ML032340716
| ML032340716 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 08/16/2003 |
| From: | Ernstes M Operator Licensing and Human Performance Branch |
| To: | Scalice J Tennessee Valley Authority |
| Shared Package | |
| ML032380265 | List: |
| References | |
| 50-259/02-301, 50-260/02-301, 50-296/02-301 50-259/02-301, 50-260/02-301, 50-296/02-301 | |
| Download: ML032340716 (31) | |
See also: IR 05000259/2002301
Text
Final Submittal
(Blue Paper)
BROWNS FERRY
EXAM 2002-301
50-259, 50-260, & 50-296
DECEMBER 13, 16-19,2002
1. Administrative Questions/JPMs
2. In-plant JPMs
3. Control Room JPMs (simulator JPMs)
FINAL JPMs
The final J P M s are the same as the drafi JPMs with the following exceptions:
JPMs a d d e d
JPM 18F - EO1 Appendix 5C - Injection System Lineup - RCIC
A3.10 - Review Gaseous Release SI
A3.12 - Review a Radiological Survey Map
JPMs replaced
JPM Administrative Question- A3.1
JPM Administrative Question - A3.2
JPM Administrative Question - A3.3
JPM 114 - Standby Gas Treatment Train C Decay Heat Removal
JPM 133F - 2-EOI-APPll8 Alternate Pressure Control, RCIC in the Test Mode
JPM 331 - 2-EO1 Appendix 165 Bypass HPCI Interlocks
JPM NO. A3.10
REV. NO 0
PAGE 1 OF 7
BROWNS FERRY NUCLEAR PLANT
JPM NUMBER: A3.10
TITLE : REVIEW 0-SI-4.8.B.l.a.1,AIRBORNE EFFLUENT RELEASE
RATE, FOR THE SHIFT (SRO ONLY)
TASK NUMBER: s-090-su-01
SUBMITTED BY: DATE :
VALIDATED BY: DATE :
APPROVED : DATE :
TRAINING
PLANT CONCURRENCE: DATE :
OPERATIONS
- Examination JPMs Require Operations Training Manager or
Designee Approval and Plant Concurrence
JPM NO. A3.10
REV. NO 0
PAGE 2 OF 7
BROWNS FERRY NUCLEAR PLANT
I
REVISION LOG
Revision Effective Pages Description
Number Date Affected of Revision
0 11/17/02 ALL NEW
JPM NO. A3.10
REV. NO 0
PAGE 3 OF 7
BROWNS FERRY NUCLEAR PLANT
OPERATOR :
JPM NUMBER: A3.10
JPM TITLE: REVIEW 0-SI-4.8.B.l.a.1,AIRBORNE EFFLUENT RELEASE
RATE, FOR THE SHIFT
TASK NUMBER: s-090-su-01
TASK TITLE: Review airborne effluent release rate SI
K/A NUMBER: 2.3.11 K/A RATING: RO 2,7 SRO: 3.2
..................................................................
TASK STANDARD: Upon reviewing 0-SI-4.8.B.l.a.l for the shift,
determine all is acceptable except Attachment 9.
LOCATION OF PERFORMANCE: SIMULATOR x PLANT -x CONTROL ROOM X-
REFERENCES/PROCEDURES NEEDED: O-SI-4.8.B.l.a.a,Airborne Effluent
Release Rate, Revision 45 (Filled out), ODCM, REVISION 14
VALIDATION TIME: CONTROL ROOM: LOCAL :
PERFORMANCE TIME: CONTROL ROOM LOCAL -
-
COMMENTS :
Additional comment sheets attached? YES _ _ NO
RESULTS : SATISFACTORY UNSATISFACTORY
EXAMINER SIGNATURE: DATE :
EXAMINER
BROWNS FERRY NUCLEAR PLANT
IN-SIMULATOR: I will explain the initial conditions and state .
the task to be performed. I will provide initiating cues and
reports on other actions when directed by you. When you complete
the task successfully, the objective for this job performance
measure will be satisfied. When your task is given, you will
repeat the task and I will acknowledge "That's Correct". (OR
"That's Incorrect", if applicable). When you have completed your
assigned task, you will say, "my task is complete" and I will
acknowledge that your task is complete.
