directed yota io align the "C" RPCCW pump and heat exchanger to the "A" train of RPCCW using OP 3330A Section 7.5.
I e
i 19
0A)0.
JOB PERFORMANCE MEASURE WORKSHEET I, JPM
Title:
LOCAL CONTAINMENT ISOLATION PHASE B i
ID Number: JPM 083 Revision: 2 ll, initiated:
A. Oxfurth 1/07/97
- Developer Date Ill. Reviewed:
h,[ L" Idd7 Technical Reviewer Date
, /n R'? NIL ~
l- '#/ I7
' Instructional R'eviewM Date IV. Approved:
( .7/747 perations Manag Date f
h A?
Nuclear Training Supervisor Date 1
1 JOB PERFORMANCE MEASWE WORKSHEET l Facility: Millstone Unit 3 Examloee:
. JPM Tracking Number: 08.3 Validation Time: 12 minutes I Task
Title:
LOCAL CONTAINMENT ISOLATION PHASE B j Time Critical Task: ( )YES (X)NO Task Number: 000'027'05'01
! K/A Number: .103 000 A2.03 K/A Rating: 3.5/3.8 l
5 Applicable Methods of Testina_:
Simulate Performance X Actual Performance -
- Classroom Simulator Plant X i
l Task Standards: Satisfactorily conduct local containment phase B isolation IAW [
i .
Reauired Materials: Nole.
l ,
i j .Genntal
References:
READ TO THE EXAMINEE l
l will explain the initial conditions, which step (s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objectives for this JPM will be satisfied.
You may use any approved reference materials normally available in the Control Room, including logs. Make all written reports, oral reports and log entries as if the evolution was actually being performed, initial Conditions: The plant has had a loss of all AC fellowed by a CDA due to a steam line rupture in containment. Containment pressure is 27 psia. The Control Room team is carrying out the actions of EOP 35 ECA 0.0. A CDA signalis actuated. RPCCW containment outer supply and return header isolation valves are Dol closed, initiating Cues: The US has directed you to locally complete a Phase B Containmer.t Iso!ation using EOP 35 ECA 0.0 Step 21.b under the " Response Not Obtained" column and locally close the valves listed.
2
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System:
, CCE JPM Numt;;r: QB3 Task Tide: WLGONTAltlMENT ISOLATION PHASE B Denote Critical Steps with an *X"
' NOTE
- Crit; cal Steps must be completed correctly to achieve a satisfactory grade Start Time:
Cornments: The examinee can perform Steps 1 - 4 in any order.
l STEP 1 X Performance Step: Close valve 3CCP'MOV49A.
l GRADE X Standards: Locates valve 3CCP*MOV49A (Train
! A RPCCW containment outer return isolation, Auxiliary Bldg. El. 4') and disengages the clutch by positioning the lever to the disengaged position.
~
t Cser: .,ThelblUtch is disengaged.i GRADE Standards: Rotates tne valve handwheelin the clockwise direction until the valve is fully closed.
L Cue: The Vaive handwheel rotates in the -
clochvise direction. Eventually, some.
resistance is met and the handwheel;
'comes to a hard stop,' The position Lindicator points to the,"close" position.
3
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: CCE JPM Number:- 013 Task
Title:
LOCAL CONTAINMENT ISOLATION PHASE B Denote Critical Steps with an *X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade STEP 2 X, Performance Step: Close valve 3CCP'MOV498.
~
GRADE X Standards:
Locates valve 3CCP'MOV49B (Train B RPCCW containment outer return isolation; Auxiliary Bldg. El. 4') and disengages the clutch by positioning the lever to the disengaged position.
Cuei; : The, clutch is~ disengaged,L GRADE X Standards: Rotates the valve handwheelin the clockwise direction until the valve is fully closed and re engages the clutch.
Cue: i The Vahishendwh^ eel rotates'in the clockwise direction.; Eventually, some -
resistance is met and the handwheel-comes to a'hard stop: The position
, ) indicator poi.nts to the "close" position..
STEP 3 X Performance Step: Close valvo 3CCP'MOV4SA.
GRADE X Standards: Locates valve 3CCP*MOV4SA (Train '
A RPCCW containment supply header isola'. ion, Auxiliary Bldg. 4') and disengages the clutch by positioning the lever to the disengaged position.
' ~
[Cuefi TTh6 clutch 1s;disehgaged.
GRADE X Standards: Rotates the valve handwheelin the clockwise direction until the valve is fully closed and re engages the clutch.
4
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: CCE JPM Number: 013 Task
Title:
LOCAL CONTAINMENT ISOLATION PHASE B Denote Critical Steps with an *X"
' NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade icuei The valve handwheel rotates in the
\; clockwise direction. Eventually, some l fi resistance is met and the handwheel comes to a hard stop.: The position indicator points to the."close" position.
STEP 4 X Performance Step: Close valve 3CCP'MOV45B.
GRADE X Standards: Locates valve 3CCP'MOV45B (Train B RPCCW containment supply header isolation, Auxiliary Bldg. El. 4') and disengages the clutch by positioning the lever to the disengaged position.
. Cue: The clutch is' disengaged.-
GRADE X Standards: Rotates the valve handwheelin the clockwise direction until the valve is fully closed and re engages the clutch.
' Cue: The vsive' handwh'eel rotatas in the~
clockwise direction. Eventually, some resistance is met and the handwhesi comes_ to a'hard stop.LThe position indicator points to the close" position.
Comments: Infoim examinee that a Control Room Operator will reset the CDA as required by the next step in the prc.aedure, STEP 5 Performance Step: Notify the Control Room that a Phase B containment isolation has been completed.
5
PERFORMANCE INFORMATION .
Facility: Millstone Unit 3 System: CCE JPM Number: 033 Task
Title:
LOCAL CONTAINMENT ISOLATION PHASE B Denote Crithal Steps with an T
- NOTE
- Critical Steps must be cornpleted correctly to achieve a satisfactory grade GRADE Standards: Examinee reports to the US that a local Phase B containment isolation has been completed and that the valves listed in step 21.b RNO of ECA 0.0 have been closed locally.
Terminating Cue: The evaluation for this JPM is concluded.
Stop Time:
t 6
_ _a
VERIFICATION OF COMPLETION Job Performance Measure Number 083 Revision: 2 Date Performed:
Examinee:
Evaluator:
Validated Time (min): .12. Actual time to Complete (min):
Result of JPM: (Denote by an S for satisfactory or a U for unsatisfactory)
Result of oral questions: Number of Questions:
Number of Correct Responses:
Score %
7
EXAMINEE HANDOUT INITIAL CONDITIONS AND INITIATING CUES JPM Tracking Number: 013 Initial Conditions: The plant has had a loss of all AC followed by a CDA due to a steam line rupture in containment.
Containment pressure is 27 pala. The Control Room team is carrying out the actions of EOP 35 ECA 0.0. A CDA signalis actuated. RPCCW containment outer supply and rlturn header Isolation valves are nni closed.
Initiating Cues: The US has directed you to locally complete a Phase B Containment isolation using EOP 35 ECA-0.0 Step 21.b under the " Response Not Obtained" column and locally close the valves listed.
8
11 3 JOB PERFORMANCE MEASURE WORKSHEET
- l. JPH
Title:
PLACING EXCESS LETDOWN IN SERVICE VIA LOOP DRAIN ID Number: NEW-3 Revision: 1 II. Initiated:
Rav Lunneburg 51D192 Developer Date l
Ill. Reviewed:
__ E Technical Reviewer 6/22/f7 Ddte Yh Instructional ReNiewer- (/N7)
Date IV. Approved:
h A~
Operations Manager Date 1%il Nuclear Training Supervisor Date 1
JOB PERFORMANCE MEASURE WORKSHEET Facility: Millstone Unit 3 Examinee:
JPM Tracking Number: t1EE3 validation Time: 17 minutes Task
Title:
PLACING EXCESS LETDOWN IN SERVICE VIA LOOP DRAIN Time Critical Task: ( )YES ( X )NO Task Number: 00E Q E Q1*01 K/A Number: 00_4.KL25 KIA Rating: 2.7/3.2 Acolicable Methods of Testing:
Simulate Performance Actual Performance X Classroom Simulator X Plant Task Sigtodards:
Satisfactorily place excess letdown in service from an RCS loop.
i Required Materials: Copy of OPS Form 3304A 7 to give to examinee.
General
References:
OP3304A, Rev. 24 READ TO THE EXAMINEE I will explain the initial conditions, which step (s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objectives for this JPM will be satisfied.
You may use any approved reference materials normally available in the Control Room, including logs. Make all written reports, oral reports and log entries as if the evolution was actually being periormed.
Initial Conditions: While performing SSPS testing, an iradvertent Si occurred. The control room team has carried out the actic. s of E-0 and transitioned to ES 1.1.
While attempting to restore letdowr , pressure control valve PCV 131 failed closed.
Initiating C.ues: The US has directed you to establish excess letdown from loop 1 using OP 3304A section 7.15. Recovery of excess letdown is desired.
2
JOB PERFORMANCE MEASURE WORKSHEET Simulator Requirements: 1. Reset to IC #14.
- 2. Place the simulator in *Run". Place the master silence i switch in " silence",
- 3. Insert the following malfunctions:
- RPOSA, Sl Train A actuation
- RPOSB, Si Train B actuation CV05, LTDN Press. Trans. Fall, PT131,0% severity
- 4. Red flag the components that started on the SI.
- 5. Remove malfunctions RPOSA & B and perform the following:
Reset Si and CIA l -
Use remote function EDR18 to
- reset" 32 3T
- Open the CTMT Inst.- Air header isolation valves Stop the *B" charging pump Complete steps 6 & 7 in ES 1.1, establish normal charging .
Stop the Si and RHR pumps Throttle 3CHS*FCV121 to obtain charging flow of approximately 55 gpm Adjust seal flow with 3CHS*HCV182 so seal flow is approximately 9.8 GPM per pump,
- 6. Acknowledge / Clear alarms, place the master silence switch in " normal, and place the simulator in
- freeze".
- 8. Place the simulator in "Run" after the examinee has read-the initial conditions and initiating cues.
Approximate simulator setup time is 10 minutes.
3
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: CllS I
-JPM Number: NEW-3 Task
Title:
PLACING EXCESS LETDOWN IN SERVICE VIA A LOOP DRAIN Denote Critical Steps with an "X"
- NOTE
- Critical Steps must be compbted correctly to achieve a satisfactory grade Start Time:
STEP 1 Performance Step: ENTER the appropriate information on OPS Form 3304A-7 GRADE Standards: Enters the following data on OPS Form 3504A-7:
Time Date 3CHS-Tl 122 reading RCS cold leg temp (any MB4 or computer point value)
~
! Cue:'- 1When the examinee; has completed?
the' above listed;entriesirole_ play as -
the US:snd ask for the fom1, Tell the' 8
l examinee that you will forward the -
iform.;to Engineering.
STEP -2 X Performance Step: RCS loop 1: OPEN 3RCS*AV8037A, loop 1 drain valve (MB4)
GRADE X Standards: Depresses the "open" push button for -
3RCS*AV8037A and observes the indication lights shift to green OFF,
' red ON. Then releases the push button.
4
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: GiS
^
JPM Number: NEW-3 Task
Title:
EglNG EXCESS LETDOWN IN SERVICE VIA A LOOP DRAIN Denote Critical Steps with an "X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grede 4
STEP 3- X Performancc Step: OPEN 3RCS*AV8153, excess letdown heat exchanger inlet isolation (MB3).
GRADE X Standards: Depresses the *open" push button for 3RCS*AV8153 and observes the indicating lights shift to green OFF, red ON. Then releases the push button.
Comment: The initiating cue told the examinee
- that the recovery of excess letdown was required. Provide an additional cue if the extuninee questions what to-I do in the next step.
STEP 4 Performance Step: DETERMINE the plant requirements and ALIGN excess letdown diversion valve,3CHS*AV8143, using one of the following:
- IE recovery of excess letdown is 1- no.t desired (e.g., during plant heatup),
PLACE divert valve to CDTT position.
GRADE Standards: Observes that the control switch for 3CHS*AV8143 is already aligned to
- the VCT position.
5
PERFORMANCE INFORMATION -
Facility: Millstone Unit 3 System: GiS JPM Number: NEW-3 Task
Title:
PLACING EXCESS LETDOWN IN SERVICE VIA A LOOP DRAIN Denote Critical Steps with an T
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade t
Comment: The next JPM step does not require any immediate actions. It states limits that must be observed.
STEP Performance Step: - MONITO., excess letdown parameters when establishing excess letdown and do att exceed the following limitations:
- Do n01 exceed 180*F excess letdown heat exchanger outlet temperature as indicated on 3CHS-Tl 122 (MB3) e Do att exceed VCT pressure of 65 psia as inoicated on 3CHS PI 115
'(MB3)
GRADE -
Standards: Reads the limitations and observes them as excess letdown is established.
Comment: If the examinee questions how much excess letdown to establish provi3e the following cue:.
- Cue:' Establish excess ~ letdown so 3CHS-
) Tl122 is between 1602175'F a
! not exceed a VCT pressure of 65l psia.
Comment: While establishing excess letdown, the excess letdown heat exchanger outlet temperature will be the controlling parameter.
6
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System:
CliS JPM Number: NEW-3 Task
Title:
PLACING EXCESS LETDOWN IN SERVICE VIA A LOOP DRAIN Denote Critical Steps with an "X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade STEP 6 X Performance Step: ESTABLISH excess letdown by ADJUSTING 3CHS HC123, excess letdown flow control valve, for the desired letdown rate (MB3).
GRADE X Standards: Slowly rotates the potentiometer knob on 3CHS-HC123 while. observing excess letdown heat exchanger outlet temperature and VCT pressure.
When either of the limits is approached, stops opening HC123.
STEP 7 Performance Step: IE the excess letdown diversion valve is in the VCT position, VERIFY reactor coolant pump seal return flows are adequate using OP 3301D, " Reactor Coolant Pump Operation", Figure 9.2 and the indications listed below:
H2 INDICATOR RCP A 3RCS-FR156(3RCS-FR160)
RCP B 3RCS-FR156(3RCS-
. FR160)
RCP C 3RCS-FR154(3RCS-FR158)
RCP D 3RCS-FR154(3RCS-FR158) 7
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: CliS l
l JPM Number: NEW-3 __ '
Task
Title:
PLACING EXCESS LETDOWN IN SERVICE VIA A LOOP DRAIN Denote Critical Steps with an "X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade GRADE Standards: Goes to OP 3301D, Attachment 2.
With the No.1 seal differential pressure (psi) determines the acceptable range for No.1 sealleak rate (GPM). Observes that the seal '
leak rates are accepta' J.
!TCommenti Lin the'above step there is a procedure:-
Ediscrepancy'in that Figure 9.2 called :
for in the procedure is actually labeled -
e Attachment 2.L Cue the examinee to-use Attachment 2 if he' appears'to be:
. ; confused?
STEP 8 Performance Step: VERIFY annunciator " EXCESS LETDOWN HX OUT TEMP Hi",
MB3B2-8, not lit.
GRADE Standards: Observes that annunciator MB3B2-8 is not lit.
STEP 9 Performance Step: Notify the US that excess letdown from loop 1 has been established.
GRADE ,
Standards: Reports to the US that excess letdown from loop 1 has been established using OP 3304A section 7.15.
Terminating Cue: The evaluation for this JPM is concluded.
Stop Time:
8
' VERIFICATION OF COMPLETION i
- Job Performance Measure Number: - NEW-3 Revision: 0-Date Performed:
Examinee:
4 Y
Evaluator:-
. Validated Time (min,): 17 Actual time to Complete (min.):
Result of JPM: (Denote by an S for satisfactory or a U for unsatisfactory) e
- Result of oral questions
- Number of Questions:
Number of Correct Responses:
J Score %
k~
e 4
f 9
Q EXAMINEE HANDOUT INITIAL CONDITIONS AND INITIATING CUES-e 9
JPM Tracking Number: 810 61 Initial Conditions: While performing SSPS testing, an inadvertent SI occurred. The control room team has carried out the
,. actions of E-0 and transitioned to ES 1.1 While attempting to restore letdown, pressure control valve 3
PCV-131 failed closed.
i Initiating Cues: The US has directed you to establish excess letdown from loop 1 using OP 3304A section 7.15. Recovery of excess letdown is desired.
l l
t b
b i
l
)
t 4
i 10
JOB PERFORMANCE MEASURE WORKSHEET <
- 1. JPM Title; PRESSURIZER PRESSURE CONTROL FOLLOWING REACTOR TRIP ID Number: JPM.050A Revision: 5
- 11. Initiated; l A. Oxfurth 3/11/97
! Developer Date Ill. Reviewed:
3-U~V Tech'nical F' Reviewer Date w 3lISlD 7'IMrudtfonkstettehn ~ . Date IV, Approved:
'. t i
K~ ' '
'~5 I 'q 7 Operations Manager Date J ' '
au 1
Nuclear Training Supervisor
>mDate 1
l JOB PERFORMANCE MEASURE WORKSHEET >
Facility: Millstone Unit 3 Examinee:
-JPM Tracking Number: -Dh0A Validation Time: ._5__ minutes Task
Title:
PRESSURIZER PRESSURE CONTROL FOLLOWING REACTOR TRIP Time Critical Task: ( X )YES ( )NO Task Number: 000'013*05*01. 000'065*05"02. 010'005*01*01 and 010*013*04*01 K/A Number: 000-027-EA1.01 K/A Rating: 4.0 / 3.9 Acolicable Methods of Testing:
. Simulate Performance Actual Performance X Classroom Simulator X Plant Task Standards: Satisfactorily complete EOP actions to control pressurizer pressure using EOP 35 ES-0.1.
Reauired Materials: None.
General
References:
EOP 35 ES-0.1 Rev.13 READ TO THE EXAMINEE I will explain the initial conditions, which step (s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objectives for this JPM will be satisfied.
You may use any approved reference materials normally available in the Control Room, including logs. . Make all written reports, oral reports and log entries as if the evolution was actually being performed.
Initial Conditions: Ai1 inadvertent reactor trip has occurred. The control room team has completed the actions of E-0 and ES-0.1, through Step 4.
Initiating Cues: The US has directed you to check pressurizer pressure control using step 5 in EOP 35 ES-0.1. You will be responsible for acknowledging the alarms on MB4. During the performance of this JPM other annunciators may come in (i.e. condenser vacuum, etc.) The instructor will role play as a second control board operator and acknowledge / reset these alarms.
2
JOB PERFORMANCE MEASURE WORKSHEET Simulator Condition: 1. Reset to IC-20,100% steady state power.-
- 2. Insert malfunctions RP02A and RP02B - reactor trip.
- 3. Place the simulator in "RUN". Allow th'e reactor trip to occur, throttle back AFW flow to approximately 150 gpm per SG by closing the MDAFW flow control valves and throttling the TDAFW flow control valves to 10% open. Trip the TDFW pumps to minimize feedwater oscillations.
- 4. Acknowledge / reset alarms and place the simulator in
" Freeze".
- 5. Insert malfunction RXO6A, pressurizer spray valve PCV-455B auto control failure, at 50% severity over a ramp time of 120 seconds.
- 6. Under Simulator diagrams (left screen):
RX Sheet 13, component 3RCS PK455B, select " auto" and then " activate" This will keep controller PK455B in the
- AUTO" position.
The intent is to have an inadvertent reactor trip with a spray valve failing open after the simulator is placed in "RUN".
- 7. Place the simulator in "RUN" and verify RCS pressure is 2000 210 psig and decreasing, Place the simulator in
" FREEZE".
- 8. After the examinee has received the initiating cues and initial conditions, place the simulator in "RUN".
Approximate setup time is 10 minutes.
3
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: S01 JPM Number: 050A 4
-Task
Title:
Pressurizer Pressure Control Followina Reactor Trio Denote Critical Steps with an "X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade
. Start Time:
NOTE: If during the performance of this JPM, a Low Pressurizer pressure Si is 4
actuated, the examinee automatically !
fails, i
STEP 1 Performance Step: Check PZR Pressure Control
' Verify PZR pressure - GREATER THAN 1890 psla.
GRADE Standards: Checks pressurizer pressure greater than 1890 psia by obseNing pressure indication on meters RCS-Pl455A RCS-Pl456A RCS-Pl457 RCS-Pl458 OR Recorder PR455.
STEP 2 Performance Step: Verify PZR pressure - STABLE AT OR TRENDING TO 2250 psia.
GRADE- Standards: Notes that PZR pressure is less than 2250 psia and decreasing. Checks the RNO column and proceeds to step Sd.
4
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: S01 JPM Number: 050A Task
Title:
Pressurizer Pressure Control Following React _or Trio Denote Critical Steps with an "X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade STEP 3 Performance Step: Check PZR status: Check PZR pressure - LESS THAN 2250 psia.
GRADE Standards: Monitors pressure and observes that pressure is less than 2250 psla.
STEP 4 Performance Step: Verify PZR PORVs - CLOSED.
GRADE Standards: Verifies PZR PORV valves closed by observing indicating lights as green ON, red OFF.
Comments: The examinee may also check PORV outlet temp (RCS-Tl463) as approximately 110*F and PRT parameters as confirmatory indications.
Comments: During JPM steps 5,6 and 7, the examinee may decide to inform the US of problems and corrective actions taken in accordance with the procedure, This is not required for satisfactory completion of the step.
STEP 5 X Performance Step: Verify PZR spray valves - CLOSED.
GRADE X Standards: Identifies that loop #1 PZR spray valve, RCS*PCV455B is OPEN.
5
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: S01 JPM Number: 050A Task
Title:
Pressurizer Pressure Control Following Reactor Trio Denote Critical Steps with an "X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade STEP 6 X Performance Step: Proceed to RNO column 4
CLOSE the spray valves, GRADE X Standards: Depresses the " manual" pushbutton on controller RCS*PCV455B.
Observes the controller will not shift to l
" manual" (" auto" light stays lit and the
" manual" light does not come on),
Comments: The examinee may depress the "UP
- ARROW"(A) and/or "DOWN ARROW"(V) pushbuttons to confirm the controller did not shift to " manual".
This is not required to complete the j step. Additionally, the examinee may place the Msster Pressure Controller (3RCS*PCV455A) in " MANUAL" and increase its output in an attempt to close the spray valve. Since the controller output is already at the maximum, this will have no effect and is not required for completion of the step.
4 6
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: S01 l .JPM Number: .. 05QA Task
Title:
Pressurizer Pressure Control Followino Reactor Trio Denote Critical Steps with an "X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade STEP 7 X Performance Step: lE any spray valve can NQI be closed THEN STOP RCPs 1 and 2.
GRADE X Standards: Rotates RCP 1 control switch RCS-P1 A to the "STOP" position and observes the indicating lights shift to green ON, red OFF and amperage goes to zero. ,
GRADE X Standards: Rotates RCP 2 control switch, RCS-P1B to the "STOP" position and !
observes the indicating lights shift to green ON, red OFF and amperage goes to zero.
Comments: Annunciators "RCP Loop 1 Flow Lo",
- RCP Loop 2 Flow Lo" and "RCP Low Speed" will alarm. The examinee should silence and acknowledge these alarms. This is not necessary to satisfy this critical step.
STEP '8 Performance Step: Verify PZR heaters - ENERGlZED.
GRADE Standards:- Verifies heater groups 3RCS*H1 A, H18, H1C, H1D and H1E are on by observing the indicating lights as green OFF, red ON.
7
. _. _ _ . . . _ _ _ _ _ _ _ _ _ . _ _ _ _ . _ . _ _ _ _ _ _ . ~ . _ . . . _ _ . . _ . - . -
m PERFORMANCE INFORMATION
. Facility;. Millstone Unit 3 System: S01 JPM Number: 050A-Task
Title:
Pressurizer Pressure Control Following Reactor Trio
- Denote Critical Steps with an T
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade 1
STEP 9 Performance Step: Inform the US that pressurizer pressure control has been checked.
! GRADE Standards: Reports to the US that pressurizer 4
pressure control has been checked, RCPs 1 and 2 have been stopped and pressure is now stable. Also reports-the problem with the spray valve , if not previously done.
- i. Terminating Cue: The evaluation for this JPM is concluded.
Stop Time:
8
VERIFICATION OF COMPLETION '
Job Performance Measure Number: -
050A Revision: 5 Date Performed:
Examinee:
- Evaluator:
i Validated Time (min): 4 Actual time to Complete (min):
l l
!~ Result of JPM: (Denote by an S for satisfactory or a U for unsatisfactory)
Result of oral questions: Number of Questions:
Number of Correct Responses:
Score % j 9
h r EXAMINEE HANDOUT INITIAL CONDITIONS AND INITIATING CUES JPM Tracking Number: 050A Initial Conditions: An inadvertent reactor trip has occurred. The control room team has completed the actions of E-0 and ES-0.1 through step 4.
i Initiating Cues: The US has directed you to check pressurizer pressure
, control using step 5 in EOP 35 ES-0.1. You will be responsible for acknowledging the alarms on MB4.
i During the performance of this JPM other annunciators may come in (i.e. AMSAC not armed, condenser vacuum, etc.) The instructor will role play as a second control board operator and acknowledge / reset these alarms i-NOTE: If durino the nerformance of this JPM. a Low Pressurizer j pressure SI is actuated. the examinee automatically fAllb 10
JOB PERFORMANCE MEASURE WORKSHEET f^'
rf I. ; JPM
Title:
STOP EDGB AND PLACE IN STANDBY ID Number: .025 Revision: 6 II. Initiated:
e l R. L. Lueneburg 6/25/97 Developer Date i
Ill. Reviewed:
._ I b/2?l1f Teclinical Reviewer s Date I C/tyk7 Instructionai Reviewer Date IV. Approved:
f 0Lh Operations Manager Date b
Q 4(3Dd)
Nuclear Training Supervisor Date 1
JOB PERFORMANCE MEASURE WORKSHEET
. Facility: Millstone Unit 3 - Examinee:
2 JPM Tracking Number: 025 Validation Time: la minutes Task
Title:
STOP EDGB AND PLACE IN STANDBY Time CriticalTask: ( )YES ( X ) NO
) Task Number: ' 064*031*01*01 and 064*049*01*02
! K/A Number: 064-000.A4.01 K/A Rating: 4.0 / 4.3 l Acolicable Methods of Testing:
i Simulate Performance _ Actual Performance X 1
Classroom Simulator X Plant
- Task Standards
- Satisfactorily shutdown and place in standby the "B" Emergency Diesel Generator in accordance with OP 3346A.
1 Reauired Materik Sequencer Cabinet Key j _ General
References:
OP 3346A Rev.18 4
READ TO THE EXAMINEE I will explain the initial conditions, which step (s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objectives for this JPM will be satisfied.
You may use any approved reference materials normally available in the Control Room, including logs. Make all written reports, oral reports and log entries as if the evolution was actually being performed, t
Initial Conditions: The "B" Emergency Diesel Generator is in parallel with NSST "A" and is loaded to approximately 5000 KW.
Initiating Cues: The US has directed you to unlo'ad, shutdown, and place the "B" EDG in standby using OP 3346A, Section 4.14 starting with the note prior to Step 4.14.2 through step 4.14.11.
2
JOB PERFORMANCR MEASURE WORKSHEET SIMULATOR REQUIREMENTS: 1. Reset to IC-20, f
l 2. Start, synchronize, and load the "B" EDG to 6
' approxima'ely 5000 KW la accordance with OP 3346A, Section 7.2. Adjust MVARs to 3 MVAR (An alternative is to have already completed JPM-026, starting EDGB from MBB).
- 3. Place the simulator in " FREEZE" once the "B" EDG is loaded and sta' ole.
- 4. After the examinee has received the initiating cues and initial conditions, place the simulator in "RUN",
Approximate setup time B:10 minutes, i
e I
3
PERFORMANCE INFORMATION FaciliN:: Millstone Unit _3 - System: "
EQG
- JPM Number: = 02fi Tesk
Title:
. STOP EDGB AND PLACE IN STANDBY Denote Critical Steps with an "X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade -
. Start Timo:
STEP -1 X Performance Step: PERFORM the following simultaneously to reduce diesel generator B load (MB8):
L Using " SPEED / LOAD", ADJUST -
load to 200 to 400 kW output .
Using the selected voltage regulator, ADJUST reactive load to maintain approximately 0 MVAR.
" AUTO VOLT REGULATOR"
? MAN VOLT REGULATOR" GRADE *
-X Standards: Takes " Speed / Load" Switch to the I
" lower" position and, using the "B" EDG KW meter as indication, incrementally reduces load to 200-400 KW. The load reduction from 4500 KW to 200-400 KW should be accomplished over a 3 minute period.
GRADE ~~
X Standards: - Simultaneously, uses the auto voltage regulator control switch and lowers MVARs to approximately 0 MVAR.
tComments: The 3 minute time period is not a consideration in the critical nature of this step.
4
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System:
Title:
STOP EDGB AND PLACE IN STANDBY Denote Critical Steps with an *X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade S'i IP 2 X Performance Step: OPEN generator output breaker DGB*34D-2, "EDG B SPLY",
GRADE X Standards: OPENS EDG "B" supply (output) breaker and observes the indicating lights shift to green "ON", red "OFF".
TComments: The "B" EDG " START" light will illuminate.
STEP 3 X Performance Step: Using the selected voltage regulator, ADJUST diesel generator output voltage to approximately 4160 volts (3,950 to 4,350 volts):
- " AUTO VOLT REGULATOR"
- " MAN VOLT REGULATOR" GRADE X Standards: Adjusts "B" EDG Auto (Manual)
Voltage Regulator as necessary and obtains a Gencrtnor output of approximately 4160V. Observes the "B" EDG volts meter while making the adjustments. -
STEP 4 X Performance Step: Using " SPEED / LOAD" switch, ADJUST EDG B frequency to approximately 60 Hz (59.8 Hz to 60.2 Hz).
GRADE X Standards: Adjusts B EDG frequency as necessary to maintain a frequency of approximately 60 Hz.
5
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: EDra
-JPM Number: 025 Task
Title:
STOP EDGB AND PLACE IN STANDBY Denote Critical Steps with an "X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade STEP 5 Performance Step: PLACE diesel generator B " VOLT REG SEL"in " AUTO" .
l f GRADE Standards: The voltage regulator selector should be in " AUTO". No action is required.
STEP 6 X Performance Step: PLACE diesel generator B " MODE SEL"in " UNIT' .
GRADE X Standards: Saifts the mode selector switch to
" UNIT".
6
PERFORMANCE INFORMATION ,
L Facility: Millstone Unit 3 System: EDE JPM Number: Q?i Task
Title:
-3 TOP EDGB AND PLACE IN STANDBY -
Denote Critical Steps with an "X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade STEP 7 X Ponormance Step: WHEN diesel has cooled for five minutes,- PLACE diesel generator B
" START" switch in "STOP",
TCuE ^" ""W'Ma%nMsjimi!
- y? jhas cooled for five_ minutes (tol
, J ;facliitate timely l completion of thisi ,
P* / auu a:n iJPM,)bi , ,_ m, _
-GRADE X Standards: Rotates the manual Start' switch to the "STOP" position, TComments: " LOAD" light will extinguish, GRADE Standards: Upon receipt of "DG 'B' underfrequency" annunciator and "DG
'B' Local Panel Trouble" annunciators, acknowledge and resets alarms as appropriate, litCueb*?
^ ~
'llfl examinee'idispatches'PEO to chehk"l t;:
" : c the local panel l inform him it is thel
. (underfrequency alaimdit.wil' I tiei
. necessarylto.;use the instractor station i 5.to reset the local panel alarm and i-
{ clear the "DG 'B' Local Panel Trouble""
(.-b ,j(EGR07); ann 6nciatoron MB_8)l ,
7
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: EDG JPM Number: 025 Task
Title:
.STOP EDGB AND PLACE IN STANDBY .
Denote Critical Steps with an "X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade STEP 8 Performance Step. CLOSE 3SWP*AOV39B, "DG B OUT" (MB1).
GRADE Standards: Depresses close/ auto pushbutton for the Diesel Service Water Outlet Valve 3SWP-AOV398. Releases the pushbutton when indicating lights are green "ON", red "OFF" l
STEP 9 Performance Step: STOP diesel genera or B enclosure ventilation fans (VP1):
- 3HVP*FN18," SUPPLY FAN /DMPRS" 3HVP*FN1D, " SUPPLY FAN /DMPRS" GRADE Standards: Turns fans 3HVP*FN1B and 3HVP*FN1D control switches on VP1 to STOP and then releases them back to the AUTO position. Observes the indicating lights for FN1B and FN1D shift to green "ON", red "OFF".
TComments: EDG "B" enclosure ventilation dampers will also change positions as the fans are secured.
e 8
L PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: EDS JPM Number: 02ii Task
Title:
STOP EDGB AND PLACE IN STANDBY Denote Critical Steps with an "X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade STEP 10 X Performance Step: RESET sequencer B " AUTOMATIC
-TESTER" as follows:
- a. PLACE " AUTOMATIC TESTER" in " RESET"
- b. PLACE "AUTOMAllC TESTER" in "ON" >
- c. CHECK sequencer automatic test status indicator
" AUTOMATIC TEST NO" changes from P to A.
GRADE Standards: Opens cove door for EDG "B" Sequencer cabinet.
GRADE X Standards: Depresses toggle switch for the
" AUTOMATIC TESTER" to the RESET position and then lifts it back to the ON position. Observes that the test status indicator LED readout shifts from P to A.
ECueE !!nform' thshxamlhee'trist for the?
(purpose of this JPM, it is nots L necessary to complete step 4.14.12 -
i4.1.4;17; Terminating Cue: The evaluation for this JPM is concluded.
Stop Time:
9-
.. )
~ VERIFICATION OF COMPLETION Job Performance Measure Numbe-' 025- Revision: 6
' Date Performed:
1
_ Examinee:
Evaluator:
Validated Time (min): la Actual time to Cornplete (min):
l L
, Result of JPM: (Denote by an S for satisfactory or a U for unsatisfactory) .
Result of oral que:,tions: Number of Questions:
Number of Correct Responses:
Score %
=
10
i 1
EXAMINEE HANDOUT INITIAL CONDITIQNS AND INITIATING CUES t
i JPM Tracking Number: Q25 Initial Conditions: The "B" Emergency Diesel Generator is in parallel with NSST "A" and is loaded to approximately 5000 KW, Initiating Cues: The US has directed you to unload, shutdown, and place the "B" EDG in standby using OP 3346A, Section 4.14 starting with the note prior to Step 4.14.2 through step 4.14.11.
11
Individual Walk Throuch Test Outline hiillsone Unit 2 Exam Date: Week of 7 #97 RO'SRO 1 Set 1 (Rev. h
- JPhi */ and Title Safety Function Svs Code 1
i in Plant 006 Place swing Charger 301 A 3 on Bus 301 A 1(D) 6 063 019 Locally restore AFW Flow (Motor driven pumps 4 061
- and valves)(A) i 137 Establish Feed & Bleed on Charging Pump Cooling (D) 2 004 Simulator New! First 8 steps in ES 1,1, Si Termination (N) 2 006 News Containment Purge System Lineup (N) 8 029 055 hianual Initiation of Containment Spray (D) 5 026
- 109 Aligning Support Systems While Performing 8 008/078 l Recovery with the SBO Diesel (D) 050 Pressurizer Pressure Control Following a Trip (A) '3 010 042 Restore 4.16 KV Bus After Loss of Power (D) 6 062 New4 Pressurizer Level Failure (N) 7 016 hb
01216 /
JOB PERFORMANCE MEASURE APPROVAL SHEET
- 1. JPM
Title:
PIACE SWING CilARGliR 301 A-3 IN SERVICli ON HATil!RY BUS 301/n,L ID Number: JPM-006- Revision: _.ft _
- 11. Initiated-b'
-did'- [-
um-k---- -
1/23/97 Developer Date 11!. Reviewed:
A}ka //1)r1 rechnical Revie@er Date
[ f
&bYL E nstmetional Reviewer _
Gbrlf7 Date IV. Approved:
/N '< 1 prations Man Date
)~
Nuclear Training Supervisor t M74 Date Page 1 of 10
JOB PERFORMANCE MEASURE WORKSHEET Facility: Millsinne Unit 3 EXAMINFI:
JPM Tracking Number: .ig. Validated time: .JL_ minutes Task
Title:
PLACE SWING CilARGER 301 A 3 IN SERVICE ON BATTERY BUS 301 A-1 Time Critical Task: () YES (X ) NO Task Number: 3 W 058*04*01 i
K/A Number: 000-058-FA1.01 K/A Rating: 3.4 /3.5_ _
i Method of Testing:
Simulate Perfomiance ._X_ Actual Performance Classroom - Simulator Plant X _
Task Standards: i charger 301 A 3 in service on battery bus Satisfactorily place the su'ng 301A-1.
Reauired Materials: Kirk Key #14 (simulated).
General
References:
OP 3345C, Rev.14
- READ TO TlIE EXAMINEE
- 4 I will explair. the initial con:fitions, which step (s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this JPM will be satisfied.
You may use uny approved :xference material normally available in the Control Room, including logs Make all written repsts, oral reports and log entries as if the evolution was actually being perfomied.
Initial Conditions: DC Bus 301 A-1 (Battery Bus 1) has been lost. The Control Room Team is carrying ott.1he actions of AOI' 3563, Loss of DC Bus Power, initiating Cues:
'Ihc US directs you to restore battery 301 A 1 to senice on battery bus
- 30) A-1 and to place charger 301 A 3 on Bus 301 A-1, You are to use OP--
3345C Steps 4..i4 and 4.1. The battery has been on open circuit for one hour. You have Kirk Key #14.
Page 2 of 10
- J
PERFORMANCE INFORMATION FACILITY: Millstone Unit 3 SYSTEM: 125 JPM NUMBER: 006 TASK E 1.E: PLACE SWING CHARGER 301 A 3 ON BATniRY llUS 301 A 1 (Denote critical steps with an "Y ' Note
- Critical Steps must be corapleted correctly to achieve a satisfactory grade)
STEP 1. _ ltrfomiance Steps: '
IE the battery has been on open circuit for an extended period (greater than 1 months), refer to Section 4.15.and PERFOIB1 an equalizing charge prior to retuming the battery to senice.
GRADE _ _ Starxiards:
No action required. 'lhe battery has been out of senice for only one hour.
S'IEP 2. 1 It fomiance Steps:
WHEN ready to restore battery to senice, CLOSE the appropriate battery breaker: 301 A 1, circuit 1 l
GRADE ._. ___ Standank:
l Locates battery breaker 301 A 1 and obsenes the front panel indications.
Cue:
'Ihe breaker indications are OPEN and DISCilARGED.
Conunents:
If the examinee checks " Bus 301 A-1 volts" meter, infomi him it reads zero.
! _ .X_ Standank:
- Charges the closing spring by cranking the extemal lever until the
- . " springs charged" indicator shows.
I Cue:
The " springs charged" indicator is showing.
Page 3 of 10
EERFORMANCE INFORMATION_
FAOLTIY: Millstore Unit 3 SYSlat: 125 JPM NUMBDI: 006 TASK 1TIU:: 11ACl3 MING G LARGER 301 A-3 ON HATIUlY.1).CS 301 A-1
.X_ Starxiarth:
Presses the "close" pushbutton to close the breaker.
Ort A loud " clunk" sound is heard and the breaker flag shifts to
" CLOSED". If the examinee checks the bus voltmeter, infonn him that it reads 125 VDC.
2 STU' .3. ._
Perfomunce Ste[s:
VERIFY battery charger " MANUAL EQUAllZE" switch (local) in the " FLOAT' position and the timer set to "ZERO". l GRADE ._ ._ Starxtutis:
Obsenes that the manual equalize switch is in the " float" position and the timer is set at zero.
l S1TP .J. __
Perfomurre Sters:
CllECK battery charger 301 A-3, ac input breaker (local) in the "OFF" position.
GRADE ._ _. Starxiarth:
Checks that the AC input breaker switch at Battery Charger 301 A 3 is in the OFF(down) position.
Ow:
Breaker switch is down; aligned to the "ofl" position.
STU' .5 _
Perfomunce Sters:
OBTAIN Kirk Key No.14 from SS Key locker. l GRADE __ __ Standarth:
The Kirk Key was provided (simulated) as part of the initiating cue.
Comnwnts:
If the examinee fbrgot the initiating cue and inquires about the key provide the following Ow: It is simulated that you have Kirk Key
- 14. l Page 4 of 10
r PERITMBIANCE INFOlB1ATION FAGU1Y: Milhtore Unit 3 SYSint: _ 125 JPM NUMBER: 006 TASK 1T11E: PLACE SMING OLARG131301 A-3 ON llATI131Y llUS 301 A-1 S113' _fi. _,
Ittfomture Ste[s:
IE either of the breakers closed in step 4.1.6 trips, Refer To step I 4.1.7 and, if necessary, step 4.1.8 and immediately PERFORM the required actions.
GRADE .__ Starukmh:
Reads the step and remains aware of the actions required.
S113' .2_ .X Perfomnrre Ste[s:
Place the following de breakers to "ON":
+
Using kirk key, at de btu 301 A-1 battery charger 1 301 A 3, de output breaker 13attery charger 301 A 3, de output breaker (local)
GRADE .X._ Starxiarth:
Inserts Kirk Key #14 into the blocking device on Bus 301 A 1 for i battery charger 301 A 3 DC Otttput 13reaker and unlocks the breaker.
Ow:
The interlock slug drops dosm out of the way.
._. .X_. Starxiank:
Moves the Battery charger 301A 3 DC output breaker switch on Bus 301 A-1 to the ON position.
Ow:
The output breaker switch handle is aligned to the "on" position.
Page 5 of 10
PERFORMANCE INFORMATION FAG 111Y: Millstore Unitl SYS1D1: 125 JPM NUMRER: _006 TASK 1 TILE: PLACE SMING OLARGDI 301 A-3 ON HATIERY llUS 301 A-1
._ .X_ Starxhuth:
Moves the 301 A 3 DC output breaker switch up to the ON position.
Ow:
1he output breaker handle is up and aligned to the "on" position.
Or:
If the examinee checks the battery charger 301 A 3 "D-C volts" meter, inform him it reads 128 volts.
STEP _fL _X_ Perfomuure Step:
IE either de output breaker trips as indicated by battery charger voltage more than 10 volts below battery bus voltage and decreasing, CYCLE both the following breakers to "OFF", then "ON": l
- a. At de bus 301 A 1, battery charger 301 A-3, de ,I output breaker
- b. 13attery charger 301 A 3, de output breaker (local).
GRADE __ X_ Starxhutis:
No action required because neither breaker tripped.
STEP .1 ._ Perfomuure Step:
IE battery charger voltage is more than 10 volts below battery bus voltage and decreasing. NOTIFY the SMUS the battery charger can l not be placed in service.
GRADE __ ___ Starxhutis:
No action required. Battery charger voltage is not low.
Page 6 of 10
EERFORMANCE INFORMATION FAGl11Y: Millitorr Unit 3 SYS1D1: 125 i JIN NUMilDt: 006 TASK 111U:: PLACE SMING OLARGDI 301 A-3 ON IIATIEllY BUS 301 A-1 STEP .IIL X_ lirfomuure Step:
PLACE the following battery charger breakers to "ON" to load the charger:
- n. 480 volt supply breaker at bus 32 2T lhiB.
- b. 301 A 3, ac input breaker (local).
l GitADE _ .X_ Starxhuth:
l At bus 32 2T, positions the breaker handle for thiB to the "on" position.
Ow:
1he breaker handle fbr thiB is aligned to the "on" position.
._. .X_ Starxhuth:
At battery charger 301 A 3, positions the breaker handle for the ae inpu: breaker up to the "on" position.
Ow:
1he breaker handle fbr the ac input breaker is up and aligned to the "on" position.
STEP .11. _ Perfomuure Step:
CllECK battery charger 301 A 3 for the followirig and IE found, NOTIFY the SM:
+
1.ocal alami lights lit Voltage out of normal band (133 to 137 VDC)
+
Amperage out of nomial band (less than 200 amps)
Page 7 of 10
PERFOlB1ANCE INFOlB1ATION FAOLIIY: Millstoir Unit 3 SYS1D1: 125 JIN NUMBDt: _1%
TASK 1T11E: ftACE SWING OIARGDI 301 A 3 ON HATITRY BUS 301 A 1 GRADE _. Staruhuth:
i At battery charger 301 A-3, checks that the alann lights are all off.
Or:
All of the alann lights on battery charger 301 A 3 are o!T,
._ Staixlank:
Checks the voltage and amperage meters on battery charger 301 A 3 Ow:
1he voltage and amperage are nomial values.
STEP 12. .X._ Perfomuure Stels:
PLACE battery charger 301 A 3 "CilARGER FAILURE ANNUNCIATOR BYPASS" switch to "ON",
GRADE .X_ Standarth:
At battery charger 301 A-3, lifts the plexiglass cover and positions the CllARGER FAILURE ANNUNCIATOR BYPASS switch to the "on" position.
Or:
The CilARGER FAILURE ANNUNCIATOR BYPASS switch is pointing to the "on" position.
STEP 13. ._ 1erfonnance Steps:
lE either de output breaker tripped while placing the charger in service, NOTIFY the SM'US. l GRADE .__ __ Starxlarth: '
Neither breaker tripped. Consequently, it is not necessary to infban the SM'US.
l Page 8 of 10 a
PERFOlB1ANCE INFOlB1ATION FA OfflY: hiillstoir_L!alL3 SYS121: 125 JIS1 NUMBER: 006 TASK 111U:: . PLA& SW1NG OlARGER 301 A 3 ON BATERY BUS 301 A-1 STEP _11 ___
lYrfomarre Ste[s:
Notify the US that battery 301 A 1 is in senice on bus 301 A 1 and l battery charger 301 A 3 is on bus 301 A 1.
GRADE _.__ Standarth:
Infonns the SCO that steps 4.14 and 4.1 of OP 3345C have been completed and battery 301 A 1 is in service on bus 301 A 1 and l
battery charger 301 A 3 is on bus 301 A 1.
Temdnatlig Che: 1he evaluation for this JPM has been completed..
Page 9 of 10
T 2
VERIFICATION OF JPM COMPIITION
) Job Perfonnance Measure No.: 006 Revision: .6.
2 l
Date Perfonned:
Ihamince: i t
l Evaluator:
l
}' e c
Validated Time (min): 8 Actual Time to Complete (min):
(
1 f
r Result of JPM: (Denote by an S for satisfactory or a U for unsatisfactory) i i
Result of oral questions: Number of Questions >
Number of Correct Responses j Score % 1
?
Page 10 of 10
FXG11 NEE IIANDOUT INITIAL CONDITIONS AND INITIATING CUES JPM Tracklig Numlen 006 initial Coixlit'osci: DC lha 301A 1 (Battery ths 1) Ims tren lost. 'Ihe Control Rooni Teani is carryirg out the actiors of AOP 3563, less of DC lhu Ibwer.
1 initiating Ctes:
1he US directs yoti to restore lattery 2dl A 1 to service on tuttery lxn 301 A-1 arxl to [ dace charger 301 A 3 on Ihn 301 A 1. You are to tse OP 3345C Steps 4.14 mul 4.1. The tuttery las tren on cien circuit for one imur. You invc Klik Key #14.
Page 11 of 10
01 JOB PERFORMANCE MEASURE WORKSHEET i
i- s i
- l. JPM
Title:
Locally Restore AFW Flow (Motor Driven Pumos and Valves) l ,
i l lD Number: JPM 019 Revision: 5 1
i ll. - Initiated:
i ,
j R. Lueneburg S/25aI Developer Date 5 i
I lil, Reviewed:
i -- ,
l I
{ '){(t'f- s. , d- 2.5 'i'T
,' Technical Reviewer Date
- Y -
$h*/),)
j Instructional Reviewer Date
- IV. Approved
t
'$k
- Operations Manager Date G(3bb') '
Nuclear Training Supervisor Date J
l 1 g
3-=- e&---%-ts-ee p -w'- ,em- w--w-- --s *- - me e s- - m> ~,w v spe m v + re-.-,*ww w - - , e .--wwy,,- ,- - - , - *7&-- rn-rer-< -- ~, - m rw- y wr vg g-+ -r rw 7e- em y m ' ew1 - r
JOB PERFORMANCE MEASURE WORKSHEET Facility: Millstone Unit 3 Examinee:
JPM Tracking Number: ,_10_ Validation Time: 10_. minutes Task
Title:
Locallvlestore AFW Flow (Motor Driven Pumos and Valves)
Time Critical Task: ( )YES ( X ) NO :
Task Number: 000'039*05*01 and 000'090'05*02 K/A Number: 000 054 EA-1.01 K/A Rating: 4.5 / 4.4 Apdcable Mehods of Testing; Simulate Performarce X Actual Performance Classroom Simulator Plant X Task Standatdr Satisfactorily complete the local checks to restore AFW flow using Attachment A of FR H.1.
Required Materials: Locked Valve Key. OP 32608 Attachment 3 General
References:
EOP 35 FR H.1, Rev.10 READ TO THE EXAMINEE l will explain the initial conditions, which step (s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objectives for this JPM will be satisfied.
You may use any approved reference materials normally available in the Control Room, including logs. Make all written reports, oral reports and log entries as if the evolution was actually being performed.
Initial Conditions: A Loss of Secondary Heat Sink event is in progress and the control room team is carrying out the actions of EOP 35 FR-H.1. AFW flow could not be established from the control room.
initiating Cues: The US directs you to locally restore the AFW flow using the A and B MDAFW pumps IAW page 1 of 4 to Attachment A to EOP 35 FR H.1.
You are also to verify the position of any TDAFW valves on page 1. A second PEO is checking the lineup for the TDAFW pump.
2
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: AFW_
JPM Number: 019 Task
Title:
Locally Restore AFW Flow (Motor Driven Pumos and Valves)
Denote Critical Steps with an T
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade Start Time:
Comment: The steps in this JPM may be done in any order Comment: Location for JPM steps 13 is DWST enclosure 24' Comment: This JPM makes the assumption that the examinee knows how to verify the position of a locked valve. If at any time it appears that the examinee is uncertain how to verify the position ask him where he would go for ,
guidance. His response should be either to contact the US or obtain a copy of OP3260B, Equipment Control.
Provide the examinee with Attachment 3 from OP3260B. However, for the purpose of the evaluation of this JPM, it is acceptable for the examinee to immediately start and indicate that the locking devices would be removed to verify the valve positions.
- Cue: If the examinee' asks the status of the
~s lack in the locking device for any -
valve in the JPM give the following
. , C' 1: The locking device is installed
.wlth iusufficient slack to check valve
. position, 3
I
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: AFW JPM Number: 019 Task
Title:
Locally Restore AFW Flow (Motor Driven Pumos and Valves)
Denote Critical Steps with an *X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade STEP 1 Performance Step: Check A MD AFW Supply Header :
Isolation valve, 3FWA*V997, OPEN l GRADE Standards: Unlocks the locking device on valve 3FWA*V997 and removes the locking device. i Cue:- The lock is unlocked and the locking device is removed.
GRADE Standards: Rotates the handwheelin the
~
clockwise direction to confirm the valve is open.
Cue: Valve handwheel rotates in the clockwise direction.
GRADE Standards: Rotates the handwheelin the counterclockwisu direction until the valve is fully open.
Cue: Valve handwheel rotates in the
. counterclockwise direction, eventually
' 'some resistance is met and the valve comes to a hard stop.
GRADE Standards: Rotates the handwheel 1/4 turn in the clockwise direction.
,e Cue: ' The valve handwheel has been rotated 1/4 turn in the clockwise direction, GRADE Standards: Installs the locking device and locks the lock.
4
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: _AFW.
JPM Number: 019 Task
Title:
Losally Restore AFW Flow (Motor Driven Pumos and Valves) i
- Denote Critical Steps with an T
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade !
4 i t Cue: ~ The locking device is installed and.~
locked.
i STEP 2 Performance Step: Check *B" MD AFW Supply Header Isolation valve,3FWA*V998, OPEN.
l _ GRADE Standards: Unlocks the locking device on valve 3FWA*V998 and removes the locking
, device.
~ Cue: The lock is unlocked and the locking i . device is removed.
GRADE- ~
Standards: Rotates the handwheelin the
' clockwise direction to confirm the valve is open.
l Cuei Valve handwheel rotates in the
- clockwise direction. .
i GRADE ~~
Standards: Rotates the handwheelin the counterclockwise direction until the valve is fully open.
LCue: Valve handwheel rotates in the -
. counterclockwise direction, eventually some resistance is met and the valve
. comes.to a hard stop.; ,
GRADE Standards: Rotates the handwheel 1/4 turn in the clockwise direction, i
, 2 Cue:- :The valve handwheel has been rotated 1/4 turn in the clockwise-direction. .
5 i
l PERFORMANCE INFORMATION Facility; Millstone Unit 3 System:
=AcW l JPM Number: 019 Task litle: Lo.cally Restore AFW Flow (Motor Driven Pumos and Valves)
Denote Critical Steps with an *X"
- NOTE
- Critical Steps miist be completed correctly to achieve a satisfactory grade GRADE Standards: Installs the locking device and locks the lock.
Cue: The locking device is installed and locked, Comment: If the examinee questions what to do with the TD AFW valve 3FWA*V999, remind him that the initiating cue directed him to verify the position of this valve also, STEP 3 Performance Step: Check TD AFW Supply Header Isolation valve, 3FWA*V999, OPEN, GRADE Standards: Unlocks the locking device on valve 3FWA*V999 and removes the locking device,
- Cue
- ? The' lock is unlocked and the locking >
devibe is removed?
GRADE Standards: Rotates the handwheelin the clockwise direction to confirm the valve is open.
~
l Cue: iValve handwheel' rotates in the
- clockwise direction.-
GRADE- Standards: Rotetes the handwheelin the counterclockwise direction until the valve is fully open, 6
PERFORMANCE INFORMATION Facility: Millsione Unit 3 System: AFW '
I JPM Number: 019 .
1 Task
Title:
Locallv Restore AFW Flow (Motor Driven Pumos and Valves)
Denote Critical Steps with an T
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grado
- Cue: Valve handwheel rotates in the counterclockwise direction, eventually
. some resistance is met and the valve comes to a hard stop.
GRADE '
Standards: Rotates the handwheel 1/4 turn in the clockwise direction.
Cue: The valve handwheel has been rotated 1/4 turn in the clockwise direction.
GRADE Standards: Installs the locking device and locks the lock.
Cue: The locking device is insta!led and tocked.
Comment: Location for JPM steps 4 7 is ESF Bldg., A MD AFW Pump Ro6m,24' Cue: . When the examinee is in a position to observe the stem of valve 3FWA*V2, inform him that the valve stem is down, Comment: The examinee may question what to do with the out of position valve (may be concerned about a security event),
If this is the case, provide him with the cue to continue with the lineup, based on the cue concerning the stem '
position, the examinee may not conform the valves position as open and immediately open the valve. This is acceptable.
7
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: AFW JPM Number: 019 Task
Title:
Locally Restore AFW Flow (Motor Driy.gn Pumos and Valves)
Dencie Critical Steps with an *X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade STEP 4 X Performance Step: Check *A" MD AFW Pump DWST Supply isolation valve, 3FWA*V2, OPEN.
GRADE Standards: Unlocks the locking device on valve 3FWA*V2 and removes the locking device.
- Cue: ' The lock is unlocked and the locking device is removed. -
GRADE Standards: Rotates the handwheelin the clockwise direction to confirm the valve is open.
. Cue: The valve handwheel does not rotate in the clockwise direction GRADE X Standards: Rotates valve handwheelin the counterclockwise direction to OPEN the valve. S Cuel Valv6 handwheel rotates. Eventually some resistance is met and valve a t handwheel comes to a hard stop. The
' valve stem'is'in the raised position -
GRADE Standards: Rotates the handwheel 1/4 turn in the clockwise direction.
- Cue:" ^ The valve handwheel has been rotatert 1/4 turn in the clockwise -
direction.1 GRADE Standards: Installs the locking device and locke 8
PERFORMANCE INFORMATION Facility: Millrone Unit 3 System: .AFW-JPM Number: 019 Task
Title:
Loral!y_ Restore AFW Flow (Motor Driven Pumos and Valves)
Denoto Critical Steps with an *X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade the lock.
Cue: The locking device is installed and locked.
Comment: If the examinee had not previously contacted the control room concerning the valve being out of position, he may do so now (acknowlqdge the report if done) or wait until the end when task completion is reported.
Cue: - When the examinee is in a position to 7 observe the stem of Valve 3FWA*V4,
- inform him that the valve sten)is
-down.
Commen;: The examinee may question what to do with the out of position valve (may be concerned about a security event).
If this is the case, provide him with the cue to continue with the lineup, based on the cue concerning the stem position, the examinee may not conform the valves position as open and immediately open the velve. This is acceptable.
STEP 5 X Performance Step: Check "A" MD AFW Pump Discharge
' Isolation valve, 3FWA*V4, OPEN.
GRADE X Standards: Unlocks the locking device on valve 3FWA*V4 and removes the locking device.
9
PERFORMANCE INFORMATION Facility: Millstone Unit.3 System: AFW JPM Number: . 019 Task
Title:
Locally Restere ArW Flow (Motor Driven Pumos and Valves)
Denote Critical Steps with an T
- NOTE
- Critical Steps must be completed correctly to achlove a satisfactory grade l
! Cue: The lock la ' unlocked and the locking i
device is removed.
GRADE Standards: Rotates the handwbeelin the clockwise direct:on to confirm the valve is open.
l Cue:~ . The valve handwheel does not rotate
~ in the clockwise direction -
GRADE X Standards: Rotates valve handwheelin the
' counterclockwise direction to OPEN the valve.
Cue: ~ The valve handwheel rotates in the counterclockwise direction. Eventually
,some resistance is met and the valve handwheel comes to a hard stop. The.-
valve stem is.in the raised position.
GRADE Standards: Rotates the handwheel 1/4 turn in the clockwise direction.
? Cue: Valve has been rotated 1/4 turn in the clockwise direction.
GRADE -
Standards: Installs the locking device and locks the lock.
- Cue:'. The locking device is instatied and locked.
1 Comment: If the examinee had not previously contacted the control room concerning 10
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: AFW JPM Number: 019 ,,.
Task
Title:
Locally Rostore AFW Flow (Motor Driven Pumos and Valves)
Denote Critical Steps with an *X"
- NOTE
- Critical Steps must be completed correctly to schieve a satisfactory grade the valve being out of position, he may do so now (acknowledge the report if done) or wait until the end when task completion is reported.
STEP 6 Performance Step: Check "A" MD AFW Pump to SG D
~
isolat'on Valve,3FWNV10, OPEN.
GRADE Standards: Unlocks the locking device on valve 3FWA*V10 and removes the locking device. '
Cuei The lock is unlocked and the locking j device is removed,-
GRADE Standards: Rotates the handwheelin the clockwise direction to confirrn the valve is open.
Cue: The valve handwheel rotates in the -
clockwise direction, GRADE Standards: Rotates valve handwheelin the counterclockwise direction to fully OPEN the valve.
Cue: Valve handwheel rotates in the counterclockwise direction, eventually some resistance is met and the valve GRADE Standards: Rotates the handwheel 1/4 turn in the clockwise direction.
- Cue: - Valve has bee'n rotated 1/4 turn in the clockwise direction.
11 b
l PERFORMANCE INFORMAT:ON Facility: Millstone Unt3 System: . AFW._
JPM Number: 019
{
Task
Title:
Locally Restore AFW Flow (Motor Driven Pumos and Valves)
I Denus Critical Steps with an "X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade i
GRADE Standards: Installs the locking device and locks the lock.
' Cue:~- The locking device is installed and locked.
STEP 7 ' Performance Step: Check 'A" MD AFW Pump to SG A lsolation valve,3FWA*VS, OPEN.
GRADE Standards: Unlocks the locking device on valve 3FWA*VS and removes the locking device.
icue: The lock is~ unlocked and the locking -
l device is removed.
GRADE Standards: Rotates the handwheelin the clockwise direction to confirm the
.. valve is open.
- Cue
- - The vaWe handwheel rotates in the
- clockwi:e direction, GRADE Standards: Rotates valve handwheelin the counterclockwise direction to fully OPEN the valve.
t Cue: ' Valve handwheel rotates in the l
- counterclockwise direction, eventually
- some resistance is met and the valve icomec to a hard stop, GRADE Standards: Rotates the handwheel 1/4 turn in the clockwise direction.
12
, _ - - _ _ . ~ __
_ _ . . _ _ _ . _ _ _ . _ _ _ . _ . _ ~ . . . _ _ _ _ _ _ - _ _ _ _ _ _ _ _ . _ _ _ . _ _ _ -
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: AFW JPM Number: 019 .
Task
Title:
Locally Restore AFW Flow (Motor _ Driven Pumos and Valves)
Denote Critical Steps with an T
- NOTE
- Critical Steps must be completed correctly to achieve a satir. factory grade Cue:' ~ Valve has been rotated 1/4 turn in the
. clockwbe direction, GRADE Standards: Installs the locking device and locks the lock.
Cue: The locking' device is installed and locked,?
Comment: Location for JPM steps 811 is ESF Bldg. D, MD AFW Pump Room,24' STEP 8 Performance Step: Check "B" MD AFW Pump DWST Supply Isolation valve,3FWA*V16, OPEN.
GRADE Standards: Unlocks the locking device on valve 3FWA*V16 and removes the locking device.
- Cue: The lock is unlocked and the locking device is removed.
GRADE Standards: Rotates the handwheelin the clockwise direction to confirm the valve is open.
Cue: ' iThe valve handwheel rotates in the clockwise direction.
GRADE Standards: Rotates valve handwheelin the counterclockwise direction to fully OPEN the valve.
Cue:' Valve handwheel rotates in the 13
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: -AFW.
JPM Number: 019 Task
Title:
Locally Restore AFW Flow (Motor Driven Pumos and Valves)
Denote Critical Steps with an "X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade counterclockwise direction, eventually-some resistance is met and the valve
, , comes to a hard stop, GRADE Standards: Rotates the handwheel 1/4 turn in the clockwise direction, cCue:- Valve has been rotated 1/4 turn in the
! clockwise direction.
GRADE Standards: Installs the locking device and locks the loci LCue: The locking device is installed and locked.
STEP , 9 Performance Step: Check *B" MD AFW Pump Discharge Isolation valve 3FWA*V18 OPEN, GRADE Standards: Unlocks the locking device on valve 3FWA*V18 and removes the locking device.
- Cue
- . The lock is unlocked and the locking device is removed, GRADE Standards: Rotates the handwheelin the clockwise direction to confirm the valvo is open, (Cue:: . The valve handwheel rotates in the clockwise direction,.
14
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: AFW_
JPM Number: 019 Task
Title:
Locally Restore AFW Flow (Motor Driven Pumos aniValves)
Denote Critical Steps with an *X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade GRADE Standards: Rotates valve handwheelin the counterclockwise direction to fully OPEN the valve.
l
- Cuet Valve handwheel rotates in the counterclockwise direction, eventually some resistance is met and the valve comes to a hard stop.
GRADE Standards: Rotates the handwheel 1/4 turn in the clockwise direction.
Cue: Valve has been rotated 1/4 turn in the clockwise direction.
GRADE Standards: Installs the locking device and locks the lock.
' Cue: The locking device is installed and locked. '
STEP 10 Performance Step: Check "B" MD AFW Pump to SG C l Isolation valve,3FWA*V24, OPEN.
GRADE Standards: Unlocks the locking device on valve 3FWA*V24 and removes the locking device.
~
" Cue: The lock is unlocked and the locking.
. device is removed.
GRADE Standards: Rotates the handwheelin the clockwise direction to confirm the valve is open.
15
____ J
PERFORMANCE INFORMATION Facility. Millstone Unit 3 'ystem: AFW_
JPM Number: 019 Task
Title:
Locally Restore AFW Flow (Motor Driven Pumos and Valves)
Denote Critical Steps with an "X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade
!. Cue: The valve handwheel rotates in the clockwise direction.
GRADE Standards: Rotates valve handwheelin the counterclockwise direction to fully OPEN the valve.
Cue: Valve handwheel rotates in the' counterclockwise direction, eventually some resistance is met and the valve comes to.a hard stop.
GRADE Standards: Rotates the handwheel 1/4 turn in the
, clockwise direction.
- Cue
- ~ Valve has been rotated 1/4 turn in the clockwise direction.
GRADE Standards: Installs the locking device and locks the lock.
- Cue: lThe locking device is installed'and
. locked.3 STEP 11 Performance Step: Check "B" MD AFW Pump to SG B Isolation valve 3FWA*V19 OPEN.
GRADE Standards: Unlocks the locking device on valve 3FWA*V19 and removes the locking device.
' Cuei The lock is unlocked and the locking
- device is removed.'
16
[,, Facility:_ ____ PERFORMANCE INFORMATION Millstone Unit 3 System: - AFW
!k 4
JPM Number: 019 Task
Title:
Locally _Rasbre AFW Flow (Motor Driven Pumos artd Valves)
Cenote Critical Steps with an "X"
' NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade GRADE Standards: Rctates the handwheelin the j clockwise direction to confirm the valve is open.
- Cue: The valve handwheel rbtates in the clockwise direction.
GRADE Standards: Rotates valve handwheelin the counterclockwise direction to fully OPEN the valve, Cue:- Valve handwheel rotates in the counterclockwise direction, eventually some resistance is met and the valve comes to a hard stop, GRADE Standards: Rotates the handwheel 1/4 turn in the
'^~
clockwise direction.
Cue: Valve has been rotated 1/4 turn in the clockwise direction, GRADE Standards: Installs the locking device and locks the lock.
' Cue:- 'The locking device is installed and locked.
)
17
PERFORMANCE INFORMAT!ON Facility: Milictone Unit 3 . Sistem: AFW JPM Number: 019 Task
Title:
Locally Restore AFW Flow (Motor Driven Pu.mos and Valvej.)
Denote Critical Steps with an "X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade STEP 12 Performance Step: Notify the control room that the checks of the AFW system IAW page 1 of Attachment A to EOP 35 FR-H.1 have been completed, GRADE Standards: Examinee reports to US that the AFW '
system lineup has been checked using page 1 of Attachment A to EOP 35 FR-H.1.
Teeminating Cue: The evaluation for this JPM is concluded, dtur Time:
18
' VERIFICATION OF COMPLETION 3 J . Job Performance Measure Number: .019 Revision: __5
- Date Performed:
J 4 .
Examinee:
j Evaluator::
i l Validated Time (min): 10 Actual time to Complete (min):
4 Result of JPM: (Denote by an S for satisfactory or a U for unsatisfactory) p Result of oral questionsi Number of Questions:
Number of Correct Responses: _
Score ' -%
J V
R W
t 4
E 19
EXAMINEE HANDOUT INITIAL CONDITIONS AND INITIATING CUES JPM Tracking Number: 019 Initial Conditions: A loss cf Secondary Heat Sink event is in progress and the control room team is carrying out the actions of EOP 35 FR-H.1. AFW flow could not be established from the control room.
initiating Cues: The US directs you to locally restore the AFW flow using the A and B MDAFW pumps LAW page i of 4 to Attachment A to EOP 35 FR-H.1. You are also to verify the position of any TDAFW valves on page 1. A second PEO is checking the lineup for the TDAFW pump.
20
OllIG JOB PERFORMANCE MEASURE WORKSHEET I, JPM
Title:
ESTABLISH FEED AND BLEED ON CHARGING PUMP COOLING (EOP 3501)
ID Number: JPM-137 Revision: 1
- 11. Initiated:
A. Oxfurth 3/19/97 Developer Date Ill. Reviewed:
k TechnicaTReviewer 4'($ '"Il Date
/
l' . . ,
M1,1 sh,/g
'Tinstruc'tidri31.Revieh Date '
a pp77._ .
l m
M /7 97 pe ions Manager (bate
( (
h Nuclear Training Supervisor 4A7A7 Date 1
i JOB PERFORMANCE MEASURE WORKSHEET Facility: . Millstone Unit 3 Examines:
[ JPM Tracking Number: 13Z Validation Time: ._15__ minutes L .. . .
Task
Title:
ESTABLISH FEED AND BLEED ON CHARGING PUMP COOLING (EOP 3501)
- Time CriticalTask
- (-)YES ( X ) NO -
Task Number: 163-001-04-01 K/A Number: 076-000 A-2.01
{
K/A Rating: 3.5 / 3.7 Acolicable Methods of Testino-J
, Simulate Performance X Actual Performance
{
Classroom - Simulator Plant X Task Standards: -Satisfactorily establish feed and bleed on Charging Pump Cooling using EOP 3501, Recuired Materials: None.
General
References:
EOP 3501, Rev. 9 READ TO THE EXAMINEE
-I will explain the initial conditions, which step (s) to simulate or discuss, and provide initiating cues.. When you complete the task successfully, the objectives for this JPM will be satisfied.
You may use any approved reference materials normally available in the Control Room, including logs. Make all written reports, oral reports and log entries as if the evolution was
- a. actually being performed.
Initial Conditions: The plant is in Mode 5. A loss of all AC power has occurred. The control room team has progrescad through EOP 3501. Attempts are being made
.to establis' injection flow using the charging pumps Attempts to restore
- cooling to CCE have failed.
J i
Initiating Cues:
The US has directed you to locally initiatsfeed and bleed for CCE using the guidance of EOP 3501 step 16b RNO. The "A" charging pump is
- available.
t
- 2
PERFORMANCE INFORMATION _
Facility: Millstone Unit 3 - System: E01 JPM Number: 137
- Task
Title:
ESTABLISH FEED AND BLEED ON CHARGING PUMP COOLING (EOP 3501)
Denote Critical Steps with an "X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade Start Time:
I Comments: For the first step of this JPM there may he several options that would i
result in success. Hoses are located in the OPS Departmen*, Locker on the -
north wall next to the RPCCW coolers.
This locker also contains " Chicago" fittings. Tl ere is a domestic water connection at 3DWS-V167 Iccated by the eyewash station near the thermal regeneration chiller. The examinee h
should clearly discuss the location of hoses and point out an acceptable
- connection to the fire or domestic water systems:
STEP 1 X Performance Step: Connect a temporary hose from fire or domestic water (or any available water source) to the appropriate valve, so '
that makeup can be added to the surge tank:
F For pump A 3CCE*V29 For pump B 3CCE*V30 GRADE X Standards: Locates a hose to use to the hookup.
Connects the hose to either the fire or domestic water connection and to valve 3CCE*V29 (A pump is the one available).
~
[CUeil*~ ""' ~ "" iThs'iiiise"is~'codfibsted to ins"two.i de dum . d connechons k 3
PERFORMANCE INFORMATION Facility:
Millstone Unit 3 System: E01
- JPM Number: 137 Task
Title:
ESTABLISH FEED AND BLEED ON CHARGING PUMP COOLING (EOP 3501)
Denote Critical Steps with an 'X" -
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade STEP 2 X Performance Step: Close both charging pump cooler isolation valves (3CCE*V10 and 3CCE*V22)
GRADE X Standards: Rotetes the handwheel for 3CCE*V10
. in the clockwise direction until the valve is fully closed.
Tchei-: ' ' TThe handsheel foY3CCE*V10 r6tafes:
- in the clockwise direction. Eventually,;
some resistance is met and the 4-
. j ha_ndwheel comes to a _hard stop..
GRADE X Standards: Rotates the handwheel for 3CCE*V22 in the clockwise direction until the valve is fully closed.
[Cbe: 1 EThe hahdwliest for 3CCE*V22' rotates t
- lri the clockwise direction. Eventually, je g
~
(some resistance is met'and the' m ;s , thandwheel come(tola hard stop. ,
Comment: There is a pipe cap installed on the end of the drain pipe. As a good practice, the examinee should explain that he is removing the cap. If the examinee fails to remove the pipe cap, the cue following the next step must be changed as indicated.
4
PERFORMANCE INFORMATION
't Facility: Millstone Unit 3 System: EO1
, JPM Number: 137 h
Task
Title:
ESTABLISH FEED AND BLEED ON CHARGING PUMP COOLING (EOP 3501)
Denote Critical Steps with an "X"
' NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade STEP 3 X Performance Step: Open the appropriate charging pump oil cooler outlet drain valve:
i For pump A 3CCE*V977 For pump B 3CCE*V975 For pump C 3CCE*V976 GRADE X Standards: Rotates the handwheel for
, 3CCE*V977 in the counter-clockwise direction until the valve is fully open, fCuei; :lThe Vsive starts to rotateln ths -
. counter-clea.kwise direction and water-islseen_ flowing from the drain pipe (if -
thel pipe cap was not removed, inform
~- the examinee that no flow is ' .
observed).- Eventually, _somei c resistance is met and the valve'
~
- i. am 2 :.- ;;hs ndwheel comes to a haidlstop?
GRADE Standards: Rotates the handwheel 1/4 turn in the clockwise (closed) direction.
[Cuef> " ~" "TThl0 vane ~hs5dwh'eelKss besn
': rotated 1/4 turn in the clockwise.
- direction l 5
[ -,
t PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: EO1 JPM Number: 137 Task
Title:
ESTABLISH FEED AND BLEED ON CHARGING PUMP COOLING (EOP 3501)
Denote Critical Steps with an "X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade Comments: For the next JPM step, it may be necessary to prompt the examinee to simulate adding water to the surge tank. He should check the level as indicated on #CCS-LIS-22A. Provide the following cue:
[CueC " , LThe surge tanklevslis?40%;
STEP 4 X Performance Step: Add makeup using the temporary hose to maintain surge tank level.
s GRADE X Standards: Opens the domestic water or fire header valve to the temporary hose and opens 3CCE*V29.
TCueK *
>TheyslGirotstss in the countsr ,
, Nclo' ckwise' direction; Evehtilallylsome y T. v ' a_lvei
. ; , uresistance is ' met and the
., , ihandwhee.lico,mes toja hard stopt
' C E" '" "'MMWi5insMt'WillMsi
. : some tims'tafill'the surgelank and!
i ., , jij provide the terminatind cues Terminating Cue: The evaluation for this JPM is concluded.
Stop Time:
6
_ . . . . . . _ . . _ . _ _ _ _ . . . . ~ _ . - _ _ . . _ . _ . _ _ . _ _ .. _ . .
1
. VERIFICATION OF COMPLETION Job Performance Measure Number: 137 Revision: 1 i
Date Performed:
! Examinee:
1 l
- Evaluator:
4-l t
Validated Time (min): 15 Actual time to Complete (min):
i Result of JPM: (Denote by an S for satisfactory or a U for unsatisfactory)
- Result of oral questions
- Number of Questions:
Number of Correct Responses:
2 4
Score %
L L
4 4
7
_ - ~ - . - . . - . . - . . . - - ._ -. - . _ - . . -.
EXAMINEE HANDOUT INITIAL CONDITIONS AND INITIATING CUES JFM Tracking Number:
137 4
4 1
initial Conditions: The plant is in Mode 5. A loss of all AC power has occurred. The control room team has progressed 1
through EOP 3501. Attempts are being made to establisia injection flow using the charging pumps.
! Attempts to restore cooling to CCE have failed.
l Initiating Cues: The US has directed you to locally initiate feed and bleed foi CCE using the guidance of EOP 3501 step 16.b.1 RNO. The "A" charging pump is available.
b s
8
O,elG ,
' JOB PERFORMANCE MEASURE WORKSHEET #
- 1. JPM
Title:
Si TERMINATION ID Number: JPM-NEW 1 Revision: 0 ll. Initiatedi Bav Lueneburg 5/12/97 Developer Date Ill. Reviewed:
Technical Reviewer- Date Instructional Reviewer Date IV. Approved:
Operations Manager- Date Nuclear Training Supervisor Date -
1
JOB PERFORMANCE MEASURE WORKSHEET Facility: Millstone Unit 3 -
Examinee:
JPM Tracking Number: New 1 -
Validation Time: minutes V
Task
Title:
Si TERMINATION Time Critical Task: ( )YES ( X ) NO Task Number: 000*018*05*01 K/A Number: E02 M'EST) - EK1.2 K/A Rating: 3.4/3.9
'Aooiicable Methods of Testing:
Simulate Performance Actual Performance - X
, Classroom Simulator X Plant ._
l Task Standards: Satisfactorily complete the first seven(7) steps of ES-1.1, Si i
Termination.
1 Reauired Materials: None General References; _ ES 1.1, Rev.12 READ TO THE EXAMINEE I will explain the initial conditions, which step (s) to simulate or discuss, and provide initiating ,
cues. When you complete the task successfully, the objectives for this JPM will be satisfied.
You may use any approved reference materials normally available in the Control Room, including logs Make all written reports, oral reports and log entries as if the evolution was actually being performed.
Initial Conditions: An inadvertent Si occurred due to an error on the part of an l&C technician performing SSPS testing. The crew has completed the actions in E-0 and is ready to transition to' ES-1.1.
Initiating Cues: The Us has directed you to complete steps 1 through 7- of ES-1.1, 2
l
JOB PERFORMANCE MEASURE WORKSHEET Simulator Requirements: 1, Reset to IC #14 2, Place tge simulator in "Run", Place the master silence switch in " silence".
- 3. Insert malfunctions:
- RPOSA, SITrain A Actuation RP05B, SITrain B Actuation
- 4. Red flag pumps that started on the Si,
- 5. Remove malfunctions RPOSA and RP05B.
L 6. Acknowledge / Clear alarms, return the master silence switch to " normal", and place the simulator in " freeze",
- 7. Place the simulator in "Run" after the examinee has read the initial conditions and initiating cues.
Approximate simulator setup time is 7 minutes.
6 3
___n
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: S11 JPM Number: New-1 Task
Title:
Si TERMINATION i
Denote Critical Steps with an "X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade 3
Start Time:
4 i STEP- 1 X Performance Step: RESET ESF Actuation signals if Required.
- Si e CDA
$ e LOP e CIA J
e CIB GRADE X Standards: Based on the initial conditions, realizes that Si and CIA need to be reset. Depresses the Si reset push buttons on MB2 and observes that the Si reset annunciator on MB4 comes in
,. and the auto EDG start annunciator on MB8 and the Si actuated.
annunciator on MB4 clear.
Comments: The examinee should acknowledge / clear annunciators as necessary. This is not required to complete the critical nature of this step.
GRADE X Standards: Depresses the CIA reset push buttons on MB2 and observes that the CIA actuation annunciator on MB2 clears.
4 J
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: S11 JPM Number: New 1 Task
Title:
SI TERMINAT!ON Denote Critical Steps with an *X*
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade Comments: The examinee should acknowledge / clear annunciators as necessary. This is not required to complete the critical nature of this step.
Comments: The examinee may elect to also depress the reset push buttons for CDA, LOP, and CIB. While not required, this action is acceptable from the standpoint of successfully completing the JPM, However, it may warrant follow-up questions at the completion of the JPM.
STEP 2 Performance Step: Restore MCC 32-3T
- b. Locally Verify inverter 6 DC input ammeter indicating zero amps.
GRADE Standards: Either directly contacts an PEO or requests that the US contact an PEO-to close the feeder breaker on 32T to MCC 32-3T and check the inverter 6 DC input amps.
~
[Cuei! jRole plsy as the PEOfor"US andi
" acknowledge the~ request:--it is not
- necessaryforthe. performance of this-
'JPM to use the remote function; L(EDR18) to reset 32-3T ?If ' tne -
examinee hesitates while waiting for-
- the co.mpletion of.this step role play as 5
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: S11 JPM Number: New-1 Task
Title:
SI TERMINATION Denote Critical Steps with an "X"
' NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade
^ ~
tthe' US and inform hirn ts consider this -
- p step in progress and to move to theJ next step.-
STEP 3 X Performance Step: Establish Instrument Air to Ctmt
- a. Check instrument air compressors
- AT LEAST ONE RUNNING
- b. OPEN instrument air Ctmt isolation valves.
GRADE Standards: Observes that the indicating lights for the "A" instrument air compressor are green OFF, red ON. The compressor is running.
GRADE X Standards: Notices the indicating lights for PV15 and MOV72 are green ON, red OFF.
Depresses the "open" push buttons for PV15 and MOV72 and observes the indicating lights shift to green OFF, red ON.
Comment: In the performance of the next JPM step, the examinee may question which charging pump to stop. If this occurs, provide the following cue:
Cue: TSt6pithe "B" charging pu'mp.
STEP 4 X Performance Step: STOP All But One Charging Pump and Place in AUTO.
6
PERFORMANCE INFORMATION '
Facility: Millstone Unit 3 System: S11 JPM Number: nee-1 Task
Title:
SI TERMINATION __
Denote Critical Steps with an "X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade GRADE X - Standards: Rotates the control switch for the "B" (or "A") charging pump to the stop position and allows the switch to spring return back to the " auto" position, Observes the indicating lights shift to green ON, red OFF, amperage goes to zero and the flag changes to green.
~
STEP 5 Performance Step: Check RCS Pressure - STABLE OR INCREASING GRADE Standards: checks any of the following indications:
MB4: 3RCS-Pl455A 3RCS-Pl456A' s
. 3RCS-Pl458 3RCS-Pl405 a 3RCS-Pl47.
3RCS-Pl403 3RCS-Pl58 and recorder: 3RCS-PR455.
Observes that pressure is slo.vly increasing.
STEP 6 X Performance Step: Establish Normal cfiarging Flow Path.
Fully Open charging line flow control valve.
GRADE X- Standards: Depresses the UP (A) arrow push 7
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: S11 JPM Number: New-1 Task
Title:
SI TERMINATION 4
Denote Critical Steps with an "X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade button on the controller for FV121 and observes the auto light goes out and the manuallight comes on. Continues to push the push button until the button back lights red indicating the valve is full open. Releases the push button.
Comment: Due to the isolation of air to containment it is poss'ble that both of the loop isolation valves are open. If the examinee questions which valve to close provide the following cue:
Cue: ,' lClose 3CHS?AV8.147 i STEP .7 X Performance Step: Verify charging header loop isolation valves (3CHS*AV8146 or 3CHS*AV8147)- ONE OPEN GRADE X Standards: Depresses the "close" push button for 3 CHS*AV8147 (or 3CHS*AV8146) and observes the indicating lights shift to green ON, red OFF. Then releases the push button.
STEP 8- X Performance Step: OPEN charging header isolation valves (3CHS*MV8106 and 3CHS*MV8105)
GRADE X Standards: Depresses the "open" push button for 3CHS*MV8106 and observes the indicating lights shift to green OFF, red ON.
8
l'ERFORMANCE INFORMATION Facility: Millstone Unit 3 System: S11 JPM Number; New-1 Task
Title:
SI TERMINATION Denett, Critical Steps with an "X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade -
GRADE X Standards: Depresses the "open" push button for 3CHS*MV8105 and observes the indicating lights shift to green CFF, red ON.
STEP 9 X Performance Step: CLOSE the charging pump miniflow isolations to the RWST (3CHS*MV8511 A and 3CHS*MV8511B)
GRADE X Standards: Depresses the "close" push button for 3CHS*MV8511A and observes the indicating lights shift to green ON, red OFF.
GRADE X Standards: Depresses the "close" push button for 3CHS*MV8511B and observes the indicating lights shift to green ON, red OFF.
STEP 10 X Performance Step: CLOSE both charging pump cold leg
~
injection valves.
GRADE X Standards: Depresses the "close" push button for 3SlH*MV8801A and observes the indicating lights shift to green ON, red OFF.
GRADE X Standards: Depresses the "close" push button for 3SlH*MV8801B and observes the indicating lights shift to green ON, red OFF.
9
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: S11 JPM Number: New-1 Task
Title:
St TERMINATION Denote Critical Steps with an "X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade STEP 11 X Performance Step: Align Charging Pump Recirculation,
- a. OPEN the charging pump recirculation isolation valves 1
3CHS*MV8111 A 3CHS*MV8111B 3CHS*MV8111C 3CHS*MV8110 GRADE X Standards: Depresses the "open" push button for 3CHS*MV8111A and observes the indicating lights shift to green OFF, red ON, GRADE X Standards: Depresses the "open" push button for 3CHS*MV8111B and observes the indicating lights shift to green OFF, red ON.
