ML032340723
| ML032340723 | |
| 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: ML032340723 (345) | |
See also: IR 05000259/2002301
Text
Draft Submittal
(Pink 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)
4. Administrative Topics Outline ES-301-1 I /
5. Control Room Systems and Facility Walk-Through
Test Outline ES-301-2 r/
ES-301 Administrative Topics Outline Form ES-301-1 (R8, SI)
Facility: BFN Date of Examination: 12/16/02
Examination Level (circle one): RO Operating Test Number:
Administrative Describe method of evaluation:
TopidSubject 1. ONE Administrative JPM, OR
Description 2. TWO Administrative Questions
ADMINISTRATIVE QUESTION A l . l J
FUEL HANDLING
ADMINISTRATIVE QUESTION A I .5 I/
SECURITY JPM A4.1 RESPOND TO A SECURITY EVENT r/
SURVEILLANCE
TESTIN5
-
JPM 510 EVALUATE RECOMBINER PERFORMANCE 1
ADMlNlSTRATiVE QUESTION A3.1 J
RADIATION
CONTROL
ADMINISTRATIVE QUESTION A3.2 +/
A.4
EPlP ADMINISTRATIVE QUESTION A4.6 I/
ADMINISTRATIVE QUESTION A4.7 1
-
~
ES-301 Administrative Topics Outline Form ES-301-1 (R8, SI)
Facility: BFN Date of Examination: 12/16/02
Examination Level (circle one): SRO Operating Test Number:
Administrative Describe method of evaluation:
TopiclSubject 1. ONE Administrative JPM, OR
Description 2. TWO Administrative Questions
-
~
4.1
Fuel Handling ADMINISTRATIVE QUESTION A I .I J
ADMNISTRATIVE QUESTION A I .8 /
~
SECURITY
-
JPM A42 RESPOND TO A SECURITY EVENT /
-
4.2
EQUIPMENT
CONTROL
-
JPM 510 EVALUATE RECOMBINER PERRORAMANCE ,/
4.3 RADIATION
CONTROL ADMINISTRATIVE QUESTION A3.1 J
ADMINISTRATIVE QUESTION A3.3 J
4.4 EPlP
-
JPM A4.5 CLASSIFY THE EVENT J
JPM NO. A3.1
REV.NO 0
PAGE 1 of 5
BROWNS FERRY NUCLEAR PLANT
JPM NUMBER: A3.1
TITLE: SECTION A QUESTION
TASK NUMBER: U-000-AD-17 S-000-AD-89
SUBMllTED BY: DATE:-
VALIDATED BY: DATE: -
APPROVED: DATE:-
TRAlNING
PLANT CONCURRENCE:
OPERATIONS
DATE:-
- Examination JPMs Require Operations Training Manager or Designee Approval
and Plant Concurrence
JPM NO. A3.1
REV.NO 0
PAGE 2 o f 5
BROWNS FERRY NUCLEAR PLANT
OPERATOR:
J P M ~ M B E R : - A3.1
TASK NUMBER: U-000-AD-17 S-000-AD-89
TASK TITLE: SECTION A QUESTION
KIA NUMBER: 2.3.1 1 KIA RATING: RO 2.7 -SRO: - 3.2
. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
TASK STANDARD: Using available references, answer the question as described.
LOCATION OF PERFORMANCE: SIMULATOR - x PLANT - x CONTROL ROOM x -
REFERENCEWPROCEDURES NEEDED: 2-ARP-9-3A, Rev 19
VALIDATION TIME: CONTROL ROOM: N/A LOCAL: N/A
MAX. TIME ALLOWED: N/A (Completed f o r r i t i c a l JPMs o n l y )
PERFORMANCE TIME: - CONTROL ROOM - LOCAL -
COMMENTS:
Additional comment sheets attached? YES - NO -
RESULTS: SATISFACTORY - UNSATISFACTORY-
EXAMINER SIGNATURE: DATE: -
EXAMINER
BROWNS FERRY NUCLEAR PLANT
. . . . .. .. .. .~~ .. . ... -
EXAMINERS KEY
REFERENCES ALLOWED
QUESTION
2-XA-55-3A, Window 27, 'MAIN STEAM LINE RADIATION HIGH-HIGH is in alarm. The following steam line
radiation readings are obtained:
2-RM-90-136 1.9E3 MWHR (Panel 9-10)
2-RM-90-137 2.6E3 MWHR (Panel 9-10)
2-RM-90-138 2.4E3 MWHR (Panel 9-10)
2-RM-90-139 2.1E3 MWHR (Panel 9-10
2-RR-90-135 2.31E3 MWHR (Both Channels) (Panel 9-2)
2-RR-90-157 5.30 WHR (Was steady at 4.0 WHR over the previous 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.)
What actions are required?
EXPECTED RESPONSE (EXACT WORDING NOT REQUIRED)
1. Notify RADCON (25%)
2. Request chemical analysis of primary coolant (25%)
3. Secure Hydrogen Water Chemistry (25%)
4. Possible power reduction (25%)
REFERENCES
2-ARP-9-3A, Rev 19, Page 29
OPERATOR ACTION:
4. If off -gas pretreatment radiation, 2-RR-90-157, has risen significantly (30% above
previous hour average), THEN.. .
CANDIDATES HANDOUT
REFERENCES ALLOWED
2-XA-55-3A, Window 27, MAIN STEAM LINE RADIATION HIGH-HIGH is in alarm. The
following steam line radiation readings are obtained:
2-RM-90-136 1.9E3 MWHR
2-RM-90-137 2.6E3 MWHR
2-RM-90-138 2.4E3 MWHR
2-RM-90-139 2.1 E3 MWHR
2-RR-90-135 2.31 E3 MWHR (Both Channels)
2-RR-90-157 5.30 WHR (Was steady at 4.0 WHR over the previous 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.)
What actions are required?
JPM NO. A 3 2
REV. NO 0
PAGE 1 of 5
BROWNS FERRY NUCLEAR PLANT
JPM NUMBER: A3.2
TITLE: SECTION A QUESTION
TASK NUMBER: U-000-AD-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. A3.2
REV.NO 0
PAGE 2 o f 5
BROWNS FERRY NUCLEAR PLANT
OPERATOR:
JPM NUMBER: A3.2
TASK NUMBER: U-000-AD-01
TASK TITLE: SECTION A QUESTION
K/A NUMBER: 2.3.10 WA RATING: RO- 2.9 SRO: - 3.3
..................................................................................................
TASK STANDARD: Using available references, answer the question as described.
LOCATION OF PERFORMANCE: SIMULATOR - x PLANT - x CONTROL ROOM - x
REFERENCES/PROCEDURES NEEDED: RCI-15, Rev 27, Attachment 1, Page 6
VALIDATION TIME: CONTROL ROOM: N/A LOCAL: N/A
MAX. TIME ALLOWED: N/A (Completed for Time Critical JPMs only)
PERFORMANCETIME: - CONTROL ROOM - LOCAL -
COMMENTS:
Additional comment sheets attached? YES - NO -
RESULTS: SAT1SFACTORY - UNSAT1SFACTORY -
EXAMINER SIGNATURE: DATE: -
JPM NO.A3.2
-REV. NO 0
PAGE 3 o f 5
EXAMINER
JPM NO. A3.2
REV. NO 0
PAGE 4 0 F 5
BROWNS FERRY NUCLEAR PLANT
EXAMINERS KEY
REFERENCES ALLOWED
QUESTION
Unit 2 is at 100% rated power. While planning maintenance near the feedwater lines it has
been determined that the total dose received by the four required maintenance personnel
can be reduced by -475 mrem if reactor power is reduced to 75% (with or without a
reduction in hydrogen injection) or can be reduced by -1 60 mrem if the hydrogen injection
rate is reduced.
In terms of ALARA considerations, what recommendation should be made to
management?
EXPECTED RESPONSE (EXACT WORDING NOT REQUIRED)
The recommendation should be to remain at 100% rated power (50%) and reduce the
hydrogen injection rate (50%).
REFERENCES
RCI-15.1, Maintaining Occupational Radiation Exposure as Low as Reasonably Achievable
(ALARA), Rev. 27, Page 6, Attachment 1
CANDIDATES HANDOUT
REFERENCES ALLOWED
Unit 2 is at 100% rated power. While planning maintenance near the feedwater lines it has
been determined that the total dose received by the four required maintenance personnel
can be reduced by -475 mrem if reactor power is reduced to 75% (with or without a
reduction in hydrogen injection) or can be reduced by -1 60 mrem if the hydrogen injection
rate is reduced.
JPM NO. A3.3
REV. NO 0
PAGE 1 of 6
BROWNS FERRY NUCLEAR PLANT
JPM NUMBER: A3.3
TITLE: SECTION A QUESTION (SRO ONLY)
TASK NUMBER: S-000-AD-91
SUBMITTED B Y 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. A3.3
REV. NO 0
PAGE 2 o f 6
BROWNS FERRY NUCLEAR PLANT
OPERATOR:
J P M ~ M B E R : - A3.2
TASK NUMBER: S-000-AD-91
TASK TITLE: SECTION A QUESTION (SRO ONLY)
WA NUMBER: -268000A1.02 RO- 2.6 -
SRO 3.6
...................................................................................................
TASK STANDARD: Using available references, answer the question as described.
LOCATION OF PERFORMANCE: SIMULATOR - x PLANT - x CONTROL ROOM - x
REFERENCESIPROCEDURESNEEDED: ODCM, Rev 14, Page 19
VALIDATION TIME: CONTROL ROOM: N/A LOCAL: NIA
MAX. TIME ALLOWED: N/A (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
JPMNO. A3.3
-REV. NO 0
PAGE 3 o f 6
JPM NO. A3.3
REV.NO 0
PAGE 4 0 F 6
BROWNS FERRY NUCLEAR PLANT
EXAMINERS KEY
REFERENCES ALLOWED
SRO ONLY
QUESTION
During discharge of a floor drain sample tank to the river, 0-RM-90-130, Liquid Radwaste
Effluent Monitor, went downscale and it has been determined that the detector must be
replaced.
What compensatory actions must be taken in order to complete the release without O-RM-
90-130?
EXPECTED RESPONSE (EXACT WORDING NOT REQUIRED)
1. The instrument should be declared inop (10%)
2. The release must be suspended until compensatory measures are completed (20%)
3. Two independent samples of the tank contents shall be analyzed by two qualified
station personnel who shall independently verify the release rate calculations and check
valving before the discharge. (70%)
REFERENCES
1. 0-01-776, Rev 38, Page18
2. 0-SI-4.8.A.l-1, Rev 60, Page 4
3. Offsite Dose Calculation Manual (ODCM), Rev 14, Page 19
CANDIDATES HANDOUT
REFERENCES ALLOWED
During discharge of a floor drain sample tank to the river, 0-RM-90-130, Liquid Radwaste
Effluent Monitor, went downscale and it has been determined that the detector must be
replaced.
What compensatory actions must be taken in order to complete the release without O-RM-
90-130?
JPM NO. A4.1
REV. NO. 0
PAGE I O F 22
JPM NUMBER: A4.1
TITLE: RESPOND TO A SECURITY EVENT IAW 0-AOI-100-8
TASK NUMBER: U-000-AB-11 S-000-AB-11
SUBMITTED BY: DATE:-
VALIDATED BY: DATE:-
APPROVED: DATE:-
TRAINING
PLANT CONCURRENCE:
OPERATIONS
DATE:-
- Examination JPMs Require Operations Training Manager or Designee Approval
and Plant Concurrence
JPM NO. A4.1
REV. NO. 0
PAGE 20F 2 2
REVISION LOG
Revision Effective Pages Description
Number Date Affected of Revision
0 9/9/02 ALL NEW
JPM NO. A4.1
^REV. NO. 0
PAGE 30F 22
. . . .. i.. ,
OPERATOR:
JPM NUMBER: 204
TASK NUMBER: ADMIN
TASK TITLE: RESPOND TO A SECURITY EVENT IAW 0-AOl-100-8
K/A NUMBER: 2.1.8 KIA RATING: RO 3.8 SRO: 3.6
.............................................................................................
TASK STANDARD: DISPATCH PERSONNEL IN RESPONSE TO A SECURITY EVENT
IAW 0-AOl-100-8.
LOCATION OF PERFORMANCE: SIMULATOR X PLANT - - CONTROL ROOM -
REFERENCESlPROCEDURES NEEDED: 0-AOI-100-8, REV 0009
VALIDATION TIME: CONTROL ROOM: 2O:OO LOCAL: -
MAX. TIME ALLOWED: -(Completed for Time Critical JPMs only)
PERFORMANCETIME: - CONTROL ROOM - LOCAL -
COMMENTS:
Additional comment sheets attached? YES - NO -
RESULTS: SATISFACTORY - UNSATISFACTORY-
EXAMINER SIGNATURE: - DATE: -
EXAMINER
JPM NO.A4.1
REV. NO.0
PAGE 40F 22
... . .
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. .... .....~
..
__
.
~~
.
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.......................................................................................................
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 1 Operator. Unit 2 is at 100% power and Unit
3 is 3 days into a refueling outage. Site Security has just notified the Shift Manager that a
group of armed guerrillas have breached the protected area but have been stymied for
the present by Nuclear Security.
INITIATING CUES: The Shift Manager directs you to carty out the operator actions of 0-
AOI-100-8, Security Event Response.
JPM NO.A4.1
REV-NO. 0
PAGE 6 OF22
1.0 PURPOSE
This instruction provides guidance for Operations Management
to evaluate and respond to site security events, and
provides appropriate interface with Nuclear Security
Services (NSS).
2.0 SYMPTOMS
Notified that an air attack on the plant site is
imminent.
Notified that plant security has been violated or
degraded by attack threat.
Notified of potential or actual acts of tampering,
vandalism, or malicious mischief. [NRC IE Notice 96-71]
Bomb threat received or sabotage device discovered.
Notified of other security contingency event (ex., civil
disturbance, internal disturbance, fire, explosion, non-
attack threats) .
3.0 AUTOMATIC ACTIONS
NONE.
4.0 OPERATOR ACTIONS
4.1 Immediate Actions
NONE.
JPM NO.A4.1
REV. NO. 0
PAGE 7 OF22
4.2 Subsequent Actions
The following steps are presented in a recommended order.
However, these steps may be performed in any order and
readdressed at any time due to circumstances and chronology of
the security event, but all steps shall be addressed prior to
procedure exit.
4.2.1 IF notified that an air attack on the plant site is
imminent, THEN extinguish all visible sources of light at
..
the plant as follows: ........................................
NOTE::
Shift Managers and licensed personnel have responsibility to
direct reasonable action that departs from a license condition or
Technical Specifications in an emergency when this action is
immediately needed to protect the public health and safety where
no action consistent with license conditions and Technical
Specifications that can provide equivalent protection is
immediately apparent. [10CFR50.54(x) and (y)1
..................................................................
Performance Step: Critical- Not Critical X
4.2.2 IF notified that plant security has been violated or
degraded by attack threat (Protected Area breached by
Adversarial Force), THEN
4.2.2.1I&f&fEDIATELYNOTIFY Unit 2 and Unit 3 Unit
Supervisors of the site security event.
Standard:
NOTIFIES Unit 2 and Unit 3 Unit Supervisors of site security
event.
SAT-UNSAT_N/A- COMMENTS:
JPM NO.A4.1
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PAGE 8 OF22
JPM NO.A4.1
TIEV.'NO.0
PAGE 9 OF22
..................................................................
__I
Performance SteD: Critical- Not Critical2
4.2.2.2PERFORM the following as applicable:
4.2.2.2.1 INITIATE a manual Reactor Scram on
all operating units. REFER TO
2 (3)-AOI-lOO-l.
4.2.2.2.2 ENSURE fuel movement stopped and
Dlace anv fuel bundle beina moved
in a safe condition. REFER TO 0 -
GO1 - 100 -3C.
Standard :
None
SAT-UNSAT_N/A- COMMENTS :
..................................................................
CUES: BY SHIFT MANAGER DIRECTIVE UNIT 2 HAS BEEN MANUALLY
SCRAMMED AND UNIT 3 REFUELING SUSPENDED WITH ALL FUEL BUNDLES
SECURED.
L
....................................................................
Performance SteD: Critical X Not Critical
4.2.2.3Unit 1 Operator MAKE a plant announcement
similar to the following: "ATTENTION, ALL
PLANT PERSONNEL, A SITE SECURITY EVENT IS IN
PROGRESS."
Standard:
JPM NO.A4.1
'REV. NO. 0
PAGE 10 OF22
MAKES P . A . announcement.
.~~.~.
.-. ~.. ~ ~ ..
SAT-UNSAT-N/A- ..,.COMMENTS. : ~ ~ ~~ ~
. . ..
~~
.
~ ~~
_.
..................................................................
JPM NO.A4.1
T E V . NO. 0
PAGE 11 OF22
..................................................................
Performance Steu: _ _ Critical- Not Critical X
4.2.2.4Units 1, 2, 3 VERIFY ZETRON dispatch console
is selected to NSS Channel (PSS HB) and
MONITOR the security event UNTIL terminated.
REFER TO Attachment 1 AND PIP 97-182, Site
Security Diagram, as necessary.
PERFORM all communication with Operations
personnel USING communication systems OTHER
THAN the Unit ZETRON dispatch console.
Standard:
VERIFIEDS ZETRON selected to NSS Channel and DIRECTED all
operations communication be performed using OTHER THAN ZETRON.
SAT-UNSAT-N/A- COMMENTS:
..................................................................
..................................................................
Performance Steu: Critical- Not Critical X
4.2.2.5 Shift Manager/affected Unit Supervisor
ESTABLISH AND MAINTAIN open channel
communication with NSS Shift Supervisor,
using X2219 and/or Operations frequency 1
(NSS frequency 5 ) .
Standard:
ESTABLISHES AND MAINTAINS open channel communication with N S S
Shift Supervisor, using X2219 and/or Operations frequency 1 (NSS
frequency 5 ) .
SAT-UNSAT-N/A- COMMENTS:
JPM NO.A4.1
REV. NO. 0
PAGE 12 OF22
CUE: [WHEN ESTABLISHED1 COMMUNICATIONS WITH THE NUCLEAR SECURITY
SUPERVISOR HAVE BEEN ESTABLIHED.
JPM NO.A4.1
T?EV.NO.0
PAGE 13 OF22
..................................................................
Performance SteD: ~ -Critical X Not Critical
4.2.2.6 INITIATE Control Room Emergency Ventilation
System from panel 2-9-22 by PLACING CREV
TRAIN A(B) INIT/CB ISOL, 0-HS-31-150A (0-HS-
31-150B) in the INIT/TEST position.
Standard :
SIMULATES PLACING 0-HS-31-150AOR 0-HS-150B in the INIT/TEST
position.
SAT-UNSAT_N/A- COMMENTS:
CUB: [WHEN SIMULATED] CREVS HAS BEEN INITIATED.
..................................................................
Performance Step: Critical X Not Critical
4.2.2.7 PERFORM a Manual Fast Start of the Standby
Diesel Generators from panel 2-9-8 and 3-9-8
via switches 2-HS-82-1and 3-HS-82-1.
Standard :
At Panel 2-9-8 manually fast STARTS requests U2 Operator to
fast start Unit 1/2 diesel generators and DIRECTS Unit 3 Operator
to start Unit 3 diesel generators.
SAT-UNSATN/A_ COMMENTS:
JPM NO.A4.1
-REV.-NO. 0
PAGE 14 OF22
..................................................................
.. .... . ~. ~ .~ ~ .
. ... , . . .. . ~. . . .... : ~ --
CUE: [WHEN CONTACTED] ALL 4 UNIT 3 DIESEL GENERATORS ARE
RUNNING.
JPM NO.A4.1
-REV. NO.0
PAGE 15 OF22
..
..................................................................
-.
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. ,
- ,~~
..
~~~~ ~
. :
Performance SteD: Critical X Not Critical
4.2.2.8 START a Fire Pump (Preferred start of an
electric fire pump in the selected sequence
at panel 1-9-20 via switch HS-26-1A, 2A or
3A) .
Standard:
At Panel 1-9-20,STARTS one of the electric fire pumps..
SAT_UNSAT_A- COMMENTS :
..................................................................
NUCLEAR SECURITY HAS ADVISED THE SHIFT MANAGER THAT TWO OF THE
INTRUDERS HAVE MADE THEIR WAY INTO THE SERVICE BUILDING.
JPM NO.A4.1
--%V.NO. 0
PAGE 16 OF22
NOTE:
For purposes of this instruction, Power Block refers to the contiguous
enclosed buildings comprised of the Unit 3 D.G. Building, the combined Unit
Reactor Buildings, the combined Turbine Building, the Unit 1/2 D.G. Building,
the Radwaste .Building,
~ ~ , ~ ~ ~ . . .. .,..
~
the
. ~
Service Building
.~ .... . . . ~ .. ~ .,~~
and the Plant Office Building.
4.2.3 IF notified that the Adversarial Force has entered
the Power Block, THEN:
..................................................................