..................................................................
INITIAL CONDITIONS: You are the Unit 2 Unit Supervisor. The log
AUO has given you 0-SI-4.8.B.l.a.1,Airborne Effluent Release
Rate, to review for the shift.
INITIATING CUES: Review this SI and initial where appropriate.
JPM NO. A3.10
REV. NO. 0
PAGE 5 OF 7
.............................................................
Performance Step: Critical- X Not Critical
Review the SR.
~ .~.~.. ~.
.~. . ~ .. ~ ~~ ....
Standard:
Initials as Unit Supervisor Attachments 2,4,6,7 and 8 (Not
Critical). Determines that Attachment 9, Unit 1, RM-90-251 is NOT
within acceptance criteria (Critical).
SAT UNSAT-N/A- COMMENTS :
..............................................................
.............................................................
Performance Step: Critical- Not Critical- X
Request maintenance to determine the problem with the 1-RM-90-251
sample flow.
Standard :
Candidate requests maintenance to determine the problem with the
1-RM-90-251 sample flow.
SAT-UNSAT N/A- COMMENTS :
ANCE INFORMS Ci
JPM NO. A3.10
REV. NO.0
PAGE 6 OF 7
.............................................................
Performance Step: Critical- X Not Critical
Determine appropriate actions.
Standard:
Candidate determines from the ODCM due to 1- RM-90-251 sampler
flowmeter being inoperative ACTION D allows releases via this
pathway provided the flow rate is estimated at least once per 4
hours.
SAT-UNSAT-N/A- COMMENTS :
..............................................................
Table 1.1-2 (Page 1 of 2)
RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION
Minimum Channels/
Instrument Devices OPERABLE Applicability ACTION
1. STACK (RM-90-147B& -148B)
a. Noble Gas Monitor 1
b. Iodine Cartridge 1
c. Particulate Filter 1
d. Sampler Flow Abnormal 1
e. Stack Flow (FT, FM, FI-90-271) 1
2. REACTOR/TURBINE/REFUEL BUILDING
VENTILATION ZONE (RM-90-250)
a. Noble Gas Monitor A/C
b. Iodine Sampler B/C
c. Particulate Sampler B/C
d. Sampler Flowmeter D
JPM NO. A3.10
REV. NO.0
PAGE 7 OF I
3. TURBINE BUILDING EXHAUST
(RM-90-249,-251)
a- Noble Gas Monitor 1 ** A/C
b. Iodine Sampler 1 ** B/C
4. RADWASTE BUILDING VENT
(RM-90-252)
a. Noble Gas Monitor 1
b. Iodine Sampler 1
c. Particulate Sampler 1
e. Sampler Flowmeter 1
5. OFFGAS POST TREATMENT
a. Noble Gas Activity Monitor 1 ** F
(RM-90-265,-266)
b. Sample Flow Abnormal 1 ** D
(PA-90-262)
- At all times.
- * During releases via this pathway.
ACTION D
With the number of channels OPERABLE less than required by the Minimum
Channels Operable requirement, effluent releases via this pathway may continue
provided the flow rate is estimated at leasc once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
JPM NO. A3.12
REV. NO. 0
PAGE 1OF 7
BROWNS FERRY NUCLEAR PLANT
JPM NUMBER: A3.12
TITLE: REVIEW A RADIOLOGICAL SURVEY MAP
TASK NUMBER: N/A
SUBMITTED BY: DATE:-
VALIDATED BY: DATE:-
APPROVED: DATE:-
TRAINING
PLANT CONCURRENCE: DATE:-
OPERATIONS
- Examination JPMs Require Operations Training Manager or Designee Approval
and Plant Concurrence
JPM NO. A3.12
REV. NO. 0
PAGE 20F 7
L
BROWNS FERRY NUCLEAR PLANT
2
REVISION LOG
Revision Effective Pages Description
Number Date Affected of Revision
0 9/9/02 ALL NEW
JPM NO. A3.12
REV. NO. 0
PAGE 30F 7
BROWNS FERRY NUCLEAR PLANT
JOB PERFORMANCE
.. . MEASURE
OPERATOR:
JPM NUMBER: A3.12
TASK NUMBER: ADMIN
TASK TITLE: NIA
KIA NUMBER: 2.3.10 WA RATING: RO 2.9 SRO: 3.3
.............................................................................................