GRADE X Standards: Depresses the "open" push button for 3CHS*MV8111C and observes the indicating lights shift to green OFF, red ON.
GRADE X Standards:- Depresses the "open" push button for 3CHS*MV8110 and observes the indicating lights shift to green OFF, red ON.
10
a PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: S11 JPM Number: New-1 Task
Title:
Si TERMINATION Denote Critical Steps with an "X"-
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade STEP 12 Performance Step: Notify the US that the fiist 7 steps of ES-1,1 have been completed.
GRADE Standards: Reports to the US that the first_7 steps of ES-1,1 have been completed. .
Terminating Cue: The evaluation for this JPM is concluded.
Stop Time: '
+
11
-VERIFICATION'OF COMPLETION Job Performance Measure Number:- NEW Revision: 0 Date Performed:
Examinee:
- Evaluator:
Validated Time (min.):. Actual time to Complete (min.):
Result of JPM: (Denote by an S for satisfactory or a U for unsatisfactory)
Result of oral questions: Number of Questions:
Number of Correct Responses:
Score %
12-
EXAMINEE HANDOUT INITIAL CONDITIONS AND INITIATING CUES JPM Tracking Number: NmE-1.
Initial Conditions: An inadvertent Sl occurred due to an error on the part of an l&C technician performing SSPS testing. The crew has completed the actions in E-0 and is ready to transition to ES 1.1.
Initiating Cues: The Us has directed you to complete steps 1 through 7 of ES-1.1.
13
- JOB PERFORMANCE MEASURE WORKSHEET I. JPM
Title:
START THE TRAIN "A" CONTAINMENT PURGE SYSTEM (FILTERED) .
ID Number: NEW-5 Revision: 0 l
ll. IM%ted:
- r l Ray Lueneburg 4fq4fg7 Developer Date IllcReviewed:
i l Tecl i nical Reviewer Date f
Instructional Reviewer Date i
IV. Approved:
Operations Manager Date i.
Nuclear Yraining Supervisor Date i
1
JOB PERFORMANCE MEASURE WORKSHEET Facility: Millstone Unit 3 Examinee:
JPM Tracking Number: NEW - 5 Validation Time: minutes Task
Title:
START THE TRAIN "A" CONTAINMENT PURGE SYSTEM (FILTERED)
Time Critical Task: ( ) YES- ( X ) NO Task Number: 022'006*01*01 KIA Number: 029-A2.03 K/A Rating: 2.7/3.1 Apolicable Methods of Testing:
Simulate Performance Actual Performance X Classroom Simulator X Plant Task Standards: Satisfactorily place the Train "A" containment purge system (filtered)in service using OP 3313F Reauired Materials: Keys for 3HVU*CTV32A and 3HVU*CTV32B (simulator keys #31.
and 31).
General
References:
OP 3313F, Rev. 8 READ TO THE EXAMINEE l will explain the initial conditions, which step (s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objectives for this JPM will be satisfied.
You may use any approved reference materials normally available in the Control Room, including logs. Make all written reports, oral reports and log entries as if the evolution was actually being performed.
Initial Conditions: A fuel handling accident occurred. The control room team carried out the actions in EOP 3502, Fuel handling Accident. Chemistry has just informed the US that it is okay to purge the containment via the Auxiliary Building Filtration System. Manual area filtration of the Auxiliary Building general area lower levels is in service.
Initiatina Cues: The US has directed you to start the Train "A" Containment Purge System (Filtered) using OP 3313F, Section 4.2 starting with step 4.2.3.
2
JOB PERFORMANCE MEASURE WORKSHEET Simulator Requirements: 1. Reset to IC #1 (Only IC close to a refueling situation.) '
, 2. Place the simulator in "Run".
- 3. At VP1 perform the following:
Stop 3HVR-HVU2B (VP1 center panel- Aux Bldg)
Stop 3HVR-FN7 (VP1 center panel- Aux Bldg)
Press / Hold
- Filter" push button for 3HVR*AOD40A/42A until the lights shift.
Press / Hold " Filter" push button for 3HVR*AOD408/42B until the lights shift.
Start 3HVR FN6A (VP1, Train A, Aux Bldg)
- 4. Place the simulator in " freeze".
l
- 5. Place the simulator in "Run" after the examinee has read
- the initial conditions and initiating cues.
Approximate simulator setup time is 5 minutes.
3
PERFORMANCE INFORMATION Facility: Millstene Unit 3 System: CMS JPM Number: NEW-5 Task
Title:
START THE TRAIN *A" CONTAINMENT PURGE SYSTEM (FILTERED) l Denote Critical Steps with an *X" l
' NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade Statt Time:
STEP 1 X Performance Step: To open 3HVR*AOD29A and 3HVR*AOD298, filter purge outlet dampers in filter MODE, PRESS
- FILTER" push buttons, (VP1) l GRAO: X Standards: On the center section of VP1,
~-
depresses the
- filter" push button for 3HVR*AOD29A and observes the indicating lights shift to green, OFF red, ON. Then releases the puch button, GRADE X Standards: On the center section of VP1, depresses the
- filter" push button for 3HVR*AOD29B and observes the indicating lights shift to green, OFF red, ON Then releases the push button.
STEP 2 Performance Step: OPEN instrument air isolation valves for 3HVU*CTV32A and 3HVU*CTV328, (local).
GRADE Standards: Either directly contacts an PEO or requests that the US contact an PEO
'to open the air isolation valves for 3HVU*CTV32A and 328.
~
~
[ Cue:_ Role' play as the PEO_or US and
- . ' acknowledge the~ order. ; Report that -
n the air isolation valves for 4
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: CVE JPM Number: NEW-5 Task
Title:
START THE TRAIN *A* CONTAINMENT PUdGEEYSTEM (FILTERED)
Denote Critical Steps with an "X
' NOTE
- Critical Steps must be completed correctly to achieve e satisfactory grade r 3HVU'CTV32A and 32B _are open,
! STEP 3 X Performance Step: PLACE key switch for
- PURGE WS" 3HVU*CTV32A and 3HVU*CTV32B, containment purge air isolation valves, to *OPEN" GRADE X Standards: Inserts the key into the control switch for 3HVU*CTV32A/32B and rotates the switch to the "open* position.
Observes the Indicating lights shift to green Off, red ON.
STEP 4 Performance Step: WHEN valves are open, return switch to " Auto" GRADE Standards: After observing the indicating lights shift to red ON, rotates the control switch back to the " auto
- position.
STEP 5 X Performance Step: PLACE key switch for *Pl1RGE WS" 3HVU*CTV33A and 3HVU*CTV33B, containment purge air isolation valves, to *OPEN'.
GRADE X Standards: Inserts the key into the control switch for 3HVU*CTV33A/33B and rotates the switch to the *open* position.
Observes the indicating lights shift to green Off, red ON, 5
PERFORMANCE INFORMATION Facility; Millstone Unit 3 System: C.VE JPM Number: NEW-5 Task
Title:
START THE TRAIN *A* CONTAINMENT PURGE SYSTEM (FILTERED) l Denote Critical Steps with an *X*
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade STEP 6 Performance Step: WHEN valves are open, return switch to
- Auto" GRADE Standards: After observing the indicating lights shift to red ON, rotates the control switch back to the " auto" position.
l l
Comment: If the examinee forgot that the initiating cue want the "A* train, provide an additional cue to ensure that the "A* train is used.
STEP 7 X Performance Step: lE It is desired to start containment purge Train A, PERFORM the following:
OPEN 3HVR*AOD55A and 3HVR*AOD174A, air handling unit A intet dampers,(VP1)
GRADE X Standards: At the center section of VP1, depresses the "open* pushbutton for 3HVR*AOD55A and observes the indicating lights shift to green OFF, red ON GRADE X Standards: At the center section of VP1, depresses the "open* pushbutton for 3HVR*AOD174A and observes the indicating lights shift to green OFF, red ON 6
PERFORMANCE INFORMATION Facility: Millstone UnlUn .
System: C.V.S JPM Number: NEW-5 Task
Title:
START THE TRAIN *A" CONTAINMENT PURGE SYSTEM (FILTERED)
Denote Critical Steps with an *X" l
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade STEP 8 X Performance Step: START 3HVR FN4A, purge exhaust fan A,(VP1)
GRADE X Standards:
~ Rotates the control switch for 3HVR-FN4A to the
- start" position and observes the indicating lights shift to green OFF, red ON.
STEP 9 X Performance Step: START 3HVR HVU1A, purge supply air handling unit A, (VP1)
GRADE X Standards:
' Rotates the control switch for 3HVR-HVU1A to the " start" position and observes the indicating lights shift to green OFF, red ON.
STEP 10 X Performance Step: Notify the US that Train "A" containment purge system (filtered) has been started.
GRADE X -Standards: Reports to the US that the 'A" train of the containment purge system (filtered) has been started IAW OP 3313F section 4.2 Terminating Cue: The evaluation for this JPM is concluded.
Stop Time:
7
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: CVS l JPM Number. NEW - 5 l
Task
Title:
START THE TRAIN *A* CONTAINMENT PURGE SYSTEM (FILTERED)
Denote Critical Steps with an *X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade 8
VERIFICATION OF COMPLETION Job Performance Measure Number: NEW.5 Revision: 0 Date Performed:
Examinee:-
l Evalustor: .s,,,..
Validated Time (min.): Actual time to Complete (min.):
Result of JPM: (Denote by an S for satisfactory or a U for unsatisfactory)
Result of oral questions: Number of Questions:
Number of Correct Responses:
Score %
9
EXAMINEE HANDOUT INITIAL CONDITIONS AND INITIATING CUES JPM Tracking Number: NEW-5 Initial Conditions: A fuel handling accident occurred. The control room team carried out the actions In EOP 3502, Fuel handling Accl.%nt. Chemistry has just informed the US that it is okay t > purge the containment via the Auxiliary Building Filtration System. Manual area filtration of the Auxillary Building general area lower levels is in service.
i hil11ating Cues: The US has directed you to start the Train "A" Containment Purge System (Filtered) using OP 3313F, Section 4.2 starting with step 4.2.3.
10
Cit \G.
JOB PERFORMANCE MEASURE WORKSHEET 1 .
I. JPM Title; MANUALLY INITIATE CTMT SPRAY l
lD Number: _ JPM.055 Revision: fi ll, Initiated:
, A. Oxfurth 2/03/97 Developer Date til. Reviewed:
2.- I d "d Tect nical Reviewer Date
{ 2/t f,7y Instructional Revie Date IV. Approved:
1 7 ??-9 7 Cipefafions M r p Date
( ' em q ,
'f sa Nuclear Training Supervisor
%9 M Date 4
1
JOB PERFORMANCE MEASURE WORKSHEET Facility: Millstone Unit 3 Examinee:
JPM Tracking Number: DE Validation Time: B_ minutes Task
Title:
Manually Initiate CTMT Soray Time Critical Task: ( )YES (X)NO Task Number: 000*102'05'02 K/A Number: 026 000 A4.01 K/A Rating: 4.5/4.3 Aeolicable Methods of Testing:
Simulate Performance Actual Performance 2._._
_ Classroom Simulator 2 Plant Task Standards:
Satisfactorily complete a manualinitiation of containment spray using FR Z.1 Steps 13 Reaulted Materials: None General Referencer FR Z.1 Rev.8 READ TO THE EXAMINEE I will explain the initial conditions, which step (s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objectives for this JPM will be satisfied.
You may use any approved reference materials normally available in the Control Room, including logs. Make all written reports, oral reports and log entries as if the evolution was actually being performed.
Initial Conditions: A steam line break inside containment has occured. Based on the plant conditions a manual reactor trip and safety injection were initiated. The Control Room team is progressing through the EOPs. The transition to E 2, Faulted Steam Generator Isolation, has just been entered, in checking the Status Trees, the crew has observed an orange path for containment integrity based on containment pressure just exceeding 23 psia, initiating Cues:
The US has directed you to perform the first three (3) steps in FR Z.1.
The US has decided to leave the Master Silence Switch in the " silence" position.
2
JOB PERFORMANCE MEAC URE WORKSHEET Simulator Reautrements: 1. Reset to C l' 20,100% power
- 2. Insert malfunction RP11C, Failure of Quench Spray to Automatically Actuate.
- 3. Place the simulator in *RUN". Take the master silence switch to
- silence" and insert malfunction MS01 A, S/G *A" faulted inside containment, at 100% severity.
- 4. Allow the simulator to run for 12 minutes (adverse CTMT will be met due to CTMT temperature and the control room air bank isolation valves will be open). During this time, stop the *C" CAR fan and the kitchen exhaust fan, throttle AFW flow to 150 GPM per S/G and place both steam dump interlock switches to *off".
Containment HI 3 setpoint will be reached and no Quench Spray '
actuation will have occured.
- 5. Acknowledge / clear alarms and place the simulator in
- Freeze". Leave the master silence switch in " silence".
- 6. Place the simulator in "Run" after the examinee has received the initial conditions and initiating cues.
Approximate simulator setup time is 5 7 minutes.
I e
3 w wyt- w w wwyw,- ,--+r-w-,-av---y-
i 1
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: EZ1 JPM Number: - 055 Task
Title:
MANUALLY INITIATE CTMT SPRAY Denote Critical Steps with an T
' NOTE
- Critical Steps must be completed correctly to achleve a satisfactory grade 1
Start Time:
i STEP 1 Performance Step: Verify CIA (FSF Group 2 Status Columns 2 through 10)
GRADE Standards: Observes that the ESF Group 2 Jc ta'tus Lights in columns 2 through 10
{ aie ht.
4 STEP 2 Performance Step: Verify CIB. Check RPCCW C(mt supply and return header isolation valves CLOSED GRADE Standards: Observes that the indicating lights for valves 3CCP'MOV45A & B, MOV49A
& B and MOV48A & B are green ON, j red OFF. The valves are closed.
Comments: The examinee may check the ESF Group 4 Status Lights for these valves as either a backup or primary indication of verifing the valves' position.
STEP 3 Performance Step: Check RPCCW pumps - STOPPED GRADE Standards: Observes that RPCCW pumps 3CCP'P1A & P1B have no running amps indicated and the indicating lights are green ON, red OFF 4
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: EZ1 JPM Number: 055 i Task
Title:
MANUALLY INITIATE CTMT SPRAY Denote Critical Steps with an "X"
" NOTE' Critical Steps must be completed correctly to achieve a satisfactory grade STEP 4 X Performance Step: STOP all RCPs GRADE X Standards: Rotates the control switch for 3RCS-P1A to the "stop" position and observes the flag shifts to green, amp >
indication goes to zero and the indicating lights shift to green on, red OFF.
GRADE X Standards: Rotates the control switch for 3RCS-P1B to the "stop" position and observes the flag shifts to green, amp indication goes to zero and the Indicating lights shift to green on, red OFF.
GRADE X Standards: Rotates the contro; switch for 3RCS-P1C to the *stop" position and observes the flag shifts to green, amp indication goes to zero and the indicating lights shift to green on, red OFF.
GRADE X Standards: Rotates the control switch for 3RCS-P1D to the "stop" position and obsentes the flag shifts to green, amp indication goes to zero and the indicating lights shift to green on, red OFF.
Comments: If the examinee questions the status of procedure ECA-1.1 due to the caution in FR-Z.1, inform him that the cbntrol room team has not entered ECA-1.1 5
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: EZ1 JPM Number: 055 Task
Title:
MANUALLY INITIATE CTMT SPRAY Denote Critical Steps with an "X" i
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade 1
STEP 5 Performance Step: Verify Quench Spray System Operation. Check RWST level.
GREATER THAN 100,000 gal (annunciator RWST EMPTY OSS PP OFF on MB2A 5-2 not lit)
GRADE Standards: Observes that annunciator MB2A 5 2 is not lit STEP 6 Performance Step: Verify quench spray pumps -
RUNNING GRADE Standards: Observes that for 30SS*P3A and P3B there are no running amps indicated and the indicating lights are green ON, red OFF. The pumps are not running, STEP 7 X Performance Step: Shifts to the RNO column - START pumps GRADE X Standards: Rotates the control switch for 30SS*P3A to the
- start" position and observes the flag shifts to red, amperage is indicated and the indicating lights shift to green OFF, red ON, GRADE X Standards: Rotates the control switch for 30SS*P3B to the " start" position and observes the flag shifts to red, amps are indicated and the indicating lights shift to green OFF, red ON, 6
~
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: EZ1 JPM Number: 055 Task
Title:
MANUALLY INITIATE CTMT SPRAY Denote Critical Steps with an "X" 4
' NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade i
I STEP 8 Performance Step: Verify quench spray pump discharge valves (30SS'MOV34A and 4
30SS*MOV348) OPEN GRADE Standards: Observes that the indicating lights for 30SS'MOV34A and 30SS*MOV348 are green ON, red OFF. The valves are closed.
STEP 9 X Performance Step: Shifts to the RNO column - OPEN -
valves GRADE X Standards: Depresses the *OPEN/ AUTO" pushbutton for 30SS*MOV34A and observes the indicating lights shift to green OFF, red ON.
1 GRADE X Standards: Depresses the "OPEN/ AUTO" pushbutton for 30SS*MOV34B and observes the indicating lights shift to green OFF, red ON.
Comments: The examinee may check the ESF GP-4 Status Lights as a second method to verify the valves have gone open.
I 7
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: EZ1 {
JPM Number: 055 Task
Title:
MANUALLY INITIATE CTMT SPRAY Denote Critical Steps with an T '
' NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade ;
STEP 10 Performance Step: Check quench spray system FLOW EXISTS IN AT LEAST ONE TRAIN.
GRADE Standards: Checks meter indications,30SS-Fl32A and Fl32B on MB2, for Quench Spray Flow and observes readings of 3000 - 4000 gpm on each meter.
Flow exis' in both trains.
STEP 11 Performance Step: Notify the US that quench spray has <
been manually initiated.
- GRADE Standards: Informs the US that the first three (3) steps in FR Z.1 have been completed and quench spray has been initiated.
l Terminating Cue: The evaluation for this JPM is concluded.
StopTime:
1 4
8
I VERIFICATION OF COMPLETION Job Performance Measure Number: 055 Revision:___fi Date Performed:
1 Examinee: _
l Evaluator:
.. Validated Time (min): 8 Actual time to Complete (min):
Result of JPM: (Denote by an S for satisfactory or' a U for unsatisfactory)
Result of oral questions: Number of Questions:
Number of Correct Responses:
Score %
9
EXAMINEE HANDOUT INITIAL CONDITIONS AND INITIATING CUES JPM Tracking Number: _015 Initial Conditions: A steam line break inside containment has necured.
Based on the plant conditions a manual reactor trip and safety injection were initiated. The Control Room team l
i Is progressing through the EOPs. The transition to E 2, Faulted Steam Generator isolation, has just been entered. In checking the Status Trees, the crew has observed an orange path for containment integrity based on containment pressure just exceeding 23 pala, initiating Cues:
The US has directed you to perform the first three (3) steps in FR.Z 1. The US has decided to leave the Master Silence Switch in the " silence" position.
10
JOB PERFORMANCE MEASURE WORKSHEET i
1, JPM
Title:
RESTORE ESSENTIAL LOADS AND ALIGN CHARGING WHILE 4
PERFORMING RECOVERY WITH THE SBO DIESEL f ID Number: JPM 109 Revision: 2
- 11. Initiated
R. L. Lueneburg 6/25/97 Developer Date i
Ill. Reviewed:
k' 6/27/77 Technical heviewer Date Instructio'nal Reviewer
&/71/?7 Date IV. - Approved:
Mk Operations Manager Date Q
~
(. 3 7 Nuclear Training Supervisor Date 1
JOB PERFORMANCE MEASURE WORKSHEET Facility: Millstone Unit 3 Examinee:
JPM Tracking Number: 102 Validation Time: .30_ minutes Task
Title:
RESTORE ESSENTIAL LOADS AND ALIGN CHARGING WHILE PERFORMING RECOVERY WITH THE SBO DIESEL Time Critical Task: ( )YES ( X ) NO Task Number: 000'027'05'01 and 000'078'05'02 K/A Number: 062-000 A2.11 KIA Rating: 3.7/4.1 ADDlicable Methods of Testing:
Simulate Performance Actual Performance X Classroom Simulator X Plant Task Standards; Satisfactorily start a charging pump in the injection mode using ECA 0.2.
Reouired Materials: None.
General
References:
ECA 0.3 Rev. 4 and ECA 0.2 Rev. 8 READ TO THE EXAMINEE I will explain the initial conditions, which step (s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objectives for this JPM will be satisfied.
You may use any approved reference materials normally available in the Control Room, including logs Make all written reports, oral reports and log entries as if the evolution was actually being performed.
Initial Conditions:- A totalloss of all AO power has occurred which resulted in a plant trip and ultimately an SI. The only available power source is the SBO diesel which is running and providing power to emergency bus 340. The Control Room Team has just ma'de the transition to ECA-0.3. The BOP has just verified that SG pressures are stable. The Si and LOP actuation signals have been reset.
Initiating Cues: The US has directed you to perform steps 2 through 5 of ECA 0.3.
2
JOB PERFORMANCE MEASUPE WORKSHEET SIMULATOR REQUIREMENTS: 1. Reset to 1C 20. Press " Audible Alarms Disable".
- 2. Place the simulator in "RUN". Insert the following malfunctions:
l ED01 Loss of Off Site Power EG06A Diesel Generator A Falls to Start EG000B Diesel Generator B Falls to Start Allow the simulator to run until the low pressure Si occurs (approximately 10 minutes).
- 3. While waiting for the Si to actuate perform the following:
Under
- Instructor Directed Actions" select EGR08 to " START" (SBO Diesel control).
At MB8 "OPEN" the "A" Train SBO tie breaker (34A12).
Using ECA 0.0, Step 6 place the indicated control switches in the " PULL-TO LOCK" positions.
Open the NSST feeder breaker (NSSA 34A 2).
Under " Instructor Directed Actions" select EDR32 to "CLOSE"(Close SBO Output Breaker).
For the "A" electrical train perform the applicable actions of ECA-0.0 Steps 7 e and 7f.
- 4. After the Sl occurs, wait the required 60 seconds and reset the St. Then perform the actions of ECA-0.0 Steps 7h through 7n.
- 5. Position the following valves as indicated:
LCV*112D CLOSE LCV*112B OPEN MV'8801A CLOSE MV'8105 OPEN MV'8511 A CLOSE MV'8512A CLOSE
- 6. Acknowledge all alarms, reset " Audible Alarms Disable", and place the simulator in " FREEZE".
I 3
JOB PERFORMANCE MEASURE WORKSHEET i
l l
- 7. After the examinee has received the initial
- conditions and initiating cues, place the simulator in "RU N".
Approximate Simulator setup time is 20 minutes ,
l
?
f i
)
l 4
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System:
, 603 JPM Number: 109 Task
Title:
RESTORE ESSENTIAL LOADS AND ALIGN CHARGING WHILE PERFORMING RECOVERY WITH THE SBO DIESEL Denote Critical Steps with an *X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade Start Time:
STEP 1 X Performance Step: Check RCP SealIsolation status.
Verify all four RCP seal supply isolation valves CLOSED 3CHS*MV8109A 3CHS*MV8109B l
JCHS*MV8109C 3CHS*MV8109D GRADE Standards: Observes that MV8109A and MV8109C ind!cate open and MV8109B ond MV8109D have no indicatior,s, Shifts to the RNO column and performs the applicable actions for a charging pump not running, GRADE X Standards: Depresses the "CLOSE" oushbutton for 3CHS*MV8109A and o9 servo the indicating lights shift to yer:en "ON ,
red "OFF",
GRADE X Standards: Depresses the "CLOSE" pushbutton for 3CHS*MV8109C and observes the indicating lights shift to green "ON",
red "OFF",
GRADE X Standards: Either directly contacts a PEO or requests that the US contact one to locally close 3CHS*MV8109B and 3CHS*MV8109D.
5
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: 603 JPM Number: 109 Task
Title:
RESTORE ESSENTIAL LOADS AND ALIGN CHARGING WHILE PERFORMING RECOVERY WITH THE SBO DIESEL Denote Critical Steps with an "X" l
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade TCuet Under" Remote Function ~s " set CVR43 and CVR45 to 0.00 to simulate locally.
closing the vakes; As the PEOi inform the examinee that MV8100B :
. and MV8109D are closed.
STEP 2 X Performance Step: Verify RPCCW Ctmt return outer isolation valves (3CCP'MOV49A and 3CCP'MOV498) - CLOSED GRADE Standards: Observes that 3CCP'MOV40B indicates open and that 3C 7P*MOV49A has no indication.
GRADE X Standards: Depresses the "CLOSE" pushbutton for 3CCP'MOV49B and observes the indicating lights shift to green "ON",
red "OFF".
GRADE X Standards: Either directly contacts a PEO or requests that the US c.ontact one to locally close 3CCP'MOV49A.
' TCue:1 : In 1/0 overridet"cc",
' "3CCP*MOV49A", "close" select "on".
When the I/O is active, inform the examinee that 3CCP'MOV49A is
- closed.-
6
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: M3 JPM Number: 109 Task
Title:
RESTORE ESSENTIAL LOADS AND ALIGN CHARGING WHil E PERFORMING RECOVERY WITH THE SBO DIESEL Denote Critical Steps with an T
' NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade STEP 3 X Performance Step: RESET ESF Actuation Signals If l Required
. Si e CDA
. CIA
. CIB e LOP GRADE X Standards: The Si and LOP signals have been reset (part of the initial conditions).
The only signal required to be reset is CIA. Depresses the two CIA reset pushbuttons on MB2 and observes that annunciator MB2B 5-8 clears indicating that CIA has been reset.
Comment: If the examinee forgot the initial conditions or failed to realize that the applicable annunciators indicating actuation of these signals are now cleared, he may reset LOP and Sl again.
7
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: AQ3 JPM Number: 109 Task
Title:
RESTORE ESSENTIAL LOADS AND AllGN CHARGING WHILE PERFORMING RECOVERY WITH THE SBO DIESEL s
Denote Critical Steps with an *X" I
' NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade STEP 4 X Performance Step: Place The Following Equipment In Service On The Energized AC l
Emergency Bus. Place RPCCW system in service. Locally Open the following valves to cross-connect RPCCW non safety headers at CDS chiller 1B: (Service Bldg. El. 61"-3")
3CCP V186 3CCP V167 3CCP V187 3CCP V177 GRADE X Standards: Either directly contacts a PEO or requests that the US contact one to locally open 3CCP V186, V 167, V187, and V177.
TCue: Use Remote Functions *CCR08" and '
'CCR09" to *OPEN!the valves. When the valves ind.icate open, Inform the examinee that 3CCP-V186, V167,
. V187 and V177 are open.
e 8
l
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: 603 JPM Number: 10.9 Task
Title:
RESTORE ESSENTIAL LOADS AND ALIGN CHARGING WHILE 4
PERFORMING RECOVERY WITH THE SBO DIESEL '
i ,
, Denote Critical Steps with an "X" 4
' NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade
, STEP 5 Performance Step: Verify total SBO dieselload (SBO D/G 3 control panel) LESS THAN OR EQUAL TO 1000 Kw GRADE Standards: Either directly contacts the PEO at the
, SBO Diesel or has the US make the <
j contact to request the dieselload. ;
@Cis: _, '
Report back as the PEO that the SBOL 1- , dieselload is 200 Kw.
l STEP 6 X Performance Step: Start one RPCCW pump GRADE X Standards: Takes the control switch for the "A" RPCCW out of " pull to lock" and
, rotates the switch to the " start" position. Observes that starting i
amperage is indicated and that this changes to running amperage. Also,
- the indicating lights shift to green OFF, red ON.
STEP 7 X Performance Step: Establish instrument air to etmt.
Perform the following: START one shutdown instrument air compressor.
t GRADE X Standards: Takes the control switch for the "A" shutdown instrument air compressor out of " pull-to lock" and rotates the switch to the
- START" position.
Observes that the indicating lights shift to green OFF, red ON.
9
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: A03 JPM Number: 102 Task
Title:
RESTORE ESSENTIAL LOADS AND ALIGN CHARGING WHILE PERFORMING RECOVERY WITH THE SBO DIESEL Denote Critical Steps with an *X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade STEP ~~
8 X Performance Step: OPEN shutdown instrument air supply 1 (3tAS AOV95)
GRADE X Standards: Depresses the "OPEN" pushbutton for 31AS-AOV95, observes the indicating lights shift to green OFF, red ON, and releases the pushbutton.
Comment: The examinee may also ensure that indications of instrument air header pressure are indicated on IAS Pl73A.
STEP 9 X Performance Step: Open the non safety header supply and return isolation valves for the running RPCCW pump. Train A:
3CCP*AOV10A/19A 3CCP'AOV197A/194A GRADE X Standards: Depresses the *OPEN/ AUTO" pushbutton for 3CCP*AOV10A/19A and observes the indicating lights shift to green OFF, red ON, GRADE X Standards: Depresses the *OPEN/ AUTO" pushbutton for 3CCP'AOV197A/194A and observes the indicating lights shift '
to green OFF, red ON.
10
PERFORMANCE INFORMATION l Facility: Millstone Unit 3 System:
, AQ3 JPM Number: 109 Task
Title:
BESTORE ESSENTIAL LOADS AND ALIGN CHARGING WHILE PERFORMING RECOVERY WITH THE SBO DIESEL l
Denote Critical Steps with an "X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade STEP 10 X Performance Step: OPEN instrument air Ctmt isolation valves, GRADE Standards: Observes that MOV72 does not have power. Since the valve was open prior to the Loss of Power, it is failed in the open position.
' TCue:-- If the examinee requests guidance concerning the position of MOV72, provide the cue that the valve is failed open.
Comment: Prior to opening PV15, sufficient air header pressure will need to be present for the valve to move.
GRADE X Standards: Depresses the "OPEN" pushbutton for PV15 and observes the indicating lights shift to green OFF, red ON.
STEP 11 Performance Step: Place service water system in service:
Verify total SBO dieselload (SBO D/G control panel)- LESS THAN OR ,
EQUAL TO 1450 Kw.
GRADE __
Standards: Either directly contacts the PEO at the SBO diesel or requests that the US contact him to request current SBO load.
11
PERFORMANCE INFORMATION Facility: Millstone Unita System: 603 JPM Number: 109 Task
Title:
BESTORE ESSENTIAL LOADS AND ALIGN CHARGING WHILE PERFORMING RECOVERY WITH THE SBO DIESEL Denote Critical Steps with an "X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade
~
TCuei ~ Role play as either the PEO or US!
and inform the examinee that the
! current load on'the SBO dieselis
, _1.000 Kw.'
STEP 12 X Performance Step: START one service water pump.
l GRADE X Standards: For the service water pump not in
" Pull-to-Lock" on the "A" train, rotates the control switch to the START position and observes that amperage is indicated and the indicating lights shift to green OFF, red ON.
I STEP 13 Performance Step: Check service water pump discharge valve - OPEN FOR RUNNING PUMP.
GRADE Standards: For the running pump observes that the indicating lights for the applicable discharge valve (3SWP*MOV102A or 102C) the indicating lights are green OFF, red ON.
STEP 14 Performancs Step: Check TPCCW heat exchanger SW supply isolation valves (3SWP*MOV71 A and 3SWP*MOV718) - CLOSED.
GRADE Standards: Observes that the indicating lights for 3SWP*MOV71 A are green ON, red OFF. The valve is closed.
12 m
PERFORMANCE INFORMATION Facility: Millstone _ljaita System: AQ3 JPM Number: 109 Task
Title:
RESTORE ESSENTIAL LOADS AND AllGN CH6RGING WHILE PERFORMING RECOVERY WITH THE SBO DIESEL Denote Critical Steps with an "X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade GRADE Standards: Observes that 3SWP*MOV71B has no power. Since the valve was open when power was lost, it is failed open.
Requests that the US send a PEO to locally close 3SWP'MOV718.
= TCue: ' Role play as the' US"and inform the examinee that a PEO has been sent to locally close 3SWP!MOV71B and that the examinee'should consider this -
a step in progress and proceed with
. the procedure.( m Comment: During the next JPM step,if the examinee questions the position of 3CHS*LCV112C or appears confused, provide the following cue:
(4Cuei .l3CHS*LCV112C was open prior to
. losing power, The valve is still open.
STEP 15 Performance Step: Place charging sytem in service:
Verify RCS makeup system is available for service:
Verify VCT to charging isolation valves
-OPEN GRADE Standards: Observes that the indicating lights for 3CHS*LCV112B ,VCT to charging isolation valve, is green OFF, red ON.
The valve is open. 3CHS*LCV112C has no lights lit. No power for 13
PERFORMANCE INFORMATION Facility: Millslone Unit 3 System: AQ3 JPM Number: 102 Task
Title:
RESTORE ESSENTIAL LOADS AND ALIGN CHARGING WHILE PERFORMING RECOVERY WITH THE SBO DIESEL Denote Critical Steps with an T
- NOTE
- Critical Steps must be completed correctly to ach eve a satisfactory grade indication. The valve was open prior to the power loss and is therefore still open.
STEP 16 Performance Step: Verify primary grade water pumps -
POWER AVAILABLE GRADE Standards: Observes that power is NOT available to the primary grade water pumps.
These pumps are powered off the non vital busses and all of the load centers were stripped prior to placing the SBO diesel on bus 34A. Shifts to the RNO column.
Comment: For the next JPM step. valve 3CHS*LCV112E has no power and cannot be opened from MB3. If the examinee requests that the valve be opened locally, acknowledge his request and provide the following cue:
SCue:: } Ths rhinirnum safety funbtidn is met Twith LCV112D being opene_d, proceed -
Ewith the procedure.-
STEP 17 X Performance Step: lE RCS makeup is HQI svailable, THEN Align charging pump suction to RWST:
OPEN the RWST to charging isolation valves.
14 5
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: AQ3 JPM Number: 109 Task
Title:
RESTORE ESSENTIAL LOADS AND ALIGN CHARGING WHILE '
PERFORMING RECOVERY WITH THE SBO DIESEL Denote Critical Steps with an "X" <
- NOTE
- Critical Steps must be comp!sted correctly to achieve a satisfactory grade GRADE X Standards: Depresses the *OPEN" pushbutton for 3CHS*LCV112D and observes the indicating lights shift to green OFF, red ON.
l GRADE X Standards: There are no light indications for 3CHS*LCV112E. The valve does not have power. Requests that the US send an PEO to locally open the valve.
Comment: For the next JPM step, valve 3CHS*LCV112C has no power and cannot be closed from MB3. If the examinee requests that the valve be closed locally, acknowledge his request and provide the following cue:
'4Cuef -The' minimum safety function is met -
(with LCV112B being cle*ed, proceed
- .with the procedure. '
STEP 18 X Performance Step: CLOSE the VCT to charging isolation valves.
GRADE X Standards: Depresses the "CLOSE" pushbutton for 3CHS*LCV112B and observes that the indicating lights shift to green "ON", red "OFF".
GRADE Standards: Valve 3CHS*LCV112C has no power.
15
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System; 603 JPM Number: 109 Task
Title:
RESTORE ESSENTIAL LOADS AND ALIGN CHARGING WHILE PERFORMING RECOVERY WITH THE SBO DIESEL Denote Critical Steps with an "X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade Requests that the US send an PEO to locally close then valve.
Comment: For the next JPM step, valve 3CHS*MV8106 has no power and cannot be closed from MB3, If the examinee requests that the valve be closed locally, acknowledge his request and provide the following cue:
14Cuei 1Thi minimu'm"safetp functiori is^ met
?with MV8105 being closed, proceed with the procedure.
STEP 19 Performance Step: Verify charging header isolation valves (3CHS*MV8105 and 3CHS*MV8106) - CLOSED.
GRADE Standards: Observes that the indicating lights for 3CHS*MV8105 are green "OFF", red-
"ON", the valve is open. Valve 3CHS*MV8106 has no indicating lights lit. The valve has no power but was last open before power was lost.
Shifts to the RNO column: CLOSE valves GRADE Standards: Depresses the "CLOSE" pushbutton for 3CHS*MV8105 and observes the indicating lights shift to green ON, red OFF.
16
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System:
A03 JPM Number: 102 Task
Title:
RESTORE ESFJ.NTIAL LOADS AND AllGN CHARGING WHILE PERFORMING RECOVERY WITH THE SBO DIESEL Denote Critical Steps with an *X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade GRADE Standards: Requests that the US send an PEO to locally close 3CHS*MV8106.
l Comment: For the next JPM step,' valves i
3CHS*MV8111A,B and C do not have power. If the examinee questions their position, provide the following cue:
- 4 Cue: The valves were open before power.
--was lost and.therefore are still open.
STEP 20 Performance Step: Verify charging pump recirculation isolation valves - OPEN 3CHS*MV8111 A 3CHS*MV8111B 3CHS*MV8111C 3CHS*MV8110 GRADE Standards: Observes that the indicating lights for 3CHS*MV8110 are green "OFF", red "ON", the valve is open.
GRADE Standards: Observes that valves 3CHS*MV8111A, B and C have no indication. The valves do not have power. The valves were open prior to the loss of power and are, therefore, still open.
17
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: M3 JPM Number: 1 19 Task
Title:
RESTORE ESSENTIAL LOADS AND ALIGN CHARGING WHILE PERFORMING RECOVERY WITH THE SBO DIESEL Denote Critical Steps with an "X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade STEP 21 Performance Step: Verify total SBO dieselload (SBO D/G control panel)- LESS THAN OR I
EQUAL TO 1450Kw GRADE ~^
Standards: Either directly contacts the PEO at the SBO or requests that the US contact the PEO to determine the current SBO dieselloading.
l TCue: . ~ Role' play as the PEO or the'US 'and~
Lprovide the cue that the current SBO
..dieselload is 1400 K_ w -
STEP 22 X Performance Step: START one charging pump.
GRADE X Standards: Rotates the control switch for the "A" charging pump to the " START" position and observes that the indicating lights shift to green OFF, red ON and amperage is indicated on the amm/er.
STEP 23 X Performance Step: Establish Charging Flow. Close charging line flow control valve.
GRADE X Standards: Depresses the down arrow (V) pushbutton on the 3CHS*FCV121 controller and observes that the
" MAN" light comes on, the controller output decreases and eventually the 18 l
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: AQ3 JPM Number: 102 Task
Title:
RESTORE ESSENTIAL LOADS AND ALIGN CHARGING WHILE PERFORMING RECOVERY WITH THE SBO DIESEL Denote Critical Steps with an T
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade down arrow pushbutton back lights green indicating the valve is closed.
Comment: In the next JPM step, valve 3CHS*MV8106 has no power. The
' valve was open prior to losing power.
If the examinee questions the status of the valve, provide the following cue:
ICue: 3CHS*MV8106 wa's .open prior to the!
i loss of p'ower and is'stillLopen.;
i STEP 24 X Performance Step: Open charging header isolation valves (3CHS*MV8105 and 3CHS*MV8106)
GRADE X Standards: Depresses the "OPEN" pushbutton for MV8105 and observes the indicating lights shift to green "OFF, red "ON".
GRADE Standards: Observes that 3CHS*MV8106 has no power. The valve was open prior to the power loss and is, therefore, still open.
STEP 25 Performance Step: Throttle Open charging line flow control valve to maintain PZR level.
GRADE Standards: Depresses the up arrow (A) pushbutton on the 3CHS*FCV121 controller and observes that charging flow is indicated. Throttles flow as a
necessary to maintain pressurizer 19
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: AQ3 JPM Number: 109 Task
Title:
RESTORE ESSENTIAL LOADS AND ALIGN CHARGING WHILE PERFORMING RECOVERY WITH THE SBO DIESEL Denote Critical Steps with an "X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade level.
1TCuef 1 After ths'sxamin'ee manipulates the -
3CHS*FCV121 controller and it is?
J elear that he is monitoring pressurizer
- level provide the. terminating cue.',
Terminating Cue: The evaluation for this JPM is concluded.
Stop Time:
20
VERIFICATION OF COMPLETION Job Performance Measure Number: 101 Revision: .1 Date Performed:
Examinee:
Evaluator:
Validated Time (min): _3.0_ Actual time to Complete (min):
Result of JPM: (Denote by an S for satisfactory or a U for unsatisfactory)
Result of oral questions: Number of Questions:
Number of Correct Responses:
Score %
-,t 21
EXAMINEE HANDOUT lNITIAL CONDITIONS AND INITIATING CUES JPM Tracking Number: 101 Initial Cor.ditions: A totalloss of all AC power has occurred which resulted in a plant trip and ultimately an SI. The only available power source is the SBO diesel which is running and providing power to emergency bus 34C. The Control Room Team has Just made the transition to ECA-0.3. The BOP has Just verified that SG pressures are stable. The Si and LOP actuation signals have been reset.
Initiating Cues: The US has directed you to perform steps 2 through 5 of EC A-0.3.
22
, cazlG.
JOB PERFORMANCE MEASURE WORKSHEET I. JPM
Title:
PRESSURIZER PRESSURE CONTROL FOLLOWING REACTOR TRIP ID Number; JPM-050A Revision: 5
- 11. Initiated:
A. Oxfurth 3/11/97 Developer Date l
l-1 Ill. Reviewed:
l 3-7(~i)
Tech'n leal $eviewer Date
,S-f.
776strudti'on514eview
~$ 3hthn Date IV. Approved: .
3 l 1 r ,
)
j 3 27 g7 Operations Manager Date J I 1
i oM n -
3%7d)
Nuc'ieliTTraining Supervisor Date 1
JOB PERFORMANCE MEASURE WORKSHEET Facility: Millstone Unit 3 - Examinee:
-JPM Tracking Number: 05DA Validation Time: 5 minutes Task
Title:
PRESSURIZER PRESSURE CONTROL FOLLOWING REACTOR TRIP Time Critical Task: ( X )YES ( )NO Task Number:
000*013*05*01. 000'065*05"02. 010*005*01*01 and 010'013*04*01 K/A Number: 000-027-EA1.01 K/A Rating: 4.0 / 3.9 Acolicable Methods of Testing:
Simulate Performance Actual Performance X L Classroom Simulator X_ Plant Task Standards: Satisfactorily complete EOP actions to control pressurizer pressure using EOP 35 ES-0.1.
Reauired Materials; None.
General
References:
EOP 35 ES-0.1 Rev.13 READ TO THE EXAMINEE l will explain the initial conditions, which step (s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objectives for this JPM will be satisfied.
You may use any approved reference materials normally available in the Control Room, including logs. Make all written reports, oral reports and log entries as if the evolution was actually being performed.
Initial Conditions: An inadvertent reactor trip has occurred. The control room team has completed the actions of E-0 and ES-0.1, through Step 4.
Initiating Cues:
The US has directed you to check pressurizer pressure control using step 5 in EOP 35 ES-0.1. You will be responsible for acknowledging the alarms on MB4. During the performance of this JPM other annunciators may come in (i.e. condenser vacuum, etc.) The instructor will role play as a second control board operator and acknowledge / reset these alarms.
, 2
JOB PERFORMANCE MEASURE WORKSHEET-Simulator Condition: 1. Recet to IC 20,100% steady state power.
- 2. Insert malfunctions RP02A and RP02B - reactor trip.
- 3. Place the simulator in *RUN" Allow the reactor trip to occur, throttle back AFW flow to approximately 150 gpm per SG by closing the MDAFW flow control valves and throttling the TDAFW flow control valves to 10% open. Trip the TDFW pumps to minimize feedwater oscillations.
- 4. Acknowledge / reset alarms and place the simulator in
" Freeze".
- 5. Insert malfunction RX06A, pressurizer spray valve PCV-455B auto control failure, at 50% severity over a ramp time of 120 seconds.
- 6. Under Simulator diagrams (left screen):
RX Sheet 13, component 3RCS-PK455B, select " auto" and then " activate" This will keep controller PK455B in the " AUTO" position.
The intent is to have an inadvertent reactor trip with a spray valve failing open after the simulator is placed in "RUN".
- 7. Place the simulator in "RUN" and verify RCS pressure is 2000 e 10 psig and decreasing, Place the simulator in
" FREEZE".
4
- 8. After the examinee has received the initiating cues and initial conditions, place the simulator in "RUN".
Approximate setup tinie 1010 minutes.
3
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: S01
-JPM Number: 050A Task
Title:
Pressurizer Pressure Control Following Reactor Trio Denote Critical Steps with an "X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade i
Start Time:
l NOTE: If during the performance of this JPM, a Low Pressurizer pressure Si is actuated, the examinee automatically fails.
STEP 1 Performance Step: Check PZR Pressure Control Verify PZR pressure - GREATER THAN 1890 psia.
- GRADE Standards
- Checks pressurizer pressure greater 4
than 1890 psia by observing pressure indication on meters RCS-Pl455A RCS-Pl456A RCS-Pl457 RCS-Pl458
$ OR Recorder PR455.
STEP 2 Performance Step: Verify PZR pressure - STABLE AT OR TRENDING TO 2250 psia.
GRADE Standards: Notes that PZR pressure is less than 2250 psia and decreasing. Checks the
. RNO column and proceeds to step 5d.
4
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: S01 JPM Number: 050A Task
Title:
Pressurizer Pressure Control Following Reactor Trio Denote Critical Steps with an "X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade STEP 3 Performance Step: Check PZR status: Check PZR pressure - LESS THAN 2250 psia.
~ GRADE Standards: Monitors pressure and observes that pressure is less than 2250 psla.
STEP 4 Performance Step: Verify PZR PORVs - CLOSED.
GRADE Standards: Verifies PZR PORV valves closed by observing indicating lights as green ON, red OFF.
Comments: The examinee may also check PORV outlet temp (RCS-Tl463) as approximately 110*F and PRT parameters as confirmatory indications.
Comments: During JPM steps 5,6 and 7, the exasnee may decide to inform the US of problems and corrective actions taken in accordance with the procedure. This is not required for satisfactory completion of the step.
STEP 5 X Performance Step: Verify PZR spray valves - CLOSED.
GRADE X Standards: Identifies that loop #1 PZR spray valve, RCS*PCV455B is OPEN.
5
r PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: S01 JPM Number: 050A Task
Title:
Pressurizer Pressure Control Following Reactor Trio Denote Critical Steps with an "X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade STEP 6 X Performance Step: Proceed to RNO column CLOSE the spray valves.
GRADE X Standards: Depresses the " manual" pushbutton on controller RCS*PCV455B.
Observes the controller will not shift to
" manual" (" auto" light stays lit and the
" manual" light does not come on).
Comments: The examinee may depress the "UP ARROW"(A) and/or "DOWN ARROW"(V) pushbuttons to confirm the controller did not shift to
- manual".
This is not required to complete the step. Additionally, the examinee may place the Master Pressure Controller (3RCS*PCV455A) in " MANUAL" and increase its output in an attempt to close the spray valve. Since the controller output is already at the maximum, this will have no effect and is not required for completion of the step.
6
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: S01 JPM Number: 050A Task
Title:
Pressurizer Pressure Control Followino Reactor Trio Denote Critical Steps with an "X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade STEP 7 X Performance Step: IE any spray valve can 110I be closed THEN STOP RCPs 1 and 2.
GRADE X Standards: Rotates RCP 1 control switch RCS-P1 A to the "STOP" pos.ition and observes the indicating lights shift to l green ON, red OFF and amperage goes to zero.
GRADE X Standards: Rotates RCP 2 control switch, RCS-P1B to the "STOP" position and observes the indicating lights shift to green ON, red OFF and amperage goes to zero.
Comments: Annunciators "RCP Loop 1 Flow Lo",
"RCP Loop 2 Flow Lo" and "RCP Low Speed" will alarm. The examinee should silence and acknowledge these alarms. This is not necessary to satisfy this critical step.
STEP 8 Performence Step: . Verify PZR heaters - ENERGlZED.
i GRADE Standards: Verifies heater groups 3RCS*H1 A, H1B, H1C, H1D and H1E are on by observing the indicating lights as green OFF, red ON.
7
PERFORMANCE INFORMATION Facility:- Millstone Unit 3 System: S01 JPM Number: 050A Task
Title:
Pressurizer Pressure Control Followina Reactor Trio Denote Critical Steps with an "X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade STEP 9 Performance Step: Inform the US that pressurizer i
pressure control has been checked.
GRADE Standards: Reports to the US that pressurizer pressure control has been checked, RCPs 1 and 2 have been stopped and pressure is now stable. Also reports the problem with the spray valve , if not previously done.
Terminating Cue: The evaluation for this JPM is concludcd.
Stop Time:
8
VERIFICATION OF COMPLETION Job Performance Measure Number: 050A Revision: 1 Date Performed:
Examinee:
Evaluator:
i i
l Validated Time (min): 4 Actual time to Complete (min):
Result of JPM: (Denote by an S for satisfactory or a U for unsatisfactory)
Result of oral questions: Number of Questions:
Number of Correct Responses:
Score %
'I 9
EXAMINEE' HANDOUT INITIAL CONDITIONS AND INITIATING CUES JPM Tracking Number: 050A initial Conditions: An inadvertent reactor trip has occurred. The control room team has completed the actions of E-0 and ES 0.1 through step 4.
Initiating Cues: The US has directed you to check pressurizer pressure control using step 5 in EOP 35 ES-0.1. You will be responsible for acknowledging the alarms on MB4, During the performance of this JPM other annunciators may come in (i.e. AMSAC not armed, condenser vacuum, etc.) The instructor will role play as a second control board operator and acknowledgelreset these alarms
(
NOTE: If during the performange of this JPM. a Low Pressurizer pressure Si is actuated. the examinee automatically faRL 10
02)d.
JOB PERFORMANCE MEASURE WORKSHEET l 1. JPM
Title:
RESTORING 4.18 KV BUS FOLLOWING A LOSS OF POWER ID Number: JPM 042 Revision: 6 II, Initiated:
R. L Lueneburg 10/15/96 Developer Date 111. Reviewed:
Technical Reviewer Date Instructional Reviewer Date IV. Approved:
- Operations Manager Date Nuclear Training Supervisor Date 4
1
JOB PERR)RMANCE MEASURE APPROVAL SHEET
- 1. JPM
Title:
RFKIDRING 4.16 KV BUS FOLI OWING A LOSS OF POWER I.D. Number: JPM-042 Resision: ._fi_.
~ II. Initiated:
! R.1 Ineneburo Date: 10/15/96 l Developer t
1 I
D III. Resiewed:
Abb h Date: /ck}fi echnical Reviewer 4'b [ Date: /sdo/fc nstructional Reiiewer IV. Appmved:
Date: /s tt-%
Opefation ianager 1
Date: (0 4 Ed C Nuclear Training Supervisor Page 1 of 10
JOB PERFORMANCE MEASURE WORKSHEET Facility: Millstone Unit 3 Examinee:
JPM Tracking Number:- 042 Validation Time: 15 minutes l Task
Title:
RESTORING 4.16 KV BUS FOLLOWING A LOSS OF POWER l Time Critical Task: ( )YES ( X ) NO l
Task Number: 062'046*01*01 K/A Number: 062-000 A2.12 K/A Rating: 3.2 / 3.6 Aeolicable Methods of Testing:
Simulate Performance Actual Performance X Classroom Simulator X Plant Task Standards: Satisfactorily complete restoring off site power to a 4.16 KV bus during the recovery from a loss of power.
Reauired Materials: None.
General
References:
OP 3343 Rev.11 READ TO THE EXAMINEE l will explain the initial conditions, which step (s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objectives for this JPM will be satisfied.
Yea may use any approved reference materials normally available in the Control Room, including logs. Make all written reports, oral reports and log entries as if the evolution was actually being performed.
Initial Conditions: A temporary UV condition has resulted in bus 34D being powered by the "B" EDG. Bus 34B is on NSSA.
Initiating Cues: The US has directed you to parallel across bus 34B to 34D tie breaker using OP 3343 Sections 7.3.2 - 7.3.4. The dieselis to remain loaded.
2
JOB PERFORMANCE MEASURE WORKSHEET SIMULATOR CONDITIONS: 1. Reset to 10-01, Cold Shutdown RCS Pressure a 75 psia, temperature a 100*F.
- 2. Insert malfunction ED04D-34D bus differential lockout.
Place the simulator in "RUN".
- 3. After the plant stabilizes, remove the malfunction. The "B" EDG output breaker will auto close and energize bus 34D. Adjust "B" EDG frequency to 60 Hz. Match flags -
for 34D - 34B tie breaker. Close the breakers for the "B" train emergency load centers. Acknowledge the clear / reset alarms and place the simulator in " FREEZE".
- 4. After the examinee has rece ived the initiating cues and initial conditions, place the simulator in "RUN".
Approximate setup time is 4 rainutes.
3
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: dEV.
~ JPM Number: 042 Task
Title:
RESTORING 4.16 KV BUS FOLLOWING A LOSS OF POWER Denote Critical Steps with an "X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade Start Time:
STEP 1 X Performance Step: TURN bus 34B to 34D bus tie synchronizing selector, on (MB8).
GRADE X Standards: Places handle into bus 34B and 34D bus tie synchronizing selector switch (if not already in place) and rotates the handle to the ON position.
Comments: The examinee has been told that the dieselis providing bus 34D and therefore, he should perform OP 3343 Step 7.3.2.6 through 7.3.4.
STEP 2 X Performance Step: lE a loss of power has occurred, RESET the LOP, (MB2).
GRADE X Sta dards: Depresses the train "B" LOP RESET pushbutton on MB2.
CommenM: The examinee may push both train A and B LOP reset pushbuttons. This is acceptable to complete the critical nature of this step.
Several annunciators associated with the LOP signal will reset. The examinee should silence and reset these annunciators. This action is not required to complete the critical nature of this step.
4 I
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: _4Ky JPM Number: 0_42 Task
Title:
RESTORING 4.16 KV BUS FOLLOWING A LOSS OF POWER Denote Critical Steps with an "X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade STEP -3 X Performance Step: PRESS the " BYPASS' pJshbutton for bus 34D undervoltage block and VERIFY white lir N .ss lit (MB8R).
GRADE X Standards: Depresses the " Bypass" pushbutton for 34D UN block and observes the "Undervolt Rly Oper." White light extinguishes.
STEP 4 X Performance Step: SHIFT EDG B mode as follows:
l ADJUST diesel" Speed / Load" switch to obtain a frequency of 60.8 HZ.
GRADE X Standards: Rotates the diesel" Speed / Load" switch in the raise direction to increase diesel frequency to 60.8 HZ.
STEP 5 X Performance Step: PLACE EDG B mode selector in
" PARALLEL".
GRADE X Standards: Turns the "B" EDG mode selectdr switch to the "PAFALLEL" position.
' Monitors the EDG frequency to ensure it remains greater than 59.2 HZ.
5 x . ,.- -
PERFORMANCE INFORMATION Facility: Mi!! stone Unit 3 System: 4Ky JPM Number: 0_42 Task
Title:
RESTORING 4.16 KV BUS FOLLOWING A LOSS OF POWER Denote Critical Steps with an "X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade STEP 6 X Performance Step: ADJUST diesel " Speed / Load" switch to maintain frequency of 59.9 to 60,1
. HZ.
GRADE X Standards: Rotates the " Speed / Load" switch as l
necessary to obtain a frequency between 59.9 to 60,1 HZ, STEP 7 Performance Step: WHEN frequency is stable at 59.9 to 60,1 HZ, continue.
GRADE Standards: Does not continue until the EDG frequency is stable between 59.9 and 60.1 HZ.
6
. .. - - _ _ - - - . _ . - . _ _ - _ = _ . . ~ - . - . . . . - - - -
PERFORMANCE INFORMATION Facility: Millstone Unit 3 Gyctem:
dKV JPM Numben 042 Task
Title:
RESTORING 4.18 KV GUS FOLLOWING A LO'3S OF POWER Denote Critical Steps with an *X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade STEP 8 X Performance Step: SYNCHRONIZE and CLOSE 34D*1T-2 "34B 34D TIE" breaker as follows:
(MBB)
ADJUST diesel generator B speed / load control to cause the synchroscope to rotate slowly in the "FAS1" direction.
- ADJUST the auto voit regulator to match diesel generator B voltage (RUNNING) to bus 34B voltage (INCOMING).
WHEN synchroscope is rotating slowly in the fast direction AND the pointer is at five minutes before the twelve o' clock position, CLOSE 34D*1T-2,"348 34D TIE" breaker.
GRADE X Standards: Adjusts "B" EDG frequency by rotating the " speed / load" switch to raise /!ower positions until the synchroscope is rotating slow in the fast direction.
GRADE ~~ ~~
X Sundards: Check voltages matched, if n ,t
, matched, adjusts "B" EDG vo'. age with the auto voltage regulat' r switch so incoming and running voltages are mctched.
7
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: dKV JPM Number: 042 Task
Title:
RESTORING 4.18 KV BUS FOLLOWING A LOSS OF POWER Denote Critical Steps with an *X"
' NOTE' Critical Steps must be completed correctly to achieve a srtisfactory grade GRADE X Standards: When the synchronizing meter reaches the five minutes before 12 o' clock po:ition, rotates the 34B 34D tie breaker switch to the "CLOSE" position and observes the lights shift to green "OFF", red "ON".
Comments: Inform the examinee that the dieselis RQIto be UNLOADED or SHUTDOWN (if he asks the question -
it was provided as an initiating cue).
STEP 9 Performance Step: 1E a loss of power has occurred, PRESS the appropriate STATION LOP RESET (Sequencer).
GRADE Standards: Depresses LOP RESET on the "B" wequencer and observes the white light goes out.
STEP 10 Performance Step: TURN the synchronizing selector, off, GRADE Standards: Turns the synchronizing selector to the "OFF" position.
8
PERFORMANCE INFORMATION Facility: Millatone Unit 3 System: dKV JPM Number: Q42 Task
Title:
RESTORING 4.16 KV BUS FOLLOWING A LOSS OF POWER Denote Critical Steps with an T
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade STEP- 11 Performance Step: Inform the US that tie breaker 34B to 34D is closed.
GRADE Standards: Reports the US that the tie breaker i
34B to 34D is closed, Terminating Cue: The evaluation for this JPM is concluded.
Stop Time:
9 n- __ l
i e
VERIFICATION OF COMPLETION i
Job Perforri?nce Measure Number: Q42 Revision: 0 Date Performed:
f I
Examinee:
L Evalualor:- I
?
Validated Time (min): Actual time to Complete (min): ;
)
Result of JPM: 15 (Denote by an S for satisfactory or a U for unsatisfactory) l l
Result of oral questions: Number of Questions: '
i Number of Correct Responses:
Score %
F 4
?
10:
w n y,y.ry re--,, e - we r , -to---..,ggo -
-sw-,-w,--n. ,r,www+-re-,.-wru... e . --m.n.ww,wse,w-*,,-,,-#,_,w-. -
.- n---,,-w,#-rw- eenm,wy, ,y,,-e - .wwm,3,,-+-
i EXAMINEE HANDOUT t
INITIAL CONDITIONS AND INITIATING CUES
\
JPM Tracking Number: 942 l l
1
, Initial Conditions: A temporary UV condition has resulted in bus 34D being
- powered by the "B" EDG, Bus 34B is on NSSA.
l Initiating Cues: The US has directed you to parallel across bus 34B to 34D tie breaker using OP 3343 Sections 7.3.2 7.3.4.
The diesel is to remain loaded.
a l
l e
{.
11
_ ~ _ _ _ . _ - _ ~ - -
-_- _ _-,_._ _ _ _ _ _ . _ _ _ _ . . _ . . ._ . ~ . ._
fl/A9 JOB PERFORMANCE MEASURE WORKSHEET l
- 1. Ja'M
Title:
-RESPOND TO A PRESSURl2ER LEVEL FAILURE e ID Number: NEW-4 Revision: 0 ll. Initiated:
Ray Lueneburg 5/13/97 Developer Date Ill. Reviewed:
E _ d/17/j/7 TechnicaliRev!hwer Date instructional flevTswer
$/?C,/ff Date IV. Approved:
D -
Operations Manager Date Y bb]
Nuclear Training Supervisor Date 1
JOB PERFORMANCE MEASURE WORKSHEET Facility: Millstone Unit 3 Examinee:
JPM Tracking Number: NEW-4 Validation Time: .15 minutes Task
Title:
RESPOND TO A PRESSURIZER LEVEL FAILURE Time Critical Task: ( )YES ( X ) NO Task Number: 344*067*04*01 )
K/A Number: 0.16 A2.01 K/A Rating: 3.0/3.1_
Applicable Methods of Testing:
Simulate Performance Actual Performance X Classroom Simulator X Plant Task Standards: Satisfactorily respond to a loss of pressurizer level channel and return pressurizer level control to automatic.
Required Materlatt None General
References:
AOP 3571, Rev.5 READ TO THE EXAMINEE l will explain the initial conditions, which step (s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objectives for this JPM will be satisfied.
You may use any approved reference materials normally available in the Control Room, including logs. Make all written reports, oral reports and log entries as if the evolution was actually being performed.
Initial Conditions: A failure of the controlling pressurizer level channel transmitter (LT450) has occurred. The crew has taken manual control of the master pressurizer level controller and the charging line flow controlvalve controller (3CHS*FCV121) Plant parameters have been stabilized.
Initiating Cues: The US has directed you to perform steps 1 - 5 of Attachment C in AOP 3571.
/
2
i l JOB PERFORMANCE MEASURE WORKSHEET l
Simulator Requirements: 1. Roset to IC # 14
- 2. Place the simulator in *Run".
- 3. Insert malfunction : RX10A at 0% severity on a 30 sec.
ramp.
- 4. Place the master PZR level controller,3RCS*LK459, and the charging line flow control valve controller, 3CHS*FCV121, in manual. Allow PZR level to increase above 62%.
- 5. Acknowledge / clear all annunciators and place the simulator in " freeze".
- 6. Place the simulator in *Run" after the examinee has read the initial conditions and initiating cues.
- Approximate simulator setup time is 5 minutes.
3 a
PERFORMANCE INFORMATION Facility: _ Millstone Unit 3 System: A71 JPM Number: NEW-4 Task
Title:
RESPOND TO A PRESSURIZER LEVEL FAILURE
, Denote Critical Steps with an T
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade Start Time:
Comments: While performing the steps in this JPM, annunciators will clear. The examinee should acknowledge / reset as appropriate. This is not required to comp lete the critical nature of any step.
STEP 1 X Performance Step: Defeat the failed channelinput.
Pressurizer Level Select Control 3RCS-LS459D t ,
Pressurizer Level Select Record 3RCS LS459E GRADE X Standards: Rotates the level select control switch to the 3 2 position, GRADE X Standards: Rotates the level select record switch to any position other than channel 1. .
Comment: With letdown stillisolated, the examinee may be unable to restore PZR level to normal, He should realize this and consider step 2 a step -
in progress and proceed to step 3. If the examinee appears confused or questions what to do, provide the-following cue:
4
]
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: A71 JPM Number: NEW-4 Task
Title:
RESPOND TO A PRESSURIZER LEVEL FAILURE Denote Critical Steps with an *X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade l
l Cue:' Consider this a step in progress',
restore letdown and then complete-
. restoring PZR level.
STEP 2 Performance Step: Restore PZR level to normal.
GRADE Standards: Depresses the down (V) arrow push outton for 3CHS*FCV121, charging line flow control valve, to close the valve and stop the increase in pressurizer level STEP 3 Performance Step: Restore letdown using OP 3304A, Charging and Letdown, section 7.33 -
GRADE Standards: Obtains a copy of OP 3304A and refers to section 7.33.
Cue: ' When theiexaminee~ opens OP 3304A,
' inform him that.it is not desired to place _' excess letdown in servlee.
Comment: Based on the cue, the examinee should proceed to the scvond step in section 7.33, iCuei ;lf ths examined requests the shift ~
' supervisor's log for the next step, tell
~ him to just keep a rough log for now.
also inform him that we will align letdown to loop 1.
5
_ J
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: A71 JPM Number; NEW.4 Task
Title:
RESPOND TO A PRESSURIZER LEVEL FAILURE Denote Critical Steps with an T
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade Comment: The NOTE prior to the first step in section 7.33 requires that charging flow be maintained untilletdown is restored. If the examinee had completely closed FCV 121 in attempts to maintain pressurizer level, he should re-open the valve to some minimum charging flow.
STEP 4 Performance Step: RECORD the following data in the Shift Supervisor's Log:
e Cold leg temperature (Tc) for the appropriate loop 1 or loop 4
- Regenerative heat exchanger outlet temperature as indicated on 3CHS Tl 126(MB3) e VCT outlet temperature as indicated on 3CHS-Tl 116(MB3)
GRADE Standards: Obtains the data from the appropriate indications and records the values in the rough log.
STEP 5 Performance Step: CLOSE letdown orifice isolation valves (MB3) e 3CHS*AV8149A
. e 3CHS*AV8149B e 3CHS*AV8149C 6
_j
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: A71 JPM Number: NEW-4 Task
Title:
RESPOND TO A PRESSURIZER LEVEL FAILURE Denote Critical Steps with an "X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grede GRADE Standards: Observes that the indicating !ights for all three valves are green ON, red OFF. The valves are closed.
STEP 6 X Performance Step: OPEN 3RCS*LCV459 and 3RCS*LCV460, letdown isolation valves (MB3).
GRADE Standards: Observes that the indications for 3RCS*LCV460 are green OFF, red ON. The valve is open.
GRADE X Standards: Rotates the control switch for 3RCS*LCV459 to "Open" and obt.erves the indicating lights shift to green OFF,~ red ON. Releases the switch back to the " auto" position.
STEP 7 Performance Step: OPEN 3CHS*CV8160 and 3CHS*CV8152, letdcan containment isolation valves (MB3).
GRADE Standards: Observes that the indicating lights for 3CHS*CV8160 and 3CHS*8152 are green OFF, red ON. The valves are open.
7
PERFORMANCE INFORMATION Facility: Mit! stone Unit 3 System: A71 JPM Number: NEW-4 Task
Title:
RESPOND TO A PRESSURIZER LEVEL FAILURE Denote Critical Steps with an *X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade STEP 8 X Performance Step: PLACE 3CHS PK131, letdown low pressure controller, in
- MANUAL" and ADJUST to 50% (MB3).
GRADE X Standards: Depresses either the up (A) arrow or down (V) arrow push button on 3CHS PK131 and observes the " auto" light goes out and the
- man" light comes on. Depresses the push buttons as necessary until the controller output indicates 50%
Comment: In the next JPM step the examinee may use the flow indicated on the controller or the computer trend to determine that adequate charging flow has been established.
STEP 9 X Performance Step: ADJUST 3CHS FK121, charging header flow controller (MB3) to establish charging flow approximately 55 ppm.
GRADE X Standards: Depresses either the up (A) arrow or down (V) arrow push button on 3CHS*FK121 until a charging flow of approximately 55 gpm is obtained.
Comment: If the examinee questions which orifice isolation valve to open in the next step, provide the following cue:
! Cue::. . Open 3CHS*AV8149B -
8 I -
PERFORMANCE INFORMATION Facility: Millstone Unit 3 .
System: A71 JPM Number: NEW4 Task
Title:
RESPOND TO A PRESSURIZER LEVEL FAILURE Denote Critical Steps with an *X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade STEP 10 X Performance Step: OPEN 3CHS*AV8149B QB 3CHS*AV8149C, letdown orifice isolation valve B or C (MB3)
GRADE X Standards: Depresses the "open/ auto" push button for 3CHS*AV8149B (or 3CHS*AV8149C) and observes the indicating lights shift to green OFF, red ON. Then releases the push button, Comment: The examinee must carefully adjust the output on the controller in the next JPM step to avoid generating an overpressure situation in the letdown lines and lifting a relief valve While this occurrence will not result in a failure of the critical nature of the step it does not meet expectations of control board manipulations.
STEP 11 X Performance Step: ADJUST 3CHS*PK131, letdown low pressure controller, to maintain 350 psig.
GRADE X Standards: Depresses either the up (A) arrow and/or down (V) arrow push button on 3CHS PK131 as necessary to obtain a letdown header pressure of 350 psig.
9 L
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: A71 JPM Number: NEW-4 Task
Title:
RESPOND TO A PRESSURIZER LEVEL FAILURE .,
Denote Critical Steps with an "X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade j
STEP 12 Performance Step: PLACE 3CHS*PK131, letdown low pressure controller, to " AUTO" GRADE Standards: Depresses the " auto / man" push button on 3CHS*PK131 and observe the
" man" light goes out and the " auto" light comes on.
STEP 13 Performance Step: VERIFY 3CHS*FK121, charging header flow controller, is maintaining approximately 55 gpm (MB3)
GRADE Standards: Observes that charging header flow is approximately 55 gpm.
Comment: Based on PZR level, the examinee may request permission to leave 3CHS*FK121 in manual to maintain a lower flow rate to assist in restoring level, if this occurs or he appears confused about level restoration, provide the following cue:
^
- Cue: ' L. eave 3CHS*FK121_ in manual and e ' control charging flow as necessary to -
restore PZR level to the' programmed
- ; level and then shift FK121 to auto.
10 u-
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: A71 JPM Number: NEW-4 Task
Title:
RESPOND TO A PRESSURIZER LEVEL FAILURE Denote Critical Steps with an *X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade STEP 14 Performance Step: PLACE 3CHS*FK121, charging header flow controller, in " AUTO",
(MB3)
GRADE Standards: Depresses the " auto / man" push button on 3CHS*FK121 and observes the
" man" light goes out and the " auto" light comes on.
Comment: No action will be required for the next step, because excess letdown is not in service.
STEP 15 Performance Step: lE required, STOP excess letdown using Section 7.16 GRADE Standards: No action required.
STEP 16 Performance Step: Verify letdown heat exchanger outlet temperature has stabilized between d 70*F and 115'F using 3CHS-Tl 130 (MB3)
GRADE Standards: Observes the indication on 3CHS Tl 130 and determines that the temperature has stabilized in the allowable band.
11
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: A71 JPM Number: NEW-4 Task
Title:
RESPOND TO A PRESSURIZER LEVEL FAILURE Denote Critical Steps with an *X*
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade STEP 17 Performance Step: CHECK the following annunciator alarms are nolilluminated:
- LETDOWN FLOW HI(MB3A 3-4) l i
GRADE Standards: Observes that all of the annunciator windows listed are not lit.
STEP 18 Performance Step: VERIFY seal return flow is within the proper limits using OP 3301D, *RCP Operation *, Figure 9.2 GRADE Standards: Obtains a copy of OP 3301D and opens to Figure 9,2, Checks the differential pressure across the no.1 seal and uses that to determine the appropriate flow range for no.1 seal return flow Observes that the return
, flows are within the allowable range, 12
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: A71 JPM Number: NEW-4 Task
Title:
RESPOND TO A PRESSUR[ZER LEVEL FAILURE Denote Critical Steps with an "X"
' NOTE' Critical Steps must be completed correctly to achieve a satisfactory grade STEP 19 Performance Step: CHECK sealinjection flow to each pump is betweM 8 gpm and 13 gpm.
GRADE Standards: Observes seal injection flow indicators on MB3 and determines that all of the flows are within the allowable range.
Returns to AOP 3571, Attachment C.
Comment: If the examinee is uncertain as to where to go after competing section 7.33 of OP 3304A, direct him to step 4 of AOP 3571, Attachment C.
Comment: Since the examinee may have not yet determined that PZR level had been restored to normal, he should check this before returning the level controller to automatic. If level is not normal, provide the following cue:
(Cue: Complete step 5 of Attachment _C'and .
. then check level again.
STEP 20 Performance Step: Place PZR level controller in automatic.
GRADE Standards: Checks that PZR level has returned to its normal programmed level. If this is the case, depresses the " auto / man" push button on the PZR level controller and observes the " man" light goes out and the " auto" light comes on. If PZR levelis not in the normal range , adjusts 3CHS*FK121 as necessary to trend level back to its 13 L-
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: A71 JPM Number: NEW-4
- Task
Title:
RESPOND TO A PRESSURIZER LEVEL FAILURE l
Denote Critical Steps with an T l
' NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade programmed level.
Comment:- While checking plant conditions the examinee may recognize that the PZR control heaters have tripped off and request permission to reset them and turn them back on. If this occurs provide the following cue:
L Cue: Roset and turn on the "C" Bank of Pressurizer Heaters.
STEP 20 Performance Step: When conditions have stabilized, Observe MB annunciators and parameters, immediately report any unexpected or unexplained conditions to the Shift Manager.
GRADE Standards: Checks all the lit annunciators and checks PZR and charging / letdown parameters to determine if indications are acceptable. Reports to the SM/US that he has no unexpected or unexplained conditions.
Terminating Cue: The evaluation for this JPM is concluded.
Stop Time:
14
VERIFICATION OF COMPLETION Job Performance Measure Number:
- NEW-4 Revision: Q Date Performed:
Examinee:
Evaluator:
l I
Validated Time (min.): -15 Actual time to Complete (min.):
Result of JPM: (Denote by an S for satisfactory or a U for unsatisfactory)
Result of oral questions: Number of Questions:
Number of Correct Responses:
Score %
15
EXAMINEE HANDOUT INITIAL CONDITIONS AND INITIATING CUES JPM Tracking Number: NEMA initial C.ondliinna: A failure of the controlling pressurizer level channel transmitter (LT459) has occurred. The crew has taken manual control of the master pressurizer level controller and the charging line flow control valve controller (3CHS*FCV121). Plant parameters have been stabilized.
Initiating _Cuta: The US has directed you to perform steps 1 5 of Attachment C in AOP 3571.
16
C))
JPM Questions -
Question #1 Plant Conditions:
- The unit is at 100% power e The loop 1 spray valve sticks partially ope n Pressuriter pressure is decreasing slowly. All pressurizer heaters are energized, o All attempts to close the spray valve have been unsuccessful __
What actions would you recommend be taken at this time? -
I-Answer:
Trip the reactor because g:at r than P.8 Go to E 0 Transition to a 0.1 Trip the #1 and #2 RCPs ( it is acceptable for the examinee to state that he would trip the 2 RCPs immediately after tripping the plant in order to stop the pressure transient)
Reference:
AOP 3554 K/A APE 27 AK3.03 actions contained in EOPs/AOPs
1 JPM 050%)
Question #2 The Plant is in MODE 3 with a cooldown in progress in accordance with the appropriate procedure.
The following parameters exist:
- Pn Water Temperature 600"F
+
Pn Level RCS Ll462 (Cold Calibrated) 40%
Describe the relationship between
+
indicated Cold Calibrated Pn Level.
+
the indicated llot Calibrated Pn Level, and
+
Actual Pn Level -
Answer:
Indicated Hot Calibrated Level is greater than Actual Level which is greater than indicated Cold Calibrated Level.
REFERENCE:
OP 3208 Note prior to section 4.2.8, and Attachment 2 JUSTIFICATION: Note indicates that the llot calibrated channels always read higher than the Cold Calibrated channels.
Pn Level - DP, DPmax = Pref-Pvar = 0? If %p of Pu decreases, density ofliguld increases causing Pvar to increase.
Pvar increasing causes DP to decrease, which has a tendency to make level read higher than nomial.
K/A: 011 KS 05 2.8/3.1 0 11): 4870
______a
JPM New 3 Question #1 Excess letdown hasjust been placed in service using the loop 2 drain going to the VCT.
A small LOCA occurs in RCS loop 1. Pressurizer level and pressure are decreasing.
The crew is carrying out the actions for an RCS leak with 3CilS*FV121 fully open and 2 charging pumps running.
Pressure drops to 1850 psia and an automatic Si actuates.
What happens to the excess letdown lineup that was just established?
l Answer:
Only the seal return isolation valves 3CilS*MV8112 and 8100 close on the CIA signal (this is the safety significant part of the answer).
This will isolate excess letdown flow but the relief valve in the line will lift and re initiate flow, which will be directed to the Containment Drains Transfer Tank (CDTT). The
. excess letdown heat exchanger valves are inside containment and do not receive a safeguards signal. The air operated loop drain valve will eventually fail closed on the loss ofinstrument air to containment and'm will stop flow through the relief valve.
The expectation is that the candidate will he able to answer concerning the seal return isolation valves. The balance of the response is not required.
JPM New.3 Question #2 If the excess letdown flow is set too high for the current plant conditions, as indicated by excess letdown heat exchanger temperatures increasing, how will the following parameters also trend over time (consider the first trend of each parameter):
. Letdown lleat Exchanger Outlet Temperature VCT Level
- Pressurizer Level
- SealInjection Temperature Explain your answer.
Answer:
If excess letdown flow is high, then excess letdown heat exchanger outlet temperature will increase. You are removing more mass from the RCS than necessary. This will cause VCT level to increase and pressurizer level to decrease. The increasing temperature from the excess letdown heat exchanger will cause VCT temperature and seal injection temperatures to increase.
K/A 004 Al.06 Ability to predict changes to VCT level 004 Kl.34 Interface of CVCS and PZR control system l
l i
l JPM 083 Question #1 If an Cll) signal isolates RPCCW to the RCP motors, under what circumstances would you be allowed to restart an RCP without re-establishing RPCCW cooling and normal RCP restart conditions?
Answer:
While in FR C.1 an RCP can be started, if needed, in an attempt to reestablish adequate core cooling.
Reference:
FR.C.1 K/A EPE 006 EKl.3 Conditions and remedial actions associated with degraded core cooling.
JPhi 083 Question #2 in the conditions we provided for this JPM, is the failure to isolate containment a loss or i
potential loss of the containment barrier such that nn event classifico ion change should l be considered? Explain.
l Answer:
No. This does not constitute a loss or potential loss of the contalrtment barrier because no potential release path to the environment exists.
K/A 2.4.41. Knowledge of emergency classificatioas and thresholds.
4
l Jfht025 .
Question #1 What are the effects of the EDO frequency set being at 61 11Z instead of 6011Z when a large break LOCA occurs with a loss of off-site power?
i l
Answer: '
The diesel would start on the LOP or Si signal and have an out,ut frequency of 61 117.,
This higher frequer.cy will result in higher pump flow rates for the running pumps,
JPM 025 Question #2 You have just placed the manual start switch on MB8 for the "A" EDG to the "stop" position after a surveillance test. The diesel is not carrying any loads and goes into its 140 -
second shutdown sequence. A loss ofoff site power occurs, How will the "A" EDG respond?
--Answer:
I: The "A" EDG will come out of the shutdown sequence, start in the emergency start sequence and load as designed (the emergency start relay contacts will de-energize the shutdown solenoids and allow the EDG to start)
. K/A 064 K4.10 Automatic load sequencer ops.
JPM 025
__ Question #3' What are the conse?;ences, if the mode selector switch is left in the " parallel" position and an SI signal occurs due to a small break LOCA7 ANSWER:
The unit parallel switches are over-ridden during an auto start of the diesel by an LOP SIS or CDA signal. The switch position will have no impact on the diesel's ability to run under the emergency conditions.
K/A 064 K4.06 9 peed Droop Control l
f l
l l
.- a
~-JPM 025 Question #i What would be the consequences, if while reducing load as part of the sequence to shutdown the diesel, you inadvertently reduced load to 75MWe instead of the required 200 - 400 MWe Answer:
Tne EDG would trip on reverse power.
K/A 064 A1.08 Maintaining minimum load to prevent reverse power.
4
., . =- -
4
JPM 113 -
-: Question #1 The RPCCW system is aligned for Mode 1 operations. The "A" RPCCW pump trips on overcurrent and cannot be restarted. What actions must be taken in order to comply with Technical Specifications?
Answer:
(if the candidate provides only the "A" response provide the cue: The "A" pump cannot be restored in 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />)
A. Ylie "A" pump must be restored to service within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. OR B. Tlic C" pump and heat exchanger must be aligned to the "A" tra'in within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
K/A 2.l,'33 Ability to recognize entry conditions for Technical Specifications.
JPM 113 Question #2
!)oth the "A" and "I3" RPCCW pumps are running under normal circumstances. The "C" pump is aligned both mechanically and electrically to the "B" train with its control switch in the " auto" position. A small break LOCA results in low pressurizer pressure, a reactor trip / safety injectica and the "A" RPCCW pump trips on overcurrent.
Given the above conditions, what will be the status of the RPCCW pumps?
Answer:
The "B" pump will continue to run. The "C" R.PCCW will remain in a " backup" mode and will not be running.
K/A 006 A3.08 Actions associated with RPCCW on an Si
. . .. -. _ = . . . - . -
t i
t JPM-006 Question #1 A. What are three possible sources of power to inverter 17 answer:
Normal MCC via rectifier to the inverter Backup DC supply MCC via Battery charger to DC bus to inverter Backup Battery to DC bus to inverter l
I
JPM 006 Question #1 B. What single indication could an operator use to determine which source is supplying power to theInverter? Explain.
Use inverter DC input voltage:
Normal rectifier output is about 140 VDC Charger output is about 132 VDC Battery output is about 125 VDC lt is not necessary that the candidate know the voltage numbers. It is important that he knows there is a difference.
... .. J
JPM 006 !
Question #21 A 480V load center supply breaker has lost control power.
- a. Ilow would you open the breaker?
- b. After it is open, what do you have to do to reclose it?
- Answer:
- a. The breaker could be locally opened using the manual trin push button.
- b. Without control power, the ' closing springs will not charge when the breaker opens. The
- operator would manually charge the closing springs and then use the manuni close lever.
REFERENCE:
OP3345C and OP3370B i
I
JPM-019 Question #1 -
Assume the crew is still responding to a loss of secondary heat sink, efforts to restore AFW have been unsuccessful.
Wide range steam generator levels in "A", "B", and "C" steam ger.erators are 32%
Wide range steam generator level in "D" steam generator is off scale low because it is faulted, CETs are 510*F and stable RCS pressure is 2350 psia Containment temperature is 170 *F What is the next recovery action the crew would take?
answer:
Attempt to restore Main Feedwater
REFERENCE:
F R H .1 9 JUSTIFICATION: The methods, in order, of recovery in FR-H.1 AFW flow Main Feedwater Condensate Bleed and Feed Bleed and Feed is initiated if:
3 Steam generators less than 27 % (57% adverse- n/a)
Pressurizer pressure greater than or equal to 2350 psia due to loss of ,
secondary heat sink indicated by core exit TCs increasing.
(the reason pressure is high is the pressurization from ECCS after the D steam generator blows down).
K/A: EPE E05 EA2,1 i
l
_ _ . _ _ _ _ _ _ _ _ _ _ __j
. JPM-019 Question #2 If both MDAFW pumps are in LOCAL control, which Motor Driven AFW pump (s), if any, will start on Lo Lo Steam Generator Level?
answer:
-The "B" MDAFW pump will start.
REFERENCE:
LSK-6.2-1 A, 6.2-l H JUSTIFICATION: In LOCAL, the "B" pump will still receive a start signal from any of the Automatic start signals, the "A" pump will not receive an automatic start.
K/A: 061 K4.02. 4.5/4.6
JPM 042 Question #1 With the initial conditions given for this JPM, what would be the "B" train response if, instead of taking the 34B.34D bus tie breaker to "CLOSE", the operator had taken the "B" EDG output breaker to "OPEN"?
answer:
no response, the EDO breaker would not open.
REFERENCE:
LSK-9.2B JUSTIFICATION: With the LOP signal present, the breaker cannot be opened by the operator.
K/A: APE 056 AA2.14 4.4/4.6 U
I 1
l l
JPM-042 Question #2 A recent plant change has replaced the EDG air operated jacket water temperature control valves, (3EGS' AOV43A/B) with self contained, thermostatically controlled temperature control valves, (3EGS*TCV50A/B).
What was the safety signficance addressed by replacing the original valves with a new design?
Answer:
The FSAR (Section 9.5.6) statet, that the Seismic Category 1 air receivers serving the EDG's are of sufficient capacity to start the EDG's and operate the engine controls for at least 7 days.
In fact, in a loss of electrical power event (and not taking credit for the EDG air compressors),
the control air demand for the jacket water temperature valve would limit the air receiver capacity to approximately one day.
In addition, the temperature control loop for the old air operated valve is non-QA.
An additional benefit of installing the thermostatic valves is less run time on the air compressors.