Performance Step: C r i t i c a l 2 Not Critical
4.2.3.1 UNLESS notified by NSS that the Control Bay
elevator is immobilized, THEN at panel 0-9-
23-7. DEENERGIZE 4KV Shutdown Board A as
follows:
m:
4KV Shutdown Board A is deenergized from the control room so that
480v DSL AUX Board A is deenergized and thus the Control Bay
elevator is verified immobilized.
4.2.3.1.1 Momentarily DEPRESS, O-HS-211-A, 4KV
SD BD AUTO TO MANUAL TRIP
push-button.
4.2.3.1.2 Momentarily DEPRESS the DG A
EMERGENCY SHUTDOWN push-button,
0-HS-82-A/4.
4.2.3.1.3 Momentarily PLACE O-HS-211-A/3A, 4KV
SD BD A NORM FDR BKR 1614, to TRIP.
Standard:
DEENERGIZES 'A' 4KV Shutdown Board by:
0 DEPRESSING O-HS-211-A, 4KV SD BD AUTO TO MANUAL
DEPRESSING DG A EMERGENCY SHUTDOWN push-button,
0-HS-82-A/4
0 PLACING O-HS-211-A/3A, 4KV SD BD A NORM FDR BKR
1614, to TRIP
SAT-UNSAT-N/A- COMMENTS:
JPM NO.A4.1
REV.NO. 0
PAGE 17 OF22
..................................................................
Performance Step: Critical- Not Critical X
4.2.3.2 PLACE CONTROL ROOM DOORS MANUAL CONTROL
keylock switch in LOCK at Unit 1/2 Shift
Manager's Console.
Standard:
REQUESTS Shift Manager to lock the control room doors.
SAT-UNSAT-N/A- COMMENTS:
..................................................................
CUE: [WHEN REQUESTED] CONTROL ROOM DOORS ARE LOCKED. 1
..................................................................
Performance Step: Critical- Not Criticalx
4.2.3.3 Unit 1 Operator MAKE a plant announcement
similar to:
"ATTENTION, ALL PLANT PERSONNEL, PLEASE STAY AT YOUR CURRENT
LOCATION DURING THIS SECURITY EVENT."
Standard :
MAKES plant announcement.
SAT-UNSAT-N/A- COMMENTS :
JPM NO.A4.1
REV. NO.0
PAGE 18 OF22
..................................................................
JPM NO.A4.1
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PAGE 19 OF22
..................................................................
Performance SteD: C r i t i c a l X Not Critical
_-
4.2.3.4 RAISE Reactor Water Level to maximum level
indication on the normal reactor water level
monitoring instrumentation.
Standard :
REQUESTS ~2 Us/Unit Operator to raise RPV water level to +60
inches.
SAT-UNSAT-N/A- COMMENTS:
..................................................................
..................................................................
Performance SteD: Critical X Not Critical
4.2.3.5 COMMENCE a reactor plant cooldown to expedite
reaching cold shutdown conditions.
Standard :
INFORMS Shift Manager that a Unit 2 cooldown is required.
SAT-UNSAT-N/A- COMMENTS :
..................................................................
CUE: [WHEN REQUESTED] THE SHIFT MANAGER HAS DIRECTED A U2
cnni.nnww I
JPM NO.A4.1
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PAGE 20 OF22
4.2.4 IF notified of any act of tampering, vandalism,
malicious mischief, bomb threat, or other security
contingency event, THEN....._....
"...."..
CUE: NUCLEAR SECURITY HAS INFORMED THE SHIFT MANAGER THAT THE
INTRUDERS HAVE BEEN NEUTRALIZED. THIS ENDS THE JPM.
END OF TASK
STOP TIME
JPM NO.A4.1
-REV. NO.0
PAGE 21 OF22
..............................................................................
Performance Steu: Critical-Not CriticalL
PERFORMER demonstrated the use of 3-WAY COMMUNICATION during this 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- COMMENTS:
............................................................
Performance Step: Critical- Not Critical2
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 N/A- COMMENTS:
JPM NO.A4.1
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PAGE 22 OF22
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JPMNO. A4.2
REV. NO. 0
PAGE 1 OF 10
TITLE: RESPOND TO A SECURITY EVENT IAW 0-AOI-100-8
TASK NUMBER: S-000-AB-11
SUBMllTED B Y DATE:-
VALIDATED BY: DATE-
APPROVED:
TRAINING
DATE:-
PLANT CONCURRENCE:
OPERATIONS
DATE:-
- Examination JPMs Require Operations Training Manager or Designee Approval
and Plant Concurrence
JPMNO. A4.2
REV. NO. 0
PAGE 2 OF 10
REVISION LOG
Revision Effective Pages Description
Number Date Affected of Revision
0 9/9/02 ALL NEW
JPM NO. A4.2
-REV. NO. 0
PAGE 3 OF 10
- . , ,. . .
. .... ~ ., .. :
OPERATOR:
TASK NUMBER: S-000-AB-11
TASK TITLE: RESPOND TO A SECURITY EVENT IAW 0-AOI-100-8
WA NUMBER: 2.1.8 WA RATING: RO 3.8 SRO: 3.6
. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ....................
TASK STANDARD: PERFORM THE ACTIONS REQUIRED BY 0-AOI-100-8,
RESPONSE TO A SECURITY EVENT.
LOCATION OF PERFORMANCE: SIMULATOR - X PLANT - CONTROL ROOM -
REFERENCESlPROCEDURES NEEDED 0-AOl-100-8, REV 9
VALIDATION TIME: CONTROL ROOM: 9:00 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
NCEMEASURE
.. ... ~-. ..
.. . . ...~ ~
..
......................................................................................................
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.
........................................................................................
mm
INITIAL CONDITIONS: You are a Unit Supervisor. Security has notified the Shift
Manager that a warning has been received from the FAA that unknown and unresponsive
aircraft are approaching the Browns Ferry Nuclear Plant area and an air attack on the
plant is possible. The time is 2:30 AM. Units 2 and 3 are at 100% power.
INITIATING CUES: The Shift Manager directs you to carry out the actions of O-AOI-100-
8 , Security Event Response.
JPMNO. A4.2
- V. NO. 0
PAGE 5 OF 10
~ ~ ... ~
. .
1.0 PURPOSE
~ .- ~ ..~..
This instruct~io,n. provides.guidance for Operations Management
to evaluate and respond to site security events, and .-.. .~.. _ ( :
~
provides'~appr0priateinterface with Nuclear-Secu~rity'
Services (NSS).
.
2.0 SYMPTOMS
Notified that an air attack on the plant site is
imminent.
Notified that plant security has been violated or
degraded by attack threat.
Notified of potential or actual acts of tampering,
vandalism, or malicious mischief. [NRC IE Notice 96-71]
Bomb threat received or sabotage device discovered.
Notified of other security contingency event (ex., civil
disturbance, internal disturbance, fire, explosion, non-
attack threats) .
3.0 AUTOMATIC ACTIONS
NONE.
4.0 OPERATOR ACTIONS
4.1 Immediate Actions
NONE.
JPMNO. A4.2
REV.NO. 0
PAGE 6 OF 10
4.2 Subsequent Actions
___
NOTE:
The following steps are presented in a recommended order.
However, these steps may be performed in any order and
readdressed at any time due to circumstances and chronology of
the security event, but all steps shall be addressed prior to
procedure exit.
4.2.11F notified that an air attack on the plant site is
imminent, THEN extinguish all visible sources of light
at the plant as follows:
..................................................................
Performance SteD: CriticalX Not Critical
4.2.1.1 PLACE O-HS-247-Rl/R2,EAST/WEST STREET AND STACK
LIGHTING, on panel 0-9-23-3to OFF.
4.2.1.2 OPEN Breaker 4D on 480v Common Board 1 for WEST AND
SOUTH SIDE STREET & STACK LIGHTING.
4.2.1.3 OPEN Breaker 5C on 4EOv Common Board 2 for NORTH, EAST
AND SOUTH SIDE STREET LIGHTING.
Standard :
DISPATCHED personnel to
Place O-HS-247-Rl/R2to OFF
OPEN Breaker 4D on 480v Common Board 1
OPEN Breaker 5C on 480v Common Board 2
SAT-UNSAT-N/A- COMMENTS:
JPMNO. A4.2
REV.NO. 0
PAGE 7 OF 10
..................................................................
-Performance Stew: Critical X Not Critical
4.2.1.4 IF exterior plant lighting (transformer yard, parking,
switchyard, etc.) is illuminated, THEN PERFORM the
following steps to extinguish exterior lighting:
4.2.1.4.1 DISPATCH personnel to the Security Diesel
Building to OPEN the following breakers on the
4 8 0 v SECURITY MCC Board (may require an MC key
to access the building):
Breaker 2A, Yard Lighting
Breaker 2E, Yard Lighting
Breaker 3A, Yard Lighting
Standard:
DISPATCHED personnel to the Security Diesel Building to OPEN the
above 3 breakers
SAT_UNSAT_N/A- COMMENTS :
..................................................................
JPMNO. A4.2
-RV.NO. 0
PAGE 8 OF 10
...................................................................
Performance Stew: Critical X Not Critical
4.2.1.4.2 DISPATCH personnel to the following switchyard
distribution cabinets to OPEN the following
breakers to deenergize transformer and
switchyard area lighting:
Breaker 15 (LC 6 0 ) , 480V XFMR YARD
DIST CAB 1
Breaker 17 (LC 61), 480V XFMR
.. . YARD
._...
DIST CAB 3
Breaker 9 (LC 6 6 ) , 500KV SWITCHYARD
24OV DISTRIBUTION CABINET NO. 1-1
Breaker 10 (LC 71), 500KV SWITCHYARD
240V DISTRIBUTION CABINET NO. 1-2
Breaker 10 (LC 73), 500KV SWITCHYARD
240V DISTRIBUTION CABINET NO. 2-1
Breaker 10 (LC 72), 500KV SWITCHYARD
240V DISTRIBUTION CABINET NO. 2-2
Standard:
DISPATCHED personnel to switchyard to OPEN the above 6 breakers.
SAT-UNSAT_N/A- COMMENTS:
...................................................................
JPMNO. A4.2
REV.-NO. 0
PAGE 9 OF 10
............... . . . .
..................................................................
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. . . . . . .
. . . . . . . . .. .. . . . .- . . .
Performance Step: .CriticalX Not Critical
4.2.1.4.3 Based on estimated reaction time PERFORM
one of the following:
4.2.1.4.3.1 DISPATCH personnel to the Office
Buildings, Cooling Towers,
Administration Building,
Engineering Building, Training
Building, Livewell Center,
Warehouse Building and any other
outbuildings which may be
illuminated to ensure lighting is
extinguished.
- OR -
-
4.2.1.4.3.2 DISPATCH personnel to the COOLING
TOWER SWITCHGEAR C & D BUILDING to
OPEN the following breakers:
0 4KV COOLING TOWER SWITCHGEAR C,
Breaker 7,
SOUTH LOOP LINE POWER
0 4KV COOLING TOWER SWITCHGEAR D,
Breaker 1,
CONSTRUCTION LOOP LINE
4KV COOLING TOWER SWITCHGEAR D,
Breaker 7,
NORTH LOOP LINE POWER
Standard :
DISPATCHED personnel to individual areas to extinguish lights
to
cooling tower switchgear to open 3 breakers.
SAT-UNSAT-N/A- COMMENTS:
JPMNO. A4.2
-REV. NO. 0
PAGE 10 OF 10
..................................................................
- _
CUE: SECURITY HAS NOTIFIED YOU THAT THE IMMINENT AIR ATTACK WAS A
FALSE ALARM AND ALL IS CLEAR. THIS ENDS THE J P M .
STOP TIME
......................................................................................................
Performance Step: Critical-Not Critical-X- -
PERFORMER demonstrated the use of 3-WAY COMMUNICATION during this 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- COMMENTS:
- JPM NO. A3.1
REV-NO 0
PAGE 1 of 5
.. .. . . .,. . BROWNS FERRY NUCLEAR PLANT: ... . ' ..
. . I JOB PERFORMANCE MEASURE '. : . ' '/:'
JPM NUMBER: A3.1
TITLE: SECTION A QUESTION
TASK NUMBER: U-000-AD-17 S-000-AD-89
SUBMITTED BY: DATE: -
VALIDATED BY: DATE:-
APPROVED:
TRAl NING
DATE:-
PLANT CONCURRENCE: DATE:
OPERATIONS
-
- Examination JPMs Require Operations Training Manager or Designee Approval
and Plant Concurrence
JPM NO. A3.1
REV.NO 0
PAGE 2 o f 5
. .. . ..
BROWNS FERRY NUCLEAR PLANT
. .
- . ", . .
' .. ,
.
. . '. .
.. . JOB PERFORMANCE MEASURE .' . ..
. . . . .. . .
OPERATOR:
JPMWMBER: - A3.1
TASK NUMBER: U-000-AD-17 S-000-AD-89
TASK TITLE: SECTION A QUESTION
WA NUMBER: 2.3.1 1 WA RATING: RO 2.7 -SRO: - 3.2
..................................................................................................
TASK STANDARD: Using available references, answer the question as described.
LOCATION OF PERFORMANCE: SIMULATOR x PLANT - - x CONTROL ROOM x -
REFERENCESlPROCEDURES NEEDED: 2-ARP-9-3A, Rev 19
VAL I DATION TIME: CONTROL ROOM: N/A LOCAL: N/A
MAX. TIME ALLOWED: N/A (Completed for Time Critical JPMs o n l y )
PERFORMANCE TIME:
COMMENTS:
- CONTROL ROOM - LOCAL -
Additional comment sheets attached? YES - NO -
RESULTS: SATISFACTORY- UNSATISFACTORY-
EXAMINER SIGNATURE: DATE:
EXAMINER
-
.. . .. ~ . .
~
. : ,
. ... . . .. -
EXAMINERS KEY
REFERENCES ALLOWED
QUESTION
2-XA-55-3A, Window 27, 'MAIN STEAM LINE RADIATION HIGH-HIGH is in alarm. The following steam line
radiation readings are obtained:
2-RM-90-136 1.9E3 MWHR (Panel 9-10)
2-RM-90-137 2.6E3 MFUHR (Panel 9-10)
2-RM-90-138 2.4E3 MWHR (Panel 9-10)
2-RM-90-139 2.1E3 MWHR (Panel 9-10
2-RR-90-135 2.31E3 MFUHR (Both Channels) (Panel 9-2)
2-RR-90-157 5.30 WHR (Was steady at 4.0 WHR over the previous 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.)
What actions are required?
EXPECTED RESPONSE (EXACT WORDING NOT REQUIRED)
1. Notify RADCON (25%)
2. Request chemical analysis of primary coolant (25%)
3. Secure Hydrogen Water Chemistry (25%)
4. Possible power reduction (25%)
REFERENCES
2-ARP-9-3A, Rev 19, Page 29
OPERATOR ACTION:
4. If off -gas pretreatment radiation, 2-RR-90-157, has risen significantly (30% above
previous hour average),THEN...
-.
CANDIDATES HANDOUT
REFERENCES ALLOWED
2-XA-55-3A, Window 27, MAIN STEAM LINE RADIATION HIGH-HIGH is in alarm. The
following steam line radiation readings are obtained:
2-RM-90-136 1.9E3 MFUHR
2-RM-90-137 2.6E3 MFUHR
2-RM-90-138 2.4E3 MWHR
2-RM-90-139 2.1 E3 MWHR
2-RR-90-135 2.31 E3 MFUHR (Both Channels)
2-RR-90-157 5.30 FUHR (Was steady at 4.0 FUHR over the previous 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.)
What actions are required?
JPM NO. A l . l
REV.NO 0
PAGE 1 OF4
. .
. . BROWNS FERRY NUCLEAR PLANT 2 ' j '. ' ' .., ., , .
JOB PERFORMANCE MEASURE .. . ,.I , .
JPM NUMBER: A I .I
TITLE: SECTION A QUESTION
TASK NUMBER: U-074-NO-12 S-074-AB-01
SUBMITTED BY: DATE: -
VALIDATED BY: DATE: -
APPROVED:
TRAINING
DATE: -
PLANT CONCURRENCE:
OPERATIONS
DATE:
-
- Examination JPMs Require Operations Training Manager or Designee Approval
and Plant Concurrence
JPMNO. A l . l
REV.NO 0
PAGE 20F4
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BROWNS FERRY NUCLEAR PLANT , , ,
.,.
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,
JOB PERFORMANCE MEASURE ,. I~
.. . . . ~,
1 i
OPERATOR
JPM~MBER: - Al.l
TASK NUMBER: U-074-NO-12 5-074-AB-01
TASK TITLE: SECTION A QUESTION
KIA NUMBER: 2.1.23 -
WA RATING: RO 3.9 SRO: 4.0 -
..................................................................................................
TASK STANDARD: Using available references, answer the question as shown. Exact
wording is not required.
LOCATION OF PERFORMANCE: SIMULATOR - x PLANT - x CONTROL ROOM x -
REFERENCESlPROCEDURES NEEDED: O-GOI-300-3C, FUEL MOVEMENT
OPERATIONS DURING REFUELING
VALIDATION TIME: CONTROL ROOM: N/A LOCAL: NIA
MAX. TIME ALLOWED: N/A (Completedfor Time Critical JPMs o n l y )
PERFORMANCE TIME: NIA
COMMENTS:
CONTROLROOM N/A -LOCAL N/A
Additional comment sheets attached? YES - NO -
RESULTS: SATISFACTORY - UNSATISFACTORY-
EXAMINER SIGNATURE: DATE: -
JPM NO. A l . l
--REV.NO 0
PAGE 30F4
EXAMINER
JPM NO. A I .I
AEV.NO 0
PAGE 4 0 F 5
8 ,..: .. '
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BROWNS FERRY NUCLEAR PLANT , ': , ,. . . . .
JOB PERFORMANCE MEASURE . ' . .' ' . .
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., ,.
,
.', . .
. ,
EXAMINER'S KEY
REFERENCES ALLOWED
QUESTION
During Unit 2 refueling operations near the core periphery, RHR shutdown cooling flow is
making it difficult for the fuel handlers to see into the reactor core. What measures can be
taken to rectify the problem?
EXPECTED RESPONSE (exact wording not required)
1. Reduce shutdown cooling flow (40%)
2.Temporarily secure shutdown cooling if: (40%)
e Shift manager approves (10%)
An alternate means of core temperature monitoring is initiated (10%)
Reference: O-GOI-100-3C, Rev 41; Page 10, Step 3.3.5
CANDIDATES HANDOUT
-__
REFERENCES ALLOWED
QUESTION
During Unit 2 refueling operations near the core periphery, RHR shutdown cooling flow is
making it difficult for the fuel handlers to see into the reactor core. What measures can be
taken to rectify the problem?
JPM NUMBER: A4.5
TITLE : CLASSIFY THE EVENT PER THE REP
TASK NUMBER: S-000-EM-21
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. 114
REV. NO. 9
PAGE 2 OF 6
BROWNS FERRY NUCLEAR PLANT
REVISION LOG
Revision Effective Pages Description
Number Date Affected of Revision
0 10/25/02 ALL NEW
JPM NO, 174
REV. NO. 9
PAGE 3 OF 6
OPERATOR :
JPM NUMBER: A4.5
TASK NUMBER: S-000-EM-21 (SRO ONLY)
TASK TITLE: CLASSIFY THE EVENT PER THE REP
K/A NUMBER: 2.4.38 K/A RATING: R O a SRO: 4.0
..................................................................
TASK STANDARD: THE EVENT IS CLASSIFIED AS AN SITE AREA EMERGENCY
BASED ON REACTOR WATER LEVEL CANNOT BE MAINTAINED
ABOVE -162 INCHES
LOCATION OF PERFORMANCE: SIMULATOR PLANT - CONTROL ROOM -
REFERENCES/PROCEDURES NEEDED: EPIP 1, REV 29; EPIP 4, REV 26
VALIDATION TIME: CONTROL ROOM: 8:OO LOCAL: N/A
MAX. TIME ALLOWED: (Completed for Time Critical JPMs only)
PERFORMANCE TIME: CONTROL ROOM _ _ LOCAL N/A
COMMENTS:
JPM NO. 174
--REV.NO. 9
PAGE 4 OF 6
Additional comment sheets attached? YES __ NO __
RESULTS : SATISFACTORY
. .
~ ~~ UNSATISFACTORY
..... ~._. . . ~
. ..: .
~..-
SIGNATURE: DATE:
EXAMINER
BROWNS FERRY NUCLEAR PLANT
JOE PERFORMANCE MEASURE
INITIAL CONDITIONS: You are the SHIFT MANAGER. Unit 2 was
operating at 100% power. A large reactor coolant leak occurred
on Unit 2. Drywell pressure increased above 2.45 psig. All high
pressure ECCS fail. Unit 1 and 3 are in cold shutdown. EOI-1 and
2 are in progress on Unit 2 . Operations personnel are venting
primary containment per 2-EO1 Appendix 12.
INITIATING CUES: The Unit 2 UNIT SUPERVISOR has informed you
that reactor water level has lowered to -162" and is slowly
trending downward due the failure of all high pressure ECCS
makeup. RHR and CORE SPRAY systems are available, and preparations
are in progress for emergency depressurization by control room
personnel.
CLASSIFY THE EVENT according to the EPIPS.