TASK STANDARD: REVIEW A RADIOLOGICAL SURBEY MAP TO DETERMINE IF A
TASK CAN BE COMPLETED WITHOUT EXCEEDING EXPOSURE LIMITS.
LOCATION OF PERFORMANCE: SIMULATOR - PLANT - CONTROL ROOM -
REFERENCES/PROCEDURES NEEDED: N/A
VALIDATION TIME: CONTROL ROOM: LOCAL: -
MAX. TIME ALLOWED: -(Completed for Time Critical JPMs only)
PERFORMANCE TIME: - CONTROL ROOM - LOCAL -
COMMENTS:
Additional comment sheets attached? YES - NO -
RESULTS: SATISFACTORY - UNSATISFACTORY-
EXAMINER SIGNATURE: - DATE: -
EXAMINER
JPM NO. A3.12
-REV.-NO. 0
PAGE 40F 7
. . ., . . , -
.. ~ - . .. .
BROWNS FERRY NUCLEAR PLANT
c
STUDENT HANDOUT
INITIALCONDITIONS: You are a Browns Ferry employee who has
obtained an accumulative yearly dose of 750 mrem.
INITIATING CUES: Given the following survey map, DETERMINE if you
can complete a task in the area without exceeding your TVA
administrative yearly dose limit.
The job will require you to transport a heavy air operated valve
wrench through the designated walkway (marked as walkway), open
the valve and bring the tool back outside the room. The walkway
is marked on the survey map, and will require approximately lo
minutes each way to transport the tool. Once the valve area on
the survey map is reached (marked as valve), it will require 30
minutes to open the valve and then transport the tool out of the
area. The map of the room has radiological survey information
you must interpret to successfully complete this JPM.
JPM NO.A3.12
--REV. NO. 0
PAGE 6 OF7
BROWNS FERRY NUCLEAR PLANT
EXAMINERS KEY
......................................................................................................
IN-SIMULATOR: I will explain the initial conditions and state the task to be performed.
I will provide initiating cues and reports on other actions when directed by you. When
you complete the task successfully, the objective for this job performance measure will be
satisfied. When your task is given, you will repeat the task and I will acknowledge "That's
Correct". (OR "That's Incorrect", if applicable). When you have completed your assigned
task, you will say, "my task is complete" and I will acknowledge that your task is complete.
......................................................................................................
INITIALCONDITIONS: You are a Browns Ferry employee who has
obtained an accumulative yearly dose of 750 mrem.
INITIATING CUES: Given the attached survey map, DETERMINE if you
can complete a task in the area without exceeding your TVA
administrative yearly dose limit.
The j o b will require you to transport a heavy air operated valve
wrench through the designated walkway (marked as walkway), open
the valve and bring the tool back outside the room. The walkway
is marked on the survey map, and will require approximately
minutes each way to transport the tool. Once the valve area on
the survey map is reached (marked as valve), it will require 30
minutes to open the valve and then transport the tool out of the
area. The map of the room has radiological survey information
you must interpret to successfully complete this JPM.
ANSWER
JPM NO.A3.12
REV. NO. 0
PAGE 7 OF7
No - The candidate would receive 12 mr to transport the wrench in
and out and an additional 250 mr to open the valve. This would
give the candidate 1012 mr f o r the year and exceed the TVA
administrative yearly dose limit.