REFERENCE:
DCR M3 96076; Replacement of EDG Jacket Water TCV, Shift Brief SB3-96-026 JUSTIFICATION: (Background information)
The new valve body is the same size and configuration as the 5* AOV valve being replaced. It operates in the same manner as the intercooler thermostatic valve and the lube oil thermostatic valve in the other EDG cooling systems. The new valve contains a thermal element located inside the valve casing. This element responds to the temperature of the medium surrounding it and provides the force necessary to position the internal poppet valve, as the temperature of the liquid passing through the valve changes.
This replacement will not affect the operability of the EDG's. The new thermostatic 3-way temperature control valve accomplishes the same function as the removed AOV, that is, it controls the amount of jacket water flow that diverts around the Jacket water heat exchanger, depending on jacket water temperature. In standby, the EDG Jacket Water Cooling System continuously operates between 115 - 135 F, with the new thermostatic valve in the full bypass position (no cooling flow to the heat exchanger). Upon engine startup, the thermostatic valve continues to bypass flow around the jacket water heat exchanger, until jacket water return temperature approaches 137 - 141'F, where it starts to open. As jacket water temperature increases, the thermostatic valve will begin to direct more flow to the heat exchanger, until an a
equilibrium is established. If the Jacket water heat load increases and jacket water temperature reaches 160*F, full flow will be directed through the heat exchanger.150*F (setpoint) represents mid-stroke position of the valve. Therefore, the TCV will control temperature in a
. range between 140 - 160'F, depending on service water temperature, in addition, all pneumatic and electrical corr.oonents of the old AOV controlloop have been removed, including:
Temperature Controlle* (3EGS TIC 43A/B)
Temperature Transmit er (3EGS-TT43A/B)
Pressure Control Valv9s (3EGA-PCV30A/B, 32A/B)
Pressure Relief Valves (3EGA-RV31 A/B, 33A/B)
Excess Flow Valve ((3EGA*EFV29A/B)
The control air supply line is capped downstream of the header valves,3EGA*V969 and 3EGA*V968.
i K/A: 064 A4.05 3.9/3.9 l
l
JPM 50 Question #1 -
The following plant conditions exist:
The Unit is operating at 100% power
+
Pressurizer pressure control is in automatic
+
One set of backup lleaters is energized -
h Actual pressurizer pressure is 2250 psia L
- The pressurizer Master Prsssure Controller malfunctions and the setpoint is step changed to 2200 psia, s Which of the following describes the initial automatic responses in the pr ssurizer Pressure Control System as a result of this failure?
4
- answer:
Spray Valves open, pressurizer heaters turn off.
REFERENCE:
Process Drawing Sheet 26 Functional Drawing Sheets 11 & 12 4 JUSTIFICATION: If the setpoint changes to 2200 psia, then the controller will take action to bring pressure to setpoint. At 50 psia below current pressure, the heaters will turn off, the spray valves will open, the PORVs will remain closed because their setpoint is 100 psia above setpoint.
K/A: 000027.EA2.03 3.3/3.4 010 GEN 07 3.4/3,4 010 K6.03 3.2/3.6 1
?
JPM 50 Question #2 The Plant is in MODE 3 with a cooldown in progress in accordance with the appropriate procedure.
The following parameters exist:
Pa Water Temperature 600 F Pn Level RCS-Ll462 (Cold Calibrated) 40%
Describe the relationship between indicated Cold Calibrated Pn Level, the indicated 110t Calibrated Pn Level, and Actual Pn Level Answer:
Indicated Ilot Calibrated Level is greater than Actual Level which is greater than indicated Cold Cailbrated Level.
REFERENCE:
OP 3208 Note prior to section 4.2.8, and Attachment 2 JUSTIFICATION: Note indicates that the llot calibrated channels always read higher than the Cold Calibrated channels.
Pn Level = DP, DPmax = Pref-Pvar = 0%, if temp of Pn decreases, density ofliguid increases causing Pvar to increase. Pvar increasing causes DP to decrease, which has a tendency to make level read higher than normal.
9 K/A: 011 K5.05 2.8/3.1 OBJ: 4870
jyM 055 ~
Question _#1 A caution prior step 3 of Fn-Z.1 informs the operator not to perform steps 3,4 and 7 if ECA 1,1 is in progress, What is the basis for this caution?
answer:
recirculation flow is not available and it is very important to conserve RWST water, if possible, by stopping containment spray pumps.
REFERENCE:
Westinghouse background for FR-Z.1, step 3 Caution JUSTIFICATION: This cautions wams the operator that the operation of the containment i
spray pumps indicated in guideline ECA 1,1 takes precedenc e over that
- noted in step 3 of this guideline. This guideline specifies maximum L
available heat removal system operability in order to reduce containment -
pressure. Guideline ECA-1,1 uses a less restrictive criteria, which permits reduced spray pump operation depending on RWST level, containment pressure and number of emergency fan coolers operating The less restrictive criteria for containment spray operation is used in guideline ECA 1,1 since recirculation flow to the RCS is not available and it is very important to conserve RWST water, if possible, by stopping containment spray pumps.
K/A: EPE El1 EK3.2 I
l JPM -055 Question #2 LTrisodium Phosphate baskets have been placed in the containment. What is the purpose for these baskets?
Answer:
To maintain the pH in the containment sump at 7,0 or higher to limit the iodines released from the water in the sump in die event of fuel failure. The higher pil also prevents stress corrosion craking of austentic c,tainless steel components in containment,
REFERENCE:
System text and Technical Specification Bases B3/4-14 K/A: 026 K4.02 s
JPM-109 - ,
- Question #l-Why is the alternate power supply to MCC32 lZ (3NiiS MCC9Al),"SBO Diesel MCC" only-used for testing?
(NO references are allowed)
Answer:
The alternate supply is not capable of carryssa 11 the SBO loads
REFERENCE:
OP3346D, basis JUSTlFICATION: Basis Information Normal supply by backfeed is preferred due to the alternate source being l
undersized and not capable of carrying all of the SBO diesel load requirements during SBO diesel operation.
K/A; ' 064 - Kl 01 4.1/4,4--
JPM 109 Question #2 The SBO diesel is the sole source of AC power when the STA reports the CSF status tree for lieat Sink is RED.
What action should the crew take?
answer:
The crew should not address the RED path (no action). The CSF status trees assume an emergency bus is energized from offsite or by an emergency diesel generator. While the SBO is the source of power, the status trees are used for information only. Therefore, the crew should continue in the current procedure.
REFERENCE:
ECA 0.3 JUSTIFICATION: NOTE at entry into ECA-0.3 l
"The CSF Status Trees should be monitored for information only. Other l
' functional Response procedures shall NOT be implemented prior to restoring power to an AC emergency bus from offsite or an emergency diesel generator."
K/A: EPE 055 EK3.02 4.3/4.6 .
I
1 i- , _ JPM.137 Question #1 -
[ What automatic actions occur in the Charging Pump Cooling System on a safeguards actuation signal?
l J
answer:
On receipt of a Safety injection Signal (SIS) or a Loss of Power (LOP) signal, the charging pump cooling pump suction and discharge cross-connect valves close and the standbv numn starts, creating two independent flaw paths.
REFERENCE:
OP3330D, LSK 9.4A, B, D -
- JUSTIFICATION: Si or LOP will start the pump, closes 3CCE* AOV26A (B) 1-1
{.
JPM 137 Question #2 Describe what actions, if any, would have to be taken if the thermal overload actuated during the operation of the Charging Pump Miniflow Isolation Valve,3CilS*h1V8110 for the following two conditions:
- a. Valve is stroking closed after the operator pressed and released the "close" push button.
- b. The valve is stroking due to a Safety injection Actuation Answer: '
- a. MOVs will normally stroke to the demanded position once the control switch push button is pressed and released. For this valve, once the thermal overload actuates it will stop stroking.
Tht. operator can close the valve by holding the "CLOSE" push button until the valve is in the l closed position (the push button bypasses the overload contact).
- b. For an Safety injection actuation signal the thermal overload contact is bypassed.
Consequently the valve will continue to stroke to its demanded Si positio i.
REFERENCE:
ESK 6PE, TRM Table 3.8.4.2.1-1, P&lD 104A, Current Events 96-7 JUSTIFICATION: MOVs, such as MV8110, which are required to go open/close on receipt of an accident signal have a bypass line which continues to power the applicable relay despite a thermal overload. The valve can be operated by the operator, if necessary, by holding the applicable open/close push button until the valve reaches the desired position.
K/A: 004 K6.14
__ J
l l
NEW - 05 Question #1 While repressurizing the containment to atmosphere, why is the operator cautioned not to open 311VU*CTV32A or 311VU*CTV32D?
(No references are allowed)
Answer:
The operator is cautioned not to open the valves to prevent damage to the ventilation ductwork.
REFERENCE:
AOP 3568 JUSTIFICATION: Caution in the AOP wams the operator damage will occur to the ductwork if the valves are open during repressurization, IUA: 103 A2.05
l-L - ' NEW -5 - --
l Question #2 Following a Safety injection actuation, what should be the lineup for the: -
+- SLCRS fans, FN 12A and B
+
- Auxiliary Building fans, FN-6A and 6B -
I- +- Charging Pump room fans, FN 13A and B and 14 A and B?
1 Assume all equipment operates as designed.
answer:
Both fans 12A and 128 should be running.-
Auxiliary building fan 6A is the lead pump and will be running One train,13A and 14A or 13B and 14B will be running (A is preferred).
REFERENCE:
LSK 22-1 A - 221 AA JUSTIFICATION: SI will open the dampers for each SLCR fan and both will start.
The 6A and B fans are set up to start. The 6A fan first, then the 6B if the 6A fan does not start.
13 and 14 fans will nm; whichever train is running will continue to run.
The A is the preferred train.
.K/A: 013 Kl.13 2.8/3.1 ,
.i
( '.
NEW-1 Qcestion #1 The crew is about to perform a startup from COLD SHUTDOWN.
. The operatar notices the " Auto St Blocked" permissive on MB4D is lit.
Whe.t action would have to be taken to clear the annunciator?
(No references are allowed)
- Answer:
Cycle the reactor trip breakers.
REFERENCE:
Westinghouse functional sheet 8, LSK 27-17A
-JUSTlFICATION: lThe permissive indicates that automatic Si is blocked, which occurs
- following the SI reset timer timing out (60 seconds) and P-4 present.-
When the operator goes to reset, (momentary contact), auto Si actuation (for each train with P-4 present)is blocked. Cycling the trip breakers will
- break the signal and reset the permissive and the circuitry to reset the system for automatic SI actuation.
K/A: 006 K4.11 3.9/4.2
__m___m_m.
L NEW-li- .
[ Question #2-SSPS testing is in progress while the plant is at 50% power. The technician makes an error and one train of Si is actuated.'
The STA recommendr not actuating the other train of SI because it is not needed to satisfy the -
minimum safety function requirements and it will extend the time the crew must spend in recovering from the inadvertant Sl? :
Do you agree with this recommendation? Why or why not?
' Answer:
' No. The opposite train should be actuated so a full actuation of Si occurs.
REFERENCE:
OP3272, attachment 3 iJUSTIFICATION: '
If a licensed operator observes that a safety signal actuation should have occurred or is required to place the plant in a safe condition, the operator shall communicate the pertinent plant conditions and intention to take-action to the SM/US and then manually initiate the required safety signal.
If the manual safety signal initiation does not result in the proper safety system actuation, the licensed operator shall then manually operate the
. associated equipment to establish the required safety function.
However, when performing steps 5 -14 ' of E-0, and a safety _ signal or component is observed to not have actuated or to have only partially.
actuated, a licensed operator should take action to manually initiate the safety' signal or, in the' case of a failed component, manually place the component in its required safety condition.'
K/A: 1006 A2.13
1 New-4
~ Question #1 The letdown relief valve opened while attempting to place letdown in service. The relief valve failed to rescat, What are 3 seperate indications that would alert you to this failure.
' ANSWER:
Any 3 of the following: '
- l. Indicated Letdown flow decreases.
2, VCT level decreases
- 4. 3CilS-131, letdown line pressure control valve, ivould be closed more than expected, . -
5, 3CilS 130, letdown temperature control valve, would be throttling closed to maintain temperature.
- 6. Annunciators for the reliefline temperature and PRT parameters would be received and stay in.
Reference:
P&lD 104A,102F
'K/A: 004 K1.08; 004 K4.11 d
i
4 New-4 Question #2 What is the expceted plant response, over the next 30 minutes, if TE 130, Letdown Heat i Exchanger Temperature Element, fails low?-
Answer:
The RPCCW temperature control vlave,3CCP*TV172) will close.
Letdown temperature will increase, When TE129 reaches its setpoint letdown will be diverted to bypass the demineralizers and the .
letdown filter,
Reference:
P&lD 104A,104C and 121B K/A: 004 K6,09; 004 A4.11 ,
4
Administrative Toolcs Outline Facility: hiillstone Unit 3 Date of Examination: Week of 7/7/97 Examination Level: SRQ Operating test Number:
Administrative Tenic/ Subject Description hiethod of Evaluation:
A.1 Conduct of Operations
.1
- 1. Given a set of conditions (i.e. equipment JPhi tagged out, Technical Specification issues, etc.) review the shutdown risk assessment g
forms for the day that were completed by the RO. (K/A 2.1.28, SRO: 3.3)
- 2. The use and requirements of a dedicated 2 Questions operator. (K/A 2.1.4, SRO: 3.4)
- A.2 Eauipment Control
- 1. The process for making configuration 2 Questions changes. (K/A 2.2.14, SRO: 3.0)
A.3 Radiation Control
- 1. -At the RCA access point, be able to explain 2 Questions radiation hazards in the area entering, radiation work permit information and radiation control. (K/A 2.3.7, SRO: 3.3)
A.4 Emercency Plan f
- 1. Compete an E-Plan classification for JPhi
- a simulator scenario.
(K/A 2.4.41, SRO: 4.1)
[
u
1
?
i
- JOB PERFORMANCE MEASURE WORKSHEET -
f j
4 l - JPM
Title:
SHUTDOWN RISK ASSESSMENT FORM REVIEW 1
! ID Number: NRC.NEW Revision: 0
} '
i I 11. Inittsted: '
1 !
1 i R L Lueneburg 5/28/97
- Developer Date 4
i 1 ,
l 111. Reviewed:
i i
a a
- Technical Reviewer Date l
j +
J j Instructional Reviewer - Date i
1 4
1
- IV. Approved
- - -
i i' -l 1
I Operations Manager Date Nuclear Training Supervisor Date e
1
JOB PERFORMANCE MEASURE WORKSHEET Facility: Millstone Unit 3 Examinee:
JPM Tracking Number: NRC NEW Validation Time: minutes Task
Title:
SHUTDOWN RISK ASSESSMENT FORM REVIEW Time Critical Task: ( )YES ( X ) NO Task Number: 119"047*0Z02 K/A Number: 2123. K/A Rating: 3.2/3.3 Acolicattle_ Methods of Testing; Simulate Performance Actual Performance X Classroom Simulator X Plant X 1
Task Standardt Satisfactorily conduct a review of a shutdown risk assessment i
form based on a set of plant / equipment conditions.
Required _Maledalt Completed Shutdown Safety Assessment Checklist, Form 3260A-4 l
General
References:
OP 3260A, Rev.10 READ TO THE EXAMINEE I will explain the initial conditions, which step (s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objectives for this JPM will be satisfied.
You may use any approved reference materials normally available in the Control Room, including logs. Make all written reports, oral reports and log entries as if the evolution was actually being performed.
Initial Conditions: The following plant conditions exist:
The plant is in Mode 5, all RCS ioops are full, RCS pressure is 325 psia and RCS temperature is 165'F.
It is the start of the day shift The calculated shutdown margin boron is 2050 ppm Train *B" electric plant outage The SBO diesel is OOS for adjustments to the governor The "A" RHR pump is running for decay heat removal The last boron concentration sample was 2510 ppm Both shutdown margin monitors are operable An oil replacement on the "C" charging pump will be completed at 10:30 AM 2
JOB PERFORMANCE MEASURE WORKSHEET The "A* SlH pump is OOS for bearing replacement.
Preparations are being made to open containment for the first time this outage. No access doors / openings are currently open, time to core bolling is 35 minutes Tiie A, B, and C SGs narrow range levels are at 48%,55% and 65% respectively. The D SG is drained down in preparation for secondary side entry. The *A" MDAFW pump is available for feed flow. The AFW cross connect valves are tagged closed.
PZR level is 88% on the cold calibrated instrument The "A" SFC pump is running with a pool level of 24'6" above the fuel No work is being performed on the NSST or RSST RWST level is 1,180,000 gallons and 3RHS*V43 is locked closed and tagged SP 3604C,6 was completed last night on the mld shift i
Initiating cuts: The RO has completed the Shutdown Safety Assessment Checklist.
You are to conduct the required review.
I 3
PERFORMANCE INFORMATION Facility: Millstone Unita System: ADMIN JPM Number: NRC NEW Task
Title:
SHUTDOWN RISK ASSESSMENT FORM REVIEW Denote Critical Steps with an *X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade 1
Start Time:
STEP 1 Performance Step Obtains a copy of OP 3260A to use in reviewing the shutdown safety Assessment Checklist.
GRADE Standards: Locates the appropriate procedure H volume and opens it to OP 3260A, section 1.2 Comments: The examinee may skim section 1.1, General Requirements.
Comments: The standards in this JPM refer to the applicable sections of OP3260A that the examinee may refer to in the process of the review. Checking these sections is not required to complete the critical nature of the step.
STEP 2 X Performance Step: Checks section I, RCS Decay Heat Removal.
GRADE ~~
X Standards: Verifies that the RO appropriately checked the RHR Train A block and no others. "B" RHR is not available due to the train electrical outage. All conditions for natural circulation are not met because both "A" side SGs are not available("D" SG drained down). Refueling has not commenced; cavity is not >23' RCS totalis 1, 4
_ _ _ _ _ _ _ _ - - . - - J
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: ADVIN JPM Number: NRC NEW Task
Title:
SHUTDOWN RISK AS.SESSMENT FORM REVIEW Denote Critical Steps with an "X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade ORANGE condition. Used Sections 1.2 and 1.8 as a reference to determine the criteria.
The RO also circled N/A for available racked down charging pump.
STEP 3 X Performance Step: Checks section 11, SFC Decay Heat Removal GRADE X Standards: Verifies the RO appropriately checked SFC Train A and >23' poollevel above the fuel. The "B" train of SFC is not available due to the train electrical outage. The SFC totalis 2, YELLOW condition. Used section 1.8 as a reference, STEP 4 X Performance Step: Checkt. section Ill, inventory GRADE X Standards: Notices that the RO inappropriately checked SlH Train A. Train *B"CHS pumps and SIH Train *B" are not available due to the electrical outage.
Also balb RHR pumps are not available due to the "B" train electrical outage making the *B" RHR pump not available. RO had total as 2, YELLOW
, condition. The total should be 1, Orange condition. The RO appropriately checked the boxes for RWST level and 3RHS*V43. Uses sections 1.3 and 1.8 as reference.
5
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: 6 Die JPM Number: NRC NEW Task
Title:
SHUTDOWN RISK ASSESSMENT FORM RE\' JEW Denote Critical Steps with an *X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade STEP S X Performance Step: ChecksSection IV, Power Availability GRADE X Standards: Verifies that the RO appropriately l
' checked A EDG, RSST and NSST/ Main. The *B" EDG is unavailable due to the electrical l
outage and the SBO is being serviced.
The Power Availability totalis 3, YELLOW. Uses sections 1.5 and 1.8 as a reference.
STEP 6 X Performance Step: Checks section V, Reactivity GRADE X Standards: Verifies that the RO checked all of the boxes and listed inventory flow paths as 1 (Charging pump *A") even though he had checked inventory boxex as 2.
The Reactivity totalis 4, YELLOW condition. Uses sections 1.6 and 1.8 as a reference.
-STEP 7 X Performance Step: Checks section VI, Containment GRADE X Standards: Verifies that the RO checked the box for Containment Closure set. The Containment totalis 1, GREEN condition. Uses sections 1.4 and 1.8 as a reference 6
_ = . ..
A
PERFORMANCE INFORMATION 1 Facility: Millstone Unit 3 System: ADMIN JPM Number: NRC NEW Task
Title:
SHUTDOWN RISK ASSESSMENT FORM REVJEW Denote Critical Steps with an T
' NOTE
- Critical Steps must be completed correctly to achleve a satisfactory grade STEP 8 X Performance Step: Checks section Vil, PZR Surge Line Flooding GRADE X Standards: Verifies that the RO has initialed rad dated the line opposite the Total pressurizer vent path are equal to or less than 6 sq. in.
STEP 9 Performance Step: Report the completion of the review of the Shutdown Safety Assessment Checklist.
GRADE Standards: Informs the examiner that he has completed the review of the Shutdown Safety Assessment Checklist and that the RO made an error in completing section lil, inventory. The Train A CHS PP A/C and associated flow path should not have been credited. The total for the section is actually 1, ORANGE condition.
Terminating Cue: The evaluation for this JPM is concluded.
Stop Time:
7
.i
VERIFICATION OF COMPLETION Job Performance Measure Number: NRC NEW Revision: 0 l
Date Performed:
I i
Examinee:-
1 Evaluator: ,
Validated Time (min): Actual time to Complete (min):
Result of JPM: (Denote by an S for satisfactory or a U for unsatisfactory)
Ret uit of oral questions: Number of Questions:
1 Number of Correct Responses:
Score %
4 8
. ... . _=J
l EXAMINEE HANDOUT INITIAL CONDITIONS AND INITIATING CUES JPM Tracking Number: NRC NEW Initial Condillona: The following plant conditions exist: l The plant is in Mode 5, all RCS loops are full, RCS l pressure is 325 pela and RCS temperature is 165'F. l It is the start of the day shift The calculated shutdown margin boron is 2050 ppm Train "B" electric plant outage The SBO diesel is DOS for adjustments to the governor The "A" RHR pump is running for decay hent removal ,
The last boron concentration sample was 2510 ppm Both shutdown margin monitors are operable An oil replacement on the "C" charging pump WHI be completed at 10:30 AM The "A" SlH pump is 005 for bearing replacement.
Preparations are being made to open containment for the first time this outage. No access doorslopenings are currently open. Time to core bolling is 35 minutes The A, B, and C SGs narrow range levels are at 48%,
55% and 65% respectively. The D SG is drained down in preparation for secondary side entry. The "A" MDAFW pump is available for feed flow. The AFW cross connect valves are tagged closed.
PZR level is 88% on the cold calibrated instrument The "A" SFC pump la running with a pool level of 24'6" above the fuel No work is being performed on the NSST or RSST
) -
RWST level is 1,180,000 gallons and 3RHS*V43 is locked closed and tagged SP 3604C.6 was completed last night on the mid shift I
Initiating Cues: The RO has completed the Shutdown Safety Assessment l Checklist. You are to conduct the required review.
9
Form Approval 1 2 n ' N 2r -7/r U
" S' "' '
g QMfdl 0 81997 "jj8j Forib Coves heet Generic Information 1 ["
Form Trtle Rev. No.
Shutdmvn Safety Assessment Checklist 10 Reference Procecure Appbcable Tech. Spec.
Frequency 3260A N/A
- This form is being used for the following:
O Teen spec surveiii.,c. O system Alignment Shutdown Risk Management
@ Other:
Q Maintenance Restoration Q Non-Tecn Spec (Retest) Survoit!ance (PM)
Speelfle information 1
References:
l Remarks:
' Daily and prior to removing any system required to support Key Safety Systems during MODE 5,6, and O.
Reviewed By: Date:
SRO OPS Form 3260A-4 Rev.10 Page 1 of 5
'Afn
- WL - ktGL)
Shutd:.wn S:fety Assessment Checklist Date: dne, Time: AJ Protected Train (s) A / B (circle one or both) Check If a single train exception in effect O l
- l. RCS Decay Heat Removal Decay Heat Removal (RCS)
RHR Train A (1) f TOTAL CONDITION O RHR Train B (1) 0 Red O All conditions satisfied 1 to support natural circulationin the RCS (1) 2 Yellow 0 > 23' refuei cavity (1) 3 o,een l RCS Total NA for Mode o
/
Available racked down charging pump: A / B / C(0) / C(P) heircle one) l
- 11. SFC Decay Heat Removal Decay Heat Removal (SFC)
TOTAL CONDITION O SFC Train B (1) 0 I Red
> 23' poollevc! above the fuel (1) 1 Orange SFC Total 7,,
2 3
b Green 111. Inventory inventory g Train A CHS PP NC and associated flow path (1) l TOTAL CONDITION 0 Train B CHS PP B/C and 0 Red associated flow path (1) 1 Orange
[ SlH Train A, aligned to RWST with - 2 h
either hot leg or cold leg injection path (1) l 3-5 Green O SiH Train B, aiionedio RWST with NA for Mode 0 either hot leg or cold leg injection path (1)
O Both RHR trains available for DHR and both capable of alignment to the RWST (1)
Inventory Total 1 Verify RWST level > 250,000 gallons .
3RHS*V43 RHR to RWST recirculation isolation tagged and locked closed. I OPS Form 3260A-4 Rev.10 Page 2 cf 5
, __o
G P w . M.tt - H e13 Shutd:,wn S:fety Assessment Checklist Date: -Ts w a Time: Nou)
IV. Power Availability Power AVallability Need at least one offsite source, one EDG, and one other.
A EDG (1) I DITION O BEDG(1) 0-1 Red I
j RSST (1) 2 Orar ge I
B NSST/ Main (1)
O Station Blackout EDG(1) 3 Yellow Power Total 3 V. Reactivity
, _ Reactivity
@yRCS Boron > required SDM (1) l IDIAl. CONDITION
@ Inventory flow paths (0-2) l 0-2 Red 9 Q At least one Shutdown Margin Monitor train "9' available (1) I 4
G Dilution paths tagged using SP 3604C.6 (1) l 5 Green NA for Mode 0 Reactivity Total VI. C tainment Containment Containment Closure set (1) CDEDITION O Containment Ciosure set witn exceptions tracked and capable of being cbsed prior o Red to the more restrictive of: (1) 1
+
Time to core bolling 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> NA for Mode 0 Containment Total /
Vll. FZR Surge Line Flooding One of the following conditions exist: ww, o.1, Reactor vesselhead removed /
Reactor core refueled or decay heat insu'ficient to cause surge line flooding /
Total pressurizer vent path area equal to or less than 6 sq in. ^ jM OPS Form 3260A-4 Rev.10 Pace 3 of 5
. . _ _ . . _ - . _ . __ ~ _ __ _
Administrative Topic Outline for SRO A.1 Conduct of Onerations The use and requirements of a Dedicated Operator Question: The plant is in Mode 1 at 100% power. The service water ventilation to the "A" train service water pumps must be shut down for 5 minutes to shift ventilation from summer to winter mode. The fan does not receive an automatic start signal. There is not a PORC approved procedure to do this task. Can a licensed operator not on shift be stationed at VPl as a dedicated operator to allow the fan to ineet Technical Specification operability requirements.
Answer: Yes. OP3260 scetion 6.17.2 states that a dedicated operator who is used to satisfy a Tech Spec operability requirement may only be posted in accordance with a PORC approved procedure, in the event that the task to be performed is a single, simple action with in the general responsibilities, skills and training of the operator, and does not replace an automatic function, this Conduct of Operations procedure shall be deemed to constitute the PORC approved procedure for the purpose of posting a Dedicated Operator.
Administrative Topic Outline for SR0 A.1 Conduct of Operations The use and requirements of a Dedicated Operator Question: Once it has been determined that it is appropriate to use a Dedicated Operator for a specific task. What things would be appropriate for the SM to brief the Dedicated i Operator on prior to assuming the position. ( List 3 things) l Answer: LAW COP 200.1 Section 1.22 i e
" In the event of an emergency, the primary function of the dedicated operator is to I restore the equipment to its proper safety alignment and to inform the SM/US.
e The dedicated operator shall remain in the vicinity of the assigned equipment or control panel at all times.
e if the dedicated operator must leave the assigned area, another qualified operator who has been briefed on the Dedicated Operator responsibilities shall relieve the dedicated operator l The deJicated operator shall not be assigned other duties concurrent with the dedicated operator role except performance of surveillance or operating procedures which involve assigned equipment A dedicated operator stationed outside the control room shall have the ability to expediently communicate with the control room Any steps that must be performed if the safety function shall be restored"
F A.2 Eauinment Control The process for making connguration control Question #1:
Ifit is necessary to lock a component for a short period of time, what information is required to be docummented on the Shih Turnover Report? (list 4 items)
-Answer #ti i
j- - OP 3260B, Equipment Control, requires the following information be documented on the l Shin Turnover Report;
- Component ID Position
- h10DE Information stating why the component is locked Infomiation stating what conditions must ne satis 0ed to remove restraining device from component When applicable, the following information is also documented on the Shih Turnover Report:
SM authorization for placement of restraining device SM authorization for removal of restraining device When a component is temporarily locked, that component must be evaluated for addition to locked component list and, if required, a change to OPS Form 32608 1 and appropriate OPS Forms is submitted,
I A.2 Equipment Control The process for making configuration control Question #2 What is the proper method for verifying the position of a locked open manual valve that has no slack in the restraining device?
Answer #2 OP 32608. Equipment Control, Attachment 3 provides the following guidance:
Remove the restraining device and then use the method for a non lc ked valve Turn valve handwheel in close direction to confinn that the valve was open Turn valve handwheel in open direction until the valve is fully open Close the valve 1/4 tum Restore the restraining device
(
i J
I A.3 Radiation Control Knowledge of radiation exposure limits and contamination control, including permissible levels in excess of those authorized.
Applicable references available at the RCA may be used to answer this question.
l Question #1 '
l
=
You have been sent to the auxiliary building to complete some tagging. One of the tags that you must hang requires you to enter a Tech Spee Locked liigh Radiation Area. What requirements must be met for you to make this entry? Assume the radiation levels and the time to complete the job will are low enough that you will not exceed any personnel exposure limits.
Answer:
Check Radiation Work Permit #', job step 2 of 4.
Must contact ilP for a PRE-JOB Brief and latest survey data The !!P briefing shallinclude: '
Digidose alarm setpoint and Stay Time Control /Retum ofIIR 2 Key Survey meter, alarming dosimeter or continuous 11P coverage required for entry into Tech Spec Locked liigh Radiation Areas.
_ _-_a
I l
A.3 Radiation Control Knowledge of radiation exposure limits and contamination control, including permissible levels in excess of those authorized.
Question #2
-If you were sent to the Auxiliary Building to replace a filter that was in a housing that had a contact dose rate of 450 mrem /hr and you expected to receive a dose to your extremity of125 mrem and a whole body dose of 20 mrem, what specialinstructions must be met.
Answer:
Check Radiation Work Permit 5, job step 1. Operations Blanket Under the Special Instructions Section notes the following for Filter change Evolutions:
Any filter housing with a contact dose rate of 500 mrem /hr or greater will be worked on RWp 10. Since the contact reading is 450 mrem /hr, can perfomt the task under RWp 5 lip to survey filter housing prior to filter removal and survey filter (s) upon removal Because filter changes are rapid evolutions, finger rings are required when dose to the extremity 5 times the whole body dose and dose to the extremity >100 mrem is expected. ' Based on the given conditions, the expected dose to the extremity is greater than 5 times the expected whole body dose and is greater than 100 mrem. A finger ring is required.
11P to survey all tools and work area 4
i
'ak
i .
Scenario Events Facility: Millstone Three Scenario No.: 2(Rev 2)
Examiners: Operators:
l Objectives: The crew will be directed to perform the steam generator blowdown valve cycling surveillance. When the first lineup is completed, the main steam Header pressure Indicator will fail low. this will require the operator to shift to manual control for the Turbine Driven Feedwater pumps. There is no backup channel for this indication and , consequently, manual control will be required for the remainder of the scenario.
Next, Pressurizer Pressure Instrument PT455A fails low. This will require taking manual control of pressurizer pressure. The crew will be able to use AOP 3571 and restore pressure control to automatic. Due to a loop seal problem, vacuum will start to decrease in the condenser. It will reach a point where the crew will start to reduce power. The cause of the vacuum problem will be found and corrected. The crew will stabilize the plant. As the crew is stopping the load decrease the letdown orifice isolation valve will fail closed. Over a period of time PZR will increase and charging flow will decrease until the charging header flow Hi/Lo alarm comes in. The crew should diagnosis that the problem is in the letdown system and not in charging. The crew will be able to restore letdown using the other 75 GPM orifice isolation valve. The "B" condensate pump will trip and the "C" condensate pump will fail to auto start. When the operator starts the "C" condensate pump it will not pump due to a shaft shear. This will result in a loss of suction pressure for the main feedwater pumps and they will trip. The motor driven feedwater pump will trip as soon as it starts resulting in a total loss of feedwater. Either due to low SG level or manual initiation by the crew, a reactor trip signal will be generated. ,
The reactor will nct trip until the trip switch at MB7-is used.
None of the AFW punpa will be running and the crew must address a complete loss of feed. The scenario will end when the crew establishes feed from a condensate pump.
Initial Conditions: The plant is operating at 100% power. The crew will be directed to maintain current plant conditions.
i 0
0
f .
Turnover: The crew will be provided the MP3 simulator standard turnover sheet which will direct them to maintain current plant conditions. The following equipment will be out of service: "A" service water pump, "A" motor driven auxiliary feedwater pump, and *B" stator cooling pump. There are thunderstorm warnings for the next 4-6 hours, l
Event Malf Ev'ent Event Description Goa Uca LYRn 1 N Conduct the surveillance for steam generator blowdown valve cycling.
2 I Main Steam Header Pressure Transmitter, PT507, fails low. This will require manual control of Turbine Driven Feedwater Pumps for the rest of the scenario.
3 I Pressurizer pressure instrument PT455A fails low. This will require the operator to take manual control of pressurizer pressure. The instrument failure will be addressed, including Tech. Spec. and pressure control will be returned to automatic control.
4 R/N A decreasing vacuum will cause the crew to rapidly reduce power in attempts to stop the vacuum decrease. The source of the vacuum decrease will be found and corrected.
5 The crew will stabilize the plant once the source of the vacuum decrease has been found.
6 C The open letdown orifice isolarion valve will fail closed. Based on annunciators rece.ived the crew will have to diagnosis this is a letdown problem and not a
charging problem. Letdown can be restored.
7 As the crew stabilizing the plant the "B" cc ensate pump will trip. The "C" condensa 9 pump will not auto start.
When the ope:.ator does start the pump it will not pump water due to a coupling chear.
8 The loss of suction pressure will cause the turbine driven feedwater pumps to i
trip and the motor driven pump trips as soon as it starts. The operators may attempt to start the MDFWP 9 C When an automatic signal is generated or when a manual trip is attempted the reactor will not trip. The operators can successfully trip th gho v k Veuo~s .s2B n~1SEy reactor f rom 10 M None of the auxiliary feedwater pumps will start. A total loss of feedwater event will occur.
SIMULATOR EXAM GUIDE APPROVAL SHEET
- 1. -
Title:
LOIT NRC #2 1D Number: NRC2 Revision: 0
- 11. Initiated:
D. Minnich 5/20'97
- Developer Date 111.
Ip'ies ti!Q l .
<.- / ' m4m 0 I 4.lX1/j)
MidEr / / C date'
- IV. - Approved:
&N Operations Manager Date f
/
9 4Gdi) Operator Training Supenisor Date - q0 0 J f
SIMULATOR EXAM GUIDE I l TAltII OF CON 1TNTS l 3 SECTIONS LISTED IN ORDFR
,i a
i 1. Exam CNerview ). : i i 1 i 4 4
- 2. Instructor Guide i
- 3. Sequence of Events Sununary I i
f . t l t
- 4. Validation Checklist t 1
- 5. Reference and Critical Task Tracking Fonn l
i
.)
- 6. Scenario Initial Conditions Sheet 4
3 4 a l'
+
4
.re--- y- ww w g , n ---=w ,,**"tn------*19--1r-*wNtv
SECrlON 1 ELu! OVERVIEW
Title:
LolT NRC 62 1D Number: NRC2 Resision: 0
- 1. Exam Brief:
'lhe crew will take the shin with plant conditions at MOL and 100% power.
Initially, the crew will perfomi a suneillance associated with the SG blowdown valves. When the initial lineup is established for the blowdown valve sun eillance, the hiain Steam Bypass licader Pressure Tmnsmitter PT 507 will fail low. 'Ihe crew should take manual control of Feed Pump speed, restore feed parameters to nomial, and cany out actions of AOP-3571. l After completion of attachment J of AOP 3571, the Pressurizer Pressure Instrument PT455A fails high over a period of 5 minutes.1he crew should diagnose the failure ar d utilize AOP 3571, Instrument Failure Response, to respond to the event. The crew should refer to T.S. 3.3.1,3.3.2, and 3.3.3.5 for applicability. Afler tripping the appropriate bistables, a loss of condenser vacuum will occur.1he failure will be such that implementation of the Foldout Page of AOP 3559, Loss of Condenser Vacuum, will need to occur. The crew will need to transition to AOP 3575, Rapid Downpower, in order to reduce power at the maximum available rate of 5%' minute [no steam dumps). The cause of the loss of vacuum is a loop seal problem which is found and corrected at about 1000 hiWe, whereupon the crew will stabilize the plant. Afler the plant is stabilized, letdown will isolate due to 3CilS8AV8149B failing closed (blown fuse). The crew must Ivestablish letdown. Aller letdown is established, one of the two mnning Condensate Pumps will trip. The standby pump will not start in automatic. When the operator starts the "C" condensate pump, it will not ptunp any water due to the motor / pump shaft coupling being sheared. This will cause a hiain Feed Pump low suction pressure.1he TDFPs will trip and the h1DFWP will trip as soon as it starts causing a loss of all SG Feed Flow. When an automatic trip signal due to low SG level or a manual trip is attempted from h184 and then hiB7, the reactor will not trip. The operators can trip the reactor successfully by opening the breakers to 32B and 32N at hiB8. Section 1 Page 1 of 2 l
At step 4 of E-0, the crew should dete'mine that a Safet)' Injection is not required arxl transition to ES-0.1, Reactor Trip Response. Upon trans,itioning, the crew should olverve a RED PAlli on the llEAT SINK Status Tree. 1he crew should transition to EOP 35 FR il.1 and cany out the action for the loss of heat sink accident.1 hey will be able to reestablish Steam Crnerator feed from a Condensate 1%np. The exercise will end when the crew has restored feed to the SGs and have transitioned back to E-0. lhe procedure flow path for this exercise is: AOP 3571, AOP3559, AOP 3575, E 0 & FR il.1
- 2. Plant / Simulator differences that may afTect the scenario are:
l None.
- 3. Duration of Session: I hour Section 1 Page 2 of 2
SECTION 2 INSTRUCIDR GUIDE
Title:
LOIT NRC #2 ID Number: NRC2 Resision: 0_ All Control Room ConArt Onerations and Communications shall he in accordance L COP 2001.Conart of Onerations. and OP 3260. Unit 3 Corviirt of Onerations. l' l: " Review the Shiulator Qwrating Limits (design limits of plant) and the Simulator Modeling Limitations and Anomalous Response List prior to perfonning this training scenario on the simulator.1he instmetor should be awnre if any of these limitations may be exceeded." (NSEM 6.02) s i l Section 2 Page 1 of 41
SIMULAIOR IMOHLFAE DURING EXANE It is the responsibility of the Instructors in the simulator to insure that exam interruptions have a minimum negative impact on the Crew and the examinations we provide. Be awe that at all times the Operators should treat the simulator as ifit were the plant and you too should treat it as much like the plant as possible when they are in the simulator. As soon as the Instructors are aware of a simulator problem that will adversely afTect the exam in progress (computer fault, etc.) the Instructor should:
- 1. Place the simulator in FREEZE if possible.
- 2. Announce to the Crew that there is a simulator problem.
- 3. Request that the Crew leave the simulator control room. Ghe Crew shou!d leave the simulator for problems which involve major switch alignments).
- 4. Deal with the problem (reboot, call STSB, etc.)
- 5. ARer the histructors believe the simulator is restored to service, the Crew should be told how the exam will continue, ifit is possible-and felt to be acceptable to the evaluators, the examination can begin where it len off with an update on plant parameters and each Crew member is prepared to restart. If the examination will not begin where it len oft, the crew should be told how and where the exam will begin again.
- 6. Once the Crew has been told how and where the exam will begin, have the crew conduct a brief so that the Instructor and evahtators can insure that the crew has all the necessary infonnation to continue with the scenario.
- 7. Once all Crew members, Instructors and evaluators are satisfied that they have the necessary information to continue the scenario, place the simulator in RUN and announce to the Crew that you have cont' ! the evaluation session.
Section 2 Page 2 of 41
- \ ..
Title:
. LOIT NRC #Q INSTRUCTOR GUIDE Revision: 9 ID: B_RCZ Task Time IDA/Malf Insinoctor Information/ Activity Assign ' Expected Responw Standard Coenp EST#9 a HI: MIDAL SEIUP Setup Issenectioss: DeserIDTas folkms : At any XERM wirxknv, type <idt> When the SUN asks for an executive type- UEXEC or RTEXEC? cnter <rx this will bring up a blank idt page. To go to a r eviously saved idt file type <rcad> at the pmmpt When the SUN asks for a file name of the file you wish to view type in the qpqdie file name-The old "Ih" files are as foikms-Old ISD pages 1-8 a c idt file OPS Old ISD pages 9-16 are idt file OISI Old ISD pages 17-19 are idt file OPS 2 o JE the stcp counters are at/ncar 000,31EN_
- REM (NE the STEP COUNHER OVERRIDE, allow the counters to stcp out during the IC reset.
Reset to IC- 14 RUNSTATE the step counter OVERRIDE A(fust f the various pot settings to the valued specified by the chart krated in the sim booth for the selected IC. Place Simulator to RUN RESET the time constant on the PZR level controller by PIACING the PZR Master Ixvel contmlier in MANUAL then return the Control 1cc to AIRO. Sct the STEP COlWERS PIACE the Main Turbine on the LOAD LIMITER Verify annunciator "COMPIRER FAILURE" (MIMC.1-11), is hDT LIT.
- Place M Curve Book in Shelfihr Operator use. Remove other Lorre Ikmks fmm the lioor.
CIcar the DCS Alarms Reset the Rad Monitor CMI'fR Console by Dtyng the " Status Grid" button twice. hkm 2 Page 3 of 41
Title:
LOIT NRC #2 INSTRUCf0R GUID Resision: A ID: NRC2 - l Task l Time IDA/Malf Instructor Information/ Activity Assign Expected Response Standani Comp i PIACE THE FOtIDW1NG EQUIPMENT IN FIL ormiign as weh I
* "A" Senice Water Pump - Caution tag and place in PIL i
* "A" MDAFW Pump - Caution tag and place in FIL "B" Stator Cooling Pump - Caution tag and place in FIL F2psipment 005: "A" Senice Water Pump "A" MDAFW Pump "B" Stator Cooling Ihmp a
Insert applicable CREW EXAM Tape into the VCR. Synchronize the MONITOR Time Display with BIG BEN. Place copy of OPS Fonn 3670.4-1 (weeldy PM's) and a copy of OP 3670 on the US de-k. - Initial Malfimetions
/Kh/IDAs:
Malf FM07A Motor-driven Feedwater hanp Trip Malf F%21B 'B" Aux Feed hanp Discharge valve Oosed hidf FW19 TDAFW hunp trip on m%cd Malf F%33C Condermde hanp C Cov[ ding Shear Malf RP09A htsnaal ReactorTrip Failise - MB4 hidf RP09B Manual Reactor' Dip Faihme - MB7 htJf RP10A Automatic Reactor' nip Failise-Train A ht:lf - RP10B Aidomstic ReactorTrip Faihme - Train B 1/O Ovenide (FM) f-3CNM-PIC [AASF)Pl fo UFF (This will make the "C" Condensate MB5 Contml Switch imisible to the software nnici and the pump will fail to auto start). ! Ann Ovenide MBIFrDI 'OFF' (TDAFW Bypass Ann) Section 2 Page 4 of 41. 1
.ei:-..; --- ---- .I. lu.,---'-
.i. -- - ---m .s-ie.--
Title:
LOIT NRC #2 INSTRUCTOR E Revision: 9 ID: NRCZ Task i Time IDA/Malf Instructor Information/ Activity Assign Expected Response Standard Comp Iral Examincr: Refer to the ' Briefing Script for the Operadonal Exam" arul lxief the crew. Booth Imtructor: Commenee hortling Simidatorsessian Booth Imtructor. Perform the crew tumover(Initiai Condi60ns page at crul of 17). Section 2 Page 5 of 41
Title:
_ LOIT NRC #2 INSTRUCTOR GUIDE Resision: R ID: NRG Task Time IDA/Malf Instructor Information/ Activity Assign Expected Response Standarti Comp T = Tumover EVENT ONE: Pierform Steam complete Generator Blontlown valve cycle as perSP 3670.4 (Routine PM's), step 4.1.3. It is expected that the US will give a pre-job brief to the RO for the SG blowdown valve cycle. EVFNrMk MAIN STFAM BYPASS IIEADER TRANSMII'Itx FAILURE T = 3 B/D RXIS Main Steam Bypass Ileader FCV's 'U%" Pmssure Transmitter Failun. First (IIV20's) 300 sec indication will be stm flow /fcal closed,1 FCV flow mismatch alarms. nm flow 1DFWP master speed contmilcr is BOP Determine the initiating pammeter and AOP 3571 the afTected controller, or individual place the affected controller in step i FW Pump Speed Controller to MANUAL manual is acceptable. Crew Stabilize the plant parameters. AOP 3571 step 2 Program AP will b: obtained using 'Ihe following annunciators are AOP 3571 feed pump discharge and S/G symptoms of a MS he:xler pres:ure Att) NO'E ' pressures instmment failure (Irf-507): None Section 2 Page 6 of 41 i
Title:
_ LOIT NRC #2 !NSTRUCTOR GUIDE Revisi n: 11 ID: NRC2 Task Time IDA/Malf Instructor Information/ Activity Assign Expected Response Standard Comp BOP Verify feedwater pump A and B AOP 3571 master speed control (3FWS-SK509A) AttJ step I in MANUAL and restore fini pump dilTerential pressure to norma! opcmting hand (Progmm- 45-195 psid) BOP Place steam generator pressum AOP 3571 controller (3 MSS-PK507) in AttJ step 2 MANUAL and reduce the output to minimum (Automatic STFAM PIESSURE steam dump mode is
, inopcmble until the cluinnel is restored.)
Crnv When conditions have stabilimi, AOP 3571 obscrve MB annunciators and AttJ step 3 pammeters and immediately report any unexpected or unexplained conditions to the Shift Supenisor. There am no tech specs associated SCO/SS Request I&C Department perform AOP 3571 with PT 507 conective maintenance on failed attJ step 4 instrument. Section 2 Page 7 of 41
Title:
LOIT NRC #2 INSTRUCTOR GUIDE Resision: 11 1D: MRC2 Task Time IDA/Malf Instructor Information/ Activity Assign Expected Response Standarti Comp I EVENT'I11REE: Failure of j Pressinizer Pressisc irr;tnnnent ) ?- Ff455A T= attachment RXO9A PT455A fails high. RO Notice and report the failing channel to J compicte sev= 100% tbc US mmp = 600 seconds US Enter AOP3571, Instmment Failure AOP3571 Response. cntry conditions lhe Pzr Master Pressure Controller US/ Determine the initiating parameterand AOP 3571 will be placed in manual. RO place the affected contmlierin step 1 MANUAL RO 5tabilize the plant p...Ars. AOP 3571 step 2 Attachment "B" is the conect US Itrform corrective actiors using AOP 3571 attaciunent. appropriate attach.nent. step 3 RO Defeat tir failed channel input. AOP 3571 Att.B step 1 RO Restore RCS pressure to normal, then AOP 3571 place PZR pressure control in Att.B step 2 automatic. Section 2 Page 8 of 41
Titi;c _ LOIT NRC #2 INSTRUCTOR CUIDE- ' Revision: 9 ID: NRC2 ; 1 Task Time - IDA/Malf Instructor Information/ Activity Assign Expected Response Standard Comp CREW When conditions have stabilized. AOP 3571 observe MB annunciators and Att.B step 3 pammeters. Immediately report any unexpected or unexplained conditions to the Shill Manager. US/ Determine which Reactor Protection AOP 3571 RO System histable (s) requires tripping- Att.B step 4 US Place a check mark in the box abost AOP 3571 the y q=iate channel that n: quires 'Att.B tripping on pages 3 or 4 of this step 4a , Attaclunent. NO'ITc only 3.3.1 action 6,33.2 SM- Refer to Technical Specification 33.1 AOP 3571 action 20 apply. SP 3673.5, 33.2, and 333.5. Att.B Remote Shutdosm Monitoring, step 4b provides guidance for TS 333.5. RO Check the existing bistable status to AOP 3571 ensure a reactor trip will not occur Att.B uhen the failed channel is tripped. step 4c Section 2 Page 9 of 41
Title:
.. LOIT NRC #2 INS 1 UCTOR GUIDE Redsion: 9 ! ID: NRC2 i Task Time IDA/Malf Instructor Information/ Activity Assign Expected Response Standani . Comp
'D= request to . RXR106 OPEN, Protection Door SM/ Request the I&C Dqurtment trip the - AOP 3571 trip B/Ss RXR27 1 RIP, Hi Pzr Press Rx Trip US appropriate histabics using Attachment Att.B j RXR120 'IRIP, P-Il B and Attachment S. step 4d RXR48 TRIP, law PzrIhs Rt Trip RXR44 TRIP, Pzr Press to SI !
RXR05. TRIP, Ol'aT' Dip RXR34 1 RIP, G3 RPR40 1 RIP, im Pzr1%ss PORY logic RXP.106 CLOSE, Protection Ihr RO Verify the appropriate bistable status AOP 35J1 lights are lit. Att.B step 4e . SM' Request I&C Dgurtment perform AOP 3571 US corTective maintenance on failed Att.B step 5 instrumert Event M ; Imss of Condemer Vacinun BOUI11 On MOD COMP in the Ihth. INST: Bring up the CIRC WATER SCIEEN - BOP, F-4, Pictiac 26 This will assist in contmiling the kus of vacuunt Section 2 Page 10 of 41
Title:
LOIT NRC #2 INSTRUCTOR GUIDE Re ision: 11 ID: MRCZ Task Time . IDA/Malf Instructor Information/ Activity Assign Expected Response Standarti Comp T= Event 3 IWI Inwering co ulerser vacimen. complete +1 so= 100% FWOI is initially entenxi at 100% minute severity. NOIE After the low vacinun alarm is US o The Foldout page must be AOP 3559 received or the crew rudices the open. Step I degrating vacinun, REDUCE the NOTE severity to ~30%and fiutherreduce o If a reactor trip occurs during the severity as necessry to preverW the performance of this exceeding 7.0"Ilg backpressine. procedure, Go to E-0, Reactor ) The goal is to not have the crew Trip or Safety Injection. I trip the plant ind to use AOP 3575 to reduce power. NOIE- 1he FOLDOUT PAGE Criteria will CREW FOll)OUT PAGE FOLDOUT apply. The crev is expected to PAGE transition to AOP 3575, Rapid 'IURBINE LOAD REDUC 110N Downpower, and perfonn a power CRTERIA reduction. When the crew t,arsitions, proceed forward to page IF condenser backpressure increases 14 fordownpoweractions to GREATER 'IlIAN 5 inches Hg absolute, turbine load must be reduced (DO NOT reduce below 360 Mur) at the maximum allowable rate until vacuum stabilizes using AOP 3575, Rapid Downpoutr. B00I11 Check the actions under AOP 3575 BOP Oneck Orculating WaterSystem AOP.3559 concuntnt with AOP3559 Operation Stcp i Section 2 Page 11 of 41
Title:
LOIT NRC #2 INSTRUCTOR CUIDE Resision: 11 i ID: NRQ i Task i Time IDA/Malf Instructor Information/ Activity Assign Expected Response Standarxl Comp BOP Verify circulating water pumps - ONE AOP 3559 PER CONDENSER RUNNING Step 1.a , i BOP Verify all available circulating unter AOP 3559 l pumps - RUNNING Step 1.b BOP Verify unter box outlet isolation AOP 3559 valves - OPEN Step 1.c BOP Verify the tmveling screen differential AOP 3559 pressure - LESS 'ITIAN 12 incirs Step 1.d 1I2 0 BOUlli Do not place second set of air BOP Check Condemer Air Remmi AOP 3559 ejectors in service when requested Discharge 1% h Step 2 by the crew. Tell them isth sets are on. IYrform as described below. IMROI or Steam jet air ejector valves. Utilize PEO locally Verify both sets of stcam jet AOP 3559 IMR02 as necessay to control the rate of air ejectors in senice using applicable Step 2.a the lowering vacuum. Pmbabaly steps in OP 3329, Condenser Air will need the second set when the Removal, Section 7.2 malfunction is removed to help restore vacuum. NOTE B00111INSTRUCIOR:'Ihe came BOP Verify SJAE auxiliary stcam supply AOP 3559 of the problem will he found if the valve (3 ASS *AOV22)- OPEN Step 2.b US semh a PEO to imestigate the loop seals. ! Section 2 Page 12 of 41 l
Etie: LOIT NRC 2 INSTRUCTOR GUIDE Resision: .Q ID: NRC7 Task Time IDA/Malf Instructor Infonnation/ Activity .A= sign Expected Response Standani Comp l BOP Verify isolation dampers for gascous AOP 3559 waste to Unit I stack Step 2.c (3GWS*AOD78A and 3GWS*AOD78B) - OPEN T+ 5 mim of IMXIIII Report tirat 3GWS-FNIA is naning PEO Imally (Aux Bldg 45') Verify process AOP 3559 reqirst vent fans (3GWS-FNI A or 3GWS- Step 2.d FN1B) at Gas Waste Panel (3GWS-PNL-P6)- ONE RUNNING T+ 5 mins of BOOrill Report that teth valves are open PEO Imally (Turbine Bldg 38' southwest) AOP 3559 regiust Verify SJAE exhaust valves (3 ARC- Step 2.c Crew should tmnsition to AOP AOV36A and 3 ARC-AOV36B)- 3575 for mpid downpower. Go to OPEN page 14. BOP Check Gand Seal Pmssure - AOP 3559 BENEEN 2 and 6 psig Step 3 Inked valve key is required for AOP 3559 some local opcmtions. Step 4 Note BOP Orck Condemase Surge Tank Level AOP 3559 Step 4 o GREATER BIAN 18,000 gal o NOT DECREASING IN AN UNEXPECIED MANNER Section 2 Page 13 of41 L--- -
Title:
. LOIT NRC #2 INSTRUCTOR GUIDE Revision: 11 , ID: NRC2 Task Time ID, W 1alf Instructor Information/ Activity Assign Expected Response ' Standard Comp CREW A ttnhine trip occurs if the exluust AOP 3559 Iml tempemtun: exceeds 225"F. Step 5 ; NOTE 13OP Orck Exhaist flood Tenpratme AOP 3559 Annunciators EXII 11000 A, B, and Step 5 C TB1P III (MB6A 5-4,5-5, ant' 5-6)- NOF IJr. Only applies if alann is rtecived BOP Slowly 'Ihmttic OPEN the exhaust AOP 3559 hood spray bypass valve (3CNM- Step 5 RNO MOV100) to reduce the temperature to LESS TIIAN 175"F using 3n11-- UR22 (points 1,2, and 3). US Dispatch An OperatorTo Impect For AOP 3559 In-Irakage Step 6 BOP CLOSE condenser vacuum breakers AOP 3559 3 ARC-MOV20A-B-C (MB7) Step 6.a PEO Locally Chwe vahcs (Turbine Bldg AOP 3559 60' west). Step 6.a RNO BOOTII Acknowledge request PEO Imcally Check vacuum breaker loop AOP 3559 seals (Turbine Bldg 60' utst) - Step 6.b FILLED Section 2 Page 14 of 41 1 _
Title:
LOIT NRC #2 INSTRUCI'OR GUIDE Revision: 9 ID: ' NEQ i Task l Time IDA/Malf Instructor Information/ Activity Assign Expected Response Standard Comp T=imi IKXJlli Report that the loop seal forSIAE rethred to "A" was empty arul you are in the 1000 MWe process of filling it. Hooth Remove RMil PEO I;cilly Check for unusual noises AOP 3559 , indicative of air in-leakage Step 6.c BOP Check seal water supply pn:ssun: : AOP 3559 annunciator EXT S'IM NRV SEAL Step 6.d PRES LO (MB6A 3-6B)- NOT LIT US/ Contact Engineering to assist in AOP 3559 SM locally checking condenser . Step 6.c penetrations for air in-leakage US/ Review cunent Maintenance and AOP 3559 SM Testing Activities. Step 7
. Section 2 Page 15 of 41
Title:
' LOIT NRC #2 INSTRUCTOR GUIDE Revision: .9 ID: NI{C2 , Task Time IDA/Malf Instructor Information/ Activity Assign Expected Response Stan6rd Comp AOP 3575 CREW Determine Ibwer Reduction Rate AOP 3575 , (Wmin). Step I i Yes. 5% / minute is the applicable US Check desired power reduction mte - AOP 3575 rate as the steam dumps are NOT, LESS TIIAN OR EQUAL TO Step l_a or soon will not be, availabic. 5Wmin. US Check power reduction a CONVEX AOP 3575 requested Emergerry Gerension Step 1.b Rea*uctiort NO. 5% / minute is the applicable US Perform de following- AOP 3575 rate. AOP 3559 prescribes the rate Step 1.b . as the maximum allowable mte, 1) Determine power reduction RNO which will be 5% / minute without rate using Table. the steam dumps.
- 2) Pmcced to Step 2.
US Check Rai Control In AUlIl AOP 3575 Step 2 US If during the performm:c of this AOP 3575 procedure the Rod Insertion Ie-IA Step 3 Limit is reached, Go to AOP 3566, CAUDON Immediate Ikration. Section 2 Page 16 of 41
...-:........... -- g--
- - - _ e-
Title:
IDIT NRC #2 INSTRUCTOR GUIDE Resision: H ID: NRC2 Task l Time IDA/Malf Instructor Information/ Activity Assign Expected Response Standard Comp- ! l Not a Convex requested reduction CREW Ifload reduction is a CONVEX AOP 3575 requested emergerry genemtion Step I reduction, the following apply- NOTE 1he Unit 1 Shift Manager will determine how the load reduction will be sinnxi among the Units. DO NOT stop a CONVEX "Oncrgency Load Reduction" request due to AFD cxceeding the target band.
'Ihe load reduction must e conpleted within 15 mbutes ofnotification.
CIEW Initiate Imad Reduction. AOP 3575 Step 3
.J Check power reduction a CONVEX AOP 3575 requcsted emergency g meration Step 3.a nxtuction.
B0 0111 Acknowledge the information and US Inform CONVEX ofload reduction AOP 3575 request the crew maintain MVARS rate (Mne/ min) and final Mwe level. Step 3.a thmughout the downpower to a RNO value of 100 20 MVARS (the US > may maintain MVAR and not contact CONVEX). Section 2 Page 17 of 41
Title:
LOIT NRC #2 INSTRUCTOR GUIDE ~ Resision: 'R, 10: ' NRC2 - Task Time IDA/Malf Instructor Ini'ormation/ Activity Assign Expecied Response Standard Comp IK)P Check turbine NOTin STANDBY AOP 3575 LOAD control. Step 3.b IK)P Check LOAD LIMIT LIMITING light AOP 3575
- LIT. ' Step 3.c BOP Intermittently Press DECREASE AOP 3575 LOAD pushbutton until LOAD Step 3.d LIMIT LIMI!1NG light - NOT LIT.
BOP Rotate LOAD LIMIT SET adjust AOP 3575 know at least one full tum in mise Step 3.e direction. BOP Select DECREASE LOADING RATE AOP 3575 to ON. Step 3.f 5% / min should be selected BOi> Scicct LOAD RATE LIMIT WMIN AOP 3575 to stquired pourr reduction rate Step 3.g (Wmin). NOL O>> Crew should adjust to about 400 IK)P Utilizing DECREASE LOAD AOP 3575 MWE as when tempcmture pushbutton, Adjust LOAD SET to Step 3.h decirases at the end of the tmnsient desired final Mwe (pourr level). load will drop an additional 20 or so MWE. NOIE>> 'Ihe enny would be required to trip BOP Maintain initial MVAR loading AOP 3575 the turbine ifload is < 360 MWE during poutr reduction unicss Step 3.i and Backpressure is greater than 5 directed otherwise.
"IIg Section 2 Page 18 of 41
l Titic: LOIT NRC #2 INSTRUCTOR GUIDE Reviskm: 0 { ID: - NBC2 Task j Time IDA/Malf instructor Information/ Activity Assign Expected Response Standard Comp US If at any time the power reduction AOP 3575 rate must be clunged, retum to Step Step 4 ,
- 1. NOTE Yes, rate is greater than 39Vmin. US Verify Ptmer Reduction Race - AOP 3575 GRENER'IllAN OR EQUAL'ID Step 4 3%fMIN.
US Initiase Rapid Boration. AOP 3575 Step 5 RO Place RCS makeup controller to AOP 3575 AUTO. Step 5.a RO- START one boric acid transfer pump. AOP 3575 Step 5.b RO OPEN emergency boration valve AOP 3575 (3CIIC*MV8104). Step 5.c RO' Verify power reduction rate - AOP 3575 US CIEATI!R'HIAN OR EQUAL to Step 5.d 53VMIN. RO START second boric acid transfer AOP 3575 pump. Step 5.c RO OPEN charging line flow contml AOP 3575 valve to match direct boric acid flow Step 5.f' (3CIIS-FI 183A) Secti(m 2 Page 19 of 41
Title:
IDIT NRC #2 INSTRUC110R GUIDE - Revision: 9 iD: NBC2 Task Time 1DA/Malf Instructor Inf'ormation/ Activity Assign Expected Response Standarti Consp ' US Record time boration started AOP 3575
, Step 5.g Time RO Energize all P7R heaters. AOP 3575 Step 5.h -
70% power change = 1050 gallons US Determine required boric acid AOP 3575 addition by multiplying Step 5.i total power change (a%) by 15 (gal /%) = gal.
~72 gpm yicids a time of ~ 15 US Determine requinxi time to bomte by AOP 3575 ~
minutes dividing mquired gallons of boric acid Step 5.j-(gal) by the direct boric xid flounte (gpm) min. US/ Boric acid flow rates are based on AOP 3575 RO approximations. Adjustments should Step 6 be made to the volume addition or NOBi flow mte as necessary to ensure the reactor reaclx:s the desired end state of: Tavg on program Reds above the RIL AFD on or above the target value US Restore RCS Mikeup AOP 3575 Step 6 Section 2 Page 20 of41 T-'-'-'irg n - i fi-- w-+
i
Title:
_LOIT NRC #2 INSTRUCTOR GUIDE Resision: R , 1D: NRC2 Task Time IDA/Malf Instructor Information/ Activity Assign Expected Response Standant Comp US/ Check rapid boration perfonned for AOP 3575 RO tir required time determine in Step Step 6.a 5.j. He first time through the US will US Proceed to Step 8 and, WIIEN Rapid AOP 3575 most likely utilize the RNO. If so, boration has been performed for the Step 6.a Proceed to step 8 and retum here required time, T1IEN Return to Step RNO uhen boration time is completc 6.b. RO CLOSE emergency boration valve AOP 3575 (3CIIS*MV81G1). Step 6.b RO STOP boric acid transfer pump (s). AOP 3575 Step 6.c RO Pixe charging line flow control vahr AOP 3575 in AUTO. Step 6.d US Proceed to Step 8. AOP 3575 ~ Step 6.e US/ Reduce Steam Supply To The MSRs, AOP 3575 His will be done automatically by BOP Using OP 3317, Rcheat and Moisture Step 8 DCS system Separator, Section 7.8. His will depend on how low power US Check if RCS Sample Is RequimL AOP 3575 was mduced before the problem Step 9 with the loop scal uns discovered Section 2 Page 21 of 4I i
Title:
LOIT NRC #2 INSTRUCTOR GUIDE Revision: R ' ID: NRC2 Task Time IDA/Malf Instructor Information/ Activity Assign Expected Response Standarti Corrp US/ Verify change in Reactor Power- AOP 3575 RO GREATER 'IllAN 15% IN ONE Step 9.a iIOUIL Acknowledge request to perform US/ Request Chemisty sample tle RCS AOP 3575 = lodine sample. SM for iodine (within 2 to 6 /oras <fter Step 9.b ; the p<ncer cimge.) This will depend on whether the US Verify Target IbwerIrvel- IISS AOP 3575 cause of the loss ofcondenser 111AN 50% Step 10 l vacuum is found and conected. If RNO conected, vacinun will ::tabilize and the US should stop the rapid . downpowerand proceed to step 20. If the cause has not been corrected, he should continue to step 11. US/ Verify Control Bank D - GREATER AOP 3575 RO 1HAN 120 steps. Step 11 T+ 3 rnin of F%R30 Remove the Desired # of Demirs BOP Renme Condersate Demirs From AOP 3575 request fmm service and report to de Service As Necessary To Maintaa Step 12 Control Room that the trk is Demin Flow Between 1200 gym and complete 3200 gprn Using OP 3319C, Condersale Demineralizer Mxed Bed System, Sectian 7J. T= request F%R57 or Set to as requested to renuwe 130P when Ibwer Decremes Bekw 50% AOP 3575 FM R58 1DMFW hunp (probably will not Stap One Main Feed Ihmp Using OP Step- 13 get to this power level). 3321, Main Feedwater, Section 7.4 or 7.9. Section 2 Page 22 of41
Title:
IDIT NRC #1 INSWUCTOR GUIDE Revision: _ D ID: NRC2 Task Time IDNMalf Instructor Information/ Activity Assign Espected Response Standard Comp RO \%en Reactorlimer Decremes 'AOP 3575 j Below the P-9 Setpoint, Verify 'NIS Step 14 IUWER RANGE P-9 PERMISSIVE" Annunciator (MB4D 6-1) - IJr. EVENT 5; Ixtdown Isolation T = Plant I/O(CV); 3ClIS*AV81498 stabilized 'CIDSE" to 'UN" . 'Ihis will close afterleak the "B" Ixtdown Orifice Isolation found and Valve. conected. It is expected the crev will detect this when the Charging Flow III/LO alarm annunciates due to low charging flow (PZR level has been increasing). 'Ihe US should direct Letdown reestablished using OP 33MA, section 4.10, Restoration Froin Ixtdown Isolation with Continuous Charging at NOP. T+ 5 mirs of BOOTII If called to investigate, wait 5 regiust minutes and report that there is a blow fuse in panel BYS*PNL20F
- (ckt 2).
Section 2 Page 23 of 41
Title:
LOIT NRC #2 INSTRUCTOR GUIDE Revision: 11 ID: NRC1 l Task Time IDA/Malf Instructor Information/ Activity Assign Expected Response Standani Comp EVENT 6: Total loss of Feedwater lime = Event 5 complete (letdown estaNished) + 1 nin. FMU3A "A"CONDENSA1E PUMP 1 RIP F%D7B and FM07C set on the rennte to enteronly if required. (A and B 1DFP trip) NOTE; 1he "C" Cond. PP will not auto start but can be started manually. 'Ihc "C" pump will not pump any water due to a shcared shaft coupling. The crew should recognize this from the low Feed Pump Suction Pressures and the near "0" running amps of the "C" Cond. PP. If the crew attempts to manually trip the Rextor from MB4 and then MB7, neither trip switch will work, but tripping fmm MB8 by opening the supply bn:akers to 32B and 32N will be successful. The sequence of events are:
* "A" Cond. PP trip, "C" Cond. PP fails to auto start, operator starts "C" Cond PP, "C" Cond PP shall shear.
- Iow feed PP suction pn:ss. followed by a trip of the TDFWPs. MDFWP trips immediately upon starting.
- Auto Rx. trip signal on SG 12-1m level, auto reactor trip fails to actuate, manual trip from MIM and MB7 fails.
- Manual trip by opening the supply breakers to 32B and 32N.
BOOHI If power is low enough such that one condensate pinnp is sufficierg to supply required ITV flow, be ready to insert rmifunctions: IM07B ("A"1DFP trip) and FW)7C ('B"1DFP trip) Section 2 Page 24 of 41 L- _ .. . . .
Title:
LOIT NRC #2 INSTRUCTOR GUIDE Revis~mn:- 11 ID: NRC2 i Task Time IDA/Malf Instructor Information/ Activity Assign Expected Response Standard Comp ; IK)P Repxts that both TDFWPs have trippx1, and that the MDFWP has tripped. j US may order BOP to attempt t.ne BOP Attempts one more start of the more start of the MDFWP. MDFWP. It does NOT start. US should reali7e that feed How US Directs the RO' BOP to Trip the cannot be reestablished and that a Reactor and cany out the immediate reactor trip is required. US should actions of E-0. go to Master Silence. NOTE RO 1 RIP the reactor [*] US stundd onier 'WterSilerre" before orrienny wactorInp. i 1he wador willnot inpfmtru MR4 orMR7. The rettforcar be successfAly inped s by operity 32B wact32Nsupply breticen. Crew Go to E-0, Reactor Trip or Safety injection. F,0 STEPS - Foldout page must be open E-0, Step 1. NOlli Section 2 Page 25 of 41
Title:
LOIT NRC #2 INSTRUCTOR CUIDE - ResisGon: 11 ID: NRCZ Task Time IDA/Malf . Instructor Information/ Activity Assign Expected Rcsponse Standard Comp ADVERSE CIMF defined as GREAlliR 111AN 180'F or GREAlliR TIIAN 10'"/w in containment. This definition applies to this and all subsequent EOPs.
- lhe reactor can be interyxtted as " tripped" and the operator shall proceed to tir next high level step when any two of the three bullet substeps of step 1 are determined to be satisfied.
After tripping by opening the 32B RO Vedfy ReactorTdp E-0. Step I and 32N supply breakers.
- Check n: actor trip and bypass breakers - OPEN
- Check rod bottom lights - LIT
- Check neutron flux -
DECREASING BOP Vedfy Tambine Tdp E-0 Step 2 Check all turbine stop valves - E-0, Step CLOSED 2.a Section 2 Page 26 of 41 _q. ,.-. . . . . .,.i..........,
Title:
IDIT NRC #2 INSTRUCTOR GUIDE Revision: D 1D: NRQ Task Time IDA/Malf- Instructo -Information/ Activity Assign Expected Response Standard Comp US Verify Pburto AC E..agwy E-0, Step 3 Bisses-BOP Check busses 34C and 34D . AT E-0, Step LEAST ONE ENERGIZED 3.a NOTE SI should not be initiated. US Oieck If SI is ActisWed E-0, Step 4
.l' RO Verify Safety Injection Actuation EOP 35 E-0, .
annunciator - LIT- Step 4.a US Check if Si is required E4), Step 4 RNO
- Ctmt pressure GREAlER BIAN 18 psia 2
- RCS pressure LESS 71IAN 1890 psia 2
- PZR level LESS 111AN 13%
2
- RCS subcooling LESS T1IAN 28"F m
- SG pressun: LESS 711AN 660 psig IE SI is rrquired TlIEN Initiate SL Sectica 2 Page 27 of 41
- . a.
Title:
_LOIT NRC #2 INSTRUCTOR GUIDE Revision: 9 ID: NRC Task Time IDA/Malf Instnscior Information/ Activity Assign Expected Response Standant Comp NOTE A RED PABI on IIEAT SINK IE Si is NOInxluired, BIEN Initiate shou!d be present requiring the monitoring of CSF Status Trees and crew to transition to FR-il.l. Go to ES-0.1, Reactor Trip Response. FR-ILI STFfS CREW If total feed flow is LESS 111AN 530 FR-II.I gpm due to opemtor action, DO NOT step 1 PERFORM BIIS PROCEDURE. Caution CREW Fced flow must not be trestablished FR-ill to any faulted SG if non-faulted SG is step 1 available. Caution US Check if Seconday Heat Sink is FR-Ill Required step i ROBOP Verify RCS pressure - GREABER FR-IL1 BIAN ANY NON-FAULTED SG step la PRESSITRE RO Verify RCS hot leg WR temiudure - FR-1LI GREA1TIR BIAN 350 F step 1b The "A" charging pump will be RO Check Charging Pump Starts - AT FR-IL1 mnning. IEAST ONE RUNNING step 2 Section 2 Page 28 of 41 l
Title:
- IDIT NRC #2 INSTRUCTOR GUIDE Revision: H ID: NRC2 Task Time IDA/Malf Instructor Information/ Activity Assign Expected Response Standani Comp CREW Steps 10 through 14 (bicci and feed)' FR-ILI . of this procedure must be immediately step 3 initiated if either of the following Caution occur-
- WR level in any 3 SGs is LESS TlIAN 27%(57%
ADVERSE Caff)
- P7J1 pn:ssun:is GREATER 111AN OR EQUAL TO 2350 psia due to loss of secondary heat sink indicated by con:
exit TCs increasing. [ If offsite power is lost afler SI nset. FR-Ill , manual action to restart safeguards Step 3 equipment may be requinxi. NOTE : If the recirculation spray pumps are FR-IL1 requinxi and have not started, DO Step 3 NOT reset CDA. NOTE US 1)y to Establish ABV How to at FR-Ill Irast One SG step 3 13OP Verify AFW valve alignment - FR-1L1 PROPER EMERGENCY step 3a ALIGNMENT I3OP Verify DWST suction valves FR-1L1 (3FWA*AOV61A and step 3b 3FWA*AOV6iB)- OPEN. Section 2 Page 29 0f 41
ID:. NRC2 Task Time IDA/Malf Instnwtor Information/ Activity Assign Expected Response Standard Comp BOP Verify DWST level - GREATER FR-1L1 TIIAN 80,000 gal . step 3e BOP Verify AFW pump opemtion: IF IL1' step 3d NOTE 'Ihe "B" MDAFW PP will be 1) Check MD pumps - FR-ILI running but not pumping any smter. RUNNING step 3d (Disc. VV closed) part i
- 1) START pumps. FR-IL1 E the pump (s) do NOIstut, THEN step 3d Restore power to the pumps part 1 RNO (MB or locally).
Check turbine-driven pump - FR-IL1 RUNNING step 3d part 2 OPEN steam supply vahc(s). FR-IlI E the pump does NOI start,'nILW step 3d OPEN the steam supply part 2 RNO isolation vahes: 3 MSS *MOV17A 3 MSS *MOVl7B 3 MSS *MOVI7D NOTE The US should send a PEO to US Dispatch an operator to locally restore FR-Ill attempt to establish flow from the AFW Ilow using Attachment A, if step 3e "B" MDAFW PP since it is irquired running. Section 2 Page 30 of 41
Title:
_ LOIT NRC #2 INSTRUCFOR GUIDE Revision: 9 ID: NRC2 Task Time IDA/Malf Instructor Information/ Activity Assign Expected Response Standard Comp BOUlliINST NUE If sent to imestigate 'B" MDARV PP, wait 3 minutes arul report the ] discharge valve (3RVA*Vl8) is closed and you cannot open it. IIc may have aircady sent a PEO to BOP Check total flow to SGs - GRENER FR-IL1 investigate the 'Il)AFW PP trip. IIIAN 530 gpm step 3f BOUI11 INST NOE 3 min. after requested to investigate US Perform tie applicable action: the 3DARV PP trip, REI'OfU that - IE no AFW llow is indicated, you attempted to reset MSV5 lud it 'IIIEN won't stay latched. Proceed to step 4. RO S'IOP all RCPs FR-IL1
. siep 4 US Try to Establish Main RV How to at FR-ILI Irast One SG step 5 NOTE Be "B" condensate pump will be BOP Verify at Icast one condensate pump - FR-ILI running. RUNNING step Sa BOP Check FW isolation trip valves - FR-ILI OPEN step Sb l
Section 2 Page 31 of 41 1
Title:
LOET NRC #2 INSTRUCIUR GUIDE Reddon: R
-ID: NRC tac Tmee IDA/Malf Instnsctor Infonn-tion /Acthity 'ssign
. Expecial Response Standard Consp BOOTTIINST NOIE Kcalled to Ptdl the Univeisal Engic OEW Perform the fblioning FR-Itt Stcp Cank, PDUORM the following Perform the folkming- 5.b RNO On any XIIRM window, hold die 1. IF SI 2 P-14 has actuated.
shin Iery and hit the '?'lary to get - WIIEN SG Icsris LESS the IDT gwoonpt. TIIAN the P-14 se: point. TIIEN RESETSI AND Type 'sead. When a file amne is Remove unhusal logic card shed fer, type UPSI'. Pge A213 from lxth Trains of the femad to page 2. Luane lines 61 Solid State Prutection System and 62 me TAISE'(FWP4A & (3RPS*RAKLOGA and FWP48). K not, type: SET. 3RPS*RAKLOGB). 61,F,<r>; then type: SET 62,F<r>. (T= TRUE, F = FAISE) 2. RFSET FWI at MB2. ROURTthe cards have been 3. RESET FW1 at MB5. pulled
- 4. Adjust SG feed n gulating and if requested to reinsert the cards, SG feed regulating bypass wait I min. and then REPORT t!c nhe controIIcrs to zero cards have been reinstalled. Igl outpuL NOTset the values back to tme.
- 5. RESEF the FW isolation trip vahu.11IEN OPEN du vahrs.
- 6. IF universal logic card A213 was remmul.11IEN Replace unhusal logic card A213 in both Trains of the Solid State Protection System Section 2 Pag 32 of41
Title:
_IIMI_NRC #2. INSTRtJCTOR GUIDE Resisiec R l ID: NRC2 Task Tirne IDA/Mair Instructor Infonnation/ Activity Assign Expected Resposee Standani Casup (3RPC*RAKLOGA and 3RPS*RAKLOGB).
- 7. IF no FW isolation trip vahr cr.n be opened.11IEN Pmcced to Step 9.
B00111 INST NOTE If called to investigate why she SENMP will not start, WAIT 4-5 niin., shre REPOIE shut the e mescanent relay on she tweakerhas 8'iPP"E CREW Establish nuin FW iknv usmg MD FR-1LI FW pump- stcp Sc NOTE The MDFWP will not start. IK)P 1) START MD FW pump FR-ILI step Sc part 1 US 1) Pmcced to CAUllON prior to FR-IL1 gg 7. gg k part 1 RNO PZR level may deu- ofFscale low FR-1L1 to SG depressuriraion. step 7 Caution Section 2 Page 33 of41
Title:
_ IDIT NRC #2 INSTRUCTOR GUIDE Resision: R IIh NRCZ Task Tr ne IDA/Malf Instructor Information/Acthity Assign Expected Response Standard Casup Folkming bkrk of automatic SI FR-Ill actuation. manual Si actuation may be step 7 required if conditions degrade bc>urxl Caution operator control If REGEN liX IEIDOWN'II31P III FR-1L1 (395T) annunciator actuatcs while step 7 using auxiliary spray flow, a charging Caution hemier kg isolation vahr must be openctL To allev condenscr steam dump FR-ILI operation to continue during step 7 hkte depressuriMion. cnsure that Inv-Is.v Tavg intenock is bypassed at ( 553 F. After the low Steam Line Pressure SI FR-IL1 signal is blocked. MSI will occur if step 7 Note the high steam pressure rate setpoint is exceeded. CREW Try to Establish Feed How Fnna FR-ILI NOTE 'Ihis is to be the success path for restoring SG Fced Flow. Condemase Syssesu step 7 [*] DOP Check condensate pumps - AT FR-IL1 LIATT ONE RUNNING step 7a RO Depressurize RCS to LESS 711AN FR-ILI
'1950 psia . step 7b i
Sectkm 2 Page 34 of41 ie
Title:
LOFT NRC #2 INSTRUCTOR GUIDE Resision: 9 ID: NRCZ. Task linee IDA/Malf . Instructor Infornistim/ Activity Asign Exgwcted Response Standard Counp I) Vcrify Ictdown in service FR-IL1 stcp 7b part 1
- 2) E<ablish auxili.vy spray- FR-ILI Step 7.62
.L OPEN charging header isolation uhrs (3GIS*MV8106 and
)- 3GIS*MV8105)
- b. Unlock and OITN auxiliary spray whr (3RCS*AV8145)
- c. CLOSE d-pug header kxp isolatien .
whrs (3G5'AV8146 and 3GE*AV8147)
- d. 'Ihnxtic charging line flow contml nhr to adjust and maintain auxiliary spay flow.
- 3) Place control switches for all FR-II.I Step PZR heaters to OFF. 7.b3 i
Section 2 Page 35 of 41
~
Title:
IDIT NRC #2. INSTRUCTOR GUIDE Revision: R ID: NRC2 Task Tinee IDA/Malf Instructor Infonnation/Actisity Awign Expected Response 9W Counp
- 4) Check the folkming- FR-Ill Step
., 7.b.4 RCS pnssure- LESS TIIAN 1950 psia
- Annunciator MIMD 3-5,
" PRESSURIZER TO INERLOCK P-11," - UT.
Retum to Stcp 7.b. FR-1L1 Stcp 7.b.4 RNO RO Block SI signals FR-IL1 Step 7.c BLOCK htiin Steam Pressure St BLOCK PZR Pressure SI Maintain RCS pressure LESS FR-ILI Stcp 111AN 1950 psia. 7.d Section 2 Ibge 36 of41 t
Title:
LOIT NRC #2 INS'IRUCTOR GUIDE Resision: 11 ID: NRC2 Task Tisne IDA/Malf Instructor Infornsation/Actisity Assign Expected Response Standard Cosup 13OP Verify condenser steam dump FR-1Li Step capability- 7.e Check annunciator
" CONDENSER AVAll FOR STM DUMP C-9" (MIMD 5-6)- LIT Check MSIVs - AT LEAST ONE OPEN NOTE If an MSLI is received during step Perform the following- FR-Ill Step 7e, the US should go to 7e RNO arxi . 7.c RNO continue. 1. CLOSE the MSIVs.
~
- 2. Dump steam to atwmice at maximum rate (MB or locally) to dqxessurize at least one SG to LESS 11IAN 550 psig.
- 3. IF steam can NOT be dumped to aLwqice.
TIIEN Proceed to Step 9.
- 4. IYoceed to Step 7.h.
Section 2 Page 37 of41
Etic: LOIT NRC #2 INSTRUCIDR GUIDE Resision: Q ID:- NRC2 Task Time IDNMalf Instructor Information/ Activity Assign Expected Response Standant ' Camp CLOSE MSIV(s) for SG(s) to be FR-IL1 Step conserved (SGs NOTselectedfor 7.f , dquentai-dion). NOUI If the crev decides to dump stcam BOP Dump steam to the condenser to FR-ILI Step - from less than all fbur SGs they will depn:ssurize at least one SG to 7.g have to close the MSIVs for the SGs LESS TIIAN 550 psig. they do not want to depn:ssurizr. Possibic n:asons to not depressurize 1. Establish no demand signal all four SGs are- on steam pressure controller 1.) Conserve inventory in one or output. more SGs.
- 2) Minimize RCS cooldown. 2. Transfer condenser steam dumps to Steam Pressure Mode.
As the RCS cools down the Pzr. level 3. Place both condenses will decrease and may go oft-scale interlock selector switches - low. ON.
'Ihe crev should start a second charging pump. 4. Adjust v. cam pressun:
The crew may discuss initiating Si, cmtroller to dump steam to but it is probably not a go(xl idea the condenscr at maximum while in FR-1Lt. rate. US IF an MSI occurs. TillW retum to iR-Ill Step Sg 7.c 7.g Section 2 Page 38 of 41 L_ _
Title:
3DIT NRC #2 INSTRUCTOR GUIDE Revision: R ID: NRC2 Task Time IDNMair- Instructor Inforenation/ Activity Assign Expected Response Standard Coenp j DOP Establish condensate flow FR-1L1 Step alignment to selected SG(s). 7.h OPEN the TD FW pump diMuy FR-ILI Step isolation valves (3FWS-MOV23B 7.h.I and 3FWS-MOV23C) Imcally, (Turbine Bldg. northeast FR-ILI Step , 38") OPEN main feed pump bypass 7.h.1 RNO l valve (3FWS-V996). l Throttic OPEN the FW regulating FR-1LI Step ! bypass vahr(s) to selected SG(s) 7.h.2 l as desired. i DOP Verify scIccted SG(s)- LESS FR-Ill Step = TIIAN 550 psig. 73 : Retum to Step 7.c. FR-1L1 Stcp 7.IRNO ! BOP Maintain selected SG(s) pressure FR-IL1 Stcp LESS 111AN 550 psig. 7.j j DOP Maintain condensate flow to the FR-!LI Step ! selected SG(s) using the FW 7.k , regulating bypass vahr(s). t . Oseck SG Imveis. FR-IL1 Step l 8 l l Section 2 . j; Pace 39 of 41 !