Reactor Power Shutdown with all rods in
Reactor Level -162" inches and trending down
Reactor Pressure 950 psig
DW Pressure 3.6 psig and rising
DW Temperature 182 degrees F
DW Radiation RR-90-256 slowly rising (prior to
isolation)
Torus Temperature 96 degrees F
Torus Pressure 2.2 psig
Torus Level +4 inches
JPM NO. 174
--REV. NO. 9
PAGE 5 OF 6
NOTE: Unit 2 conditions are deteriorating and wind speed is 10
mph
~~. -
from
~.
the NW. .~.No
~ ~ . ~~
abnormal
.. ~ ..
radiological releases offsite.
... - . _ _. ~. ~~. . ..
. .
,;
STUDENT HANDOUT ...
.
INITIAL CONDITIONS: You are the SHIFT MANAGER. Unit 2 was
operating at 100% power. A large reactor coolant leak occurred
on Unit 2. Drywell pressure increased above 2.45 psig. All high
-pressure ECCS fail. Unit 1 and 3 are in cold shutdown. EOI-1 and
2.are in progress on Unit 2. Operations personnel are venting
primary containment per 2-EO1 Appendix 12.
INITIATING CUES: The Unit 2 UNIT SUPERVISOR has informed you
that reactor water level has lowered to -162" and is slowly
trending downward due the failure of all high pressure ECCS
makeup. RHR and CORE SPRAY systems are available, and preparations
are in progress for emergency depressurization by control room
personnel.
CLASSIFY THE EVENT accordinq to the EPIPs.
Reactor Power Shutdown with all rods in
Reactor Level -162" inches and trending down
Reactor Pressure 950 psig
DW Pressure 3.6 psig and rising
DW Temperature 182 degrees F
DW Radiation RR-90-256 slowly rising (prior to
isolation)
Torus Temperature 96 degrees F
Torus Pressure 2.2 psig
Torus Level +4 inches
NOTE: Unit 2 conditions are deteriorating and wind speed is 10
mPh from the NW. No abnormal radiological releases offsite.
JPM NO. A4.7
REV:NO 0
PAGE 1 OF 5
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BROWNS FERRY NUCLEAR PLANT . . . ,.' ' . .
... .. . .
. . .
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JPM NUMBER: A4.7
TITLE: SECTION A QUESTION
TASK NUMBER: U-000-AD-17 S-000-AD-89
SUBMITTED BY: DATE -
VALIDATED BY: DATE:-
APPROVED: DATE:-
TRAINING
PLANT CONCURRENCE:
OPERATIONS
DATE: -
- Examination JPMs Require Operations Training Manager or Designee Approval
and Plant Concurrence
JPM NO. A4.7
REV.NO 0
PAGE 2 0 F 5
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.. ., . .. !.. . ... .... ..
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. . , .BROWNS.FERRYNUC.LEAR.PLANT--:
' JOB PERFORMANCE MEASURE . I ' '...
. .. ... j , . ,. I . ,. ..
OPERATOR:
JPM~BER:
SRO - A4.7
DATE:
TASK NUMBER: U-000-AD-17 S-000-AD-89
TASK TITLE: SECTION A QUESTION
WA NUMBER: 2.4.39 WA RATING: RO- 3.3 SRO: - 3.1
. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
TASK STANDARD: Without using references, answer the question as described. (Exact
wording is not required.)
LOCATION OF PERFORMANCE: SIMULATOR x PLANT - - x CONTROL ROOM - x
REFERENCES/PROCEDURES NEEDED: None
VALIDATION TIME: CONTROL ROOM: N/A LOCAL: N/A
MAX. TIME ALLOWED: N/A (Completed f o r m r i t i c a l JPMs o n l y )
PERFORMANCE TIME: N/A
COMMENTS:
CONTROLROOM N/A -LOCAL - N/A
Additional comment sheets attached? YES - NO -
RESULTS: SATISFACTORY - UNSATISFACTORY -
EXAMINER SIGNATURE: DATE
EXAMINER
-
JPM NO.A4.7
REV.NO 0
PAGE 3 OF 5
~
JPMNO. A4.7
-REV. NO 0
PAGE 4 0 F 5
EXAMINERS KEY
REFERENCES NOT ALLOWED
QUESTION:
Upon receiving a fire emergency call and obtaining the pertinent information, what four (4)
actions should the Unit Operator take?
EXPECTED RESPONSE
1. Initiate the fire alarm (50%)
2. Announce the fire location over the PA system at regular intervals until otherwise
instructed.(30%)
3. Notify fire protection personnel using the OpslFire Protection radio(lO%)
4. Notify the Shift Manager of the fire(lO%)
REFERENCE:
EPIP-21, Fire Emergency Procedure, Page 1, Step 3.2
.-
CANDIDATES HANDOUT
REFERENCES NOT ALLOWED
Upon receiving a fire emergency call and obtaining the pertinent information, what four (4)
actions should the Unit Operator take?
JPM NO. A4.6 .,
REV. NO 0
PAGE 1 OF 5
JPM NUMBER: A4.6
TITLE: SECTION A QUESTION
TASK NUMBER: U-000-AD-17 S-000-AD-89
SUBMllTED B Y 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. A4.6
REV.NO 0
PAGE 2 OF 5
OPERATOR:
JPM~MBER:
SRO - A4.6
DATE:
TASK NUMBER: U-000-AD-17 S-000-AD-89
TASK TITLE: SECTION A QUESTION
WA NUMBER: 2.4.39 WA RATING: RO- 3.3 SRO: -3.1
.
TASK STANDARD: Without using references, answer the question as described. (Exact
wording is not required.)
LOCATION OF PERFORMANCE: SIMULATOR x PLANT - - x CONTROL ROOM x -
REFERENCES/PROCEDURES NEEDED: None
VALIDATION TIME: CONTROL ROOM: N/A LOCAL: N/A
MAX. TIME ALLOWED: N/A (Completed f o r r i t i c a l JPMs o n l y )
PERFORMANCE TIME: N/A CONTROLROOM N/A LOCAL N/A
COMMENTS:
Additional comment sheets attached? YES - NO -
RESULTS: SATISFACTORY - UNSATISFACTORY -
EXAMINER SIGNATURE:
EXAMINER
DATE
-
JPM NO. A4.6
'-REV.-NO 0
PAGE 3 0 F 5
b______-.-_ _.__
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a
c
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JPM NO. A 1 2
-REV.NO 0
PAGE 40F5
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. . BROWNS ~EF~RY-,NUCLEAR PLANT :
.. ., . .
. . . .. . . . .
EXAMINERS KEY
REFERENCES NOT ALLOWED
QUESTION:
Upon receiving a Medical Emergency call, what information should the Unit Operator obtain
from the caller?
EXPECTED RESPONSE: (
-
1. Name of caller (30%)
2. Location of the medical emergency(40%)
-
3. Type of medical emergency(lO%)
4. Number of people involved (1O%)(
5. Telephone number of caller (10%)
6.
REFERENCE:
EPIP-10, Medical Emergency Procedure, Page 1, Step 3.1.1
-~
-_ -.
-
CANDIDATES HANDOUT
REFERENCES NOT ALLOWED
Upon receiving a Medical Emergency call, what information should the Unit Operator obtain
from the caller?
J P M NO. A1.5
-REV. NO 0
PAGE 1 OF 4
. . .,.
. . ' . BROWNS FERRY N'UCLEAR PLANT .." ....
'JOB PERFORMANCE MEASURE ; .'.
. . . .
h
JPM NUMBER: A I .5
TITLE: SECTION A QUESTION
TASK NUMBER: U-000-AD-17
SUBMITTED BY: DATE: -
VALIDATED BY: DATE:-
APPROVED: DATE-
TRAlNrNG
P -
PLANT CONCURRENCE: DATE
- Examination JPMs Require Operations Training Manager or Designee Approval
and Plant Concurrence
JPM NO. A1.5
REV. NO 0
PAGE 2 OF 4
. . ...
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BROWNS FERRY NUCLEAR PLANT ' .
I
.
, . . . .. . .
.. . ,
. - - --JOB:PERFORMAWCE
.. .. . , MEKSURE , . . . )..
. .
OPERATOR:
J P M ~ M B E R : - A1.5
TASK NUMBER: U-000-AD-17
TASK TITLE: SECTION A QUESTION
WA NUMBER: 2.1.32 KIA RATING: RO 3.4 SRO: 3.8
..................................................................................................
TASK STANDARD: Using references, answer the question as described. (Exact wording
is not required.)
LOCATION OF PERFORMANCE: SIMULATOR x PLANT - - x CONTROL ROOM - x
REFERENCES/PROCEDURESNEEDED: 2-01-78, Fuel Pool Cooling
VALIDATION TIME: CONTROL ROOM: NIA LOCAL: NIA
MAX. TIME ALLOWED: N/A (Completed for Time Critical JPMs o n l y )
PERFORMANCE TIME: NIA CONTROLROOM N/A LOCAL N/A
COMMENTS:
Additional comment sheets attached? YES - NO -
RESULTS: SATISFACTORY - UNSATISFACTORY -
EXAMINER SIGNATURE:
EXAMINER
DATE: -
JPM NO. A1.5
-REV. NO 0
PAGE 3 OF 4
.. . .
.. BROWNS FERRY NUCLEAR PLANT "
JOB PE-RFOR.MANCEMEASURE
..
_I
EXAMINERS KEY
REFERENCES ALLOWED
QUESTION:
Why is a spent fuel pool temperature of <00Idegrees F desired?
EXPECTED RESPONSE: This minimizes the release of soluble activity.
REFERENCE: 2-01-78, P&L 3.1
CANDIDATES HANDOUT
REFERENCES ALLOWED
Why is a spent fuel pool temperature of 4 0 0 degrees F desired?
JPM NO. A1.8
REV. NO ' 0
PAGE 1 of 5
. . .
JPM NUMBER: A I .8
TITLE: SECTION A QUESTION (SRO ONLY)
TASK NUMBER: S-000-NO-012
SUBMITTED BY: DATE:-
VALIDATED BY: DATE:-
APPROVED: DATE:-
TRAINING
PLANT CONCURRENCE:
OPERATIONS
DATE:-
- Examination JPMs Require Operations Training Manager or Designee Approval
and Plant Concurrence
JPM NO. A1.8
REV. NO 0 "
PAGE 2 of 5
OPERATOR:
JPM~MBER:
SRO - A I .8
DATE:
TASK NUMBER: U-000-AD-17 S-000-AD-89
TASK TITLE: SECTION A QUESTION
WA NUMBER: 2.1.8 WA RATING: RO 3.8 -SRO: - 3.6
.
TASK STANDARD: Without references, answer the question as described.
LOCATION OF PERFORMANCE: SIMULATOR - -
x PLANT x CONTROL ROOM x -
REFERENCESlPROCEDURESNEEDED
VALIDATION TIME: CONTROL ROOM: N/A LOCAL NIA
MAX. TIME ALLOWED: N/A (Completed f o r r i t i c a l JPMs o n l y )
PERFORMANCE TIME:
COMMENTS:
- CONTROL ROOM - LOCAL -
Additional comment sheets attached? YES - NO -
RESULTS: SATISFACTORY - UNSATISFACTORY-
EXAMINER SIGNATURE:
EXAMINER
DATE: -
JPM NO. A1.8
REV. NO 0
PAGE 3 OF 5
EXAMINERS KEY
REFERENCES ALLOWED
QUESTION
Unit three is approximately one-half the way through an in-progress fuel loading when the
refueling bridge malfunctioned requiring 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to repair.
How does the Fuel Handling Supervisor determine what prerequisites must be re-verified
prior to resuming fuel handling operations?
EXPECTED RESPONSE (EXACT WORDING NOT REQUIRED)
The prerequisites which must be re-confirmed are designated by note (8) throughout 0-G01-
100-3C.
REFERENCES
0-GOI-100-3C, Notes (3) and (8).
4.0 PREREQUISITES
(3) Prior to resuming fuel handling after a significant delay ( 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or
more) prerequisites denoted by ( 8 ) in this Section shall be reviewed and
verified by the Fuel Handling Supervisor to ensure continued compliance.
This review shall be documented by an entry in the Operations narrative
log AND on Attachment 3 . For surveillances (SIs/SRs) and maintenance
instructions, it is sufficient
(8) This procedure may be worked in conjunction with 0-GOI-100-3Aand/or 2.
Prerequisites completed in one procedure do not need to be repeated but
only v e r i f i e d using t h e companion procedure. In t h i r c a s e i n i t i a l
s t e p and denote v e r i f i e d p e r 0-GOI-100-3A o r s.
CANDlDATE'S HANDOUT
.>
REFERENCES ALLOWED f
QUESTION
Unit three is appro) lately one-half the way through an in-progress fuc 'ading when the
refueling bridge malfunctioned requiring 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to repair.
How does the Fuel Handling Supervisor determine what prerequisites must be re-verified
prior to resuming fuel handling operations?
JPM NO. A2.1
REV. NO. 0
PAGE 1 OF 17
- .,' . .. .. . .
BROWNS FERRY NUCLEAR PLANT
, . . . .
JPM NUMBER: 510
TITLE: EVALUATE RECOMBINER PERFORMANCE
TASK NUMBER: U-066-NO-02
SUBMITTED BY: DATE :
VALIDATED BY: DATE :
APPROVED : DATE :
TRAINING
PLANT CONCURRENCE: DATE :
OPERATIONS
JPM NO. A2.1,
REV. NO. 0
PAGE 2 OF 17
Examination JPMs Require Operations Training Manager or Designee Approval and
Plant Concurrence
JPM NO. A2.1
REV. NO. 0
PAGE 3 OF 17
, .
' ' BRO'NNS FERRY' NUCLEAR PLANT .. ~
.. . .
REVISION LOG
Revision Effective Pages Description
Number Date Affected of Revision
0 8/8/02 A1 1 New
JPM NO. A2.1
REV. NO. 0
PAGE 4 OF 17
. . . ~. . ... , .. .. . .
BROWNS' FERRY NUCLEAR PLANT ' :';::.
. . . , .. ..,
JOB PERFORMANCE IllEASURE , . .,' . . . .
. . . .
OPERATOR :
JPM NUMBER: A2.1
TASK NUMBER: U-066-NO-02
TASK TITLE: EVALUATE RECOMBINER PERFORMANCE IAW 3-01-66
K/A NUMBER: 2.17 K/A RATING: R O X SRO: 4.4
..................................................................
TASK STANDARD: SIMULATE EVALUATING OFF-GAS RECOMBINER PERFORMANCE
LOCATION OF PERFORMANCE: SIMULATOR - PLANT - CONTROL ,ROOM 2
REFERENCES/PROCEDURES NEEDED:3-01-66,OFF-GASSYSTEM,REVISION 0043
VALIDATION TIME: CONTROL ROOM: 12:OO LOCAL :
MAX. TIME ALLOWED: N/A (Completed for Time Critical JPMs
only)
PERFORMANCE TIME: CONTROL ROOM LOCAL __
-
COMMENTS :
JPM NO. A2.1
REV. NO. 0
PAGE 5 OF 17
Ad iti nal comment sheets attached? YES - NO -
RESULTS: SATISFACTORY UNSATISFACTORY
EXAMINER SIGNATURE: DATE :
- .~~
.~ ~~.
~
. . . . ....I~ .L - . .~ . ~ ~. ... -. .
...................................................................
IN-PLANT: I will explain the initial conditions and state the
task to be performed. All steps shall be simulated. I will provide
initiating cues and indicate any steps to be discussed. Ensure
that you observe electrical safety precautions when working near
energized equipment. When you complete the task successfully, the
objective for this job performance measure will be satisfied.
Ensure you indicate to me when you understand your assigned task
and when you have completed the assigned task.
INITIAL CONDITIONS: You are the desk operator. A startup is in
progress on Unit 3 and reactor power has been raised to 99% rated
thermal power. The Hydrogen Water Chemistry System is out of
service IAW 3-01-4.
INITIATING CUES: The Shift Operations Supervisor directs you to
evaluate Off-Gas Recombiner 3A performance in accordance with 3-01-
66, Section 6.1.
JPM NO. A2.1
REV. NO.0
PAGE I OF 17
6.0 SYSTEM OPERATIONS
6.1 Recombiner Performance Evaluation
NOTE :
1) The production of hydrogen and oxygen in the reactor is
dependent upon reactor power level and upon the amount of
hydrogen injected by the Hydrogen Water Chemistry System if
in service. Since the recombination of hydrogen and oxygen
is exothermic, the operating temperature of the recombiner is
also dependent upon power level and the status of the HWC
System.
2) Following startup, while still at low power, recombiner
performance and hydrogen concentration should be closely
monitored.
...........................................................
Performance Step: Critical- Not C r i t i c a l 2
OBTAIN a current copy of 01-66, Off-Gas System, Section
6.1,Recombiner Performance Evaluation.
Standard:
OBTAINED control room copy of 01-66, Off-Gas system, Section
6.1,Recombiner Performance Evaluation.
SAT-UNSAT-N/A- COMMENTS :
JPM NO. A2.1
REV. NO.0
PAGE 8 OF 17
.................................................................
~
~ -.
Performance step:^- - Critical- X Not Critical-
6.1.1 PERFORM a recombiner performance evaluation as
follows:
6.1.1.1 DETERMINE the in-service recombiner inlet
temperature as indicated on RECOMBINER
3A(3B), INLET TEMP 3-TI-66-75A(B),
Panel 3-9-53.
Standard:
DETERMINED RECOMBINER 3A INLET TEMP 3-TI-66-75A,Panel 3-9-53.
SAT-UNSAT -N/A- COMMENTS:
Cue: 3-TI-66-75A,Recombiner3A Inlet Temperature, indicates 393
degrees Fahrenheit.
JPM NO. A2.1
REV. NO.0
PAGE 9 OF 17
...........................................................
. _-
Performance Step: Critical X Not Critical-
6.1.1.2 DETERMINE the in-service recombiner operating
(center) temperature as indicated on
RECOMBINER 3A/3B TEMPERATURE recorder,
3-TRS-66-77,Panel 3-9-53.
Standard :
DETERMINED the in-service recombiner operating (center)
temperature as indicated on RECOMBINER 3A TEMPERATURE recorder,
3-TRS-66-77,Panel 3-9-53.
SAT-UNSAT -N/A- COMMENTS :
Cue: 3-TR-66-77,Point 2, Recombiner 3A center temperature, is
reading 618 degrees Fahrenheit.
.
...........................................................
Performance Step: Critical X Not Critical
6.1.1.3 CALCULATE the temperature difference (AT)
between the values obtained in Steps 1 and 2.
Standard :
Calculated Recombiner 3A inlet/center At and determined At is 225
degrees Fahrenheit
SAT UNSAT-N/A- COMMENTS :
JPM NO. A2.1
REV. NO. 0
PAGE 10 OF 17
...........................................................
. ~.
~. -~ ~
.
.. ~
.
... . .
JPM NO. A2.1
REV. NO.0
PAGE 11 OF 17
Performance Step: Critical X Not Critical-
6.1.1.4 DETERMINE the reactor thermal power (MWt)
from process computer.
Standard:
DETERMINED reactor thermal power from the process computer.
SAT-UNSAT N/A- COMMENTS :
Cue: Reactor thermal power is 3430 MWt.
1
JPM NO. A2.1
REV. NO. 0
PAGE 12 OF 17
...........................................................
Performance Step: Critical X Not Critical-
6.1.1.5 Using Illustration 1 plot the corresponding
point of reactor power in MWT and AT.
Standard:
Using illustration 1, DETERMINED At corresponding to 3430 MWT is
240.1 degrees Fahrenheit.
SAT-UNSAT-N/A- COMMENTS :
...........................................................
Performance Step: Critical X Not Critical-
6.1.1.6 VERIFY point on illustration 1 is above or
equal to the appropriate line (HWC in service or HWC
out of service)
Standard :
Determines from Illustration 1 that calculated At vs MWt plots
BELOW the HWC Out of Service (solid) line.
Stops task performance and informs SRO that acceptance criteria is
NOT met. (Not Critical)
SAT-UNSAT N/A- COMMENTS :
JPM NO. A2.1,.
REV. NO.0
PAGE 13 OF 17
...........................................................
Performance Step: Critical- Not Critical X
6.1.2 IF the in-service recombiner performance is below the
minimum allowable, THEN
PERFORM the following:
6.1.2.1 CHECK Off-Gas Preheater, Recombiner and SJAEs
are in operation in accordance with Section 5.0.
Standard :
PROCEEDS to check Off-Gas Preheater, Recombiner and SJAEs are in
operation in accordance with Section 5 . 0 .
SAT-UNSAT-N/A- COMMENTS:
Cue: (When performers obtains 01-66, Section 5.0) Another
operator will verify proper operation of Off-Gas components. I
Performance Step: Critical- Not Critical X -
6.1.2.2 Closely MONITOR the OFFGAS HYDROGEN ANALYZER
recorder, 2-H2R-66-96on Panel 2-9-53.
Standard:
MONITORS the OFFGAS HYDROGEN ANALYZER recorder, 2-H2R-66-96 on
Panel 2-9-53.