JPM NO. 18F
REV. NO. 1
PAGE 1 O F 15
BKOWNS FERRY NUCLEAR PLANT
JOB I'EKFORMANCE MEASURE
JPM NUMBER 18F
TITLE EO1 APPENDIX 5C - INJECTION SYSTEM LINEUP - RCIC
TASKNUMBER U-000-EM-31
SAFETY FUNCTION 2
02 TYPE CODE: S,DA
SUBMITTED B Y DATE :
VALIDATED B Y DATE
APPROVED DATE
TRAINING
PLANT CONCURRENCE: DATE
OPERATIONS
- Examination JPMs Require Operations Training Manager or Designee Approval and Plant Concurrence
JPM NO. 18F
REV. NO. 1
PAGE 2 OF 15
BROWNS FERRY NUCLEAR PLANT
REVISION LOG
Revision Effective Pages Description
Number Date Affected of Revision
0 All New
1 All UpdatedRevised for NRC Exam
JPM NO. 18F
REV. NO. 1
PAGE 3 OF 15
BIIO\VNS FERRY NUCLEAR PLANT
OPERATOR
JPM NUMBER 18F.
TASK NUMBER U-000-EM-3 1
TASK TITLE LINE UP INJECTION SYSTEMS - RCIC IN ACCORDANCE WITH EO1 APPENDIX 5C
WA NUMBER 217000A4.04 WA RATING R 0 . 6 S R O 3
...................................................................
TASK STANDARD: MANIPULATE CONTROLS REQUIRED TO INJECT WATER TO THE RPV USING
THE REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM AND MAINTAIN
LEVEL AS REQUIRED.
LOCATION OF PERFORMANCE SIMULATOR - PLANT - CONTROL ROOM -
REFERENCES/PROCEDURES NEEDED 2-EO1 APPENDIX 5C - INJECTION SYSTEM LINEUP - RCIC, REV 4
VALIDATION TIME CONTROL ROOM 5:OO LOCAL -
MAX. TIME ALLOWED -(Completed for Time Critical JPMs only)
PERFORMANCE TIME: - CONTROL ROOM - LOCAL -
Additional comment sheets attached? YES - NO -
RESULTS SATISFACTORY -UNSATISFACTORY -
EXAMINER DATE:
BKOWNS FERRY NUCLEAR PLANT
...................................................................
IN-SIMULATOR I will explain the initial conditions and state the task to be performed. I will provide
initiating cues and reports on other actions when directed by you. When you complete the task successfully, the
objective for this job performance measure will be satisfied. When your task is given, you will repeat the task and I will
acknowledge "That's Correct". (OR "That's Incorrect", if applicable). When you have completed your assigned task,
you will say, "my task is complete" and I will acknowledge that your task is complete.
...................................................................
INITJAL CONDITIONS You are the Unit 2 Operator. The reactor has scrammed and RPV water level is lowering
slowly. EOI-I has been entered and followed to RCL-4.
INITIATING CUES: The US has directed you to restore RPV water level +2 to +51 inches using the Reactor Core
Isolation Cooling System as directed by 2-EO1 Appendix 5C, INJECTION SYSTEM LINEUP - RCIC.
JPM NO. 18F
REV. NO. 1
PAGE 5 OF 15
START TIME-
.................................................................
Performance SteD: Critical- Not C r i t i c a l x
WHEN REQUESTED BY EXAMINER identifylobtain copy of required EO1 Appendix
Standard
IDENTIFIED OR OBTAINED copy of 2-EO1 Appendix 5C.
SAT-UNSAT-NIA- COMMENTS
..................................................................
Performance Stev: Critical- Not CriticalX
1. IF.....BOTH of the following exist:
! Rx Pressure is at or below 50 psig,
AND
! Bypass of RCIC low RPV pressure isolation interlocks is necessary,
. . . . . . . THEN
. . . . . . . . . PERFORM the following:
a. EXECUTE EO1 Appendix 16K concurrently with
this procedure.
b. RESET auto isolation logic using RCIC
AUTO-ISOL LOGIC A(B) RESET 2-XS-71-51 A(B)
pushbuttons.