Title:
LOIT NRC #2 -INSTRUCTOR GUIDE Revision: 9 , ID: NRC2 Task Tiene ' IDA/Malf -. ' Instrictor Information/Actisity Assign Expected Response Stand rd Coenp NOTE SG NR level will be < 6%. US DOP Verify NR level in at least one SG FR-ILI Step should perform step 8.a. RNO - GREATER T11AN 6% (42% 8.a ADVERSE CIMT). 3 BOP Perfonn the following- FR-ILI Step 8.a RNO I. Vcrify feed Ilmv to at least i one SG as follows-j WR Icvel in at Icast one SG is increasing. Core Exit TCs are stable or . decrcasing. , 2. IF feed 11mv to at least one SG is veriGcxL TIIEN Maintain flow to restore NR level to GREATERllIAN 6%(42% ADVERSE ! CIMF).
- 3. IF feed fimv can NOT be verified. TIIEN Proceed to :
Step 9. 1 ' The US should transition to 150.1 US Go to pmcedure and step in efTect. IR-ILi Step , 8.b i I Section 2 f Page 40 of 41 [
Title:
LOIT NRC #2 TNSTRUCTOR GUIDE Revision: 9 ID: NRC2 Task Time IDNMalf Instructor Information/Actisity Assign Expected Response Standani Comp FRFF7Fr STOP THE SESSION WHEN 1RE CREW TRANSTHONS TO ES-0.1 I;wl Evaluator- Request a final classification from the US. A RF- CHARUE 1 based on Red Heat Sink and required Feedner Hmv Can NOT be established within 15 Mnutes (RCB1). Section 2 Page 41 of 41
SFCT10N 3 SIMULAIOR EXAM SEQUENCE OF EVEN'IS
SUMMARY
litle: LOIT NRC EXAM 2 ID Number: NRC2 Revision: 0 llME 'QA_ INSTRUCTOR AIDS DESCRIP110N MALF. RF.10 T-0 Malf FWO7A Motor-driven Feedwater Pump Trip Malf FW21B "13" Aux Feed Pump disch. valve closed Malf FW19 TDAFW Pump trip on overspeed Malf FW33C "C" Condensate Pump coupling shear Malf RP09A Manual Reactor Trip Failure - Train A Malf RP0913 Manual Reactor Trip Failure - Train 13 Malf RP10A Automatic Reactor Trip Failure - Train A Malf RP1013 Automatic Reactor Trip Failure - Train 13 1/0(FW) 1-3CNM P1C AASTOP to " False" T= WD Valve Cycling Complete Malf RX15 PT507 fails low T= AOP 3571, att "J" Complete Malf RX09A PT455A fails high T= Event 3 complete + 1 minute MALF FW01 Lowering Condenser vacuum 1 T= Plant stabilized Malf 1/0 (CV) 3CilS'AV814913 to "CLOSE" letdomi isolates T= Event 5 complete + 1 minute Malf FWO3A Trips the "A" Condensate Pump Section 3 Page1 of1
SECDON 4 . VAUDATION OIEGUST Titic: . LOIT NRC EXAM 2
- ID Number
- NRC2 Revision: 1 Remote functions: Verified by All remote functions contained in the guide are certified.
hblfunctions: All malfunctions contained in the guide are certified. , Initial Conditions:
'lhe initial condition (s) contained in the guide are certified or have been developed from ecitified ICs in accordance with NSEM-4.02.
Simulator Ooerating Limits: 1he siniulator guide has been evaluated for operating limits and'or anomalous resportse. k l Test Rmt The scenario contained in the guide has been / b test run and validated (validation sheet completed, next page)on the simulator. Simulator response is reasonable and as expected. Enmination Scenario Review The dynamic examination review checklist , is complete. S.: tion 4 Page 1 of 3 m__.-k
StrI10N 4 OPERATIONAL EXAM VAUDA110N SlHIr Program Etle: 1 icensed Ooerator Reannlification Training
. Etle: LOIT NRC EXAM 2 ID Number: NRC2 Revision: Q By their signature below, the people acknowledge the confidentiality and validity of the
- material contained within and will not willfully disclose its contents to othen; enrolled in the Millstone Three Licensed Operator Requalification Progmm.
VAUDA1B) BY: hint Signature Date SM N/A- / US A1 n~I Ludw / m vy
.M m
g/nhi RO / BOP /l&/d m / v^' /c # / / _ 6 /J 7M ?
/
1 /
/
/
/
/
/ _
I Section 4 Page 2 of 3
SECIlON 4 DYNAMIC EXAMINA*I1ON RD'IDY 01FfKLJ5T Note: 1he following criteria list scenario traits that an: numerical in nature. A second set of numbers indicates a range to be met for a set of two scenarios. Quantitative Attributes 8 13. Total nulfunctions inserted: 4-8/10 14 3 14. Malfunctions that occur after EOP entry: 1-4/3-6 2 15. Abnomul Events: 12/23 2 16. Major Transients: 12/23 J 17. EOPs used beyond primary scram response EOP: 13/3-5 1 18. EOP Contingency Procedures used: 03/13 70 19. Approxinute scenario run time: 45-60 minutes (one scenario may approach 90 minutes) 60 % 20. EOP run time: 40-70% of scenario run time 2 21, Crew Critical Tasks: 2-5/5-8 yes 22. Technical Specifications are exercised during the test COMMENTS: Section 4 Page 3 of 3 - w - - [
SECDON 5 REFERENCl3 AND CRIDCAL TASK *IRACKING
Title:
. LOIT NRC liXAM 2 . ID Number: NRC2 Revision: Q
- l.
References:
AOP 3571, Instrument Failure Response, attachment D. AOP 3559, I.oss of Condensa Vacuum AOP 3575, Rapid Downpower EOP 35 E-0, Reactor Trip or Safety injection. EOP 35 ES-0.1, Rx Trip Response EOP 35 FR 11.1 Response to 1.oss of Secondary 11 eat Sink EOP* ERG _EXE Westinghouse Owners Group Exceutive Document EOP* Step _ DOC MP3 step desiation Document EOP* ERG _ IIP Westinghouse Owners Group Background Document EPlP*EPIP4400 Event Assessment, Classification & Reportability L NUREG'1021 rev 7 Examiners Standards
- 11. Critical Tasks Covered in this Test:
NOIE : Critical Tasks are marked by an (*] within guide l CRITICAL CRITICAL TASK K/A >/- 3,0 BASIS FOR SFIFC1 TON TASK # DESCRIPTION Exams only Section 5 Page 1 of.2 e
-J
E-0-A Manually trip the reactor from 000-029 Failure to manually trip the reactor the control room prior to EAl.08 causes a challenge to the suberiticality leasing E-0, step 1. 4.5/4.5 CSF tryond that invparably introduced 000-029 by the postulated conditions. SGA.10 Additionally, it constitutes an "inconvet 4.5/4.5 perfornunce that necessitates the crew 000-029 taking compensating action which SGA.12 complicates the event mitigation strategy 4.1/4.2 and demonstrates the inability by the crew to recognize a failure of the automatic actuation of the RPS." FR il.1-E Establish the minimum 059-000 Because the secondary heat sink is required feedwater flow mte to A2.01 required but not satisfactorily provided, the SG's before SG dryout. 3.4/3.6 the RCS heats up, if feedwater flow raie commensurate with core decay heat is not established, the heat sink CSF is challenged. With continued insuflicient feedwater flow, the SG's dryout, causing an RCS pressure increase that open the P7R PORVs. 'Ihe open PORVs create a small bn:ak LOCA that eventually challenges the core cooling CSF. Ultinutely, the fuel matrix / clad is challenged. Section 5 Page 2 of 2
SFfl10N 6 SCENARIO INTIRL 00NDIDONS Reactor Power: 100 % Opemting ilistory: 250 days on line RCS Boron: 988 ppm Core Bumup: 10,500 MWDMTU Condensate Demins: 7 IN SERVICE Evolutions in Progn ss: NONE Major Equipment OOS: *
"A" Senice Water Pump for preventive maintenance.
"A" MDAFW Pump for motor bearing replacement.
"B" Stator Cooling Pump for preventive maintenance.
1 Cnnv Instmetions: Maintain present plant conditions. Perfonn Steam Generator Blowdown valve cycle as per SP 3670.4 (Routine PMs), step 4.1.3.
- Plant / Simulator Diffen ness; Rad Monitor IIistorical Data-Simulator Rad Monitor historical data not valid prior to the beginning of this exercise.
Reactor Makeup System batch counten; different from plant system. (If required to perform a makeup evolution, refer to the RO procedure can for setting the Batch Counter.) All Main steam atmospheric dump valve controllers are different from plant. Section 6 Page1of1 e . . .. .
W 9 ( Scenario Events Facility: M111 stor.; Three Scenario No.: 3 (Rev.2) Examiners: Operators: Objectives: The crew will conduct the downpower to 90% power. During the downpower, after reactivity control has been demonstarted; The "D" SG level transmitter will fail to zero, the operators will be required to take manual control of the "D" SG feed regulating valve. after taking the actions in AOP 3571 and addressing Tech Specs., the crew will be able to return to automatic control of the feed regulating valve. All the necessary preliminary checks of the motor driven feedwater pump will be completed and the crew will make start the third condensate pump in preparation for swapping the feedwater pumps. When this is completed, a power range channel will slowly fail causing the rod control system to move rods. The operators will take manual rod control and will be able to bypass the affected channel. When rod control is returned to automatic a contintos rod insertion begins. The operators will need to trip the reactor to stop the insertion. When the reactor trips, the turbine will fail to trip nor can it be run back. The operator will need to close the MSIVs. The shock of the MSIVs closing will cause an unisolable steamline break inside containment. When containment pressure reaches 23 psia, the automatic CDA wl]l not occur. Initial Conditions: The plant is at 100% power. Excessive vibration exists on the "B" TDFWP. The crew will be directed to reduce power to 90% at 1/2% per minute and swap feed water pumps. Turnover: The crew will be provided the MP3 simulator standard turnover sheet which will airect them to reduce power to 90% at a rate of 1/24 per minute. The following equipment will be out of service: "A" service water pump, "A" motor driven AFW pump and the "B" stator cooling pump. There are thunderstorm warnings for the next 4-6 hours. . e _a
ig Event Malf Event Event Description RCL. ECL. 1.yD2 1 R/N The crew will reduce power to 90%. 2 I The "D" SG 1evel transmitter will fail low requiring manual control of the "D" SG feed regulating valve. Once the procedure steps have been completed, the i operators can restore the feed regulating valve back to auto control. 3 N The crew will start the third condenrate
-pump in preparation for swapping the feedwater pumps.
4 I An NI power range channel fails high which will result in manual rod control. The crew will be able to remove the channel from service and return to automatic rod control. 5 C When the operator returns rod control to automatic a continuos insertion of the control bank "D" rods will occur. The operators will attempt to return the rods to manual. control. The operators will be unable to stop the insertion except to trip the reactor. 6 C When the reactor is tripped, the turbine will fail to trip. Additionally the turbine will not runback nor will an automatic main steamline isolation occur. The operator will have to use the control switches to shut the MSIVs. 7 M When the MSIVs are closed a unisolable steamline break occurs inside containment. This will result in a safety injection actuation. g . .. . ..
. 1 g 8 C When containment pressure exceeds 23 psia, an automatic CDA will not occur.
The operators will need to manually C initiate CDA at the component operating switches (pushbuttons failed also). 1
~
1 'Y SIMULATOR EXAM GUIDE APPROVAL SHEET 1.
Title:
LOIT NRC #3 1D Number: NRG Revision: 0
- 11. Initiated:
J. William Cote 5/28/97 Developer Date l i 111. Reviewed:
, na Cf27lD
%WW/ e_---- ~ i> ate IV. Approved:
pb Operations Manager Date s'
.v v OptTator Training Supervisor de\7 Date z
i [ , .
. . __)
SIMULA'IDR EXAM GUIDE TABI F OF CONTFEFS SECTIONS LISTED IN ORDIUt
- 1. Exarn Overview-1 l 2. Instmetor Guide l
- 3. . Sequence of Events Summary
- 4. Validation Checklist
- 5. Reference and Critical Task Tracking Fomi
- 6. Scenario Initial Conditions Sheet
SECTION 1 ELul OVERVIEW
Title:
LolT NRC_f3 1D Number: SRC2 Revision: 0
- 1. Exam Ilrief:
The crew will conduct the downpower to 90% power. All the necessary prelinsnary checks of the motor driven feedwater pump will be completed and the crew will make the swap of the feedwater pumps. During the downpower the "D" S'O level transmitter will fail to 0% over 3 minutes. The operators should enter AOP 3571 to address the failed instmment. Once the failed instrument actions are complete, the crew should complete the downpower. When the downpower is completed, the crew will start the "C" Condensate pump in preparatiom of transfering feed pumps. After the "C" Condensate pump is staned, a power mnge channct will slowly fail causing the rod control system to move rods. The opemtors will take nunual rod control and will be l able to bypass the affected channel. When rod contml is retumed to automatic a continuous rod insenion begins. The operators will need to trip the reactor to stop the insenion. When the reactor trips, the turbine will fail to trip nor can it be run back. The failed turbine trip will cause an excessive cooldown and result in a safety injection. The operator will need to close the MSIVs to stop the steam Dow. The shock of the MSIVs closing will cause an unisolable steamline break inside containment. The leak will stan slowly and upon exiting E-0, the leak will rapidly escalate and fon'e an Orange Path on CThff Integrity. When containment pressure reaches 23 psia, the autonutie CDA will not occur and the CDA pushbuttons will fail to actuate.. 'fhe crew will need to transition to FR-Z.1, Response to liigh CBff Pressure, and manually actuate CDA. Initial Conditions: 1he plant is at 100% power. Excessive vibration exists on the "B" TDFWP. The crew will be directed to reduce power to 90% at 1/2% per minute and swap feed water pumps. Tumover: The crew will be provided the MP3 simulator standard tumover sheet which will direct them to reduce power to 90% at a rate of 1/2% per minute, lhe following equipment will be out of senice: "A" senice water pump, 'A" motor driven AFW pump and the "B" stator cooling pump. There are thunderstomi wamings for the next 4-6 hotus.
- 2. Plant / Simulator differences that may affect the scenario are: None.
- 3. Duration of Session: 90 minutes Section 1 Page 1 of 2
-)
SECI1ON 2 INSTRUCIOR GUIDE
Title:
LOIT NRC #3 ID Number: NRC3 Revision: 0. All Control Room Corviirt Onerations and Communications shall be in accordance COP 200.1.Corviirt of Onerations. and OP 3260. Unit 3 Conduct of Oix mtions. I i l " Review the Simulator Operating Limits (design limits of plant) and the Simulator Modeling Limitations and Anomalous Response List prior to performing this training scenario on the simulator. 'Ihe instmetor should be aware if any of these limitations nmv be exceeded." (NSEM 6.02) r Section 2 Page 1 of 40
.__J
SM1UlXIOR PIK)llIFMS DURING INAMS It is the responsibility of the Instructors in the simulator to insure that exam interruptions have a minimum negative impact on the Crew and the examinations we provide. Be aware that at all times the Operators should treat the simulator as ifit were the plant and you too should treat it as much like the plant as possible when they are in the simulator. As soon as the htstructors are aware of a simulator problem tlut will adversely affect the exam in progress (computer fault, etc.) the htstructor should:
- 1. Place the simulator in FREEZE if possible. ,
- 2. Announce to the Crew that there is a simulator problem.
- 3. Request that the Crew leave the simulator control room. (De Crew should leave the simulator for problents which involve nujor switch alignments).
- 4. Deal with the problem (reboot, call STSB, etc.)
l
- 5. After the Instructors believe the simulator is restored to senice, the Crew should be told how the exam will continue, ifit is possible and felt to be acceptable to the evaluators, the examination can begin where it left off with an update on plant parameters and each Crew member is prepared to restart. If the examination will not begin where it left oft, the crew should be told how and where the exam will begin again.
- 6. Once the Crew has been told how and where the exam will begin, have the crew conduct a brief so that the Instructor and evaluators can insure that the crew has all the necessary infomution to continue with the scenario.
- 7. Once all Crew members, Instructors and evaluators are satisfied that they have the necessary infornution to continue the scenario, place the simulator in RUN and announce to the Crew that you have continued the evaluation session.
Section 2 Page 2 of 40 _ _ - - - - - - 9
Title:
IDIT NRC #3 INSTRUCIDR GUIDE . Resision: B ID: EhD Task Time IDA/Malf Instructor Infornostion/ Activity Assign Expected Response Standard Cosnp DTAT#6 ' TTI1 R INfilAL SEIUP Setup Irstructioss: ! LeerIDTas folkms : ; At any XERM window, type <idt> ' When the SUN asks for an executive type- UEXEC or RTEXEC? cnter <r>: this will bring up a blank idt page. To go to a previously saved idt file type <n:ad> at the prompt When the SUN asks for a file name of the file you wish to view type in the qvgaate file name- ; He old "Imxkm" files are as folkms: Old ISD pages 1-8 are idt file OPS Old ISD pages 9-16 are idt file OISI - Old ISD pages 17-19 are idt file OPS 2 o IE the step counters are at/ncar 000, HEZL RDKNE the S'EP COUNER OVERRIDE.
- i allow the counters to step out during the IC reset.
Reset to IC-14 : RDNSTATE the step counter OVERRIDE Place Simulator to RUN RESET the time constant on the PZR level controller by PLACING the PZR Master Ixvel controller in MANUAL l then retum the Controller to AUID. Set the STEP COUNERS 1
- place the Main Turbine on the LOAD LIMfER ,
Verify annunciator, "COMIUER FAILURE" (MIMC,1-1 I). is NOT LIT. Place MOL Cune Book in Shelf for Operator use. Remost other Cunt ikxis from the floor. Clear the DCS Alarms : Reset the Rad Monitor CMFIR Console by Depressing the "Srmus Grid" button twice. Section 2 i Page 3 of40 I t - - - - i
Title:
LOIT NRC #3 INSTRUCIDR GUIDE Revision: 11 ID: BRQ Task Time IDA/Malf Instnsctor Information/ Activity Assign Expected Rgw,- Standard Comp PIA ' HIE FOIRJWING EQUIPMENTIN I'II Djuipment OOS: "A" Service Water Pump "A" Motor Driven AFW Pump ,
"B" Stator Water Cooling Pump At MB5 place the MDFP aux oil punp on (IMirP2).
i Insert applicable CREW EXAM Tape into the VCR. , Synchronize the MONITOR Time Display with BIG BEN. i Initial Mdrunctions
/IOs/IDAs: i T-0 RP06A Failure of CDA to auto actuate Train "A" T-0 RP06B Failure of CDA to auto actuate Tmin "B" T-0 TC03 Turbine Fails to Trip T-0 TC04 Turbine Fails to runback T-0 RP08A Train "A" MSI Auto Failure T-0 RP08B Train "B" MSI Auto Failure T0 I/0 under RP heading PB2-3 ADS-CDA value = "OIT" CDA actuation pushburton failure T-0 I/O under RP heading PB3-3 ADS-CDA value = "OIT" CDA actuation pushbutton failure lead Examiner: Referto the ' Briefing Script forthe Operational Fm"and brief the cirw.
Booth Iminsetor: Commence Recording Sirradalorsession Section 2 Page 4 of 40 e
.. - - _ _ _ . . .- ..-. . - _ . - .. - . _ = . .- .
Title:
LOIT NRC #3 INSTRUCTOR GUIDE Resisions R ID- NRO ; i Task j Time IDA/Malf . Instructor Information/Actisity Assign Expected Response Standant Coeny Booth Imtructor IVrfonn the crew tunmer(initial Conditiom page at esul of LP) with the crew.
- i f
i i t i
!P l
I i. l r i l Section 2 Page 5 of40 m_ - -.
Title:
LQLT NRC #3 INSTRUCTOR GUIDE Revision: 0 1D: LNRQ Task Time b +;s M alf Instructor information/ Activity Assign Expected Response Standard Comp 4 Event 1: Shift of the Main Feedwater Pimqw. e CREW Enter AOP 3575. Rapid downpourr. AOP 3575
')
Entry conditions AOP 3575 Rev. 5 CREW Determine Itwer Reduction Rate AOP 3575 (*Nnin). Step 1 US Check desiredI xmtr reduction rme- AOP 3575 LESS llIAN OR EQUAL TO Step 1.a 5Wmin. NOT requested by CONVEX US Check pourr reduction a CONVEX AOP 3575 requested Emergency Genertti# Step 1.b Reductiort Ops Management order uns to US Perfoan the foiioning- AOP 3575 perform at 1/2% per minute Step 1.b
- 1) Detennine pourt reduction rate RNO using Table.
- 2) Proceed to Step 2.
US Check Rod Contml in AUIII AOP 3575 Step 2 Only lourring Ixmtr to 90% Rod US If during the performance of this AOP 3575 insertion limit should not be procedure the Rod Insertion Io-lo Step 3 reached Limit is reaclxx1, Go to AOP 3566, CAUllON Section 2 Page <. . , s- ,
Title:
IDIT NRCE INSTRUCTOR GUIDE Revision: H ID: NRQ 4 1 Task Time IDA/Malf Instructor Information/ Activity Assign Expected Response Standard Comp Immediate Boration. NOT CONVEX Requested CREW Ifload nxiuction is a CONVEX AOP 3575 requested emergency genemtion Step I reduction, the fblioning apply- NOTE 1he Unit i Shift Manager will determine how the load nxluction will be shared among the Units. DO NOT stop a CONVEX "Emergeng' Load Reduction" request due to AFD cxceeding _ the target band.
'Ihe load reduction must be completed within 15 minutes of notification.
B00111 NOTE >> AT either95%poweror Examiner's CREW Initiate Imad Rc6xtion. . AOP 3575 cue, Initiale Event 2, Faihae of 'D" Step 3 S/G Irvel trasmitter(go to page 12). US Check power reduction a CONVEX AOP 3575 requested emergency genemtion Step 3.a reduction.
,xtion 2 I> age 7 of 9 u- ------ _ - - - -
Title:
LOIT NRC #3 INSTRUCTOR GUIDE Revision: 9 ! ID: NRQ Task Time - IDA/Malf Instnictor Information/ Activity Assign Expected Response Standard Comp If .uluested, Infimus CONVEX of 120 MWe US Inform CONVEX ofl<xxl axiuction AOP 3575 teil them to reduciion at 1/2% per n.inute(would mte (Mut/ min) and final Mwe levei. Step 3.a maintain be ~ 6 MWE / min) RNO current MVAR. hxxiing Not in Standby BOP Check turbine NOT in STANDBY AOP 3575 LOAD contral. Step 3.b BOP Check LOAD LIMIT LIMIllNG light AOP 3575
- LIT. Step 3.c
'lhe shill to I2xxl Set normally BOP Intermittently Press DECREASE AOP 3575 sheds 5 to 30 MWe. 'Ilr crew LOAD pushbutton until LOAD LIMIT Step 3.d should monitor nxis as they begin LIMlllNG light - NOT LIT.
to insent in auto. BOP Rotate LOAD LIMIT SET adjust AOP 3575 know at least one full tum in raise Step 3.c direction. BOP Select DECREASE LOADING AOP 3575 RKE to ON. Step 3.f 1/2% per minute BOP Select LOAD RA1T: LIMIT AOP 3575 WMIN to required pourr Step 3.g reduction rate (Wmin). Secti<m 2 Page 8 of 40 i L____________. .. -
Titler LOIT NRC #3 - INSTRUCTOR GUIDE Reaision: 9 ID: MILQ Task 1 Time IDA/Malf Instructo- Information/ Activity Assign Expected Response Standard Comp j
.9 x 1200 = 1080 MWE BOP Utilizing DECREASE LOAD AOP 3575 pushbutton, Adjust LOAD SET to Step 3.h ;
desinxi final Mwe (poutr level). BOP Maintain initial MVAR loading AOP 3575 during pourr reduction unicss Stcp 3.i directed otherwise. US If at any time the pourr reduction AOP 3575 mte must be changed, irturn to Step 4 Step 1. NOTE US Verify 3tmer Reduction Rate - AOP 3575 GREATER 111AN OR FX2UAL Stcp 4
'ID 3% MIN.
US Pmcced to Step 7. AOP 3575 Step 4 RNO During tbc power level change AFD US Boric acid total volume addition AOP 3575 may go outside the target band but it and flow rates are based on Step 7 - will remain within the curves for approximations. Adjustments NOTE RAOC so no action is required. should be made to tir volume addition or flow rate as necessay DCS may alarm dur to stator bar. to ensure the reactor reaches the tempemtures incicasing. 'Ihe ennv desired end state of: may check the ARP. No action is Tavg on pmgmm required. Rods above the Rod Insertion Limit AFD on or above the target va!ue Section 2 Page 9 of 40 l . . . . . . _ - - -- t_
Title:
LOIT NRC #3 INSTRUCTOR GUIDE Revision: R
.ID: NRQ Task ,
Time IDA/Malf Instructor Information/ Activity Assign Expected Response Standard Comp ! RO Align RCS Makeup System For AOP 3575 - Horation. Step 7 10 x 15 = 150 gallons US/RO Determine required boric acid AOP 3575 addition by multiplyirg Step 7.a total pour change (a%) by 15 (gal /%) = gal 150 gallons RO Set the boric acid batch counter to AOP 3575
~
total gallons of boric acid rtquinxi. Step 7.b l RO/US Check power reduction rate - AT AOP 3575 1 0.5%' min. Step 7.c . RO Adjust boric acid blend flow AOP 3575 controller pot setting to 1.9 (7.5 Step 7.d gpm). RO Place reactor coolant makeup AOP 3575 control mode switch to BORATE Step 7.e RO Select START on reactor coolant AOP 3575 makeup start switch. Stcp 7.f RO Fncrgize all PZR heaters. AOP 3575 Step 7.g NO action required. this will be done BOP Rethre Steam Supply To The AOP 3575 automatically. MSRs, Using OP 3317, Retrat and Step 8 n1oisture Separator, Section 7.8. Section 2 Page 10 of 40 o__
Titic: LOIT NRC #3 INSTRUCTOR GUIDE Rcvision: H ID: NRQ Task Time IDA/ Malt Instructor Infornatian/ Activity Assign Expected Response Standard Comp US Check if RG Sample is RequimL AOP 3575 , Step 9 l NO sample will be required. US Verify change in Reactor Power - AOP 3575 GREATER TIIAN 15% IN ONE Step 9.a iIOUR. US Proceed to Step 10. AOP 3575 Step 9.a RNO US Verify Target PbwerIrvel - IISS AOP 3575 111AN 50% Step 10 B00111 NME>> - At exarniners cue or pwer reduction CREW Continue power nxluction to AOP 3575 complete, Go desired target power Icvel. Step 10 To Everd 2, Phge 12. RNO WilEN final power level is reached,] LIEN Proctu! to Step 20. CREW Check Plant Status. AOP 3575 Step 20 RO Verify - AT TARGEl' POWER AOP 3575 LEVEL Step 20.a RO Borate or Dilute as necessary to r.. '3575 _ maintain AFD as close to the target Step 20.b value as possible while maintaining nxis above the Rod Insertion Limit. Section 2 Page 11 of 40
l il p m o C 5 5 5 dr 7 50
- c. 7 d.
50 7 c. 5 0 5 7 5 7 a. 5 7 a. 5 7 b. a 3 2 32 32 51 32 51 52 52 d 32 3 2 32 n P p P p Pp P p P p P pO Pp t a Oe t Oe Oe Oe Oe OeN Oe AS t S AS AS t AS t AS t ASR t AS t y r ca p ). fd f t n R S i t m n, md um y ona o a aio r c t t l l l P C R mPi o it di u n n uX ni uh
- t u C,d meq age oE oS tnle n
o e i n a4A d ar ef ies r mV m1 l ab a i s n t a r0 t s (i g nm aN at P c i i s v o b o o3l fpP 3 c a eh n oe dOn d n n i l l ap e p s y i h c i w i t c d eon aC . aU np nA R u t n o eOem t e r i o ut n o2 o R t s ka gh nws o l d st ec i otnp 2 ot n Nng i . ms l o e uu i i 2 0 minC t t d e Tr F r r qd e o e l i eo his n4 e el sd Eo e ree ptcS t l i pt t iU of h p e r c mu t t Sun 2 mu c S c i c o e p x CmRop t s Cn a 7 Ee Re s l ht n w oXn pEi o od cerd t o od c r r. W s s. e nowe t S1 e2 naeoun uih ie E e u n i t t n kVt a t r t e tr r g nt e qm ck - o r orc oea ian eo i grki e ace t e x fr eNen c pu c pw na t nex r g a Rb l AoMs p l Sn ex t I hoe CCg e om R pP Re pM o opn COP P n W kg i P E s s as S O O S S S S R TA U R B U U U U C t y E i v D I i t c U / A G n y . o r a R i t s O a s T e m c C r e fo n U n e R I b T r t o S o n N t c I u r d l u t s o n h I S f l 3 a
- M C /
A R D N I T I Q OR LN l t e'
'e m
TID i i T t
)1 ljllllll!
p m o C 1 s i 2 3 4 i t 7 n 1 7 1 1 p 1 p 1 p 1 p r 5 o 7 7 e 7 e 7 e 7 e a i 5 5 5t 5t 5t 5t 3 t 3 3 s 3 s 3 s d i 2 3 3 s n -ndn 1 P P P P N. PNL a Oep p P N. P N. t S Otno AEC Oe Ot t Ot t Ot t Ot Ats Ats A A. AA AA AA l r n y Q. m t t ei r b no n e c o c ml i s L t ul ao r A pe n l a r r at pn t e d eU d e l u n nn o e s u n gc o e m fNe eL pA i l e u i n m nc l i s v o p u n i t n d e m a GA SM sU pN o n n e e at p at R s e i c dn m uA o h a R e k aV 1 i t nf e t n a t ei pM l t de cm t R 7 i f ce e 2 0 e a t d oF 5 l p flev dei n v e l et a n4 e t 3 ht he f a i e fc si fa e of l t c PG P av c o i e e te L ht G h t O/S O eg e et p x B " A i n cA e z h n t ht cr S ht g S1 e3 E mlaU i l e n rD e r e r pN e i l i fl ya t f ym i r o t i at e g b fe ec l " iu i t Oo nf t n t eda n a r eg r e n t s e a E dam S t Vre Voc R Dse el P k g n W E W W s s i E E P P P P as S R R R O O O U C C O TA C B B B B r G
/ t of o e r
o S s e l d f y n i 2 t l i an c E i v "U f r e l rl u c d e D i t c oc l d n I f i n n U A o t ag m a G
/
n e cn t n ao st h c o m i i dl o s u R i h nl o c ua t cl . O t a i a F r i l t n d e csi n l ee e v F m eo t i d r sl e C fo r wtet vC r( fe c yi l c dR U oi I f a l R I n Sms l R45
)
a mtm uN o T r 2
- n a N5 i s
Po n hGs/ S o " T Oc N t c T T r L) V wS G I u r N e E v l D(S R F Be v
&e a e
r" cD t s n V x Gm"
/eD D S l e" I E I Sz" " Ut o heh Tt f
%0 08 l 1 3 a P0 .
h 1
- 2 = m E*
1
- v. oc -
C A Xv e . R D Rs r. se N I T I Q r O R e LN e 5rrsn 1 oe e l t iD i m R x%i 5 m TI T =9am x T=EO L
l ; 1 j ii)))ll)IIll li' 1' p m o C 5 6 7 dr 1 p 1 p 1 p 1 7 5 t e 7 e 7 e 7 a 3 s 5t 3 s 5t 3 s 5 a d 3 n P N. t a Ot t P N. Ot P N. Ot t P OtN.7 t p S AA t e AA AA AAts d n ad . t 1 d e gO , a s 1 e ) e d t r. h eg d e d p mn T e zdnpna r odeg e t n1 ax p sPs i s aiUt i
)
xl a orp pD p pD seaA l dl x
.t l ba a rein i
(s b ut s n o e ec rt mla4 0 umI d ugn t s s y l a a pM ri c r wla u m1 pU e ob ei r s oa ol tex i ct a ce i t l s n t smngp - t r r c e et et t de o p e =0iAedl viaani f as n et h R s e r sa eid r wee nc4 i nnf i f el af er o acl uh h n i urSe R ei b i k an t
- r. f r er n t s u hmg r i apr ot n e wlof o ro el:mahl e e h too n io i
R o u c ei n moge nn l t l 2 0 o etndh t d c v of t l t c i t sp n nn e ororger er o ea iaI h yp n4 cet o i e el t t k nph t l e f et t iB wSr i c pc of c s l ih snroct oP a gv nc eae v ol anl d . e eaia i o nn t e Gant e nMsps r h rt t c p x l e v Sc mr Rc(lpcP o cet eo exn e i o )s c et t h es sA S1 e4 E e n t
/s o nr v ni mi(
r c t e r at ee mui d e t l edf ei er myn i h et u e c viuh g e e r h s t e oq a bo eqf a Wfe ep* t ht
- Wbano opac DP r er l P ar o P
s n W kig P E s s as O R S S TA B C U U y d t n e E i v s . D I i t c t o U A
/
t pe s G , n el o 1 Dba R i t t e t O a S Cis F m &bp r n C U fo i o I ti n t c cr a t M e nt o I t t 1 r r m o s o P cn N t c a u l I , l i c r 4 i t s 5 5 unhi n T L Sc I Ute f l 3 a
- M
/
C A R D N I T I G O R LN l e e t m iD TI i T
- i f llL
Title:
LOIT NRC #3 INSTRUCTOR GUIDE Revision: D ID: NRO Task Time - IDA/Malf Instructor Information/ Activity Assign - Expected Response Standard Comp r, 33.1, function 13, action 6 SM Refer to Technical Specification AOP 3571 33.1,33.2,333.5 and 333.6. 33.2, function 5b & 6c action 20,21 Att.N Surveillance procedures will confirm Also circk suneillance procedums step 7b that no actions required for 333.5 SP3673.5 and 3673.6 and 333.6 CREW Check the existing bistable status AOP 3571 to ensure a reactor trip will not Att.N occur when the failed chararl is step 7c tripped. T= Request to RXR106 'OPEN"1%ecction Set 1 Door SM/ Request the I&C Department trip AOP 3571 Trip IVSs RXRl34 "IRIP" P-14, IS554B US the appmpriate bistabics using Att.N RXR81 "IRIP" La level Rx Trip IS554A Attachment N.and Attachment R. step 7d RXR106 'GOSE"1%tection Set 1 Door RO Verify the appropriate bistable AOP 3571 status lights are lit. Att.N step 7e SM/ Request I&C Department perfonn AOP 3571 US corrective maintenance on fhiled Att.N step 8 instrument. 1 Section 2 Page 15 of 40 L_ ____
Title:
LOIT NRC #3 INSTRUCFOR GUIDE Revision: 11 ID: NRQ Task Time IDA/Malf Instnictor Information/ Activity Assign Expected Response Standard Comp , i T= Downpowercomplete i EVErff 3: Start "C" Corx!cnsate Pump in pnqiaration to transfer Fced Pumps. The "C" pimp should be started IAW OP 3319A, section 7.9.1. T= when IMR34 Dis will open the Condensate pp
'OPEN" nxjucsted discharge bypass valves,3CNM-V39, V44, V49.
%c TDFWP master speed controller will be shifled to amnual prior to starting the third condensate pump Proceed to Event 4 aller "C" Condensate pump is running.
EVEffT 4: Ibwer Range Giannel Faihme - T= 'C' Cond. N109A Ibwer Range Giannel 41 lower PP is mnning sev=100% detector fails high. 30sec unp 1 Section 2 Page 16 of 40
lll jj ljllll4 p m o C 1 i 1 7 1 1 p 1 1 n 5 7 5 7 5t e 7 5 7 a 3 3 3 s 3 a 5 3 b d 1 2 n P OtD.pel P P OtD. pel p P p P D. t a Oe Oe Ot t t t S Ats At s AA AAts AAts r n r e s . r.
! ei oh s t r
f t e e ml l . t u t u cp t oiorp a ne ah ao s t r p gs wS t y t r d et or r r e n n e at pno t e i l o gd n n oI hc mB t ah o t u o s gc m e n ciR r c i n n a ,t onu s id r n t w di t w i v o p t at e a p u n el o: in i nw i e c rl r oct sci as m r g o l R s i t t c e ie R i nT l n a d e ufe weM c wS to nC 2 0 e a l p rhi r r ai t a de ht he l i ot cee r wl : e n4 e fa -uocf t t e nd pw po w e of mlo - 3l ht cr c o c e t L e e i t e tet uliUP of uD p i n ceA e z ht d a , , c el i S1 e7 naU e ee ssno rf x E nlpN e i l t a ht ht ehdc nc- e fe i t e dA b wh ptai c t e g DnM t a e t at r ye t mi l u a P a S D AdtoBS At fC ual _ n W E W kg i E s as s R R O O O TA C C R R R i n y d t d e E i v ec' cl a t D I i t c Tp e U A abe l
/
C n o it l ed R i O t a bh s eou' T m r l C fo l i s U n wdo R I l oR T r r r. S o t ne N' t c ol l l I u r Co rau t s dt na n I n RcM oo f l 3 a
# M
/
C A R D N I T I 3 C O R LN e e t l t : n TID i i T
, . . l l
~
Title:
LOIT NRC #3 - INSTRUCTOR GUIDE Revision: 0 ID: NRQ Task l Time IDA/Malf Instructor Information/ Activity Assign Expected Response Standard Comp T= Rmk RD02(I) When the RO places nxi contml in RO Restore Ty - Tu error to within AOP 3571 placed in when Rod "AUTU', INfflA'lE EVENT S, I *F and place nxi control in Att.D step 2 Auto Selector. Contimans hmad Rod Motion. (On automatic. Switch MOIX'OMP, select ' ROD taken to SUPERVISION' to determine kration
' Auto'. ofnxis.)
Enter RD02(II) if luink D imerts to I15 steps before the cirw trips the plant. EVENT 5: Contirmans hmad Rod Motion. Crew should attempt to plact 'tod CREW Stalilize Plant Conditions AOP 3552 control in MANUAL Crew may not Step i enter AOP 3552, Rod Contml. system malfunction. Crew may elect to trip plant based on inability to contml rod movement. Pmcedure is listed as guidance for the situation. RO Place control rtxi bank SEL switch AOP 3552 in MAN Step 1.a RO Verify - NO RODS MOVING AOP 3552 Step 1.b' Section 2 Page 18 of 40
) l ) !llI! i lij{;lj ' ! ' r p
m o C O _ N 1 dr 2R 5 p 1 p a 5 3 b. t e e d n P p 1 SE ,T S t t a Oe t 0O - 0 S AS EN E-n F d n dt o e e dT a e rad . 1 1 0n p e( 5 S nd a e ' o o i1 n 8 0 ," .s 1 i e n1 e i Ei t e f e Ih d" c psf o jc e b dNNIt oPs . e or ei n t oi n t s FAA i1 I t ep p p t s a r s t o e u Ml 1*ieE l1 " sO bil rl oeb s Gy i s n o m I
" nt a" ah s i
v e p dt e nf e CRR"lpt n csars opo g EEI pe et p T T '" a u R s aa a r R e rS p E SAA nq odt oi h t t sd e i T r d t or c o t u o R E EE't b oe is t ct a r rp e ea$yb ce r un si r o 2 0 n4 e ap ei d V RR"iun a e o"cie ntcr m t c of D GGI is t c r r l e a i c o o t Aa rSda f e p eT ht r F s el l ht Tit n h f* hbd ue l t R e e9 x o S1 E Ptca f y e I i g Re TR r e a P
- - - V kg n W E
i s s as R S S S O TA C U U U R F a k e s l e ah y "e c c
)
k( w w e Mib t n l et sl e . eht r o t E i v n e ). r l ud i e ch C Aou r l D i t l FAc4E dIs wFh c i 'en deg i t S ei MDe I U A r Cthm Dw i r
/
hwQC i G n e t t st u d o cem I o emiaZ t s 1, R i t a Ceiro l r t f v a c u r i fOteh a O a M hun h tA st e eVng d t T C mr o cs aretene ud oro a R- nI un U fo t t ppino i t F iS l mMge o ss i o ia o t R n o w s T I r g t t vi i t i a qT nod i t a emlyg r N S o d l u sietcn r s l a o f oiOie
. t s wl qi ap m
mu am t I c u h o gedeNi t r Ga
/ Fni s i
t r s ussTt eamtr uaq si t s S oeOs a hwo r t SMiywe "1 n
'Crmrc r
YPNh I I U Tasbt r e r 1 l f i p 3 l a H B5ma - d s
# M X 1 r 0
0 n 0 = C / A K S ve o R N D I I Ms%6c 7 = se T C 3 O R LN s e V I e l
- m S de t
iD TI i T Mso T= G f l?1
Title:
IDIT NRC #3 INSTRUCTOR GUIDE Revision: 0 ID: NBQ Task , Time- IDA/Malf instructor Information/ Activity Assign Expected Response Standard Comp I Check reactor trip and bypass breakers - OPEN Check rod bottom lights - LIT CI'eck neutron flux - DECREASING BOP Verify Tubine Trip E-0, Stg 2 [*] Turbine will not trip Check all turbine stop valves - E-0, Step 2.a CLOSED
RIP the turbine. E-0, Step 2.1, RNO 4
Cnny will attempt runback and then E the turbine will NOT trip, will need to close the MSIVs. 'HIEN Runback the turbine to close the control valves. E the turbine can NOT be runback
'HIEN CLOSE the MSIVs and MSIV bypass valves.
BOP Verify Ibwerto AC E.m.ymy E-0, Step 3 B mses BOP Check busses 34C and 34D - AT E-0, Step 3.a LEAST ONE ENERGI71D Section 2 Page 20 of 40
l lj ]!!I)jj)jjllIl I l l i' p m o C
- b. 0 3 4 5 5 6 i
t p p E- p p p r e e s a t t 5 a. t e e e S S 34 t t d n a 0 0-
, P p e
Sm 0 S S S t E Ot E O' 0 0 E- ES N E- E-E n b e yr a ei o n T N 9 i t o ya r. mdt r e A O a - mder
- sol D t u kcym p s p s p
c mIN 4 o hena o n 4 n o e s 3 d A 1 y c n c uA uG r i s n d e n hn P PN o n s o ga ei4 rRT aD i s v u oi n 1 p u i vl VI N e s t c l aape AR R R e C7E 4I t A c jTe hd r v nt s WE ON d 3G sR i s iLnI y-t e 5 mr Wfm rt o e P KU R R 2 0 n4 t e e sE I fe t or s pf o Ce-Cpo i cE uIN of c S vN G o i e sN er e P r t c buE Rb ei nA at p r SeO N t p f Si a e1 E x ki l I k f ync Sp ySTIN TRyI S2 e cT c f h0 e h e iu er n i r AN feE'R i r g a C1 3 C Vna - - VIeIUR VP P n kg i P s s as O S O S S O O TA 3 I U R U U R R e r u l y y l i l a t fa ci s E v ei t r i h D i t t eh at I c ht n . mt U A
/
t h os pp o a G n t ud ow .so t R i o niUt are i t a d ed eim p eu U I m t at r a t aq u e C fo r tuiote c c at t c e r U R n a os ees t t ab I es nh oT 5T r o va nr aitbf nO wt u o N l N t h l c e i I u r l l id er o wd l t wlot h us Aon u )t of l o s n I Scoc Dhi o I C (s p f > l a > 3 E
# M
/
T C A O R D N N I TQ l R M} N s e l e : m KD 1I i T il1l,
Title:
LOIT NRC #3 INSTRUCI'OR GUIDE Revision: Q ID: NRQ , j l Task Time IDA/Malf Instructor Information/ Activity Assign Expected Response Standard Comp RO Verify ECG hunps Running E-0, Step 7 Check SI pumps - RUNNING Check RI1R pumps - RUNNING
- Check two charging pumps
- RUNNING BOP Verify ARV hunps Running E-0, Step 8 BOP Check MD pumps - RUNNING E-0, Step 8.a BOP Check turbine - driven pump - E-0, Step 8.b RUNNING, IF NECESSARY BOP Verify RVIsolatior E-0, Step 9
- Check SG feed regulating valves - CLOSED
- Check SG feed regulating bypass valves - CLOSED
- Check RV isolation trip valves - CLOSED
- Check MD FW pump -
STOPPED Section 2 Page 22 of 40
~^ ^
p_ m o x C 0 0
- a. b.
1 1 0 1 t n p p p O p a e e eN e S R t t t d S S S t n , . t a 0, 0 0. a. 0 S E- E- E0 1 E-i D D k u 0 6 9 E iE o s
- S s uS h R T
6 s a s nL O e v fOc S 1 N p i n wC mla l aC L s e A A l b b y n o e t p u o d - d mv c n E R i T 0 V i s s n ws wn i - ms U G 1 I V oe oi o S ee p S i v o S v m e S e e p s I l bl a l b a t h v cl a a r u R E t s M R l o e L R e DD 1E Gv Sn GsD Si Gv Sn S t s s e O e mi r I d nD aE 2 0 d kcPP ki o kl eE S ki o i n r pi a r o op frt e sS n4 e ct a c pO a s VOL cta t p e p s of t c e hR eI el h o hemL a el h o Md e m 8 m n o I SC i c o t p CT Ci s CsC Cis ft t C1 Tt e3 i M-x I al E ko s kN G Od S2 cI e c eA S Ne ec ys f e e g he h 1 yig Oo r i r v a CH C1 1 ns DP el a P
- - - - ap Vv n /
kg i P P P s s O O OO as B R S O TA BR U B e r g u s t y n s e y i s r l E i v d e a p l a D I i t c s o t r F t u c t n U G A
/
n l c y i n Mi I o n e v o l e Ctp e R i t s u b a
. f es d O a o l l i i
e T m r i v iwp s Oeh i r u C o e r e8 Nt q U f n p r u 1 Rd e e r R I e r sn mh e T r t s a r c b S N t o u eh r Pt s fo r r ea l l c s et i I u r V F s e po w t s n I S Mlu I t y n as a A D I M Cb Mh C f l 3 a
# M C /
A R D N I T C I 3 OR LN l e e t : m TID i i T (
Title:
LOIT NRC #3 INSTRUCTOR GUnsE Revision: 11 ID: NRQ ; Task Time IDA/Malf instnictor Information/ Activity Assign Expected Response Standani Comp Crew may paxxed past this step anel probably NOT retum bec nise they ; will use FR-Z.l. I Should not be required at this point RO Check if CDA Required (E-0, Step 11) [*] l RO Check Ctmt pressure is GREATER E-0, Step 11.a 11IAN 23 psia DR Ctmt spray is initiated US DO NOT pr'orm steps 1Ib,1Ic, E-0, Stept 1,a, anxi iId. Proceed to step 12. RNO BOP Verify CAR Fans Operating In E-0, Step 12 Ernergency Mode US Check CAR fan status: E-0, Step 12.a BOP - CAR fans A and B - RUNNING BOP - CAR fan C - STOPPED Section 2 Page 24 of 40 c__--
Title:
LOIT NRCJ_3 INSTRUCFOR GUIDE Revision: R I ID: NRC3 ) Task Time IDA/Malf Instructor Information/ Activity Assign Expected Response Standard ' Comp US- IE CDA is actuated, TIIEN E-0, Step Proceed to next immediate action 12.a. RNO and do NOT perform steps 12b and 12c. RO Verify CIA E-0, Step 13 RO Check ESF Gmup 2 status columns E-0, Step 13.a 2 through 10 - LIT RO Verify 1%per ESF Statis Panel E-0, Step 14 Indication RO - Verify ESF Group i lights - OFF RO - Verify ESF Group 2 lights - LIT R9 - IE Main Steam Line Isolation has occurred, 11IEN Verily ESF Group 3 lights - LIT RO - IE CDA has occurnd, TllEN Verify ESF Guup 4 lights - LIT-Section 2 Page 25 of 40
Titic: LOIT NRC_#3 INSTRUCTOR GUIDE Revision: f! ID: ERQ l Task Time IDA/Malf Instructor Information/ Activity Assign Expected Response Standard Comp CREW should perfbrm a short brief and come out of" Master Siltmce" ADVERSE Conditions may exist on IRO Determine If ADVERSE CIMF E-0, Step 15 CTMF Tempemtun: Condi6ons Faist RO - Ctmt tempemture GREAlliR TllAN 180"F DR Ctmt radiation GREATTIR 11lAN 10'"/w CREW DO NOT use ADVERSE CIMF E-0, Step 15, pammeters. RNO US To pmvide adequate ECCS flow, E-0, Step 16. RCS subcooling ami P7R level Caution should be monitored to ensure tint the charging pump is manually restarted if RCS subcooling based on core exit tCs is less than 32"F ' or P7.R level is Icss than 15% RO Verify FfG How E-0, Step 16 RO Check charging pump flow E-0, Step 16.a indicator - FLOW CONSISTINT WrIlI RCS PRESSURE Section 2 Page 26 of 40
Title:
- LOIT NRC #3 INSTRUCFOR GUIDE . Revision: 0-ID: NRC3 Task Time- IDA/Malf- Instructor Information/ Activity Assign Expected Response Standard . Comp 4 RO Check RCS pn:ssun:- LESS E-0. Step 16.b T11AN 1650 psia (1950 psia ADVERSE CIMT) US Check ifcharging pump simuld be E-0, Step stopped: IE the following 16.b, RNO conditions exist: RO Both clurging pumps running. Crov Should be able to stop one of RO RCS subcooling based on con: the two running CIIS Pumps exist TCs GREATER TIIAN 32"F. BOP Secondary heat sinic
- Total feed flow to SGs is GREARR TlIAN 530 gpm.
M
- NR level in at least one SG is GREATER 11IAN 6%
RO RCS pressure is stable or increasing. RO P7R level is GREARR11IAN 15 % US TilEN Section 2 Page 27 of 40 u____.
Title:
LOIT NRC #3 INSTRUCTOR GUIDE Revision: 9 ID: NRC3 Task
. Time IDA/Malf Instnictor Information/ Activity Assign Expected Response Standarti Comp RO RESET St.
l RO STOP all but one charging pump 1 and Place in AUFO. l l US Proceed to step 17. I l BOP Verify Total ARV Haw- E-0, Step 17 l GREATER 111AN 530 gpm BOP Verify ARYValve Alignment- E-0, Step 18 PROPER EMERGENCY AUGNMENT , RO Verify Ff0S Valve Alignment- E-0, Step 19 PROPER EMERGENCY AUGNMENT US Check Plant Statm E-0, Step 20 BOOTII Report as Security Shift Supervisor SM Verify SLCRS doors - CIJ3 SED E-0, Step 20.a that all Unit 3 SifRS doors = closed. CBI will not be required until CIMF CREW Check if CBI actuated E-0, Step 20.b Pressure exceeds 18 psia.
- 1) CBI arsnunciator - LIT RO Check if CBI is requinxi E-0. Step 20.b. RNO Section 2 Page 28 of 40 c_______ .
Title:
LOIT NRC #3 - INSTRUCIDR GUIDE Revision: 9 ID:- NRC3 Task Time - IDNMalf instructor Information/ Activity Assign Expected Response Standarti Coenp RO - Ctmt presstre GRFATER 11IAN 18 psia 2 Control Building radiation monitor in alarm M SI manually actuated US IE CBI requinxi 11IEN Initiate CBl.' IE CBI is HQIrequired, TIIEN Proceed to step 21. US Orck RG Temperature E-0, Step 21 NOTE The failun: of the turbine to trip RO Verify RCS cold leg WR E4, Step 21.a probably reduced tuniuutures below tempemture - STABLE AT OR 5&F. TRENDING TO 5&F US Perform the applicable action: E-0, Step 21.a. RNO IE the temperature is LIES 11IAN 560" , TilEN Pimul to step 21c. Section 2 Page 29 of 40
Title:
LOITERC #3 INSTRUCTOR GUIDE Resision: R IIh NRG Task Time IDA/Malf Instructor Information/Actisity Assign Expected Response Standard Comp US Stop dumping stcan- E-0. Step 21.c BOP Place both condenser steam dump E-0, interlock selector switches to OFF Step 21.c.1 BOP Close SG atmospheric dump vahu E-0, Step 21.c.2 BOP Verify the following valves - E-0, Step 21.d CLOSED
- htSIVs MSIV byruss vahu
%e enny may have already stopped BOP Maintain total feed flow E-0. Step 21.e feeding the "B" SG because it is BEEVEEN 530 and 600 gpm until faulted. Must amintain minimum NR level is GRENER 'HIAN 6%
flow to the other 3 SGs (42% ADVERSE CRH) in at least one SG. RO Oneck PZR Valves E-0, Step 22 , PORVs may have started cycling RO Verify PORVs - CLOSED E-0. Step 22.a based on S1 flowing into an intact RCS (however uncetrolled cooldmm may result in sullicient RCS contraction to prevent this). RO Verify nonnal PZR spmy valves - E-0, Step 22.b CLOSED Section 2 Page 30 of 40
Title:
LOIT NRC #3 INSTRUCTOR GUIDE Revision: 9 ID: MRQ Task Time IDA/Malf Instructor Information/ Activity Assign Expected Response Standant! - Comp RO Verify PZR safety valves - F,0, Step 22.c CLOSED RO To prevent damage to the RCP E-0, Step 23, scal (s), seal injection flow should CAUllON be maintained to all RCPs. If CDA actuated, RCPs would be RO Check If RCPs Shouki Be Stopped E-0, Step 23 procedurally stopped. RCS Pressum should be above 2000 RO Ve.-ify RCS pressum - LESS E-0, Step 23.a psia TIIAii 1500 psia (1800 psia
, ADVERSE CIMF)-
Proceed to step 24 E-0, Step 23.a. RNO.
"IY S/G is FAULTED. 'Ihe crew may BOP /RO Check If SG Secondary E-0, Step 24 .
not feel there is sullicient leakage to Boundaries Are intact warrant a transition to E-2. 'Ihe crew may elect to tmnsition ES-1.1, SI Termination. BOP / Check pressum in all SGs E-0, Step 24.a RO NO SG PRESSURE DECREASING IN AN UNCONTROLLED MANNER NO SG COMPLETELY DEPRESSUR17ED a Section 2 Page 31 of 40
Title:
. LOIT NRC #3 INSTRUCTOR GUIDE Revision: 11 , ID: NRC3
- Task Time IDA/Malf Instructor Information/ Activity Assign Expected Response Standard Comp T= tramition MS01B ' Inenze the severity of the tweak to CREW Commence monitoring ESF status E-0, Step 24.a male sev= 100% emure CIMF Pressee is above 23 trees and Go To E-2. RNO tamp = 10 psia. The goal is to have the crew secomh tramition to FR-Z,1 NOTE: Upon transition the operators should US Tmnsition to FR-Z.1 OP 3272, recognize the ORANGE PA'llI on EOP Users FR-7.1 and transition to FR-7.1 Guide ,
Ji]{Z1 ANS US/RO Verify CIA (ICSF Group 2 Statm colunm 2 'Ihrough 10) FR-Z.1, Step 1 RO Initiate CIA OR reposiiion valves FR-Z.1, Step for minimum safety function. IRNO CDA will have failed to Auto US Venry CIB FR-Z.l. Stcp Actuate 2 CIB will have closed the isolation RO Check RPCCW Ctmi supply and FR-Z.1, S;cp valves retum header isolation vahes - 2.a CLOSED t RO Check RPCCW pumps - STOPPED FR-Z.1, Step lb , RO STOP pumps. FR-7_l, Step , 2.b, RNO " RO STOP all RCPs FR-Z.1, Step. 2.c ' Section 2 Page 32 of 40 4
Title:
LOIT NRC #3 INSTRUCTOR GUIDE Resision: 9 ID: NRC3 Task Time IDA/Malf Instructor Information/ Activity Assign Expected Response Standarti Comp N/A If ECA-1.1, Inss of Eirugacy FR-Z.1, Step Coolant Recirculation, is in 3 CAUTION progress, Ctmt spray simuld be operated as din:cted in ECA-1.1 mther that steps 3,4, and 7 US Verify Quench Spmy System FR-7.1, Stcp OperAion 3 RO Check RWST level - GREATER FR-7.1, Step T1IAN 100.000 gal (annunciator 3.a RW5T EMIYIY QSS PP OFF on MB2A 5-2 not lit) RO Verify quench spmy pumps - FR-7.1, Stcp RUNNING 3.b The crew will need to start the RO START quench spray pumps. FR-Z.1, pumps. Step 3.b, RNO [*] The crev will need to open the RO Verify quench spray pump FR-Z.1, Step valves. discharge valves (3QSS*MOV34A 3.c and 3QSS*MOV34B)- OPEN RO OPEN valves. FR-Z.1, Step [*] 3.0,RNO Flow should exist if the operators RO Check quench spmy system - FR-Z.I. Step [*] started pumps and opened the vahes FLOW EXISTS IN AT LEAST 3.d ONE TRAIN Section 2 Page 33 of 40
Title:
IDIT NRC #3 INSTRUCTOR GUIDE Revisior; 11 ID: NRC3 Task Time IDA/Malf Instructor Information/ Activity Assign Expected Response Standani Comp l US Proceed to step 5. FR-Z.1, Step 3.c i BOP STOP AII Main Ortulating Wakr FR-Z.1, Step Ptmqn 5 CAR Fans Should be oft by this US/ Orck Containment Ventilation FR-7.1, Step point BOP 6 Verify CAR fans - STOPPED Verify CRDM fans - STOPPED , BOP STOP fans. FR-Z.1, Step 6, RNO US Verify Recirculation Spmy System FR-Z.1, Step Operation 7 Crew may be at this step in less than RO Check CDA signal - PRESENT FR-Z.1, Step 11 minutes. Expect the cnnv to start a AFER II minutes (annunciator 7.a timer and aller 11 minutes start the Ca1T RECIRC PUMP AUTD RSS pumps. START SIGNAL on MB2B l-8 lit) step 8 starts on the next page. US Proceed to step 8 :vid, W1HN 11 FR-Z.1, Step minutes have clainxi since CDA 7.a. RNO initiation, TiiEN Perfixm steps 7b through 7e. RO Verify recirculation spray pumps - FR-Z.l. Step Section 2 Page 34 of 40
Title:
IDIT NRC #3 INSTRUCFOR GUIDE Revision: 9 ID:- NRC3
' Task' Time. IDNMalf Instructor Information/ Activity Assign Expected Response Standard Comp RUNNING 7.b RO Verify recirculation spray pump FR-7.1,' Step suction isolation vahcs - OPEN - 7.c RO Verify recirculation spray pump FR-Z.1, discharge isolation valves - OPEN Step 7.d RO Verify recinxilation spray - FLOW FR-Z.1, Step EXISTS IN AT LEAST ONE 7.c 1 RAIN w/ cxception to RSS Pumps and RO Verify ESF Statis Panel Group 4 FR-Z.1, Step _
associated ACUS, WFC*AOV25NB. Ughts - IE 8 SW*AOVil5N115B, SW71NB not closed BOP / Verify Main Steam Une Isolation FR-7_1, Step RO 9 Check MISVs and MISV bypass val -t - CLOSED Check ESF Status Group 3 , lights - LIT ! t Section 2 Page 35 of 40
Title:
LOIT NRC #3 INSTRUCTOR GUIDE Revision: R ID: NRC1 Task Time IDA/Malf Instructor Information/ Activity Assign Expected Response Standard Comp With adverse containment being BOP / Verify Main FeedwaterIsolation FR-7.1, Step obtained it'is possible that a red path RO 10 on heat sink will occur because of the - Verify MD AND TD FW opemtor throttling back on AFW pumps - TRIPPED flow. The crev may transistion to FR-II.l. They should reali7e that the - Verify FW isolation trip nxi path is due to their actions and it valves - CLOSED can be cleared by increasing AFW flow. the crev should exit FR-II.1 - Vcrify SG feed regulating when AFW flow is increased. valves - CLOSED ; Verify SG feed regulating bypass valves - CLOSED US - At least one SG must be . FR-7.1, Step ' maintahed available for 11, RCS cooldown. CAlmON US - If all SGs are faulted, at FR-7.1, Step , least 100 gpm feed flmv i 1, should be maintained to CAUTION cach SG. US Check If Auxiliary Feedwater How FR-7.1, Step ' Should Contimse To All SGs 11 "B" S/G is depressurizing BOP Check pitssure in all SGs 'FR-Z.1, Step uncontmilably ' 11.a NO SG PRESSURE DECREASING IN AN UNCONTROLLED Section 2 Page 36 of 40
Title:
LOIT NRC_#3 INSTRUCTOR GUIDE Resision: R ID: NRQ Task Time IDA/Malf Instructor Information/ Activity Assign Expected Respome Standart! - Comp M N .4ER NO SG COMPLETELY DEPRESSUR17ED "Il" S/G is the affected S/G BOP Isolate AFW flow to the affected FR-7.1, Step SG 11.a. RNO US Check Ilydmgen Concentration FR-7.1, Step
- 12 RO! Place hydrogen monitor in senice FR-7.1, Step PEG using OP 3313A, Ilydrogen 12.a Recombiners and Recombiner
. Building Ventilation, section 7.5.
Opemtors will not be able to check US Verify hydrogen concentmtion - FR-Z.1, Step 112 levels until aller the monitor is in LESS 11(AN 5% 12.b ; senice US Verify hydrogen concentration - FR-7_l, Step , LESS TlIAN 0.5% 12.c US Proceed to step 15. FR-Z.1, Step 12.d SM Notify DS00 of Ilydrogen FR-Z.l. Step ' Concentration imide Containment 13 1: SM/ Periodically MorstorIlydrogen FR-7.1, Step CREW Concentration (every 8 hours) 14 Section 2 Page 37 of 40
Title:
LOIT NRC #3 INSTRUCI'OR GUIDE Revision: D ID: - NRO Task Time . IDA/Malf Instructor Information/ Activity Assign Expected Response Standarti . Camp T= Transition liRFFI" E us co to Iwcedine and Seep In EKect FR-7.1, Step Made 15 1 Section 2 Page 38 of 40
ID Number. NRC3 Revision: 0 EVALUATOR GUIDE SillFT'ITf11NICAL ADVIEOR EVALUATION GUIDE - POST S&NARIO_ LBOPOSED STA SIMULXIDR EXAM SGNARIO OUFXf10NS N/A. NO STA FOR LOIT EXAM i i Section 2 Page 39 of 40
SEC110N 3 SIMUIATOR EXAM SEQUENCE OF EVENTS SUhtMARY
Title:
OPERAllONAL EXAM ID Number: NRCA Revision: 0 31ME*QA -INSTRUCTOR AIDS DESCRIPTION MALF. RF.10 T-0 Malf RP06A Failure of CDA to actuate, Train A Malf RP06B Failure of CDA to actuate, Train B Malf TC03- Turbine Fails to Trip Malf TC04 Turbine Fails to Runback Malf RP08A Train A MSI Auto Failure Malf RP08B Train B MSI Auto Failure I/O (RP) PB2-3 ADS-CDA "OFF" CDA Actuation Pushbutton Failure I/O (RP) PB3-3 ADS-CDA "OFF" CDA Actuation Pushbutton Failure T= Examiner's Cue Malf RX12P SG "D" NR Level Indicator Fails Low T= Event 3 complete MALF N109A PR 41 Lower Detector Fails High Tc Rods in Auto Malf - RD021 - Continuous Inward Rod Motion (Bank D) Malf RD0211(as required) Continuous Imvard Rod Motion (Bank C) T= Crew closes MSIVs Malf MS01B,7% 600 secs "B" SG Steam Line Fault Inside CTMT T=E-0 Transition Malf MS01B,100% 10 secs "B" SG Steam Line Fault inside CThir Section 3 Page 40 of 1
SECHON 4 VAllDA' DON CHECKUST
Title:
LOIT NRC #3 1D Number: NRC3 Revision: 0 -- Remote functions: Verified by All remote functions contained in the guide are cenified.
- Malfunctions
l l All malfunctions contained in the guide are cenified. 4, - ! Initial Conditions: l l-he initial condition (s) contained in the - / guide are cenified or have been developed t* from cenified ICs in accordance with NSEM-4.02. Simulator Oncrating Limits.; He simulator guide has been evaluated for . operating limits and/or anomalous response. Test Run: De scenario contained in the guide has been test nin and validated (validation sheet completed, 4 -) next page)on the simulator. Simulator response is reasonable and as expected. Examination Scenario Review 1 he dyrmmic examination resiew checklist ) is complete. E~ 4 Section 4 Page 1 of 3 i
SECTION 4 OPERA 110NAL EXAM VAUDATION SHEET Program
Title:
_ licensed Onerator Requalification Training
Title:
LOIT NRC #3
. ID Number. NRC3 Revision: 0 By their signature below, the people acknowledge the confidentiality and validity of the material contained within and will not willfully disclose its contents to others enrolled in the Millstone Three Licensed Operator Requalification Program.
l VAUDATED BY: Bint Signature Date SM MI6 / -- US +wb lwE=u / ~ l C[2)ln RO - O @* 0 t'n 1 w* c H / - k , - _d/2}/97 BOP . /
/
/
/
/
! . / t
/
Section 4 Page 2 of 3
SFfDON 4 DYNAMIC EXAMINA* DON REVIEW OIECKlJST Note: The following criteria list scenario traits that are nurnerical in nature. A second set of numbers indicates a range to be met for a set of two scenarios. Ouantitative Attributcs i 7- 13. Total malfunctions insened: 4-&/10 14 4 14. Malfunctions that occur after EOP entry: 1-4/3-6 3 15. Abnormal Events: 1-2/2-3 o 3 16. Major Transients: 1-2/2-3 1 17. . EOPs used beyond primary scram response EOP: 1-3/3-5 1 18. EOP Contingency Procedures used: 0-3/1-3 60 19. Approximate scenario mn time: 45-60 minutes (one scenario may approach 90 minutes) . 40 % 20. EOP mn time: 4470% of scenario run time 2 21. Crew Critical Tasks: 2-5/5-8 yes 22. Technical Specifications are exercised during the test COMMENTS: _ Section 4 Page 3 of 3 _ _ ~ - -
SECDON 5 REFERENCES AND CRTHCAL TASK TRACKING
Title:
LOIT NRC #3 ID Number: NRC3 Revision: Q
- l.
References:
AOP 3575, 3' Rapid Downpower AOP 3571, Instrument Failure Response. E OP'35 E-0 Reactor Trip or Safety injection EOP35 FR-Z.1 Response to High CTMT Pressure EOP* ERG-HP Westinghouse Owners Group ERG-HP Background a Document EOP* Step-Doc Millstone Unit 3 Step Deviation Document EPIP 4400 Event Assessment, Classification and Reportability Tech Specs Technical Specifications for MP3 OP*3272 EOP Users Guide NUREG*1021 rev 8 Examiners Standards
- 11. Critical Tasks Covered in this Test:
NOIE : Critical Tasks are marked by an (*] within guide CRITICAL CRITICAL TASK K/A >/= 3.0 BASIS FOR SELECTION IASK # DESCRIPTION lhmm_0nh l l E0-E Establish at least one Quench 026 000 Failure to establish at least one Quench Spray train flow before Al.01 Spray train flor under the postulated completion of FR-Z 1 step 3. 3.9/4.2 conditions constitutes a " demonstrated inability by the crew to recognize a failure / incorrect auto actuation of an ESF system or component." E-0--P Manually actuate MSI or close 000-040 Failure to close the MSIVs under the the MSIVs before a severe EAl.01 postulated plant conditions causes orange path challenge 4.6/4.6 challenges to CSFs beyond those develops to either intpambly introduced by the postulated suberiticality or integrity CSF conditions. Additionally, such an or before transitioning to omission constitutes a " demonstrated ECA-2.1, whichever happens inability by the crew to recognize a first failure of the auto actuation of an ESF system or component and to take an action that would prevent a challenge to plant safety." Section 5 Page1 of1
, 1
f '- SEC110N 6 SCENARIOINT11AL 00NDfl10NS Reactor Power: 100 % Operating History: 200 days on Line-
- RCS Boroni 988 ppm Core Bumup: 10,500 MWD'hm]
- Condensate Demins: 7 IN SERVICE Evolutions in Progress: None, lhunderstonn Wamings have been issued for the next 4 to 6 hours.
l Major Equipment OOS: "A" Service Water Pumr - Bearing Replacement "A" Motor I riven AFW Pump - Motor Ground Troubleshooting L "B" Stator V ater Coaling Pump - Seal Replacement >
- Crew Instructions- Excessive vibration exist on' the B" TDFW Pump. The Operations Manager has directed your crew to reduce Reactor
. power to 90% @ 1/2 % per minute and swap feedwater pumps.
You are to use AOP 3575, Ryid Downpower, to perform the evolution. All necessary checks to start the Motor Driven Main Feedwater Pump have been completed. PEOs are standing by to : start the MDFP and the "C" condensate pump. Plant /Simnhtor Differences: 1 Rad Monitor Historical Data-Simulator Rad Monitor historical data not valid prior to-the beginning of this exercise. 4-
.Recctor Makeup System bctch counters different fium plant system. (if required to perfonn a makeup evolution, refer to the RO procedte: cart for setting the Batch Counter.)
Simulator main steam atmospheric dump valve controllers diffen:nt fmm plant.-- a Section 6 Page1 ofI
gO n kdm,a .
/d6cs on 3 6 n.t. Ti> duTuscj 5
,(
_m_. .- ______._________.-____.d
h!Q Administrative Topic Outline for RO A,1 Conduct of Operations - _. Responsibilities as the oncoming operator concerning the shift turnover ; process. l Question: The plant is in Mod 2 conducting a reactor startup. Bank D control rods are
~60 steps from the ECP. You are the oncoming RO When would it be appropriate to relieve the shift? -
Cop 200.1 Section 1.20 states that "The SM/US shall ensure that the nlant is in a controlled condition at the beginning of the shift relief process." A reactor start up is not a controlled situation. The RO should not relieve the shift until the reactor is critical and at a stable power level.- ( Example would be stable in the IR below the POAll)
)
.J
Administrative Topic Outline for RO A.1 Conductpf 0perations Responsibilities as the oncoming operator concerning the shift turnover process. Question: As the oncoming RO what are examples of things tharrost be discussed and/or reviewed prior to assuming the watch? (list 5 examples) COP 200.1 States that " The oncoming shift shall : Ensure properly licensed or qualified to assume the assigned shift posuion Ensure physically and mental fitness to completely discharge assigned responsibiinies e Discuss important items affecting plant operations with counterpart s Review pertainent information identified on the shift relief and turnover report generated in the last 24 hours Review logs and .hccklists applicable to assigned shift position Walkdown control boards and discuss the following: Unusual events that occurred during the last 24 hours > e Status of safety related equipment Inoperable equipment and ACTION staten'ents. including surveillance requirements e Reasons for annunciator alarms Tagged equipment. including any surveillance or equipment work in progress at time of shift relief and turnover Running equipment and train alignments e Read and Sign the turnover report" k
, _ _ _ _ - - - - J
JOB PERFORMANCE MEASURE WORKSHEET y I. -JPM
Title:
DETERMINE TIME TO CORE BOILING ID Number: NRC-NEW3 Revision: 0 1 II, Initiated:
, R.L Luenebura 5/29/97 Developer Date l
Ill. Reviewed: Technical Reviewer Date 4 Instructional Reviewer Date IV; Approved: Operations Manager Date 9 Nuclear Training Supervisor Date 1 o
'. OMNMNM$'[TN?. ll' JOB PERFORMANCE MEASURE WORKSHEET j Facility: Millstone Unit 3 Examinee: _ _ . . _ . -
JPM Tracking Number: NRC NEVD._ Validatiot Tne: minutes Task
Title:
CALCULATE TIME TO QQRE,.B.hllhG Time Critical Task: ( )YES (X)NO Task Number: 119*047*03'02, K/A Number: 2.1.25 K/A Rating: 22L31 Applicable Methods of Testing: Simulate Performance Aca, al Performance X Classroom Simulator X Piar't X Task Standards: Satisfactorily complete the determinat!on of time to core boiling for a given set of conditions, Reauired Materials: None General
References:
OP 3260A Rev.10 READ TO THE EXAMINEE l will explain the initial conditions, which step (s) to sirnulate or oiscuss, and provide initiating cues. When you complete the task successfully, the objectives for this JPM will be satisfied. You may use any approved reference materials nonnally avaaabte in the Control Room, including logs Make all written reports, oral reports and log entries as if the evolution was actually being performed. Initial Conditions: The plant is in MODE 5, shutdown 160 days for an extended non-refueling outage, RCS pressure is being maintained at 45 psia on a N 2. RCS temperature is 105'F, and none of the RCS loops has been drained or isolated. Initiating Cues: Given the plant conditions above, the 'US has directed you to calculate
" time to core boiling",
2 l l
PERFORMANCE INFORMATION 2 Facility: Millstone Unit 3 System: GOP
-JPM Number: NRC-NEW3 Task
Title:
Determino Time to Core Boiling Denote Critical Steps with an "X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade Start Time:
STEP 1 Performance Step: Obtain a copy of the appropriate l procedure and select the appropriate sect _ ion to determine time to core 1 boiling. ! GRADE Standards: Obtains a copy of OP326CA, Conduct of Outages,- and selects section 1.1.4.a as the proper guidance for determining the time to core boiling. Comments: If the examinee questions " update the plant " STATUS BOARD", provide the following cue:
!Cuei _
?Thd US wiIl ensure that_thsl
, jappropr: ate updates are made.- ,
STEP Performance Step: DETERMINE the time to core boiling and UPDATE the plant " status board" daily as follows: E the plant is in MODE 5 MQ the RCS is vented to atmosphere OE with pressure between 45 psia and 170 psia, Perform the following:
- 1) E RCS temperature is s 110'F, Refer to Attachment 5.
- 2) E RCS temperature is s 140*F, Refer to Attachment 6.
3
PERFORMANCE INFORMATION - 7 : Facility: Millstone Unit 3 System: GOP JPM Number: NRC-NEW3 Task
Title:
Determine Time to Core Boiling Denote Critical Steps with an "X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade GRADE Standards: Uses OP3260A, Step 1.1.4.a.1, and selects Attachment 5 as the correct attachment to use for the determination c! time to core boiling.
STEP 2 Performance Step: Use Attachment 5 to determine time to core boiling. GRADE Standards: Uses Attachment 5, column 1 Shutdown time (days), and reads down the column until he comes to 160. GRADE Standards: From 160 in column 1, goes across to column 6,-labeled 4 Loops and reads time to core boiling (hours) 5,6
. STEP 3 Performance Step: Notify US that the time to core boiling -
has been determined GRADE Standards: Notifies the US that the time to core boiling has been determined as 5.6 hours. Terminating Cue: The evaluation for this JPM is concluded. Stop Time: 4
, - VERIFICATION OF COMPLET!ON-4 4 ..
Job Performance Measure Number: NRC-NEW3 Revision: 0 Date Performed: Examinee: Evaluator: Validated Time (min): Actual time to Complete (min):
^
Result of JPM: (Denote by an S for satisfactory or a U for unsatisfactory)- Result of oral questions: Number of Questions: 4
- Number of Correct Responses
Score % 4 T f ) d f i 5
- - _ - _ .,- ,_ _ . - - - _ . , ~ _ - . -
t EXAMINEE HANDOUT , INITIAL CONDITIONS AND INITIATING CUES JPM Tracking Number:- NRC-NEW3 Initial Conditionn: The plant is in MODE 5, shutdown 160 days for an extended non refueling outage, RCS pressure is being maintained at 45 psia on a N2 , RCS temperature is 105'F, and none of the RCS loops has been dralned or isolated. l Initiating Cues: Given the plant conditions above, the US has directed you to calculate " time to core boiling". 6
-JOB PERFORMANCE MEASURE WORKSHEET 4
- 1. JPM
Title:
P & ID Reading and Identification of Comoonents/ Nomenclature ID Number: NRC-NEW2 Revision: Q i ll. Initiated: Ri. Lueneburg 5/29/97 Developer Date lil. Reviewed: ( l I Technical Reviewer Date Instructional Reviewer Date IV, Approved: Operations Manager Date Nuclear Training Supervisor Date I 1
- JOB PERFORMANCE MEASURE WORKSHEET l,. ,
Ficility: - Millstone Unit 3 Examinee: f JPM Tracking Number: NRC-NEW2 Validation Tima: l minutes Task
Title:
P & ID Reading and Identification of Comoonents/ Nomenclature
- Time Critical Task
- ( )YES ( X-) NO
-119*048*01*01- I b . Task Number:
l K/A Number: Eauloment Control K/A Rating: I Anolicable Methods of Testing: i ] b ' Simulate Performance Actual Performance X !- Ciassroom Simulator X Plant X [ Task Standards: Satisfactority ask the provided questions using a set of PalDs as i the only reference, i Reauired Materials: Set of P&lDs General
References:
P&lDs f' READ TO THE EXAMINEE j l will explain the initial conditions, which step (s) to simelate or discuss, and provide initiating i- cues.1When you complete the task successfully, the objectives for this JPM will be satisfied. ! You may use any approved reference materials normally available in the Control Room, [
. . including logs. Make all written reports, oral reports 'and log entries as if the evolution was actually being performed.
F Initial Conditions: You have been asked to answer a series of questions using a set of P&lDs as your only reference. F Initiating Cues: Answer the following questions: [ - If it became necessary'to drain the " Neutron Shield Tank Surge P - Tank", to which plant system would it be drained? What automatic functions are associated with 30SS-TE38? i List the 9 signals that would result in an SBO diesel shtidown. I 2
, _ . . _ . . _ , _ - - ~ . . . -_ _ _ _ _- - . .
PL!RFORMANCE INFORMATION 1 Facility: Mihtone Unit 3 System: g L\dmin. JPM Number: NRC-NEW2 Task
Title:
P & ID Reading and Identification of Comoonents/ Nomenclature Denote Critical Steps with an "X"
- NOTE' Critical Steps must be completed correctly to acnieve a satisfactory grade Start Time:
Comments: The examinee may answer the questions in any order. STEP 1 X Performance Step: If it became necessary to drain the t
- Neutron Shield Tank Surge Tank", to which plant system would it be drained?
GRADE ~ X Standards: Looks at the P&lD index and determines that EM 114A is the appropriate one for Neutron Shleid Tank Cooling, Locates the Surge tank and its associated drain line. Reads the nomenclature concerning where the drain line goes. Answer: Radioactive Liquid Waste and Aerated Draint..
- STEP ~
2 X Performance Step: What automatic functions are associated with 30SS-TE387 GRADE Standards: Looks at the P&lD index and
~~~
determines that EM 115A is the appropriate one for the QSS system. locates instrument 30SS TE38 as a temperature element on the RWST (l. 3). Determines that there are 2 automatic functions associated with this element:
- Auto starts 30SS-1A/B on Hi Temp.
3
PERFORMANCE INFORMATION
> Facility: Millstone Unit 3 , System: Admin JPM Number: NRC NEW2 Task
Title:
P & !D Reading and Identification of Comoonents/ Nomenclature ,, Denote Critical Steps with en *X"
' NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade l
(requires going to location B-4 on the i I same P&lD and analyzing the puinp start circuit).
- Follows the lines that go to EM-122A . Reactor Plant Chilled Water System. Determines that 3OSS-TE-38 provides an open signal to 3CDS-SOV26 to provide cooling water to the Refueling Water Coolers.
STEP 3 X Performance Step: List the 9 signals that would result in an SBO diesel shutdown. GRADE X Standards: Looks at the P&lD inde:: and oetermines that the EM 158 series is the right series for the SBO Diesel. After locating that series, determines that EM 158B is the correct page. Locates the engine shutdown symbol (6 2 at J 11) and traces the 9 input lines:
- Primary Protective Relay
- Backup Protective Relay
- Overspeed Trip
- Emergency Stops
- Crankcase Hi Pressure
- Low Lube Oil Pressure
- High Lube Oil Temp.
- High Coolant Temp.
Low Water Pressure w/ Low Water Level 4
-)
PERFORMANCE INFORMATION 3 Facility: Millstone Unit 3 System: Admin JPM Number: NRC NEW2 Task
Title:
P & ID Readina and Identification of Comoonents/ Nomenclature Denote Critical Steps with an T
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade STEP 4 Performance Step: Indicate that all of the questions have been answered.
GRADE Standards: Informs the examiner that he has completely answered the 3 questions. Terminating Cue: The evaluation for this JPM is concluded. Stop Time: 5
r VERIFICATION OF COMPLETION Job Performance Measure Number: NRC NEW2 Revision: Q Date Performed: l Examinee: I
- Evaluator:
Validated Time (min): Actual time to Complete (min): Result of JPM: (Denote by an S for satisfactory or a U for unsatisfactory) Result of oral questions: Number of Questions: Number of Correct Responses: Score % 6 1
EXAMINEE HANDOUT i 1
- e INITIAL CONDITIONS AND INITIATING CUES
, 1 4 1 JPM Tracking Number: NRCeEW2_.
i ( , jnitlai Conditinna: You have been asked to answer a series of questions using a j set of P&lDs as your only reference. 4
)
- initiating _CMan
- Answer the following questions:
l - If it became necessary to draln the " Neutron Shield Tank Surge Tank", to which plant system would it he drained? 4 What automatic functions are associated with 3QSS. TE38? . +
- List the 9 signals that would result in an SBO diesel shutdown.
L l 7
7, 1 A.3 Radiation Control Knowledge of radiation exposure limits and contamination control, including permissible levels in excess of those authorized. Applicable references available at the RCA may be used to answer this question. Question #1 You have becn sent to the auxiliary building to complete some tagging. One of the tags that you must hang requires you to enter a Tech Spec Locked liigh Radiation Area. What , requirements must be met for you to make this entry? Assume the radiation levels and the time to complete the job will are low enough that you will not exceed any personnel exposure limits. Answer: Check Radiation Work Permit #5, job step 2 of 4. Must contact ilP for a PRE JOB Brief and latest survey data The llP briefing shall include: Digidose alarm setpoint and Stay Time ControliReturn ofIIR.2 Key Survey meter, alarming dosimeter or continuous llP coverage required for entry into Tech Spec Locked liigh Radiation Areas.
g . I I A 3 Radiation Control I i Knowledge of radiation exposure limits and contamination control, including permissible levels in excess of those authorized. Question #2 If you were sent to the Auxiliary Building to replace a Alter that was in a housing that had a contact dose rate of 450 mrem 41r and you expected to receive a dose to your extremity of 125 mrem and a whole body dose of 20 mrem, what special instructions must be met. Answer: Check 1(adiation Work Permit 5. job step 1, Operations Blanket t Under the Special Instructions Section notes the following for Filter change Evolutions: Any niter housing with a contact dose rate of 500 mrem'hr or greater will be worked on f(WP 10. Since the contact reading is 450 mrem /hr, can perform the task under 1(WP 5 lip to survey filter housing prior to filter removal and sun ey Glter(s) upon removal [ Because Slter changes are rapid evolutions, nnger rings are required when dose to the extremity 5 times the whole body dose and dose to the extremity >100 mrem is expected. Based on the given conditions, the expcted dose to the extremity is greater than 5 times the expected whole body dose and is greater than 100 mrem. A Enger ring is required. i- . IIP to survey all tools and work area ,
A 4 i i9 -! 1 1 . i
;I A.4 Emergency Plan , l 1
( - Knowledge of Ros responsibilities in emergency plan implementation. i.