SAT-UNSAT-N/A- COMMENTS :
Cue: (When checked) Both Off-Gas Hydrogen Analyzers are
JPM NO. A2.1
REV. NO. 0
PAGE 14 OF 17
JPM NO. A2.1
REV. NO.0
PAGE 15 OF 17
Performance Step: Critical- Not Critical X
6.1.2.3 IF both hydrogen analyzers are inoperable,
THEN
REQUEST Chem Lab to obtain a grab sample to
determine hydrogen concentration. REFER TO TRM
3.3.9.
Standard :
Determined Step 6.1.2.3 is N/A.
SAT-UNSAT-N/A- COMMENTS :
...........................................................
Performance Step: Critical Not Critical-X
6.1.2.4 IF a malfunction of the SJAE is suspected,
THEN
REFER TO Section 8.4 and TRANSFER SJAEs.
Cue: Another operator has determined that che operating SJAE has
mr m a l f j r n r t i n n n A
Standard:
Does NOT transfer SJAEs.
SAT-UNSAT-N/A- COMMENTS :
JPM NO. A2. l,,
REV. NO.0
PAGE 16 OF 17
...........................................................
Performance Step: Critical Not Critical X
6.1.3 IF off-gas hydrogen rises above 1%, THEN
REFER TO 2-AOI-66-1.
Cue: Off-Gas hydrogen concentration is 0.24%.
Standard:
I
Determines off-gas hydrogen has NOT risen above 1%.
SAT UNSAT N/A- COMMENTS :
...........................................................
Performance Step: Critical Not Critical X
6.1.4 Only IF analysis or hydrogen analyzers show hydrogen
concentration is below 4%, THEN
PLACE standby recombiner in operation. REFER TO
Section 8.3.
Standard:
Proceeds to PLACE standby recombiner in operation. REFER TO
Section 8.3.
SAT UNSAT-N/A- COMMENTS :
service. This ends the JPM.
JPM NO. A2.1
REV. NO.0
PAGE 17 OF 17
............................................................
Performance Step: Critical Not Critical-X
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 W A COMMENTS :
..............................................................
Performance Step: Critical- Not Critical- X
PERFORMER demonstrated the use of 3-WAY COMMUNICATION during this
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 N/A COMMENTS :
...........................................................
END OF TASK
STOP TIME
~ .- . . .. .. . ~ ~~ ~ . ~ ~~. ... ~
ES-301Control Room Systems Form ES-301-2 (R8, SlBnd Facility Walk-Through Test Outline
Facility: BFN Date of Examination: 12/16/02
Exam Level (circle one): RO Operating Test No.:
B.l Control Room Systems
System / JPM Title Type Code* Safety
Function
I I
a. STANDBY GAS TREATMENT JPM 114. STANDBY GAS
TREATMENT TRAIN 'C' DECAY HEAT REMOVAL I DJI 9
b. OFF GAS JPM 116F PLACING STANDBY STEAM JET N,A 9
AIR EJECTOR IN OPERATION
c. RHR JPM 201 LOSS OF SHUTDOWN COOLING I NS,A JI 4
d. ELECTRICAL JPM 84 ENERGIZE A UNIT % 4 KV SD D J 6
BOARD VIA A UNIT 3 DIESEL GENERATOR
e. RClC JPM 133F 2-EOI-APPIIB ALTERNATE D,A J 2
PRESSURE CONTROL, RClC IN THE TEST MODE
f. MAIN STEAM JPM 35 2-EOI-APPENDIX 8B 3
REOPENING THE MSlVs FOLLOWING A GROUP 1
ISOLATION
g. CONTROL ROD DRIVE JPM 148F LOSS OF A CRD N,A J 1
PUMP
8.2 Facility Walk-Through
a. EOVRPS JPM 340 3-EO1 APPENDIX 16F AND 16G
BYPASSING RHR INJECTION VALVE TIMERS
b. SSI JPM 205 PERFORM 2/3-SSI-16, ATTACHMENT 2,
I M4 5
a
SECTION 2
J
C. EOVSLC JPM 26 2-EO1 APPENDIX 78, ALTERNATE D,R 2
RPV INJECTION SYSTEM LINEUP - SLC TANK
- Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol
room. fS)imulator. (Uow-Power. (RKA
ES-301 Control Room Systems Form ES-301-2 (R8, S I )
and Facility Walk-Through Test Outline
.-.J
Facility: Date of Examination: 12/16/02
Exam Level (circle one):SRO(U) Operating Test No.:
B.l Control Room Systems
System / JPM Title Type Code* Safety
Function
a.
RHR JPM-201 LOSS OF SHUTDOWN COOLING
b.
PRIMARY CONTAINMENT VENTING JPM-51F 2-EO1
APPENDIX 12
C.
D / 6
ELECTRICAL JPM 96 PERFORM CONTROL ROOM
TRANSFER OF 4KV SHUTDOWN BOARD 'A' POWER
SUPPLIES
d.
e.
f.
8.2 Facility Walk-Through
a. 7
EOVHPCI JPM 331 2-EO1APPENDIX 16J BYPASS HPCl
INTERLOCKS
b. J
EOVALTERNATE INJECTION SOURCE JPM-24 2-EO1
APPENDIX 7A ALTERNATE INJECTION SYSTEM - D,R 2
CONDENSATE TRANSFER TO CORE SPRAY
C.
I I
- Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol
room, (S)imulator, (L)ow-Power, (R)CA
JPM NUMBER: 133F
TITLE: 2-EO1 APPENDIX 11B - ALTERNATE PRESSURE
CONTROL - RCIC TEST MODE (FROM STANDBY, TRIP
THROTTLE VALVE TRIPPED)
TASK NUMBER: U-000-EM-54
SAFETY FUNCTION: 2
TYPE CODE: D,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. 133F
REV. NO. 7
PAGE 2 OF 19
BROWNS FERRY NUCLEAR PLANT
i
REVISION LOG
Revision Effective Pages Description
Number Date Affected of Revision
2 12/8/94 1,2,3,4 REVISE TO NEW FORMAT
3 10/22/95 ALL FORMATTING, TYPOS, UNIT 2
SPECIFIC ITEMS
4 9/5/96 ALL DELETED PLANT INST.,
ADDED CRIT. STEP ON TOUCH
STAAR, CHANGED ASOS TO
us.
5 10/29/96 4, 13 CHANGED CRIT. STEP ON
TOUCH STAAR TO NON-
CRITICAL.
6 10/28/98 ALL GENERAL REVISION
7 9/16/02 ALL GENERAL REVISION
JPM NO. 133F
REV. NO. 7
PAGE 3 OF 19,
BROWNS FERRY NUCLEAR PLANT
OPERATOR :
JPM NUMBER: 133F
TASK NUMBER: U-000-EM-54
TASK TITLE: 2-EO1 APPENDIX 11B - ALTERNATE PRESSURE CONTROL -
RCIC TEST MODE (FROM STANDBY, TRIP THROTTLE VALVE
TRIPPED)
K/A NUMBER: 295025EA1.05 K/A RATING: ROU SRO:
3.7
..................................................................
TASK STANDARD: PERFORM OPERATIONS NECESSARY TO PLACE RCIC IN TEST
MODE FROM STANDBY FOR ALTERNATE RPV PRESSURE
CONTROL AS DIRECTED BY 2-EO1 APPENDIX 11B.
LOCATION OF PERFORMANCE: SIMULATOR PLANT - CONTROL ROOM -
REFERENCES/PROCEDURES NEEDED: 2-EOI-APPENDIX 11B, REV 4
VALIDATION TIME: CONTROL ROOM: 6:OO LOCAL :
MAX. TIME ALLOWED: (Completed for Time Critical JPMs only)
PERFORMANCE TIME: CONTROL ROOM - LOCAL -
-
COMMENTS :
JPM NO. 133F
REV. NO. 7
PAGE 4 OF 1 9
Additional comment sheets attached? YES - NO -
~~
RESULTS : SATISFACTORY UNSATISFACTORY
SIGNATURE: DATE :
I EXAMINER
- __
BROWNS FERRY NUCLEAR PLANT
.. ~~ .~. . . ~ ~~~~~~~~ ~~ .
.................................................................
~~~ ~~~ ~~ ~~~ ~~~~ ~
IN-SIMULATOR: I will explain the initial conditions and state the
task
on to be performed. I will provide
when^ directe.~
o~the~r~act~i~ons initiating
by you.^^^ cues and reports
When.~you~com~p~lete~~the~:ta~sk
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 Thats Correct. (OR Thats 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 an operator. The Unit 2 reactor has
scrammed and the turbine bypass valves are not responding properly
for pressure control. EOI-1 has been entered and followed to
RC/P-11.
INITIATING CUES: The UNIT SUPERVISOR directs you to place RCIC
in Alternate RPV Pressure Control as directed by 2-EO1 Appendix
11B.
JPM NO. 133F
REV. NO. I
PAGE 6 OF 19
~~~ ~~ ~ . ~ ~
START TI&-- '~~~
.................................................................
. .. ..__, ~
Performance Step: Critical- Not Critical2
WHEN REQUESTED BY EXAMINER identify/obtain copy of required
EO1 Appendix.
Standard :
IDENTIFIED OR OBTAINED copy of 2-EO1 Appendix 11B.
Satisfactory- Unsatisfactory-
Comments :
JPM NO. 133F
REV. NO. 7
PAGE 7 OF 19
.................................................................
CAUTION
0 Operating RCIC turbine below 2100 rpm may result in
unstable system operation and damage.
0 Elevated Suppression Chamber pressure may trip the RCIC
turbine on high exhaust pressure.
0 Operating RCIC Turbine with suction temperatures above
14OOF may result in equipment damage.
..................................................................
............................................................
Performance Step: Critical- Not Critical2
1. IF ..... Emergency RPV Depressurization is required,
THEN ...EXECUTE EO1 Appendix 16A and 16B as necessary to
bypass RCIC Low RPV Pressure and Test Mode Isolation
Interlocks.
Standard:
DID NOT request Appendix 16A and 16B.
CUE: EMERGENCY DEPRESSURIZATION NOT REQUIRED.
Satisfactory- Unsatisfactory-
Comments :
JPM NO. 133F
REV. NO. 7
PAGE 8 OF 19
.............................................................
Performance Step: Critical Not Critical-X
2. IF.."._.....
Suppression Pool level CANNOT be maintained below 7 in.,
THEN....EXECUTE EO1 Appendix 16E concurrently with this
procedure to bypass HPCI High Suppression Pool Level Suction
Transfer Interlock
Standard :
Did -not REQUEST EO1 Appendix 16E.
SAT UNSAT N/A- COMMENTS :
..............................................................
JPM NO. 133F
REV. NO. I
PAGE 9 OF 19
...............................................................
Performance Step: Critical- Not Critical2
3. IF .....RCIC Turbine is operating and 9 required for
RPV level control,
THEN ...ALIGN RCIC in test mode as follows:
a. OPEN 2-FCV-71-38,RCIC PUMP CST TEST VLV.
b. VERIFY OPEN 2-FCV-73-36,HPCIIRCIC TEST RETURN
VLV .
C. CLOSE 2-FCV-71-39,RCIC PUMP INJECTION VALVE.
d. CONTINUE in this procedure at Step 5.
Standard :
VERIFIES RCIC Turbine not operating by any of the following:
Speed 0 on 2-SI-71-42A
Flow 0 on 2-FIC-71-36A
2-FCV-71-8Closed
2-FCV-71-39Closed
Discharge pressure 0 on 2-PI-71-35A
Satisfactory- Unsatisfactory-
JPM NO. 133F
REV. NO. 7
PAGE 10 OF 19
4. IF .....RCIC is in standby readiness,
THEN ...START RCIC as follows:
...............................................................
Perormance Step: Critical- Not Critical2
a. VERIFY CLOSED 2-FCV-71-39,RCIC PUMP INJECTION
VALVE.
Standard :
VERIFIED illuminated GREEN valve position indicating lamp
above 2-HS-71-39A.
Satisfactory- Unsatisfactory-
Comments :
................................................................
Performance Step: Critical-& Not Critical-
b. VERIFY RESET and OPEN 2-FCV-71-9,RCIC TURB TRIP &
THROTTLE VALVE RESET.
Standard :
PLACED 2-HS-71-9Bin the CLOSE position and VERIFIED
illuminated GREEN valve position indicating lamp. PLACED 2 -
HS-71-9 in the OPEN position and VERIFIED illuminated RED
valve position indicating lamp. VERIFIED illuminated RED
condition indicating lamp 2-ZI-71-9.
Satisfactory- Unsatisfactory-
Comments :
JPM NO. 133F
REV. NO. 7
PAGE 11 OF 19
. ., . . ..
JPM NO. 133F
REV. NO. 7
PAGE 12 OF 19
...............................................................
Performance Step: CriticalX Not Critical-
c. VERIFY OPEN the following valves:
0 2-FCV-71-38,RCIC PUMP TEST RETURN VLV.
0 2-FCV-71-25,RCIC LUBE OIL CLR COOLING WTR
VLV .
0 2-FCV-71-34,RCIC PUMP MINIMUM FLOW VLV.
0 2-FCV-73-36,HPCI/RCIC TEST RETURN VLV.
Standard :
HELD 2-HS-71-38Ain the OPEN position until VERIFIED
illuminated RED valve position indicating lamps above
associated control switch.
PLACED 2-HS-71-25A,34Aand 36A in the OPEN position and
VERIFIED illuminated RED valve position indicating lamps
above associated control switches.
Satisfactory- Unsatisfactory-
Comments:
...............................................................
Performance Step: Critical- Not Critical2
d. PLACE 2-HS-71-31A,RCIC VACUUM PUMP, handswitch in
START.
Standard :
PLACED 2-HS-71-31Ain the START position and VERIFIED
illuminated RED motor breaker position indicating lamp
JPM NO. 133F
REV. NO. 7
PAGE 13 OF 19
Satisfactory- Unsatisfactory-
Comments :
JPM NO. 133F
REV. NO. 7
PAGE 14 OF 19
...............................................................
Performance Step: CriticalX Not Critical-
e. OPEN 2-FCV-71-8,RCIC TURBINE STEAM SUPPLY VLV, to
start RCIC Turbine.
Standard :
PLACED 2-HS-71-8 in the OPEN position and VERIFIED
illuminated RED valve position indicating lamp above
associated control switch.
Satisfactory- Unsatisfactory-
Comments :
...............................................................
Performance Step: Critical- Not Critical2
f. VERIFY RCIC Turbine speed accelerates to above
2100 rpm.
Standard :
VERIFIED speed greater than 2100 rpm on 2-SI-71-42A.
Satisfactory- Unsatisfactory-
Comments :
JPM NO. 133F
REV. NO. 7
PAGE 15 OF 19
...............................................................
Performance SteD: Critical- Not Critical2
5. VERIFY proper RCIC minimum flow valve operation as
follows :
a. IF . . . . .RCIC flow is above 120 gpm,
THEN ...VERIFY CLOSED 2-FCV-71-34,RCIC PUMP
MINIMUM FLOW VALVE.
b. IF .....BOTH of the following exist:
e RCIC Initiation signal is pJ present,
AND
0 RCIC flow is below 60 gpn,
THEN ...VERIFY OPEN 2-FCV-71-34,RCIC PUMP
MINIMUM FLOW VALVE.
Standard:
VERIFIED illuminated GREEN valve position indicating lamp
above 2-HS-71-34.
Satisfactory- Unsatisfactory-
Comments:
...............................................................
Performance SteD: Critical- Not Critical2
6. THROTTLE 2-FCV-71-38,RCIC PUMP CST TEST VLV, to
control RCIC pump discharge pressure at or below 1100
psig .
Standard:
MANIPULATED 2-HS-71-38to maintain pressure on 2-PI-71-35Aat
JPM 1\TO. 133F
REV. NO. 7
PAGE 16 OF 19
or below 1100 psig .
Satisfactory- Unsatisfactory-
JPM NO. 133F
REV. NO. 7
PAGE 17 OF 19
Performance Stels: Critical- Not Critical2
6. ADJUST 2-FIC-71-36A,RCIC SYSTEM FLOW/CONTROL,
controller to control RPV pressure.
Standard :
ADJUSTED 2-FIC-71-36Aas required to maintain RPV pressure
and :
Maintain RCIC flow 120-600 gpm on 2-FIC-71-36A.
Maintain RCIC discharge pressure 5 1100 psig on
2-PI-71-35A.
Maintain RCIC Speed > 2100 rpm on 2-SI-71-42A.
Satisfactory- Unsatisfactory-
JPM NO. . 133F
REV. NO. 7
PAGE 18 OF 19
...............................................................
Performance Stew: Critical- Not Critical2
I. IF ....RCIC injection to the RPV becomes necessary,
THEN... ALIGN RCIC to RPV as follows:
a. OPEN 2-FCV-71-39,RCIC Pump Injection valve.
b. CLOSE 2-FCV-71-38,RCIC Pump Test return valve.
c. GO TO EO1 Appendix 5C.
CUE: SRO DOES NOT DIRECT RCIC INJECTION.
~
Standard :
Does not INJECT with RCIC
Satisfactory- Unsatisfactory-
Comments :
............................................................
Performance Stew: 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- N/A- COMMENTS:
JPM NO. 133F
REV. NO. 7
PAGE 19 OF 19
................................................................
Performance Step: Critical Not Critical X
PERFORMER demonstrated the use of 3-WAY COMMUNICATION during
this 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 N/A COMMENTS
-
END OF TASK
STOP TIME:
JPM NO. 331
R E T -NO. -5
PAGE 1 OF 14
BROWNS FERRY NUCLEAR PLANT
JPM NUMBER: 331
TITLE : 3-EO1 APPENDIX 16J - BYPASSING HPCI HIGH RPV
WATER LEVEL TRIP INTERLOCKS
TASK NUMBER: U-000-EM-43
SAFETY FUNCTION: 4
TYPE CODE: D
SUBMITTED BY: DATE :
VALIDATED BY: DATE :
APPROVED : DATE :
TRAINING
PLANT CONCURRENCE: DATE :
OPERATIONS
JPM NO. 331
REV. NO. 5
PAGE 2 OF 14
- Examination JPMs Require Operations Training Manager or Designee Approval and
Plant Concurrence
JPM NO. 331
REV. NO. 5
PAGE 3 OF 14
L
BROWNS FERRY NUCLEAR PLANT
z
REVISION LOG
Revision Effective Pages Description
Number Date Affected of Revision
0 8/7/95 ALL NEW JPM
1 9/6/96 ALL REFORMAT JPM, ADDED MGT
EXPECTATIONS AND CRIT.
STEPS ON TOUCH STAAR AND
SAFETY, AND DELETED
UNDERSTAND AND SIM. INST.
2 10/24/96 4, 9 CHANGED CRIT STEP ON
TOUCH STAAR AND SAFETY
TO NON-CRIT.
3 11/7/96 7 DELETED "WITH BANANA JACK
PLUG" IN STEP 4.
4 10/28/98 ALL GENERAL REVISION
5 9/9/02 3 REMOVE SS#, CHANGE PROCED
REV
JPM NO. 331
REV. NO. 5
PAGE 4 OF 14
BROWNS FERRY NUCLEAR PLANT
OPERATOR : I
JPM NUMBER: 331
TASK NUMBER: U-000-EM-43
TASK TITLE: BYPASS HPCI HIGH RPV WATER LEVEL TRIP INTERLOCKS
IN ACCORDANCE WITH 3-EO1 APPENDIX 16J
KIA NUMBER: 295008AA1.04 K/A RATING: R O X SRO: 3.5
..................................................................
TASK STANDARD: SIMULATE PERFORMING ACTIONS REQUIRED TO DEFEAT
HPCI HIGH RPV WATER LEVEL INTERLOCKS AS DIRECTED
BY 3-EO1 APPENDIX 16J.
LOCATION OF PERFORMANCE: SIMULATOR - PLANT X CONTROL ROOM -
REFERENCES/PROCEDURES NEEDED: ~ - E O IAPPENDIX 165, REV 1 I
VALIDATION TIME: CONTROL ROOM: 7:OO LOCAL: 4:OO
MAX. TIME ALLOWED: (Completed for Time Critical JPMs only)
PERFORMANCE TIME : CONTROL ROOM LOCAL __
-
COMMENTS :
JPM NO. 331
REV. NO. 5
PAGE 5 OF 14
Additional comment sheets attached? YES - NO -
RESULTS : SATISFACTORY UNSATISFACTORY _ _ .
SIGNATURE : DATE :
EXAMINER
BROWNS FERRY NUCLEAR PLANT
.................................................................
.
IN-PLANT: I will explain the initial conditions and state the
task to be performed. All steps shall be simulated. I will provide
initiating cues and indicate any steps to be discussed. 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 an operator. Unit 3 reactor has
scrammed due to a leak in the drywell. Reactor water level cannot
be determined. EOI-1 has been followed to C4-13. The HPCI system,
using auxiliary steam, is to be used as an injection source as
directed by 3-EOI-Appendix 75.
INITIATING CUES: The UNIT SUPERVISOR directs you to bypass the
HPCI high RPV water level shutdown interlocks as directed by 3-EO1
Appendix 16J.