Standard
DETERMINED RPV PRESSURE >50 PSIG, as indicated by 2-PI-207A, Panel 2-9-5.
SAT- UNSAT- NIA -COMMENTS:
JPM NO. 18F
REV. NO. 1
PAGE 6 OF 15
..................................................................
Performance Stev: Critical- Not CriticalX
2. IFE. HJiJI of the following exist:
! High temperature exists in the RCIC area,
AND
! SRO directs bypass of RCIC High Temperature Isolation interlocks,
THEN...EXECUTE EO1 Appendix 16K concurrently with
this procedure.
Standard
DETERMINED high temperature does not exist in the RCIC area, as indicated by Panel 2-9-21 (2-TS-69-71-
41A,B,C) alarms clear= no alarm on Panel 2-9-3D window 10 (2-TA-71-41).
SAT- UNSAT- NIA - COMMENTS:
JPM NO. 18F
REV. NO. 1
PAGE I OF 15
- $*************$*$*$**$$$$******$**$**$$*$****$*******$*********************
CAUTlON
1 Operating RCIC turbine below 2100 rpm may
result in unstable system operation and
equipment damage.
! High Suppression Chamber pressure may trip RCIC. (Trips at 25#)
! Operating RClC Turbine with suction (CST Suction)
temperatures above 140°F may result in
equipment damage.
...........................................................
...................................................................
Performance Steu: Critical- Not CriticalX
3. VERIFY RESET and OPEN 2-FCV-71-9, RClC TURB TRIP1
THROT VALVE RESET.
Standard
VERIFIED illuminated RED indicating lamp 2-ZI-71-9.
SAT- UNSAT- NIA -COMMENTS:
JPM NO. 18F
REV. NO. 1
PAGE 8 OF 1 5
...........................................................................................
Performance Stew Critical- Not Critical3
4. VERIFY 2-FIC-71-36A, RCIC SYSTEM FLOW/CONTROL, contioller in AUTO with set-point at
600 gpm.
Standard
VERIFIED 2-FIC-71-36A in AUTO and tape set-point at 60 (XIO).
SAT- UNSAT- N/A -COMMENTS:
...............................................................
Performance Stew CriticalX Not Critical-
5. OPEN the following valves:
! 2-FCV-71-39, RCIC PUMP INJECTION VALVE.
Standard
PLACED 2-HS-71-39A in the OPEN position and OBSERVED illuminated RED valve position indicating
lamp above associated control switch.
SAT- UNSAT- NIA -COMMENTS:
JPM NO. 18F
REV. NO. 1
PAGE 9 OF 15
................................................................................................
Performance Stew Critical- Not Critical3
! 2-FCV-71-34, RCIC PUMP MIN FLOW VALVE.
Standard
PLACED 2-HS-71-34A in the OPEN position and OBSERVED illuminated RED valve position
indicating lamp above associated control switch.
SAT- UNSAT- NIA -COMMENTS:
.............................................................
- $*****************$**$$*~*$**$**$*~$$****$**:********~**
Performance Stew CriticalX Not Critical-
! 2-FCV-71-25, RCIC LUBE OIL CLR COOLING WTR VLV.
Standard
PLACED 2-HS-71-25A in the OPEN position and OBSERVED illuminated RED valve position indicating
lamp above associated control switch.
SAT- UNSAT- NIA -COMMENTS
JPM NO. 18F
REV. NO. 1
PAGE 10 O F 15
................................................................
Performance Sten: Critical- Not CriticalX
6. PLACE 2-HS-71-31A, RCIC VACUUM PUMP, handswitch in START.
Standard
PLACED 2-HS-71-31A in the START position and OBSERVED illuminated RED niotor breaker position
indicating lamp above associated handswitch.
SAT- UNSAT- NIA -COMMENTS:
.................................................................