- Question #1 ,
i I ! You are the on shlll Reactor Operator when a significant plant event occurs and a Site ! l Area Emergency classification has been declared. You find yourselfin a situation where { l you know you must take action promptly to protect the public health and safety. ! { llowever, the action you must take is not covered by any plant procedure nor is it in the ! ! plant's Technical Specification. - What should you do? l 1 1 Answer #1 l 10CFR 50.54(X) allows the licensee to take reasonable actions that depart from license { condition or Technical Specification under an emergency situation when the action must ! be taken to immediately protect the public health and safety,10CFR 50.54(Y) further ; [ states that actions taken under 50.54(X) must be approved by a licensed senior operator
- prior to taking the action. i
)
. Consequently, the RO should state that he would take the required action aller having the
- SM or US or another licensed senior operator approve the ection. .
l 1- , a e i I _ i t i P i-J e.g-av,,Le,n,-,,n -en.,w-~,--,,,~w.-i-eewer-wen, ..rno- --e,m-- - ,--w-e.,n,,rn., ._., -v<.,pver,.,,w. a . + m < + w Aw , ,ew m v .em. - en ,-o re-
. 1 e
A.4 Emergency Plan Knowledge of Ros responsibilities in emergency plan implementation. Question #2 You are on day shin. The swing shin arrived on site 30 minutes ago to conduct a thorough shift briefing prior to perfonning a PORC approved test during their shift. Ten (10) minutes ago a RCS leak occurred which ultimately resulted in your crew initiating a reactor trip and a safety injection, the crew is currently at step 14 of E 0 conducting a crew briefof the event belbre coming out of master silence, it is time for the shift turnover. ~ Will the shift relcif occur at this time?? i Answer #2 . In accordance with C OP 200.1, the SM/US shall ensure the plant is in a controlled condition at the beginning of the shin relief and turnover process. Even though the on shift crew is currently conducting a briefing, the plant is not considered stable since the leak it still present and the crew has not transitioned to the appropriate recovery procedure. The shift relief will not take place at this time. ) i a
d Ec2
$2D
/La 4,cs a s.< o a .-m
Administrative Topic Outline for SRO A.1 Conduct of Operations The use and requirements of a Dedicated Operator Question: The plant is in Mode 1 at 100% power. The service water ventilation to the "A" train service water pumps must be shut down for 5 minutes to shin ventilation from summer to winter mode. The fan does not receive an automatic start signal. There is not a pol (C approved procedure to do this task. Can a licensed operator not on shift be stationed at VPl as a dedicated operator to allow the fan to meet Technical Specification operability requirements. Answer: Yes. OP3260 section 6.17.2 states that a dedicated operator who is used to satisfy a Tech Spec operability requirement may only be posted in accordance with a PollC approved procedure, in the event that the task to be performed is a single, simple action with in the general responsibilities, skills and training of the operator, and does not replace an automatic function, this Conduct of Operations procedure shall be deemed to f constitute the POltC approved procedure for the purpose of posting a Dedicated Operator. . l i
"'% ,.eom:- s ---- , -,7 my.. w y. .. _.. - - , -... -+
Administrative Topic Outline for SRO A.1 Conduet of Operations : 1 The use and requirements of a Dedicated Operator 1 Question: Once it has been detennined that it is appropriate to use a Dedicated Operator for a specific task. What things would be appropriate for the SM to brief the Dedicated Operator on prior to assuming the position. (l.ist 3 things) Answer: LAW COP 200.1 Section 1.22 e
" In the event of an emergency, the primary function of the dedicated operator is to restore the equipment to its proper safety alignment and to inform the SM/US.
The dedicated operator shall remain in the vicinity of the assigned equipment or control panel at all times. if the dedicated operator must leave the assigned area, another qualified operator who has been briefed on the Dedicated Operator responsibilities shall relieve the dedicated operator
. The dedicated operator shall not be assigned other duties concurrent with the dedicated operator role except performance of surveillance or operating procedures which involve assigned equipment A dedicated operator stationed outside the control room shall have the ability to expediently communicate with the control room
. Any steps that must be performed if the safety function shall be restored" l
l i (
JOB PERFORMANCE MEASURE WORKSHEET
- l. JPM
Title:
SHUTDOWN RISK ASSESSMENT FORM REVIEW ID Number: NRC NEW Revision: Q l l i ll. Initiated: R.L. Luenebur9 S/28/97 Developer Date Ill. Reviewed: Technical Reviewer Date Instructional Reviewer Date IV. Approved: Operations Manager Date Nuclear Training Supervisor Date I i 1
i I JOB PERFORMANCE MEASURE WORKSHEET 1 Facility: Millstone Unit 3 Examinee: JPM Tracking Number: NRC-NEW Validation Time: minutes Task
Title:
SHUTDOWN RISK ASSESSMENT FORM REVIEW Time Critical Task: ( )YES ( X ) NO Task Number: 119'047'03'02 K/A Number: 2.1.28 K/A Rating: 3.2/3.3 Aeolicable. Methods of Testing: Simulate Performance- Actual Performance X Classroom Simulator X Plant X Task Standards: Satisfactorily conduct a review of a shutdown risk assessment form based on a set of plant / equipment conditions. Reauired Materials: Completed Shutdown Safety Assessment Checklist, Form 3260A-4 General
References:
OP 3260A, Rev.10 READ TO THE EXAMINEE I wl!I explain the initial conditions, which step (s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objectives for this JPM will be satisfied. You may use any approved reference materials normally available in the Control Room, including logs. Make all written reports, oral reports and log entries as if the evolution was actually being performed, initial Conditions: The following plant conditions exist: The plant is in Mode 5, all RCS loops are full, RCS pressure is 325 psia and RCS temperature is 165'F. It is the start of the day shift The calculated shutdown margin boron is 2050 ppm Train *B" electric plant outage The SBO diesel is OOS for adjustments to the governor The "A" RHR pump is running for decay heat removal The last boron concentration sample was 2510 ppm Both shutdown mhtgin monitors are operable An oil replacement on the *C" charging pump will be completed at 10:30 AM 2
JOB PERFORMANCE MEASURE WORKSHEET l The 'A' SlH pump is OOS for bearing replacement. ! Preparations are being made to open containment for the first i time this outage. No access doors / openings are currently open. I time to core boiling is 35 minutes The A, B, and C SGs narrow range levels are at 48%,55% and 65% respectively. The D SG is drained down in preparation for secondary side entry. The A' MDAFW pump is available for feed flow. The AFW cross connect valves are tagged closed. PZR levelis 88% on the cold calibrated instrument . The "A" SFC pump is running with a pool level of 24'6" above the fuel No work is being performed on the NSST or RSST ' RWST level ls 1,180,000 gallons and 3RHS*V43 is locked closed ' and tagged ' SP 3604C.6 was completed last night on the mid shift I t laitiating Cues: The RO has completed the Shutdown Safety Assessment Checklist. You are to conduct the required review. i 3
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: ADMIN JPM Number: NRC-NEW Task
Title:
SHUTDOWN RISK ASSESSMENT FORM REVIEW Denote Critical Steps with an *X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade l
Start Time: i STEP 1 Pedormance Step: Obtains a copy of OP 3260A to use in reviewing the shutdown safety Assessment Checklist. GRADE Standards: Locates the appropriate procedure volume and opens it to OP 3260A, section 1.2 Comments: The examinee may skim section 1.1, General Requirements. Comments: The standards in this JPM refer to the applicable sections of OP3260A that the examinee may refer to in the process of the review, Checking these sections is not required to complete the critical nature of the step. STEP 2 X Performance Step: Checks section I, RCS Decay Heat Removal. GRADE X Standards: Verifies that the RO appropriately checked the RHR Train A block and no othere. "B" RHR is not available due to the train electrical outage. All conditions for natural circulation are not met because both "A" side SGs are not available("D" SG drained down). Refueling has not commenced; cavity is not >23', RCS totalis 1, 4 i
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: ADMIN JPM Number: NRC-NEW Task
Title:
SHUTDOWN RISK ASSESSMENT FORM REVIEW Denote Critical Steps with an *X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade ORANGE condition. Used Sections 1.2 and 1.8 as a reference to determine the criteria.
4 The RO also circled N/A for available
- racked down charging pump.
STEP 3 X Performance Step: Checks section ll, SFC Decay Heat Removal GRADE X Standards: Verifies the RO appropriately checked SFC Train A and >23' poollevel above the fuel. The *B" train of SFC is not available due to the train electrical outage. The SFC totalis 2, YELLOW , 4 condition. Used section 1.8 as a reference. I STEP 4 X Performance Step: Checks section Ill, inventory GRADE X Standards: Notices that the RO inappropriately checked SlH Train A. Train "B" CHS pumps and SlH Train *B" are not available due to the electrical outage. Also ho.ib RHR pumps are not available due to the "B" train electrical outage making the *B" RHR pump not available. RO had total as 2, YELLOW condition. The total should be 1, Orange condition. The RO appropriately checked the boxes for RWST level and 3RHS*V43. Uses sections 1.3 and 1.8 as reference. 5
PERFORMANCE INFORMATION Facility: Millstone UniL3 . System: ADMIN JPM Number: NRCd4EW { Task
Title:
SHUTDOWN RISK ASSESSMENT FORM REVIEW l Denote Critical Steps with an "X*
' NOTE" Critical Steps must be completed correctly to achieve a satisfactory grade STEP 5 X Performance Step: Checks Section IV, Power Availability GRADE X Standards: Verifies that the RG appropriately checked A EDG, RSST and NSST/ Main. The *B' EDG is unavailable due to the electrical outage and the SBO is being serviced.
The Power Availability totalis 3, YELLOW. Uses sections 1.5 and 1.8 as a reference. STEP 6 X Performanco Step: Checks section V, Reactivity GRADE X Standards: Verifies that the RO checked all of the boxes and listed inventory flow paths as 1 (Charging pump *A") even though he had checked inventory boxex as 2. The Reactivity totalis 4, YELLOW condition. Uses sections 1.6 and 1.8 as a reference. STEP 7 X Performance Step: Checks section VI, Containment GRADE X Standards: Verifisa 'nat the RO checked the box for Containment Closure set. The Containment totalis 1, GREEN condition. Uses sections 1.4 and 1.8 as a reference 6
PERFORMANCE .;4 FORMATION
)
Facility: Millstone Unit 3 System: ADMIN JPM Number: NRC NEW Task
Title:
SHUTDOWN PISK ASSESSMENT FORM REVIEW l Denote Critical Steps with an *X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade STEP 8 X Performance Step: Checks section Vil, PZR Surge Line Flooding GRADE X Standards: Verifies that the RO has initialed and dated the line opposite the Total pressurizer vent path are equal to or less than 6 sq. in.
STEP 9 Performance Step: Report the completion of the review of the Shutdown Safety Assessment Checklist. GRADE Standh<ds: Informs the examiner that he has completed the review of the Shutdown Safety Assessment Checklist and the the RO made an error in completing section Ill, Inventory. The Train A CHS PP A/C and associated flow path should not have been credited. The total for the section is actually 1, ORANGE condition. Terminating Cue: The evaiuation for this JPM is co.,cluded. Stop Time: 7
... ._ . . - . - . . . . . - . - - - - - - - - - - - - - - - - - - - - ~ - - - -
i
- VERIFICATION OF COMPLETION l
- I
-Job Performance Measure Number: NRC.NEW Revision: 0 Date Performed: ,
Enminee: 1 1 3 Evaluatcr _ _ _ _
; Validated Time (min): Actual time to Complete (min):
' Result of JPM: - (Denote by an S for satisfactory er a U for
; unsatisfactory)
Result of oral questions: Number of Questions: Number of Correct Responses: Score .% 8
EXAMINEE HANDOUT INITIAL CONDITIONS AND INITIATING CUES JPM Tracking Number: NRC NEW Initial Conditions: The following plant conditions exist: The plant is in Mode 5, all RCS loops are full, RCS pressure is 325 pela and RCS temperature is 165'F. It is the start of the day shift The calculated shutdown margin boron is 2050 ppm Train "B" electric plant outage The SBO diesel is OOS for adjustments to the governor The "A" RHR pump is running for decay heat removal The last boron concentration sample was 2510 ppm Both shutdown margin monitors are operable An oil replacement on the "C" charging pump will ba - completed at 10:30 AM The "A" SlH pump is OOS for bearing replacement. Preparations are being made to open containment for the first time this outage. No access doorslopenings are currently open. Time to core boiling is 35 minutes The A, B, and C SGs narrow range levels are at 48%, 55% and 65% respectiveiy. The D SG is dralned down in preparation for secondary side entry. The "A" MDAFW pump is available for feed flow. The AFW cross connect valves are tagged closed. PZR level is 88% on the cold calibrated instrument The "A" SFC pump is running with a pool level of 24'6" above the fuel No work is being performed on the NSST or RSST RWST level is 1,180,000 gallons and 3RHS*V43 is locked closed and tagged SP 3604C.6 was completed last night on the mid shift l initiating Cues: The RO has completed the Shutdown Safety Assessment Checklist. You are to conduct the required review. l 9
' form Approval 1 $tt' A/2 ( - t/ f U "c*
g gMMt 0 81997 PO C 3N Forb Cover heet Genericinformation i /" Form True Rev No. Shutdown Safety Asseasment Checklist 10 Reference Procedure Appheable Tech. Spec. Frequency 3260A N/A
- l This form is being used for the following:
O Tech Spec Surveillance O system")anment Shutdown Risk Management 8 Other: Q Maintenance Restoration Q Non-Tech Spec (Retest) Surveillance (PM) Socettic Information l
References:
Remarks:
' Da 'f snd prior to removing any system required to support Key Safety Systems during MODE 5,6, and O.
Reviewed By: Date: SRO OPS Form 3260A-4 Rev.10 Page 1 of 5
Shutdown S fety Assessment Checklist Date: do,$ , Time: ___ A.) Protected Train (s) A / B (circle one or both) Check if a single traln exception in effect O i
- 1. RCS Decay Heat Removal Decay Heat Removal (RCS)
RHR Train A (1) f TOTAL CONDITION O RHR Train B (1) 0 Red O Allconditions satisfied 1 to support natural circulationin the RCS (1) 2 Yellow O > 23' refuel cavity (1) 3 Green RCS Total NA for Mode 0
/
Available racked down charging pump: A / B / C(0) / C(P) hcircle one) l ll. SFC Decay Heat Removal Decay Heat Removal (SFC) SFC Train A (1) l TOTAL CDNDITION O SFC Train B (1) o I Red
> 23' poollevelabove the fuel (1) 1 Orange SFC Total 2, 2
3 h Green 111. Inventory Inventory g Train A CHS PP NC and associated flow path (1) l TOTAL CONDITION O Train B CHS PP B/C and 0 Red associated flow path (1) 1 Orange [ SlH Train A, aligned to RWST with 2 either hot leg or cold leg injection path (1) ) 3-5 Green O SiH Train B,aiianed to nwST with NA for Mode 0 either hot leg or cold leg injection path (1) Q Both RHR trains available for DHR and both capable of alignment to the RWST (1) Inventory Total 1 Verify RWST level > 250,000 gallons 3RHS*V43, RHR to RWST recirculation isolation tagged and locked closed. ! OPS Fona 3260A-4 Rev.10 Pace 2 of 5
GPw vtt- Hed Shutdown Sdety Assessment Checklist I Date: -Cha Time: N6u) IV. Power Availability Power Availability Need at least one offsite source, one EDG, and one other. A EDO (1) ,1 Om MDM D B EDG(1) 0-1 Red I RSST (1) I 2 Orange NSST/ Main (1) - O Station Brackout EDG(1) 3 Yellow Power Total 3 V. Reactivity _f _ Reactivity if RCS Boron > required SDM (1) l TOTAL CONDmON
@ Inventory flow paths (0-2) l 0-2 Red 3 Orange Q At least one Shutdown Margin Monitor train j vailable (1) 4 Q Dilution paths taggod using SP 3604C.6 (1) l 5 Green NA for Mode 0 Reactivity Total VI C tainment Containment Containment Closure set (1) CONDmQN O Containment Ciosure set witn exceptions tracked and capable of being closed prior o ned to the more restrictive of: (1) 1
=
Time to core bolling NA for Mode 0 4 hours Containment Total / Vll. PZH Surge Line Flooding One of the following conditions exist: w.m o.1, Reactor vesselhead removed /
+
Reactor core refueled or decay heat insufficient to cause surge line flooding /
+
Total pressurizer vent path area equal to or less than 6 sq in, g . g gj" OPS Form 3260A-4 Rev.10 Pate 3 of 5
A.2 Fouinment Control The process for making configuration control Question #1: Ifit is necessary to lock a component for a short period of time, what information is required to be docummented on the Shift Tumover Report? (list 3 items) Answer #1: OP 32608, Equipment Control, requires the following information be documented on the Shift Turnover Report; Component ID
- Position MODE Information stating why the component is locked Infomiation stating what conditions must ne satisfied to remove restraining device j from component Wher applicable, the following information is also documented on the Shift Turnover Report:
SM authorization for placement of restraining device SM authorization for removal of restraining device When a component is temporarily locked, that component must be evaluated for addition ( to locked component list and, if required, a change to OPS Fomi 32600-1 and l appropriate OPS Forms is submitted. i i i
A.2 Eaulnment Control The process for making configuration control Question #2 What is the proper method for verifying the position of a locked open manual valve that has no slack in the restraining icvice? Answer #2 OP 3260B, Equipmet Control, Attachment 3 provides the following guidance: Remove the restraining device and then use the method for a non locked valve Turn valve handwheel in close direction to confirm that the valve was open Turn valve handwheel in open direction until the valve is fully open Close the valve 1/4 turn
- Restore the restraining device
A.3 Radiation Control Knowledge of radiation exposure limits and contamination control, including pennissible levels in excess of those authorized. Applicable references available at the RCA may be used to answer this question. Question #1 You have been sent to the auxiliary building to complete some tagging. One of the tags that you must haug requires you to enter a Tech Spec Locked liigh Radiation Area. What requirements must be met for you to make this entry? Assume the radiation levels and the time to complete the job will are low enough that you will not exceed any personnel exposure limits. Answer: Check Radiation Work Pennit #5, job step 2 of 4. Must contact ilP for a PRi? Joll lirief and latet survey data The !!P briefing shallinclude: Digidose alann setpoint and Stay Time Control / Return ofIIR-2 Key Survey meter, alanning c:c imeter or continuous llP coverage required for entry into Tech Spec Locked liigh Radiation Areas.
t A.3 Radiation Control Knowledge of radiation exposure limits and contamination control, including pennissible ' levels in excess of those authorized. Question #2 If you were sent to the Auxiliary lluilding to replace a filter that was in a housing that had a contact dose rate of 450 mrem /hr and you expected to receive a dose to your extremity of 125 mrem and a whole body dose of 20 mrem, what special instructions must be met. I Answer: Check Radiation Work Pennit 5. job step 1. Operations liianket Under the Special Instructions Section notes the following for Filter change Evolutions: Any filter housing with a contact dose rate of 500 mrem /hr or greater will be worked on RWP 10. Since the contact reading is 450 mrem'hr, can perfonn the task under RWP 5 lip to survey filter housing prior to filter removal and survey filter (s) upon removal Ilecause fluter changes ace rapid evolutions, finger rings are required when dose to the extremity 5 times the whole body dose and dose to the extremity >iOO mrem is expected. Based on the give.. conditions, the expected dose to the extremity is greater than 5 times the expected whole body dose and is greater than 100 mrem. A finger ring is required. IIP to survey all tools and work area r i
. , , . m. - --e o
J. .
- JOB PERFORMANCE MEASURE WORKSHEET
- 1. JPM
Title:
EAL Classification for NRC Scenarios-1997 1 ..
~ ID Number: JPM NRC-Scenario 2 Revision: Q ll. -Initiated:
R.L. Lueneburg 6/2/97 Developer Date Ill. Reviewed:
~
Technical Reviewer Date Instructional Reviewer Date IV. Approved: Operations Manager Date Nuclear Training Supervisor Date 1
JOB PERFORMANCE MEASURE WORKSHEET Facility: Millstone Qaitj Examinee: ) JPM Tracking Number: NRC-Scenario 2 Validation Time: minutes Task
Title:
EAL Classification for NRC Scenarios-1997 Time Critical Task: ( )YES ( X ) NO Task Number: 301*002 05*02 K/A Number: 2.4.41 KIA Rating: 4.1
- Acolicable Methods of Testino:
Simulate Performance Actual Performance X Classroom Simulator & Plant Task Standards: Satisfactorily classify the event for the scenario just completed on the simulator, Beautred Materials: None General
References:
EPIP 4400, rev 4 READ TO THE EXAMINEE I will explain the initial conditions, which step (s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objectives for this JPM will be satisfied. You may use any approved reference materials normally available in the Control Room, including logs. Make all written reports, oral reports and log entries as if the evolution was actually being performed, initial Conditions: You have just completed the scenario in which you participated. Assume that you are the SM. The simulator will remain in freeze with the conditions that existed at the end of the scenario. Initiating Cues: Determine the highest classification you would have declared during the scenario you just completed. Inform the examiner of this classification and the basis for your decision. 2
. ~
4 JOB PERFORMANCE MEASURE WORKSHEET Simulator Requirements: DO NOT reset the simulator until the examinee has completed ! this JPM and the NRC lead examiner indicates it is okay to proceed, s i l i 3
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: Admin JPM Number: NRC-Scenario 2 Task
Title:
EAL Classification for NRC Scenarios-1997 - Denote Critical Steps with an "X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade Start Time:
STEP 1 Performance Step: Obtain a copy of EPIP 4400 or use the laminated copies that are available on the SM desk. GRADE Standards: Pulls out the procedure EPIP 4400 or obtains the laminated copies of the classification tables STEP 2 X Performance Step: Determine the conditions that existed during the scenario that will contibute - to the information needed to accurately make the classification. GRADE X Standards: If a first out occured before the crew , manually initiated a reactor trip, the crew should have realized that an auto reactor trip did not occur, but they were successful at initiating a manual trip. If the crew manually tripped first then there was a manual actuation of ESF including RPS or there was an event that prevented fulfillment of a safety function ( remove residual heat) 4
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: Admin JPM Number: NRC-Scenario 2 Task
Title:
EAL Classification for NRC Scenarios-1997 4 Denote Critical Steps with an "X"
,
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade STEP 3 X Performance Step: Use the applicable table (s), to determine the correct classification.
GRADE X Standards: If the the auto trip failed to actuate, goes to The Equipment Failure column and goes don 1 to EA1, Automatic Trip Failue(Failure of Automatic reactor Tri,n and Manual Trip was Successful). Classification is Alert, Charlie-one If the crew manually tripped first, goes to Attachment one of EPIP4400 and uses either to page S/12 (ESF actuation) or page 6/12 (failure to remove decay heat) . Classification is an Echo and the NRC must be notified within 1 hour via ENS' STEP 4 Performance Step: Inform the examiner of the classification. GRADE Standards: Reports to the examiner that the event is either an Alert or an Echo and provides the reason for the decision. 1 Terminating Cue: The evaluation for this JPM is co.ncluded.
' Stop Time: .
t 5
VERIFICATION OF COMPLETlON Job Performance Measure Number: NRC- Scenario 2 Revision: 0 l Date Performed: Examinee: Evaluator: Validated Time (min): Actual time to Complete (min): Result of JPM: (Denote by an S for satisfactory or a U for unsatisfactory) I i 4 l
-s 6
EXAMINEE HANDOUT INITIAL CONDITIONS AND INITIATING CUES JPM Tracking Number: NRC-Scenario 1 Initial Conditions: You have just completed the scenario in which you participated. Assume that you are the SM. The simulator will remain in freeze with the conditions that existed at the end of the scenario. I Initiating Cues: Determine the highest classification you would have declared during the scenarlo you just completed. Inform the examiner of this classification and the basis for your decision. 7
.i
- - ..~ _ -.-. - .. - -- - - _ -._.-. - -
JOB PERFORMANCE MEASURE WORKSHEET
- l. ~JPM
Title:
EAL Classification for NRC Scenarios-1997 i i ID Number: JEM-NRC-Scenarin 3 Revision:- 0 l ll. Initiated: R.L. Luenebur9 6/2/97 Developer Date 111. Reviewed: i Technical Reviewer Date Instructional Reviewer Date j l IV. Approved: Operations Manager Date Nuclear Training Supervisor Date 1-
JOB PERFORMANCE MEASURE WORKSHEET Facility: Millstone Unit 3 Examinee: JPM Tracking Number: NRC-Scenario 3 Validation Time: minutes Task
Title:
EAL Classification for NRC Scenarios-1997 Time Critical Task: ( )YES ( X ) NO Task Number: 3.0f002*05*02 K/A Number: 2.4.41 K/A Rating: 4.1 Apolicable Methods of Testing: Simulate Performance Actual Performance X Classroom Simulator X Plant Task Standards Satisfactorily classify the event for the scenario just completed on the simulator. Reauired Materiait None General
References:
EPIP 4400, rev 4 READ TO THE EXAMINEE I will explain the initial conditions, which step (s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objectives for this JPM will be satisfied. You may use any approved reference materials normally available in tne Control Room, including logs. Make all written reports, oral reports and log entries as if the evolution was actually being performed. Initial Conditions: You have just completed the scenario in which you participated. Assume that you are the SM. The simulator will remain in freeze with the conditions that existed at the end of the scenario. Initiating Cues: Determine the highest classification you would have declared during the scenario you just completed. Inform the examiner of this classification and the basis for your decision. 2
i . e JOB PERFORMANCE MEASURE WORKSHEET Simulator Requirements: DO NOT reset the simulator until the examinee has completed this JPM and the NRC lead examiner indicates it is okay to-proceed.
PERFORMANCE INFORMATION , 1 Facility: Millstone Unit 3 System: Admin JPM Number: NRC-Scenario 3 Task
Title:
EAL Classification for NRC Scenarios-1997 { Denote Critical Steps with an "X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade Start Time:
STEP 1 Performance Step: Obtain a copy of EPIP 4400 or use the laminated copies that are available on the SM desk. GRADE Standards: Pulls out the procedure EPIP 4400 or obtains the laminated copies of the classification tables 2 STEP 2 X Performance Step: Determine the conditions that existed during the scenario that will contibute to the information needed to 4 accurately make the classification, GRADE X Standards: There was an event which resulted in ECCS discharge into the RCS, Also, there was a amnual/ auto actuation of ESF. 4
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: Admin JPM Number: NRC-Scenario 3 Task
Title:
EAL Classification for NRC Scenarios-1992. Denote Critical Steps with an *X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade STEP 3 X Performance Step: Use the applicable table (s), to determine the correct classification.
GRADE X Standards: Goes to Attachment one of EPIP4400 and uses either to page 5/12 (F.SF actuation) or page 3/12 (ECCS discharge into the RCS) . Classification is an Echo and the NRC must be notified within 1 hour via ENS STEP 4 Performance Step: Inform the examiner of the classification. GRADE Standards: Reports to the examiner that the event is an Echo and provides the reason for the decision. Terminating Cue: The evaluation for this JPM is concluded. Stop Time: 5
. . - - . - - . . . - . . . ~ . . _ . . . - - _ . . . ~ - . . . _ . . -
VERIFICATION OF COMPLETION J
- Job Performance Measure Number: NRC-~ Scenario 3 ~ ' Revision: 0
' Date Performed:
Examinee: Evaluator: Validated Time (min): Actual time to Complete (min): Result of JPM: ._, (Denote by an S for satisfactory or a U for unsatisfactory) 6
EXAMINEE HANDOUT 4 INITIAL CONDITIONS AND INITIATING CUES JPM Tracking Number: NRC-Scenario 3 Initial Condillana: You have Just completed the scenario in which you participated. Assume that you are the SM. The simulator will 4 romain in freeze with the conditions that existed at the end of the scenario. , initiatina Cues: Determine the highest classification you would have declared i during the scenario you just completed. Inform the examiner of this classification ard the basis for your decision. 4 7
l JOB PERFORMANCE MEASURE WORKSHEET
- l. JPM
Title:
EAL Classification for NRC Scenarios-1997 ID Number: JPM NRC-Scenario 6 Revision: 0
- 11. Initiated:
R.L. Lueneburg 6/2/97 Developer Date Ill. Reviewed: Technical Reviewer Date instructional Reviewer Date IV. Approved: Operations Manager Date Nuclear Training Supervisor Date 1
. . . . ~ . - . - . .- . .- -.
JOB PERFORMANCE MEASURE WORKSHEET Facility: Millstone Unit 3 Examinee: JPM Tracking Number: NRC-Scenario 6 - Validation Time: minutes Task
Title:
EAL Classification for NRC Scenarios-1997 Time Critical Task: (-)YES ( X ) NO Task Number: 301*002*0S*02 K/A Number: 2.4.41 K/A Rating: 4.1 Aeolicable Methods of Testing: Simulate Performance Actual Performance -X ' Classroom Simulator X Plant Task Standards: Satisfactorily classify the event for the scenario just completed on the simulator. Reauired Materials: None General
References:
EPIP 4400, rev 4 READ TO THE EXAMINEE I will explain the initial conditions, which step (s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objectives for this ~JPM will be satisfied. You may use any approved reference materials normally available in the Control Room, including logs. Make all written reports, oral reports and log entries as if the evolution was actually being performed. Initial Conditions: You have just completed the scenario in which you participated. Assume that you are the SM.- The simulator will remain in freeze with the conditions that existed at the end of the scenario, initiating Cues: Determine the highest classification you would have declared during the scenario you just completed. Inform the examiner of this classification and the basis for your decision. 2
' JOB PERFORMANCE MEASURE WORKSHEET - Simulator Requirements: DO NOT reset the simulator until the examinee has completed this JPM and the NRC lead examiner indicates it is okay to proceed, i
1 4 e 4 4 3 g .-cy-, _ _
PERFORMANCE INFORMATION { Facility: Millstone Unit 3 System: Admin JPM Number: NRC-Scenario 2
- Task
Title:
EAL Classification for NRC SceDarios-1997 Denote Critical Steps with an T
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade Start Time-
- STEP 1 Performance Step: Obtain a copy of EPIP 4400 or use the laminated copies that are available on the SM desk.
, GRADE Standards: Pulls out the procedure EPIP 4400 or obtains the laminated copies of the classification tables STEP 2 X Performance Step: Determine the conditions that existed during the scenario that will contibute 4 to the information needed to accurately make the classification. GRADE X Standards: A Loss of Coolant accident occured that was beyond the capability of one , charging pump and the crew entered E-0. i 9 d 4
PERFORMANCE INFORMATION
- Facility: Millstone Unit 3 System: Admin - JPM Number: NRC-Scenario 2 Task
Title:
EAL Classification for NRC Scenarios-1997 Denote Critical Steps with an "X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade STEP. 3 X Performance Step: Use the applicable table (s), to determine the correct classification.
GRADE X Standards: Goes to The Barrier Failure Reference Table and goes to the RCS Barrier column and goes down to RCB4, Potential Loss (reactor coolant leak
>one charging pump capacity AND entry into E-0, Reactor Trip or Safety injection)
Determines that this applies and goes-to the farthest right hand area for "only one barrier affected" and determines that with only the RCS barrier potential loss it is classified as Alert, Charlie-one. STEP 4 Performance Step: Inform the examiner of the classification, GRADE Standards: Reports to the examiner that the event is an Alert and provides the reason for the decision. Terminating Cue: The evaluation for this JPM is concluded. Stop Time: 5
VERIFICATION OF COMPl.ETION ! Job Performance Measure Number: ' NRC- Scei.ario 6 Revision: il Date Performed: Examinee: Evaluator: Validated Time (min): Actual time to Complete (min):
. Result of JPM: (Denote by an S for satisfactory or a U for unsatisfactory) 8 T
s t i l. J t f J. h -~ 6 w- -
. _ . _ _ __ _ _._._ _ ~ . _ . . _ _ _ . __ __ _._. _ _ _ _ _ . _ _
EXAMINEE HANDOUT ^ INITIAL CONDITIONS AND INITIATING CUES JPM Tracking Number: NRG Snenarlo_6 Initial Conditions: You have Just completed the scenario in which you participated. Assume that you are the SM. The simulator will remain in freeze with the conditions that existed at the end of the scenario. 4 Initiating Cues: Determine the highest classification you would have declared during the scenario you Just completed. Inform the examiner J of this classification and the basis for your decision. a l J i 7
a. l Scenario Events Facility': Millstone Three Scenario No.: ifRev 1) Examiners: Operators: Objectives:- The crew will be directed to perform the stasm generator _ blowdown valve cycling surveillance. When the first
.'ineup is completed, Pressurizer Pressure Instrument PT455A fails low. This will require taking manual control of pressurizer pressure. The crew will be able to use AOP 3571 and restore pressure control to automatic. Due to a loop seal problem, vacuum will start to decrease in the condenser. It-will reach a -point where the crew will start to reduce power. The cause of the vacuum problem will be found and corrected. The crew will stabilize the plant. The "B" condensate pump will trip and the "C" condensate pump will fail to auto start. When the operator starts:the "C" condensate pump it will not-pump due to a shaft shear. This will result in a loss of suction pressure for the main feedwater pumps and they will trip. The motor driven feedwater pump will trip as soon as it starts resulting in a total loss of feedwater. Either due to low SG level or manual initiation by the crew, a reactor trip signal will be generated.
The reactor will not 1trip until the trip switch at MB7 is used. Nonelof the AFW pumps will:be running and the crew must address a complete loss of feed. The scenario will end when the crew establishes feed from a condensate pump. Initial-Conditions: The plant-is operating at 100% power. The crew will be directed to maintain current plant' conditions. Turnover: The crew will be-provided the MP3 simulator standard-turnover sheet which will direct them to maintain current plant ' conditions. The following equipment will be out of service: "A"
. service water pump, "A" motor driven auxiliary feedwater pump, and "B" stator cooling pump. There are thunderstorm warnings for the next 4-6 hours.
0
-s .
4 Event eMalf Event Event Descrintion h A' tygg 11 4N -Conduct the surveillance for steam generator ~ blowdown valve cycling.
'2 I Pressurizer pressure instrument PT455A fails _ low. this will require the-operator to take manual control of' pressurizer pressure, the instrument
_ failure will be addressed, including
- Tech. Spec. and pressure control will be returned to automatic control..
3- R. A decreasing vacuum.will cause the crew to rapidly reduce power in attempts _to stop the' vacuum decrease. _-The source of-the vacuum decrease'will be found and corrected. 4 N: The crew will stabilize the plant once the source-of the vacuum decrease has been found 5 C- As the crew is stabilizing the plant i the "B"; condensate pump will trip. The "C" condensate-pump will not: auto start.
- When the operator does start theLpump it.will not pump water due to a coupling
' shear.
j-- 6 C The loss of. suction pressure will'cause j-- -the turbine driven feedwater pumps to
' trip and the motor driven pump trips as soon-as it starts. The operators may attempt to start the MDFWP
. 7 C When an automatic signal is generated or when'a manual trip is attempted the reactor will not trip. The operators i t f._
can successfully trip the reactor from MB7, 8 M Norte of the auxiliary feedwater pumps will start. A total loss of feedwater event will occur. i-
I
- l ,
Scenario Events
' Facility: Millstone Three Scenario No.:- 3 (Rev.1)
Examiners: Operators: Objectives: The crew will conduct the downpower to 90% power. During the downpower, after reactivity control-has been l demonstarted, The "D" SG-level transmitter will fail to zero. [ the operators will_ be required to take manual control of the "D" SG feed regulating valve. after taking the actions in AOP 3571 >
- and addressing Tech Specs., the crew will_be able to return to b automatic-control of the_ feed regulating valve. All the necessary
- preliminary checks of the motor driven feedwater pump will be completed and the crew will make start-the third condensate pump in preparation for swapping the feedwater pumps. When this is completed, a power range channel will slowly fail causing the rod
~ control system to move rods. The operators will take manual rod
' control and.will be able to bypass the affected channel. When
- rod-control is returned-to automatic a continuor rod insertion h begins. 'The operators will need to trip the reactor to stop the i insertion. _When the reactor trips, the turbine will fail to trip
{ nor can-it be run back. The operator will need to close the
- MSIVs. The shock of the MSIVs. closing will cause an unisolable steamline break inside containment. -When containment
- pressure reaches 23 psia,'the automatic CDA will not occur.
l : Initial Conditions: The plant ~is at 100% power. Excessiv:. 11 vibration exists on the "B" TDFWP. The crew will be directed to
- ~ reduce power to 90%-at 1/2% per minute and swap feed water pumps.
Turnover: The crew will be provided the MP3-simulator standard
-turnover _r.heet which will direct them to reduce power to 90% at a
' rate of 1/i%-per minute. The following equipment will be out of i
service: '"A" service water pump, "A" motor driven AFW pump and ~
'the-"W' stator cooling pump. There are thunderstorm warnings for
- the next 4-6 hours.
)
_ . . . . . -. . _ _ . . . __ _ _ _ . _ - . . _ . = _ . _ . _ - _ _ _ ,
}.
,. -Event' Malf' Event Event Description -/
-L~ k; Lygg V 1: R -The crew-will reduce power to 90%.
2 I The "D" SG level transmit'ter will fail ' low requiring manual control of the "D" I SG feed regulating valve.- Once the procedure steps have been completed, the operators can restore the feed regulating-valve back to auto contol. 13 N The crew will start the third condensate pump in preparation for swapping the feedwater-pumps. . 4 I- An NI power range channel fails high which will result in manual-rod control. y The crew will be able to remove the-channel from service and return to-automatic rod control. q 5 ,C When the operator returns rod. control to automatic a continuos insertion of the control bank "D" rods will occur. The operators will attempt to return the rods to manual control. The operators will be' unable to stop the insertion except to' trip _the reactor.
;6 M/C When the reactor is tripped, the turbine willtfail to trip. Additionally the turbine will not runback nor will an automatic main steamline~ isolation occur. The operator--will have to use ,
the control switches to. shut the MSIVs.
-7 M'- When the MSIVs are closed a unisolable steamline break occurs inside containment. This will result in a .
safety injection actuation.
1 1 i I
- . 8 C When containment pressure e ceeds 23 psia, an automatic CDA will ot occur.
The operators will need to mutually initiate CDA at the component operating switches (pushbuttons failed also) .
, - _ , ~ . _ . - - - . . .. - - ~.. - - . - _ . - .~.- - . . - . . - - . - ~ _ .
Tf A E F.L !& Scenario Events q l
- Facility
- Millstone'Three. Scenario No.: 6 (Rev.1)
Examiners't. Operators: Objectives: The crew will be_ told that the "A" service water pump is' ready for a test run. The crew.will conduct the swap from the "C" to the "A" SWP. The crew will conduct the test of N) the HP-turbine stop valves, after the first stop valve is tested, the selected first stage pressure channel will fail low resulting in the control rods stepping in. The operator will take manual control'of the rods. When the crew returns to automatic rod control CONVEX-will request a 200MW load reduction. The crew fwill conduct this lead change. After the crew has-satisfactorily demonstrated reactivity control, one of the control bank "D" rods will stick and eventually be out of position. While I&C is
' investigating, they inadvertently cause the affected group of
-rods to drop into the core. The crew should recognize that this
-requires.a_ reactor _ trip. When the trip occurs, a large break LOCA occurs. Automatic SI will not occur, The motor driven AFW pumps will not auto start and some of.the charging system valves will not re-align for the SI.
Initial Conditions: The plant.will be at 100% power. The crew w ill be directedLto shift to the "A" CWP and when that.is
-completed, to conduct the test of the HP turbine stop valves.
Turnover:- The crew will_ be provided the MP3 ' simulator star dard turnover sheet which will have-them maintain current plant conditions. the following equipment will be out of service: "A" service water pump (but is ready to be placed back in service),
="A" motor driven AFW pump, and "B" stator cooling pump. There-are thunderstorm warnings for the next 4-6 hours, i
_____ _ _ _._ _.._,_ _,.__ _._._ . _ _ _ _ . _ _ . . _ _ _ _ _ . _ . . . . _ _ _ _ _ _ _ . _ ~ . _ c ie-Event Malf Event' Event nameription HA. HL. 14tpA 1- N Conduct a swap from the *C" to the "A" Service Water Pump. l 2 N t Conduct the surveillance for the llP _; Turbine Stop. Valves. { 3 I- First staga pressure transmitter PT505 will slowly fail low. This will cause rods to-start driving in and manual rod control'will be required. The crew will be able to return to automatic rod-control. 4 R Convex will call and request a load shed of 200MW. The crew will commence a rapid downpower. 1 5 C After the crew has addressed the control of the reactor in the downpower procedure, one of the control bank "D" rods will tich and eventually be out of position. 6 M When the I&C department personnel are sent to investigate the; stuck rod,Ethe affected group of rods will drop into
- v. the core. The crew should recognize that a reactor trip is required.
7 M When the reactor is tripped a large break-loss of coolant accident occurs, An automatic SI will not occur.
.8 .C Neither motor driven auxiliary feedwater-pump-will auto start on the SI. -The operator will be able to manually start l them.- -
1 . E C 'The charging system valves ~will not i realign for the SI. The operator "ill i I
i o be able-to operate the valves using the individual valve control switches. l o A 4
sed 0 N pp, Q hg b dr (l e 5 T l H S
'l Il 710
individual Walk Throttgh Test Outline Millsone Unit 3 Exam Date: Week of 7/7/97 RO/SRO 1 SrldRevi) JPM fi and Title Safety Function Svs Code I inPlant ' 006 Place swing Charger 301 A 3 on Bus 301 A 1(D) 6 063 019 Locally restore AFW Flow (hiotor driven pumps 4 061 and valves)(A) 137 Es;ablish Feed & Bleed on Charging Pump Cooling (D) 2 004 Simulator XXX First 8 steps in ES 1.1, Si Termination (N) 2 006 XXX Containment Purge System Lineup (N) 8 029 055 hianual Initiation of Containment Spray (D) 5 026 109 Aligning Support Systems While Perfonning 8 008/078 Recovery with the Si!O Diesel (D) 050 Pressurizer Pressure Control Following a Trip (A) 3 010 042 Restore 4.16 KV Bus Aher Loss of Power (D) 6 062 130 Control Rod Out of Alignment (D) 1 001
JPM 006 l Question #1 What are three possible sources of power to inverter l? I answer: Normal hiCC via rectifier to the invener llackup DC supply hiCC via llattery charger to DC bus to inverter 13ackup Ilattery to DC bus to inverter d il 6 I e
l JPM 006 Question #2 l 1 l What single indication could an operator use to determine which source is supplying power to the Inverter? k Use inverter DC input voltage: Normal rectifier output is about 140 VDC Charger output is about 132 VDC 11attery output is about 125 VDC 1 I I
JPM.006 Question #3 Why is 125 VDC system voltage limited to a maximum of 140 VDC7 answer: liasis Infonnation At voltages greater than 140 VDC components may suffer from insulation breakdown, which may result in shoner equipment life and failure. i
REFERENCE:
OP3345C basis document JUSTIFICATION: Basis information (From procedure) At voltages greater than 140 VDC, components may suffer from insulation breakdown. which may result in shorter equipment life and failure. K/A: 063 A3.01
9 JPM 019 Question #1 Assume the crew is still responding to a loss of secondary heat sink, efforts to restore AFW have been unsuccessful. Wide range steam generator levels in "A", "11", and "C" steam generators is 32%
+
Wide range steam generator level in "D" steam generator is off scale low because it la faulted.
- CETs are 510'F and stable
+
RCS pressure is 2350 psia
- Containment temperature is 170 'F What is the next recovery action the crew would take?
answer: Attempt to restore Main Feedwater
REFERENCE:
FR il.1 JUSTIFICATION: The methods, in order, of recovery in FR il.1 AFW flow Main Feedwater Condensate 111ee1 and Feed illeed and Feed is initiated if: 3 Steam generators less than 27 % (57% adverse n'a) Pressurizer pressure greater than or equal to 2350 psia due to loss of secondary heat sink indicated by core exit TCs increasing. (the reason pressure is high is the pressurization from ECCS aller the D steam generator blows down). K!A: DE E05 EA2.1
l l l JPM 019 1 Question #2 Ifin LOCAL, which Motor Driven AFW pump (s),if any, will start on Lo Lo Steam Generator Level? answer: the 11" MDAt W pump will start.
REFERENCE:
LSK 6.21 A. 6.2111 JUSTIFICATION: In LOCAL, the "!!" pump will still receive a start signal from any of the Automatic start signals, the "A" pump will not receive an automatic stan. K/A: 061 K4.02 4.5/4.6 i
JPM 042 Question #1
% ith the initial conditions given for this JPM, what would be the "11" train response if, instead of taking the 341134D bus tie breaker to "CLOSE", the operator had taken the "11" EDO output breaker to "0 PEN"?
answer: no response, the EDO breaker would not open.
REFERENCE:
LSK 9.213 JUSTil'ICATION: With the LOP signal present, the breaker cannot be opened by the operator. K/A: APE 056 AA2.14 4.4/4.6
11 h 042 Question #2 > Assurne the EDO is being loaded to full load at a nonnal loading rate. Approximately how long should it take the operator to fully load the diesel? answer: l 10 minutes. REFEllENCE: OP3346A JUSTIFICATION: 6.8 Unless an emergency situation exists or specified by surveillance test, emergency diesel generator should not be loaded immediately to ra'ed capacity. Nonnal loading rate is approximately 10%/ minute K/A: 064 A4.05 3.9/3.9 5
JPM:10 Question #1 The following plant conditions exist:
- The Unit is operating at 100% power
+
Pressurizer pressure control is in automatic
+
One set of backup Heaters is energized
+
Actual pressurizer pressure is 2250 psia The pressurizer Master Pressure Controller malf unctions and the setpoint is step changed to 2200 psia. Which of the iollowing describes the initial automatic responses in the pressurizer Pressure Control System as a result of this failure answer: Spray Valves open, pressurizer heaters turn off. REFERENCEt Process Drawing Sheet 26 Functional Drawing Sheets 11 & 12 JUSTIFICATION: If the setpoint changes to 2200 psia, then the controller will take action to bring pressure to setpoint. At 50 psia below current pressure, the heaters will turn off, the spray valves will open, the PORVs will remain closed because their setpoint is 100 psia above setpoint. K/A: 000027 EA2.03 3.3/3.4 010 GEN.07 3.4/3.4 010 K6.03 3.2/3.6 (
JPM 50 l Question #2 { The plant is at full power, with all systems in AUTO. What wou!d be the response of Pressurizer PORV 3RCS'PCV455A if the controlling channel of Pressurizer pressure failed 1110117 answer: The PORV opens due to the high input but closes when RCS actual pressure is less than 2200 psia on the other 3 channels being below 2200 psia.
REFERENCE:
PPLO10T, Functional sheet 11 and 18 JUSTIFICATION: see answer K/A: 010 A4.03 4.0\3.8 l v' e w - w w wgw
I JpM 055 Question #1 i A caution prior step 3 of FR Z.1 informs the operator not to perfonn steps 3,4 and 7 if ECA 1.1 is in progtess. What is the basis for this caution? 1 answer: recirculation flow is not available and it is very important to conserve RWST water, if possible, by stopping containment spray pumps, i REFERENCF Westinghouse background for FR Z.1, step 3 Caution i t JUSTIFICAT!ON: This cautions wams the operator that the operation of the containment spray pumps indkated in guideline ECA 1.1 takes precedence over that noted in step 3 of this guideline. This guideline specifies maximum available heat removal system operability in order to reduce containment pressure. Guideline ECA 1.1 uses a less restrictive criteria, which pennits reduced spray pump operation depending on RWST level, containment pressure and number of emergency thn coolers operating. The less 4 restrictive criteria for containment spray operation is used in guideline ECA 1.1 since recirculation flow to the RCS is not available and it is very important to conserve RWST water, if possible, by stopping containment spray pumps. K/A: EPE Ell EK3.2 e P
. _ . - - , . . , . , _ - , - . - - . - . . , _.--,w.,_.,
JpM 055 Question #2 Step 2 of FR Z.1 has the operator stop the RCPs. Why are the RCPs stopped? answer: Clu results in loss of cooling to the RCP seals and motors. To prevent damage to the p* imps, they are stopped.
REFERENCE:
FR Z.1 background and E 0 background JUSTlFICATION: 1113 trips the RPCCW pumps and isolates the RPCCW containment headers. This results in loss of cooling to the RCP seals and motors, since it is not vital for the pumps to be operating, they are tripped to prevent damage to the motors or seals.
!!/A: EPE E14 EK3.3
JPM 109 Question #1 Why is the alternate power supply to MCC32 lZ (3 Nils MCC9Al), " Silo Diesel MCC" only used for testing? answer: The alternate supply is not capable of carrying all the Silo loads
REFERENCE:
OP3346D, basis JUSTlFICATION: liasis Infonnation Normal supply by backfeed is preferred due to the alternate source being undersized and not capable of carrying all of the Silo diesel load requirements during Silo diesel operation. K/A: 064 K1.01 4.1/4.4
l l l ! JPM.109 l- Question #2 l i Why are the CSF status trees monitored "for information only" if the SIl0 diesel is the sole
- source of power? l l
answer: ! implementation of the status trees cannot begin without an emergency bus powered from an i Emergency Diesel Generator or offsite power, i
REFERENCE:
ECA 0.3, Integrated Safety Evaluation Determination 10/26/95 I i JUSTIFICATION: The ISED dealt with deleting the note dealing with implementing CSF . status trees. ! l "The change deletes a Note allowing implementation of CSF Status Trees. i l This implementation cannot begin without an Emergency 13us powered by an EDO or Offsite Power. Therefore the change does not affect the strategy of the procedure, but ensures that the procedure is implemented , successfully." ,
- K/A
- EPE 0$$ EK3.02 4.3/4.6 q
l r l L e 9 i J
= - . . , e.-. ~ . . , ,m,w.,y....,..,r_., ,m...., ..,,.,.,,..m,%m.,,,_,v,y%,w.,,,._y__,..,y, m, _,..-..g.,,s. ,_.,..,,my,.,py..,3.,,,,. , . . , , -,,,w.,r< -
JPM 130 l Question #1 Assume that in the initial conditions you were given for this JPM, that the misaligned rod was found to be untrippable, llow, if at all, is SilVTDOWN MARGIN affected? answer: SDM decreases by the amount of the untrippable rod.
REFERENCE:
Technical Specification 4.1.1.1,3.1.3.1 JUSTIFICATION: With an untrippable rod, Technical Specification 3.1.3.1 has the operator verify SDM in accordcnce will: 4.1.1.1. Specification 4.1.1.1 i states the required SDM shall be verified acceptable with an increased allownace for the withdrawn worth of the immoable or untrippable control rod (s) K/A: 001 A2,03 3.5/4.2 APE 005 AKl.05 9 i
. , , - , , , . . . - . . , . . - .c , - .,, . , , , . -
1 JPM 130 , Question #2 Why is the reactor shutdown if a rod becomes misaligned during a startup? answer: Dut to the preelse reactivity control necessary during startup, little or no reactivity feedback in l cffect, and the tirne required for alignment which could change conditions assumed in the FCP, l the rods should be reinserted by performing a shutdown.
REFERENCE:
AOP 3552, attachment A background document. JUSTIFICATION: answer is the wording from the background document. K/A: APE 00$ AK 3.04 - 3.4/4.1 e
l ! i JPM.137 Question #1 4 What happens to the Charging Pump Cooling System on a safeguards actuation signal? i.
- - answer
' On receipt of a Safety injection Signal (SIS) or a Loss of Power (LOP) signal, the charging pump _ cooling pump suction and dkcharge cross connect valves close and the standby pumn starts, i creating two independent flow paths. 4 f
REFERENCE:
OP3330D, LSK 9.4A, H. D
. JUSTIFICATION: Si or LOP will start the pump, closes 3CCE' AOV26A (B) l_
I J 1 I i i J-s
JPM 137 Question #2 The procedure for operating the CCE system instnicts the operator to place the non running _ pump in P T L prior to stopping the running CCE pump. What would be the consequen:e of stopping the running CCE pump prior to placing the non. running pamp in P T L7 l answer: the non runnh t' pump would auto stint on low pressure.
REFERENCE:
OP3330D, P&lD 106A JUSTIFICATION: If not in PTL, the standby pump will auto start on low pressure when the
.' inning pump is stopped.
t
. . - - - . . .. . _ . - .---_. . . - - _ . _ . = = _ _- . . . . - . .
NEW . 05 Question #1 While repressurizing the containment to atmosphere, why is the operator cautioned not to open 311VU'CTV32A or 311VU*CTV3211? answer: the operator is cautioned not to open the valves to prevent damage to the venti!ation ductwork.
REFERENCE:
AOp 3568 JUSTIFICATION: caution in the AOp warns the operator damage will occur to the ductwork if the valves are open during repressurization. K/A: 103 A2.05 i l l l
NEW-$ Question #2 Following a Safety injection actuation, what should be the lineup for the:
- SLCRS fans, FN 12A and B
+ Auxiliary Building fans, FN 6A and 6B + Charging Pump room fans, FN.13A and B and 14 A and 11? Assume all equipment operates as designed, answer: Both fans 12A and 128 should be running. Auxiliary building fan 6A is the lead pump and will be running One train,13A aad 14A or 13B and 14B will be running (A is preferre(). REFERENCE. LSK 221 A 221 AA JUSTIFICATION: Sl will open the dampers'for each ScCR fan and both will start. The 6A and B fans are set up to start. The 6A fan first, then the 6B if the 6A fan does not start. 13 and 14 fans will run; whichever train is running will continue to run. The A is the preferred train. K/A: 013 Kl.13 2.8/3.1
NEW1 Question #1 l The crew is about to perfonn a startup from COLD SilUTDOWN. The operator notices the "Arto SI Illocked" permissive on M134D is '.it. What action would have to be taken to clear the annunciator? answer: Cycle the reactor trip breakers.
REFERENCE:
Westinghouse functional sheet 8, LSK 27-17A JUSTIFICATION: The pennissive it.dicates that automatic Si is blocked, which occurs following the Si reset timer timing out (60 seconds) and P-4 present. When the operator goes to reset (momentary contact), auto Si actuation (for each train with P 4 present)is blocked. Cycling the trip breakers will break the signal and reset the permissive and the circuitry to reset the system for automatic Si actuation. K/A: 006 K4.11 3.9/4.2 1 J
f NEW-1 , Question #2 ! i SSPS testing is in progress while the plant is at 50% power. The technician makes an error and l one train of Si is actuated. The STA recommends not actuating the other train of Si becruse it is not needed to satisfy the minimum safety function requirements and it will extend the time the crew must spend in recovering from the inadvertant Sl? ' Do you agree with this recommendation? Why or why not? ! answer: no. The opposite train should be actuated.
REFERENCE:
Op?272, attachment 3 i JUSTIFICATION: If a licensed operator observes that a safety signal actuation should have occurred or is required to place t!.e plant in a safe condition, the operator shall communicate the p, rtinent plant conditions and intention to take action to the SM/US and then manually initiate the required safety signal. , if the manual safety signal initiation does not result in the proper safety system actuation, the licensed opera'or shall then manually operate the associated equipment to establish the required safety function. .
~
However, when performing steps 5 14 of E-0, and a safety signal or component is observed to not have' actuated or to have only partially actuated, a licensed operator should take action to manually initiate the safety signal or, in the case of a failed component, manually place the component in its required safety condition. 1 K/A: 006 A2.13 9 _ , ..,,.__m,-,y--,_.,_.,-.,__,,,,-,,,,,...,,_r. . . , , _ , _ , , . . , . _ , , , . , , , , , , , . , . , , , . . , . ..C, mv m ,, ,, .,,_,.,.,...;._,, _ _ .,.. .. .,.,,,_.J
ORIG. JOB PERFORMANCE MEASURE WORKSHEET
- 1. JPM
Title:
CONTROL ROD OUT OF ALIGNMEblI ID Number: JPM 130 Revision: 1
- 11. Initiated:
1 R.L. Luenebur9 5/15/97 l Developer Date 111. Reviewed: ! I. Technical Reviewer Date instructional Reviewer Date , IV. Approved: l Operations Manager Date Nuclear Training Supervisor Date I t 1 p 1h
j JOB PERFORMANCE MEASURE WORKSHEET Facility: Millstone Unit.3 Examinee: JPM Tracking Number: .130 Validation Time: minutes Task
Title:
CONTROL ROD OUT OF ALIGN'/EMI Time Critical Task: ( )YES ( X ) NO Task Number: 344'045'04'01 and 344'122'04'02 K/A Number: 001-A2.03 K/A Rating: 3.5/4.2 Acohenble Methods of Testina: Simulate Performance __ Actual Performance X Classroom Simulator X Plant Iask Standards: Satisfactorily recovery from a misaligned control rod using AOP 3552 Attachment A
- Recuired Materials
- Shutdown margin calculation General References AOP 3552 Rev. 3 READ TO THE EXAMINEE I will explain the initial conditions, which step (s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objectives for this JPM will be satisfied.
1 You may use any approved reference materials normally available in the Control Room, including logs. Make all written reports, oral reports and log entries as if the evolution was actually being performed, laitial Conditions: A problem in the EHC circuit caused a momentary runback of the turbine / generator. During the subsequent insertion of the reactor control rods, rod D4 in Control Bank D was observed tu be misaligned. The control room team entered AOP 3552 and has decided that Attachment A to that procedure is to be used to recover from the misaligned rod. Initiating Cues: The US has directed you to complete Attachment A of AOP 3552 through step 7.e. 2
~
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: _A52_ JPM Number: 130 Task
Title:
CONTROL ROD OUT OF ALIGNMENT I Denote Critical Steps with an *X*
' NOTE
- Critical Steps must be completed correctly te achieve a satisfactory grade i
Start Time: STEP 1 Performance Step: Verify operational mode MODE 1 GRADE Standards: Based on current power level, verifies
~
that the plant is in mode 1 STEP 2 Performance Step: Identify affected rod (s) as follows:
- DRPl display
. Rod supervision on plant process computer GRADE Standards: Checks the DRPI display and cotis up the rod supervision display (NSSS, page forward, F6, F2) and identifies rod D4 as the only affected rod.
STEP 3 Performance Step: Verify ROD CONTROL URGENT FAILURE (MB4C 4 8) annunciator - NOT LIT GRADE Standards: Checks Main Board annunciator MB4C 4-8 as not lit. 3
a
- PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: A52
. - JPM Number: 130 i- _ Task
Title:
CONTROL ROD OUT OF ALIGNMENT I _
. . Denote Critical Steps with an "X"
- ' NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade d
[ STEP 4 -Performance Step:- Request l&C verify affected rod lift coil j
. fuse - NOT BLOWN i
1- -GRADE :Standarde: Elther contacts I&C directly or-
- requests that the US contact l&C to i verify the status of the rod lift coil fuse.
! [Cuei!~ * $5 l [Rolsilaylaseithe!11&Clofthe USTand i -- L
" ~
l"
- finform the ~ examinee that the lift coil?
~ < ? fuse'was blown but 6as been' replaced ;
heu ,. L lbyll&Ch a g _ % y .i [l STEP 5 _ Performance Step: Verify all shutdown rods greater than or equal to insertion limit using TRM, OPS Form 3273-3/4.3,1,3,5,
- SHUTDOWN ROD INSERTION LIMIT a
TGRADE Standards: Refers to the appropriate form in the Technical Requirements Manual and verifies that the shutdown rods are greater than the listed insertion limit. Comment: If the examinee is a RO license holder, he may request that the US l check the limit in the TRM. If this i occurs, role play as the SCO and
, provide the following Cue:
[Cus:N-i, b e- $Thesindacsni6diaisgreatsf thent [~ c . - ithe insertioril_imits .in the TRMt 4 i
1
-PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: A52 JPM Number: 130 Task
Title:
CONTROL ROD OUT OF ALIGNMENT Denote Critical Steps with an "X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade STEP 6 Performance Step: Verify at least one rod misaligned by more than i 12 steps from its group step counter.
GRADE ~ ' " - ' ~ Standards: Checks DRPI and/or the plant process computer rod supervision display and verifies that rod D4 is out of alignment by more than 12 steps. STEP 7 Forformance Step: Verify only one rod misaligned by more than i 12 steps from its group step counter. GRADE Standards: Either based on checks in the previous step or by checking DRPI and/or the plant process computer rod supervision display, verifies that only one rod, D4, is misaligned by more than 12 steps. [" Cue:I' fAfth'e'c6mpisti6n~6f thiidspinform
~ [the' examinee tisat the US will sheck -
'the Technical Specifica;tioni_
. n_' jl requirements and notify Reactors
} Engineering [ Additionally l hand thef texaminee the(completed Shutdown 1 5 Margin' calculation land info'rm hini that
. Lit was completed bylanother operator -
fon shift / 5
I . PERFORMANCE INFORMATION l . 1 Facility: - Mibtone Unit 3 System: .A52. '
- JPM Number: 130 Task
Title:
CONTROL ROD OUT OF AllGNMENT 5
- Denote Critical Steps with an "X"
' NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade Comments: The examinee may ask if the adequacy of the shutdown margin had been checked. Provide the following Cue: .
[CueF iThe shiitdown~ margin value neieds to e m_ ,, ; be' verified to be adequate.- , STEP 8 Performance Step: Verify SHUTDOWN MARGIN - ADEQUATE GRADE Standards: Checks the shutdown margin calculation and determines that adequate shutdown margin exists. STEP 9 Performance Step: Verify reactor power - GREATER THAN 50%.
= GRADE Standards: Checks the power range meters on MB4 and determines that reactor power is greater than 50E
[cueiR iAfthe~c6hbluilsn"6f thisstepinfoFm
- the' examinee t*.at the QPTR has beent F .
checked ahdhrified to bs less than::
~
~
11.02iAls6 inform him that AFD'isi 2Within thsLlimits specified in thel g
. [Tschnical_ Requirements Manual 2
, i Additionally l Inform' the. examinee that ?
E Jthe rod has besh rnisaligned for25: a I minutes 'and he should proceed to the? y riote prioho 'stsp 5 and eontinue'with"
. , ithefecoVeryLactions] .
6
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: A52 JPM Number: 130 Task
Title:
CONTROL ROD OUT OF ALIGNMENI Denote Critical Steps with an "X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade STEP- 10 Performance Step: Verify fuse check of affected rod -
COMPLETE. GRADE Standards: No action required since this information was previously provided. [Cuei L if_the examirise'qu'estions the status ; of the'. fuse' checks. again inform him;
. that the lift coil fuse for rod D4 has; been replaced by l&C STEP 11 X Performance Step: Record affected group step counter position.
GRADE X Standards: Notes the position of the control bank D group 1 step counter and records that number on a piece of paper / log. STEP 12 X Performance Step: Align control rod disconnect uwitches: Unlock and Open control roci disconnect switch box (BOX 3RDS-HDSBOX1, CAT 60, Key #18 in CO key locker) GRADE X Standards: The rod control disconnect switch box is unlocked. Opens the switch box.
^
Cue:; 'If tns exsmines'hsidfor the key to the box inform h'im thst the box is already unlocked! 7
PERFORMANCE INFORMATION Facility: Millstone Unit 3 - System: .A52
- JPM Number
- 130 Task
Title:
CONTROL ROD OUT OF AllGNMENT Denote Critical Steps with an "X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade STEP 13 X Performance Step: Place each rod disconnect switch for
~
the affected bank, except the misaligned tod, to the ROD DISCONNECTED position. GRADE X Standards: Positions all of the disconnect switches for the control bank D rods with the exception of rod D4 "up" to the ROD DISCONNECT position. STEP 14 X Performance Step: Place control bank SEL switch to affected uank position. GRADE X Standards: Places the control bank SEL switch to the CBD position. STEP 15 Performance Step: Check misaligned rod higher than associated bank using DRPI display. GRADE Standards: Checks the DRPl display and verifies that rod D4 is higher than the remaining rods in control bank D. 8
PERFORMANCE INFORMATION Facility: M:llstone Unit 3 System: . A52 JPM Number: 130 Task
Title:
CONTROL ROD OUT OF ALIGNMENT Denote Critical Steps with an "X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade STEP 16- X Performance Step: Insert misaligned rod until nextJower position DRPI LED just changes state.
l GRADE X Standards: Takes the In-Hold-Out switch to the i ' "in" position until the next lower position LED for rod D4 comes on and then releases the switch, t l Comment: This action will cause main board annunciator MB4C 4-8 to alarm. The examinee should silence and acknowledge the alarm. This is not required to satisfy the critical nature of the step. STEP 17 X Performance Step: Reset affected group step counter to a value of 2 steps higher than affected rod's indicated DRPI position. GRADE X Standurds: Resets the control bank D group 1 step counter to a position that corresponds to 2 steps higher than the DRPIindication for rod D4. 9
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: _A52_ JPM Number: 130 Task
Title:
CONTROL ROD OUT OF ALIGNMENT - ' Denote Critical Steps with an "X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade STEP 18 Performance Step: Proceed to step 6.g, Verify rod misaligned - LESS THAN 16 hours.
GRADE Standards: Based on information provided, the rod has been misaligned less than 16 hours. [Cuei~ . ilf_ ths exaniinee'as(s how long'the rod i has bearimisaligneditell him less than 1 hou_re Comment: Prior to moving the rod, it is expected that the examinee will notify the US. However, this is not required to complete the critical nature of the JPM. STEP 19 X Performance Step: Move misaligned rod until affected group step counter indicates value recorded in step 5.b. GRADE X Standards: Takes the In-Hold-Out switch to the "in" position until the control bank D group 1 step counter is at the number that was previously recorded and than , releases the switch. STEP 20 X Performance Step: Place all lift coil disconnect switches for affected bank to ROD CONNECTED position. GRADE X Standards: At the rod control disconnect switen 10
.- . - ~ _ _ = _ _. .- .- . -- _ _---- -- -. _ .. ..
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: . A52 JPM Number: 130 Task
Title:
CONTROL ROD OUT OF ALIGNMENT Denote Critical Steps with an *X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade box positions the switches fer the control bank D rods "down" to *he Rod Connected position.
d STEP 21 X Performance Step: Verify ROD CONTROL URGENT FAILURE (MB4C 4-8) annunciator - LIT
- GRADE X Standards: Observes that annunciator MB4C 4-8 is lit.
, STEP 22 X Performance Step: Press ROD DRIVE RESET GRADE X Standards: Presses the ROD DRIVE RESET pushbutton on MB4. Comments: This action will cause annunciator MB4C 4-8 to clear. The examinee should reset this alarm. This is not required to complete the critical nature of the step. STEP 23 Performance Step: Verify ROD CONTROL URGENT FAILURE (MB4C 4-8) annunciator - NOT LIT. GRADE Standards: Checks that annunciator MB4C 4-8 is not lit. 11
PERFORMANCE INFORMATION Facility: Millstone Unit 3 ' System: .A52 JPM Number; 130 Task
Title:
CONTROL ROD OUT OF AllGNMENT Denote Critical Steps with an T
- NOTE Critical Steps must be completed correctly to achieve a satisfactory grade 4 STEP 24 X Performance Step: Place control bank SEL +, witch in Man GRADE X Standards: Rotates the control bank SEL switch j to the MAN position.
! STEP ~25 Performance Step: Notify the US that the misaligned rod has been realigned with the rest of the rods in control bank D. 1 GRADE Standards: Informs the US that he has completed the step in Attachment A of AOP 3552 through step 7.e and rod D4 has been realigned with the rest of the rods in control bank D4. Terminating Cue: The evaluation for this JPM is concluded. Stop Time: I 12
VERIFICATION OF COMPLETION ! Job Performance Measure Number: 130 Revision: 0 < l Date Performed: l Examinee: Evaluator: i Validated Time (min): Actual time to Complete (min): j Result of JPM: (Denote by an S for satisfactory or a U for
- unsatisfactory)
- Result of oral questions: Number of Questions:
Number of Correct Responses: Score % r 1 13
..y &, yr..
. . . _ _ - _ . . . . - -. - - . - - - . - - . - . , _ - - . . . . - - . ~ . - . . - . - . _ - .
EXAMINEE HANDOUT INITIAL CONDITIONS AND INITIATING CUES I JPM Tracking Number: 130 Initial Conditions: A problem in the EHC circuit caused a momentary runback of the turbinelgenerator. During the subsequent insertion of the reactor control rods, rod D4 in Control Bank D was observed to be misaligned. The control room team entered AOP 3552 and has decided that 4 Attachment A to that procedure is to be used to recover from the misaligned rod. Initiating Cues: The US has directed you to complete Attachment A of AOP 3552 through step 7.e. 14
0)2IG JOB PERFORMANCE MEASURE WORKSHEET ,
- 1. JPM
Title:
RESTORE ESSENTIAL LOADS AND ALIGN CHARGING WHILE
- EEBFORMING RECOVERY WITH THE SBO DIESEL
$ ID Number: JPM 109 Revision: 1
- 11. Initiated:
i R. L Luenebur9 2/7/97 4 Developer Date 4 111. Reviewed: 1 Technical Reviewer Date i Instructional Reviewer Date 4 s IV. Approved: Operations Manager Date Nuclear Training Supervisor Date
- 1-
JOB PERFORMANCE MEASURE WORKSHEET Facility: Millstone Unit 3 Examinee: JPf/ Tracking Number: 102 Validation Time: minutes Task T;tle: RESTORE ESSENTIAL LOADS AND AllGN CHARGING WHILE PERFORMING RECOVERY WITH THE SBO DIESEL Time Critical Task: ( )YES ( X ) NO Task Number: 000*027*05*01 and_0A0*078*05*02 K/A Number: 062-000-A2.11 K/A Rating: 3.7 / 4.1 Acolicable Methods of Testing: Simulate Performance Actual Performance X Classroom Simulator X Plant Task Standards: Satisfactorily start a charging pump in the injection mode using ECA-0.2. - Reauired Materials: None. General
References:
ECA-0.3 Rev 4 and ECA-0.2 Rev. 8 READ TO THE EXAM! NEE I will explain the initial conditions, which step (s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objectives for this JPM will be satisfied. You may use any approved reference materials normally available in the Control Room, including logs. Make all written reports, oral reports and log entries as if the evolution was 4 actually being performed. 4 Initial Conditions: A totalloss of all AC power has occurred which resulted in a plant trip and ultimately an SI. The only available power source is the SBO diesel which is running and providing power to emergency bus 34C. The Control Room Team has just made the transition to ECA-0.3. The BOP-has just verified that SG pressures are stable. The Si and LOP actuation signals have been reset.
' Initiating Cues: The US has directed you to perform steps 2 through 5 of ECA-0.3.
2
. . _ _ - . .- .- - .. ~- - - ..
JOB PERFORMANCE MEASURE WORKSHEET SIMULATOR REQUIREMENTS: 1. Reset to IC-20. Press " Audible Alarms Disable".
- 2. Place the simulator in "RUN". Insert the following malfunctions:
ED01 Loss of Off-Site Power EG06A Diesel Generator A Falls to Start EG060B Diesel Generator B Fails to Start i Allow the simulator to run until the low pressuie Sl occurs (approximately 10 minutes).
- 3. While waiting for the Si to actuate perform the following:
Under " Instructor Directeo Actions" select i
- EGR08 to " START"(SBO Diesel Cortrol).
At MBS "OPEN" the "A" Train SBO tie breaker (34A1-2). Using ECA-0.0, Step 6 place the indicated control switches in the " PULL-TO-LOCK" positions. Open the NSST feeder breaker (NSSA 34A 2), Under " Instructor Directed Actions" select EDR32 to "CLOSE"(Close SBO Output Breaker). For the "A" electrical train perform the applicable actions of ECA-0.0 Steps 7 e and 7f. ! 4. After the Si occurs, wait the required 60 seconds
- ' and reset the SI. Then perform the actions of ECA-O.0 Steps 7h through 7n.
- 5. Position the following valves as indicated:
LCV*112D CLOSE LCV'112B OPEN MV*8801A CLOSE MV*8105 OPEN MV*8511 A CLOSE MV*8512A CLOSE
- 6. Acknowledge all alarms, reset " Audible Alarms Disable", and place the simulator in " FREEZE".
3
- - . . . . . . . . . . - . . - - . - - . . - . . . - . - . . - . ... . - =-. - . - -
~ JOB PERFORMANCE MEASURE WORKSHEET ; l -
. 7. After the examinee has received the initial conditions and initiating cues, place the simulator in t
. RUN", , 4 Approximate Simulator setup time is 20 minutes E a I i 4
'h y-.
4 1 +
)
A t' f 4
PERFORMANCE INFORMATION Facility: Millstone Unit 3 - System: A03 JPM Number: 102 Task
Title:
RESTORE ESSENTIAL LOADS AND ALIGN CHARGING WHILE l PERFORMING RECOVERY WITH THE SBO DIESEL L Denote Critical Steps with an "X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade Statt Time:
STEP 1 X Performance Step: Check RCP Sealisolation status. Verify all four RCP seal supply isolation valves - CLOSED 3CHS*MV8109A 3CHS*MV8109B 3CHS*MV8109C 3CHS*MV8109D GRADE Standards: Observes that MV8109A and MV8109C indicate open and MV81098 and MV8109D have no indications. Shifts to the RI4O column and performs the applicable actions for a charging pump not running. GRADE X Standards: Depresses the "CLOSE" pushbutton for 3CHS*MV8109A and observes the indicating lights shift to green "ON", red "OFF", GRADE X Standards: Depresses the "CLOSE" pushbutton for 3CHS*MV8109C and observes the indicating lights shift to green "ON", red "OFF". GRADE X Standards: Either directly contacts a PEO or requests that the US contact one to locally close 3CHS*MV8109B and 3CHS*MV8109D. 5 _--_______1
PERFORMANCE INFORMATION Facility: Millstone Unit 3 - System: A03 JPM Number: 1Q2 Task
Title:
RESTORE ESSENTIAL LOADS AND ALIGN CHARGING WHILE PErdORMING RECOVERY WITH THE SBO DIESEL Denote Critical Steps with an *X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade f Che: - l Under
- Remote Functions" set CVR43
~ and CVR45 to 0,00 to simulate locally .
t ' t closing the valvesJAs the PEO,<
< inform the examinee that MV81098 ' .
, _ Land MV8_109D are closed.
STEP 2 X Performance Step: Verify RPCCW Ctmt return outer isolation valves (3CCP*MOV49A and 3CCP*MOV498)- CLOSED GRADE Standards: Obseives that 3CCP*MOV49A indicates open and that 3CCP*MOV49B has no indication. GRADE X Standards: Depresses the "CLOSE" pushbutton for 3CCP*MOV49A and observes the indicating lights shift to green "ON", red "OFF". GRADE X Standards: Either directly contacts a PEO or requests that the US contact one to locally close 3CCP*MOV498. ICue:j " iln 1/O'oyerride?cc"if (,..
"3CCP!MOV49B", "slose" select *on"!
?When the I/O is active, inform thei examinee that 3CCP*MOV498 is'
; closed; 6
N PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: AQ3-1 JPM Number: 109 Task
Title:
RESTORE ESSENTIAL LOADS AND' ALIGN CHARGING WHILE PERFORMING RECOVERY WITH THE SBO DIESEL. Denote Critical Steps with an T
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade
~ STEP 3 X Performance Step: RESET ESF Actuation Signals If Required 4
. Si e CDA e CIA i
. - ClB
. LOP l
GRADE X Standards: The Sl and LOP signals Save been reset (part of the initial conditions). The only signal required to be . reset is CIA. Depresses the two CIA reset pushbuttons on MB2 and observes that annunciator MB2B 5-8 clears indicating that CIA has been reset. Comment: If the examinee forgot the initial conditions or failed to realize that the applicable annunciators indicating actuation of these signals are now cleared, he may reset LOP and Si again. 7
l PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: A0.3 JPM Number: 102 Task
Title:
RESTORE ESSENTIAL LOADS AND ALIGN CHARGING WHILE PERFORMING RECOVERY WITH THE SBO DIESEL Denote Critical Steps with an "X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade STEP 4 X Performance Step: Place The Following Equipment in -
Service On The Energized AC Emergency Bus. Place RPCCW system in service. Locally Open the following valves to cross-connect RPCCW non-safety headers at CDS chiller 18: (Service Bldg. El. 61"-3") 3CCP-V186 3CCP-V167 3CCP-V187 3CCP-V177 GRADE X Standards: Either directly contacts a PEO or requests that the US contact one to locally open 3CCP-V186, V-167, V187, and V177. ICue:; 3 Use Rern6te Functions 1"CCR08" ahd:
- t. _
1"CCR09" to "OPEN" the velves?When: J i the' valves indicate open'. uparm the Jexaminee that 3CCP-V186, V167,5 V187.and V177 are.open. s 8 l
M PERFORMANCE INFORMATION
- Facility: Millstone Unit 3 ' System: A02 JPM Number: 109 Task
Title:
RESTORE ESSENTIAL LOADS AND ALIGN CHARGING WHILE EEBFORMING RECOVERY WITH THE SBO DIESEL Denote Critical Steps with an "X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade STEP 5 Performance Step: Verify total SBO dieselload (SBO D/G control panel)- LESS THAN OR EQUAL TO 1000 Kw GRADE Standards: Either directly ontacts the PEO at the .
SBO Diesel or has the US make the contact to request the dieselload. Cue: Report back as the PEO that the SBO dieselload is 200 Kw. STEP 6 X Performance Step: Start one RPCCW pump GRADE X Standards: Takes the control switch for the "A" RPCCW out of" pull-to lock" and rotake the switch to the "sta1" position. Observes that starting amperage is indicated and that th:a changes to running amperage. Also, the indicating lights shift to green OFF, red ON. STEP 7 X Performance Step: Establish instrument air to ctmt. Perform the following: START one shutdown instrument air compressor, GRADE- X Standards: Takes the control switch for the "A" shutdown instrument air compressor out of " pull-to-lock" and totates the switch to the " START" position. Observes that the indicating lights shift to green OFF, red ON. 9
PERFORMANCE INFORMATION Facility: Millstone Unit 3 . System: - AQ3 JPM Number:- 102 Task
Title:
RESTORE ESSENTIAL LOADS AND ALIGN CHARGING WHILE FEREPRMING RECOVERY WITH THE SBO DIESEL-Denote Critical Steps with an "X"
- NOTE' Crihl Steps must be completed correctly to achieve a satisfactory grade STEP 8 X Performance Step: OPEN shutdown instrument air supply.
(3lAS-AOV95) GRADE X Standards: Depresses the *OPEN" pushbutton for
' 3lAS-AOV95, observes the indicating lights shift to green OFF, red ON, and releases the pushbutton.
-1 Comment: The examinee may also ensure that !
- indications of instrument air header -
pressure are indicated on IAS-Pl73A. > STEP 9' X Performance Stap: Open the non-safety header supply. and return isolation valves for the running RPCCW pump. Train A: 3CCP*AOV10N19A
. 3CCP*AOV197N194A ' '
-GRADE X Standards: Depresses the "OPEN/A'UTO" pushbutton for 3CCP*AOV10N19A and observes the indicating lights chift -
to green OFF, red ON. GRADEI X - Standards: - Depresses the "OPEN/ AUTO" pushbutton for 3CCP*AOV197N194A and observes the indicating lights shift 4 to green OFF, red ON. , 10
- PERFORMANCE INFORMATION -
Facility: - Millstone Unit 3' " System: AQ3 JPM Number:- 109-Task
Title:
. RESTORE ESSENTIAL LOADS AND ALIGN CHARGING WHILE - PERFORMING RECOVERY WITH THE SBO DIESEL l Denote Critical Steps with an "X"
- NOTE' Critical Steps must be completed correctly to achieve a satisfactory grade STEP 10 X Performance Step: OPEN instrument air Ctmt isolation valves.
GRADE Standards: Observes that MOV72 does not have power, Since the valve was open prior to the Loss of Power, it is failed in the open position. Cue: If the examinee requests guidance concerning the position of MOV72, provide the cue that the valve is failed open. Comment: Prior to opening PV15, sufficient air header pressure will need to be present for the valve to move. GRADE X Standards: Depresses the "OPEN" pushbutton for . PV15 and observes the indicating lights shift to green OFF, red ON. STEP 11 Performance Step: Place service water system in service: Verify total SBO dieselload (SBO D/G control panel)- LES.S THAN OR EQUAL TO 1450 Kw. GRADE- . Standards: Either directly contacts the PEO at the SBO diesel or requests that the US contact him to request current SBO load. 11
PERFORMANCE INFORMATION Facility: Millstone Unit 3 - System: AQ3 JPM Number: 109 Task
Title:
RESTORE ESSENTIAL LOADS AND AllGN CHARGING WHILE PERFORMING RECOVERY WITH THE SBO DIESEL Denote Critical Steps with an "X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade Cue: Role play as either the PEO or US and inform the examinee that the current load on the SBO dieselis
- 1000 Kw.
STEP 12 X Performance Step: START one service water pump. GRADE X Standards: For the service water pump not in
" Pull-to-Lock" on the "A" train, rotates the control switch to the START position and observes that amperage is indicated and the indicating ligMs shift to green OFF, red ON.
STEP 13 Performance Step: Check service water pump discharge valve - OPEN FOR RUNNING PUMP. GRADE Standarc3: For the running pump observes that the indicating lights for the applicable discharge valve (3SWP*MOV102A or 102C) the indicating lights are green OFF, red ON. STEP 14 Performance Step: Check TPCCW heat exchanger SW supply isolation valves (3SWP*MOV71 A and 3SWP*MOV718)- CLOSED. GRADE Standards: Observes that the indicating lights for 3SWP*MOV71 A are green ON, red OFF. The valve is closed. 12
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: eaa
- JPM Number: 109 Task
Title:
RESTORE ESSENTIAL LOADS AND ALIGN CHARGING WHILE PERFORMING RECOVERY WITH THE SBO DIESEL Denote Critical Steps with an T
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade GRADE Standards: Observes that 3SWP*MOV71B has no power. Since the valve was open when power was lost, it is failed open.
Requests that the US send a PEO to locally close 3SWP*MOV718. Cue: Role play as the US and inform the examinee that a PEO has been sent ~ to locally close 3SWP'MOV71B and that the examinee should consider this a step in progress and proceed with the procedure. STEP 15 Performance Step: Place charging sytem in service: Verify RCS makeup system is available for service: Verify VCT to charging isolation valves
-OPEN GRADE Standards: Observes that the indicating lights for 3CHS*LCV112B ,VCT to charging isolation valve, is green OFF, red ON.
The valve is open. 3CHS*LCV112C has no lights lit. No power for indication. The valve was open prior to the power loss and is therefore still open. Comment: If the examinee questions the position of 3CHS*LCV112C or appears confused, provide the following cue: l 13
- PERFORMANCE INFORMATION Facility
- Mi!! stone Unit 3 System: e&3 JPM Number: 102 i Task
Title:
RESTOPE ESSENTIAL LOADS AND ALIGN CHARGING WHILE PERFORMING RECOVERY WITH THE SBO DIESEL l Denote Critical Steps with an X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade CW' ^~ ^
~f3CHS*LCV112C was olien pilor to l
, diosing power. Jhe valve is still openb STEP 16 Performance Step: Verify primary grade water pumps -
POWER AVAILABLE GRADE Standards: Observes that power is NOT available to the primary grade water pumps. These pumps are powered off the non vital busses and all of the load centers were stripped prior to placing the SBO diesel on bus 34A. Shifts to the RNO column. Comment: Valve 3CHS*LCV112E has no power and cannot be opened from MB3, if the examinee requests that the valve be opened locally, acknowledge his request and provide the following cue:
~
iCueE ~ iThiiiiminlmdrisafety; function is~ met isith LCV1120 beli h . m
' , Swith.the procedure &, (opened, proceed STEP 17 X Performance Step:- lE RCS makeup is MQI available,
,THEN Align charging pump suction to RWST:
OPEN the RWST to charging isolation valves. 14
PERFORMANCE INFORMATION J l- Facility: Millstone Unit 3 System: AQ3 JPM Number: .109 Task
Title:
RESTORE ESSENTIAL LOADS AND AllGN CHARGING WHILE PERFORMING RECOVERY WITH THE SBO DIESEL Denote Critical Steps with an "X"
- NOTE
- Critical Steps must be completed correctly to achieve a ^atisfactory grade GRADE X Standards: Depresses the "OPEN" pushbutton for 3CHS*LCV112D and observes the indicating lights shift to green OFF, red ON.