CAUTION: ALL JPM STEPS PERFORMED IN THE PLANT WILL BE SIMULOATED.
NOT OPERATE ANY PLANT EQUIPMENT.
JPM NO. 331
REV. NO. 5
PAGE 7 OF 14
START TIME
.................................................................
Performance Step: Critical- Not Critical2
WHEN REQUESTED BY EXAMINER identify/obtain copy of required
EO1 Appendix.
Standard :
IDENTIFIED OR OBTAINED Copy Of 3-EO1 Appendix 16J.
SATUNSATN/A- COMMENTS :
~~
EXAMINER'S NOTE: STEPS ARE TO BE PERFORMED IN SEQUENCE.
.............................................................
Performance Step : Critical- N o t Critical2
1. REFER TO Attachment 1 and OBTAIN necessary tools and
equipment.
Standard:
REFERRED TO Attachment 1 and SIMULATED OBTAINING 3-EOI-
Appendix 16J package from Unit 3 Auxiliary Instrument Room
EO1 equipment storage box containing:
1. Screwdriver
2. Insulated Grip Needle-Nose Pliers
3. Roll of Electrical Tape
SAT- UNSAT-N/A- COMMENTS :
JPM NO. 331
REV. NO. 5
PAGE 8 OF 14
JPM NO. 331
REV. NO. 5
PAGE 9 OF 14
CUE: [WHEN SIMULATED] YOU HAVE A COPY OF APPENDIX 165. A
SCREWDRIVER, INSULATED NEEDLE-NOSE PLIERS AND A ROLL OF
ELECTRICAL TAPE.
.............................................................
Performance SteD : Critical- Not Critical2
2. LOCATE terminal strip AA inside Panel 3-9-39, Bay 1,
Rear.
Standard :
INDICATED location of terminal strip AA inside rear of Panel
3-9-39.
SAT- TJNSAT-N/A- COMMENTS :
__
............................................................
Performance Step : CriticalX Not Critical-
3. LOCATE black wire attached to terminal AA-65.
Standard :
INDICATED BLACK wire attached to terminal AA-65.
SAT- UNSAT-N/A- COMMENTS :
JPM NO. 331
REV. NO. 5
PAGE 10 OF 14
.............................................................
Performance Step : CriticalX Not Critical-
4. REMOVE terminal screw at terminal AA-65 WHILE ,holding
the black wire with needle-nose pliers.
Standard :
SIMULATED REMOVING terminal screw at terminal AA-65 while
holding black wire with needle-nose pliers.
SAT-UNSAT-N/A- COMMENTS :
CUE: [WHEN SIMULATED] YOU HAVE REMOVED THE TERMINAL SCREW
AT TERMINAL AA-65 AND ARE HOLDING THE BLACK WIRE WITH THE
NEEDLE-NOSE PLIERS.
............................................................
Performance Stev : CriticalX Not Critical-
5. REMOVE and TAPE lugged end of black wire lifted from
terminal AA-65.
Standard :
SIMULATED REMOVING and TAPING lugged end of black wire.
SAT- UNSAT-N/A- COMMENTS :
JPM NO. 331
REV. NO. 5
PAGE 11 OF 14
CUE: [WHEN SIMULATED] YOU HAVE REMOVED AND TAPED THE LUGGED
END OF THE BLACK WIRE LIFTED FROM TERMINAL AA-65.
JPM NO. 331
REV. NO. 5
PAGE 12 OF 14
.............................................................
~
Performance SteD : Critical- Not Critical2
6. NOTIFY Unit Operator that HPCI High RPV Water Level
Trip is bypassed.
Standard:
SIMULATED NOTIFYING Unit 3 Operator that the HPCI high RPV
water level trip is bypassed.
SAT- TJNSAT N/A COMMENTS :
CUE: [WHEN SIMULATED] UNIT 3 OPERATOR REPEATS "HPCI HIGH
RPV WATER LEVEL TRIP IS BYPASSED IN ACCORDANCE WITH
APPENDIX 165".
JPM NO. 331
REV. NO. 5
PAGE 13 OF 14
..................................................................
Performance Stels: Critical- Not Critical
PERFORMER demonstrated the use of 3-WAY COMMUNICATION during
this JPM.
Standard:
PERFORMER utilized 3-WAY COMMUNICATION i.e., used phonetic
alphabet, received/solicited and acknowledged repeat-backs.
SAT- UNSAT- N/A- COMMENTS :
...........................................................
Performance Stew: Critical- Not Critical&
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 WA- COMMENTS :
JPM NO. 331
REV. NO. 5
PAGE 14 OF 14
................................................................
Performance SteD: Critical- Not Critical
PERFORMER complied with all safety rules and regulations.
Standard:
PERFORMER complied with all safety rules and regulations
(hardhat, safety glasses, sideshields, and hearing protection
was worn AS REQUIRED.) (INSTRUCTOR determines if N/A due to
plant conditions)
ELECTRICAL SAFETY was a l s o adhered to: Exposed conductive
articles such as rings, metal wristwatches, bracelets, and
metal necklaces shall not be worn by employees within
reachinq distance of exposed energized electrical conductors of
50 volts or greater.
SAT- UNSAT- N/A- COMMENTS :
-
END OF TASK
STOP TIME:
JPM NO. 340
REV. NO. 0
PAGE 1 OF 17
BROWNS FERRY NUCLEAR PLANT
JPM NUMBER: 340
TITLE: 3-EO1 APPENDIX 16F & 16G - BYPASSING RHR
SYSTEM I & I1 INJECTION VALVE TIMERS
TASK NUMBER: U-000-EM-71
SAFETY FUNCTION: .5
TYPE CODE: M*
TO REQUEST BOTH APPENDICES BE PERFORMED WHEN CONTAINMENT
COOLING/SPRAY IS PERFORMED IT HAS BEEN CONVERTED TO A SINGLE JPM
TO PERFORM THE REQUIRED TASK.
SUBMITTED BY: DATE :
VALIDATED BY: DATE :
APPROVED : DATE :
TRAINING
PLANT CONCURRENCE: DATE :
JPM NO. 340
REV. NO. 0
PAGE 2 OF 1 7
OPERATIONS
- Examination JPMs Require Operations Training Manager or Designee Approval and
- Plant Concurrence
JPM NO. 340
REV. NO. 0
PAGE 3 OF 17
BROWNS FERRY NUCLEAR PLANT
J O B PERFORMANCE MEASURE
REVISION LOG
Revision Effective Pages Description
Number Date Affected of Revision
0 9/9/02 ALL NEW JPM
JPM NO. 340
REV. NO. 0
PAGE 4 OF 17
BROWNS FERRY NUCLEAR PLANT
OPERATOR :
JPM NUMBER: 340
TASK NUMBER: U-000-EM-71
TASK TITLE: BYPASS RHR SYSTEM I & I1 INJECTION VALVE TIMERS IN
ACCORDANCE WITH 3-EO1 APPENDIX 16F & 16G
K/A NUMBER: 203000A2.13 K/A RATING: RO 3.2 SRO: 3.3
..................................................................
TASK STANDARD: PERFORM OPERATIONS NECESSARY TO BYPASS RHR SYSTEM
I & I1 INJECTION VALVE TIMERS AS DIRECTED BY 3-EO1
APPENDIX 16F & 16G
LOCATION OF PERFORMANCE: SIMULATOR - PLANT CONTROL ROOM -
APPENDIX i 6 ~ ,REV 1, ~ - E O I
REFERENCES/PROCEDURES NEEDED: ~ - E O I
APPENDIX 16G, REV 1
VALIDATION TIME: CONTROL ROOM: 1O:OO LOCAL: 6:OO
MAX. TIME ALLOWED: (Completed for Time Critical JPMs only)
PERFORMANCE TIME: CONTROL ROOM _ _ LOCAL _ _
COMMENTS :
Additional comment sheets attached? YES _ _ NO __
JPM NO. 340
REV. NO. 0
PAGE 5 OF 17
RESULTS : SATISFACTORY UNSATISFACTORY
SIGNATURE: DATE :
EXAMINER
BROWNS FERRY NUCLEAR PLANT
IN-PLANT: I will explain the initial conditions and state the
task to be performed. All steps shall be simulated. I will
provide initiating cues and indicate any steps to be discussed.
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 Thats
Correct. (OR Thats 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 an Operator. Unit 3 reactor has
scrammed and a small coolant leak exists in the drywell. EOI-2 has
been followed to PC/P-10. Appendix 17B, RHR System Operation -
Drywell Sprays, is in progress.
INITIATING CUES: The Unit 3 Unit Supervisor directs you to bypass
RHR System I and System I 1 injection valve timers as directed by
3-EO1 Appendices 16F and 16G.
CAUTION: ALL JPM STEPS PERFORMED IN THE PLANT WILL BE SIMULATED;
QQ NOT OPERATE ANY PLANT EQUIPMENT.
JPM NO. 340
REV. NO. 1
PAGE 7 OF 17
START TIME
EXAMINERS NOTE: THE TWO EXCEPTIONS TO THE EXACT STEP SEQUENCE
ARE 1) EITHER APPENDIX MAY BE PERFORMED FIRST AND 2) THE
CANDIDATE MAY RETRIEVE FINGER BOOTS FOR BOTH APPENDICES AT THE
SAME TIME.
.................................................................
Performance Stew: Critical- Not C r i t i c a l X
WHEN REQUESTED BY EXAMINER identify/obtain copy of required
EO1 Appendix.
standard :
IDENTIFIED OR OBTAINED copy of 3-EO1 APPENDIX 16F and 16G.
SAT- UNSAT-N/A- COMMENTS :
............................................................
Performance Stew: Critical- Not C r i t i c a l X
1. REFER TO Attachment 1 and OBTAIN one relay contact finger
boot and small fuse pullers.
Standard:
LOCATED EO1 equipment storage box in Unit 3 Aux Instrument
Room and SIMULATED obtaining boot and fuse puller.
SAT- UNSAT-N/A- COMMENTS:
JPM NO. 340
REV. NO. 1
PAGE 8 OF 17
CUE: [WHEN SIMULATED] YOU HAVE A BOOT AND FUSE PULLER.
i
.............................................................
Performance SteD : Critical- Not C r i t i c a l X
2. LOCATE Relay 10A-K35A on Panel 3-9-32, Front.
Standard :
LOCATED Relay 10A-K35A on Panel 3-9-32.
SAT- UNSAT-N/A- COMMENTS :
............................................................
Performance SteD: CriticalX Not Critical-
3. REFER TO Attachment 2 and INSTALL boot on Relay 10A-K35A,
contact 5-6, using small fuse pullers to pull back contact
finger .
Standard :
LOCATED relay 10A-K35A and SIMULATED pulling back contact
finger 5-6 and installing boot.
SAT- UNSAT-N / A- COMMENTS :
JPM NO. 340
REV. NO. 1
PAGE 9 OF 17
CUE: [WHEN SIMULATED] THE BOOT IS INSTALLED BETWEEN
CONTACTS 5 AND 6 ON RELAY 10A-IC35A.
I
JPM NO. 340
REV. NO. 1
PAGE 10 OF 17
............................................................
Performance Step: Critical- Not Critical& ~
4. NOTIFY Unit Operator that System I RHR Injection Valve timer
is bypassed.
Standard :
SIMULATED NOTIFYING Unit 3 Operator that System I RHR
Injection Valve timer is bypassed.
SAT- LJNSAT-N/A- COMMENTS :
CUE: [WHEN SIMULATED] UNIT 3 OPERATOR ACKNOWLEDGES RHR
SYSTEM I INJECTION VALVE TIMER BYPASSED.
JPM NO. 340
REV. NO. 1
PAGE 11 OF 17
Performance Step: Critical- Not Critical2
1. REFER TO Attachment 1 and OBTAIN one relay contact finger
boot and small fuse pullers.
Standard:
LOCATED EO1 equipment storage box in Unit 3 Aux Instrument
Room and SIMULATED obtaining boot.
Satisfactory- Unsatisfactory-
Comments :
CUE: [WHEN SIMULATED] YOU HAVE A BOOT AND FUSE PULLER.
JPM NO. 340
REV. NO. 1
PAGE 12 OF 17
.............................................................
Performance Step : CriticalX Not Critical-
2. LOCATE Relay 10A-K35B on Panel 3-9-33, Front.
Standard :
LOCATED Relay 10A-K35B on Panel 3-9-33.
SAT- UNSAT N/A COMMENTS :
............................................................
Performance Step: CriticalX Not Critical-
3. REFER TO Attachment 2 and INSTALL boot on Relay 10A-K35B,
contact 5-6, using small fuse puller to pull back contact
finger.
Standard:
LOCATED relay 10A-K35B and SIMULATED pulling back contact
finger 5-6 and installing boot.
Satisfactory- Unsatisfactory-
Comments :
CUE: [WHEN SIMULATED] THE BOOT IS INSTALLED BETWEEN
CONTACTS 5 AND 6 ON RELAY 10A-K35B.
JPM NO. 340
REV. NO. 1
PAGE 13 OF 17
JPM NO. 340
REV. NO. 1
PAGE 14 OF 17
............................................................
Performance Step: Critical- Not Critical2
4. NOTIFY Unit Operator that System I1 RHR Injection Valve timer
is bypassed.
Standard :
SIMULATED NOTIFYING Unit Operator that System I1 RHR
Injection Valve timer is bypassed.
Satisfactory- Unsatisfactory-
Comments :
CUE: [WHEN SIMULATED] UNIT 3 OPERATOR ACKNOWLEDGES RHR
SYSTEM I1 INJECTION VALVE TIMER BYPASSED. THAT WILL BE ALL
FOR NOW.
JPM NO. 340
REV. NO. 1
PAGE 15 OF 17
............................................................
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 f o r additional training on TOUCH STAAR to maintain
plant standards).
SAT- UNSAT N/A COMMENTS :
-
JPM NO. 340
REV. NO. 1
PAGE 16 OF 17
................................................................
Performance Step: Critical- Not Critical
PERFORMER complied with all safety rules and regulations.
Standard:
PERFORMER complied with all safety rules and regulations
(hardhat, safety glasses, sideshields, and hearing protection
was worn AS REQUIRED.) (INSTRUCTOR determines if N/A due to
plant conditions)
ELECTRICAL SAFETY was also adhered to: Exposed conductive
articles such as rings, metal wristwatches, bracelets, and
metal necklaces shall not be worn by employees within
reachinq distance of exposed energized electrical
conductors of 50 volts or greater.
SAT- UNSAT- N/A- COMMENTS :
..................................................................
Performance Stew: Critical- Not Critical
PERFORMER demonstrated the use of 3-WAY COMMUNICATION during
this JPM.
Standard :
PERFORMER utilized 3-WAY COMMUNICATION i.e., used phonetic
alphabet, received/solicited and acknowledged repeat-backs.
SAT- UNSAT N/A COMMENTS :
-
END OF TASK
JPM NO. 340
REV. NO. 1
PAGE 17 OF 17
STOP TIME:
JPM NO. 205
REV. NO. 0
PAGE 1 OF 11
BROWNS FERRY NUCLEAR PLANT
JPM NUMBER: 205
TITLE: PERFORM 2/3-SSI-16,ATTACHMENT 2, SECTION 2
TASK NUMBER: U-000-SS-08
SAFETY FUNCTION: 8
TYPE CODE: N,R
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. 205
REV. NO. 0
PAGE 2 OF 11
BROWNS FERRY NUCLEAR PLANT
J03 PERFORMANCE MEASURE
REVISION LOG
Revision Effective Pages Description
Number Date Affected of Revision
0 9/29/02 ALL NEW
JPM NO. 205
REV. NO. 0
PAGE 3 OF 11
BROWNS FERRY NUCLEAR PLANT
OPERATOR :
JPM NUMBER: 205
TASK NUMBER: U-000-SS-08
TASK TITLE: PERFORM 2/3-SS1-16, ATTACHMENT 2, SECTION 2
KIA NUMBER: 600000 AA2.05 RATING: RO 2.9 SRO: 3.0
..................................................................
TASK STANDARD: CORRECTLY SIMULATE ACTIONS REQUIRED TO START UNIT
2 ELECTRIC BOARD ROOM AIR HANDLING UNIT AND BLOCK OPEN DOORS ON IC
ELEVATION TO REDUCE HEAT LOAD IN THE EVENT OF A FIRE IN THE
CONTROL BUILDING [EXACT STEP SEQUENCE NOT REQUIRED]
LOCATION OF PERFORMANCE: SIMULATOR PLANT X CONTROL ROOM -
REFERENCES/PROCEDURES NEEDED: 2/3-ss1-16, REVISION 0007
VALIDATION TIME: CONTROL ROOM: 18:OO LOCAL: 17:OO
MAX. TIME ALLOWED: (Completed for Time Critical JPMs only)
PERFORMANCE TIME: CONTROL ROOM LOCAL -
-
COMMENTS :
Additional comment sheets attached? YES NO
RESULTS : SATISFACTORY UNSATISFACTORY
JPM NO. 205
REV. NO. 0
PAGE 4 OF 11
EXAMINER SIGNATURE: DATE :
EXAMINER
L
BROWNS FERRY NUCLEAR PLAN?!
JOB FERFORMANCE MEASURE
...................................................................
IN-PLANT: I will explain the initial conditions and state the
task to be performed. All steps shall be simulated. I will provide
initiating cues and indicate any steps to be discussed. 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 Thats Correctgt.
(OR Thats 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 an extra operator. A fire has broken
out in the control bay on Unit 1 elevation 5 9 3 . 2/3-SSI-16 has
been activated.
INITIATING CUES: The Unit 2 Unit Supervisor has directed you
to perform Attachment 2, Section 2.0 of 2/3-SSI-16.
CAUTION: ALL JPM STEPS PERFORMGD IN THE PLANT WILL BE SIMULATED;
-
DO NOT OPERATE ANY PLANT EQUIPMENT.
JPM NO. 205
REV. NO. 0
PAGE 6 OF 11
EXAMINER'S NOTE: EXACT STEP SEQUENCE NOT REQUIRED.
2.OStart Unit 2 Electric Board Room AHU 2A and Open Doors
on 1C Elevation to reduce heat load
(60 Min)
2.1 Notification has been received from the Unit 2
Unit Supervisor to perform this section.
.............................................................
Performance Step: Critical x Not Critical
2.2 PERFORM the following to START ELEC BD RM AHU 2A:
2.2.1 PROCEED to 2-LPNL-925-8613AND PLACE
2-XSW-031-2320,APPX R E L E C T RM AHU 2A
NORMAL/EMERGENCY switch in EMER.
Standard :
At 2-LPNL-925-8613 (C 4KV SD BD ROOM, EAST WALL) SIMULATES
PLACING 2-XSW-031-2320,APPX R ELEC ED RM AHU 2A NORMAL/EMERGENCY
switch in EMER.
SAT-UNSAT-N/A- COMMENTS :
CUE: [WHEN SIMULATED] 2-XSW-031-2320 IS IN EMERGENCY.
..............................................................
JPM NO. 205
REV. NO. 0
PAGE 7 OF 11
.............................................................
Per'formance Step: Critical X Not Critical
2.2.2 PROCEED to 2-LPNL-925-0539 PERFORM
the following:
2.2.2.1 PLACE 2-XS-031-2320,ELEC BD RM AHU 2A
LOCAL/REMOTE XFER SWITCH in LOCAL.
Standard:
At 2-LPNL-925-0539,(C 4KV SD BD ROOM, EAST WALL) SIMULATED
PLACING 2-XS-031-2320in LOCAL.
SAT ~ UNSAT-N/A- COMMENTS :
UE: [WHEN SIMULATED] 2-XS-031-2320IS IN LOCAL.
..............................................................
I
.............................................................
Performance Step: Critical X
_ .
Not Critical
2.2.2.2 PLACE 2-HS-031-2320A,ELEC ED RM AHU 2A
LOCAL CONTROL SWITCH, in START and
RETURN to AUTO.
Standard:
SIMULATED PLACING 2-HS-031-2320Ain START and RETURNING to AUTO.
SAT -UNSAT N/A- COMMENTS :
.
CUE: [WHEN SIMULATED] 2-HS-031-2320AIS IN START.
[WHEN SIMULATED] 2-HS-031-2320AIS IN AUTO.
JPM NO. 205
REV. NO. 0
PAGE 8 OF 11
.............................................................
Performance Step: Critical X
~ Not Critical
2.3 PERFORM the following to ALIGN doors on
Control Bay EL. 1C:
2.3.1 BLOCK OPEN door to Battery Board Room
No. 3 , door 476A.
Standard:
SIMULATED BLOCKING OPEN door 476A with wooden wedge obtained from
black operations equipment cabinet.
SAT-UNSAT-N/A- COMMENTS :
Cue: [WHEN SIMULATED] DOOR 47614 IS BLOCKED OPEN.
..............................................................
I
.............................................................
Performance Step: Critical__X Not Critical
2.3.2 BLOCK OPEN door to Battery Board Room
No. 2, door 466A.
Standard:
SIMULATED BLOCKING OPEN door 466A with wooden wedge obtained from
black operations equipment cabinet.
SAT UNSAT N/A- COMMENTS:
CUE: [WHEN SIMULATED] DOOR 4 6 6 A IS BLOCKED OPEN.