Performance Stev: Critical& Not Critical-
7. OPEN 2-FCV-71-8, RCIC TURBINE STEAM SUPPLY VLV, to
start RCIC Turbine.
Standard
PLACED 2-HS-71-8A in the OPEN position and OBSERVED illuminated RED valve position indicating
lamp above associated control switch. (Steam flow and turbine speed increase)
SAT- UNSAT- NIA -COMMENTS:
JPM NO. 18F
REV. NO. 1
PAGE 11 OF 15
Performance See: Critical- Not C r i t i c a l X
8. CHECK proper RCIC operation by observing the
following:
a. RCIC Turbine speed accelerates above 2100 rpm
Standard:
VERIFIED RCIC turbine speed > 2100 by OBSERVING 2-SI-71-42A.
SAT- UNSAT- NIA- COMMENTS
...............................................................
Performance Stew Critical- Not CriticalX
b. RClC flow to RPV stabilizes and is controlled
automatically at 600 gpm.
Standard:
OBSERVED 2-FIC-71-36A and VERIFIED RCIC flow to RPV stabilized at 600 GPM
SAT- UNSAT- NfA- COMMENTS
JPM NO. 18F
REV. NO. 1
PAGE 1 2 O F 15
.............................................................
Performance Stev: Critical- Not CriticalX
C. 2-FCV-71-40, RClC Testable Check Vlv, opens by observing 2-ZI-71-40A, DISC POSITION, red
light illuminated.
Standard
OBSERVED illuminated RED check valve DISC POSITION indicating lamp.
SAT- UNSAT- NIA -COMMENTS
~~~ ~
...............................................................
Performance Stev: Critical- Not CriticalX
d. 2-FCV-71-34, RCIC PUMP MINIMUM FLOW VLV, closes
as flow rises above 120 gpm.
Standard
OBSERVED RClC system flow to RPV > 120 GPM as indicated on 2-FIC-71-36A and VERIFIED
illuminated GREEN valve position indicating lamp above 2-HS-71-34A.
SAT- UNSAT- NIA -COMMENTS:
JPM NO. 18F
REV. NO. 1
PAGE 13 OF 15
..............................................................
Performance Stew Critical- Not Criticalx
9. IF.....BOTH of the following exist:
! RCJC Initiation signal is present,
AND
! RCJC flow is below 60 gpm,
THEN...VERIFY OPEN 2-FCV-71-34, RCIC PUMP MIN FLOW
VALVE.
Standard
VERIFIED RClC initiation signal not present as indicated by 2-IL-71-52, RCIC AUTO-INIT, amber lamp
being extinguished.
SAT- UNSAT- NIA -COMMENTS:
Performance Stea C r i t i c a l X Not Critical-
IO. ADJUST 2-FJC-71-36A, RClC SYSTEM FLOWICONTROL, controller as necessary to control
injection.
Standard
DETERMINES the automatic flow controller is failed and takes manual control of RCIC. Adjusted 2-FlC-71-
36A setpoint as necessary to obtain 600 gpm flow, or a level of +2 inches.
SAT- UNSAT- NIA -COMMENTS:
JPM NO. 18F
REV. NO. 1
PAGE 14 OF 15
Performance Step: Critical- Not Criticalx
PERFORMER demonstrated the use of TOUCH STAAR during this JPM.
Standard
PERFORMER verified applicable components by utilizing TOUCH STAAR (Standard is subjective and
instructor must evaluate the need for additional training on TOUCH STAAR to maintain plant standards).
SAT__UNSAT__NIA__ COMMENTS
Performance Steu: Critical- Not Criticalx
PERFORMER demonstrated the use of 3-WAY COMMUNICATION during is JPM
Standard
PERFORMER utilized 3-WAY COMMUNICATION (Standard is subjective and
instructor must evaluate the need for additional training on 3-WAY COMMUNICATION to maintain plant
standards).
SAT-UNSAT__NIA__ COMMENTS:
END OF TASK
JPM NO. 18F
REV. NO. 1
PAGE 15 OF 15
STOP TIME __