GRADE X Standarde; There are no light indications for 3CHS*LCV112E. The valve does not have power. Requests that the US send an PEO to locally open the valve. Comment: Valve 3CHS*LCV112C has no power and cannot be closed from MB3. If the examinee requests that the valve be closed locally, acknowledge his request and provide the following cue:
!Cuef >
?Ths'minirnurn safeti function is met c issth LCV112'8 being' closed, proceed:
px. a , iwith the procedure , ,, , STEP 18 X Performance Step: CLOSE the VCT to charging iso,ation valves. GRAD 3 X Standards: Depresses the "CLOSE" pushbutton for 3CHS*LCV112B and observes that the indicating lights shift to green "ON", red "OFF". . GRADE Standards:- Valve 3CHS*LCV112C has no power. Requests that the US send an PEO to locally close then valve. 15 I
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: A03 JPM Number: 102 -
~
Task
Title:
RESTORE ESSENTIAL LOADS AND ALIGN CHARGING WHILE PERFORMING RECOVERY WITH THE SBO DIESEL Denote Critical Steps with an "X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade iCuei l Ttie; minimum safety l function is met' with LCV112B being closed; proceed -
;with the procedureR
- Comment: Valve 3CHS*MV8106 has no power and cannot be closed from MB3, if the examinee requests that the valve be closed locally, acknowledge his request and provide the following cue:
STEP 19 Performance Step: Verify charging header isolation valves (3CHS*MV8105 and 3CHS*MV8106) - CLOSED. GRADE Standards: Observes that the indicating lights for 3CHS*MV8105 art green "OFF", red "ON", the valve is open. Valve 3CHS*MV8106 has no indicating lights lit. The valve has no power but was last open before power was lost. Shifts to the RNO column: CLOSE valves GRADE Standards: Depresses the "CLOSE" pushbutton for 3CHS*MV8105 and observes the indicating lights shift to green SN, red OFF. GRADE Standards: Requests that the US send an PEO to
; locally close 3CHS*MV8106.
16
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: A03 JPM Number: .102 ' Task
Title:
BESTORE ESSENTIAL LOADS AND AllGN CHARGING WHILE PERFORMING RECOVERY WITH THE SBO DIESEL Denote Critical Steps with an "X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade Comment: Valves 3CHS*MV8111A,B and C do not have power. If the examinee questions their position, provide the following cue:
~
[ Cue:1 [The)alves were open before" power-
;was lost and therefore are still_open.
STEP 20 Performance Step: Verify charging pump recirculation
~
isolation valves - OPEN 3CHS*MV8111 A 3CHS*MV81118 3CHS*MV8111C 3CHS*MV8110 GRADE Standards: Observes that the indicating lights for 3CHS*MV8110 are green "OFF", red "ON", the valve is open. GRADE Standards: Observes that valves 3CHS*MV8111A, B and C have no indication. The valves do not have power. The valves were open prior to the loss of power and are, therefore, still open. 17
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: M3 JPM Number: .109 Task
Title:
RESTORE ESSENTIAL LOADS AND ALIGN CHARGING WHILE , PERFORMING RECOVERY WITH THE SBO DIESEL l Denote Critical Steps with an *X*
' NOTE
- Critical G!eps must be completed correctly to achieve a satisfactory grade STEP 01 Performance Step: Verify total SBO dieselload (SBO D/G control panel) LESS THAN OR EQUAL TO 1450Kw 1
GRADE Standards: Either directly contacts the PEO at the SBO or requests that the US contact the PEO to determine the current SBO dieselloading. Cue: Role play as the PEO or the US and provide the cue that the current SBO dieselload is 1400 Kw STEP 22 X Performance Step: START one charging pump. GRADE X Standards: Rotates the control switch for the *A" charging pump to the
- START" position and observes that the indicating lights shift to green OFF, red ON and amperage is indicated on the ammeter.
STEP 23 X Performance Step: Esatablish Charging Flow. Close charging line flow control valve, GRADE X Standards: Depresses the down arrow (7) pushbutton on the 3CHS*FCV121 controller and observes that the
- MAN" light comes on, the controller output decreases and eventually the down arrow pushbutton back lights green indicating the valve is closed.
! 18
l PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: AQ3 : I JPM Number: 109 Task
Title:
RESTORE ESSENTIAL LOADS AND ALIGN CHARGING WHILE PERFORMING RECOVERY WITH THBfGSO DIESEL Denote Critical Steps with an *X"
' NOTE
- Cr!tical Steps must be completed correctly to achieve a satisfactory grade Comment: In the next JPM step, valve 3CHS*MV8106 has no power, The valve was open prior to losing power.
If the examinee questions the status of the valve, provide the following cue:
! Cue:: ' 3CHS*MV8106 was open prior to the
; n 11oss.of power and in still open, ,
STEP 24 X Performance Step: Open charging header isolation valves (3CHS*MV8105 and 3CHS*MV8106) , GRADE X Stanwards: Depresscs the "OPEN" pushbutton for MV8105 and observes the indicating lights shift to green "OFF, red "ON". GRADE Standards: Observes that 3CHS*MV8106 has no power, The valve was open prior to the power loss and is, therefore, still open. STEP 25 Performance Step: Throttle Open charging line flow control valve to maintain PZR level. GRADE ' Standards: Depresses the up arrow (A) pushbutton on the 3CHS*FCV121 controller and observes that charging flow is indicated. Throttles flow as necessary to maintain pressurizer level. 4 19
l PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: AQ3 JPM Number: 102 Task
Title:
RESTORE ESSENTIAL LOADS AND AllGN CHARGING WHILE PERFORMING RECOVERY WITH THE SBO DIESEL Denote Critical Steps with an *X*
' NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade Cue: After the examinee manipulates the 3CHS*FCV121 controller and it is clear that he is monitoring pressurizer l
l level provide the terminating cue,. Terminating Cue: The evaluation for this JPM is concluded. Stop Time: _ l 1 1 {'. I I l 20 l l
VERIFICATION OF COMPLETION Job Performance Measure Number: 102 Revision: 1-Date Performed: l Examinee: i Evaluator: l Validated Time (min): Actual time to Complete (min): ;
- Result of JPM: (Denote by an S for satisfactory or a U for unsatisfactory)
Result of oral questions: Number of Questions: Number of Correct Responses: i Score % 1 21 l-
~ - . . . . - _ -- --_ _ _ _.__ _ ,_ ._. -
EXAMINEE HANDOUT INITIAL CONDITIONS AND INITIATING CUES JPM Tracking Number: 101 initlai Conditions: A totalloss of all AC power has occurred which resulted in a plant trip and ultimately an Sl. The only available power source is the SBO diesel which is running and providing power to emergency bus 340. The Control Room Team has just made the transition to ECA4.3. The BOP has just verified that SG pressures are stable. The Si and LOP actuation signals have been reset. Initiating Cues: The US has directed you to perform steps 2 through 5 of ECA 0.3. 22
JOB PERFORMANCE MEASURE WORKSHEET bb l
- l. JPM
Title:
Locally Restore AFW Flow (Motor Driven Pumos and Valves) ID Number: JPM 019 Revision: 4 ll. Initiated: A. Oxfurth 3/1/97 Developer Date Ill. Reviewed: M ' 3 to- M Techn :al Re)lewer Date 1 3 In ructt6fi Date
}
IV. Approved: Sk Whperstrons Manager - f 12, ' {
' 97 date k /r m 3 k) i7 Nuclear Training Supervisor Date 1
_ .__ _. _. . _ . _ _ _ _ _ _ _ _ _ _ _ . _ _ . _ . _ _ _ _ _ . ~ . _ . Facility: JOB PERFORMANCE MEASURE WORKSHEE' Millstone Unit 3 Examinee: [ i JPM Tracking Number: ._19_. Validation Time: 10_ minutes Task
Title:
Locally Restore AFW Flow (Motor Driven Pumos and Valves) i Time Critical Task: ( )YES ( X )NO Task Number: 000'039'05*01 and 000'090'05'02 K/A Number: 000-054 EA 1.01 K/A Rating: 4.5 / 4.4 Applicable Methods of Testing: i
- Simulate Performance X Actual Performance Classroom Simulator Plant X Task Standards: Satisfactorily complete the local checks to restore AFW flow using Attachment A of FR H.1, Reauired Materials: Locked Valve Key. OP 3260B Attachmerit 3 General
References:
EOP 35 FR H.1, Rev.10 4 READ TO THE EXAMINEE I will explain the initial conditions, which step (s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objectives for this JPM will be satisfied. You may use any approved reference materials normally available in the Control Room, including logs. Make all written reports, oral reports and log entries as if the evolution was 4 actually being perfonned. Initial Conditions: A Loss of Secondary Heat Sink event is in progress and the control room team is carrying out the actions of EOP 35 FR H,1 AFW flow could not be established from the control room, ^ initiatina Cues: The US directs you to locally restore the AFW flow using the A and B MDAFW pumps IAW page 1 of 4 to Attachment A to EOP 35 FR-H.1. You are also to verify the position of any TDAFWvalves on page 1. A second PEO is checking the lineup for the TDAFW pump. 2
PERFORMANCE INFORMATION l Facility: lAillstone Unit 3 System: AFW - ! 1 JPM Number: 019 Task
Title:
Locally Restore AFW Flow (Motor Driven Pumos and Valves) Denote Critical Steps with an *X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grado Start Time: _
Comment: The steps in this JPM may be done in any order Comment: Location for JPM steps 1-3 is DWST enclosure 24' Comment: This JPM makes the assumption that the examinee knows how to verify the position of a locked valvo. If at any time it appears that the examinee is uncertain how to verify the position ask him where he would go for guidance. His response should be either to contact the US or obtain a copy of OP3260B, Equipment Control. Provide the examinee with Attachment 3 from OP3260B. However, for the purpose of the evaluation of this JPM, it is acceptable for the examinee to immediately start and indicate that the locking devices would be removed to verify the valve positions, i Cue: 'If the examinee asks the status of the slack in the locking device for any - t valve in the JPM give the'following Cue: The locking device is installed with insufficient slack to check valve position. 3
PERFORMANCE INFORMATION l Facility: Millstone Unit 3 System: _AFW JPM Number: 019 Task
Title:
Locally Restore AFW Flow (Motor Driven Pumos and Valves) Denote Critical Steps with an T
' NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade STEP 1 Performance Step: Check A MD AFW Supply Header Isolation valve,3FWA*V997, OPEN GRADE Standards: Unlocks the locking device on valve 3FWA*V997 and removes the locking device.
t Cue: The lock is unlocked _ and the locking . device is removed. GRADE Standards: Rotates the handwheelin the counterclockwise direction until the valve is fully open.
; Cue: Valve handwheel rotates in ths counterclockwise direction and then comes to a_hard stop..
GRADE Standards: Rotates the handwheel 1/4 turn in the clockwise direction. ICue:1 The valve han'dwheel has been l rotated 1/4 turn in the clockwise
! . ' direction.
GRADE Standards: Installs the locking device and locks the lock. f Cus:{ Th'e Iocking" device'is Installed'and L ;_ , locked, 4
[ l PERFORMANCE INFORMATION ! Facility: Millstone Unit 3 System: AFW ' JPM Number: 019 Task
Title:
Locally Restore AFW Flow (Motor Driven Pumos and Valves) Denote Critical Steps with an *X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade STEP 2 Performance Step: Check *B" MD AFW Supply Header Isolation valve, 3FWA*V998. OPEN.
GRADE Standards: Unlocks the locking device on valve 3FWA*V998 and removes the locking device. Cue: The lock is unlocked and the locking device is removed. GRADE ' Standards: Rotates the handwheelin the counterclockwise direction until the valve is fully open.
' Cue:- Valve handwheel rotates in the counterclockwise direction and then comes to a.hard stop. .
GRADE Standards: Rotates the handwneel 1/4 turn in the clockwise direction. l Cue:' The valve handwheel has been rotated 1/4 turn in the clockwise
, _ direction ( , _
GRADE Standards: Installs the locking device and locks the lock,
! Cue;f The 16cking' device is installed and
. -locked l 5
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: _AFW JPM Number: 019 Task
Title:
Locally Restore AFW Flow (Motor Driven Pumos and Valves) Denote Critical Steps with an T
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade Comment: If the examinee questions what to do with the TD AFW valve 3FWA*V999, remind him that the initiating cue directed him to verify the position of this valve 61o.
STEP 3 Performance Step: Check TD AFW Supply Header Isolation valve, 3FWA*V999, OPEN. GRADE- Standards: Unlocks the locking device on valve 3FWA*V999 and removes the locking device.
" Cue: ' The' lock is unlocked and the locking device is removed.
GRADE Standards: Rotates the handwheelin the counterclockwise direction unt.i the valve is fully open.
- Cue:- Valve handwheel rotates in the -
counterclockwise direction and then L comes.toLa hard.' s topi GRADE Standards: Rotates the handwheel 1/4 iurn in the clockwise direction.
- Cue:. 1Theialve hsndsheel his been:
l irotated;1/4 turn in the clockwise-
, - direction.
GRADE Standards: Installs the locking device and locks the lock.
! Cde:1' The locking' device is Iristalled and .
lockedt-6
1 PERFORMANCE INFORMATION
^
Facility: Millstone Unit 3 System: AFW JPM Number: 019 Task
Title:
Locally Restore AFW FlowJMotor Driven Pumos and Valves) Denote Critical Steps with an "X"
' NOTE' Critical Steps must be completed correctly to achieve a satisfactory grade Comment: Location for JPM steps 4 7 is ESP Bldg., A MD AFW Pump Room,24'
; Cue: When the examinee is in a position to observe the stem of valve 3FWA*V2, inform him that the valve stem is down.
Comment: The examinee may question what to do with the out of position valve (may be concerned about a security event). If this is the case, provide him with the cue to continue with the lineup. I STEP 4 X Performance Step: Check "A" MD AFW Pump DWST' Supply Isolation valve, 3FWA*V2, OPEN. GRADE Standards: Unlocks the locking device on valve 3FWA*V2 and removes the locking device.
;Cuef 1The lock'ls unlocked and the locking -
device is removed. GRADE X Standards: Rotates valve handwheelin the counterclockwise direction to OPEN the valve. Cue:' - Valve ha'ndwhest rotates. Eventually some resistance islaet and valve hr.ndwheel comes to a hard stop. The valve stem _is in the; raised position 7
. ~. _ .. _ -_-. -_.- - ._ - _ - _ - _ _ - - . - . - - _
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: _AFW JPM Number: 019 . ! Task
Title:
Locally Restore AFW Flow (Motor Driven Pumps and Valves) l l Denote Critical Steps with an T
- NOTE' Critical Steps must be completed correctly to achieve a satisfactory grade l
l GRADE Standards: Rotates the handwheel 1/4 turn in the l clockwise direction.
' Cueti _ The valve handwheel has been rotated 1/4 turn in the clockwise
, direction.
l GRADE Standards: Installs the locking device and locks i the lock.
' Cuei ' ~ The locking' device is installed and i locked.
Comment: If the examinee had not previously contacted the control room concerning the valve being out of position, he may do so now (acknowledge the report if done) or wait until the end when task completion is reported. l l Cue: :When the examinee'is in a position to observe the stem of valve 3FWA*V4,-
~ inform him that the valve stem is down;,
Comment: The examinee may question what to do with the out of position valve (may be, concerned about a security event). If this is the case, provide him with the cue to continue with the lineup. STEP 5 X Performance Step: Check "A" MD AFW Pump Discharge isolation valve,3FWA'V4, OPEN. i l 8
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: AFW JPM Number: 019
\
Task
Title:
Locally Restore AFW Flow (Motor Driven Pomos and Valves) Denote Critical Steps with an "X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade GRADE X Standards: Unlocks the locking device on valve 3FWA*V4 and removes the locking device.
Cue: ~ The~ lock is unlocked and the locking device is removed. GRADE X Standards: Rotates valve handwheelin the counterclockwise direction to OPEN the valve. Cue:: The valve handwheel rot _ates in the. counterclockwise direction. Eventually .
,some resistance is met and the valve handwheel comes to a hard stop, The valve stem is in the raised position-GRADE X Standards: Rotates the handwheel 1/4 turn in the clockwise direction.
- Cue: . Valve ha' s been' rotated 1/4 turn in the clockwiseLdire.ction.L , :
GRADE X Standards: Installs the locking device and locks the lock.
! Cue:t ; The locking device is' installed and ?
u , l locked. f1 ., Ct. .trent: If the examinee had not previously conte::ted the control room concerning the valve being out of position, he may do so nca (acknowledge the report if done) or wait until the end when task completion is reported. 9
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: AFW JPM Number: 019 Task
Title:
Locally Restore AFW Flow (Motor Driven Pumos and Valves) Denote Critical Steps with an "X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade STEP 6 Performance Step: Check "A" MD AFW Pump to SG D isolation Valve, 3FWA*V10, OPEN.
GRADE Standards: Unlocks the locking device on valve 3FWA*V10 and removes the locking device. Cue:- The lof :s unlocked and the locking devics removed. GRADE Standards: Rotates valve handwheelin the counterclockwise direction to OPEN the valve.-
- Cuei Valve handwheel rotates in the counterclockwise direction and then comes. to a.hard_ stop.;
GRADE Standards: Rotates the handwheel 1/4 turn in the clockwise direction.
- Cue:- Valve h'as been~ rotated 1/4 tum in"the
; clockwise direction ,
GRADE ~ Standsrds: Installs the locking device and locks the lock. lCuei: The;loaking devics is installed and -
- locked.' , .
10
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: _AFW ! JPM Number: 019 Task
Title:
Locallv Restore AFW Flow (Motor Driven Pumos and Valves) Denote Critical Steps with an "X"
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade STEP 7- Performance Step: Check *A" MD AFW Pump to SG A 4
Isolation valve,3FWA'VS, OPEN. GRADE Standards: Unlocks the locking device on valve 3FWA'V5 and removes the locking device. Cuet' The lock is unlocked and the locking j device is removed. I
' GRADE Standards: Rotates valve handwheelin the counterclockwise direction to OPEN ; the valve,
! Cuei' Valve' handwheel rotates in the counterclockwise direction and then i
. _comes to.a hard stop._
2 GRADE Standards: Rotates the handwheel 1/4 turn in the cloc.< wise direction, Cue: 4 Valve"has been rotated 1/4 turn in the Lelockwise_ direction. GRADE Standards: Installs the locking device and locks the lock. lC0ef lThe looking device is installed 'and -
- locked,:
Comment: Location for JPM steps 8-11 is ESF Bldg. 8, MD AFW Pump Room,24' 11
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: _AFW JPM Number: 019 Task
Title:
Locally Restore AFW Flow (Motor Driven Pumon and Valves) Denote Critical Steps with an *X"
' NOTE' Critical Steps must be completed correctly to achieve a satisfactory grade STEP 8 Performance Step: Check *B" MD AFW Pump DWST Supply isolation valve,3FWA*V16, OPEN.
GRADE Standards: Unlocks the locking device on valve 3FWA*V16 and removes the locking device. Cue: The lock is unlocked and the' locking
. device is.. removed.
GRADE Standards: Rotates valve handwheelin the counterclockwise direction to OPEN the valve. Cue: ~ Valve handwn' eel rotates in'the
~
counterclockwise direction and then comes.to a hard stop. GRADE Standards: Rotates the handwheel 1/4 turn in the clockwise direction. iCue:; ~ Valve hs been ' rotated ',I4 turn in the
,_ , , clockwise: direction. 1._ -
GRADE Standards: Installs the locking device and locks the lock, iCue: , lTh'e 16cking~desice is installed a' nd : l locked. , 12 l _. . _ _ . _ __ - _ . - - - - - - - - - - -- - - - - - - -
'i PERFORMANCE INFORMATION Facility: Millstone Unit 3 System; AFW i
- JPM Number
- 019 Task
Title:
Locally Restore AFW Flow (Motor Driven Pumos and Valver) Denote Critical Steps with an T
' NOTE' Critical Steps must be completed correctly to achieve a satisfactory grade i
STEP 9 Performance Step: Check *B" MD AFW Pump Discharge Isolation valve 3FWA'V18 OPEN. ^ GRADE Standards: Unlocks the locking device on valve 3FWA*V18 and removes the locking device. LCue: ?The lock is' unlocked and the locking device is' removed. . GRADE Standards: Rotates valve handwheelin the counterclockwise direction to OPEN the valve.
- Cue: ~ Valve haridwheel rotates in the-counterclockwise direction and then comes.to a hard stop. .
GRADE Standards: Rotates the handwheel 1/4 turn in the clockwise direction. icue:1 Valve has tieen rotated 1/4 tum in the clockwise. direction GRADE Standards: Installs the locking device ano locks the lock. ' 7 r Cue: Tlie locklrig device is installed and J lockedi 13
PERFORMANCE INFORMATION Facility: Millstone Unit 3 System: AFW JPM Number: 019 Task
Title:
Locally Restore AFW Flow (Motor Driven Pumos and Valves) Denote Critical Steps with an T
' NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade STEP 10 Performance Step: Check *B" MD AFW Pump to SG C lsolation valve,3FWA*V24, OPEN.
GRADE Standards: Unlocks the locking device on valve 3FWA'V24 and removes the locking device. Cuei ' The lock is ' unlocked and the locking device is removed. GRADE Standards: Rotates valve handwheelin the counterclockwise direction to OPEN the valve.
! Cuei Valve' handwheel rotates in the counterclockwise direction and then Leomes.to a hard stop.
GRADE Standards: Rotates the handwheel 1/4 turn in the clockwise direction.
~
.. Cue: - ' Valve has bee ~n" rotated 1/4 turn ln the '
clockwise direction. GRADE Standards: Installs the locking device and locks the lock.
!C0s:: .Tiie'16cking device is installed'and
. locked .
14
PERFORMANCE INFORMATION i Facility: Millstone Unit 3 System: AFW JPM Number: 019 Task
Title:
Locally Restore AFW Flow (Motor Driven Pumos and Valves) Denote Critical Steps with an T
- NOTE
- Critical Steps must be completed correctly to achieve a satisfactory grade STEP 11 Performance Step: Check *B" MD AFW Pump to SG B Isolation valve 3FWA*V10 OPEN.
GRADE Standards: Unlocks the locking device on valve 3FWA*V19 and removes the locking device.
" Cue: The lock is unlocked and the locking device is removed. -
GRADE Standards: Rotates valve handwheelin the counterclockwise direction to OPEN the valve.
; Cue: Valve handwheel rotates in the counterclockwise direction and then comes to.a hard stop..
GRADE Standards: Rotates the handwheel 1/4 turn in the clockwise direction.
- Cuei ~ ' Valse has been rotated 1/4 turn in the
._ . clockwise _ direction.-
GRADE Standards: Installs the locking device and locks the lock. TCuei; The losking devke is installed and 2 locked; . i 15 a
~__ ______ . - . . _ . . _ _ . _ _ _ _ _ . _ _ _ _ .
i PERFORMANCE INFORMATION
^
Facility: Millstone Unit 3 System: -AFW JPM Number: 019 Task
Title:
Locally Restore AFW Flow (Motor Driven Pomos and Valves) Denote Critical Steps with an *X"
' NOTE' Critical Steps must be completed correctly to achieve a satisfactory grade l
STEP 12 Performance Step: Notify the control room that the checks of the AFW system LAW page 1 of Attachment A to EOP 35 FR H.1 have been completed. GRADE Standards: Examinee reports to US that the AFW system lineup has been checked using page 1 of Attachment A to EOP 35 FR H.1. Terminating Cue: The evaluation for this JPM is concluded. Stop Time: e 16
l VERIFICATION OF COMPL'ETION l Job Performance Measure Number:- ._019_ Revision: 4.____ Date Performed: Examinee: l 3 i Evaluator: Validated Time (min): 10 Actual time to Complete (min): Result of JPM: (Denote by an S for satisfactory or a U for unsatisfactory) Result of oral questions: Number of Questions: Number of Correct Responses: Score % i 4 17'
EXAMINEE HANDOUT INITIAL CONDITIONS AND INITIATING CUES JPM Tracking Number: . 019 Initial Conditions: A loss of Secondary Heat Sink event is in progress and the control room team is carrying cut the actions of EOP 35 FR H.1. AFW flow could not be establ!shed from the control room, initiating Cues: The US directs you to locally restore the AFW flow using the A and B MDAFW pumps IAW page 1 of 4 to Attachment A to EOP 35 FR H.1. You are also to verify the position of any TDAFW valves on page 1. A second PEO is checking the lineup for the TDAFW pump. 18
, a Scenario Events Facility: Millstone Three Scenario No.: 2 (Rev 1)
Examiners: Operators: Objectives: The crew will be directed to perform the staem generator blowdown valve cycling surveillance. When the first 4 lineup is completed, Pressurizer Pressure Instrument PT455A fails low. This will require taking manual control of pressurizer pressure. The crew will be able to use AOP 3571-and restore pressure control to automatic. Due to a loop seal problem, vacuum will start to decrease in the condenser. It will reach a point where the crew will start to reduce power. The cause of the vacuum problem will be found and corrected. The crew will stabilize the plant. The "B" condensate pump will trip'and the "C" condensate pump will fail to auto start. When the operator starts the "C" condensate pump it will not pump due to a shaft shear. This will result in a loss of suction pressure for the main feedwater pumps and they will trip. The motor driven feedwater pump will trip as soon as it starts resulting in a total loss of feedwater. Either due to low SG level or manual initiation by the crew, a reactor trip signal will be generated. The reactor will not trip until the trip switch at MB7 is used. None of the AFW pumps will be running and the crew must address a complete loss of feed. The scenario will end when the crew establishes feed from a condensate pump. Initial Conditions: The plant is operating at 100% power. The crew will be directed to maintain current plant conditions, Turnover: The crew will be provided the MP3 simulator standard turnover sheet which will direct them to maintain current plant conditions. The.following equipment will be out of service: "A"
. service water' pump, "A" motor driven auxiliary feedwater pump, and "B" stator cooling pump. There are thunderstorm warnings for the next 4-6 hours, 11 g3
l l Event Malf Event Event Description L k k Lypt 1 N Conduct the surveillance for steam generator blowdown valve cycling. 2 I Pressurizer pressure instrument PT455A fails low. this will require the ! operator to take manual control of
. pressurizer pressure. the instrument failure will be addressed, including Tech. Spec. and pressure control will be 1
returned to automatic control. s 3 R A decreasing vacuum will cause the crew to rapidly reduce power in attempts to stop the vacuum decrease. The source of the vacuum decrease will be found and corrected. 4 N The crew will stabilize the plant once the scurce of the vacuum decrease has l been found 5 C As the crew is stabilizing the plant the "B" condensate pump will trip. The "C" condensate pump will not auto start.
- When the operator does start the pump i
it will not pump water due to a coupling shear. i 6 C The loss of suction pressure will cause l the turbine driven feedwater pumps to i trip and the motor driven pump trips as soon as it starts. The operators may attempt to start the MDFWP 7 C When an automatic signal is generated or when a manual trip is attempted the reactor will not trip. The operators l
e can successfully trip the reactor from MB7. 8 M None of the auxiliary feedwater pumps will start. A total loss of feedwater event will occur.
4 e t Scenario Events Facility: Millstone Three Scenario No.: 3 (Rev.11 ' Examiners: Operators: Objectives: The crew will conduct the downpower to 90% power. During the downpower, after reactivity control has been demonstarted, The "D" SG level transmitter will fail to zero, the operators will be required to take manual control of the "D" SG feed regulating valve, after taking the actions in AOP 3571 and addressing Tech Specs., the crew will be able to return to automatic control of the feed regulating valve. All the necessary preliminary-checks of the motor driven feedwater pump will be completed and the crew will make start the third condensate pump in preparation for swapping the feedwater pumps. When this is completed, a power range channel will slowly fail causing the rod control system to move rods. The operators will take manual rod
- control and will be able to bypass the affected channel. When rod control.is returned to automatic a continuos rod insertion begins. The operators will need to trip the reactor to stop the insertion. When the reactor trips, the turbine will fail to trip nor can it be run back. The operator will need to close the MSIVs. The shock of the MSIVs closing will cause an unisolable ;
steamline break inside containment._ When containment pressure > reacher 23 psia, the automatic CDA will not occur. Initial Conditions: The plant is at 100% power. Excessive vibration exists on the "B" TDFWP. The crew will be directed to reduce power to 90% at 1/2% per minute and swap feed water pumps. Turnover: The crew will be provided the MP3 simulator standard turnover sheet which will direct them to reduce power to 90% at a-rate of 1/2% per minute. The following equipment will be out of service: "A" service water pump, "A" motor driven AFW pump and the "B" stator cooling pump. There are thunderstorm warnings for the next 4-6 hours. ,
Event Malf Event Event Description L k Lyne 1 R The crew will reduce power to 90%. 2 I The "D" SG level cransmitter will fail low requiring manual control of the "D" SG feed regulating valve. Once the procedure steps have been completed, the operators can restore the feed regulating valve back to auto contol. I 3 N The crew will start the third condensate i pump in preparation for swapping the feedwater pumps. 4 I An NI power range channel fails high which will result in manual rod control. The crew will be able to remove the channel from service and return to automatic rod control. 5 C When the operator returns rod contrcl to automatic a continuos insertion of the control bank "D" rods will occur. The operators will attempt to return the rods to manual control. The operators wil.' be unable to stop the insertion except to trip the reactor. 6 M/C When the reactor is tripped, the turbine will fail to trip. Additionally the turbine will not runback nor will an automatic main steamline isolation occur. The operator will have to use the control switches to shut the MSIVs. 7 M When the MSIVs are closed a unisolable steamline break occurs inside containment. This will result in a safety injection actuation.
8 -C When containment pressure exceeds 23 psia, an automatic CDA will not occur. The operators will need to manually initiate CDA at the component operating switches (pushbuttons failed also), e r
.w
n l Scenario Events Facility: Millstone Three Scenario No.: F j7ev.1) Examiners: Operato1' , Objectives: The crew will be told that the "A" service water pump is ready for a test run. The crew will conduct the swap from the "C" to the "A" SWP. ine crew will conduct the test of the HP turbine stop valves, after the first stop valve is tested, the selected first stage pressure channel will fail low resulting in the control rods stepping in. The operator will take manual control of the rods. When the crew returns to automatic rod control CONVEX :111 request a 200MW load reduction. The crew will conduct this load change. After the crew has satisfactorily demonstrated reactivity control, one of the control ban'k "D" rods will stick and eventually be out of position. While I&C is investigating, they inadvertently cause the affected group of rods to drop into the core. The crew should recognize that this requires a reactor trip. When the trip occurs, a large break LOCA occurs. Automatic SI will not occur, The motor driven AFW pumps will not auto start and some of the chargia., system valves will not re-align for the SI. Initial Conditions: The plant will be at 100% power. The crew will be directed-to shift to the "A" SWP and when that is completed, to conduct the test of the HP turbine stop valves. Turnover: The crew will be provided the MP3 simulator standard turnover sheet which will have them maintain current plant conditions. the following equipment will be out of service: "A" service water pump (but is ready to be placed back in service),
"A" motor driven AFW pump, and "B" stator cooling pump. There are thunderstorm warnings for the next 4-6 hours.
Event Malf Event Event Description No _ Ho tyne 1 N Conduct a swap from the "C" to the "A" Service Water Pump, 2 N Conduct the surveillance for the HP Turbine Stop Valves. 3 I First stage pressure transmitter PT505 will slowly. fail lor, This will cause rods to start driviig in and manual rod control will be required. The crew will be able to return to automatic rod control. 4 R Convex will call and request a load shed of 200MW. The crew will commence a rapid downpower. 5 C After the crew has addressed the control of the reactor in the downpower procedure, one of-the control bank "D" rods will stick and eventually be out of position. 6 M When the I&C department personnel are sent to investigate the stuck rod, the affected group of rods will drop into the core. The crew should recognize that a reactor trip is required. 7 M When the reactor is tripped a large break loss of coolant accident occurs. An automatic SI will not occur. 8 C Neither motor driven auxiliary feedwater pump will auto start on the SI. The operator will be able to manually start them. 9 C The charging systen valves will not realign for the SI. The operator will
._y_-- - - - -- - - - -
be able to operate the valves using the individual valve control switches. i l
l -o. \ L SIMULATOR EXAM GUIDE APPROVAL SHEET 1.
Title:
LOIT NRC #2 1 ID Number: NRC2 - Resision: 0 : II. Initiated: D. Minnich 5/20/97 L Developer Date Ill. Reviewed: l l Reviewer Date IV, _ Approved; i i L Operations Manager - Date 1 Operator Training Supersisor Date.- \ l l I i l t z v --- -
-r, .g.-.., , _
m-
i
- SIMULA'IDR EXAM GUIDE TABII OF CONTENE SECT 10NS LIS'mD IN ORDER
- 1. Exam Osmiew-
- 2. Instmetor Guide
- 3. Sequence of Events Sununty
- 4. Validation Checklist
- 5. Reference and Critical Task Tracking Form
- 6. Scenario Initial Conditions Sheet ;
c - SEC110N 1 - EXAM OVERVIEW
Title:
LOIT NRC #2 - h ID Number: NRC2 Revision: 0 1.. Exam Brief: f f The crew will take the shiR with plant conditions at MOL and 100*A power,
- ARer tumover, the Pressurizer Pn:ssure Instrument PT455A fails low over a period of 5 minutes. The crew should diagnose the failure and utilize AOP 3571, Instrument-Failure Response, to n:spond to the event. The enny should n:fer to T.S. 3.3.1, 3.3.2, and 3.3.3.5 for applicability. --
ARer tripping the sprugiate bistables, a loss of condenser vacuum will occur. The failure will be such that implementation of the Foldout Page of AOP 3559,- Loss of Ce ;mser Vacuum, will need to occur. The crew will need to transition to AOP 3575, Rapid Downpower, in order to reduce power at the maximum available rate of; 5Wminute [no steam dumps]. The cause of the loss of vacuum is a loop seal problem-which is found and conected at about 900 MWe, whereupon the ertav will stabilize :i the plant.
'One of the two running Condensate Pumps will trip. The standby pump will start but L the motor / pump shan coupling will shear. This will cause a Main Feed Pump low suction pressure.L'Ihe TDFPs will trip, causing a loss of all SG Feed Flow.
When an_ automatic trip signal due to low SG level or a manual trip is attempted from ; MIM, the reactor will not trip. The operators can trip the reactor stx:cessfully from - MB7.= At step 4 of E-0 the crew should determine that a Safety injection is not required and -
- transition to ES-0.1, Reactor Trip Response. Upon transitioning the crew should -
observe a RED PATH on the HEAT SINK Status Tree.- The crew should transition to EOP 35 FR-H.1 and carry out the action for the loss of heat sink accident. _1 hey will be able to reestablish Steam Generator feed from a Condensate Pump._ 1he exercise will end when the crew has restored feed to the SGs and have ' tmnsitioned to the procedure and sig in'effect. The procedure flow path for this exercise isi AOP 35M, AOP3559, AOP 3575, E-0 & l Section 1 Page 1 of 2 ;
l FR-II.1 l
- 2. Plant / Simulator difTerences that nwy affect the scenario are: 1 None.
- 3. Duration of Session: I hour J
Section 1 Page 2 of 2
SECTION 2 INSTRUCTOR GUIDE
Title:
.LOrr N~C #2. ID Number: NRC2 Revision: .0_ All Control Room Corvhrt. Onerations and Communications shall be in accordance
- COP 200.1.Conart of Onerations. and OP 3260. Unit 3 Conart of Oncrations.
i'
" Review the Simulator Operating Limits (design limits of plant) and the Simulator Modeling Limitations and Anomalous Response List prior to perfbrming this training scenario on the simulator. The instmetor should be aware if any of these limitations
'may be exceeded." (NSEM 6.02) d s
r Section 2 Page 1 of 39
- SIMULATOR PROBIME DURING EXAMS It is the responsibility of the Instructors in the simulator to insure that exam ,
interruptions have a minimum negative impact on the Crew and the examinations we provide. Be aware that at all times the Operators should treat the simulator as ifit were the plant and you too should treat it as much like the plant as possible when they are in the simulator. As soon as the Instructors are aware of a simulator problern that will adversely l affect the exam in progess (computer fault, etc.) the Instructor should:
- 1. Place the simulator in FREFZE if possible.
- 2. Announce to the Crew that there is a simulator problem.
- 3. Request that the Crew leave the simulator control room. ('The Crew l should leave the simulator for problems which involve major switch alignments).
- 4. Deal with the problem (reboot, call STSB, etc.)
- 5. After the Instructors believe the simulator is restored to service, the Crew should be told how the exam will continue. Ifit is possible and felt to be acceptable to the evaluators, the examination can
- begin where it left off with an update on plant parameters and each Crew member is prepared to restart. If the examination will not begin where it left off, the crew should be told how and where the exam will begin again.
- 6. Once the Crew has been told how and where the exam will begin, have the crew conduct a brief so that the Instructor and evaluators can insure that the crew has all the necessary information to continue with the scenario.
- 7. Once all Crew members, Instructors and evaluators are satisfied that they have the necessary information to continue the scenario, place the simulator in RUN and announce to the Crew that you have continued the evaluation session.
Section 2 Page 2 of 39 _a
Title:
LOIT NRC #2 INSTRUCTOR GUIDE Revision: D ID: NRC% Task Time IDA/Malf Instructor Information/ Activity Assign Expected Response Standant Comp EVENT #0 TTRE: INfilAL SEIUP Setup Iminrtiom: EnterIDT as follows :
- At any XiliRM window, type <idt>
When the SUN asks for an executive type: UEXEC or RlliXEC! cnter <r>: this will bring up a blank idt . page. To go to a pnniously saved idt file type <rcad> at the prompt When the SUN asks for a file name of the file you wish to view type in tk appmpriate file name - 1hc old "Landon" files are as fbibws: Old ISD pages 1-8 are idt file OPS Old ISD pages 9-16 are idt file OPSI Old ISD pages 17-19 are idt file OPS 2 o IE the step counters are at/near 000, IllEN , REMOVE the S111P COUNTliR OVERRIDE, allow the counters to step out during the IC mset, Reset to IC- 14 REINSTATE the step counter OVERRIDE Adjust the various pot settings to the valued specified by the chart located in the sim booth Ibr the selected IC. Place Simulator to RUN RESEF the time constant on the PZR level contmilcr by PLACING the PZR Master Irvel controller in MANUAL then retum the Controller to AUFO. Set the S'EP COUNiliRS PLACE the Main Turbine on the LOAD LIMFFER a Verify annunciator, "COMPUFER FAILURE" (MIMC,1-11), is NOT LIT. Place M Curve 13ook in Shelf Ibr Opemtor use. Remove other Curve Ilooks fium the floor. Clear the LX'S Alamts Reset the Rad Monitor CMFIR Console by Depnssing the " Status Grid" button twice. Section 2 Page 3 of 39
Title:
IDIT NRC #2 INSTRUCTOR GUIDE Resision: D ID: NRC2 Task Time IDA/Malf Instructor Information/ Activity ' Assign Expected Response . Standarti- Comp P1 ACE Tile FOUDWING EQUIPMENT IN I'IL oralign as needed:
"A" Service Water Pump - Caution tag and place in I'lL "A" MDARV Pump - Caution tag and place in P1L "B" Stator Cooling Pump - Caution tag and place in I'FL FxpfpmerW OOS: "A" Service Water Pump "A" MDAFW Pump "B" Stator Cooling Pump a
insert applicable CREW EXAM Tape into the VCR. Synchronize the MONITOR Tinr Display with BIG BEN. Place copy of OPS Fonn 3670.4-1 (weekly PMs) on US desk Initial Malfunctions /lOs/IDAs: Malf RM)7A Motor-driven Fcedwater Pump Trip Malf RV21B 'B" Aux Feed 1%mp Discharge valve Oosed Malf RVl9 'IDAFW Pump trp on overspeed Malf MV33C Condernate Pterj C Cagling Shear Malf RP09A Manual Reacnr Trip Failure - MB4 Malf RP10A Automatic Res:torTrip Failure - Train A Malf RP10B Automatic RectorTrip Failure - Train B 1/O Ovenide (IM) 1-3CNM-P1C 'C' CondersMe IP amberlight 'OW' Ann Ovenide MBIF,DI 'OW' [IDARY Bypes Arm) Section 2 Page 4 of 39
Title:
_LQIT NRC #2 INSTRUCTOR GUIDE Revision: G ID: NRC2 Task Time - IDNMalf Instructor Information/ Activity Assign Expected Respoerse Standant Comp tral Examinen Refer to the ' Briefing Script for the Operational Exarn" and twief the crew. Booth Imtnrton Commence RecortEng Sinadatorsession Booth Imtnetor. Itiform the crew timwwcr(Initial Conditions page at erxl of IE) with the SM. Have the SM twief his crew on plant coruEtiorts azul any maywequipment OOS. i i l Section 2 Page 5 of 39 i
Title:
_ LOIT '2f_#1 INSTRUCTOR GUIDE Revision: D ID: NRC2 Task Time IDA/Malf Instructor Information/ Activity Assign Expected Response Standard Comp EVENT ONE: IVrform Steam Genergar Nwdmn valve cycle as per SP 3670.4 (Rondine 1%fs), step 4.1.3. It is expected that the US will give a pre-job brief to the RO lbr the , SG blowdotm valve cycle. EVENT TVO: Failure of Pressinizer Pressine InstnanerW IT455A , T= Tumover RXO9A PT455A fails low to 1700 psia RO Notice and report the failing channel to Complete sev= 0% the US ramp = 600 secoruk 1 US Enter AOP3571, Instmment Failtne AOP3571 Response. entry conditi(ms De 15zr Master Pressure Controller US/ Determine the initiating parameterand AOP 3571 will be placed in manual. RO giace the affected contmilerin step 1 MANUAL RO Stabilize the plant parameters. AOP 3571 step 7 Section 2 Page 6 of 39 s h
Title:
LOIT NRC #2 INSTRUCTOR GUIDE Revision: 11 l ID: NRC2 Task Time IDA/Malf Instructor Inibrmation/ Activity Assign Expected Response Standarti Comp Attachment "B" is the correct US IYrform conective actiom ming AOP 3571 attachment. appropriase attachment. step 3 RO Ikfeat the failed channel input. AOP 3571 Att.B step 1 RO Restore RCS pressure to normal, then AOP 3571 place PZR pressure control in Att.B step 2 automatic. , CREW When conditions have stabilinxi. AOP 3571 observe MB annunciators and Att.B step 3 parameters. Immediately report any unexpected or unexplained conditions to the Shill Manager. US/ Determine which Reactor Pmtection AOP 3571 RO System bistable (s) nxluins tripping- Att.B step 4 US Place a check mark in the box above AOP 3571 the q>inquiate channel that requires Att.B ; tripping on pages 3 or 4 of this step 4a Attachnrnt 33.1 action 6,33.2 action 20 SM Refer to Technical Specification 33.1, AOP 3571 33.2. and 333.5. Att.B step 4b RO Check the existing bistable status to AOP 3571 cnsuit a reactor trip will not occur Att.B when the failed channel is tripped step 4e Section 2 [ Page 7 of 39
Title:
_I OIT NRC #2 INSTRUCTOR GUIDE Resision: 9 ID: NRC2 Task Time IDA/Malf Instructor Information/ Activity Assign Expected Response Standarti Comp T= request to RXRl06 OPEN, Pentection Dnor SM/ Regtx:st the I&C Ilyutment trip the AOP 3571 trip IVSs RXR40 'IRIP, Ili lYr Press Rx Trip US annquiate bistables using Attachment Att.B RXR120 TRIP, P-il B and Attachment S. step 4d RXR48 'IRIP, l>>w IVr Rx Trip RXR44 TRIP, lirPressI;>SI RXR05 'IRIP, OraTTrip RXR34 'IRIP, C-3 RPR40 'IRIP, I;> IVr Press PORV Ifigic RXR106 CIBSE, Protection Ihwr RO Verify the appnpiate histable status AOP 3571 lights are lit. . Att.B step 4e SM/ Request I&C Dgxutment perform AOP 3571 US corrective maintenance ca failed Att.B step 5 instrument. Event #3: l>>ss of Condemer Vacinan B00111 On MOD COMP in the Ikuth. INST: Bring up the CIRC WA'ER SCREEN by - BOP, F-4, Picture 26
'lhis will assist in controlling the loss of vacuum.
Section 2 Page 8 of 39
Title:
LOIT NRC #3 INSTRUCTOR GUIDE Revision: H ID: N_RC2 Task-Time IDA/Malf Instructor Information/ Activity Assign Expected Response Standard Comp T= Event 2 ITWI Lawering condemervaciman, complete +1 sev= 100% FWOI is initially entenxi at 100% minute severity. NOE Aller the low vacuum alarm is US o 'Ihc Foldout page must be AOP 3559 received or the crew notices the open. Step I degmding vacuum, REDUCE the ' NO'E severity to 5-30% and funher o If a reactor trip occtus during reduce the severity as necessry to the perfixmance of this prevent exceeding 7.0" IIg procedure, Go to E-0 Reactor backpresure. The goal is to not Trip or Safety Injection. have the crew trip the plant.' NOIE 'Ihe FOLDOUT PAGE Criteria will CREW FOU)OUT PAGE FOLDOUT Ikx>th Inst: apply. 'the crew is expected to PAGE adjnst tmnsition to AOP 3575, Rapid 'IURBINE LOAD REDUCDON severity of linmpower, and perform a Ixnver CRIIIRIA malf. so nxiuction. When the crew vacuum framitiom, proceed forward to page IF condenser backpressure increases remains 14 fordownpoweractiom. to GRFATER 'MIAN 5 inches Ifg between 5- absolute, turbine kod must be reduced 6" (DO NOT nxluce below 360 Mwe) c: the maximum allov.able rate until . vacuum stabilizes using AOP 3575, Rapid Ilmnixmtr. IlOOfHI Check the actions under AOP 3575 IlOP Check Ortidating WheerSystem AGP 3559 concuntnt with AOP3559 Operation F.cp 1 < Section 2 I Page 9 of 39 l
Title:
LOIT NRC #2 INSTRUCTOR GUIDE Revision: '9 ID: NRC2 Task Time - IDA/Malf . Instructor Information/ Activity Assign Expected Response Standarti Comp 130P Verify cirtulating unter pumps - ONE AOP 3559 PER CONDENSER RUNNING Step 1.a llOP Verify all available circulating unter AOP 3559 pumps - RUNNING Step 1.b BOP Verify unter box outlet isolation AOP 3559 valves - OPEN Step 1.c IOP Verify the traveling screen dilTerential AOP 3559 pressure - LESS 11IAN 12 inclus Step 1.d i10 2 B00Ill Do not place second set of air BOP Check Condemer Air Renmal AOP 3559 ejectors in service when requested Discharge 1%sh Step 2 by the crew. Tell them both sets are on. IYrform m described below. IMR01 or Steam jet air ejector valves. Utilize PEO Locally Verify both sets of steamjet AOP 3559 IMR02 as necessary to contml the rate of air ejectors in senice using applicable Step 2.a the toutring vacuum steps in OP 3329, Condenser Air Rerr.wal. Section 7.2 NOIE BOOlli INSTRUCIOR: The cause BOP Verify SJAE auxiliary steam supply AOP 3559 of tir pmblem will be found if the valve (3 ASS *AOV22)- OPEN Step 2.b US sends a PEO to investigate the loop seals. Section 2 Page 10 of 30
Title:
LOIT NRC #2 INSTRUCTOR GUIDE Revision: D ID: NR_C2 Task Time IDA/Malf Instructor Information/ Activity Assign Expected Response Standard Comp IlOP Verify isolation dampers for gascous AOP 3559 waste to Unit I stack Step 2.c (3GWS*AOD78A and 3GWS*AOD78B) - OPEN T+ 5 mim of IlOOfIll Reput tirat 3G%S-FNI A is running PEO Incally (Aux Bldg 45') Verify process AOP 3559 rwinest vent fans (3GWS-INI A or 3GWS- Step 2.d INIII) at Gas Waste Panel (3GWS-PNL-P6)- ONE RUNNING T+ 5 mim of BOOrill Report that lxith valves are ogen PEO locally (Turbine Bldg 38'southurst) AOP 3559 ruguest Verify SJAE exhatrt valves (3 ARC- Step 2.e Crew should transition to AOP AOV36A and 3 ARC-AOV36B)- 3575 for rapid downpmver when OPEN backpressurt is > 5". Go to page 14. IlOP Orck G!arxl Seal Pmsstur - AOP 3559 BEIMEEN 2 and 6 psig Step 3 Locked valve key is required for AOP 3559 some kral operations. Step 4 Note llOP Oieck Onulemate Surge Tank Irrel AOP 3559 Step 4 o GREA'IliR TIIAN I8,000 gal o NOT DECREASING IN AN UNEXPECTED MANNER Section 2 Page 11 of 39 k _ _ . - - - - - - - -
Title:
LOIT NRC #2 INSTRUCTOR GUIDE Revision: .H ' ID: NRC2 Task Time iDA/Malf insinnfor Information/ Activity Assign Expected Response Standant Comp CREW A turbine trip occurs if the exhaust AOP 3559 imi tempcmture exceeds 225"F. Step 5 NOTE IK)P Oseck Extrast Ilood Temperahme AOP 3559 l Annimiciators EXII11000 A H,and Step 5 C MVP 1II (MH6A 5-4, 5-5, and 5-
- 6) - NOT IJr.
Onl; applies if alami is received BOP Slowly 'Ihmttle OPEN the exhaust AOP 3559 l lxxxi spmy bypass valve (3CNM- Step 5 RNO MOV100) to reduce the temperature I to LESS 'nIAN 175"F using 3TMI-UR22 (points 1,2, and 3). US Dispatch An OperatorTo lempect For AOP 3559 In-Irakage Step 6 13OP CLOSE condenser vacuum breakers AOP 3559 3 ARC-MOV20A-B-C (MB7) Step 6.a PEO laxally Close valves (Turbine Bldg AOP 3559 60' utst). Step 6.a RNO IKXJIlI Acknowledge request PEO locally Check vacuum breaker kxp AOP 3559 seals (Turbine Bldg 60' west) - Stcp 6.b FILLED Section 2 Page 12 of 39 i
~
Title:
LOIT NRC #2 INSTRUCTOR GUIDE Resision: H ID: NRC2 Task Time IDA/Malf Instructor Information/ Activity Assign Expected Response Standarti Cosnp T = 5 min of IKXIHI Report that the loop seal forSlAE request "A" was ernpty and you are in the process of filling it. Booth Renuwe IWI PEO Ircally Check for unusual noises AOP 3559 indicative of air in-leakage Step 6.c BOP Check scal water supply pnssum AOP 3559 annunciator EXT STM NRV SEAL Step 6.d PRES LO (MIMA 3-6B)- NOT LIT US/ Contact Digineering to assist in AOP 3559 ; SM locally checking condenser Step 6.e penetmtions for air in-Icakage US/ Raicw cunent Maintenance and AOP 3559 SM Testing Activities. Step 7 Section 2 Page 13 of 39
Title:
LOIT NRC #2 INSTRUCTOR GUIDE Revision: 11 ID: SBC2 Task Time IDA/Malf' Instructor Infirmation/ Activity Assign Expected Respome Standard Comp AOP 3575 CRiiW Iktermine Ibwer Reduction Rase AOP 3575 (%fmin). Step 1 Yes. 5% / minute is the applicable US Check desired power nxluction rate - AOP 3575 mte as the steam dumps are NOT, IliSS TilAN OR EQUAL.TO Step 1.a or soon will not be, available. 53Vmin. US Check power reduction a CONVEX AOP 3575 requested Snergener Gerrnrion Step 1.b Redrwtiort NO. 5% / minute is the applicable US Perform the fbikming: AOP 3575 mte. AOP 3559 prescribes the mte Step 1.b as the maximum allowable mte, 1) Determine power reduction RNO which will be 5% / minute without mte using Table. the steam dumps.
- 2) Proceed to Step 2.
US Check Rod Contml In AUID AOP 3575 Stcp 2 US If dining the performance of this AOP 3575 procedum the Rod inserti(m Im-Lo Step 3 Limit is reached, Go to AOP 3566, CAUDON Immediate Ikrati(m. Secti<m 2 Page 14 of 39
Title:
LOIT NRC #2 INSTRUCTOR GUIDE Revision: Q ID: NilC2 : Task Time IDA/Malf Instructor Information/ Activity Assign Expected Response ' Standard Comp CREW If hud m!uction is a CONVEX AOP 3575 nxiucsted enrrgency gerrration Step 1 l reduction, the following apply- NOTE l
'lhe Unit 1 Shift Manager will determine Ixnv the load l reduction will be shanxi among the Units.
i DO NOT stop a CONVEX
" Emergency Load Reduction" l request due to AFD exceeding t tlx: targe; band.
The load nxluction must be completed within 15 minutes ofnotification.
-CREW Initiase Imad Reduction. AOP 3575 Step 3 i
US Check poutr reduction a CONVEX AOP 3575 requested emergency gencmtion Step 3.a nxiucti<n IKX7111 Acknowledge the information and US Infonn CONVEX ofload reduction AOP 3575 request the crew maintain MVARS mte (Mue/ min) and final Mwe level. Step 3.a throughout the dongower to a RNO vahe of 100 20 MVARS (the US may maintain MVAR and not contact CONVEX). t Section 2 Page 15 of 39
Title:
LOIT NRC #2 INSTRUCTOR GUIDE- Revision: H ID: NRC2 Task' Time IDA/Malf Instructor Infbrmation/ Activity Assign Expected Response Standant Comp IOP Check turbine NOTin STANDBY AOP 3575 LOAD contml. Step 3.b BOP Check LOAD LIMIT LIMITING light AOP 3575
- LIT. Step 3.c BOP Intermittently Press DECREASE AOP 3575 LOAD pushbutton until LOAD Step 3.d LIMIT LIMITING light - NOT LIT.
BOP Rotate LOAD LIMIT SET adjust AOP 3575 know at least one fiill tum in raise Step 3.c directi(n BOP Select DECREASE LOADING RATE AOP 3575 to ON. Step 3.f 5% / min should be selected BOP Select LOAD RATE LIMIT %' MIN AOP 3575 to required power reduction rate Step 3.g (%' min). NME>> Crew should adjust to about 400 BOP Utilizing DECREASE LOAD AOP 3575 MWE as when temperatore pushbutton, Adjust LOAD SET to Step 3.h decreases at the end of the tmnsient desired final Muc (p(mtr level). ; load will drop an additional 20 or so MWE. t NWF7> lhe enny would be requinxi to trip BOP Maintair' initial MVAR loading AOP 3575 l the turbine if kiad is < 360 MWE during power rrduction unless Step 3.i and Backpnssure is greater than 5 dirrcted othenvise.
"Iig Section 2 Page 16 of 39 ;
Title:
I OIT NRC #2 INSTRUCTOR GUIDE Resision: 9 ID: NRC2 Task Time IDA/Malf Instructor Information/ Activity Assign Expected Response Standani Comp US If at any time the pmtr ruluction _ AOP 3575 rate must be clunged, retum to Step Step 4
- 1. NOTE US Verify Pbwer Reduction Rate - AOP 3575 GRENIFR111AN OR EQUAL 1D Step 4 3*N MIN.
US Initiate Rapid Horation. AOP 3575 Step 5 RO Place RCS makeup contmlier to AOP 3575 AlJIO. Step 5.a RO START one luric acid transfer pump. AOP 3575 Step 5.b RO OPEN cmcrgency boration valve AOP 3575 (3CIIC*MV81(M). Step 5.c RO/ Verify pmtr irduction rate - AOP 3575 US GRENER 'IllAN OR EQUAL to Step 5.d 5%' MIN. RO START second boric acid transfer AOP 3575 pump. Step 5.c RO OPEN charging line flow control AOP 3575 valve, to match dirret boric acid flow Step 5.f (3CIIS-Fi 183A) Section 2 Page 17 of 39
Title:
LOIT NRC #2 INSTRUCTOR GUIDE Revision: 9 ID: NRC2. Task Time IDA/Malf Instructor Inf~ormation/ Activity Assign Expected Response Standant Comp US Recoril time horation started AOP 3575 Step 5.g
'line RO Energi7e all PZR heaters. AOP 3575 Step 5.h 70% power change = 1050 gallons US Determine requimi boric acid AOP 3575 addition by multiplying Step 5.i total power change (6%) by 15 (galM'o) = gal.
~72 gpm yields a time of~ 15 US Determine required time to bomte by AOP 3575, minutes dividing required gallons of boric acid Step 5.j (gal) by the direct boric acid flownte (gpm) min.
US/ Boric acid flow mtes are based on AOP 3575 RO approximations. Adjustments should Step 6 be made to the volume acklition or NOTE flow mte as necessary to ensure the reactor reaches the desired end state of: Tavg on progmm Rais above the RIL AFD on or above the target value US Restore RCS Makety AOP 3575 Stop 6 Secti(m 2 Page 18 of 39
Title:
LOIT NRC #2 INSTRUCTOR GUIDE Revision: 9 ID: NEG Task Time IDA/Malf Instnictor Informati<m/ Activity Assign Expected Response Standard Comp US/ Check mpid boration perfomni Ibr AOP 3575 RO the requinxi time detemiine in Step Step 6.a
.5.j.
'lhe first time through the US will US lhxxul to Step 8 and, WIIEN Rapid AOP 3575 nest likely utilize the RNO. If so, bomtion has been perfonned for the Step 6.a Proceed to step 8 and retum here requinxi time, TIIEN Retum to Step RNO when time is complete 6.b.
RO CLOSE emergency boration vahe AOP 3575 (3ClIS*MV8104). Step 6.b RO STOP boric acid tmnsfer pump (s). AOP 3575 Step 6.e RO Place charging line flow control valve AOP 3575 in A UIO. Step 6.d
~
US Proceed to Step 8. AOP 3575 Step 6.c - US/ Raksee Steam Supply To 'Ihe MSRs, AOP 3575 IlOP Using OP 3. i, Reheat and Moisture Step 8 . Separdor, S nan 7.8. US Orck If RG Samide is Required. AOP 3575 Step 9 US/ Verify change in Reactor Power- AOP 3575 RO GREATER TIIAN 15% IN ONE Step 9.a iIOUR. Section 2 Page 19 of 39
Title:
LOIT NRCJt2 INSTRUCFOR GUIDE Revision: 9 ID: NRC1 Task Time IDA/Malf- . Instructor Information/ Activity Assign Expected Respome Standarti Comp 4 Acknowledge nx]uest to perform US/ Request Chemistry sample tic RCS AOP 3575 hxline sample. SM lbr imline (within 2 to 6 /xnas <fter Step 9.b' the jxncer c/xnge.)
'lhis will depend on whether the US Verify Target IbwerIrvel- IESS AOP 3575 caisse of the kiss of condenser 'IllAN 50% Step 10 vacuum is found and cmected. If RNO corrected, vacimen will stabilize and the US shoukt stop the rapkl downpowerand proceed to step 20.
If the cause has not been corrected. he should continue to step i1. US/ Verify Cmtml Bank D - GRENITR AOP 3575 , RO 'HIAN 120 steps. Step I1 T+ 3 min of F%R30 Renme the Desired # of Demim BOP Renme Condemale Dernim Fmm AOP 3575 . request fmm service and report to the Senice As Necessary To Maintain Step 12 Contml ihmm that the task is Demin Flow Between 1200 gpm and ' complete 3200 ggun Using OP 3319C, Condemale DemineralizerMixed Bed System, Section 7.4. l T= request FMH57 or Set to as requested to renwive BOP When Mmer Decremes Below 50% AOP 3575 !" FMR58 TDMFW hanp (probably will not Stop One Main Feed Pump Using OP Step 13 get to this power level). 332?, Main Feedwater, Section 7.4 or 7.9. RO Mhen ReactorIbwer Decreases AOP 3575 Below the P-9 Setpoint, Verify 'NIS Stty 14 ! POWER RANGE P-9 PERMISSIVE" Annimciator(MB4D 6-1) - IR. Section 2 Page 20 of 39
Title:
IDIT NRC #2 INSTRUCTOR GUIDE Roision: 11 IIh NRC2 Task Stadard Tiene IDA/Malf Instnictor Information/ Activity Assign Expected Response Co up EVENT 4: Total loss of Feedne lhne = Event 3 cosuplete + 1 niin. I%C3C "C" CONIXENSATli IM1P 1R1P FWl3A - rscu 1: "A" CONDENSNE IB1P 1 RIP Booth INST NUE: He stady to delete FWl3C m soon m 'C' pung trips. The trip will be L.quud to the crov ( amber light is ovatiden "OFF")- they should diagnose the pmbicm as the "A" pump tripping and a failure of the "C" pump to aula-start. F%T)3C must be removed before the BOP manually starts the "C" pump. The "C" Gu!. PP will start but not pump any water dte to a shem:d shall coupling.1he aov should recognize this fmm the Inv Fced Pump Suctim Pressures and de near "0" unning amps of the "C" Cond. PP. If the cov attempts to manually trip the Reactor fium MIM. the trip switch will not md. but tripping from MB7 will be successful. The sequence of events with no operator action arc-
"A" Cond. PP trip. "C" Cond. PP start. "C" Gni PP shaft shcar.
Imv feed PP suction press. folkmtd by a trip of thelDF%Ps. Auto Rx. trip signal on SG Im-Le lor! Manual trip fmm MB7 B00111 If poweris km enoegh such that one condemate pump is sunicient to s@ sequised IMh, le stadv to inct nudfiertions FW)7B ("A"TDFP trip) and FWI7C('B"1DFP srip) Section 2 Page 21 of 39
Tstle: IDIT NRC #2 INSTRtLTOR GUIDE Roision: R ID: BBC2 Task Tinee IDA/Malf Instructor Infonnation/Acthity Assign Fagwcted Response Standant Casup IK)P Rc;wts that bith TIEfINPs inve tripped. and tlut the MDNfFV.? lus tri m d US may order IK)P to attempt me IUP Attemrts me more start of the more start of the AfDNfF%P. AfDNfEWP. It does NOT start. US should realin: that feed fimv US Directs the RO10P to Trip the caruxt be reestablished and that a Rector and carry out the immediate reactor trip is requinxi. US sixxdd acrims of E-0. go to Afaster Silence. NOTE RO 1 RIP she sanctor ['j i5sinr>nid order 'Mader5 dance" lufore ordedag matforidp. Ik rencfor will sent tdpfart MR4. Cmv Go to E-0. Rcetor Trip or S.<q Injection. E-0 SL'S - Foldout page must bc <pm E-0. Step I. NOTTI k Section 2 Page 22 of 39
Title:
IDIT NRC #2 INSTRCCFOR GUIDE Raision: 9 Ilk bRC2 Task Timee IDA/Malf Instructor Infimnation/ Activity Assign Exgweted Response Standard Cosep ADVERSE CIMF dermed as GREATFR TIIAN IWV or GREAT 1R T11AN 10'"/ in ctetsinment. This definition applics to this and all sulu p EOlk The reactor can be interpnsed as " tripped" and the operator shall proceed to the rd high level step when any two of the three tulict substeps of step I are determined to be satisfxxi. RO Verify HractorTrip E-0. Stcp 1 [*] Check reactor trip and inpass breakers - OPEN Check rod bottom lichts -IlT Check neutmn flux - Shifts to E-0 DECREASING RNO to trip the reactor DOP Verifv Turbine Trip E-0. Step 2 Check all turbine sty mhrs - E-0. Step CLOSED 2.a t Section 2 Page 23 oi39
Title:
IDIT NRC #2 INSTRUCIUR GUIDE Revision: 9 ID: hRC2_ Task Tense IDA/Malf lastructor Infernestion/Acthity A@ Emsweted Response Standani Consp i US Vesifv Ibwerto AC Enongency E-0. Step 3 Innses IK)P Check tusses 34C an_ MD - AT E-0. Step IFAST ONE ENERGZED 3.a NOTE SI should rot be initiated. - US OrckIrSIIs Actassed E-0. S!q,4 . RO Verify Safety Injection Actuation EOP 35 E-0. annunciator - LIT- Stcp 4.a US Check if SI is required E-0. Step 4 j RNO . Ctmt pressun- GREATER 11IAN 18 psia .i 2 - RCS pressure LESS 1RAN ' 1890 psia M PZR Icvel LESS 111AN 13% M i RCE _ acooling LESS 11LAN : 2rF ! i 2
- SU yressure LESS 11L\N 660 PS18 IE Si is required.11IEN Initiate SL l i
Sectim 2 i
- Page 24 of 39
i f
Title:
LOIT NRC #2 INSTRUCIDR GUIDE Resision: R lih NRC2 i Task 'linie - IDA/Malf Instructor Infornudion/ Activity Assign Exgwctal Response Shadard Connp l NOlli . A RED PATl! on iIEAT SINK IE SI is NOT required.111EN Initiate should be present requiring the monitoring of CSF Status Trees and crew to transition to FR-1L1. Go to ES-0.1. Reactor Trip Respmse. i FR-IL1 SITES CREW If total feed flow is LESS TlIAN 530 FR-1LI ! gprn due to opcmtor action. DO NOT step 1 i PERFORM 11IIS PROCEDURE. Caution ! CRLTV Fced iknv must not be reestabFished FR-1LI i to any faulted SG if rxm-faulted SG is sicp 1 availabic. Caution US Oseck ifSeconduv Hest Sink is IR-1L1 Respsind stcp i ROBOP Verify RCS pressun - GREATIER FR-1L1 T1IAN ANY NON-FAUL11?D SG step la PRESSURE RO Vcrify RCS hot leg WR temperature - FR-ILI GREAlliR TilAN 350 F step lb The "A" charging pump will be RO Ourck Osmging linup Sedes - AT FR-ILi mnning. IIASTONE RUNNING step 2 Section 2 Page 25 of 39
Tstic IDIT NRC #2 - INSTRLLTOR GUIDE Roisina: R ID: NRC2 Task Tissee IDA/Malf Instnoctor Infernestion/ Activity Assign FW Reposese Staer'wd Cosup CREW Stcps 10 timmgh 14 (biced and feed) FR-ILI i of this procedurt must be immediately step 3 initiated if either of the fbHoning Caution wm
- WR level in any 3 SGs is LESS11IAN 27%(57% i ADVERSE CTMT)
- PZR pressure is GREATER
- 111AN OR EQUAL TD 2350 ;
psia due to kiss ofsecondary heat sink inficated by core ' cxit TCs increasing. , t i IfofTsite power is lost aficr Si reset. FR-IL1 l nunual action to restart safegumis Step 3 ; j apipment nmy be rapiral NOTE i 1 If the recirculation spsy pisnps are FR-1LI required and have not started. DO Step 3 1 NOT reset CDA. NOTE t US Tsy to FAmNisit AFW Fhm to at FR-Ill i Imust One SG step 3 a i IX)P Verify AFW valve alignment - FR-1L1 PROPER EMERGENCY stcp 3a AlJGNMENT DOP Verify DW5Tsuction ulves FR-IL1 l (3FWA*AOV61 A and step 3b 3FWA*AOV6T B)- OPEN Section 2 i Itge 26 of 39 t [
Titic: LOIT NRC #2 INSTRUCTOR GUIDE Revision: G ID: NRC2 Task Time IDA/Malf Instnxtor Information/ Activity Assigri Expected Response Standard Comp BOP Verify D\BT Icrel- GREATTiR FR-IL1 TIIAN 80.000 gal step 3c BOP Vcrify AFW pump opcmtiort FR-ILi step 3d NOTE The "B" MDAFW PP will be 1) Check MD pumps - FR-ILI running but not pumping any water. RUNWING step 3d (Disc. VV ckad) part I
- 1) START pumps. FR-IL1 IE the pump (s) do NOT start,11IEN step 3d Restore poutr to the pumps part i RNO (MB or locally).
Check turbine-drhrn pump - FR-IL1 RUNNING step 3d part 2 OPEN stcam supply vahr(s). FR-IL1 IE the pump does NOT start. TlIEN step 3d OPEN the steam supply part 2 RNO isolation ulu:s-3 MSS *MOV17A 3 MSS *MOVl7B , 3 MSS *MOVI7D NOTE The US should send a PEO to US Dispatch an operator to locally restore FR-IL1 ancmpt to establish flow from the AFW llow using Attachment A. if step 3e "B" MDAFW PP since it is nypdred running. Section 2 Page 27 of 39
Title:
LOIT NRC #2 INSTRUCTOR GUIDE Resision: 9 ID: BRC2 Task l Time IDA/Malf Instructor Infonnation/Acthity Assign Expected Response Standani Consp 3OOIH INST MNE If sent to investigate 'B" AWAFW PP, muit 3 minutes and seport the discharge valve is closed and you , cannot open it ' Ile nuy have aln:ady sent a PEO to BOP Check total flow to SGs - GRFATER FR-IL1 investigate the 1DAFW PP trip. 11IAN 530 gm step 3f B00111 INST NOTE 3 min, aner requessed to isrvestigate US Perfinn the applicabic action-the TDAFW PP trip, REFORT that - IE no AITV ikwv is indicated. i you attempted to reset MSV5 but it 311 3 wcn't stav laeched. IhM to stcp 4. RO SIUP all RCPs FR-ILI , stcp 4 l US Tay to E6 Shin FW How to at FR-ILI 12st One SG sicp 5 NOTE lhe "B" condensate pump will be BOP Verify at Icast one cmdensate pump - FR-1 L1 running. RUNNING step Sa , BOP Check FW isolation trip wht:s - FR-1L1 i OPEN step 5b I i Section 2 Pace 28 of 39 , I
Tstle: IDIT NRC #2 INS 1RIXT. OR GUIDE Reision: R IIh NRCZ Task 4 Tinic IDA/Malf Instructor Inferniation/ Activity Assign Expected Response Se W Casup , B00nf INST NOTE If called to Pull the Universal Irgic CREW Perfonn the follocing FR-1L1 Step i Cards. PERFORM the folkming Perfinn the folkming 5.b RNO ; i SEIECT pg 12 on the ISD 1. IF SI E P-14 has actuated. i taminal WIIEN SG levels LESS - TlIAN the P-14 setpsnt. SET lines 1 & 11 (RP;FWP4A TilEN RESET SI AND v
&RP;FWP4B) to FAISE Renxwe universal logic card !'
- A213 fawn both Trains of the I REFOKr the cards have been Solid State Prmcction System !
pulled (3RPS*RAKLOGA and
- 3RPS*RAKLOGB).
If requested to reinsert the cards. wait I min. and then REPORT the 2. RESET F%1 at MB2. I cards haw been reinstalled. Igl ! Norset the values back to tnr. 3. RESET FW1 at MB5.
, 4. Adjust SG feed regulatir.g and I SG foul regulating bypass !
valve controllers to 7xro l ot=put. i 4
- 5. RESET the FW isolation trip I i valms. TilEN OlEN the i I
mlves. I
- 6. IF universal locic card A213 vus removed. hIEN Replace universal logic card A213 in both Trains of the Solid State l Protection System 1 f Stuion 7 i
- Pace 29 of 39
, t
Title:
LOIT NRC #2 INSTRUCIIR GUllE Raision: 9 IIh NRC2 Task Time IDA/Malf Instructor Information/ Activity Assign Expected Reponse Standani Camp (3RPC'RAKLOGA and 3RPS*RAKLOGB).
- 7. IF no FW isoiation trip valve can be opened 11IEN Ihurd to Step 9.
B00111 INST NOTE If called so iwestignee wtw the AWRW will not start, WATT 4-5 min., then REFORT that the ovemment relav on the tweaker has tripgmL , CREW Establish nnin FW fimv using MD FR-IL1 RV pump: step Sc NOTE The MDFWP will not start. BOP 1) START MD FW pump FR-Ill step Sc 1 part 1 i US 1) Proceed to CALTilON prior to FR-Ill sg 7. sg k j lut 1 RNO i i PZR Icvel may decrease offscale low FR-1L1 i to SG deprtaion. step 7 Caution , Section 2 ! Page 30 of 39 i I i
t
~
Title:
. IDIT NRC #2 INSTRUCTOR GUIDE. Resision: R IIh NBCZ Task Time IDA/Malf Instructor Infornistion/ Activity Assign Expected Response Standarti Casup t Following bkr.k of automatic SI FR-Ill actuation. nunual Si actuation may be step 7 rcquired if conditions degrade bevmd Cadion ' operator control. > If REGEN IIX LETDOWN TT31P I11 FR-1Li (395"F) annunciator actuates while step 7 ; using auxiriary spray flow, a charging Caution header loop isolation valve must be opened. I To allmv condenser stcam dump IR-1 t.1 operation to continue during stcp 7 Note dqussurinnkm. ensure that Ixwv- l Ixnv Tavg interkd is bypassed at l 553'F. ! Aller the low Steam Line Pnssure SI IR-ILI ! signal is blocked. MSI will occur if step 7 Note l the high steam pressure rate setpoint j is exceeded. ; I INSTRUCIR NOE 'Ihis is to be the success path fir CREW Try to BesNish Feed Fhm Fmas FR-IL1 restoring SG Fced Flow. Condensate Sgt.ni step 7 [*l l DOP Check condensate pumps - AT FR-ILI ! LEAST ONE RUNNING ' step 7a RO Depressurize RCS to IESS TlIAN FR-ILi 1950 psia sicp 7b t I t Section 2 i Page 31 of 39 !
Title:
_IDIT NRC #2 INS'IRUCTOR GUIDE Resision: R ID:' NRCZ Task-Tiene IDA/Malf Instructor Information/Acthity Assign Expected Response Standant Coenp ,.
- 1) Verify letdown in senice FR-ILI step 7b rut 1
- 2) Establish auxiFiary w FR-ILI Step 7.b2 l l a. O192 charging hcakr '
i isolation uhu (3OIS*MV81% and 3OIS*MV8105) ;
- b. Unlock and OPEN auxiliary spray vahr I (3RCS*AV8145) !
j c. CLOSE charging header loop isolation , vahrs (30IS*AV8146 and 3GIS*AV8147) [ , d. Throttle charging line ' iknv contml whc to
- aljust and maintain 4
auxifiary spray Iknv.
- 3) Place control switches for all FR-1L1 Step PZR heaters to OFF. 7.b.3 i S
Scttion 2 Page 32 of 39 - l
Title:
LOIT NRC EZ INS'IRUC00R GUIIE Revision: 9 ; ID: NRCZ Task Tiene 19A/Malf Instnsetor Inforrnation/Actisity Assign Expected Rgure Standani Cosep
- 4) Check the felkming- FR-1L1 Step 7.b.4 RCS gwessure- LESS llIAN 1950 psia
- i Annunciator MIMD 3-5.
" PRESSURIZER 'IO IN1TERLOCK P-11."- LIT.
Retum to Step 7.b. FR-1LI Step 7.b.4 RNO 1 RO Block SI signals FR-1L1 Step 7.c
. BLOCK Nhin Steam Pressure SI BLOCK PZR Pressure SI Abintain RCS pressure LESS FR-Ill Step TilAN 1950 psia. 7.d j i
i i i i Section ' Ibge 33 of 39 l i l
IIh NRC2 Task Time IDA/Malf Instructor information/ Activity Assign Expected Response Standant Casup ,
.t IKF Verify cinknser steam dump FR-IL1 Step capability- 7.c i
M 3RRE1CiMor "CONTXiNSER AVAll FOR SIM DUMP C-9" j
- (MIMD 5 6) - IlT f
Check MSIVs - AT LEAST - ONE OPEN i NOTE If a MSIJ is received during stcp 7c. Perfixm the fiAlowing- FR-IL1 Step the US should go to 7e RNO and 7.c RNO ;
- continue. 1. CLOSE the MSIVs. !
- 2. Dump stcam to atmosphere i
at maximum rate (MB or krally) to depressurize at least one SG to LESS i 71IAN 550 psig. j 3. IF stcam cm NOT be , dumped to atmosphere. 11IIW Proceed to Step 9.
- 4. Pmcced to Stcp 7.h. r t
i
- Section 2 i Page 34 of 39 i
Title:
IDIT NRC #2 INS'IRUCTOR GUIDE Raision: R ID: NRC2 Task Tinie IDA/Malf Instnscior Infirnestion/ Activity Assign Exgwcted Response S8==derd Casup CLOSE MSIV(s) fbr SG(s) to be FR-Ill Step cmscrved (SGs NOTsekctedfir 7.f dprtssiai alonL
'# m If the crav decides to dump steam IK)P Durnp steam to the condemer to FR-ILi Step from less than all fixr SGs. they will depressurire at Icast one SG to 7.g have to close the MSIVs fir the SGs LESS THAN 550 psig.
they do not want to depnssurize. Possible nmsons to not depressuri7e 1. Establish no demand signal all four SGs are- on steam pressure cmtroller
- 1) Conserve inventory in one or output.
more SGs.
- 2) Minimize RCS cooldown. 2. Transfer condenser steam i dumps to Steam Pressure hkde.
As the RCS cools down the Pir. level 3. Place both condenser
. will decrease and may go off-scale interlock selector switches -
low. ON. The crav should start a second charging pump 4. Ad,iust steam pressure The crev may discuss initiating SI, cmtroller to dump steam to initiation of SI will need to occur if the condenser at nuximum the operators feel the situation is not rate. in their contml (i.e loci will be restored) Section 2 Page 35 of 39
Title:
JDIT NRC #2 INSTRUCTOR GUIDE Raision: 9 ID: NBC2 i Task ; Tinse IDA/3haf Instructor Inforniation/ Activity Assign Expected Reponse Standard Coenp US IF an MSI occurs.11IEN return to IR-1L1 Step Ftc'7.c. 7.g j IK)P Establish condensate 11mv FR-ILI Step alignment to selectcd SQs). 7.h OPEN the 3D FW pump disciurge FR-IL1 Stcp isolation vahrs (3F%%hKW23B 7.ItI and 3F%%NKW23C) locally. (Turbine Bkig. northeast IR-IL1 Step 38") OPEN main fccd pump bypass 7.h.I RNO vah e (3FWS-WX>). . Throttle OPEN the ITV regulating IR-ILi Step bypass valve (s) to sckrted SG(s) 7.h.2 as desinxt I3OP Verify scIccted SG(s)- LESS FR-ILI Step 111AN 550 psig. 7.i Return to Step 7.c. FR-Ill Step 7.I RNO IK)P Maintain selected SG(s) pressure IR-IL1 Step LESS TIIAN 550 psig. 7.j 13OP Maintain condensate 11mv to the IR-ILI Step selected SG(s) using the FW 7.k regulating bypass valw(s). Section 2 Page 36 of 39 u____ .
TWie: IDIT NRCR INSTRUCTOR GUIDE Roision: R ID: NRC2 Task Tinie IDA/Malf instnscior Infernestion/ Activity Assign Expected Response Standard Cosep Oseck SG Encis. FR-1LI Step 8 NOTTI SG NR level will be < 6%. US BOP Verify NR level in at least one SG FR-1L1 Step should perrmn step 8.a. RNO - GREAlliR 11IAN 6%(42% 8.a ADVERSE CmfD. BOP Perfmn the following- FR-ill Step 8.a RNO
- 1. Verify feed limv to at least one SG as Ibilmss-WR level in at least one SG is increasing.
Core Exit TCs are stable or decstasing.
- 2. IF feed flmv to at least one SG is veriikxl. TlIEN Maintain ilmv to restore hR level to GREA11IR TlIAN 6%(42% ADVERSE CBff).
- 3. IF feed flow can NOT be verified.11IEN lhucd to Step 9.
The US slujald snesition to E50.1 US Go to pnnure and step in effect. FR-1Li Step 8.b Section 2 Page 37 of 39
Titic: LOIT NRC #2 INSTRUCTOR GUIDE Resision: 9 l ) ID: NRC2 ! t Task Time IDAS1alf Instructor Information/ Activity Assign Expected Response Standard Comp f IRF121f- STOP THE SI5S10N WHEN THE CREW TRANSTHONS TO EM).1 i [ Irad Evalindor- Request a final cimification from the US. AIFRT- CHARUE 1 based on Red Heat Sink and required Feedwater How Can NOT be established within i 15 Mnutes (RCBI). i ) l e i i f i ) i I i t i Section 2 Ibge 38 of 39 l l I
- i
_ . I
\
SECI1ON 3 i SIMULAIOR EXAM SFQUENCE OF D'INIS
SUMMARY
Title:
1 OIT NRC EXAM 2 ID Number: NRC2 Revision: 0 31hjB *.QA INS 1RUC1DR AIDS DESCRIPT10N MALF. RF.10 i T0 hblf FWO7A Motor driven Feedwater Pump Trip hblf FW2113 "13" Aux Feed Pump disch. valve closed hbif FWl9 TDAFW Pump trip on overspeed Malf - FW33C "C" Concknsate Pump coupling shear Malf RP09A hhnual Reactor Trip Failure - Tmin A hblf RP10A Automatic Reactor Trip Failure Train A hblf RPloll Automatic Reactor Trip Failure - Train 11 T= 'lumover Complete - Malf RXO9A PT455A fails low T= Event I complete = 1 minute MALF FW01 lowering Condenser vacuum T= Event 2 complete + 1 minute Malf FWO3A Trips the "A" Condensate Pump ; 1 Section 3 Page 1 of 1
,) StrI10N 4 VAUDA*I1ON CINXK1hT
Title:
LOIT NRC EXAM 2 ID Number: NRC2 - Revision: 1 Remote functions; yerified by All remote functions contained in the guide are certilled. l Malfpnetkms; i All malfunctions contained in the guide are certilled. j initial Conditions:
'lhe initial comlition(s) contained in the-guide are certilled or have been devekiped from certified ICs in accordance with NSEM-4.02, -
Sinmlntor Oncrating l_imits:
'lhe simulator guide has been evaluated fir ,
openiting limits and'or anomalous response. Test Runt The scenario contained in the guide has been _ J test mn and validated (validation sheet completed, next page)on the simulator. Simulator response is reasonable and as expected. Examination Scenario Review lhe dynamle examination review checklist is complete. Section 4 Page 1 of 3
StrI10N 4 ; OPDtATIONAL EXAM VAUDA110N SiOEI' ' Program
Title:
Licensed Oncrator Recualification Tmining
Title:
1 OIT NRC EXAM 2 - ID Number: NRC2 Revision: 0 By their signature telow, the people acknowledge the confidentiality and validity of the ; material contained within and will not willfully disclose its contents to others ervolled in the i Millstone 'Ihree Licertsed Opemtor Requalification Program. VAUDATED BY: Print Signaturc Date - SM / US ~ / RO / IlOP /
/
/
/
/
/
/
Section 4 Page 2 of 3
SECI1ON 4 DYNAMIC INAMINNI1ON REVIEW C1GCKLEI' Note: 1he following criteria list scenario traits that are numerical in ruture. A second set of numbers indicates a mnge to be met for a set of two scenarios. Quantitative Attributes 6 13. Total nulfunctiorts inserted: 4-W1014 3 14. Malfunctions that occur aller EOP entry: 1-4/3-6 2 15. Abnonnal Events: 1-2/23 2 16. Major Tnutsients: 1-2/23 1 17. EOPs used beyond prinvuy semm response EOP: 13/3 5 0 18. EOP Contingency Procedturs used: 0-3/13 60 19. Approxinute scenario nui time: 45-60 minutes (one scen:vio nuy approach 90 minutes) 60 % 20. EOP mn time: 40 70% of scenario mn time 2 21. Crew Critical Tasks: 25/58 yes 22. Technical Specifications are excreised during the test COMMENIS: Section 4 Page 3 of 3 m
SirI10N 5 RFJERENOS AND CRTI1CALTASK'IRACKLNG
Title:
1 OIT NRC liXAM 2 1D Number: NRC2 Revision: O
- l.