..............................................................
I
JPM NO. 205
REV. NO. 0
PAGE 9 OF 11
- ****** . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
Performance Step: Critical X Not Critical
~. ?' .~ .
2.3.3 BLOCK OPEN door to Battery Board Room
No. 1, door 462.
Standard:
SMULATED BLOCKING OPEN door 462 with wooden wedge obtained from
black operations equipment cabinet.
SAT-UNSAT N/A- COMMENTS:
CUE: [WHEN SIMULATED] DOOR 462 IS BLOCKED OPEN.
..............................................................
.............................................................
Performance Step: Critical- Not Critical X
2.4 NOTIFY Unit 2 Unit Supervisor of completion of
this section.
Standard :
Using hand-held radio or phone (2269) SIMULATED NOTIFYING UNIT 2
US 2/3-SSI-16 ATTACHMENT 2, SECTION 2 COMPLETED.
SAT-UNSAT N/A- COMMENTS:
CUE: [WHEN SIMULATED] UNDERSTAND 2/3-881-16 ATTACHMENT 2, I
SECTION 2 IS COMPLETE.
I
..............................................................
JPM NO. 205
REV. NO. 0
PAGE 10 OF 11
Performance Step: Critical__ Not Critical- X
2.5 PROCEED to Battery Board Room No. 1 in
preparation of performing Section 3.0.
Standard :
PROCEEDED to Battery Board Room NO. 1 .
SAT-UNSAT-N/A- COMMENTS:
TERMINATING CUE: [WHEN WAITING AT BATTERY BOARD ROOM NO.ll
THAT WILL BE ALL FOR NOW.
..............................................................
STOP TIME
............................................................
Performance Step: CriticalI_ 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- COMMENTS:
JPM NO. 205
REV. NO. 0
PAGE 11 OF 11
~~ ~ ~ ~~ ~ ~ ~~.. .~
..................................................................
Performance Step: Critical- Not Critical X
. ~.
PERFORMER demonstrated the use of 3 -WAY COMMUNICATION during
this JPM.
Standard :
PERFORMER utilized 3-WAY COMMUNICATION i.e., used phonetic
alphabet, received/solicited and acknowledged repeat-backs.
SAT- UNSAT- COMMENTS :
...............................................................
Performance Step: Critical__ Not Critical X
PERFORMER complied with all safety rules and regulations.
Standard :
PERFORMER complied with all safety rules and regulations
(hardhat, safety glasses, sideshields, and hearing protection
was worn AS REQUIRED.) (INSTRUCTOR determines if N/A due to
plant conditions)
ELECTRICAL SAFETY was also adhered to: Exposed conductive
articles such as rings, metal wristwatches, bracelets, and
metal necklaces shall not be worn by employees within
reachinq distance of exposed energized electrical conductors
of 50 volts or greater.
SAT UNSAT__ N/A- COMMENTS :
END OF TASK
JPM NO. 24
REV. NO. 6
PAGE 1 OF 9
BROWNS FERRY NUCLEAR PLANT
JPM NUMBER: 24
TITLE: EO1 APPENDIX 7A - ALTERNATE INJECTION SYSTEMS
- CONDENSATE TRANSFER TO CS SYSTEM
TASK NUMBER: U-000-EM-36
SAFETY FUNCTION: 2
TYPE CODE: D
SUBMITTED BY: DATE :
VALIDATED BY: DATE :
APPROVED : DATE :
TRAINING
P N T CONCURRENCE: DATE :
OPERATIONS
JPM NO. 24
REV. NO. 6
PAGE 2 OF 9
- Examination JPMs Require Operations Training Manager or Designee Approval and
Plant Concurrence
JPM NO. 24
REV. NO. 6
PAGE 3 OF 9
.
BROWNS FERRY NUCLEAR PLANT
>
REVISION LOG
Revision Effective Pages Description
Number Date Affected of Revision
2 10/18/94 ALL GENERAL REVISION
3 11/8/95 ALL ADDRESS NORMALLY LOCKED
VALVES, ADDED NOTE ON
PAGE 5
4 10/27/96 4, 8 ADDED NON-CRITICAL STEPS
ON TOUCH STAAR AND
SAFETY, CHANGED ASOS TO
us.
5 9/13/99 ALL PROCEDURE REVISION,
FORMAT DOCUMENT, ADDED 3 -
WAY COMM.
6 8/12/02 3.4 Removed SS# line, removed
statements
JPM NO. 24
REV. NO. 6
PAGE 4 OF 9
BROWNS FERRY NUCLEAR PLANT
OPERATOR : I
JPM NUMBER: 24
TASK NUMBER: U-000-EM-36
TASK TITLE: LINE UP ALTERNATE RPV INJECTION SYSTEM -
CONDENSATE TRANSFER PUMPS TO RHR AND CS IN
ACCORDANCE WITH EO1 APPENDIX 7A
K/A NUMBER: 209001G13 K/A RATING: RO3.7 SRO: 3. 7
..................................................................
TASK STANDARD: LOCATE AND SIMULATE MANUAL OPERATION OF CORE SPRAY
SYSTEM VALVES REQUIRED BY 2-EO1 APPENDIX ?A
LOCATION OF PERFORMANCE: SIMULATOR - PLANT - CONTROL ROOM -
REFERENCES/PROCEDURES NEEDED: 2-EO1 APPENDIX ?A, REV 8
VALIDATION TIME: CONTROL ROOM: 16:OO LOCAL: 12:oo
MAX. TIME ALLOWED: (Completed for Time Critical JPMs only)
PERFORMANCE TIME: CONTROL ROOM LOCAL -
-
COMMENTS :
JPM NO. 24
REV. NO. 6
PAGE 5 OF 9
Additional comment sheets attached? YES __ NO __
RESULTS : SATISFACTORY UNSATISFACTORY -
~
SIGNATURE: DATE :
EXAMINER
BROWNS FERRY NUCLEAR PLANT
. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ..-
.......................
IN-CLAl??: I will explain the initial- conditions and state the
task to be performed. All steps shall be simulated. I will provide
initiating cues and indicate any steps to be discussed. 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 Thats Correct.
(OR Thats 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.
.................................................................. I
INITIAL CONDITIONS: You are an Operator. The Unit 2 reactor has
scrammed and several failures have made it difficult to maintain
reactor water level. The Unit 1 Operator has CLOSED the condensate
head tank outlet valve, 0-LCV-2-177,and STARTED both condensate
transfer pumps.
INITIATING CUES : The Unit 2 Operator has directed you to
perform Steps 2.a.l), CS System I, and 2.b.l), CS System 11, of 2-
EO1 Appendix 7A, ALTERNATE RPV INJECTION LINEUP - CONDENSATE
JPM NO. 24
REV. NO. 6
PAGE 7 OF 9
START TIME
.................................................................
Performance SteD: Critical- Not Critical&
WHEN REQUESTED BY EXAMINER identify/obtain copy of required
procedure.
Standard :
IDENTIFIED OR OBTAINED Copy of 2-EO1 APPENDIX 7A.
SAT-UNSAT-N/A- COMMENTS:
NOTE : All operations performed at Control Room Panel 2-9-3
unless otherwise stated.
1. NOTIFY Unit 1 Operator to perform the following:
a. CLOSE 0-LCV-2-177,CNDS HEAD TANK OUTLET, (Panel
1-9-20).
b. START BOTH Condensate Transfer pumps
(Panel 1-9-20).
EXAMINERS NOTE: STEP 1 IS GIVEN IN THE INITIAL CONDITIONS.
EXACT STEP SEQUENCE IS NOT REQUIRED FROM THIS POINT ON.
JPM NO. 24
REV. NO. 6
PAGE 8 OF 9
..............................................................
Performance Stew: CriticalX Not Critical-
2. INJECT to RHR and/or CS as required using ANY of the
following:
a. CS System I
1) DISPATCH personnel to unlock and open 2-SHV-
075-0582A, CS SYSTEM I CNDS FLUSH AND FILL
SHUTOFF VALVE, (RB, Platform, West, above El
593 ft, R10-p).
Standard :
LOCATED and SIMULATED TURNING 2-SHV-075-0582Ahandwheel in
the COUNTERCLOCKWISE direction.
CUE: THE HANDWHEEL IS TURNING, THE STEM IS MOVING OUTWARD.
PAUSE
THE HANDWHEEL IS SNUG, THE STEM HAS STOPPED MOVING.
J A
SAT- UNSAT-N/A- COMMENTS:
2) OPEN the following valves:
b 2-FCV-75-23,CORE SPRAY SYS I OUTBD
INJECT VALVE
b 2-FCV-75-25,CORE SPRAY SYS I INBD
INJECT VALVE.
JPM NO. 24
REV. NO. 6
PAGE 9 OF 9
..........................................................
Performance Stew: CriticalX Not Critical-
b. CS System I1
1) DISPATCH personnel to unlock and open 2-SHV-
075-0582B, CS SYSTEM I1 CNDS FLUSH & FILL
SHUTOFF VALVE (RB, Platform above El 593 ft
at top of stairs, R12-P)
Standard:
LOCATED and SIMULATED TURNING 2-75-582B handwheel in
the COUNTERCLOCKWISE direction.
CUE: THE HANDWHEEL IS TURNING, THE STEM IS MOVING OUTWARD.
PAUSE
THE HANDWHEEL IS SNUG, THE STEM HAS STOPPED MOVING.
SAT- UNSAT-N/A- COMMENTS :
2) OPEN the following valves:
0 2-FCV-75-51,CORE SPRAY SYS I1 OUTBD
INJECT VALVE
0 2-FCV-75-53,CORE SPRAY SYS I1 INBD
INJECT VALVE.
JPM NO. 24
REV. NO. 6
PAGE 10 OF 9
................................................................
Performance Stev: Critical- Not Critical
PERFORMER complied with all safety rules and regulations.
Standard :
PERFORMER complied with all safety rules and regulations
(hardhat, safety glasses, sideshields, and hearing protection
was worn AS REQUIRED.) (INSTRUCTOR determines if N/A due to
plant conditions)
ELECTRICAL SAFETY was also adhered to: Exposed conductive
articles such as rings, metal wristwatches, bracelets, and
metal necklaces shall not be worn by employees within
reachinq distance of exposed energized electrical conductors of
50 volts or greater.
SAT- UNSAT- N/A- COMMENTS :
-
............................................................
Performance Stev: Critical- Not Critical&
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 f o r additional training on TOUCH STAAR to maintain plant
standards).
SAT- UNSAT N/A COMMENTS :
JPM NO. 24
REV. NO. 6
PAGE 11 OF 9
JPM NO. 24
REV. NO. 6
PAGE 12 OF 9
- k** . . . . . . . . . . . . . . . . . . . . . . . . . . . .
Performance SteD: Critical- Not Critical
PERFORMER demonstrated the use of 3-WAY COMMUNICATION during
this JPM.
Standard :
PERFORMER utilized 3-WAY COMMUNICATION, i.e. used phonetic
alphabet, received/solicited and acknowledged repeat-backs.
SAT- UNSAT N/A COMMENTS :
END OF TASK
STOP TIME
JPM NO. 26
REV. NO. 7
PAGE 1 OF 22
BROWNS FERTY NUCLEAR PLANT
JPM NUMBER: 26
TITLE : 2-EO1 APP 7B - ALTERNATE RPV INJECTION SYSTEM
LINEUP - SLC
TASK NUMBER: U-000-EM-37
SAFETY FUNCTION: 2
TYPE CODE: D
SUBMITTED BY: DATE :
VALIDATED BY: DATE :
APPROVED : DATE :
TRAINING
PLANT CONCURRENCE: DATE :
0PERATIONS
JPM NO. 26
REV. NO. 7
PAGE 2 OF 22
- Examination JPMs Require Operations Training Manager or Designee Approval and
Plant Concurrence
JPM NO. 26
REV. NO. 7
PAGE 3 OF 22
BROWNS FERRY NUCLEAR PLANT
REVISION LOG
Revision Effective Pages Description
Number Date Affected of Revision
3 10/18/94 ALL GENERAL REVISION
4 11/16/95 8,15,ALL CHANGED CUE TO REFLECT
"UNLOCKING", ADDED
CUE.CHANGED PAGE NUMBERS
5 11/8/96 4, 17 ADDED NON-CRITICAL STEPS
ON TOUCH STAAR AND
SAFETY, CHANGED ASOS TO
us.
6 9/13/99 ALL PROCEDURE REVISION,
FORMAT DOCUMENT, ADDED 3-
WAY COMM.
7 10/25/02 ALL GENERAL REVISION
JPM NO. 26
REV. NO. 7
PAGE 4 OF 2 2
BROWNS FERRY NUCLEAR PLANT
OPERATOR :
JPM NUMBER: 26
TASK NUMBER: U-000-EM-37
TASK TITLE: LINE UP ALTERNATE RPV INJECTION SYSTEM - SLC
SYSTEM IN ACCORDANCE WITH EO1 APPENDIX 7B
K/A NUMBER: 295031EA1.08 K/A RATING: R O X SRO: 3.9
..................................................................
TASK STANDARD: SIMULATE PERFORMING LOCAL COMPONENT MANIPULATIONS
REQUIRED TO ALIGN THE STANDBY LIQUID CONTROL (SLC)
SYSTEM TEST TANK FOR INJECTION INTO THE RPV
LOCATION OF PERFORMANCE: SIMULATOR - PLANT CONTROL ROOM -
REFERENCES/PROCEDURES NEEDED: 2-EO1 APPENDIX 7B, REV 6
VALIDATION TIME: CONTROL ROOM: LOCAL : 9:oo
MAX. TIME ALLOWED: (Completed for Time Critical JPMs only)
PERFORMANCE TIME: CONTROL ROOM _ _ LOCAL -
-
COMMENTS :
Additional comment sheets attached? YES _ _ NO -
RESULTS : SATISFACTORY UNSATISFACTORY _ _
SIGNATURE: DATE:
JPM NO. 26
REV. NO. 7
PAGE 5 OF 22
EXAMINER
.. . . . .. I .. . ... . . . BROWNS FERRY NUCLEAR PLANT -
.................................................................... 5
. ~~~. . .. .-. ~ ~~
.-
I N - P e : I will explain the initial conditions and state the
task to be performed. All steps shall be simulated. I will provide
initiating cues and indicate any steps to be discussed. 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 an Operator. The Unit 2 reactor has
scrammed and due to several malfunctions RPV water level cannot be
maintained > +2 inches. SLC is NOT required or reactivity
control.
INITIATING CUES: The Unit 2 Operator directs you to align the
SLC Test Tank as an RPV injection source as directed by 2-EO1
Appendix ?B, ALTERNATE RPV INJECTION SYSTEM LINEUP - SLC SYSTEM
beginning at Step 3.0.
JPM NO. 2 6
REV. NO. 7
PAGE 7 OF 22
START TIME
EXAMINERIS NOTE: EXACT STEP SEQUENCE IS REQUIRED.
1
.................................................................
Performance Step: Critical- Not CriticalX
WHEN REQUESTED BY EXAMINER identify/obtain copy of required
procedure.
Standard:
IDENTIFIED OR OBTAINED COPY Of 2-EO1 APPENDIX 7B.
SAT-UNSAT-N/A- COMMENTS :
1. IF ..... EO1 Appendix 3A is required to be performed,
THEN ...EXIT this procedure.
N0TE:SLC Test Tank is preferred source because unborated
water may be supplied to the RPV through this
injection path.
2. IF .... RPV injection is needed immediately ONLy to
prevent or mitigate fuel damage,
THEN ...CONTINUE at Step 10 to inject SLC Boron Tank to
RPV .
N0TE:Steps 3 through 8 inject demineralized water to the RPV
using the SLC Test Tank.
3. DISPATCH personnel to Unit 2 SLC pump area to line up
SLC Test Tank as follows (RB NE, El 639 ft):
JPM NO. 26
REV. NO. 7
PAGE 8 OF 22
.................................................................
Performance Step: Critical- Not C r i t i c a l X
a. REFER TO Attachment 1 and OBTAIN a 25-ft section
of 3/4-in. rubber hose from EO1 Equipment Storage
Cabinet (RB, El 621 ft, elevator area).
Standard :
REFERRED to Attachment 1, LOCATED required EO1 equipment
storage box and SIMULATED OBTAINING 25 foot section of hose
from box.
CUE: YOU HAVE A 25 FOOT SECTION OF 3/4 INCH RUBBER HOSE
WITH CHICAGO FILLTING.
SAT- UNSAT-N/A- COMMENTS :
JPM NO. 26
REV. NO. 7
PAGE 9 OF 22
..............................................................
Performance Step: CriticalX Not Critical-
b. CONNECT hose to 2-2-1254, DEMIN WTR SERVICE CONN.
(wall near SLC pumps), and ROUTE into top of SLC
Test Tank.
Standard :
LOCATED AND SIMULATED CONNECTING 25 foot hose to 2-2-1254 and
SIMULATED ROUTING hose to top of SLC test tank.
CUE: THE HOSE IS CONNECTED TO 2-2-1254 AND ROUTED INTO THE
SAT- UNSAT-N/A- COMMENTS :
.................................................................
Performance Step: Critical- Not CriticalX
C. VERIFY OPEN 2-2-1255, SLC DEMIN WTR SPLY VALVE
(on wall next to SLC pumps).
Standard :
LOCATED 2-2-1255 and VERIFIED OPEN by SIMULATING moving lever
counterclockwise to the open position.
CUE: THE OPERATING LEVER FOR 2-2-1255 IS POSITIONED
PARALLEL WITH ITS ASSOCIATED DOWNSTREAM PIPING.
JPM NO. 26
REV. NO. 7
PAGE 1 0 O F 2 2
JPM NO. 26
REV. NO. 7
PAGE 11 OF 22
...............................................................
Performance Step: CriticalX Not Critical-
d. UNLOCK and OPEN the following valves:
1) 2-SHV-063-0502, SLC SYSTEM SUCTION DEMIN
WATER SHUTOFF VALVE.
Standard:
LOCATED 2-SHV- 63-0502 and SIMULATED UNLOCKING and ROTATING
handwheel in the COUNTERCLOCKWISE direction.
CUE: THE HANDWHEEL IS TURNING, THE STEM IS MOVING OUTWARD.
PAUSE
THE HANDWHEEL IS SNUG, THE STEM HAS STOPPED MOVING.
SAT-TJNSAT-N/A- COMMENTS :
JPM NO. 26
REV. NO. 7
PAGE 12 OF 22
..............................................................
Performance Step: CriticalX Not Critical-
2) 2-SHV-063-0509,2A SLC PUMP SUCTION DEMIN
WATER SHUTOFF VALVE.
Standard:
LOCATED 2-SHV-063-0509and SIMULATED UNLOCKING and ROTATING
handwheel in the COUNTERCLOCKWISE direction.
CUE: THE HANDWHEEL IS TURNING, THE STEM IS MOVING OUTWARD.
PAUSE
THE HANDWHEEL IS SNUG, THE STEM HAS STOPPED MOVING.
SAT-UNSAT-N/A- COMMENTS :
..............................................................
Performance Step: CriticalX Not Critical-
3) 2-SHV-063-0511,2B SLC PUMP SUCTION DEMIN
WATER SHUTOFF VALVE.
Standard:
LOCATED 2-SHV-063-0511and SIMULATED UNLOCKING and ROTATING
handwheel in the COUNTERCLOCKWISE direction.
CUE: THE HANDWHEEL IS TURNING, THE STEM IS MOVING OUTWARD.
PAUSE
THE HANDWHEEL IS SNUG, THE STEM HAS STOPPED MOVING.
JPM NO. 2 6
REV. NO. 7
PAGE 13 OF 2 2
SAT-UNSATN/A- COMMENTS :
JPM NO. 26
REV. NO. 7
PAGE 14 OF 22
NOTE : A ladder may be required to perform the following step.
REFER TO Tools and Equipment, Attachment 1.
............................................................
Performance SteD: CriticalX Not Critical-
e. OPEN 2-SHV-063-0532, SLC TEST TANK DEMIN WATER
SHUTOFF VALVE.
Standard :
LOCATED and SIMULATED TURNING 2-SHV-063-0532 in the
COUNTERCLOCKWISE direction.
CUE: THE HANDWHEEL IS TURNING, THE STEM IS MOVING OUTWARD.
PAUSE
THE HANDWHEEL IS SNUG, THE STEM HAS STOPPED MOVING.
SAT-UNSAT-N/A- COMMENTS :
JPM NO. 2 6
REV. NO. 7
PAGE 15 O F 22
..............................................................
Performance Step: Critical& Not Critical-
f. OPEN 2 - S H V - 0 6 3 - 0 0 1 4 , SLC TEST TANK SHUTOFF VALVE.
Standard :
LOCATED and SIMULATED TURNING 2 - S H V - 0 6 3 - 0 0 1 4 in t h e
COUNTERCLOCKWISE direction.
CUE: THE " H E E L I S TURNING, THE STEM I S MOVING OUTWARD.
PAUSE
THE HANDWHEEL I S SNUG, THE STEM HAS STOPPED MOVING.