References:
AOP 357), Instmment Failure Response, attachment D. AOP 3559, - Loss of Condenser Vacuum AOP 3575, Rapid Downpower EOP 35 E-0, Reactor Trip or Safety injection. EOP 35 ES-0,1, Rx Trip Resportse j EOP 35 FR il.1 Response to less of Secondary lleat Sink EOP*ERO_EXE Westinghouse Owners Group Executive Document EOP' Step _ DOC MP3 step deviation IArument EOP*ER0_1IP Westinghouse Owners Group llackground Document EPIP*EPIP4400 Event Assessment, Classification & Reportability NUREG'1021 n.T 7 Examiners Starxiards
- 11. Qitical Tasks Covered in this Test:
NOIE : Critical Tasks are marked by an l*] within guide CRITICAL CRITICAL. TASK K/A >/= 3.0 13 ASIS FOR SFI FCTION TASK # DESCRIP110N Exams only Section 5 Page 1 of 2
E-0--A Manually trip the reactor from 000-029 Failun. to nunually trip the rector the control room prior to FA1.08 causes a challenge to the suberiticality leaving E-0, step 1. 4.5/4.5 CSF beyond that irrepambly introduced 000-029 by the postulated conditions. SGA.10 Additionally, it constitutes an " incorrect 4.5/4.5 perfomtance that necessitates the crew 000-029 taking compensating action which SGA.12 complicates the event mitigation stmtegy 4.1/4.2 and demonstmtes the inability by the l crew to recognize a failure of the l automatic actuation of the RPS." l l FRil.1-E Establish the minimum 059-000 Because the secondary heat sink is required feedwater flow mte to A2.01 required but not satisflictorily pmvidal, the SG's before SG dqout. 3.4/3.6 the RCS heats up. If feedwater flow rate commensurate with core decay heat is not established, the heat sink CSF is challenged. With continued insullicient feedwater flow, the SG's dqout, causing an RCS presstur increase that open the PZR PORVs. The open PORVs create a snull break LOCA that eventually challenges the core cooling CSF. Ultinutely, the fuel nutrix/ clad is challenged. Section 5 Page 2 of 2
SIrnON 6 SCENARIO INmAL 00NDmONS l Reactor Power: 100 % Opemting llistory: 250 days on line RCS Boron: 988 ppm l Core Bumup: 10,500 MWDhm) Condertsate Demins: 7 IN SERVICE Evolutioris in Progniss: NONE ,. Major Equipment OOS: * "A" Service Water Pump for preventive maintenance.
* [
"A" MDAFW Pump for motor bearing replacement. '
"B" Stator Cooling Pump for preventive maintenance.
Crew Instmetions: Maintain pn:sent plant conditions. Perfomt Steam Genemtor _ > Blowdosm valve cycle as per Sp 3670.4 (Routine PMs), step 4.1.3. - Plant /simnihtor Difrerences: Rad Monitor llistorical Data--Simulator Rad Monitor historical data not valid prior to the beginning of this exercise. a l Reactor Makeup System batch counters different fmm plant system. (If required to perfonn a makeup evolution, refer to the RO procedure eart for setting the Batch Counter.) a Main steam atmospheric dump valve controller for the "B" and "C" S/G is ditTerent : from plant. , Section 6 Page1of1
. - ~ _
SIMULNIOR EXAM GUIDE APPROVAL SHEET 1.
Title:
- LOIT NRC #3 1D Number: NRG Resision: 0 11.- Initiated: J. William C6td 5/2897 Ikveloper lhte 1 111. Reviewed:- : r i ' Reviewer lhte , I t IV. Approved: Operations Manager lhte i Operator Training Supenisor Date i-i 4 'I V t
--1+~-- r-y ee n ,r,mm..,,,- .,4--y.-r ,m-*-,,---r- & , om m., p ro v,n w , - --pwp:*- ---e -a y-4..',.mm,~-.zm-
- c. -
,,m,,b,c,,y.,,,w ,-w--,--y-w,-. o. ,E v e-- -- , > I r,[-
SIMULATOR EXAM GUIDE Tant i OF CONTENTS SEC110NS LIS111D IN ORDER
- 1. Exam Oveniew i
- 2. Instructor Guide
- 3. Sequence of Events Summary
- 4. Validation Checklist
- 5. Reference and Critical Task Tracking Fonu
- 6. Scenario Initial Conditions Sheu i
e
SECI10N 1 i EXAM OVERVIEW - i L
Title:
. LOIT NRC #3
-ID Number: NRC3 Revision: 0
- 1. Exam lkief:
1he crew will conduct the downpower to 90% pov All the necessary preliminary checks of the motor driven feafwater pump will be completed and , the crew will make the swap of the feedwater pumps. During the downpower i the "D" S/G level transmitter will fail to 0% over 3 minutes.1he gerators ! should enter AOP 3571 to address the failed instrument. Once the faikxl instrunwnt actions are complete, the crew should complete the downpower. - j! f A When the downpower is complded, the enny will start the "C" Condensate l pump in preparatiom of transfering feed pumps. Afle.- the "C" Condensate pump is started, a power range channel will slowly fail causing the rod contml , system to move mds.1he operators will take manual rod control and will be able to bypass the affected channel. When rod control is retumed to automatic a continuous tal inseition begins. The operators will need to trip the reactor to stop the insertion. When the reactor trips, the turbire will fail to trip nor can it be run back. The failed turbine trip will cause an excessis e cooldown and result in a safety injection. The operator will need to close the MSIVs to stop the steam flow. lhe shock of the MSIVs closing will cause an unisolable steamline break inside containment lhe leak will stcrt slowly and upon exiting E-0, the leak will rapidly escalate and force an Orange Path on C1Mr Integrity, When containment pressure reaches 23 psia. the automatic CDA will not occur and the CDA pushbuttons will fail to actuate.. -lhe enny will need to transition to FR-Z.1, Response to liigh CTMT Pressure, and manually actuate CDA.
- Initial Conditions: 1he plant is at 100% power. Excessive vibration exists on the "B" 1DFWP. The enny will be directed to rrduce power to 90% at 1/2%
per minute and swap feed water pumps. Tumover: The enny will be provided the MP3 simulator standard tumover sheet which will din:ct them to reduce power to 90% at a rate of 1/2% per minute. The following equipment will be out of senice: "A" senice water pump, "A" motor driven AFW oump and the "B" stator cooling pump. There are thunderstonn wamings for tie next 4-6 hours.
- 2. Plant / Simulator differences that may affect the scenario are: None.
- 3. Duration of Session: I hour t -
Section 1 Page 1 of 2
SECTION 2 INSTRUCTOR GUIDE I
, J 'litle: LQlT NRC #3 1D Number: NRG Resision: .n.
All Control Room Conduct. Onerations and Communications shall be in accordance COP 200.1.Conect of Oncrations. and OP 3260. Unit 3 Coneet of Onerations. 4
" Review the Simulator Operating Limits (design limits of plant) and the Simulator-Modeling Limitations and Anomalous Response List prior to performing this training <
scenario on the simulator. 'The instructor should be aware if any of these limitations may be exceeded." (NSEM 6.02)- J i - 4 1 Section 2 Page 1 of 40
. - - - . - - . ~ -- - . - - - . - - ..
SIMULATOR PROBIFAE DURING ELGE lt is the responsibility of the Instructors in the simulator to insure that exam interruptions have a minimum negative impact an the Crew and the examinations we provide. Be aware that at all times the Operators should treat the simulator as ifit were the plant and you too should treat it as much like the plant as possible when they are in the simulator. As soon as the Instructors are aware of a simulator problem that will adversely affect the exam in progress (computer fault, etc.) the Instructor should:
- 1. Place the simulator in FREEZE if possible.
- 2. Announce to the Crew that there is a simulator problem.
- 3. Request that the Crew leave the simulator control room. (The Crew should leave the simulator for problems which involve major switch alignments).
- 4. Deal with the problem (reboot, call STSB, etc.)
- 5. After the Instructors believe the simulator is restored to senice, the Crew should be told how the exam will continue. If it is possible and felt to be acceptable tc the evaluators, the examination can begin where it len off with an update on plant pamrr.eters and each Crew member is prepared to restart. If the examination will not begin where it left off, the crew should be told how and where the exam will begin again.
- 6. Once the Crew has been told how and where the exam will begin, have the crew conduct a brief so that the Instructor and evaluators can insure that the crew has all the necessary information to continue with the scenario.
- 7. Once all Crew members, Instructors and evaluators are satisfied that they have the necessaiy information to continue the scenario, place the simulator in RUN and announce to the Crew tha+ you have continued the evaluation session.
Section 2 Page 2 of 40
Title:
LOIT NRC #3 INSTRUCTOR GUIDE Raision: 11 ID: NRC3 Task Time IDA/Malf Instructor Information/ Activity Assign Expected Response Standard Comp EVIAT#0
'ITHI: INTHAL SEIUP Setup Imtmetiom:
Enter IDT as folkms : At any XIliRM windmv. type <idt> When the SUN asks fir an executive type UEXEC or RTEXEC? cter <r>: this will bring up a blank idt page. To go to a presiously saved idt file type <rtad> at the prompt When the SUN asks ihr a file name of the file you wish to view type in the m=q=iate file name-
'Ihe old "Landon" files are as follows:
Old ISD pages 1-8 are idt file OIS Old ISD pages 9-16 are idt file OPS 1 Old ISD pages 17-19 are idt file OIS2 o IE the step counters are at/near 000, nIEN . REMOVE the SlliP COUNiliR OVERRIDE, allow the counters to step out during the IC reset. Reset to K)14. REINSTATE the step counter OVERRIDE Place Simulator to RUN RESET the time constant on the PZR level controller by PLACING the PZR Master Irvel controller in MANUAL - then return the Controller to AUIO. Set the SlliP COUNHIRS PLACE the Main Turbine on the LOAD LIMITER Verify annunciator, "COMPUITIR FAILURE" (MIMC,1-11), is NOT LIT. Place MOL Curve Book in ShelfIbr Opemtor use. Remove other Curve Books from the floor. Cicar the DCS Alarms Reset the Rad Monitor CMirUt Console by Dernessing the " Status Grid" imtton twice. Section 2 Page 3 of 40
Title:
LOIT NRC #3 INSTRUCTOR GUIDE Revision 9 ID: NRC3 , Task Time IDA/Malf Instructor Information/ Activity Assign Expected Response Standard Comp PIACE ' HIE FOtMMMNG FRIUll31 EAT IN I'IL-F;1uipment OOS: "A" Sen' ice Water Pump "A" Motor Driven AFW Pump "B" Stator Water Cooling Pump Insert applicable CREW EXAM Tape into the VCR. Synchronize the MONITOR Time Display with BIG BEN. At MB5 place the MDFP aux oil pump on (FWL-P2). Initial Malfimetiom /lOs/IDAs: T-0 RP06A Failure of CDA to auto actuate Tmin "A" T-0 RP06B Failure of CDA to auto actuate Train "B" T4) TC03 Turbine Fails to Trip T-0 TC04 Turbine Fails to runback - T4) RP08A Train "A" MSI Auto Failure T4) RP08B Train "B" MSI Auto Failure T-0 I /0 under RP he:xling PB2-3 ADS-CDA value = "Off" CDA actuation pushbutton failure T4) 1/O under RP heading PB3-3 ADS-CDA value = "OFF" CDA actuation pushbutton failun: leal Examiner. Refer to the ' Briefing Script for the OperAiormd Exam"and brief the crew. Ihth Imtneton Commence Recording Sinadatorsession [hth Imtnrtor. It form the ennv timmver(Initial Conditiom page at end of II) with the crew. Section 2 Page 4 of 40 i
Title:
LOIT NRC #3 INSTRUCTOR GUIDE Resision: D ID: NRQ Task Time IDA/Malf Instructor Information/ Activity Assign Expected Respmse Standard Comp Event 1: Shift of the Main Feedwater finnps. , CREW Enter AOP 3575, Rapid d(mnpmer. AOP 3575 Entry i conditions AOP 3575 Rev. 5 CREW Determine 1%rr Reduction Rate AOP 3575 (Wmin). Step I US Check desinxi pmer reduction mic - AOP 3575 LESS lllAN OR EQUAL 10 Step 1.a 5Wmin. NOT requested by CONVEX US Check pmtr reduction a CONVEX AOP 3575 requested Emergeirr Genension Stcp 1.b Reductiort Ops Management order uns to US Perform the Ibikming: AOP 3575 perfbnn at 1/2% per minute Step 1.b
- 1) Determine pmtr reduction mte RNO using Table.
- 2) Pnuut to Step 2.
US Oneck Rod Control in AUTO. AOP 3575 Step 2 Only lowering power to 90*i Rod US If during the performance of this AOP 3575 insertion limit should not be procedure the Rod Insertion Im-Io Step 3 reached Limit is reached, Go to AOP 3566, CAUflON Section 2 Page 5 of 40
Title:
IDIT NRC11 . INSTRfJCFOR GUIDE Resision: 9 ID: NRQ Task Time IDA/Malf ~ Instructor Information/Actisity Assign Expected Response Standarti Comp Immediate Ikwation. NUF CONVEX Requested CREW Ifload reduction is a CONVEX AOP 3575 reytusted emergency genemtion Step i reduction. the following apply- NOE lhe Unit i Shill Manager will determine how the hxxi reduction will be shared among the Units. DO NOT stop a CONVEX
" Emergency I2xxi Reduction" ,
request due to AFD exceeding the target band. 1he load reduction must be completed within 15 minutes of notification. IMXIIll NOTE >> AT cither 95% poweror Examiner's CREW Initinde load Redirtion. AOP 3575 cie, initiate Eve:W 2, Failine of 'U" Step 3 S/G level tr:msmitter(go to page 12). US Check pourr nxtuction a CONVEX AOP 3575 rcqt*.-c.al emergency generation Step 3.a reduc;kn Section 2 Page 6 of 40
Title:
LOIT NRC #3 INSTRUCTOR GUIDE Revision: 9 lih NRQ Task Time IDA/Malf Instructor Information/ Activity Assign Expected Response Standani Cosep 1/2% per minute unuld be ~ 6 MWE US Infixm CONVEX ofload reduction AOP 3575
/ min mte (Mwe/ min) and final Muc Ictel. Step 3.a RNO Not in Standby BOP Check turbine NOT in STANDBY AOP 3575 LOAD control. Step 3.b i BOP Check LOAD LIMIT LIMITING light AOP 3575 ,
- LIT. Step 3.c
'Ihe shilfling to lead Set rxxmally BOP Intermittently Press DECREASE AOP 3575 sheds about 15 to 30 MWe. The LOAD pushbutton until LOAD LIMIT Step 3.d crew should monitor nxis as they LIMIllNG light - NOT LIT.
begin to insert in auto. BOP Rotate LOAD LIMIT SET adjust AOP 3575 know at lecst one full tum in mise Step 3.e direction. BOP Select DECREASE LOADING AOP 3575 RAlli to ON. Step 3.f 1/2% per minute BOP Select LOAD RAlli LIMIT AOP 3575 WMIN to required poutr Step 3.g nxluction mte (Wmin). ;
.9.x 1200 = 1080 MWE BOP Utilizing DECREASE LOAD AOP 3575 pushbutton, Adjust LOAD SET to Step 3.h desinxi final Mwe (power level).
i Section 2 Page 7 of 40
Title:
LOIT NRC #3 INSTRUCIDR GUIDE Revision: 9 ID: NRQ Task Time IDA/Malf Instructor Information/ Activity Assign Expected Response Standarti Comp- i BOP Maintain initial MVAR loading AOP 3575 during gymtr reduction unless Step 3.i - directed otherwise. US If at any time the p(mtr reduction AOP 3575 mte must be changed, retum to Step 4 Step 1. NOTE US Verify Ibwer Reduction Race - AOP 3575 GRENIIR'IllAN OR EQUAL Step 4
'IO 3WMIN.
US Proceed to Step 7. AOP 3575 Step 4 RNO US Ikric acid total volume addition AOP 3575 and flow rates are based on Step 7 approximations. Adjustments NOTE should be made to the volume addition or flow rate as necessary to ensure the reactor reaches the desired end state of: Tavg on pmgmm > Rods above the Rod Insertion Limit AFD on or above the *.arget value RO Align RG Makeup Spiem For AOP 3575 Horation. Step 7 Section 2 Page 8 of 40
Title:
LOIT NRC #3 INSTRUCTOR GUIDE Revision: !! ?D: NRC3 Task Time IDA/Malf Instructor Infonnation/ Activity Assign Expected Resporte Standant Comp 10 x 15 = 150 gallons US/RO Determine requin:d boric acid AOP 3575 addition by multiplying Step 7.a total pmer change (4%) tw 15 (gal %) = gal 150 gallons RO Sct the boric acid hatch counter to AOP 3575 , total galkms of boric acid required. Step 7.b RG'US Check omtr reduction rate - AT AOP 3575 0.5%' min. Step 7.c RO Adjust boric acid blend flow AOP 3575
, controller pot setting to 1.9 (7.5 Step 7.d gpm).
RO Place reactor coolant makeup AOP 3575 contrel mode switch to 13 ORA'E. Step 7.e RO Select START on reactor coolant AOP 3575 makeup start switch. Step 7.f RO Energize all PZR heaters. AOP 3575 Step 7.g NO action required. this will be done I)OP Reduce Secam Supply To 'Ihe AOP 3575 automatically. IERs, Using OP 3317, Rehest and Step 8 Moisture Sepanwor, Section 7.8. US Check If RG Sampic Is Required. AOP 3575 Stcp 9 Scction 2 Page 9 of 40
Title:
LOIT NRC #3 INSTRUCTOR GUIDE Revision: 0 ID: NRC3 Task Time IDA/Malf Instructor Information/ Activity Assign Expected Response Standarvi Comp NO sample will be rujuired. US Verify clunge in Reactor Power - AOP 3575 GREATER 'UIAN 15% IN ONE Step 9.a IIOUR. US Pmceed to Step 10. AOP 3575 Step 9.a RNO US Verify Target IbwerIrvel - IJ3S AOP 3575 lliAN 50% Step 10 HOOrHI NOR>> At examiners cue or power reduction CREW Continue power nxluction to AOP 3575 complete, Go desired target pourr level. Step 10 To EverW 2, Page 12. RNO WIIEN final powtr level is reached,11IEN Proceed to Step 20. CREW Oneck Plant Stahs. AOP 3575 Step 20 RO Verify - AT TARGET POWER AOP 3575 LEVEL Step 20_a RO Ikrate or Dilute as necessary to AOP 3575 mintain AFD as close to the target Step 20.b value as possible while maintaining rods above the Rod Insertion Limit. US Request Chemistry obtain RCS AOP 3575 bonm sampics. Step 20.c Section 2 Page 10 of 40
Title:
LOIT NRC #3 INSTRUCTOR GUIDE Resision: Q IIh NRC3 Task Time IDA/Malf Instructor Information/ Activity Assign Expected Response Standard Comp RO Align RCS makeup for automatic AOP 3575 operation using OP 3304C, Primary Step 20.d Makeup and Chemical Addition, section 7.2. Should not be necessary. HOP Select RFSET on the steam dump AOP 3575 nule selector switch (ifnyfulnv/). Step 20.c US lYrfonn the Folkming: AOP 3575 Step 21 US Check power n: duction is a AOP 3575 CONVEX trquested emergency Step 21.a generation reduction. US Report completion and amount of. AOP 3575 pourr reduction to CONVEX and Step 22.a Proceed to Step 22. RNO US Report completion and amount of AOP 3575 pourr reduction to Unit 1 Shill Step 22.b Manager. CREW Continue with Nonmi Plant Operatiom Using Applicable Plant Phwkses. I Section 2 Page11 of40
Title:
LOIT NRC #3. INSTRUCTOR CUIDE Revision: 11 ID: NRQ Task Time IDA/Malf Instructor Information/ Activity Assign Expected Response Standani Comp EVENT 2: Slow Faihme of 'D"S/G tevel Trammitter T= Rx Ibwer RX12P S/G 'D" NR level indicator fails to US Order BOP to take manual control = 95% or sev = 0.0% zem, (L1554) of"D" S/G FRV Etaniners ramp = 180 Cue secomh CREW Ente AOP 3571 AOP 3571 Entry Conditions "D" FRV is affected contmlier CREW Determine the initiating parameter AOP 3571 and place the alTected controller in step 1 MANUAL CREW Stabilize the plant pammeters. AOP 3571 step 2 BOP Verify the afTected SG foul AOP 3571 regulating valve in MANUAL Att.N step 1 US & BOP may discuss and decide BOP Verify the feed pump speed AOP 3571 to leave controller in auto contmilcr is in MANUAL Att.N step 2 BOP - Restore SG level to normal. AOP 3571 Att.N s:cp 3
'The crew should select channel 2 for BOP Defeat the failed channel input by AOP 3571 the "D" S/G NR level. selecting the altemate channel on Att.N step 4 Section 2 Page 12 of 40
Title:
LOIT NRC #3 INSTRUCTOR GUIDE Revision: 11 ID: NRC3 Task , Time IDA/Malf Instructor Information/ Activity Assign Expected Response Standard Comp the level selector. BOP When SG level is n: stored and AOP 3571 feed / steam flow are matched, Att.N step 5 perfirm the following- i Restore feed pump spet4 control to normal DP (Pmgmm- 40-140 psid) and place the feed pump speed , controllerin AUTO. Place the afTected steam generator feed n gulating valve controller in AUIO. CREW When conditions have stabilimi, AOP 3571 obsen'e MB annunciators arxi Att.N step 6 pammeters. Immediately rtyxt any unexpected or unexplained conditions to the Shill Manager. LT554, IWection Set 1 US Determine which Reactor AOP 3571 IMection System bistabic(s) Att.N step 7 raguire(s) tripping-US Place a check mark in the box AOP 3571 above the appropiate channel that Att N requires tripping on the last pages step 7a of this Attachment. Section 2 Page 13 of 40
Title:
IDIT NRC #3 INSTRUCTOR GUIDE Resision: D ID: NRC3 Task Time IDA/Malf Instructor Information/ Activity Assign Expected Response Standard Comp 33.1, function 13. action 6 SM Refer to Technical Specification AOP 3571 33.2, function 5h & 6c action 20,21 33.1,33.2. 333.5 and 333.6. Att.N step 7b CREW Check the existing bistable status AOP 3571 to ensure a reactor trip will not Att.N occur nim the failed channel is step 7c tripped. T= Request to RXRIM 'OPEN" Protection S*.t I Door SM/ Request the I&C IXpartment trip AOP 3571 Trip B/Ss RXR81 "IRIP" P-14, LS/554B US the ypqWate bistables using Att.N RXR134 "IRIP"In Ifvel Rx Trip LS/554A Attachment N and Attachment R. step 7d RXR106 'CIDSE" Protection Set 1 Door RO Verify the appropriate bistable AOP 3571 status lights are lit. Att.N step 7e SM' Request I&C Department perform AOP 3571 - US corrective maintenance on failed Att.N step 8 instmment. t-Section 2 Page 14 of 40
r-
Title:
LOIT NRC #3 INSTRUCTOR GUIDE Resision: ' 9 ID: NRO Task Time IDA/Malf Instructor Infonnation/Actisity Assign Expected Response Standant Comp T= Downpowercomplete EVINT 3: Start "C" Condensate Pump in preparation to transfer Feed Pumps.
- 'lhe "C" pump should be started IAW OP 3319A. section 7.9.1.
T= when IMR34 'Ihis will open the Condensate pp requested 'OPEN" discharge bypass valves,3CNM-V39. V44, V49. Proceed to Event 4 aller "C" Condensate pump iis running. . EVENT 4: NwerRange Channel Faihme T= 'C' CorxL NIO9A Nwer Range Omnnel 41 lower PP is naning sev=100% detector fails high. 30 sec ramp Rod Control will be the alTected CREW Determine the initiating pammeter AOP 3571 controller. Rods should be placed in and place the afRued controller in step 1 Manual MANUAL Section 2 Page 15 of 40
Title:
IDIT NRC #3 INSTRUCTOR GU'IDE ' flesision: . R ID: NRQ Task Time IDA/Malf - Instructor Information/ Activity Assign Expected Response Standarti Cosnp CREW Stabilize the plant parameters. AOP 3571 step 2 RO Defeat the failed channel input AOP 3571 Att.D step I RO At the deicctor current compamtor ADP 3571 dmwer, tum the folkming switches Att.D g to the failed channel: Rc.i Stop s:cp la Bypass, Upper Section, I mwr Section, Power Mismatch Bypass. RO At the comparator and rate drmwr, AOP 3571 tum the following switch to the Att.U failed channcI: Comparator step lb Channel Defeat. Section 2 Page 16 of 40
- 3.
w-+ y e-_
Title:
IDIT NRC #3 INSTRUCTOR GUIDE Revision:' D ID: NRO Task Time IDA/Malf instructor Information/ Activity Assign Expected Response Standant Comp T= Rmk RD02(I) When the RO places rod co Wml in RO Restore Tor - T,,r error to within AOP 3571 placed in when Rml "AUIU', INfnATE EVENT 5, i "F and place nxi contml in Att.D step 2 AtWo Selector Cordirmus Inward Rod Motion. (On autmutic. , Switch ' MODCOMP select ' ROD , taken to SUPERVISION' to determine hxntion
'AtWo'. of nxis.)
Erwer RD02(II) if innk D irserts to 115 steps i trfore the crew trips the [dard. EVENT 5: Contiinas krward Rod Motion. Crew shoe *
- attempt to place Rai CREW Stabilize Plant Conditions AOP 3552 contml in MANUAL Crnv may not Step I .
enter AOP 3552, Rod Contml system malfunction. Crav may elect to trip plant based on inability to control rul movement. Pmcedure is listed as guidance for the situation. RO Place control rod bank SEL switch AOP 3552 in MAN Step I.a RO Verify - NO RODS MOVING AOP 3552 Step 1.b Section 2 Page 17 of 40
Title:
LQLT NRC #3 INSTRUCTOR GUIDE Resision: 9 iD: NRCI Task Time IDA/Malf Instructor Information/ Activity Assign Expected Response Standard Comp US should go to " Master Silence" CREW- 1 RIP the reactor and Go to E-0 AOP 3552 Reactor Trip or Safety Injection. Step 1.b RNO US - Foldout page must be open E-0, Step 1. NOTII IKXJHI You mist watch CIMF US - ADVERSE CfMr defined Pressaire to enstne CDA does as GREA'ITIR llIAN 180'F NOT activate until the crew or GREAT 1" llIAN 10' g, ; g */w in cv.ainiartt. 'Ilu,s 7 t t "on applies to this and , all subsequent EOPs. The goal is to luive the crew US - The iractor can be aware of a proNem with interpreted as " tripped" and the operator shall pmcced to something pressinizing CIAH, Ind NOTinitiate a CDA taWil a transition to FR-Z,1 wondd be ~ tk'h rce l bullet substeps of step I are reqtsired. determined to be satisfied. ! T= 5EIVs MS01B 'B"S/G steam line fait imide RO Verify HeactorTrip E-0, Step 1 Gosed sev = 7% CIMF upon SEIV Ooswe.This leak rany =600 vary initially go undetected while the secomh crew is progressing thrmgh EA). Section 2 ; Page 18 of 40
Title:
' LOIT NRC #3 INSTRUCTOR GUIDE Resision: 11 ID: NRQ Task Time IDA/Malf Instructor information/ Activity Assign Expected Response Standant Coenp Check reactor trip and bypass bn:akers - OPEN Check rod bottom lights - LIT Check neutnm flux - DECREASING IK)P Verify Turbine Trip E-0. Step 2 [*l Turbine will not trip Check all turbine stop valves - E-0. Step 2.a CLOSED TRIP the turbine. E-0, Step 2.1. RNO Crov uill attempt runback and then IE the turbine will NOT trip, will need to close the MSIVs. 111EN Runback the turbine to close the control vahrs. IE the turbine can NOT be runback TIIEN CLOSE the MSIVs and MSIV bypass valves. BOP Verify Pbwerto AC E.a.g&y E-0. Step 3 Basses IK)P Check busses 34C and 34D - AT E-0. Step 3.a LEAST ONE ENERGI7ED Section 2 Page 19 of 40
Title:
LOIT NRC #3 INSTRUCTOR GUIDE Resision: 9 -ID: NRC3 Task Time IDA/Malf Instructor Information/ Activity Assign Expected Response Standard Consp IK)P Check busses 34C and 34D - E-0. Step 3.b IDHI ENERG17ED NO'IF2> SI will have actuated on the US Check If SI is Actumed E-0, Step 4 cooldown associated with the failure of the turbine to trip. Upon the ch> sun: of the steam stops. RO Verify Safety Injection Actuation EOP 35 E-0, annunciator - LIT Step 4.a US - Steps 5 through 14 may be E-0. Step 5, performed in any order. NOTE US - RPCCW valve checks may be performed in any order prior to step 14 completion. RO Verify Senice Water Pumps - AT E-0, Step 5 IEAST ONE PER1 RAIN RUNNING CDA will not actuate automatically RO Verify Twu RFOCW Pumps - ONE E-0. Step 6 (should NOT be required at this PER TR\lN RUNNING point). Section 2 Page 20 of 40
Tit'e: LOLT NRC #3 INSTRUCTOR GUIDE Resision: 9 ID: NRC3 Task Time IDA/Malf Insiructor Information/ Activity Assign Expected Response Standard Cosap l l RO Verify ECG Pumps Running E-0. Step 7 l i l Check Si pumps - RUNNING l l Check RIIR pumps - RUNNING Check twu charging pumps
- RUNNING BOP Verify ABV Pumps Running E-0 Step 8 BOP Check MD pumps - RUNNING E-0, Step 8.a IK)P Check turbine - driven pump - E-0, Step 8.b RUNNING IF NECESSARY BOP Verify RV isolation E-0 Step 9 Check SG feed regulating valves - CLOSED Check SG feed regulating bypass valves - CLOSED Check FW isolation trip valves - CLOSED Check MD FW pump -
STOPPED Section 2 Page 21 of 43
Title:
IDIT NRC #3 INSTRUCTOR GUIDE . Revision:- H ID: NRC3 Task Time IDNMalf Instnwtor Information/ Activity Assign Espected Response Standant Comp Check TD IV pumps - TRIPPED Check SG blondosm isolation valves - CLOSED
- Check SG bhnydown sample isolation vahts -
CLOSED Check SG chemical feed isolation valves - CIDSED MSIVs utw previously closed. BOP Oneck If min Skam Unes Shonid E-0. Step 10 Be Isolated CTMF Pressum will be increasing RO Check Ctmt prussine GREATTR E-0 Step 10.a but less than 18 psia. 11IAN 18 psia BOP / M RO any SG pressure 113S T11AN 660 psig May perform RNO if CIMF pressure US DO NOT perform step 10b. E-0. Step has not reached the setpoint Proceed to step 11 10.a. RNO BOP Verify MSlVs and MSIV bypass E-0, Step 10.b vahes - CLOSED CDA will be required. eventually Section 2 Page 22 of 40
Title:
LOIT NRC #3 INSTRUCTOR GUIDE Resision: 9 ID:- NRC3 Task Time IDA/Malf Instructor Information/ Activity Assign Expected Response Standard Comp Crew may pmcced past this step and pmbably NOT retum because they will use FR-7.1. Should not be required at this point RO Oneck if CDA Requiva(E-0. Step 11) l*) RO Check Ctmt pnssure is GREAlliR E-0. Step 11.a
'llIAN 23 psia DR Ctmt spray is initiated US IX) NOT perform steps Ilb.1Ic, E-0. Step 11.a.
and Iid. Proceed to step 12. RNO BOP Verify CAR Fans Operating In E-0. Step 12 E..- r, .-y Mode US Check CAR fan status: E-0, Step 12.a 13OP - CAR fans A and B - RUNNING 13OP - CAR fan C - STUPPED Section 2 Page 23 of 40
Titleg IDIT NRC #3 INSTRUCFOR GUIDE Revision: H ID: NRC3 Task Time IDA/Malf; Instructor Infonnation/Acthity Assign Expected Response Standard Comp US E CDA is actuated,11IEN E-0. Step thxred to next immediate action 12.a. RNO and do NOT perform steps 12b and 12c. RO Verify CIA E-0. Step 13 RO Orck ESF Gmup 2 status columns E-0. Step 13.a 2 through 10 - LIT RO Verify PmperIBFStatis Planel E-0 Step 14 Indication RO - Verify ESF Group 1 lights - OFF RO - Verify ESF Group'2 lights - LIT RO - E Main Steam Line Isolation has occtnTed, llIEN Verify ESF Gmup 3 . lights - LIT RO -- E CDA has occtumi, lllEN Verify ESF Group 4 lights - LIT Section 2 Page 24 of40
Title:
LOIT NRC #3 INSTRUCTOR GUIDE Revision: M ID: NRC3 Task Time - IDA/Malf Instructor Information/Activ;ty Assign Expected Response Standani - Comp CREW should perfonn a short brief and come out of" Master Silence" ADVERSE Conditions may exist on RO Determine if ADVERSE CIMF E-0, Step 15 CIMF Tempemture Conditiors Exist RO - Ctmt temperaturt GRENER TilAN 180"F M Ctmt radiation GREATER lllAN 10"/u CREW DO NOT use ADVERSE CIMF E-0, Step 15, pammeters. RNO US To pmvide adequate ECCS flow, E-0. Step 16, RCS subcooling and PZR Icvel Caution should be monitmxi to ensure that the charging pump is manually restarted if RCS subcooling based on core exit ICs is less than 32"F or P7R level is less tlun 15% RO Verify FLCS How E-0, Step 16 RO Check charging pump flow E-0 Step 16.a indicator - FLOW CONSISlTNT Wrfil RCS PRFSSURE Section 2 Page 25 of 40
Title:
IDIT NRC #3 INSTRUC 3% GUIDE - Revision: 11 ID: NRC3 Task Time iDAStaff Instructos Information/ Activity Assign Expected Response Standard ' Comp' < RO Check RCS pn:ssure - LESS E-0, Step 16.b TIIAN 1650 psia (1950 psia ADVDISE CIMF) , i US Check if charging pump should be E-0. Step stopptM: IE the following 16.b, RNO conditions exist: RO Ik>th charging pumps running. Crew Should be able to stop one of RO RCS subcooling lxtsed on core the tun mnning ClIS Pumps exist TCs GREATER 11IAN 32"F. , BOP Secondary heat sink-Total feed flow to SGs is GREATER TIIAN 530 , gpm. DE NR Icvel in at least one SG is GREATER 11IAN 6% RO RCS pressure is stable or increasing. RO P7J1 level is GREATER 11IAN 15 % US TllEN Section 2 Page 26 of 40
Title:
LOIT NRC #3 INSTRUCTOR GUIDE Revision: 9 ID: NRG Task Time IDA/Malf Instrwtor Information/ Activity Assign Expected Response Standard Comp ' RO RESET SI. RO STOP all hit one ciurging pump and Place in AUTO. US Ihul to step 17. 130P Verify Total AFW Fkm - E-0. Step 17 GREATTR111AN 530 gpm 13OP Verify AFWValve Alignment- E-0. Step 18 PROPER EMERGENG' .
, AUGNMENT RO Verify EOCS Valve Alignment - E-0, Step 19 PROPER EMERGDKY AUGNMENT US Oseck Plant Stahs E-0, Step 20 BOOTil Report as Secisity Shift Supervisor SM Verify SLCRS doors - CLOSED E-0, Step 20.a that all Unit 3 SifRS doors are ekmL CBI will not be required until C1MF CREW Check if CBI actuated E-0, Step 20.b Pressure exceeds 18 psia.
- 1) CBI annunciator- LIT RO Check if CBI is required E-0. Step 20.b. RNO Section 2 Iage 27 of 40
Title:
' LOIT NRC #3 INSTRUCTOR CUIDE Revision: D ID: NRO Task Time IDA/Malf instructor Information/ Activity Assign Expected Response Standant Comp RO - Ctmt pressun- GREAlliR 11IAN 18 psia m Contml Building mdiation monitor in alarm 2 SI manually actuated US IE CBI required,11IEN Initiate CBI. IE CBI is NQI required,11IEN Pmceed to step 21. US Geck RG Tempendure E-0 Step 21 NUE lhe failun of the turbine to trip RO Verify RCS cold leg WR E-0, Step 21.a probably nxiuced tempemtun:s below tempcmture - STABLE AT OR 560'F. 1 RENDING TO 5MrF US Perfomi the applicable actiort E-0, Step 21.a RNO IE the teinperature is LESS 11IAN 5MP ,11IEN Pmceed to step 2ic. Section 2 Page 28 of 40
Tetic: LOIT NMC #3 INSIRUCTUR GUIDE Resision: 9 IIh NRC3 > Task' Tune II)A/Malf Instructor Infernuwinn%cthity Assign Expected Respanw Standar1 Casap !
-US Stop dumping stcam: E-0. Stcp 21.c IK)P Place luh cmdenscr steam dump EA). ;
i i interlock selecht switches to OIT Step 21.c.! j IK)P Close SG atnospheric dump vahrs E-0. Step j 21.c.2 ! f IK)P Verify the following vahrs - E-0. Step 21.d ; CLOSED i i MSIVs MSIV Inp vahrs IK)P Maintain total feed Ikw E-0. Step 21.c BEnVEEN 530 and 600 ppm until NR icvel is GREATER TlLAN 6?6 (42?& ADVERSE CTMT) in at Icast one SG. t t i ~ l RO Orck PZR Vahes E-0. Step 22 j l PORVs nuv have started cycling RO Verify PORVs - CLOSED E-0. Stcp 22.a : based on SI ikming into an intact l RCS (lmever uncontrolled cooldosm ! may result h mflicient RCS !
- j. contraction to prevent this).
l: i j RO Verify rxunal PZR spray whrs - E-0. Sacp 22.b r Cl OSID ! i i Section 2 i Page 29 of40 !
Tstte IDIT NRC #3 INSTRUCTOR GUIDE Raision: R IIh NRC3 Task Tense' IDA/ Matt' Instrwtor Inforenation%cthity Assign Exgwcted Response Standard Casup RO Verify PZR safety vahrs - E-0. Step 22.c
- CLOSED i
RO To prevent damage to the RCP E-0. Step 23. scal (s). seal injection Iknv sixmid CAUUON be maintained to all RCPs. If CDA actuated. RCPs mmld be RO Oeck K RCPs Simsidd Be Senpped E-0. Step 23 ; procedumily stopped. t i RCS Prtssure should be ahnt 2(XX) RO Verify RCS pressure- LESS E-0. Step 23.a , psia TilAN 1500 psis (1800 psia ADVERSE Cmff) . ! Proceed to step 24 E-0. Step 23.a. RNO. , I "If S'G is FAULlEllhe crew may BOP /RO Orck KSG Seceedwy E-0, Stcp 24 l not feel there is suf5cient leakage to Boemaduies Ase lutact wvmnt a transition to E-2. The crew may elect to transition ES-1.1, SI
, Termination.
i DOP/ Check pressure in all SGs E-0. Step 24.a RO NO SG PRFSSURE : DECREASING IN AN ! , UNCONTROLLED : MANNER NO SG COMPIETEIX DEPRESSURIZED i : F Section 2 i Pace 30 of 40 ! t I
Title:
IDIT NRC #3 INSTRUCf0R GUIDE Ibisns: R ID: NRC3 Task Time IDA/Malf Instructor Infornistion/ Activity Assign Esgweted Responw Standard Coenp T= transition MSGIB Incseze the severity of slee tweak to CRISV Commence monitoring ESF status E-0. Stcp 242 nande sev= 100% emise CIMT I%ssuse is ahmc 23 trtu and Go To E-2. RNO rany = 10 pia. ' Hie goal is to lasve the crew secauk trasmition to FR-El NOTE- Upm transition the operators should US Tmnsition to FR-Z.1 OP 3272. recognize the ORANGE PAllI on EOP L%crs FR-El and transition to FR-Z.1 Guide FR-Z.1 ACHONS USRO verih CLMESFGsoup 2 Swm FR-Z.l. Stcp columes 2 'Ilmough 10) 1 RO Initiate CIA 2 reposition vahrs IR-Z.I. Step for minimum safety function. IRNO CDA will have failed to Auto US Verify CIB FR-Z.l. Stcp Actuate 2 CIB will have closed the isolation RO Check RPCCW Ctmt supply and IR-Z.I. Stcp vahcs retum header isolation vahrs - 2.a CI.OSED RO Check RITCW pumps - STOPPED IR-Z.l. Step 2.b RO STOP pumps. FR-Z.l. Step 2.b. RNO RO STOP all RCPs FR-7.1. Step 2.c Section 2 Page 31 of 40
Title:
IDIT NRC #3 INSTRUCf0R GUIIE Raision: 9 ID: biBQ Task 'Ilme IDA/Malf Instructor Infernistion/Acthity Assign Expected Response Standard Casup N'A If ECA-1.1. loss of Emergency IR-EI. Step Guiant Recirculatkut. is in 3 CAUTION progress. Ctmt spray sixmid be spTated as directed in ECA-1.1 rather that stcps 3. 4 and 7
.US Vesify Quench Sprzr Specin IR-Z.1. Step Opermaion 3 RO Check RWST level - GREATIiR FR-Z.1. Step !
T11AN 100.000 gal (annunciator 3.a ! R%5F EMPTY QSS PP OIT on ! MB2A 5-2 not lit) l t RO Verify quench sprw pumps - FR-Z.1. Step ! RUNNING 3.b j The crew will need to start the RO START quench spray pumps. FR-7.1 l pumps. Step 3.b. RNO [*] : The crew will need to open the RO Verify quench spray pump FR-Z.1, Step j valves. discharge vahu (3QSS*MOV34A 3.c , and 3QSS*hKW34B)- OPEN l RO OPIN vahu. FR-Z.1. Step [*l [ 3.c. RNO i i Flow sixxild exist if the operators RO Check quench spray system - FR-Z.l. Step [*l i started pumps and opened the valves FLOW EXISTS IN AT LEAST 3.d ONE TRAIN , l Section 2 . Page 32 of 40
Title:
LOIT NRC #3 INSTRUCIUR GUIDE Redsion: D ID: hBQ Task Time IDA/Malf Instnsetor Infornsation/ Activity Assign Espected Resgwnise Standani Counp US Proceed to step 5. FR-7.1 Step 3.c IX)P STOP All Main G% Water IR-7.1. Step Pune 5 CAR Fans Should be olTby this US/ Orck Containnuent Ventilseion FR-7.1. Step point. IX)P 6 Verify CAR fans - STOPPED Verify CRDM fans - 51DPPED i DOP STOP fans.. FR-7.1, Step , 6.RNO US Verify Recimdseiosi Sprw Systens FR-7.1. Step Operzeion 7 Crew nuv be at this stcp in less than RO Check CDA signal - PRESENT FR-7.1, Step ii minutes. Expect the crew to start a AFER 1I minutes (annunciator 7.a timer and afler 11 minutes start the CIMF REGRC PUMP AUfD RSS pumps. START SIGNAL on MB2B l-8 lit) step 8 starts on the next page. US Proceed to step 8 and. WIIEN 11 FR-7_l, Step minutes han elapsed since CDA 7.a. RNO initiation. TilEN Perfinn steps 7b j through 7e. RO Verify rceirculstion spray pumps - FR-7_l, Step ; Section 2 Page 33 of40 l l t
Title:
IDIT NRC #3 INSTRUCTOR GUIDE Raision: R ID: N_RQ i Task Tinee IDA/Malf Instrisctor Inforniation/ Activity Assign Expected Response hd-d Cosep RUNNING 7.b RO Verify recirculmion sgay pump FR-7.1.. Step suction isolmion valves - OI4W 7.c ' RO Verify recirculsion spray pump FR-Z.I. discharp- isolmion valves - OPEN Step 7.d RO Verify recirculsion spay- FLOV.' FR-Z.1, Step EXISTS IN AT LEAST ONE 7.c 1 RAIN i
- w/ exception to RSS Pumps and . RO Vedfy ESFSeaha Pued Geney 4 FR-7_1. Step .
- associated ACUS lights - IJT 8 i DOP/ Verify Maisi Scans line helmiion FR-Z.1. Stcp !
RO 9 Check MISVs and MISV
- inpass valves - CLOSED L
Check ESF Status Cwoup 3 , lights - LIT l i i, ! I i i d Section ' Page 34 of40 , i
Title:
LOIT NRC #3 INSTRUCIT)R GUIIE Resision: R ID: NRQ Task Tinie IDA/Malf Instnsctor Infernistion/ Activity Assign Expected Response Se==d-d Casup DOP/ Verify Main Feedwzeer beheios FR-7_l, Stcp ; RO 10 ; Verify MD iWD TD FW pumps-1 RIPPED
- Verify FW isolatkm trip valves - CLOSED i Verify SG feed regulating whrs - CLOSED
- Verify SG fini regulating by;uss uhrs - CLOSED US - At Icast one SG must be FR-Z.l. Step maintained available for 11 RCS cookknm. CAIJi1ON US -
If all SGs are faulted. at IR-Z.I. Step icast 100 ppm feed fknv I I, should be maintained to CAUllON cach SG. US Oseck Ir Auxiliary Feedwzeer How FR-Z.l. Stcp ! Slinald Coseinue To All SGs 11 "B" S/G is depressurizing IK)P Check pressure in all SGs FR-7.1. Step uncontmilably I12 NO SG PRESSURE DECREASING IN <W UNCONTROLIED Sectkm 2 Page 35 of 40
Title:
IDIT NRC #3 INSTRUCTOR GUIDE Resision: R ' ID: BRO Task Time IDA/Malf Instnsciar Information/Actisity Assign Expected Response Standani Comp i . MANNT.R NO SG COMIUilTIIX DEPRESSURIZED ,
"Ir S/G is the affected S'G BOP isolate AFW llow to the affected FR-Z.l. Step SG ll.a. RNO US Oseck Ilvdmgen Concentrusion FR-Z.l. Step 12 ;
RO' Place hydmgen monitor in senice FR-Z.l. Step PEO using OP 3313A. Ilydrogen 12.a Renwnbiners and Reawnbiner ; Ikiildug Vcntilation. section 7.5. ; Operators will not be ahic to check US Verify hydrogen cmcentration - FR-7.1. Step II 2levels until aller the nxxiitor is in LESS TIIAN 5?6 12.b : senice ! US Verify hydrogen cr=wsutim - FR-7_1. Step ! LESS 11IAN 0.5?6 12.c , US Pnxred to step 15. FR-Z.l. Step 12.d SM Notify DSEO ofIbdogen FR-7.1. Step I Concentrasion imide Containment 13 SM' Ibiodically MonieurIlydmgen FR-Z.l. Step CREW Concentration (every 8 hoems) 14 Section 2 Pace 36 of 40
Title:
IDIT NRC #3 INSTRUCTOR GUIDE Resision: R l ID: NRQ Task i Tinee IDA/Malf Instructor Inforenation/ Activity Assign Expected Response Standard Casup T= Trasition M, US Go so I%cedure mal Step in Ufect FR-7_1. Step ! 4 M ule 15
- L 1
2 1 i t r i i i 1 d i Section 7 Page 37 of40 '. I I
ID Nunder: NRC3 Rcrision: 0 D'AlllATOR GUIDE $} lilt 1EGINK%L AlWISOR D'AlliA110N GUIDE - 1%T S&NMllO PROfGED STA SIMULATOR EXAM SUNARIO OUFSMONS N/A. NO STA FOR IRf EXAM Section 2 Page 38 of 40
1 SECI10N 3 i i SIMUIAIOR EXAM SEQUENCE OF EVENTS
SUMMARY
Title:
OPERA 110NAL EXAM ID Number: NRC3 Revision: 0 1&Hi 2 INSTRUCTOR AIDS DESCRIP110N mal F. RF.10 T-0 Malf RP06A . Failure of CDA to actuate, Train A Malf RP0613 Failure of CDA to actuate, Tmin B Malf TC03 Turbine Falls to Trip Malf TC04 Turbine Fails to Runback Malf RP08A Train A MSI Auto Failure Malf RP081) Train B MSI Auto Failure
- 1/0 (RP) PB2-3 ADS-CDA "OFF" CDA Actuation Pushbutton Failure I/O (RP) PB3-3 ADS CDA "OFF" CDA Actuation Pushbutton Failure l T= Examiner's Cue Malf RX12P SG "D" NR lxvel Indicator Fails Low T= Event 3 complete mal.F N109A PR 411.ower INtector Fails liigh 1
T= Rods in Auto Malf RD021 Continuous Imvard Rod Motion (Bank D) Malf - RD0211(as required) Continuous Imvard Rod Motion (Bank C) T= Crew closes MSlV's Malf MS01B,7% 600 sees "B" SG Steam Line Fault Inside CTMT l T=E-0 Transition Malf MS01B,100% 10 secs "B" SG Steam Line Fault inside ClMr Section 3 Page 39 of 1
SECI10N 4 VAUDA110N OIECKilST
Title:
LOIT NRC ff3 ID Number: NRC3 Revision: 0 Remote functions: Verified by j l All remote functions contained in the guide are certified. Malfunctions: All nulfunctions contained in the guide are cenified. Initial Conditient The initial condition (s) contained in the guide are certified or have been developed from cenitied IC's in accordance with NSEM-4.02. Simulator Occrating Limits: 'lhe simulator guide has been evaluated for operating limits and'or anonulous response. Test Run: The scenario contained in the guide has been test run and validated (validation sheet completed, next page)on the simulator. Simuutor response is reasonable and as expected. Examination Scenario Review lhe dynamic examination review checklist is complete. Section 4 Page 1 of 3
SECi1ON 4 OPDINI1ONAL EXAM VAUDAllON SI10!!' l Program
Title:
1 icensed Oncmtor itexgtalification Training
Title:
LOIT NRC #3 ID Number: NRC3 Revision: Q lly their signature below, the people acknowledge the confidentiality and validity of the material contained within and will not willf'ully disclose its contents to others enrolled in the Millstone linv 1.icensed Operator Requalification Program. VAUDATED llY: liint Signattte Date SM / US / RO / __. IlOP /
/
___ /
/
/
/
Section 4 Page 2 of 3
SFL'I1ON 4 DYNAMIC EXAMINA110N RD'IDV ORIKlJST l Note: 'the ibliowing criteria list scenario imits that an: numerical in nature. A second set of numbers indicates a range to be nwt for a set of two scenarios. Ouantitative Attributes
- 2. 13. Total nulfunctions inserted: 44/1014 4 14. Malfunctions that occur after EOP entry: 1-4/3-6 3 15. Abnomul Events: 1-2/2-3 3 16. Major Tmnsients: 12/2-3 1 17. EOPs used beyond primary scram response EOP: 1-3/3 5 1 18. EOP Contingency Procedturs used: 03/13 60 19. Approxinute scenario run time: 45-60 minutes (_one seerurio nuy approach 90 minutes) 40 % 20. EOP mn time: 40-70% of scenario mn time 2 21, Crew Critical Tasks: 25/5-8 yes 22. Technical Specifications are exercised during the test COMMENTS:
Section 4 Page 3 of 3
I I SirlK)N 5 REITJUNCCS AND CRTHCALTASK'lRACKING
Title:
LOIT NRC #3 1D Number: NRG Revision: 0 l
- 1.
References:
AOP 3575, Rapid IAmupower AOP 357). Instnunent Failure Response. EOP'35 E-0 Reactor Trip or Safety injection EOP35 FR Z.1 Response to liigh C1Mr Pressure EOP* ERG-ilP Westinghouse Osmers Gmup ERG ilP Background Document EOP* Step Doc Millstone Unit 3 Step Deviation Document EPIP 4400 Event Assessment, Classification and Reportability ' Tech Specs Technical Specifications for MP3 OP'3272 EOP Usem Guide NUREG*1021 rev 8 Examinem Standards
- 11. Qitical Tasks Covered in this Test:
NWT, : Critical Tasks are nurked by an (*] within guide CRfilCAL CRfilCAl_ TASK K/A >/= 3.0 BASIS FOR SFI FC110N TASK # DESCRIPTION lituns only E0-E Establish at least one Quench 026 000 Failun: to establish at least one Quench Spmy train flow belbre Al.01 Spmy train flow under the postulated completion of FR-Z.1 step 3. 3.9/4.2 conditions constitutes a "demonstmted inability by the crew to n cognize a failure / incorrect auto actuation of an ESF system or component." E-0-P Manually actuate MSI or close 000-040 Failure to close the MSIVs under the the MSlVs before a severe EA1.01 postulated plant conditions causes orange path challenge 4.6 / 4.6 challenges to CSFs beyond those develops to either im:parably introduced by the postulated suberiticality or integrity CSF conditions. Additionally, such an or belbre transitioning to omission constitutes a " demonstrated ECA 2.1, whichever happens inability by the crew to n: cognize a first failure of the auto actuation of an ESF system or component and to take an action that would pn vent a challenge to plant safety." Section 5 Page 1 ofI
l SECI1ON 6 L SCENARIO INmAL 00NDm0NS Reactor Power: 100 % 1 l Operating llistory: 200 days on Line l I RCS Iken: 988 ppm Core Burnup: 10,500 MWDMIU Condensate ihmins: 7 IN SERVICE r l Evolutions in Progress: None, 'Ihunderstonn Wamings have been issued for the next 4 ! to 6 hours. l Major Equipment OOS: "A" Senice Water Pump . Bearing Replacement "A" Motor Driven AFW Pump - Motor Ground Troubleshooting.
"B" Stator Water Cooling Pump - Seal Replacement-Crew Insmrtiorm Excessive vibration exist on the "B" 'IDFW Pump. 'Ihe l Operations Manager has directed your crew to reduce Reactor .
L power to 90% @ 1/2 % per minute and swap feedwater pumps, . l You are to use AOP 3575, Rapid Downpower, to perform the , L evolution. All necessary checks to start the Motor Driven Main Feedwater Pump have been completed. PE0fs are standing by to L start the MDFP and the "C" condensate pump. il s ! Plant / Simulator Differeires: 1 Rad Monitor IIistorical Data-Simulator Rad Monitor historical data not valid prior to i the beginning of this exercise. Reactor Makeup System batch counters diffen:nt from plant system.- (if required to ! perfomi a makeup evolution, refer to the RO pmcedure cart for setting the Batch L Counter.) Simulator main steam atmospherie dump valve contmllers different from plant. 1. i E i Section 6 Page 1 of 1-1 r ,_ - . ,-. -.-- ; ---. .,_-_ - ,. _ . .-.---~.-44-.. - - - - - -, _- - - - . _ , . . . - . . . , - - . .
SIMULNIDR EXAM GUIDE APPROVAL SHEET 1.
Title:
LOIT NRC #6 ID Number: NRC6 Revision: D
- 11. Initiated:
J. William C6td ' 5/29/97 Ikveloper Date 111. Reviewed: Reviewer Date
-IV. Approved:
Operations Manager . Date Operator Training Supenisor Date - t a
l SIMULNIDR EXAM GUIDE TARI.F OF CONTEm ) SEC110NS LISTED IN ORDIUt
- 1. Exam Overview i
II
- 2. . Instructor Guide
- 3. Sequence of Events Summary
- 4. Validation Checklist
- 5. Referrnee and Critical Task Tracking Fonn
- 6. Scenario Initial Conditions Stwet
SECrlON 1 EXAM OVERVIEW i
Title:
LOIT NRC #6 l ID Number: NRC6 Resision: 0
- 1. Exam lirief:
1he plant is opemting at 100% power, MOl, XEeq conditions.1he shift is to nuintain l present plant conditions for the remainder of this shift 1 Initially PT505 will fait low.1he crew will take nunual control of the rods and should address the malfunction using AOP 3571, Instmment Failure Response. Once the crew retums rod contml to atu matic and Tech Specs are addressed. CONVEX will call and request a 200 MW load reduction. After the crew has demonstrated satisfactory reactivity control, a control bank "D" rod will stick and fail to move in with the rest of the bank. When this is discovered the crew should enter AOP-3552, Rod Control Malfunction. While l&C is investigating. they inadvenently cause the affected group of rods to drop. The crew should recognize this and insert a reactor trip. When the trip occurs, a large break LOCA occurs. Autonutic S1 will not occur, necessitating the crew to nunually actuate SI, in addition, the motor driven AFW pumps will not autonutically stan and some Charging System valves will not align to their Si positions. 1he exam will be temiinated at the point in E-1 where the crew checks RCS and SG pressures stable (step 10).
- 2. Plant / Simulator diflirences that may affect the scenario are:
{ None. l
- 3. Duration of Session:
I hour Section 1 Page 1 of 2
SECTION 2 , INSTRUCIDR GUIDE 11tle: LOIT NRC #6 1D Number: NRC6 Revision: _0_ All Control Room Corvimt Oxrations and Communications shall be in accordance COP 200.1. Conduct of Oncrations. and OP 3260. Unit 3 Corviet of Oncrations.
" Review the Simulator Operating Limits (design limits of plant) and the Simulator Modeling Limitations and Anonulous Response List prior to performing this training scenario on the simulator. The instmetor should be aware if any of these limitations nmy be exceeded." (NSEM 6.02)
Section 2 Page 1 of 47
l SIMULAIOR PROBIBE D"JRING EXAhE It is the responsibility of the Instructon; ir simulator to insure that exam interruptions have a minimum negative ,act on the Crev and the examinations sw provide. l l Be mmre that at all times the Operators should tnzat the simulator as ifit were the plant and you too should treat it as much like the plant as possible when they are in the simulator. As soon as the Instructors are aware of a simulator problem that will adversely affect the exam in progress (computer fault, etc.) the Instructor should:
- 1. Place the simulator in FREE 7.E if possible.
- 2. Announce to the Crew that there is a simulator problem.
- 3. Request that the Crew leave the simulator control room. (1he Crew should leave the simulator for problems which involve major switch alignments).
4.- Deal with the problem (reboot, call SEB, etc.)
- 5. After the Instructors believe the simulator is restored to senice, the Crew should be told how the exam will continue, ifit is possible and felt to be acceptable to the evaluators, the examination can '
begin where it left off with an update on plant parameters and each-Crew member is prepared to restart. If the examination will not - begin where it left off, the crew should be told how and where the exam will begin again.
- 6. Once the Crew has been told how and where the exam will begin, have the crew conduct a brief so that the Instructor and evaluators can insure that the crew has all the necessary_infonnation to continue with the scenario.
- 7. Once all Crew members, Instructors and evaluators are satisfied that they have the necessary infonnation to continue the scenario, place the simulator in RUN and announce to the Crew that you have continued the evaluation session.
Section ? Page 2 of 47
Title:
LOIT NRC #6 - INSTRUCTOR GUIDE Revision: 9 ID: hBC6 Task Time IDA/Malf Instnictor Infonnation/ Activity Assign Exrectal Response Standant Coenp EVENT #0
'ITIII: INIllAL SEIUP Setup Imtnsctiom:
DWerIDTm folkms : At any XIERM window. type <idt> When the SUN asks fir an executive type- UEXEC or RTEXEC? cnter <r>- this will tving up a blank idt IuBC-To go to a pnxiously saved idt file type <rcad> at the gnxnpt When tir SUN asks fir a file name of the file you wish to view type in the argugviate file name-1he old "IMm" files are as finms-Old ISD pages 1-8 are idt file JPS Old ISD pages 9-16 are idt fi:e OPSI Old ISD pages 17-19 are idt file OPS 2 o IE the step counters are at/ncar O(X). HW2L RE5KNE the SlliP COUNIER OVERRIDE. allow the counters to step out during the IC reset. Reset to IG14 l REINSTA'IE the step counter OVERRIDE Place Simulator to RUN j RESET the time constant on the PZR Icvel contmlict by PLACING the PZR Master Level controller in MANUAL then retum the Controller to AUTO. Set the SlEP COUNIERS t PIACE the Main Turbine on the LOAD LIMITER Verify annunciator. "COMPUIER FAILURE" (MIMC,1-11), is NOT LIT. Place MOL, Cunt Book in Shelf for Operator use. Remove other Cunt Books fnwn the Ikmr. ; Cicar the IX'S Alanns Reset the Rad Monitor CMI'IR Console by Depressing the " Status Grid" button twice. ; l r 4 4 i Section 2 ! Pace 3 of 47
Title:
LOFT NRC #6 INSTRUCTOR GUIDE - Ibision: 9
. ID: NRC6
- ' Task Time -
IDA/Malf Instnscior inronnation/ Activity Assign Expected Response Standani Camp PIACE ME FOllDMNG EQUIPMEhT IN l'IL & YFllJOWTAG: Fayuipment OOS: "A" Senice Water Pump "A" Motor Driven AFW Pump "B" Stator Water Cooling Pump Insert applicable CREW EXAM Tape into tim VCR. Synchronize the MONITOR Time Display with BIG BEN. Initial Mairunctions
/ ion /IDAs: .
RD0359 rscu=1 CBD Cep 2 rod D12(Dmpped Rod) , RD0361 rscu=1 CBD Grp 2 rod I18 (Droppcti Rod) RCO2A sev =5% ramp =180 seconds BT=1 Ixxy #1 Ikt Irg rupture FW20A AFW Pump Fail to Auto Start. "A"
, F%20B AFW Pump Fail to Auto Start. "B" RPilF CVCS Components fail to rcrosition RP07A Failure of Tr "A" SI to Auto Actuate RP07B Failure ofTr"B" Si to Auto Actuate j BT=1 is Reactor Trip Breakers Open l
Section 2 Page 4 of 47
Title:
LOFT NRC #6 INSTRUCIOR GUIDE lbision: R IIh ' NRC6 Task Tune- IDA/Malf Instructor InRwmation/Actisity Assign Expected Reponse Standard Coenp had Examiner: Refer 80 the ' Briefing Script for the OperaIional Exam"and brief the c=w. Booth hatnsetor: Cornmence RecortEng Simulasorsession Booth isstnsetor Itefonn the ciew inrnmcr(Initial Conditioes page at end of IP) with she SMUS . the time SM /US twief his evew on plant conditioss and any num)wequipnient OOS. Sectkn 2 Page 5 of 47
Title:
IDIT NRC #6 INSTRUCIDR GUIDE Resision: R IIh Ni{C6 Task Tinie IDA/Malf Instnsctor Inforniation/ Activity Assign Expecial Response Standsni Coeup EVENT ONE: Start "A"SWP and place 'C' SWP in standy. T= 1 minute US will direct tir start of the "A" aller tumover SWP and placing the "C" SWP in standby. IAW OP 3326 section 7.7. T= uhen EVINT'lWO: Cycle Test ofIIP 3SWP*MOV2 Tishine Seop Vahes. 4A closes. US will direct the urckly Cycle Test of the IIP Ttabine Stop Vakes. IAW SP 3623.2. section 4.2. The US will have a ctg of OPS Form 3623.2-1 complete thmugh section 4.1 t Cycle one valve then go to crent 4
- three.
l EVENT TilRFF: IT-505 Fail I;w T= IIP turbine RX16A IT-505 Fails to 0% CREW Determine the initiating parameter and AOP 3571
- stop valve sev = 0.0% Rod control is the affected place the alTected cmtroller in step i ;
- fully opens. ramp = 60 controller MANUAL !
l seconds Section ' Page 6 of 47
Title:
IDIT NRC #6 INSTRtLTOR GUIDE Revision: 9 ID: NIK6 I t Task Time IDA/Malf Instructor InRwnistion/ Activity Assign Expected Responw Standarti Cosep j CREW Stabilize the plant sw . d crs. AOP 3571 , step 2 ! i IK)P Defeat the failed du..d by selecting AOP 3571 i i the altenate channel en first st. ige Att.G step i steam pressure cimnci select (r switch i (3 MSS-PS505Z). f BOP If C-7 is actuated. select RESET on AOP 3571 I the steam dump m(xle selector. Att.G step 2 IK)P Set steam generator pressure controller AOP 3571 (3MS3-PK507) to 1092 psig. Att.G step,3 : DOP Place one c(nienscr interlock select (r AOP 3571 switch to OFF. Att.G step 4 ; i BOP Place the steam dump mode scicctor in AOP 3571 the STFAM PRESSURE mode. Att.G step 5 , IK)P Place lxth condenser interlock selector AOP 3571 suitches to ON. Att.G step 6 PO RestoremT - T, cmr to within I 'F AOP 3571 and place rix! control in ALTFO. Att.G step 7 i 4 NOlli If a crew nieniher heads kmuds , the Rark Roorn to perfonn this next i step, INHRCITF and Iwing b the hooth while you ' BYPASS" AMSAC i Section 2 i Page 7 of 47 ; I
Title:
' LOIT NRC #6 INSTRLUOR GUIDE Reision: 0 ID: NRC6 Task Time IDA/Malf Instnscior Ini'ormation/Actisity Awign Expecial Reposee Standard Coenp T+ 3 minutes ANN Ove: Tide "ON" AMSAC CREW Bypass AMSAC using OP 3350 AOP 3571 of mysest ovenide Trouble' Bypass. Override m when A1V3 Mitigating System Ac*uating Art G stcp 8 NB4C F-8 requested to bypass AMSAC Chruitry, section 7.4.
.g,,,
i Duty Oflicer Pamission required CREW Refer to 3TR47.2. Addithmal AOP 3671 for continued operatim. Requirements, AMSAC. Att G step 9 Booth Infbrrn the crew that permission has BOP / % hen coexlitims lure stabilized. AOP 3571 been granted to continue. RO obscrst MB annunciators and Att G step parameters. Immediately report any 10 t unexpected or unexplained conditions
; to the SM.
US Within one hour. perfmn the AOP 3571 , i fbikming- Att.G step II This action is required by the'IS RO Determine 'by obsenution of the AOP 3571 when < Minimum Channels asmciated permissist annunciator Att.G t Opauble. wirxkms) if the interlock is in the step ila ' required state for the existing plant ; conditims. j Rx or turbine not at pourr P ? (MIMD 5-3) Turbine not at power P-13 7 (MIMD 6-3). i Action 8 will re-emphasize step SNFUS Refer to Technical Specification 3.3.1. AOP 3571 11.a Action 8. Att.G l step lib l j- Section 2 Page 8 of 47 'I
- - ~ - -, -_ _______._____-m___.._.__.m_ _ _ . _
Title:
LDIT NRC M INSIRUCIDR GUIDE Raision: R ID: NRC6 i Task Tinie IDA/Malf Inserv:for Infernietiene/ Activity Assign Espected Response Standard Conny , US Retpest I&C Department perfmn AOP 3571 cor:tctive mairdenance m failed Att.G instmment. stcp 12 Section 2 Page 9 of47
Title:
LOIT NRC #6 INSTRUCTOR GUIDE Revisiont 9 ID: b'RC6 Task i Time IDA/Malf Instructor Information/ Activity Assign Expected Response Standard Comp EVENT FOUR: 200 MM Rapid ekmnpower - Booth Call the US as the Unit 1 SM and i pmvide the folkming direction:
"An Emergency Genemtion reduction has been ordered by CONVEX due to Critical Transmission Elements Out<>f Senice. In accordance with ,
Section 1.4 of COP 200.8, Millstone 3 must reduce electrical output by 200 MWe in the next 15 minutes. Unit 3 must maintain the currtnt MVAR loading during and follcuing the kud reduction." NOlli>> Note the current MVAR hxxiing and ensure BOP nmintains the current MVAR loading during and following, the hud reduction. NO'Ili>> 'Ihe US may immediately perform SM /US When notified by Unit 1 SM to reduce COP 200.8, the emergency kud reduction using load, Refer to applicable procedure and Step 1.4.2 AOP 3575. If the US uses OP REDUCE poutr: 32(M to reduce knd he should implement Section 4.2, Load - OP 3204, "At Power Opemtion" ! Reduction. ,
'Ihe load 200 MWe load reduction SM /US INillATE kud decrease- OP 32(M.
Section 'l Page 10 of 47 !
Title:
LOLT NRC #6 INSTRUCTOR GUIDE Resismn: 9 ID: NRC6 Task Time IDA/Malf Instructor Informat~mn/ Activity Assign Expected Response Standani Camp must be accomplisini in 15 IE a load decrease rate of greater than step 4.2.1 minutes. 'Ihis is > 10Whr. 10Whour is desired AND permission Neither the Operations Manager nor to use this procedun: has not been the Unit Director has given given by the Operations Manager or permission to use OP 32(M to Unit Director, Go To AOP 3575, perform the reduction. 'lhe Crew " Rapid Don'gmtr". should not unste time trying to contact these individuals to obtain permission. 'Ihe Crew should Go To AOP 3575. - AOP 3575 Rev. 5 Stem US Determine Pbwer Reduction Race AOP 3575 (Wmin). Step 1 NOTI >> The Crew will should notc the kud US Check desired poutr reduction rate - AOP 3575 reduction is CONVEX requested LESS TilAN OR EQUAL 10 Step 1.a and should be perfixmed at SWmin. 5Wmin. I2nd reduction is a CONVEX US Check power reduction a CONVEX AOP 3575 requested Energerry (l'neirrion requested Emergerry Gerrirsion Step I.b Reduction. Redactiort CREW Perform load reduction at 5Wmin. AOP 3575 Step 1.c US Proceed to Step 2. AOP 3575 Step 1.d Section 2 Page 11 of 47-
~
Title:
LOIT NRC #6 INSTRUCIDR GUIDE Resiision: 9 ID: NRC6 Task Time IDA/Malf Instructor Information/ Activity Assign Expected Response Standard . Comp. T=Secorul RIXM60 Contml Ihxl M4 CBD Gp2 US orck Rea contml In atrio. AOP 3575 Boric Acid sticks in guesitionipage 19) Step 2 Transfer hunp started as part of the rapid tx> ration. US If during the perfomunce of this AOP 3575 pmcedure the Rod Insertion Im-Ie S8cp 3 Limit is reaclxx1, Go to AOP 3566. CALTflON Immediate Ikration. All these Notes should be alhcred CREW Ifload reduction is a CONVEX AOP 3575 to by the Crew. requested emergency surration Step I reduction, the following apply: NO1T: The Unit i Shift Manager will determine Ixnv the load i reduction will be :6::nxl anmg the Us11tS. DO NOT stop a CONVEX
" Emergency lead Reduction" request due to AFD exceeding the target band.
The load reduction must le completed within 25 minutes of Section 2 Page 12 of 47
Title:
LOIT NRC #6 INSTRUCI'OR GUIDE Revision: 9 ID: MRGi Task Time .. IDA/Malf Instructor Information/ Activity Assign Expecicti Response Standant Comp ' notificatim , CREW Initiate Imd Reduction. AOP 3575 ' Step 3 Yes it is a CONVEX requested SCO Check power reduction a CONVEX AOP 3575 ' emergency genemtion nxiuction. requested emergency generation Step 3.a reduction. YES, turbine IS NOT in standby BOP Check turbine NOT in STANDBY AOP 3575 hud control. US should move to LOAD contml. Step 3.b Stcp 3.c. . YES, load limit limiting light BOP Check LOAD LIMIT LIMlllNG light AOP 3575 simuld be LIT. - LIT. Step 3.c t BOP Intermittently Press DECPEASE AOP 3575 LOAD pushbutton until LOAD LIMIT Stcp 3.d LIMlllNG light - NOT LIT. , BOP Rotate LOAD LIMIT SET adjust AOP 3575 knob at least one full tum in mise Stop 3.e directim i BOP Select DECREASE LOADING AOP 3575 RATE to CN. Step 3.f Section 2 Page 13 of 47 !
Title:
LOIT NRC #6 INSTRUCTOR GUIDE Revis~ m n: 11 ID: NRC6 Task Tinw IDA/Malf instructor Information/ Activity Assign Expected Response Standard Comp 13OP should be ordenxi to select 130P Select LOAD RATE LIMIT AOP 3575 5?Vmin. BOPshouldinfonn RO //us SUMIN to required pantr Step 3.; he is nvlucing nahine hxul reduction mte (9Wmin). 13OP should be ordenxi to adjust IlOP Utilizing DECREASE LOAD AOP 3575 LOAD SET to - 1000 Mwe pushbutton, Adjust LOAD SET to Step 3.h desinxi final Mwe (power level). 13OP periodically adjust MVAR 130P Maintain initial MVAR hxxiing AOP 3575 hiading as necessary to maintain during power reduction unicss Step 3.i initial MVAR hiading. directed otlunise. Power reduction rate should remain at US If at any time the patr reduction AOP 3575 59Vmin. throughout. rate must be changed, retum to Step 4 Step 1. NO'E YES power reduction rate is 2 US Verify Pbwer Rakattion Rase - AOP 3575 39Vmin. GREATER 11LAN OR EQUAL Step 4 TO 3WMIN. US Initiate Rapid Horation. AOP 3575 Step 5 RO/13OP Place RCS makeup controller to AOP 3575 AlHO. Step 5.a RO,73OP START one boric acid transfer AOP 3575 pump. Step 5.b RO,13OP OPEN emergency boration valve AOP 3575 (3ClIC*MV8104). Step 5.c Section 2 Page 14 of 47
Title:
LOIT NRC #6 INSTRUCTOR GUIDE Revision: !! ID: NRC6 Task Time IDA/Malf - Instructor Information/ Activity Assign Expected Response Standarti Comp YliS, guver reduction rate is US Verify power reduction rate - AOP 3575 5Wmin. GRENII!R TIIAN OR EQUAL to Step 5.d 5%' MIN. RO'IOP START second boric acid transfer AOP 3575 pump. Step 5.e RO'IOP OPEN charging line flow control AOP 3575 valve, to match direct boric acid Step 5.f flow (3ClIS-FI 183A) NO'IF7> ' Ensure boration start time is US/RO Recorti time lxration started AOP 3575 recorded / LOP Step 5.g Time RO/ LOP Energize all PZR heaters. AOP 3575 Step 5.h The total poutr change (a%) is: US Deterrr.ine required boric acid AOP 3575 200 MWe/1200 MWe X 100% = addition by multiplying Step 5.i 16.7% so the boric acid addition total poutr change (a%) by 15 should be ~250 gal. (galm) = gal. The time requin:d should be about: Cnny Determine required time to bomte AOP 3575 250 gal + 75 gpm = 3 min. by dividing required galkms of Step 5.j boric acid (gal) by tir direct boric acid flowrate (gpm) min. Section 2 Page 15 of 47
Title:
IDIT NRC #6 INSTRUCTOR CUIDE Revision: 9 ID: NRC6 Task. IDA/Malf Instructor Information/ Activity Standant Time - Assi;:n Expected Response Comp Ikric acid flow rates are based on ' AOP 3575 appmximations. Adjustments Step 6 should be made to the volume NO~m addition or flow rate as necessary to ensure the reactor reaches the desinxi cnd state of: Tavg on program Rods above the Rod Insertion Limit l AFD on or above the target value NOTE: 'Ihe US may decide to terminate the US Restore RCS Makeup. AOP 3575 rapid downpower once the stuck nxi Step 6 is observed. Ifso, he should cmtact Unit i SM to request they make up lbr incomplete load reduction. Proceed to page 19.- Cnnv Check rapid lxxation performed for AOP 3575 the nxjuired time determine in Step Step 6.a-5.J. RNO action should be taken only if US Pnxred to Step 8 and, WIIEN AOP 3575 ' boration time is not yet completed. Rapid boration has been performed Step 6.a lbr the required time,11IIN RNO Retum to Step 6.b. RO/lK)P CLOSE emergency boration valve AOP 3575 (3ClIS*MV81N). Stcp 6.b Section 2 Page 16 of 47
Title:
LOIT NRC #6 INSTRUCFOR GUIDE . Revision: 9 1D: BRC6 Task Time IDA/Malf Instructor Information/ Activity Assign Expected Response Standarti Comp RO'IOP STOP boric acid transfer pump (s). AOP 3575 Step 6.c RO,'10P Place charging line flow control AOP 3575 valve in AtJFO. Step 6.d US Pmcced to Step 8. AOP 3575 Step 6.e MSR Imad Control Valves should not US/IOP Reduce Steam Supply To 'Ihe AOP 3575 need be adjusted for the 200MWe MSRs, Using OP 3317, Reheat and Step 8 load reduction: however, they should Moisture Separator, Section 7.8. be checked to be operating properly in ALIFO. US Orck If RCS Sanple Is Required. AOP 3575 Step 9 Power change will be > 15% in one Verify change in Reactor Power - AOP 3575 hour GRENIER 'IlIAN I5% IN ONE Step 9.a iIOUR. US/SM Request Chemistry sample the RCS AOP 3575 for iodine (within 2 to 6 hows <fter Stcr 9.b the power clxnge.) No, Target Power Irvel is - 83% US Verify Target Pbwerlevel - IISS AOP 3575 TilAN 50% Step 10 Section 2 Page 17 of 47 l
Title:
LOIT NRC #6 ' INSTRUCTOR GUIDE Revision: R ID: NRC6 Task Time IDA/Malf lustructor Informafmn/ Activity Assign Expected Response Standard Comp _ US Continue pourr reduction to AOP 3575 desired target power level. Step 10 RNO WIIEN final pwver level is When turbine kud is at 1(XX) MWe reached.1UEN Proceed to Step 20. the US should proceed to Step 20 US Check Plant Stahs. AOP 3575 Step 20 Cnnv should be at the target pnver Verify - AT TARGIH POWER AOP 3575 level of 1000 MWe befbre they LEVEL Step .20.a perfbrm Step 20. Cnny Borate or Dilute as n-y to AOP 3575 maintain AFD as close to the target Step 20.b value as possible while maintaining rods above the Rod hisertion Limit. US/SM Request Chemistry obtain RCS AOP 3575 boron samples. Step 20.c NO'IF>> Refer RO/lK)P to guidance for using RO'P,OP Align RCS makeup for automatic AOP 3575 Simulator. specific Ihtch Counters operation using OP 3(MC, Primary Step 20.d which is allixed to the RO Procedure Makeup and Chemical Addition, cart. section 7.2. BOP Select RESIR on the steam dump AOP 3575 mode selector switch (ifmquimh. Step 20.e Section 2 Page 18 of 47
I
Title:
LOIT NRC #6' INSTRUCTOR GUIDE Revision: 9 ID: NRC6 Task Time IDA/Malf Instructor information/ Activity Assign Expected Response Standard Comp IYrfonn the Following: AOP 3575 Step 21 Imad nx!uction is CONVEX US Check power reduction is a AOP 3575 rtquested so US/SM should inibmi CONVEX requested emergency Step 21.a Unit 1 SM uhen complete. generation reduction. Report completion and amount of AOP 3575 pmtr reduction to Unit i Shill Step 21.b Manager. NOTF>> Applicable Normal Plant Operating US Contiram With Normal Plant AOP 3575 Procedum is OP 3204, Section 43. Operatiom Using ApplicaNe Plant Step 22 . Procethwes. Booth The sitrk rod will be inserted when the second BA Tramfer panp is startett EVENT HVE: Sitrk Rod CREW Enter AOP 3552, Rod Control AOP 3552 Malfunction based on misaligned Entry Rod Conditions CREW Stabilize Plant Corulitiom AOP 3552 Step i RO Place control rod bank SEL switch AOP 3552 in MAN Step I.a Section 2 Page 19 of 47
Title:
LOIT NRC #6 INSTRUCTOR GUIDE Resision: h ID: Mtf6 Task ~ Time IDA/Malf Instructor Information/ Activity Assign Expected Response Standarti Comp RO Verify - NO RODS MOVING AOP 3552 Step I.b CREW Stop any Ixnver incmase or AOP 3552 decmase evolutions in prognss. Step 1.c RO' Verify Tavg - Tref desiation - AOP 3552 13OP 5_ l.5 F Step I.d RO' Adjur4 turbine load to minimize AOP 3552 13OP Tavg - Tref desiation Step 1.d RNO RO Borate or Dilute as necessary to AOP 3552 maintain Tavg within 1.5"F or Tref Step 1.e RO Verify 'IURB LOAD REJECITON AOP 3552 ARM C-7 (MIMD M) annunciator Step I.f
- NOT LIT US Oeck For Dmpped Rod AOP 3552 i
Step 2 RO Verify RPI URGENT FAILURE AOP 3552 (MIMC 4-10) annunciator - NOT Step 2.a LIT US Check rod bottom lights - AOP 3552 NONE LIT Step 2.b i Section 2 Page 20 of 47 i
Title:
LOIT NRC #6 INSTRUCTOR GUIDE Reision: 9 ID: MRC6 Task Time IDA/Malf Instructor Information/ Activity Assign Expected Respome Standard Comp US Check No Rod Position Irxlication AOP 3552 Malliinctions Step 3 RO Verify DRPI pour available AOP 3552 Step 3.a < Any DRPI display light lit US Verify status of following _ AOP 3552 annunciators: Step 3.b RO - RPI NON URGINT FAILURE (MIMC 3-10) annunciator - NOT LIT RO - RPI URGENT FAILURE (MIMC 4-10) annunciator - NOT LIT RO Verify status of DRPI display AOP 3552 - alanns: Step 3.c RO - URGENT AIARM - NOT FLASillNG RO - DATA A FAILURE - NOT FIASHING RO - DATA B FAILURE - NOT FIASIIING Section 2 ; Page 21 of 47
ui i E l 3= 04 ' E BE
<M
- U QIo $
= ,k,, + o sd a z 5 e z y gz 5, = zag i 3c s
^l W ' E"O p go om P'@ 3 P ed 4
l.o !c
.z a ils588E, pg E-z!s El oc .ili$
n _e u g!!h=mEmla wsz less 8 s xs 3 I 2 5 88 f.gla.p 2- - _s E et u d b> 63E 6$mg 8 6px g .a 6bs" jg
- a 1 #is 1589 Is$ 6mt 3:F5 Ill] a e
8 . . . . .
.2 .El o
c
- 4
- 9_ _9 9
_ _9 h2x m 2 = r b 'E - 2 6
< E g m y,g b
5
.h =.@ $ 3 3 .E D
1ll E y 2
'd j'j
$ $ $e sE g - = se I N
@ 3 'r)
! W c 3=s i 5 x
6 z $]6
<_p k
u x a Z bb 92
- zl U
lili .$ e- 6 1-4
Title:
LOIT NRC #6 INSTRUCTOR GUIDE Revision: il ' ID: NRC6 Task Time IDA/Malf Instructor information/ Activity Assign Expected Response Standard Comp SillJI1X)WN ROD INSER~IlON LIMIT US Align nxi using Attachment A AOP 3552 Step 4, RNO ATTACllMENT A CREW - Improper nxi alignment can AOl>3552 ' cause fuel damage either Attachment directly or in conjunction with A Step 1, plant tmnsients. Caution CREW - Resetting ROD CONTROL. AOP 3552 URGINF FAILURE (MB (C 4- Attachment
- 8) alarm without contctin ; the A Step 1, cause may result in dror.Ang a Caution group of control rtxis.
US/ Check Plant Conditiom AOP 3552 , SM Attachment ! A Step 1 : i US/ Verify operational nxxk - MODE 1 AOP 3552 SM Attachmmt A Step 1.a AITected nxl is M-4 RO identify affected rtxl(s) as follows: AOP 3552 Attachment A Step 1.b DRPI display Section 2 Page 23 of 47
Title:
LOIT NBCJ6 INSTRUCIOR GUIDE Resision: I! ID: NBC6 Task Time IDNMalf Instructor Informatk>n/ Activity Assign Expected Response Standant Comp Rod Supenision on plant protus computer RO Verify ROD CONTROL URGINF AOP 3552 FAILURE (MIMC 4-8) annunciator - Attachment NOT LIT A Step 1.c T+ 4 ndm of REMOVE Report that a idown lift coil fise US/ Request I & C verify af fected rod lifl AOP 3552 call RD0460 appears to be the pmidem. Request SM coil fuse - NOT BLOWN Attachment permission to replace the fase A Step I.d T= ordered to RD0360 Do NOT ACI1VA1E RSCU=1. replace fisc rscir=1 1his ordy sets ign the nxl to dng, with the other nxk in Bank 'D" T+ 3 mim of Activate lhis will drop all 3 Hank 'D" Grp LOCAL Replace fuse. AOP 3552 order to RSCU=1 2 nxk Attachment replace the A Step 1.d. fme RNO Mhen nxk drop, Page US Check Reactivity Control Units AOP 3552 Forward to l' age 25 for Fr0 Attachment , actiorts and everW 6. A Step 2
??? steps is RIL fbr the Shutdown US/ Verity all shutdown axis greater than AOP 3552 .
Hanks SM or equal to insertion limit using 'IRM. Attachment OPS Form 3273-3/4.3.1.3.5, A Step 2.a SIIUIDOWN ROD INSERTION LIMIT Section 2 Page 24 of 47 l
Title:
LOIT NRC #6 INSTRUCTOR GUIDE . Revision: !! ID: NRC4 3 Task Time iDA/Malf Instructor Information/ Activity Assign Expected Response . Standant ' Comp RO Verify at least one nx! misaligntM by AOP 3552 more than + 12 steps fmm its group Attachment step cmnter A Step 2.b RO Verify only me rod misaligned by AOP 3552 nxxe than
- 12 steps from its group Attachment step counter. A Step 2.c Opemtors have I hour to reston: US/ Refer to Technical Specification AOP 3552 ,
nxi alignment belbre more SM 3.1.3.1 ACllON b., and Determine Attachment ' nstrictive actions are taken AC110N requirenrnt A Step 2.d HOOHI INS'IRUCIOR: When US Notify Reactor Engineering AOP 3552, contacted acknowledge the problem Attachment and infbrm the crew that nxi A Step 2.c rtcovery is desired t T= Rods drop EVENT SIX- 3 RODS DROP CREW Crew should manually trip the Reactor AOP3552 and Tmnsition to E-0 Step 2b : RNO & 2 nxi Bottom ARP Section 2 Page 25 of 47
Title:
IDIT NRC #6 INSTRUCTOR GUIDE Resision: 0 1D: NRCi-Task Time IDA/Malf Instructor Information/Actisity Assign Expected Response Standani Comp I NOTE Upon Entry into E0, a I;irge Ikeak IJOCA will occur. 'Ihe cmv will manually need to actuate SI. " Start the Motor IAiven AFW - Pumps and stalign several ClIS components CREW Go to E-0, Reactor Trip or Safety AOP 3555, Injection. Step 4.a3, RNO Foldout page must be open EOP 35 E-0, Step 1, NOTE ADVERSE CIMF defined as GREATER T11AN 18&F or GREATER 11IAN 10"/w in containment. This definition applies to this and all subsequent EOPs. The reactor can be intemrtted as " tripped" and the operator shall pmcced to the next high level step when any two of tir three bulict substeps ofstep I am determined to be satisikd. RO Verify Reactor Trip EOP 35 E-0 Section 2 Page 26 of 47-
Title:
LOIT NRC #6 INSTRUCTOR GUIDE Reviskm: R ID: NRC6 Task Time IDA/Malf instructor Information/ Activity Assign Expected Response Standan! Comp , Step I EOl' 35 E-0, Check n: actor trip and bypass breakers - OPEN Step 1 Check digital nxi position indicators - AT ZERO Check neutron Hux - DECREASING BOP Verify Turbine Trip EOP 35 E-0, Step 2 BOP Verify Pontr to AC Emergency EOP 35 E-0, Busses Step 3 BOP Check busses 34C and 34D - AT EOP 35 E-0, LEAST ONE ENERGlZED Step 3.a , i Check busses 34C and 34D - BOTII EOP 35 E-0, . ENERGlZED Step 3.b Si has failed to auto actuate. CREW CREW Check If SI Is Actuated EOP 35 E-0, [*l uill need to actuate Si and procccd Step 4 on RO Verify Safety Injection Actuation EOP 35 E-0, annunciator- LIT Step 4.a hion 2 Page 27 of 47 ;
Title:
LOIT NRC f_in INSTRUCTOR GUIDE Revision: 9 ID: NRC6 Task Time IDA/Malf Instructor Information/ Activity Assign Expected Response Standant Comp US - Steps 5 through 14 may be EOP 35 E-0, perfixmed in any order. Step .5, NOTE US - RPCCW valve checks may be EOP 35 E-0, perflumed in any order prior to Step 5. step 14 completion. NOTE RO Verify Service Water Pumps - AT EOP 35 E-0, LEAST ONE PER TRAIN RUNNING Step 5 RO Verify Two RPCCW Pumps - ONE EOP 35 E-0, PER1 RAIN RUNNING Step 6 RO Verify ECCS Pumps Running EOP 35 E-0, Step 7 Check SI pumps - RUNNING Check RIIR pumps - RUNNING Check two charging pumps - RUNNING NOIE RCPs will need to be tripped on BOP Verify AFW Pungs Running E-0. Step 8 Foldout Page Criteria MDAFW pumps failed to auto-start. BOP Check MD pumps - RUNNING E-0, Step BOP should manually start. 8.a Section 2 Page 28 of 47
Title:
LOIT NRC #6 INSTRUCFOR GUIDE . Revision: 9 ID: NRC6 Task Time 10A/Malf Instructor Information/ Activity Assign Expected Response Standani Comp BOP START ptunp(s) E-0 Step 8.a. RNO [*] BOP Check ttabine - driven pump - E-0. Step RUNNING, IF NECESSARY 8.b BOP Verify FW Isolation EOP 35 E-0, Stty 9 IJOP - Check SG feed regulating valves - CLOSED BOP - Check SG feed regulating bypass valves - CLOSED BOP - Check FW isolation trip valves
- CLOSED _
RO - Check SG blowdown isolation valves - CLOSED RO - Check SG blowdown sample isolation valves - CLOSED RO - Check SG chemical feuf isolation valves - CLOSED Section 2 Page 29 of 47
Title:
LOIT NRC #6 ' INSTRUCTOR GUIDE Revision: 9. ID: N_RC6 Task Time IDA/Malf Instmetor information/ Activity Assign Expected Response Standani . Comp RO Check If Main Steam Lines Should Be EOP 35 E-0, Isolated Step 10 RO Verify Ctmt pnssure GRENIER EOP 35 E-0,
'HIAN 18 psia Step 10.a I O P/ M RO any SG pnssure LESS 11IAN 660 psig IOP Verify MSIVs and MSIV bypass EOP 35 E-0, valves - CLOSED Step 10.b RO Check if CDA Requinxi EOP 35 E-0, Step 11 RO Verify Ctmt pressure is GREATER EOP 35 E-0,
'llIAN 23 psia Step I1.a m
RO Ctmt spray is initiated US DO NOT perform steps Ilb,1Ic, and EOP 35 E-0, 11d. Proceed to next immediate Step 11 a. action. RNO 10P Verify CAR Fans Operating In EOP 35 E-0, Emergency Akxle Step 12 i Section 2 Page 30 of 47 i
Title:
IDIT NRC #6 INSTRUCTOR GUIDE Resision: 9 Ilh NRC6 Task Time IDA/Malf Instructor Information/ Activity Assign Expected Response Standant Comp BOP Check CAR fan status: EOP 35 E-0 Step 12. CAR fans A and B - RUNNING CAR fan C - STOPPED BOP IE CDA is NOJ' actuated, BIEN EOP 35 E-0 START /STOP CAR fans as necessary. Step 12.a RNO RO Verify RPCCW Ctmt supply and EOP 35 E-0, retum header isolations - OPEN Step 12.b , RO Verify Tmin A and B RPCCW supply EOP 35 E-0, and retum to chill unter valves - Step 12.c OPEN RO Verify CIA EOP 35 E-0 Step 13 US/ Check ESF Gmup 2 status columns 2 EOP 35 E-0, RO through 10 - LIT Step 13.a Several IIPSI valves failed to RO Verify Proper ESF Status Panel EOP 35 E-0, [*] reposition as nxluired. 'Ihe Indication Step 14 operators are expcoted to rqxsition the valves IAW the RNO column of Verify ESF Group 1 lights - OFF step 14. Verify ESF Group 2 lights - LIT Section 2 Page 31 of 47
'litle: LOIT NRC #6 INSTRUCTOR GUIDE - Revision: 0 ID: NRC6 Task Time IDA/Malf - Instructor Information/ Activity Assign Expected Response Standarti Comp IE Main Steam Line Isolation has occumx1, TilEN Verify ESF Group 3 lights - LIT IF CDA has occumxi, T11f24 Verify ESF Gmup 4 lights - LIT Crew should perrmn a short brief RO Determine If ADVERSE CTMF EOP 35 E-0, and acknowledge alarms, then come Conditions Exist Step 15 out of" Master Silence", prior to continuing. ADVERSE CIMf will pmbably be - Ctmt tempcmture GREATTIR in based on CIMf Tempemtum 'IIIAN 18(rF
-m Ctmt mdiation GRENFER TIIAN 10'%r Step 16 notes do NOT apply. SI CREW To pmvide adequate ECCS flow, RCS E-0, Step will not be reset subcooling and PZR level should be 16 Caution monitored to ensure that the charging pump is manually restarted if RCS subcooling based on core exit TCs is less than 32"F or PZR level is less <
than 15% t CREW If offsite pourr is kW aller SI reset, E-0 Step ) manual action to restart safeguirds 16, Caution equipment may be rtxiuinxi. . Section 2 Page 32 of 47
Title:
LOIT NRC #6 - INSTRUCTOR GUIDE- Revision: 0 ID: 'NBfs Task Time IDA/Malf Instructo. Information/ Activity Assign Expected Response Standant Comp CREW IX) NOT reset CDA if recirculation E-0. Step spray pumps are required and have not 16, Caution automatically staned. RO Verify ECCS Flow EOP 35 E-0 Step 16 RO Check charging pump flow indicator - EOF 35 E-0, FLOW CONSIS1] INT WITil RCS Step 16.a PRESSURE RCS Pressure may have drilled RO Check RCS pressure - LESS TIIAN EOP 35 E-0 dmm to this point. RCP TRIP 1650 psia (1950 psia ADVERSE Step 16.b criteria might be met by this point CIMI) RO Check high pressure SI pump flow EOP 35 E-0, indicators - FLOW CONSISlTNT Step 16.c WTill RCS PRESSURE RO Check RCS pressure - LESS TIIAN EOP 35 E-0 300 psia (500 psia ADVERSE CTMT) Step 16.d RO Verify RIIR Flow EOP 35 E-0 Step 16.c NOlli: CIMF should be BOP Verify Total AFW Flow - GREATTIR EOP 35 E4).
. ADVERSE due to tempemture. 'the IllAN 530 gpm crew simuld maintain > 530 gpm until > 42% NR in at least intact SG.
Section 2 Page 33 of47 u _ ~ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _
Title:
LOIT NRC #6 INSTRUCTOR GUIDE Revision: 9 ID: NRC6 Task Time IDA/Malf Instructor Information/ Activity Assign Expected Response Standartl Comp IK)P Verify AFW Valve Alignment - EOP 35 E-0, ' PROPER EMERGENCY . Step 18 ALIGNMENT Several llPSI Valves have failed to RO Verify ECCS Valve Alignment - EOP 35 E-0, [*] ) repwition PROPER EMERGENCY Step 19 ! ALIGNMENT US Check Plant Status EOP 35 E-0. Step 20 - SM/ Verify SLCRS docus - CLOSED EOP 35 E-0 SECUR Step 20.a ITY
.When requested, repxt all SLCRS SM Request S rurity Close all SLCRS EOP 35 E-0, doors are eksed doors. Step 20.a.
RNO i Section 2 Page 34 of 47
Title:
LOIT NRC #6 INSTRUCTOR GUIDE Resision: 11 1D: N_BG ! Task Time IDA/Malf Instructor Information/ Activity Assign Expected Respmse Standani Comp Clli will have actuated on liigh Crew Check if CBI actuated CIMI' Pressure I) CBI annunciator - LIT Verify Cl31 status EOP 35 E-0 Step 20.c RO Verify ESF Group 2 lights - LIT EOP 35 E-0. Step 20.c.1 T BOP Control Building purge supply fan and EOP 35 E-0, purge exhaust fan - NOT RUNNING Step 20.c.2 BOP Contml building air bank isolation EOP 35 E-0, valves - OPEN (after 60 seconds) Step 20.c.3 13OP STOP kitchen exhaust fan EOP 35 E-0, Step 20.d T+3 minutes IKXJHI Report that the control imilding SM/ Ckse and Dog (as applicabic) Control EOP 35 E-0, of request pressime hoemdary doors are closed PEO Building pressurr bo mdary doors Step 20.e andtk W RO Check RCS Tempemture EOP 35 E-0. Step 21 ' RO Verify RCS cold leg WR temperature - EOP 35 E-0, STABLE AT OR TRENDING TO Step 21.a 560"F Section 2 Page 35 of 47
Title:
LOIT NRC #6 INSTRUCFOR GUIDE ' Revision: !! ID: NRC6 Task ' Time IDA/Malf Instructor Information/ Activity - Assign Expected Response Standani Comp US Perfixm the applicable action: EOP 35 E-0. Step 21.a. RN3 US - IE the tempemture is LESS EOP 35 E-0 ' TIIAN 56(r AND decreasing. Step 21.", , 11IEN Proceed to step 21c. RNO IlOP Stop dumping steam: EOP 35 E4). Step 21.c IlOP Place both condenser steam dump EOP 35 E-0. ; interlock selector suitches to OFF Step 21.c.1 i IlOP Close SG atmospheric dump valves EOP 35 E-0. Step 21.c.2 130P Verify the fblioning valves - CLOSED EOP 35 E-0. Step 21.d
- MSIVs MSlV bypass valves ,
BOP Maintain total feed flow between 530 EOP 35 E-0, and 600 gpm until NR level is > 6% Step 21.c (> 42% Adverse) NR level. { RO Check PZR Valves EOP 35 E-0, Step 22 . Section 2 Page 36 of 47
_ .. _ . ~ .
Title:
LOIT NRC #6 INSTRUCTOR GUIDE Revision: D ' - ID: NRC6 t Task . Time iDA/Malf Instructor information/ Activity Assign Expected Response Standaruf Comp RO Verify PORVs - CLOSED EOP 35 E-0 Step 22.a Verify normal PZR spray valves - EOP 35 E-0, CLOSED Step 22.b RO Verify PZR safety valves - CLOSED EOP 35 E-0 Step 22.c ; US To prevent damage to the RCP scal (s). EOP 35 E-0, seal injection flow should be Step 23 maintained to all RCPs. CAUITON
'lhe leak is large enough to nxtuire US Check If RCPs Should Be Stopped EOP 35 E-0, the RCPs tripped Step 23 RO Verify charging or SI pumps - AT EOP 35 E-0 LEAST ONE RUNNING Step 23.a RO Verify RCS pressure - LESS llIAN EOP 35 E-0, 1500 psia (1800 psia ADVERSE Step 23.b CTMO RCPs should have aheady been US Stop the RCPs EOP 35 E-0, tripped Step 23.e 10P/ Check if SG Secondary Ik>undaries EOP 35 E-0 RO Are Intact Step 24 IOP/ Check pressur in all SGs EOP 35 E-0, RO Step 24.a t
Section 2 Page 37 of 47
Title:
LCfT NRC #6 INSTRUCTO!A GUIIE Re-isines: 9 IIh NRC6 TA Timee IDA/Malf Instructor Infor nation /Acthity Asign FW Response Standani Cassp : IX)lY - NO SG PRESSURE EOP 35 E-0 ! RO DECREASING IN AN Step 242 I UNCONTROLLED MANNEI - IX)P - NO SG COMPIETELY
- DEPRESSTJRIZED Ensure crew request activity BOP Check If SG Tubes Are Intact EOP 35 E-0. i sampl:s with IIP coverage. Step 25 ,
Verify trend history and alarm status ! of radiation monitors Main steam line- NORMAL Corxicnser air ejector-NORMAL i i SG blomkwm - NORMAL , } BOP Check steam gewater levels - NO SG EOP 35 E-0 ! LEVEL INCREASING IN AN Step 25.b !
- UNCONIROLLED MANNER l Acknowicdge sampics request. US Align all SGs for activity sampics. EOP 35 E-0. j Ertsure that the operators require Stcp 25.c !
IIP coverage. ! RO RESET SG blomknm sampic isolation EOP 35 E-0. l Step 25.c.I t i hkm 2 Pace 38 of47 ! l f
... _ - - - . . - - - - _ _ = - - -
Title:
LOIT NRC #6 INSTRUCTOR GUIDE Roision: R IIh . NRC6 , Task Tune IDA/Malf Instructor Inferination/Actisity Assign Expected Reponse Standard Casup RO. OPEN SG blowdosm sar.pic isolation EOP 35 E-0, valvc(s) Step 25.c2 Acknowledge request US/ Request Chemistry obtain actisity EOP 35 E-0 ; SM samples using IIP coverage Step 25.d ! RO Check If RCS Is Intact EOP 35 E-0. Step 26 I CMS *RE22 pir-trip not nmnal RO - Verify Ctmt radiation using ; 3 CMS *RE22 (pre-trip)- NORMAL i i y CIMF Iristogram, not normal RO - Verify Ctmt radiatic-: using i radiation monitoring gmup histogram (CIMI)- NORMAL CIMF pnssure, slowly increasing RO - Verify th pressure - - NORMAL i i RO - Verify Ctmt recirculation sump l Icvel- NORMAL j if RCS tcu,uuture has decreased US/ Initiate monitoring of CSF Status Trees EOP 35 E-0 ! sufliciently. an orange or red path Crew and Go to E-I. Ioss of Reactor or Step 26 : on Integrity may exist. If so, the Secondary Coolant. RNO I crew should transition to I-R-P.1 f l 1 i Sectim ' Page 39 of47 l 1
Title:
LDIT NRC #6 INSTRUCTOR GUIIE Resision: 9 I ID: HRC6 . Task i Time IDA/Malf Instructor Information/ Activity Assign Expected Response Standard Casup l FR-P.1 STEPS If R%NT level decreases to I"ISS FR-P.I. Step i TIIAN 520.000 gal. ECCS must be 1. Caution [
- aligned for cold leg reciruciation using i ES-13. Transfer to CWd Leg l Recirculation ;
t NO. RCS pn:ssure will be US'RO Check RCS Pressure - GREATER FR-P.I. Stcp i appmximately CIMF pnsmre. TIIAN 300 psia (500 psia ADVERSE 1 CTMT) ! Perfirm the applicabic action- FR-P.I. Step 1.RNO IE RIIR pump Ikw is LESS
. 11IAN 1000 ppm 11IEN :
Pmcced to step 2. RIIR pump flow will be > 1000 - IE RIIR pump flow is gpm. GREATER TILAN 1000 ppm , 11IEN Go to pmcedun and i
~
j- , step in efTcct. . If CIMT pressure has exceeded 23 i psia, an ORANGE path on CIMT ; will be pn:sent and the crew should tmnsition to FR-7_1. O i i i i 4 j, Section 2 . Page 40 of 47 1
Title:
LOIT NRC M INSTRUCIUR GUllW, Redsion: 9 I IIh NRC6 ! Task ,
'linie IDA/Malf Instnscior Infonnation/ Activity Assign Ewed Response Standard Casup s
- FR-Z,1 STUS USRO Verify OA (ESF Gmay 2 Sembs FR-7_1. Step columes 2 Dsough 10) !
] US Vesify O R FR-7.1. Step
' [
2 i RO Check RIW Ctml supply and retum FR-Z.l. Step header isolation uhrs - CLOSED 2.a l RO Check RPCCW pumps - STOPPED FR-7_1. Step r 2.b l l RCPs should be oft RO STOP all RCPs FR-7_1. Step ! ^ 2.c If ECA-1.1. Loss of Emergwcy FR-7_1. Step Coolant Recintulatkm. is in progess. 3 i Ctmt spray should be operated as CAUIlON } , distcied in ECA-1.1 rather that s(cps 3. i
- 4. and 7 j i SCO Verify Quench Sprav Speese FR-7_1. Stcp i Opesasion 3 RO Ch
- ck RWSTIcvel- GRENER FR-7_1. Stcp ,
11IAN 100.000 gal (annunciator 3.a j RWST EMMY QSS PP OFF m j j MB2A 5-2 nc4 lit) ; i Sectkm 2 Page 41 of 47 t
TWie: LOIT NRC #6 INSTRUCIDR GUIDE Resision: 9 IIh NRC6 Task Tense IDA/Malf Instructor Infonnation/ Activity Av.ign Expected Response SW Casup RO Verify quench spmy pumps - FR-7.1, Stcp RUNNING 3.b
- RO Verify quench spray pump discharge FR-Z.l. Step vahes (3QSS*MOV34A and 3.c 3QSS*MOV348)- OPEN RO Check quench spray system - FLOW FR-Z.I. Step EXISTS IN AT LEAST ONE TRAIN 3.d US Proceed to step 5. FR-7_1. Step 3.c 4
BOP SFDP All Main Osudasing Water FR-7_1. Step I%ngs 5 BOP Oueck Containneent Veneitseion FR-Z.1. Step 6 Verify CAR fans - STOPPED Verify CRDM fans - STOPPED SCO Verify Reciscidseien Sprar Sysenn FR-Z.l. Step Operation 7 RO Check CDA signal- PRESENT FR-7_1. Step AFER 11 minutes (annunciator 7.a CIMF RECIRC PUMP AUFO START SIGNAL on MB2B l-8 lit) Section 2 Page 42 of 47
Title:
II)lT NRC #6 INSTRUCTOR GUIDE Resision: R ID: NRC6 Task
'linee IDA/Malf Instnscior Infornostion/Acthity Assign Expecial Response Standard Cosep RO Verify recirculsion spray pumps - FR-Z.l. Step RUNNING 7.b RO Verify recirculsion sprav pump FR-7_1. Stcp ,
suction isolmion vahrs - OPEN 7.c l RO Verify recirtulsion spray pump FR-Z.l. disciurg-isolation vahrs - OIBI Step 7.d RO Verify recirculsion spray - FIf)W FR-7_1. Step EXIS'IS IN AT LEAST ONE1 RAIN 7.e RO Verify ESFSems Phasel Gsoup 4 FR-Z.1, Step Ughts - IJF 8 US/ Verify Main Seesen I.ine bolation FR-Z.l. Step BOP 9 Check MSIVs and MSIV j bypass vahrs - CLOSED Check ESF Stsus Gmup 3 lights - LIT Section 2 Page 43 of47
Title:
LOIT NRC #6 INSTRUCTOR GUIDE Revision: D ID: NRC6 i rask Time !DA/Malf Instnscior Information/Activhy Assign Exgweted Response Standani Casap IK)P/ Verify Main FeedmiterIsolmeion FR-7_l. Step RO 10 Verify MD AND TD FW pumps - TRIPPED Verify FW isolation trip vahrs
- CLOSED Verify SG feed regulating vahrs - CLOSED Verify SG feed regulating i
bypass valves - CLOSED At Ican one SG must be FR-7_l, Step maintained amilable for RCS 11, cookkmn. CAlmON
- If all SGs are faulted, at least FR-7_1. Stcp 100 ppm feed fimv should be i 1, maintained to cach SG. CAlmON SCO Oseck If Auxiliary Feedwater Fhm FR-7_l, Step Should Continue To All SCs iI IK)P/ Check pressure in all SGs FR-7_1. Stcp RO 11.a 1 -
NO SG PRESSURE i DECREASING IN AN UNCONTROLLED MANNTR Section 2. , Page 44 of47 ,
- i
I
Title:
LOIT NRC #6 INSTRUCTOR GUIDE Resision: 9 ID: NRC6 Task
' Time IDA/Malf Instructor Information/Actisity Assign Expected Response Standasd Consp NO SG COMPLEELY DEPRESSUR173D US Oseck thdingen Concenhusion IR-7.1. Step 12 PEO Place hydrogen monitor in senice FR-7_1. Step using OP 3313A. Ilydmgen 12.a l Recanbiners and Recombiner Building Ventilation. section 7.5.
i 3 SCO Verify hydmgen concentration - LESS FR-7.1. Step a TIIAN 5% 12.b ' US Verify hydmgen unuedion - I.ESS FR-7.1. Step TlIAN 0.5% 12.c SCO Pmetui to step 15. FR-7.1, Step 12.d ; SM Notify DSEOof thdogen IR-7.1. Step Concentration imide Contaisanent 13 ! t i US Iwodically MumieorIbeogen FR-7.1. Step , i Concennation (every 8 leones) 14 ; L lYocedure transition to E-1 uns in SCO Go to 5%cedine and Step In Effect FR-7.1. Step pmgrts 15 i Section 2. ISpe 45 cf 47
6 - +. u _ A iA Lu,.-
Title:
IDIT NRC #6 INSTRUCTOR GUIDE Roision: R ID: NBC6 Task Time - IDA/Malf Instnsctor Inforenation/ Activity Assign Expected Response Stambrd Camp , US To gwvent scal damage, scal injection E-1. Step I thr.v should be maintained to all RCPs. CAUTION lhe US should direct the opemtors US Note- Foldout page must be open. E-1. Step 1 ! to gxm their Foldout Page Books NOlli for E-1 T= Coniplete the transition to E-1, FRFF7E I 1 4 E I i i Section 2 Page 46 of'47
ID Numirr: NRC6 Revision: 0 EVAll1ATOR GUIDE SillEI"ITOINICAL ADVISOR EVA111NIlON GUIDE - IWF SOWARIO IMOlGED STA SIMUlXIOR EXAM SCGARIO OUIXI1ONS NO STA FOR LOIT EXAM o 1 Section 2 Page 47 of 47
SECI1ON 3 SIMUlA10R EXAM SEQUENCE OF EVEN1S SUMSLARY
Title:
OPERAT10NAL EXAM iD Number: NRC6 Revision: 0 TlME 'QA INS 111UC1DR AIDS DESCRilrnog i MALF. RF.10
- T=0 i RD0359 rseu=1 CllD Grp 2 rod D12 (Dropped R(x!)
RD0361 rseu=1 CBD Cup 2 rod 118 (Dropped R(xi) i RCO2A sev =5% ramp =180 seconds llT=1 loop #11 lot Leg mpture FW20A AFW Pump Fall to Auto Start, "A" i FW20ll AFW Pump Fail to Auto Stait, "B" i RPilF CVCS Components fall to reposition RP07A Failure of Tr "A" Si to Auto Actuate RP0711 Failure of Tr "B" Si to Auto Actuate IIT=1 is Reactor Trip 13reakers Open T = Stop Valve Closed RX16A sev4% PT505 fails low T = 2nd llA Transfer Pump staned
- RIXM60 Rod M4 sticks in position ;
T = replace fuse RIX)360 rseu=1 Rod M-4 drop (when rscu=1 is activated 3 rods will drop) '
- Section 3 Page 48 of 1
. _ . _ _ _ _. ._ .~ . _ _ _ . _ . _ . _ . _ _ _ _ _ _ . .
1 SECHON 4 l VAUDA110N CHECKUST
Title:
. LOIT NRC ff6 ID Number: NRC6 Revision: 0 RenWe functions: Verified by All remote functions contained in the guide are certified. Malfunctions: All malfunctions contained in the guide are certified. t laitial Conditions; lhe initial condition (s) contained in the guide are certified or have been developed fmm certified ICs in accordance with NSEM-4.02, simnIntor onerating I imits: The simulator guide has been evaluated for operating limits and'or anomalous response. Test Run: .
- lhe scenario contained in the guide has been test mn and validated (validation sheet completed, next page)on the simulator. Simulator response is reasonable and as expected.
Examination Scenario Review The dynamic examination resiew checklist is complete. Section 4 Page 1 of 3
3 SFfl10N 4 i OPERA 110NAL EXAM VAUDA110N SK[TIr ! Prognun
Title:
__ Licensed Onemtor Reaualification Trainine i
Title:
LOIT NRC (16 4
- 1D Number
- IEC6 Resision: 0
- )
j 13y their signature below, the people acknowledge the confidentiality and validity of the material contairal within and will not willfully disclose its contents to others enrolled in the Millstone ' livre l.icensed Operator initial Training Progmm. 4
, VAUDA1ED BY:
Print Signature Date SM / US i RO / ! 130P /
/
/
/
1 /
/
l / I Section 4 Page 2 0f 3
l SECI10N 4 IWNAMIC EXAMINATION REVIEW 00KKUST Note: 'lhe following criteria list scenario traits that are numerical in natun:, A second set of numbeni indicates a range to be met for a set of two scenarios. Quantitative Attributes 7 13. Total nulfunctions inseited: 48/1014 4 14. Malfunctions that occur after EOP entry: 14/3-6 3 15. Abnonnal Events: 1-2/2-3 2 16. Major Tnnsients: 12/2-3 3 17. EOPs used beyond primary scram response EOP: 13/3 5 0 18. EOP Contingency Procedures used: 0-3/1-3 70 19. Approximate scenario mn time: 45-60 minutes (one scenario rnay approach 90 minutes) 50 % 20. EOP run time: 40-70% of scenario run time 2 21. Crew Critical Tasks: 25/58 yes 22. Technical Specifications are exercised during the test COMMENTS: Section 4 Page 3 of 3 _- _= um
SEC110N S REERENCES AND C1til1CALTASK11 TACKING { I
Title:
LOIT NRC #6 j l ID Number: NRC6 Revision: 0 I
- 1.
References:
AOP 3571, Instnunent Failure Response. AOP 3575, Rapid Downpower AOP 3552, Rod Control System hialfunction EOP*35 E-0 Reactor Trip or Safety injection EOP35 FR P.1 Response to imminent PIE Conditica EOP35-FR-Z.1 Response to liigh C1Mr Pressure EOP35- E 1 Loss of Reactor or Secondary Coolant EOP* ERG-1IP Westinghouse Owners Group ERG llP lbckgmund Document EOP* Step-Doe hiillstone Unit 3 Step Deviation Document EPIP 4400 Event Assessment, Classification and Reportability Tech Specs Technical Specifications for hip 3 OP*3272 EOP Users Guide NUREG*1021 rev 8 Examiners Standards
- 11. Diti2tLlasks Covered in this Test:
NUE : Critical Tasks are nurked by an (*l within guide CRillCAL CRIIlCAl. TASK K/A >/= 3.0 itAsis FOR SEl ECTION TASK # DESCRIPTION Exams only E-0--D hianually actuate at least one 006 030 Failure to nunually actuate SI under the tmin of SIS actuated A2.01 postulated plant conditions constitutes safeguards before tnmsition 4.5/4.8 " mis-operation or incorrect crew past step 4 of E-0 perfomunce that leads to degraded ECCS capacity." E-0 --O Close ctmt isolation valves 4.1/4.1 Failure to close at least one valve in such that at least one valve on 006 000 each etmt penetration, constitutes " mis-each phase-A penetration is A3.03 operation or incorrect crew perfonnance closed by the end of the which lads to the degnvMan of any scenario. banier to fission product release." Section 5 Page1ofI
- SECHON 6 SONARIOINmAL CONDm0NS -
Reactor Power: 10(M 1 Operating llistory: - 200 days on Line
- RCS Horon: - 988 ppm Core Bumup: 10,500 MWD'MTU Condensate Demins: 7 IN SERVICE - -
Evolutions in Progress: None, lhunderstomi Wamings have been issued for the next 4 to 6 j ' hours. Major Equipment OOS: "A" Smice Water Pump - Bearing Replacement "A" Motor Driven AFW Pump - Motor Ground Troubleshooting -!
"B" Stator Water Cooling Pump - Seal Replacement l I
i 4 Crew Instmetionst _ 1he "A" Service Water Pump is mady for retest. SillFf fmm "C" Service Water Pump to the "A" Service Water Pump, IAW OP 3326, i section 7.7. Upon completion of the SWP shift, conduct the weekly Cycle test of the llP Turbine Stop Valves IAW SP 3623.2, section 4.2,- t Planusimnh'or werences: i F ' Rad Monitor Historical Data-Simulator Rad Monitor historical data not valid prior to the , beginning of this exercise.
- Reactor Makeup System batch counters different from plant system.- (if required to perfonn a ,
makeup evolution, refer to the RO procedure cart for setting the Batch Counter.) Simulator main steam atmospheric dump valve controllers (B and C) different from plant. 1 , 1 ,I
-i
- t Section 6
,, Page1 of1 y ups wg-- 'a -dv--tr*t-y*-Mgg- *-n-na- -# ey efi- w an ,ym+rta+r-,-,y-'1rwaP-w ->-W 'W
a2e , A 4 - _ - C- - ._-~..___,.e C R )G. S un ,, q ,,, L Q j h21iTc'N C#)nmted g,cw% 9'7s /oo gt
l RO1 Which of the following conditions would require the crew to initiate immediate boration of the RCS? -
- A. In MODE 5, with dilution paths NOT isolated and cold calibrated pressurizer level at 50% core burnup is 6.000 MWD /MTU and RCS boron concentration is 2050 PPM. (See attached curves.)
B. With the plant at 100% power, an unexplained event is causing Tave and reactor power to increase, and control rods to insert. C. After a reactor trip, with the crew performing ES 0.1, " Reactor Trip Response", the RCS cools down uncontrollably to 540'F. D. While performing a rapid downpower IAW OP 3275, the ROD CONTROL BANKS LIMIT Lo Alarm is received. ANSWER:
- B.- With the plant at 100% power, an unexplained event is causing Tave and reactor power to increase, and control rods to insert.
JUSTIFICATION: "B"is correct, since this is indication of an unexplained positive reactivity addition. ,
"A" is wrong since there is adequate boron per the " loops filled" curve, and PZR levelis > 40%.
"C" is wrong since the setpoint is 530'F, "D"is wrong since Rod LO LO is the immediate Borate setpoint.
REFERENCE:
AOP 3566 Entry Conditions K/A: 000024.EK3.01 Emergency Boration Requirem60ts Exam llam: 2373 1 4-
=
D
RO 2 The following plant conditions exist:
- The plant has just completed a 428 day full power run.
- The plant is cooling down in MODE 3
- RCS temperature is 490'F e RCS pressure is 1800 psia e Excess letdown is in service
-)
A leak developa in train *B* of the RPCCW sys'am causing the train 'B' surge tank level to INCREASE. WHICH of the following could be the potential source of leakage into train *B'? I A. Excess letdown heat exchanger B. *B" RHR heat exchanger C. Letdown heat exchanger I D. Seal Water heat exchanger ANSWER: A. Excess letdown heat exchanger
REFERENCES:
P&lD 1 CC B2020A, CC JUSTIFICATION: Only the letdown heat exchanger, the excess letdown heat exchanger and the seat water heat exchanger have reactor coolant moving through them in MODE 3 for the stated conditions. The letdown heat exchanger is on Train "A*, The seal water return pressure is 30 - 50 psig, or less than RPCCW pressure. A leak into the "B" RPCCW surge tank can only come from excess letdown heat exchanger. The *B" heat exchanger is isolated from the RCS. K/A: APE 026 A2.01,3.5 97 Exam 8 - 4
't e rww.c,..n ev g - , c sw y - -r,, -,- ,,.e,.
- , . ~~ . . . , ._,,,,,+.m-y.,, w--,,-w.-.-.,,.-,-~e , - ,,re- .-, -.w,-~,.e--.... y--.e- ,r c - e . , - , , ,
RO3 Which of the following signals will cause the RPCCW to CDS cross ties in containment (MOV226 229)to close? A. High RPCCW flow rate B. Containment isolation Phase A C. Containment isolation Phase B D. Low RPCCW surge tank level ANSWER:
- D. - Low RPCCW surge tank level JUSTIFICATION: LSK 91C K/A: 026 EA 1,05 - RPCCW Surge Tank, include level control, alarms in RMS.- - EXAM BANK ITEM: 2177
RO4 The following conditions exist:
. The plant is currently in operational mode 2.
. Reactor power is 4%
Prepvations to increase power to 100% are in progress. The Pressurizer Pressure Channel Selector Switch is in the PT 455/PT-450 position.
. The annunciator for HIGH PRESSURE ALARM, actuates.
. PORV PCV-450 opens.
Actual pressurizcr pressure is 2200 psia and decreasing rapidly. Which one of the following describes the instrument malfunction which caused this transient and the response of the PORV (PCV-456) A. PT 455 failed high and PORV will remain open in AUTO. B. PT-456 failed high and PORV will close in AUTO when actual pressure decreases
- below 2200 psia C. PT-456 failed high and PORV will remain open in AUTO D. PT-455 failed high and PORV will close in AUTO when actual pressure decreases below 2200 psia ANSWER
B. PT-456 failei high and PORV will closein AUTO when actual pressure decreases below 2200 psia K/A: 027AA1.01 Ability to operate / monitor pressurizer heaters, spray, PO3Vs. JUSTIFICATION: In the CHl/CHil position PORV456 is controlled by PT456. On high pressurizer pressure on channel 456 the PORV will open and wi:1 close when 2/4 pressunzer channel decrease to less than 2200 psia if the PORV is in AUTO. (B is correct) A is incorrect because PT 456 failed and the PORV will close in AUTO. C is incorrect because PORV will close if in AUTO. D is incorrect because PT456 failed not PT455. Modified question 2118
RO S Given the following situation: A safety injection actuation has occurred due to a steam line break upstream of the MSIV.
- The operators have isolated the affected SG in accordance with E 2
- Faulted SG isolation".
Which one of the following correctly describes the plant response, during the next hour, once the affected steam generator is empty? (Assume no further operator actions.) A. Pressurizer pressure, level, and RCS hot leg temperatures stabilize. B. Pressurizer pressure, level , and RC3 hot leg temperatures continue to decrease. C. Pressurizer pressure, level increase, RCS hot leg temperatures continue to decrease. D. Pressurizer pressure, level, and RCS hot leg temperatures increase, ANSWER: D. Pressu: . er pressure, level, and RCS hot leg temperatures increase. JUSTlFICATION: Once the faulted SG has blown dry, ECCS injection flow will cause an increase in pressurizer pres.sure and level. Decay heat will cause RCS hot leg temperatures to increase. As a result, "D"is the correct answer. KIA: 000040K1.03 3.8/4.2
- Objective: - E0203C 95 LolT NRC Exam 1
0 e &
RO6 l Whi!e oerforming E 3," Steam Generator Tube Rupture", prior to initiating the RCS ! COOLDOWN, the Unit Supetvisor directs you to determine if the ruptured steam generator pressure is gleater than 420 psig. If pressure is less than 420 psig, E 3 directs you to transition to ECA 3.1, "SGTR with Loss of Reactor Coolant Subcooled Recovery Desired". Which of the following describes a reason for ensuring the ruptured SG pressure is greater than 420 psig prior to performing the cooldown of the RCS? A. To ensure subsequent cooldown does not cause a PTS concern. B. - To ensure the ruptured SG pressure is greater than the intact SG pressures. C. -To ensure that a low steam line pressure Safety injection does not occur, - D. To ensure subsequent RCS cooldown does not cause a red path on suberiticality due to
=
- a loss of shutdown margin.
ANSWER: A. To ensure subsequent cooldown does not cause a PTS concern.
REFERENCE:
E 3, Step 13 Basis, WOG Background Document JUSTlFICATION: Although it is important that the ruptured SG pressure be greater than intact SG pressure, this verification is made at step 13 of E 3, and appropriate action taken if these conditions do not exist ("B"is incorrect). Since intact SG pressure must be less than ruptured SG pressure to maintain RCS subcooling, the RCS cooldown that would be required to maintain the necessary pressure differential between the ruptured and intact SG's would present an PTS concern in the RCS ("A"is correct). Distracter "C" cannot be correct because automatic Si actuation at this point in the recovery would have been defeated since Si is reset in Step 8 of E 3. "Dis incorrect because a suberiticality red path only comes in for reactor power greater than 5% which could not occur based on the conditions provided. K/A:- WEST E08 EK2.2,4.0 Used 97 exam 8
l RO7 Given the following conditions:
- Reactor trip due to station blackout has occurred.
Natural Circulation cooldown has been established.
- The crew is in ECA 0.0 dumping steam at the maximum rate.
- The RO states that he is unsure if natural circulation is providing adequate heat removal.
Which one (1) of the following indications would indicate a patential problem _ with core heat removal by natural circulation. (Consider each condition independently). A. SG pressures have decreased from 700 psia to 600 psia and are now starting to decrease at a slower rate. B. Pressurizer level is 15% and decreasing while subcooling is 80*F and increasing. C. Tsor is 520*F and Teoto is 460'F and the AT between the two is increasing-D. Tso7 is 490*F and decreasing and CET's are decreasing slowly. f- ANSWER: C. Tsor is 520'F and Tcoto is 460'F and the AT between the two is increasing. JUSTIFICATION: For adequate natural circulation the following should be occurring: SG pressure stable or decreasing 4 This condition is satisfied. It is expected that the depressurization rate slows as pressure gradient decreases. (A is not a problem). The pressurl?.er is expected to empty under these conditions. The RCS is adequately subcooled. The contraction cannot be compensated for due to the loss of power. (B is not a problem). The core AT is greater than full power AT which is indicative of degrading natural circulation and cooldown. AT should be stable or decreasing during the cooldown, not increasing. Tsor and CET must be decreasing if a cooldown is in progress. K/A: 055 AK1.02 Natural Circulation Cooling
_. - = _ _ _ _ _ _ - ___ __ RO8 The plant is at 100% power when the following alarm is received on Main Board 8A: Inverter 1 Trouble Locally at Inverter 1, the operator observes that only the reverse transfer light is lit. Which of the following events is the likely cause of these alarms / indications? A. Inverter 1 is de energized. B. Inverter 1 DC feeder breaker has opened. C. Inverter 1 is being supplied from it's DC supply. D. Inverter 1 has transferred to it's alternate supply. ANSWER: D. Inverter i has transferred to it's alternate supply. K/A Rating: APE 057 A2.06, Inst. Bus Alarms for Alt Power
REFERENCE:
OP 3353.MB8A,15 JUSTIFICATION: "A"is incorrect, if the reverse power is lit, the UPS must have transferred to its alternate supply.
"C"is incorrect because the reverse transfer hght would not light if Inverter 1 is being supplied by its backup DC power supply. Additionally, the backup DC would have to go through the same UPS as the normal AC supply.
"B"is incorrect because if the cause was only the DC feeder breaker opening the UPS would still be supplied by its normal AC power supply.
"D" is correct because the local indication is that the inverter 1 is still powered otherwise there would be more alarms than just the reverse transfer.
97 Exam 8
RO9 Given the following conditions: The control room has been evacuated due to a fire.
- All remote shutdown system line ups have been completed.
- RCP #2 is running.
The RCS is borated to cold shutdown conditions ,
- A plant cooldown is in progress
! Which of the following describes the preferred sequence to depressurize the RCS to 1950 psia l in accordance with EOP 3504 over the next 4 8 hours. A. Use aux spray, use one PORV, de energize all pressurizer heaters. B. Use normal spray, use aux spray, use one PORV. C,. De energize all heaters, use aux spray, use one PORV. D. Use normal spray, use aux spray, de energize all pressurizer heaters. ANSWER: C. De energize all heaters, use aux spray, use one PORV. JUSTIFICATION: Normal spray is not available from the auxiliary shutdown panel, thus b and d are incorrect. The preferred way to depressurize the RCS is to deenergize heaters and allow the RCS to depressurize slowly due to ambient losses, if need to depressurize further, procedure guides them to place letdown in service and use aux spray. If letdown not available, then use one PORV. Thus c is correct. A is incorrect sequence is reversed. Tested caution note in procedure. K/A: 068 A1.12 Aux Shutdown Panels / controls New Question __mm __-a_m
RO 10 Plant conditions are as follows:
. Reactor Trip & SI have occurred No high head SI pumps or charging pumps are running
. RCS pressure is 800 psia
. Containment pressure is 20 pria
. RVLMS 0% (plenum)
CETs are 703'F and increasing The crew has properly transitioned to the appropriate functional recovery procedure. Why is the operrtor directed to check if one RCP should be stopped? l A. To minimize RCS inventory pumped or lost out to the break. B. To reduce the heat input into the RCS and rielp maintain SI inventory. C. To reserve one RCP for future use and aid in the plant recovery. D. To reduce the inventory lossed when the seal packages fail in the running RCPs ANSWER: C. To reserve one RCP for future use and aid in the plant recovery. JUSTIFICATION: EOP 35 F-02 Background document. One RCP is preserved to be able to be restarted in FR C.1 if plant conditions degrade to an inadequate cooling situation. K/A: 074K3.04 Tripping RCPs New Question 1 e l
RO 11 Plant Conditions e The operators are performing ES 1.3, " Transfer to cold leg recirculation," The RO is aligning the RHR and RSS Systems for cold leg recirculation using the recire. array per Step 2. The BOP operator informs the US of an Orange Path on the integrity CSF Status Tree. i Which of the following is the correct course of action? A. Perform FR P.1 immediately, B. Perform FR.: -n parallel with ES 1.3. C. Continue on with ES 1.3 unless a Red Path CSF Status is encountered. D. Complete ES-1.3, Steps 1 thru 3 then go to FR P.1. ANSWER: D. Complete ES 1.3, Steps 1 thru 3 then go to FR-P.1.
REFERENCE:
ES 1.3, NOTE prior to Step 1. Exam Bank 2577 s ... 1 d
i
; RO _12-The LOCAloutside containment procedure (ECA 1.2)is entered based on:
- : A.- Inadequate inventory of the containment sump to allow shiftover to cold leg recirculation.
B. Si actuation with indications that the RCS is lntact, SG tubes are intact, and SG t'oundaries are intact. j' C~ - Abnormal radiation level in the auxiliary building or ESF building with Si actuation. D. Abnormal radiation levels in the spent fuel buik . Nith Si actuation. i ANSWER: ! _ C. Abnormal radiation level in the auxiliary building or ESF building with Si actuation. JUSTIFICATION: Symptom which requires entry into ECA-1.2 from E-1/E-0.
"A"is incorrect - there are symptoms of a Loss of Emergency Coolant
- Recirculation.
L "B" is incorrect - they are possible indications for an inadvertent Si signal [ or extremef/ small break. i
- "D"is incorrect - because no safeguards release paths or components f are located in tN spent fuel building.
l K/A: W/E 04 EK 1.1 - 3.5 Components, Functions, and capacities. Neve
- i d
k I i i-c e b
RO 13 - The following conditions exist:
- A steam generator tube rapture has occurred.
The operators are present!y at step 4 of E 3 " Steam Generator Tube Rupture" verifying !
- ruptured SG level greater than 6% (42% adverse) level.
Which one of the following describes the basis for maintaining the ruptured SG level greater than 6% (42% adverse) level after the SG is isolated? > A. Providcs filtering of the element iodine present in the ruptured steam generator. B. Maintain a thermal stratification layer over the ruptured SG U tubes, allowing for depressurization of the RCS to the ruptured SG pressure. C. Maintain an adequate heat sink available in the ruptured SG. D. Minimize stresses on the SG U-tube bends to prevent subsequent failures when the RCS is cooled down and depressurized. ANSWER:
- 8. Maintains a thermal stratification layer over the ruptured SG U tubes, allowing for depressurization of the RCS to the ruptured SG pressure.
REFERENCE:
000037K3.07 4.2/4.4 JUSTIFICATION: WOG ERG background document for E 3
- Steam Generator Tube Rupture" s+ates the reason for a minimum level in the SG is to maintain a thermal stratification layer over the top of the SG U-tubes. This will insulate the affected SG steam bubble and prevent the affected SG from depressurizing during the RCS cooldown. This makes selection 'B' correct.-
K/A: 000037K3.07 Actions in EOPs OBJECTIVE: E0303C COMMENTS: SRO #77,95 NRC Exam
h RO 14 4 The plant is at 100% power. A loss of DC bus 5 occurs. Which of the following describes the f.xpected plant response?
- A. - The Tu aine Stop valves close due to low ETS pressure, the plant trips on Low Steam Jan' .ator level or OTAT.
B. Power is lost to the ETS pressure switches in the Turbine Trip / Reactor Trip circuit causing a reactor trip. ! C. ETS oil pressure is dumped causing the turbine to trip, which causes a reactor trip. D. Tu_rbine stop valve close due to low ETS pressure, causing a turbine trip on reverse power,- which causes a reactar trip.
' ANSWER:
B. Power is lost to the ETS pressure switches in the Turbine Trip / Reactor Trip circuit causing a reactor trip.
REFERENCE:
. AOP 3563, Attachment E JUSTIFICATION: ETS pressure is powered from 301C-1 A6, from battery bus 5 K/A: 058 A2.03 Impact on Indications 97 Exam 7 l
l
RO 15 A loss of off site power has occurred. l l While the Emergency Generator Loading Sequencer (EGLS)is in the process of completing the stepping sequence, an automatic safety injection occurs. Which of the following describes the operation of the EGLS upon initiation of the Safety Injection? A. Sequencer resets to step 0, Emergency Diesels remain running, Ernergency Diesel " output breakers remain closed, a:1 previously running loads remain running unless not required for the Si and the sequencers sequence the Si loads. B. Emergency Diesel output breakers open to strip the bus, sequencer reset to sicp 0, *SI" signal causes the Emergency Diesel output breakers to close and the sequencers to restart all the loads in the SI/ LOP stepping sequence. C. Sequencers stop at the step in progress, Emergency Diesels remain running. Emergency Diesel output breakers remain closed, the EGLS' start any Si loads that should be running and then resumes sequencing at the steps in progress in the SI/ LOP mode. D. Emergency Diesel output breakers open to strip the bus, Emergency Diesels remain runric.g but the breaker will not close for at least 6.8 seconds. The sequencers reset to step 0 in the SI/ LOP mode and will restart the entire sequence when 6.8 seconds have elapsed and the "second' SI/ LOP is sensed by the sequencers. ANSWER: A. Sequencer resets to step 0, Emergency Diesels remain running, Emergency Diesel output breakers remain closed, all previously running loads remain running unless not required for the Sl and the sequencers sequence the Si loads. K/A: APE 056 A2.47 Component, Capacity, Functions
REFERENCES:
, LSK 24-9A JUSTIFILAT!ON: "B" & 'D" are incorrect because the diesel output breaker does not open.
"C" is incorrect because the sequencer resets to time 0. "A' is correct, the sequencer resets, any loads not needed for the m ode, such as RPCCW pumps for CDA would be tripped, any Si loods would be staited.
97 Eram 8
RO 16 The control room is responding to an overpressure condition in No. 2 SG. SG pressure is currently 1250 psig and no safety valves or atmospheric relief valves are open. In order to depressurize the SG as fast as possible, in accordance with FR H.2 the operators should: A. Maximize blowdown flow from No. 2 SG. B. Feed No. 2 SG to cooldown the SG and lower the pressure. , C. Dump steam from the No. 2 SG to lower the pressure. D. Dump steam from the other SG's to cool down the RCS to depressurize the No. 2 SG. i ANSWER: C. Dump steam from the No. 2 SG to lower the pressure. JUSTIFICATION: The quickest way to remove heat from the SG is to dump steam. (C is 1 correct) A cannot remove much heat coo 1 pared to B, C, and D. ( A is incorrect) Feed will cool the SG but procedure caution against feeding SG until steam heat removal path is available.-(B is incorrect). D cannot remova as much heat as C. D is the second alternative in ' accordance with FR-H.3 to depressurize the SG. K/A: -W/E 13 K 1.1 Components, capacity and functions.
- RO 1'1i Given the following conditions:
- MP3-is operating at 80% power.
e Rod controlis in automatic. Rods are at 225 on Bank D.
- The controlling Irmi signal fails to a value of 575'F.
. Control rod speed will indicate a speed of steps per minute, and the indication will be lit. A. 48. out L B. -72, out Oc 48, in - . D. ' 72, in ANSWER: - DJ 72, in K/A*. 001000K6.02 Sensor feed to RCS 4 JUSTIFICATION: Tavg (80%) = 557 + 24 = 581 Tref = 575 Tavg - Tref = 6*F Max rod speed at 72 spm
-(d is correct)
' A is incc.~ect - wrong speed / direction -
B is incorrect - wrong direction C is incorrect - wrong speed . Modified 382
+
a.r-
RO 18 The analysis for locked rotor loss of flow accident predicts the initial trend over the first few seconds is: A. Both DNBR and Pressurizer pressure increase. B; Both DNBR and Pressurizer pressure decrease, C. DNBR increases, Pressurizer pressure decreases. D. DNBR decreases, Pressurizer pressure increases. ANSWER: D. DNBR decreases, Pressurizer pressure increases.
REFERENCE:
Decrease in Reactor Coolant System Flowrate (MCORE04) JUSTIFICATION: Loss of flow causes the DNBR to DECREASE (closer to DNB), the loss of flow also causes the RCS to heat up as less heat is removed, and pressure will increase ("D" is correct). OBJECTIVE: MC0402 K/A: 003 K 5.01 - RCS Flow 97 EOP Exam Question ID 2509 l i r i 1
RO 19
. Which one of the following is the reason that RCP #1 sealleakoff is isolated at RCS pressures below 125 psia?
A. Leakoff flow decreases at low pressures so #1 sealleakoff is isolated to force more flow through #2 seal. B. Backflow from the VCT through the seal leakoff line could flush contaminants into the seals. C. Controlled leakage limits may be exceeded due to excessive seal injection flow at low , pressures. D. Leakoff flow instruments are not accurate at low pressures and excesnive leakoff could go undetected. ANSWER: B. Backflow from the VCT through the seal leakoff line could flush conttminants into the seals.
REFERENCE:
RCP003C Reactor Coolant Pump JUSTlFICATION: The VCT may be at higher pressure than the RCS and backflow through tFe seal leakoff line may result. This flow is not subject to filtration (no seal injection filters on this line) so VCT contaminants may be introduced into the seals and result in mechanical damage when the pump is restarted. K/A: 00300K1.03 RCP Seals - 3.3/3.6 Objective: RCP06C 95 NRC exam
. _ - . . . . - - . . - - . - . - . - .- . ---.-. - - - - .-. - - - - - ~ .
RO 20 What is the purpose of the interlock requiring the Letdown isolations (3CHS*LCV459/460) to be , open prior to opening the orifice isolations (3CHS_*AV8149A C)? A. To perunt flashing downstream of the Letdown pressure control valve (3CHS PCV131). ) I , B. To prevent flashing in the Letdown Regenerative Heat Exchanger. i C. To prevent excessive Letdown Heat Exchanger temperatures overloading the RPCCW system. 4 D. To prevent the letdown relief valve from lifting due to the water hammer. ANSWER: Bc To prevent flashing in the Letdown Regenerative Heat F.xchanger,
REFERENCE:
NSSS TEXT, VOL 1: JPM28 4 l K/A: 004K4.15 - Interlocks with letdown orifice isolator valves 4 Modified Bank 818 i r G
RO 21 Which of the following is a reason for placing the control switches for the charging pumps in pull to-lock during a Loss of all AC Power? } A. To prevent the injection of cold seal injection water into the RCP sesi packages when an l' emergency bus is restored, possibly damaging the seal packages or bowing the RCP pump shaft. i
, B, To prevent PTS by thermal shocking the reactor vessel downcomer with cold, high pressure Safety injection water when an emergency bus is restored after the Sgs are
- depresearized.
C. To prevent thermal stressing the charging loop penetrations by injecting cold, safety } injection water into the RCS possibly creating an unisolable LOCA. F D. To prevent a pressurizer overfill situation when power is restored, since FCV-121 will be j full open and the pressurizer will be emsty due to the cooldown when the Sgs were depressurized. answer: I i
- A, To prevent the injection of cold seal injection water into the RCP seal packages when an i emergency bus is restored, possibly damaging the seal packages or bowing the RCP pump shaft.
REFERENCE:
ECA-0.0 Step 6 basis ! JUSTIFICATION: Defeating automatic loading of Charging /SI pumps functions to protect 4 RCP from damage when AC power is restored. This action prevents the automatic delivery of relatively cold sealinjection flow into the RCP number 1 seal chamber and shaft are which has the potential for thermal i shock and subsequent damage to the RCP seals and shaft, i 3 K/A: 000055 K3.02 4.3/4.6 003 GEN.10 3.3/3.6 2 004 K2.02 test item 690 modified
RO 22 The plant is operating normally at 100% power.
-Which of the following would be a result of the Letdown Pressure Transmitter (3CHS*PT131) failing LOW 7 A. _ The Regenerative Heat Exchanger Outlet Temperature increases B. the Letdown Heat Exchanger Outlet temperature increases.
C. The CDTT levelincreases. D, The PRT Levelincreases. ANSWER: D. The PRT Levelincreases.
REFERENCE:
P&lD 104A,102F J'JSTIFICATION: Indicated pressure decrease = PCV131 close = actual pressure increases = relief lifts to the PRT. A is incorrect. When PT 131 fails low, letdown pressure control valve PCV*131 will close. Regenerative heat exchanger outlet temperature will ' decrease because more heat is being removed by the charging flow. When the letdown relief opens, the temperature will increase slightly, but it will not increase above the original value. B is incorrect. Letdown flow will decrease. The initial heat exchanger outlet temperature will decrease and the RPCCW valve will close. C is incorrect. The letdown relief lifts to the PRT not the CDTT. 96 NSSS Exam ID 2213
" - ^ ' " - '
.RO 23 :
PLANT CONDITIONS: Plant is at 100% power
; e Pressurizer pressure channel, PT-455, failed high three (3) hours ago.
j :. The operating crew carried out the actions of AOP 3571, Instrument Failure Response and removed the channel from service. Channel PT-457 is now the controlling channel. e- All systems have been returned to automatic control 1 l A loss of 120 VAC vital instrument panel VIAC 3 has just occurred. 4 )= Which of the following describes the impact on the plant of the loss of VIAC 37 i A. The plant will remain at 100% power. PZR pressure controller will shift to manual and ! the automatic actuation of the PORVs has been lost. l B. A safdy iniection will have occurred due to low pressurizer pressure logic coincidence being met. .
- . C. The PORVs will open due to a high pressure signal and this will eventually lead to a l,
safety injection on low pressurizer pressurec i D. The master pressure controller will cause the pressurizer control heaters to go to ) minimum output and close the spray valves.
- ANSWER:
i B. A safety. injection will have occurred due to low pressurizer pressure logic coincidence - I being met. 1
REFERENCES:
AOP 3571 Functional sheets 12 and 12a JUSTIFICATION: The operators will have tripped the bistables associated with the failure of L the pressurizer pressure channel. T his wil! include the low pressure Si bistable. When the vital AC bus is lost a second low pressurizer pressure ] oistable will be received and an SI will occur. The
- K/A Rating
- 013-A3.01 Loss of instrument bus 97 Exam 8 -
RO 24 A Safety injection Signal occurs while VIAC 2 is deenergized. How will the Train *B" ESF equipment respond? A. Diesel Generator "B' starts, Bus 34D is stripped but the EDG outpu+ breaker does not close and the associated Train B loaos do not start. B. Diesel Generator "B' starts, Bus 34D is Etripped, then the EDG output breaker closes and the Train B ESF loads are sequenced onto Bus 340. C. Diesel Generator "B" does not start, Bus 34D is not stripped, and the Train B ESF loads do not start. D. Diesel Generator "B" does not star:, Bus 34D is stripped, and the Train B ESF loads are sequenced onto the RSST. ANSWER: C. Diesel Generator "B" does not start, Bus 34D is not stripped, and the Train B ESF loads do not start.
REFERENCE:
AOP 3564, Caution prior to Step 6 JUSTIFICATION: Tne caution prior to Step 6 of AOP 3564 states that:
' Loss of VIAC 1(2) results in diesel generator A(B) being de-energized. If an ESF actuation takes place during this condition, the following items will not occur automatically.
The A(B) diesel will rn; Start (except LOP)
- Loads will not be stripped from the emergency busses
- A(B) train loads will not start' Distractor "C"is therefore correct. Distractors "A" & *B' are incorrect because they state the 'B' EDG will start even though the question does not assume an LOP is present. Distractor "D" is incorrect because loads will not be stripped from Bus 34D.
K/A: 013 A3.02 Actuation of safeguards equipment t SOURCE: 97 Mitcore Exam QUESTION ID: 2370
RO 25 Given the foliowing conditions: . The crew is performing a reactor startup. The RO has just pulled the control rods several steps end is waiting for source range counts to stabilize.
' Assuming the reactor is very close, but not yet critical, source range counts should:
l A. . Stop increasing and stabilize immediately, with SUR decreasing to zero. l L B. SUR will decrease to 0 with SR counts increasing at u onstant rate. I l C. Continue to increase, but at a slower rate, with SUR stabilizing at a lower positive value. D. Continue to increase for a short period of time, then plateau, with SUR decreasing to zero. ANSWER: D. Continue to increase for a short period of time, then plateau, with SUR decreasing to zero.
REFERENCE:
Reactor startup procedura and fundamentals JUSTlFICATIOh A is incorrect. Doesn't consider the effects of subcritical multiplicetion and its impact as criticality is approached. B is incorrect. The reactor is still suberitical. 1 C is incorrect because SUR will decrease to zero, and count will stabilize at higher volume. D is correct. K/A: 015000K5.05 Criticality and its indications 4.1 New Question
RO 26 The plant is operating at 95% power. The Balance of Plant (BOP) operator inadvertently partially opens the Low Pressure Feedwater Heater Bypass Valve (CNM MOV88). How will opening the valve affect plant cycle efficiency? A. Decrease since more energy from the reactor is required due to feedwater entering the steam generator at a lower temperature. B. Increase due to less work required to pump the water through the low pressure feedwater heaters. C. Remain the same because mass flowrate entering the steam generators has not changed. D. Increase due to an increase in feedwater temperature resulting in more efficient high pressure feedwater heater performance. ANSWER: A. Decrease since more energy from the reactor is required de t to feedwater entering the steam generator at a lower temperature.
REFERENCE:
Westinghouse heat transfer fundamentals chapter 7, Mollier diagram. JUSTIFICATION: Shutting the bypass valve will result ir an increase in feedwater temperature due to more flow thru the feedwater heaters to be preheated an no " cold' feedwater bypassing the heater strings. As a result, feedwater will enter the steam generators at a higher temperature. The enthalpy change of the working fluid across the steam generator is smaller therefore, the heat transferred into the system (Q ) is smaller. A smaller heat addition results in increased cycle efficiency. K/A: 056020.A2112 Heater String Dypass SOURCE: Modified exam item 127
% h+
RO 2r Event Sequence: [0900 A turbine trip / reactor trip occurs 0905 A loss of offsite power occurs A loss of all main feedwater occurs Auxiliary feedwater initiates with s,pproximately 1200 gpm total flow 0915 Narrow range level in the "C" SG is 6% and increasing 0918_ Auxiliary feedwater total flow continues at approximately 1200 gpm What are the consequences of not throttling back on AFW flow to all of the SGs at this time? - A. SG levels willincrease until SG overfill protectiori on high-high SG levelisolates AFW flow to all SGs. l B. Full AFW flow will cause the RCS to couldown and depressurize. Letdown willisolate and an Sl will occur. C. Full AFW flow will cause a plant cooldown untillow-low Tav is reached and the ,. feedwater isolation signal stops AFW flow to all SGs. D. The SGs will cooldown and depressurize. This will result in a safety injection on the high steam pressure rate. ANSWER:- B. Full AFW flow will cause the RCS to cooldown and depressurize. Letdown willisolate and an SI will occur. Justification: A is incorrect because the high-high signal trips the turbine, which ids already tripped and provides no isolation of AFW. C is incorrect because a feedwater isolation signal has no affect on AFW flow. D is incorrect because the high steam pressure rate will result in a amin steamline isolation, not an SI. K/A 059 K3.04 l
. _ - . - - . - . - . . - . - - .~ .. .-. .- - - - . - . ~ . . - . -.- . - . . . _._.
e RO 28
- Given the following conditions. l
- i. \
. MP3 was operating at 100% power.
The station experienced s. totalloss of a!! AC power. The crew is currently depressurizing the SGs in ECA 0.0. As SG pressures are lowered, available AFW flow will as SG pressure decreases to 240-260 psig. A. ~ Decrease to zero (0) gallons total flow B. Drop to 100 GPM per steam generator C. Remain above a total of 530 GPM D. Remain near the original flow of approximately 1150 GPM ANSWER: C. Remain above 530 GPM K/A: 061000A1.02 Steam generator pressure effects on terry turbine 3.6
'JUSTlFICATION: The Terry Driven AFP is sized to remove the decay heat and cooldown the plant to go on RHR at 250 psig in RCS (SG Pres ~100 psig)
The Terry Turbine will provide adequate heat sink for reactor and be above red path value. (C is correct) A & B are incorrect. B is the value of flow due to the flow restricting ventuni for feedline break protection (incorrect). A is from number for SG pressure 150 when RHR is put in service, (A is incorrect). D is incorrect because TT flow decreases when pressure drops especially when SG pressure drops < 600 psig (FSAR), New Question _ ~ _ , , , . , ,- _ . _ _ , - _ , . _ ,
RO 29-t l Given the following conditions: }~ .- - Unit is operating at 100% power.
.* A Hi alarm is received on the containment gaseous radiation monitor, i ..
* : Charging flow is 135 GPM.
- Seal return flow is 3.2,2.8,3.3, 3.4 gpm (A, B, C, D)
- Seal injection flow is 9.8,9.0,9 2, 9.0 gpm (A, B, C, D)
L e Letdown flow is 75 GPM.
- RCS Tave is on program.
j; e . Containment sump levelis increasing
. PRZR levelis on prcgram.-
l . VCT levelis 30% and decreasing
- j. .
.PDTT levelis stable at 25%
i C Based on the above information, the current leak rate is GPM. I A_ 53.0 B. 60.0 C. 84.3 i D. ' 94.0 ANSWER: C. 84.3 K/A: 000009K3.06 RCS inventory balance 3.9 Modified Exam item 659 I
.._.2
j i I
- RO 30 --
- INITIAL CONDITIONS; >
. Reactor power is 60%.
Loop 1 Delta T indicates LOW '
. Loop 1 Tave indicates HIGH ~
Which of the following Loop 1 RTD failures could cause these indications?
- A T hot failed HIGH.
j - B. T cold failed LOW.-- C. T-cold failed HIGH. D. ~ T-hot failed LOW. ANSWER:
' C .- T-cold failed HIGH.'
L H + Tc
. JUSTIFICATION: Tave = AT := TH ~ Tc
- 2 If Tc fails high, Tavg indicates high AT indicates low, (c is correct)
A is incorrect because AT would indicate high.'
- D is incorrect because AT would indicate highi
- D is incorrect Tavg could indicate low.
1
-K/A: 002K5.12 Relation of temperature indications Modified item 1468
RO 31 Given the following conditions: - A small break LOCA has occurred. $ Fuel failure occurred during rapid downpower prior to trip. Crew is currently in ES-1.2 " Post LOCA Cooldown and Depressurization."
- RCS pressure is 1400 psia and decreasing Wide range Tc's are 550*F and_ decreasing Wide range Th's are 560*F and decreasing CET's are 565'F and appear stable.
- Ccatainment pressure is 20 psia and decreasing.
Containment temperature is 185*F and decreasing. SG levels are being maintained at 35% Pressurizer levelis 25% and stable Based upon the above indications, Si flow can: A. Be reduced because CET's are stable or decreasing. B. Cannot be reduced since subcooling is inadequate. C. Be reduced because the SG's are an adequate heat sink. D. Cannot be reduced when the containment is adverse. ANSWER:
' B. Cannot be reduced since subcooling is inadequate.
JUSTIFICATION: B is correct. Subcooling is less than 115'F. Thus Si flow cannot be reduced.- A is incorrect because Si reduction criteria is a function of subcooling and pressurizer level not CET's alone. C is incorrect. SG's levels aren't greater than those required for heat-removal under adverse containment conditions. D is incorrect. Sl flow can be reduced under circumstances when containment is adverse due to radiation levels or containment temperature conditions, as lang as subcooling and RCS inventory are satisfied. K/A. 006 A1.19 Effects of subcooling 4.0 SOURCE:- New
RO 32-The plant is in MODE 5 with Tave approximately 105'F. The crew is in the process of drawing a bubble in the pressurizer, Pressurizer level has just started to come on scale. A complete loss of instrument air occurs. Which of the following describes plant response with NO operator action? A. The plant slowly depressurizes. B. RCS pressure willincrease to the COPS setpoint, C. RCS pressure will increase to safety valve setpoint. D. The plant will maintain pressure until pressuriz er heaters trip. i ANSWER: B. RCS pressure willincrease to the COPS setpoint.
REFERENCE:
OP 3201 Attachment 1 JUSTIFICATION: Letdown isolates, spray valves fail closed. COPS is armed.. Setpoint for COPS at the current temperature is = 400/450 psia. Pressure will increase until COPS open K/A: 010000.K4.03 Overpressure Control 97 Exam 9 Question ID 2184
RO 33 Given the following conditions: MP3 is holding at 9% to complete turbine shell warming. PZR pressure channel 11 bistables are in trip because channel previously drifted high. SG levelis being controlled with the FRV bypass valves, which are in automatic. FRVs are isolated. RCS temperature is being controlled by the steam dumps. I WHICH ONE of the following events would, if no corrective actions were taken, result in a reactor trip? A. Running charging pump trips. B. A second PZR pressure channel fails to 1900 psia. C. Loss of power to the FRV bypass solenoids. I D. EHC piping rupture. ANSWER: C. Loss of power to the FRV bypass solenoids.
REFERENCE:
Tech Specs, Functional sheets 6 & 7 The loss of power to the FRV bypass solenoids will result in them failing closed. This will result in a reactor trip on SG lo-lo level, a trip that is not bypassed by P-7. JUSTIFICATION: Power < P-7 (10%) blocks or bypasses the following trip: Turbine trip - Rx trip bypassed by P-9 (D is incorrect) Pressurizer low press Rx trip (B !s incorrect) High Pressurizer level Running charging pump trip will cause auto start of standby pump and ' will not cause a trip. RPS trip is off high pressurizer level (A is incorrect) An SI signal, causing a reactor trip, will not be generated because the setpoint is 1892 psia.
~K/A: 012000K6.10 Permissive circuits 3.3
- New Question
_ . m
. _ _ . . _ _ . . _ _ . _ _ _ _ _ . . _ - _ . _ __ _ .~ . _ . _ _ _ - . _. ._ . . _ _ _ _
d I RO 34 2 initial Conditions
- The plant is operating at 100% power.
- . OTAT CHil bistable is tripped because of a temperature instrument failure in loop B.
- Pressurizer pressure transmitter PT 455 fails high.
Pressurizer pressure (CHI) high bistable trips. in order to satisfy tech specs action statement for the pressurizer pressure failure you must: e _ A. Trip bistables for pressurizer pressure low (CHI), low pressurizer press e SI (CHI), and j OPAT (CHI)
- B. Trip bistables for pressurizer pressure low (CHI), low pressurizer pressure SI (CHI), and OTAT (CHI).
C. Trip bistables for pressurizer pressure low (CHI) low pressurizer pressure SI (CHI), and bypass trip on OTAT (CHI) for up to 4 hours. > D. Trip bistables for pressurizer pressure low (CHI), low pressurizer pressure SI (CHI), and 4 restore a channel to operable status within an hour or proceed to hot standby within the next 6 hours. ! ANSWER: D. Trip bistables for pressurizer pressure low (CHI), low pressurizer pressure IS (CHI), and restore a channel to operable status within an hour or proceed to hot standby within tne
- next 6 hours.
[ JUSTIFICATION: A is incorrect because pressurizer pressure doesn't feed OPAT, B is incorrect because tripping OTAT bistable will cause a limit trip. C is incorrect because you no longer Tech Spec LCO for minimum operable channels for OTAT. i K/A: 012 A3.05 - RPS Channel Trips 1 New Question i i d 1 1 i _ _ . . _ .~ . . _ . . , _ _ _ _ . . _ _ . _ . , ._. ,-
. - . - . .. _ =. . --. .-- - .- -
RO35 All DRPI rod bottom annunciators are blocked during start-up until: 1 A. Control Bank D is greater than or equal to 12 steps off the bottom. B. The respective shutdown bank is greater than or equal to 12 steps off the bottom. C. The shutdown banks are fully withdrawn and control bank A is greater than or equal to
-12 steps off the bottom.
D. All shutdown banks are greater than or equal to 12 steps off the bottom. ANSWER: C. The shutdown banks are fully withdrawn and control bank A is greater than or equal to 12 steps off the bottom.
REFERENCES:
9002 DRPI-000, DRPl Technical Manual K/A: 004 A1,02 control Board Indicators Exam item: 2248 J
RO 38 What will be the effect on Feed Regulating Valve 3FWS*FCV510 due to the controlling channel
- for 'A' Steam Generator levelinstantaneously failing high? Assume the feed regulating valve
. utilizes a Pi type control circuit.
A. The feed regulating valve will start to close after a predetermined time due to the built in lag circuit of the controller. B. The feed regulating valve will immediately start to close and then close at a speed determined by the magnitude of the error signal and the time the error signalis present. f C. The feed regulating valve will start closing, th6r change its closing speed based on the time the error signalis present only. D. The feed regulating valve willimmediately start closing at a constant rate for a , predetermined time, then begin opening at a rate determined by the actuallevel error. ANSWER: l 3 B. The feed regulating valve will immediately start to close and then close at a speed determined by the magnitude of the error signal and the time the error signalis present.
REFERENCE:
Functional drawing 108D685, Instrumentational and Operational Analysis, Nuclear Energy TRNG. Module 7 JUSTIFICATION: The vaRe will close immediately without any lag. (A is incorrect) The valve will close immediately at a rapid rate then close at rate dependent on the integral time constant. (C is incorrect). Because the proportional and integral signals are additive, the rate is never constant and the valve is always closing due to the system being level dominant. (D is incorrect). K/A: 016 A3.01 - Auto select / signals to control currently.
4 - RO 37 Following a CDA signal, what is the purpose of the time delay associated with the start of the Recirculation Spray System (RSS) Pumpss? i-A. To allow the operators time to override the starting of the RSS pumps, on an inadvertent ] CDA signal, preventing an undesired spray down of Containment. B.- To allow time for the RHR pumps to trip off on low RWST level to prevent overloading the EDGs if they are the only source of power. C. To be consistent with the sequencer time delays for a CDA/ LOP situation. D. To allow time for proper NPSH to the RSS pumps to be established. 4 ANSWER: D. To allow time for proper NPSH to the RSS pumps to be established.
REFERENCE:
FSAR Section 6.2.2.3 JUSTIFICATION: The 11 minutes allows CTMT sump level to increase with OSS water, and condensed RCS or MSS steam, preventing RSS pump starts prior to achieving and edequate net positive suction source. K/A: 026 K.101 Relationship with ECCS Exam item 2473
. , . . . . . = . . . . . . . . . _ . - - . . . . . . - - . - - _ . . . . . . - - _ _ . - . . - . - . . - - - . ~ . . .
RO 38
- Given the_following conditions:
s
- The Unit has just synched on line and is ramping past 15% power.
"B". reactor coolant pump trips.
- Assuming no operator actions, "B" steam flow will and "B" SG level will (consider the immeJiate effects),
A. Increase, increase B. Increase, decrease C.- Decrease, increase - a D. Decrease, decrease t . ANSWER: i D. Decrease, decrease i
REFERENCE:
i K/A: 035010K5.03 Shrink and Swell JUSTlFICATION: Steam flow will decrease as pressure drops and level will decrease, due
. to colder RCS when flow reverses.
l Modified Exam item 1818 5 I
.-, .-. ., . . ...- .-.. .. - - ---.~.. . - - .-. _ - _.
RO 39-With the plant operating at 100% in a normal electrical lineup, the
- Bus 34A Differential" alarm is received.
_What will be the expected electrical distribution response as a result of the 34A differ;ntial? A. . Bus 34A de energizes, bus 34C slow transfers to the RSST. . B. 34C fast transfer to the RSST, the tie breaker remains closed allowed 34A to remain , energized, C. Bus 34A de-energizes, bus 34C is powered from the 'A' emergency diesel.
- D. Bus 34A deenergizes, bus 34C fast transfers to RSST,
} ANSWER: j -- A. Bus 34A de-energizes, bus 34C slow transfers to the RSST. 3
REFERENCE:
LSK 24-3D ! JUSTIFICATION: Buses 34A/B differential overcurrents trips and locks out NSST feeder i and bus tie breakers. This will result in slow transfer to the RSST. 1 ! K/A: 062 K4.03 Interlocks, auto transfer 97 MITCORE Exam a T d 4 e d N
RO 40 Which one of the following describes he expected battery capacities for a loss of DC on battery bus (301 A 1/30181)? A. 1 hour B. 2 hours C. 4 hours O 8 hours 4 SWER:
- 8. 2 hours JUSTIFICATION: The battery capacity is assumed to be 2 hours. (TS 3/4.8.2) *B"is correct.
KIA: 063 K4.03 - Battery Charger Capacities New Question
- - . . - . . -.. . - - - . - _. - . - - . - - .. ~._ - . _ - . . - .. - - .. .
l 1 RO 41 The crew is in E-0, " Reactor Trip or Safety injection', due to Si actuation Prior to resetting the Si signal the operator depresses both Emergency STOP pushbuttons on - , MB8 for the *B' Emergency Diesel Generator. i
.1 Which of the following decribes the response to the "B" Emergency diesel Generator?
(No further operator e,ttion occurs). A. The diesel coninues to run. B. The diesel would stop and remain shutdown C. The diesel would stop but restart in 140 seconds, and restart EG_a 3 the mode SI/ LOP
, D. - The diesel would stop and then immediately restart and restart EGLS in the mode SI/ LOP. i i
answer: B. The diesel would stop and remain shutdown.
REFERENCE:
LSK 24 09.3A,B and J
-Justification: The emergency stop pushbuttons energi2es the shutdown relay which energizes the solenoid to cut fuel to the diesel, preventing a start. The diesel will remain shutdown.- (B correct)
K/A: 064 K3.01 from 443, new i !~ II 4 ' . m-- w -w-, , - e , - . , . , . . - , -e - , - - , . , . . - - . , - - - - nu,< -- - , v- e.
" RO 42 The plant is in:
. Mode 3 e' _ RCS.is solid
. . COP's is in auto and armed e, RCS is at 150 F and 340 psia i e SG temp are 200 F after natural circulation -
Which of the following will cause an RCS overpressure transient in the RCS: A. Loop A Ts fails low, i B. RCP B is restarted. C. _ Letdown Pressure Control valve fails open. -D. Starting an RHR pump. ANSWER: l B. RCP B is restarted. 1 JUSTIFICATION: "A"is incorrect because COPS valves are armed and won't open unless i RCS pressure exceed setpoint. This f9ilure will not cause any transient in RCS. ;
"B"is correct - starting "B" RCP is solid plant with COPS armed and a 50aT will cause a pressure increase and the COPS valves will open.-
"C" is incorrect - letdown pressure control valve failing open will cause RCS pressure to decrease.
"D"is incorrect - starting the RHR pump should cause the RCS pressure to decrease slightly due to increase flow a heat removalin the RHR heat exchanger. PCV 113 will reposition in auto to maintain RCS pressure.
K/A: : 005 A2.02 Cold Overpressure Protection New Question
RO 43 Maximum allowed RHR flow and the bases for this maximum during reduced inventory l conditions are:
. A. RHR flow limited to 3000 gpm to prevent level indication error due to surge flow.
B. RHR flow limited to 1000 gpm to prevent loss of flow due to vortex entrainment of air at pump suction. C. RHR flow limited to 1000 gpm to minimize potential inventory loss in the event of a leak. D. RHR flow limited to 3000 gpm to prevent overloading the pump motor from operating near runout conditions. ANSWER: B. RHR flow limited to 1000 gpm to prevent loss of flow due to vortex entrainment of air at pump suation. JUSTIFICATION: "B"is correct. EOP 3505 limits flow to 1000 gpm to minimize effects of vortexing.
"D"is incorrect. RHR flow is released from 3000 gpm to 1000 gpm as reduced inventq procedures are implemented.'
"B" is incorrect because pressure limits flew from leaks not RHR flowrate.
"A" is incorrect because flow is limited 1000 gpm and pump is not operating near runout conditions..
K/A: 005 A1.02 RHR flow rates. New Question
RO 44 The plant has tripped and experienced a safety injection and
- CIA".
Which of the following decribes how the reactar plant chilled water system is affected? A. Chilled water containment isolation valves close, the RPCCW to CDS cross ties open, and all other loads outside containment isolate. B. All loads outside containment isolate, the chilled water loads in containment are maintained unless a 'CIB" actuates. C. Chilled water containment isolation volves isolate, RPCCW to CDS cross-ties open, flow to all other loads is maintained. D. All loads outside containment isolate, the chilled water loads in containment are maintained unless a 'CDA" actuates, answer: C. Chilled water containment isolation valves isolate, RPCCW to CDS cross-ties open, flow l to all other loads is maintained.
REFERENCE:
P&lD 122B and 1218 JUSTIFICATION: CIA closes the containment valves and opens the RPCCW cross ties (C Correct) f CDA will not directly cause any valves to reposition. (D incorrect) CIB will cause the RPCCW supplies to CDS to close. (B Incorrect) CIA will not cause a loss of all loads outside containment. (A Incorrect) K/A 008 A3.05
RO 46
- The following plant conditions exist:
- A plant cooldown from 557'F has been started.
- Tho steam dumps are being utilized in the pressure mode. ,
- At 553'F all the steam dumps close.
Select the action which will allow continuation of the cooldown on steam dumps. A. Take the " mode selector" switch to " reset". B. Take bypass interlock selector switches to " bypass". C. Take bypass interlock selector switches to off/ reset position. D. Shift steam pressure controller to manual to open the steam dump valves. ANSWER: B. Take bypass interlock selector switches to " bypass". JUSTIFICATION: - To bypass low low Tavg interlock you must take both bypass interlock switches to bypass. ("B"is correct.) Taking the mode syritch to reset - resets the load rejection arming memory (C-7) only, ("A" is incorrect.)
' the bypass interlock select switches to off/ reset position will block' x . .smp operation ("C"is incorrect.)
Shifting steam pressure controller to manual doesn't override / bypass the block signal ("D"is incorrect.)
-K/A: 041 A4.02 Use of cooldown valves Modified from 353 Confidence Weighted Question
RO 44 Plant Conditions:
' A & B SW pumps selected as lead pumps
- C & D SW pumps selected as follow pumps
-The following plant conditions exist:
- Reactor trip has occurred due to a loss of off-site power.
The "A" EDG starts and immediately closes in to supply bus 34C e The 'B" EDG starts but its output breaker does not close automatically. The operator closes the output breaker after the diesel has been started for 30 secs. ! _ On a board walkdown the expected following service water pump combinations should be i- running:-
- A. All 4 service water pumps should be running.
l-B. .The A and O SW pumps should be running. C. The C and D SW pumps should be running.
. D.- The A and B pumps should be running off their respective emergency diesels.
I ANSWER: D. The A and B pumps should be running off their respective emergency diesels. JUSTIFICATION: The lead pumps should be running. The follow pumps only start if a lead pump fails to start. (A, B, & C are incorrect.) K/A: 076 K4.02 Auto Start Features i Modified Exam item 1997 4
RO 47 initial Conditions: e Unit is at 100% power
.- All circulating water pumps are running
- It is August 20th and Long Island Sound average temeprature is71'F e All heater drain pumps are running
. A & C TPCCW pumps are running B Stator liquid cooling pump is running A
- BUS 34A BUS DIFF" alarm occurs on main Board 8. The operators should:
A. Trip the reactor and go to E 0 because the unit will trip on OTAT due to the MSIVs closing. l B. Reduce load in an attempt to maintain vaccum in the condenser, i C. Trip the reactor and go to E-0 because the main feedwater pumps tripped on low. suction pressure. D. Stabilize the unit after the trubine runback due to high stator water cooling temperatures, ANSWER: B. Reduce load in an attempt to maintain vaccum in the condenser. JUSTIFICATION: A is incorrect. the MSIVs would close on loss of DC power to the solinoids or the loss of instrument air. DC power is not affected by the given AC power loss. The "B" TPCCW pump will auto start on low TPCCW pressure. Even if TPCCW was lost the air compressors would shift to the domestic water system as a backup. C is incorrect because even though heater drain flow will be reduced and main feed pump suction will start to decrease, the condensate pumps will make up for the lost flow. As feed flow decreases, the feed regulating valves open, causing feed pressure to decrease which in turn causes main feed pump speed to increase. The unit will not trip on loss of the main feed pumps or loss of suction pressure. D is incorrect because the stator water cooling pump has not been lost (B pump not powered by 34A). Additionally the unit can operate for up to one hour without stator water cooling or cooling to the stator cooling heat excahngers by TPCCW. The "B" TPCCW pump will start in auto on low TPCCW pressure. B is correct. With only one circulating water pump running for each bay of the condenser, vacuum will start to decrease if the plant remains at 100% power. Per the Caution prior to Step 6 in ECA-0.3 Distractor "D' is correct. K/A: 062 K2.01 Loss of power to major loads New Question
RO 48 Refueling operations are in progress, , 3RMS*RE41 begins to operate errectically and l&C reports that the power supply for 3RMS*RE41 needs to be replaced. 1What action should be taken by the crew? A. Decla}}