SAT- UNSAT-N/A- COMMENTS :
JPM NO. 26 ,
REV. NO. 7
PAGE 16 OF 22
................................................................
Performance Step: C r i t i c a l X Not Critical-
g. UNLOCK and CLOSE 2-SHV-063-0500, SLC STORAGE TANK
OUTLET SHUTOFF VALVE.
Standard :
SIMULATED UNLOCKING AND TURNING 2-SHV-063-0500 in the
CLOCKWISE direction.
CUE: THE HANDWHEEL IS TURNING, THE STEM IS MOVING INWARD.
PAUSE
THE HANDWHEEL IS SNUG, THE STEM HAS STOPPED MOVINQ.
SAT-UNSAT-N/A- COMMENTS :
JPM NO. 26
REV. NO. 7
PAGE 17 OF 2 2
..............................................................
Performance Step: Critical- Not Critical2
h. NOTIFY Unit Operator that SLC pumps have been
aligned to the test tank.
i. REMAIN in area for additional steps as directed by
the Unit Operator.
Standard:
NOTIFIED Unit Operator SLC pumps aligned to test tank.
SAT- UNSAT-N/A- COMMENTS:
CUE: UNIT OPERATOR ACKNOWLEDGES SLC PUMPS ALIGNED TO TEST
TANK. [PAUSE] SLC PUMP B IS NOW RUNNING. [PAUSE] THE
UNIT OPERATOR DIRECTS YOU TO PERFORM STEP 7 OF
APPENDIX 7B.
I
JPM NO. 26
REV. NO. 7
PAGE 18 OF 22
4. UNLOCK and PLACE 2-HS-63-6A,SLC PUMP 2A/2B, control
switch in START-A or START-B (Panel 9-5).
- 5. CHECK demineralized water is injecting to the RPV by
observing the following:
Selected pump running, as indicated by red light
illuminated above pump control switch.
Squib valves fire, as indicated by SQUIB VALVE A
and B CONTINUITY blue lights extinguished,
SLC SQUIB VALVE CONTINUITY LOST Annunciator in
alarm (2-XA-55-55B,Window 20).
2-PI-63-7A,SLC PUMP DISCH PRESS, indicates above
RPV pressure.
e System flow, as indicated by 2-IL-63-11.SLC FLOW,
red light illuminated,
SLC INJECTION FLOW TO REACTOR Annunciator in alarm
on Panel 9-5 (2-XA-55-5B,Window 14).
6. IF ...... Proper system operation CANNOT be verified,
THEN .... RETURN to Step 4 and START other SLC pump.
7. NOTIFY personnel in SLC area to perform the following:
NOTE : Opening 2-2-1254, DEMIN WTR SERVICE CONN,
provides enough make-up to operate SLC pump
continuously.
JPM NO. 26
REV. NO. 7
PAGE 1 9 O F 22
...............................................................
Performance Step: C r i t i c a l X Not Critical-
~ ~
.~
.. ~~
. ~~ ~~
..
a. - OPEN 2-2-1254,,DEMIN WTR SERVICE CONN.
Standard :
LOCATED AND SIMULATED TURNING 2-2-1254 lever in the
counterclockwise direction.
SAT- UNSAT-N/A- COMMENTS :
CUE:[WHEN SIMULATED] THE HANDLE IS PARALLEL WITH THE PIPING.
JPM NO. 26
REV. NO. 7
PAGE 2 0 OF 22
...............................................................
L
CUE: THE TEST TANK IS NEARLY FULL AND THE LEVEL IS STILL
RISING.
Performance Step: Critical- Not C r i t i c a l 2
b. THROTTLE 2-2-1254, DEMIN WTR SERVICE CONN, as
necessary to maintain Test Tank level.
Standard :
SIMULATED MANIPULATING 2-2-1254 lever in the CLOSE
(CLOCKWISE) direction as required to maintain constant test
tank level.
SAT- UNSAT-N/A- COMMENTS :
TERMINATING CUE: THE TEST TANK IS NEARLY FULL AND THE LEVEL
IS STEADY. THAT WILL BE ALL FOR NOW.
8. MONITOR and CONTROL SLC System as necessary to
maintain injection
JPM NO. 26
REV. NO. 7
PAGE 21 OF 22
................................................................
Performance Stels: Critical- Not Critical 2
-
PERFORMER complied with all safety rules and regulations.
Standard:
PERFORMER complied with all safety rules and regulations
(hardhat, safety glasses, sideshields, and hearing protection
was worn AS REQUIRED.) (INSTRUCTOR determines if N/A due to
plant conditions)
ELECTRICAL SAFETY was also adhered to: Exposed conductive
articles such as rings, metal wristwatches, bracelets, and
metal necklaces shall not be worn by employees within
reachinq distance of exposed energized electrical conductors of
50 volts or greater.
SAT- UNSAT- N/A- COMMENTS :
............................................................
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 N/A COMMENTS :
JPM NO. 26
REV. NO. 7'
PAGE 22 OF 22
..................................................................
Performance Step: Critical- Not Critical
PERFORMER demonstrated the use of 3-WAY COMMUNICATION during
this JPM.
Standard :
PERFORMER utilized 3-WAY COMMUNICATION, i.e. used phonetic
alphabet, received/solicited and acknowledged repeat-backs.
SAT- UNSAT N/A COMMENTS :
END OF TASK
STOP TIME
JPM NO. 116F
REV. NO. 1
PAGE 1 OF 23
BROWNS FERRY NUCLEAR PLANT
JPM NUMBER: 116F
TITLE: PLACING STANDBY STEAM JET AIR EJECTOR IN
OPERATION
TASK NUMBER: U-066-NO-07
SAFETY FUNCTION: 9
02 TYPE CODE: N,A
SUBMITTED BY: DATE :
VALIDATED BY: DATE :
APPROVED : DATE :
TRAINING
PLANT CONCURRENCE: DATE :
OPERATIONS
JPM NO. 116F
REV. NO. 1
PAGE 2 OF 23
- Examination JPMs Require Operations Training Manager or Designee Approval and
Plant Concurrence
JPM NO. 116F
REV. NO. 1
PAGE 3 OF 23
BROWNS FERRY NUCLEAR PLANT
1
REVISION LOG
Revision Effective Pages Description
Number Date Affected of Revision
0 10/10/99 ALL NEW JPM
1 08/15/02 ALL DELETED SS#, PAGE 4
DELETED PLANT WORK
EXPECTATIONS, TOUCH
STAAR, AND 3-WAY COMM.
GENERAL REVISION OF
PROCEDURE.
JPM NO. 116F
REV. NO. 1
PAGE 4 OF 23
BROWNS FERRY NUCLEAR PLANT
OPERATOR :
JPM NUMBER: 116F
TASK NUMBER: U-066-NO-07
TASK TITLE: PLACE THE STANDBY SJAE IN OPERATION
K/A NUMBER: 271000A4.09 K/A RATING: RO 3 . 3 SRO: 3.2
..................................................................
TASK STANDAFD: PERFORM CONTROL ROOM MANIPULATIONS REQUIRED TO
PLACE THE STANDBY STEAM JET AIR EJECTOR IN
OPERATION DURING POWER OPERATION
LOCATION OF PERFORMANCE: SIMULATOR X PLANT - CONTROL ROOM -
REFERENCES/PROCEDURES NEEDED: 2-01-66, REV 7 7
VALIDATION TIME: CONTROL ROOM: 14:OO LOCAL:
MAX. TIME ALLOWED: (Completed for Time Critical JPMs only)
PERFORMANCE TIME: CONTROL ROOM _ _ LOCAL -
-
COMMENTS :
JPM NO. 116F
REV. NO. 1
PAGE 5 OF 23
Additional comment sheets attached? YES NO I_
RESULTS : SATISFACTORY UNSATISFACTORY _ _
SIGNATURE: DATE :
EXAMINER
BROWNS FERRY NUCLEAR P W
J O B PERFORMANCE MEASURE
.................................................................
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 an Operator. Unit 2 is at 1 0 0 %
power. 2A steam jet air ejector is in service in accordance with
Section 5 . 9 of 2 - 0 1 - 6 6 . 2A steam jet air ejector is to be removed
from service for maintenance and 2B steam jet air ejector is to be
placed into operation. HWC is shutdown per 2 - 0 1 - 4 . The outside
Unit Supervisor and an AUO are standing by at Panel 2 5 - 1 0 5 in Unit
2 turbine building with a hand-held radio.
INITIATING CUES : (NAME) , remove 2A
steam jet air ejector from service and place 2B steam jet air
ejector into operation.
JPM NO. 116F
REV. NO. 1
PAGE 7 OF 23
START TIME
EXAMINER'S NOTE: EXACT STEP SEQUENCE IS REQUIRED.
1
...................................................................
Performance SteD: Critical- Not CriticalX
WHEN REQUESTED BY EXAMINER identify/obtain copy of required
procedure.
Standard:
IDENTIFIED OR OBTAINED COPY Of 2-01-66.
SAT-UNSAT-N/A- COMMENTS :
8.4 Placina Standby SJAE in Operation
NOTES :
1. Auto swapping of SJAE is administratively prohibited per GE-
SIL-150. See Precautions and Limitations 3.17.
3 The HWC system is shutdown prior to intentional swapping of
SJAEs to prevent receipt of the automatic trip of the HWC
system that will occur when both SJAE DISCHARGE VALVES 2-FCV-
66-14 and 18 are closed.
.............................................................
Performance SteD : Critical- Not C r i t i c a l X
8.4.1 REVIEW all Precaution and Limitations in Section
3.0.
Standard:
REVIEWED all Precautions and Limitations in Section 3.0.
JPM NO. 116F
REV. NO. 1
PAGE 8 OF 2 3
SAT- UNSAT-N/A- COMMENTS :
JPM NO. 116F
REV. NO. 1
PAGE 9 OF 23
...............................................................
Performance SteD : Critical- Not CriticalL
8.4.2 VERIFY the following initial conditions have been
met:
8.4.2.1 Off-Gas System hydrogen concentration is
less than 4% (by volume).
Standard :
VERIFIED hydrogen concentration less than 4% by any of the
following methods:
B No high off gas hydrogen alarms on annunciator panel 2-
XA-55-53
B Offgas Hydrogen Analyzer recorder 2-H2R-66-96,Panel 2-
9-53, indicates less than 4% hydrogen (A & B analyzers)
/ H2 Analyzer Conc Hi, 2-IL-66-96Aand 2-IL-66-96B,Panel
2-9-53, status indicating amber lamps EXTINGUISHED
SAT-UNSAT-N/A- COMMENTS :
.............................................................
Performance SteD : Critical- Not CriticalX
8.4.2.2 IF HWC System is in service, THEN
SHUTDOWN HWC System. REFER TO 2-01-4.
(otherwise N/A)
Standard :
None
SAT-UNSAT-N/A_li_ COMMENTS: Given in initial
JPM NO. 116F
REV. NO. 1
PAGE 10 OF 23
conditions.
JPM NO. 116F
REV. NO. 1
PAGE 11 OF 23
.............................................................
Performance Step : Critical- Not CriticalX
8.4.2.3 SJAEs are in operation. REFER TO Section
5.9.
Standard :
None
SAT- UNSAT- N / A A COMMENTS: Given in initial
conditions.
.............................................................
Performance Step : Critical- Not CriticalX
8.4.3 At Panel 2-9-6,VERIFY OPEN the following valves:
8.4.3.1 SJAE 2B(2A) CNDS INLET VALVE, using 2-
HS-2-31A(36A).
8.4.3.2 SJAE 2B(2A) CNDS OUTLET VALVE, using 2-
HS-2-35A(41A).
Standard :
At Panel 2-9-6,VERIFIED illuminated RED valve position
indicating lamps above 2-HS-2-31Aand 2-HS-2-35A.
SAT- UNSAT N/A COMMENTS :
JPM NO. 116F
REV. NO. 1
PAGE 12 OF 23
.............................................................
Performance Stev : Critical- Not CriticalX
8.4.4 At Panel 25-105, VERIFY CONDENSATE FROM SJAE B(A)
pressure, 2-PI-2-34(40), is greater than 60 psig.
Standard :
CALLED Turbine Building AUO/Outside US to determine reading
from 2-PI-2-34,CONDENSATE FROM SJAE B, Panel 25-105.
SAT- LJNSAT-N/A- COMMENTS :
-
CUE: [WHEN CALLED] 2-PI-2-34,CONDENSATE FROM SJAE B,
INDICATES 88 PSIG.
JPM NO. 116F
REV. NO. 1
PAGE 13 OF 23
.............................................................
Performance Steo : Critical- Not C r i t i c a l X
8.4.5 At Panel 25-105, VERIFY manual/hand loader output
pressure and pressure controller setpoints are
adjusted as follows:
8.4.5.1 Setpoint for STEAM TO S J A E B ( A ) STAGE I
& 11, 2-PC-1-153(150) set for
approximately 225 psig (dial located
inside controller housing).
8.4.5.2 Manual/Hand loader for STEAM TO SJAE
B ( A ) STAGE I & 11, 2-PC-1-152(150) Set
for approximately 8 psig.
8.4.5.3 Setpoint for STEAM TO SJAE B ( A ) STAGE
111, 2-PC-1-167(166) set for
approximately 225 psig (dial located
inside controller housing).
8.4.5.4 Manual/hand loader for STEAM TO S J A E
B (A) STAGE 111, 2-PC-1-167(166), set for
approximately 8 psig.
Standard:
DISPATCH US to perfom/verify steps 8.4.5.1 through 8.4.5.4.
SAT- UNSATN/A- COMMENTS :
JPM NO. 116F
REV. NO. 1
JPM NO. 116F
REV. NO. 1
PAGE 15 OF 23
.............................................................
Performance Step : Critical- Not Critical_X _
8.4.6 At Panel 25-105, VERIFY both SJAE dilution steam
pressure modifiers are adjusted to approximately
mid-position (located at the rear of panel).
8.4.6.1 SJAE B(A) STG I & I1 PRESSURE, 2-XM-1-
152 (150).
8.4.6.2 SJAE B(A) STAGE I11 PRESSURE, 2-XM-1-
167 (166).
Standard :
CONTACTED AUO/OSUS to verify both SJAE B dilution steam
pressure modifiers, 2-XM-1-152 and 2-XM-1-167 are in mid-
posit ion.
SAT- UNSAT-N/A- COMMENTS :
CUE: [WHEN CALLED], BOTH SJAE DILUTION STEAM PRESSURE MODIFIERS
(2-XM-1-152 and 2-XM-1-167) ARE ADJUSTED TO MID-POSITION.
.............................................................
Performance Step : Critical- Not C r i t i c a l X
8.4.7 At Panel 2-9-8, VERIFY OPEN both SJAE Inlet Valves
using the following:
8.4.7.1 SJAE 2A INLET VALVE, 2-HS-66-11.
8.4.7.2 SJAE 2B INLET VALVE, 2-HS-66-15.
Standard:
VERIFIED/PLACED 2-HS-66-11 and 15 in the OPEN position.
JPM NO. 116F
REV. NO. 1
PAGE 16 OF 23
SAT-UNSAT- N/A- COMMENTS :
.............................................................
Performance Step : CriticalX Not Critical-
8.4.8 At Panel 2-9-7, PLACE the STEAM TO SJAE 2A(2B)
handswitch, 2-HS-l-l55A(156A), in CLOSE.
Standard:
VERIFIED/PLACED 2-HS-1-155Ain CLOSED position.
SAT- UNSAT N/A COMMENTS :
.............................................................
Performance Step : CriticalX Not Critical-
8.4.9 At Panel 2-9-7, PLACE the SJAE 2A(2B) PRESS
CONTROLLER handswitch, 2-HS-1-150(152), in CLOSE.
Standard:
VERIFIED/PLACED 2-HS-1-150 in CLOSED position.
SAT- UNSAT N/A COMMENTS :
Performance SteD : CriticalX Not Critical-
8.4.10 At Panel 2-9-8, PLACE the SJAE 2A(2B) OG OUTLET
VALVE using 2-HS-66-14(18), in CLOSE.
JPM NO. 116F
REV. NO. 1
PAGE 1 7 OF 23
Standard:
VERIFIED/PLACED 2-HS-66-14 in CLOSED position.
SAT- UNSAT N/A COMMENTS :
JPM NO. 116F
REV. NO. 1
PAGE 18 OF 23
.............................................................
Performance Step : CriticalX Not Critical-
~
8.4.11 At Panel 2-9-8, PLACE in OPEN/AUTO the SJAE 2B(2A)
OG OUTLET VALVE using, 2-HS-66-18(14).
Standard :
VERIFIED/PLACED 2-HS-66-18 in the OPEN/AUTO position.
SAT- TJNSAT-N/A- COMMENTS :
.............................................................
Performance SteD : CriticalX Not Critical-
8.4.12 At Panel 2-9-7, PLACE the SJAE TO SJAE 2B(2A)
handswitch, 2-HS-l-l56A(155A)in OPEN.
Standard:
PLACED 2-HS-1-156Ain OPEN position.
SAT- UNSAT-N/A- COMMENTS: ___
JPM NO. 116F
REV. NO. 1
PAGE 19 OF 23
.............................................................
Performance Step : CriticalX Not Critical-
8.4.13 At Panel 2-9-7, PLACE the STEAM TO SJAE 2B(2A)
PRESS CONTROLLER handswitch, 2-HS-1-152(150), in
OPEN.
Standard :
PLACED 2-HS-1-152in the OPEN position AND RECOGNIZED THAT
SAT- UNSAT-N/A- COMMENTS:
Note :
It may be necessary to return 2-HS-1-152(150)to CLOSE position,
then back to OPEN i n order to open the SJAE steam supply valves.
This will reset the logic sequence.
.............................................................
Performance Step : CriticalX Not Critical-
(PER NOTE) Return 2-HS-152 to CLOSE and then back to OPEN.
Standard:
RETURNED 2-HS-152 to CLOSE and then back to OPEN. RECOGNIZED
B SJAE functioning properly.
SAT- UNSAT-N/A- COMMENTS :
JPM NO. 116F
REV. NO. 1
PAGE 20 O F 2 3
.............................................................
Performance SteQ : Critical-Not Criticalx
8.4.14 On Panel 25-105, ADJUST manual/hand loaders until
dilution steam pressure is indicating
approximately 190 to 220 psig on the following
indications:
8.4.14.1 STEAM TO SJAE B ( A ) STAGE I & 11, 2 - P I - 1 -
152 (150).
8.4.14.2 STEAM TO SJAE B ( A ) STAGE 111, 2 - P I - 1 -
167 (166) .
CUE: [WHEN CALLED], INFORM OPERATOR THAT LOCAL STEPS 8.4.14
THROUGH 8.4.19 HAVE BEEN COMPLETE.
Standard :
DISPATCHED Operator to perorm steps 8.4.14 through 8.4.19
locally.
SAT-UNSAT-N/A- COMMENTS :
-
JPM NO. 116F
REV. NO. 1
PAGE 21 OF 23
.............................................................
Performance Step : Critical- Not C r i t i c a l 2
8.4.20 On Panel 2-9-6, MONITOR hotwell pressure as
indicated on HOTWELL TEMP AND PRESS recorder, 2-
XR-2-2.
Standard:
VERIFIED stable hotwell pressure and temperature indications
on 2-XR-2-2.
SAT-UNSAT-N/A- COMMENTS :
.................................................................
Performance Step : Critical- Not CriticalX
6.4.21 After stable SJAE operation has been confirmed,
the HWC system may be placed back in service at
the direction of the Unit Supervisor, REFER TO 2-
01-4, HWC System (N/A is HWC System is
unavailabled) .
Standard:
None
SAT-UNSAT-N/A- COMMENTS :
TERMINATING CUE: THE US ADVISES HWC WILL BE RETURNED TO
SERVICE AT A LATER TIME. THAT WILL BE ALL FOR NOW.
JPM NO. 116F
REV. NO. 1
PAGE 22 OF 23
............................................................
Performance SteD: Critical- Not C r i t i c a l X
PERFORMER demonstrated the use of TOUCH STAAR during this
JPM .
Standard:
PERFORMER verified applicable components by utilizing TOUCH
S T M (Standard is subjective and instructor must evaluate
the need for additional training on TOUCH STAAR to maintain plant
standards).
SAT- UNSAT-N/A- COMMENTS :
Performance SteD: Critical Not Critical X
PERFORMER demonstrated the use of 3-WAY COMMUNICATION during
this JPM.
Standard:
PERFORMER utilized 3-WAY COMMUNICATION using phonetic
alphabet, receiving/requesting and acknowledging repeat-
backs.
SAT UNSAT N/A COMMENTS
-
END OF TASK
JPM NO. 116F
REV. NO. 1
PAGE 23 OF 2 3
STOP TIME:
JPM NO. 114
REV. NO. 6
PAGE 1 OF 12
BROWNS FERRY NUCLEAR PLANT
JOB PERFORLWCE MEASURE
JPM NUMBER: 114
TITLE : STANDBY GAS TREATMENT TRAIN C DECAY HEAT
REMOVAL
TASK NUMBER: U-065-NO-13
SAFETY FUNCTION: 9
TYPE CODE: D
SUBMITTED BY: DATE :
VALIDATED BY: DATE :
APPROVED : DATE :
TRAINING
PLANT CONCURRENCE: DATE :
OPERATIONS
JPM NO. 114
REV. NO. 6
PAGE 2 OF 12
- Examination JPMs Require Operations Training Manager or Designee Approval and
Plant Concurrence
JPM NO. 114
REV. NO. 6
PAGE 3 OF 12
BROWNS FERRY NUCLEAR PLANT
-. . . . . ... .., .__ . . JOB- .-
PERFORMANCE MEASURE
-- - .- - __ .. ...
REVISION LOG
Revision Effective Pages Description
Number Date Affected of Revision
1 10/4/94 ALL GENERAL REVISION
2 10/24/94 2,3,5 PROCEDURE UPDATE
3 5/2/96 2,3 PROCEDURE UPDATE
4 8/8/97 ALL FORMAT DOCUMENT, ADD NON-
CRITICAL STEPS ON TOUCH
STAAR, 3-WAY COMM.,
CHANGE ASOS TO US.
5 10/27/98 ALL PROCEDURE REVISION
6 10/14/02 ALL GENERAL REVISION
JPM NO. 114
REV. NO. 6
PAGE 4 OF 12
BROWNS FERRY NUCLEAR PLANT
I
OPERATOR :
JPM NUMBER: 114
TASK NUMBER: U-065-NO-13
TASK TITLE: PERFORM SGT TRAIN C DECAY HEAT REMOVAL
K/A NUMBER: 223001G13 K/A RATING: R O X SRO: 3.7
..................................................................
TASK STANDARD: PERFORM CONTROL ROOM OPERATIONS REQUIRED TO
PERFORM STANDBY GAS TREATMENT TRAIN C DECAY HEAT
REMOVAL
LOCATION OF PERFORMANCE: SIMULATOR PLANT - CONTROL ROOM I
REFERENCES/PROCEDURES NEEDED: 0-01-65, REV 41
VALIDATION TIME: CONTROL ROOM: 8:OO 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 ___
JPM NO. 114
REV. NO. 6
PAGE 5 OF 12
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 an Operator. Standby Gas Treatment
Train C has been operated to vent the drywell and has been
secured. 2-XA-55-3B,Window 25, SGT TRAIN C FILTER BANK TEMP HIGH,
2-TA-65-63 is in alarm.
INITIATING CUES : (NAME) , perform Standby
Gas Treatment Train C decay heat removal using Standby Gas
Treatment Fan C and SGT C decay heat damper as directed by O-OI-
65.
JPM NO. 114
REV. NO. 6
PAGE 7 OF 12
START TIME
EXAMINER'S NOTE: EXACT STEP SEQUENCE REQUIRED.
.................................................................
Performance Step: Critical- Not Critical2
WHEN REQUESTED BY EXAMINER identify/obtain copy of required
procedure.
Standard :
IDENTIFIED OR OBTAINED COPY of 0-01-65.
SAT-UNSAT-N/A- COMMENTS :
8.9 SGT Train C Decay Heat Removal
-.NOTES *
(1) This section provides methods to remove decay heat from the
charcoal filters after flow is terminated through Train C.
(2) The SGT System will be operated from both Panels 1-9-25 and
2-9-25 throughout this section.
(3) Section 8.9.1 and 8.9.2 utilize Fan C for decay heat removal;
and Section 8.9.3 utilizes Fan B. These sections are stand
alone.
JPM NO. 114
REV. NO. 6
PAGE 8 OF 12
8.9.1 SGT Train C decay heat removal using Fan C and
SGT Train C decay heat damper.
.............................................................
Performance Stew : CriticalX Not Critical-
8.9.1.1 PLACE SGTS TRAIN C INLET DAMPER
handswitch, O-HS-65-51A,in the CLOSE
position on Panel 2-9-25.
Standard :
PLACED 0-HS-65-51Ain the CLOSE position and VERIFIED
illuminated GREEN damper position indicating lamp above
associated hand switch.
SAT- UNSAT- N/A- COMMENTS :
.............................................................
Performance Step : Critical- Not Critical2
8.9.1.2 VERIFY OPEN SGTS TRAIN C OUTL DAMPER, using
0-HS-65-67Aon Panel 2-9-25.
Standard :
VERIFIED illuminated RED damper position indicating lamp
above 0-HS-65-67A.
SAT- UNSAT-N/A- COMMENTS :
JPM NO. 114
REV. NO. 6
PAGE 9 OF 12
.............................................................
performance^^^ step : ~ ~ T ~ r - ~~ .
CriticalX Not Critical-
8.9.1.3 START SGTS TRAIN C FAN, using O-HS-65-69A/2
on Panel 2-9-25.
Standard :
PLACED O-HS-65-69A/2in the START position and VERIFIED
illuminated RED motor breaker position indicating lamp above
associated hand switch.
SAT-UNSAT- N/A- COMMENTS :
...............................................................
Performance Steo : CriticalX Not Critical-
8.9.1.4 OPEN SGTS TRAIN C DECAY HEAT DAMPER, using 0-
HS-65-52A on Panel 1-9-25.
Standard :
CONTACTED Unit 1 Operator and REQUESTED SGT TRAIN C DECAY
HEAT DAMPER 0-DMP-65-52OPENED.
SAT- UNSAT- N/A- COMMENTS: Candidate may state that
he/she would loq time and bank dp in narrative 10s.
TERMINATING CUE: [WHEN REQUESTED] REPORT BACK THAT SGT
TRAIN C DECAY HEAT DAMPER 0-DMP-65-52AIS OPEN. THAT WILL
BE ALL FOR NOW.
.L
JPM NO. 114
REV. NO. 6
PAGE 10 OF 12
JPM NO. 114
REV. NO. 6
PAGE 11 OF 12
..................................................................
Performance Stev: Critical Not Critical x
. ..- .~~~~~~~~~~
- ,~.. .~.. .~
~ ~~~
~ ~~
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 N/A COMMENTS :
.................................................................
Performance Stev: Critical Not Critical x
PERFORMER demonstrated the use of 3-WAY COMMUNICATION during
this 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 W A COMMENTS :
END OF TASK
JPM NO. 114
REV. NO. 6
PAGE 1 2 OF 12
STOP TIME:
JPM NO. 96
REV. NO. 6
PAGE 1 OF 1 4
BROWNS FERRY NUCLEAR PLANT
TITLE: PERFORM CONTROL ROOM TRANSFER OF 4KV SHUTDOWN
BOARD A POWER SUPPLIES
TASK NUMBER: S-57A-NO-01
SAFETY FUCTION: 6
TYPE CODE: D
SUBMITTED BY: DATE :
VALIDATED BY: DATE :
APPROVED : DATE :
TRAINING
PLANT CONCURRENCE: DATE :
OPERATIONS
JPM NO. 96
REV. NO. 6
PAGE 2 OF 14
- Examination JPMs Require Operations Training Manager or Designee Approval and
Plant Concurrence
JPM NO. 96
REV. NO. 6
PAGE 3 OF 14
BROWNS FERRY NUCLEAR PLANT
REVISION LOG
Revision Effective Pages Description
Number Date Affected of Revision
1 12/8/94 1,2,3,4 REVISE TO NEW FORMAT
2 8/5/96 ALL PROCEDURE UPGRADE, ADDED
CRITICAL STEP ON TOUCH
STAAR, AND CHANGED COMM.
STD .
10/27/96 4, 14 CHANGED CRIT. STEP ON
TOUCH STAAR TO NON-CRIT
2,3,4,14 PROCEDURE CHANGE, ADDED
3-WAY COMM. AND CHANGED
MGT EXPECT. TO PLANT WORK
EXPECT.
5 10/24/01 A11 PROCEDURE CHANGE
6 9/1/02 3 PROCEDURE # CHANGE
JPM NO. 96
REV. NO. 6
PAGE 4 OF 14
BROWNS FERRY NUCLEAR PLANT
OPERATOR :
JPM NUMBER: 96
TASK NUMBER: S-57A-NO-01
TASK TITLE: PERFORM CONTROL ROOM TRANSFER OF 4KV SHUTDOWN
BOARD POWER SUPPLIES
K/A NUMBER: 262001A4.03 K/A RATING: R O X SRO: 3 .4
..................................................................
TASK STANDARD: PERFORM CONTROL ROOM OPERATION REQUIRED TO
SUCCESSFULLY TRANSFER 4KV SD BOARD A POWER SUPPLY
FROM NORMAL TO ALTERNATE POWER SUPPLY
LOCATION OF PERFORMANCE: SIMULATOR PLANT - CONTROL ROOM -
REFERENCES/PROCEDURES NEEDED: 0-01-57A, REV 04 I
VALIDATION TIME: CONTROL ROOM: 15:OO LOCAL :
MAX. TIME ALLOWED: (Completed for Time Critical JPMs only)
PERFORMANCE TIME: CONTROL ROOM - LOCAL -
-
COMMENTS :
~ ~~~~
Additional comment sheets attached? YES - NO -
JPM NO. 96
REV. NO. 6
PAGE 5 OF 14
RESULTS : SATISFACTORY UNSATISFACTORY _ _
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 Supervisor. Units 2 and 3
are at 100% rated power. 4kV Shutdown Bus 1 is to be de-energized
and tagged. 4kV Shutdown Board A is to remain energized from 4kV
Shutdown Bus 2.
INITIATING CUES : The Shift Manager has directed you to
transfer 4kV Shutdown Board A power supply from Shutdown Bus 1 to
Shutdown BUS 2 in accordance with 0-01-57A.
JPM NO. 96,
REV. NO. 6
PAGE 7 OF 14
START TIME
EXAMINER'S NOTE: EXACT STEP SEQUENCE REQUIRED.
.................................................................
Performance SteD: Critical- Not Critical2
WHEN REQUESTED BY EXAMINER identify/obtain copy of required
procedure.
Standard:
IDENTIFIED OR OBTAINED COPY Of 0-01-57A.
SAT-UNSAT-N/A- COMMENTS:
8.0 INFREQUENT OPERATIONS
8.1 Control Room Transfer of 4kV Shutdown Board A Power Supplies
8.1.1To transfer 4KV SD BD A to the ALT FDR BKR 1716,
PERFORM the following:
..............................................................
Performance SteD: Critical- Not Critical2
8.1.1.1 REVIEW all Precautions and Limitations
in Section 3.0.
Standard:
REVIEWED Precautions and Limitations in Section 3.0.
SAT-UNSAT-N/A- COMMENTS:
JPM NO. 96
REV. NO. 6
PAGE 8 OF 14
JPM NO. 96
REV. NO. 6
PAGE 9 OF 1 4
..............................................................
~ ~ ~~~~~
Performance SteD: ~~~~~~~. . ~~ ~~~ - ~ ~ . .Critical- Not Critical2
8.1.1.2 NOTIFY Chem-lab prior to transferring(if
feeding 480V D/G Aux. Board A)
Standard:
NOTIFIED Chem-lab of 4kV Shutdown Board A power supply
transfer.
CUE: [CHEM LAB1 "REPEATS: TRANSFERRING POWER SUPPLIES TO
4kV SHUTDOWN BOARD A.
SAT-UNSAT-N/A- COMMENTS :
NOTE:
All procedural steps are performed from Control Room Panel 0-9-23-
7.
..............................................................
Performance SteD: Critical- Not Critical2
8.1.1.3 PLACE O-XS-211-A, 4KV SD BD A VOLTAGE/
Standard :
PLACED 0-XS-211-Ato 4KV SD BUS 2 position.
SAT-UNSAT-N/A- COMMENTS :
JPM NO. 96
REV. NO. 6
PAGE 10 OF 14
JPM NO. 96,
REV. NO. 6
PAGE 11 OF 14
..............................................................
Performance SteD: Critical- Not Critical2
8.1.1.4 CHECK 4KV SD BUS 2 voltage is between
3950 and 4400 Volts as indicated on 0 -
Standard:
VERIFIED 0-EI-211-A indicating 3950 to 4400 volts.
SAT- UNSAT-N/A- COMMENTS:
.............................................................
Performance Step : CriticalX Not Critical-
8.1.1.5 PLACE 0-25-211-A/24A,4Kv SD BD A BKR
1716 SYNC switch to ON.
Standard:
PLACED 0-25-211-A/24Ain the ON position.
SAT- UNSAT-N/A- COMMENTS:
The GEN SYNC Breaker is the breaker to be closed onto the board.
The SYSTEM SYNC Breaker is the breaker supplying the board prior
to the transfer.
JPM NO. 96
REV. NO. 6
PAGE 12 OF 14
.............................................................
Performance Step : Critical- Not Critical2
8.1.1.6 CHECK GEN SYNC REF VOLTAGE and SYSTEM
SYNC REF VOLTAGE is between 116 and 125
volts.
Standard:
VERIFIED 0-EI-82-AB&?& 0-EI-211-ABindicating between 116
and 125 volts.
SAT- UNSAT-N/A- COMMENTS :
~~ ~
.............................................................
Performance Step : Critical- Not Critical2
8.1.1.7 CHECK GEN SYNC FREQUENCY and SYSTEM SYNC
FREQUENCY are approximately 60 Hz.
Standard :
VERIFIED 0-SI-81-AB and 0-SI-211-ABindicating approximately
60 HZ.
SAT- UNSATN/A- COMMENTS :
JPM NO. 96
REV. NO. 6
PAGE 13 OF 14
.............................................................
Performance Step : Critical- Not Critical2
. . ~~ . ~~ ~~ . ..~.~ . ~. 8.1.1.8 CHECK O-SCP-82-AB,DG A/B SYNCHROSCOPE,
at 12 o'clock position.
Standard :
VERIFIED 0-SCP-82-ABindicating approximately 12 o'clock
posit ion.
SAT- UNSAT-N/A- COMMENTS:
.............................................................
Performance SteD : Critical2 Not Critical-
8.1.1.9 Momentarily DEPRESS O-HS-211-A,4KV SD
BD A AUTO TO MANUAL TRIP pushbutton and
CHECK the following:
8.1.1.9.1 O-HS-211-A,4KV SD BD A
AUTO TO MANUAL TRIP,
amber light extinguished.
8.1.1.9.2 0-43-211-A,4KV SD BD A
AUTO/LOCKOUT RESET,
trips.
Standard :
DEPRESSED 0-HS-211-A4KV SD BD A AUTO TO MANUAL TRIP
pushbutton (CRITICAL), VERIFIED TRIP TO MANUAL amber light
extinguished (NOT CRITICAL) and 0-43-211-Atripped to the
angled position (NOT CRITICAL).
SAT- UNSAT-N / A- COMMENTS:
JPM NO. 96
REV. NO. 6
PAGE 14 OF 14
..............................................................
CAUTION
The 4kV Shutdown Boards are NORMAL seeking. Therefore, to prevent
undesired auto transfer, 0-43-211-A,4KV SD BD A AUTO/LOCKOUT
RESET switch should be left in the TRIPPED position whenever 4KV
SD BD A is selected to the alternate source.
................................................................
.............................................................
Performance Step : Critical2 Not Critical-
8.1.1.10 PLACE and HOLD O-HS-211-A/24A,4KV SD BD
A ALT FDR BKR 1716, to CLOSE.
Standard:
PLACED and CONTINUED HOLDING O-HS-211-A/24Ain the CLOSE
position.
SAT- UNSAT-N/A__ COMMENTS:
.............................................................
Performance SteD : Criticalx Not Critical-
8.1.1.11 PLACE O-HS-211-A/3A,4KV SD BD A NORM
FDR BKR 1614, to TRIP.
Standard:
JPM NO. 96
REV. NO. 6
PAGE 15 OF 14
PLACED O-HS-211-A/3A in the TRIP position.
SAT- UNSAT-N/A- COMMENTS:
.............................................................
Performance Stev : Critical- Not Critical2
8.1.1.12 CHECK CLOSED 4KV SD BD A ALT FDR BKR
1716.
Standard:
VERIFIED illuminated RED breaker position indicating lamp
above O-HS-211-A/24A.
SAT- UNSAT N/A COMMENTS:
.............................................................
Performance Steu : Critical- Not Critical2
8.1.1.13 CHECK OPEN 4KV SD BD A NORM FDR BKR
1614.
Standard :
VERIFIED illuminated GREEN breaker position indicating lamp
above O-HS-211-A/3A.
JPM NO. 96
REV. NO. 6
PAGE 16 O F 1 4
SAT- UNSAT N/A COMMENTS :
.............................................................
Performance SteD : Critical- Not Critical2
8.1.1.14 RELEASE breakers 1614 and 1716 switches.
Standard :
RELEASED O-HS-211-A/24Aand O-HS-211-A/3A.
SAT- UNSAT-N/A- COMMENTS :
.............................................................
Performance SteD : Critical- Not Critical2
8.1.1.15 PLACE O-XS-211-A,4KV SD BD A VOLTAGE
Standard:
PLACED 0-XS-211-Ain the 4KV SD BD A position.
SAT- UNSAT N/A COMMENTS :
.............................................................
Performance SteD : Critical- Not Critical2
8.1.1.16 CHECK 4KV S D BD A Voltage is between
JPM NO. 96
REV. NO. 6
PAGE 17 OF 14
3950 and 4400 volts.
Standard:
__
VERIFIED 0-EI-211-Aindicating between 3950 and 4400 v o l t s .
SAT- UNSAT-N/A- COMMENTS:
Performance Step : Critical- Not Critical2
8.1.1.17 PLACE 0-25-211-A/24Ar4KV SD BD A BKR
1716 SYNC, to OFF.
Standard:
PLACED 0-25-211-A/24Ain the OFF position.
SAT- UNSAT-N/A- COMMENTS:
JPM NO. 96,
REV. NO. 6
PAGE 18 O F 14
.............................................................
Performance SteD : Critical- Not C r i t i c a l 3
8.1.1.18 Verify locally 4KV SD BD A ALT FDR BKR
1716 closing spring target indicates
charged and the amber breaker spring
charged light is on.
Standard:
DISPATCHED AUO to verify breaker 1716 closing spring
recharged.
CUE: [AFTER DISPATCHED] THE AUO REPORTS THAT BREAKER 1716
CLOSING SPRING TARGET INDICATES CHARGED AND THE AMBER
BREAKER SPRING CHARGED LAMP IS ILLUMINATED.
JPM NO. 96,
REV. NO. 6
PAGE 19 OF 14
............................................................
Performance SteD: 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-N/A- COMMENTS :
-
................................................................
Performance SteD: Critical Not Critical X
PERFORMER demonstrated the use of 3-WAY COMMUNICATION during
this JPM.
Standard :
PERFORMER utilized 3-WAY COMMUNICATION i.e., used phonetic
alphabet, received/solicited and acknowledged repeat-backs.
SAT UNSAT N/A COMMENTS
STOP TIME:
END OF TASK
JPM NO. 51F
REV. NO. 10
PAGE 1 OF 27
BROWNS FERRY NUCLEAR PLANT
JPM NUMBER: 51F
TITLE : 2-EO1 APPENDIX 12 - PRIMARY CONTAINMENT
VENTING FROM PRESSURE SUPPRESSION CHAMBER
THROUGH FCV-84-20
TASK NUMBER: U-000-EM-61
SAFETY FUNCTION: 9
TYPE CODE: D,A
SUBMITTED BY: DATE :
VALIDATED BY: DATE :
APPROVED : DATE :
TRAINING
PLANT CONCURRENCE: DATE :
OPERATIONS
JPM NO. 51F
REV. NO. 10
PAGE 2 OF 21
- Examination JPMs Require Operations Training Manager or Designee Approval and
Plant Concurrence
JPM NO. 51F
REV. NO. 10
PAGE 3 OF 21
BROWNS FERRY NUCLEAR PLANT
JOB PERFORMANCE MEASURE -
REVISION LOG
Revision Effective Pages Description
Number Date Affected of Revision
3 11/28/94 REVISE TO NEW FORMAT
4 10/28/95 GENERAL REVISION
5 10/24/96 4, 15 ADDED NON-CRIT. STEP ON
TOUCH STAAR, AND CHANGED
ASOS TO US.
6 10/1/97 ALL FORMAT, CHANGED MGT.
EXPECTATIONS TO PLANT
WORK EXPECTATIONS AND
ADDED 3-WAY COMM.
7 01/04/99 ALL NEW EO1 REVISION
8 10/21/99 ALL PROCEDURE REVISION
9 9/22/00 ALL GENERAL REVISION
10 8/13/02 ALL GENERAL REVISION
JPM NO. 51F
REV. NO. 10
PAGE 4 OF 21
BROWNS FERRY NUCLEAR PLANT
OPERATOR :
JPM NUMBER: 51F
TASK NUMBER: U-000-EM-61
TASK TITLE: VENT PRIMARY CONTAINMENT IN ACCORDANCE WITH 2-EO1
APPENDIX 12
K/A NUMBER: 295024EA1.20 K/A RATING: R O X SRO: 3.6
..................................................................
TASK STANDARD: PERFORM OPERATIONS NECESSARY TO VENT THE PRESSURE
SUPPRESSION CHAMBER AS DIRECTED BY 2-EO1 APPENDIX
12.
LOCATION OF PERFORMANCE: SIMULATOR X PLANT - CONTROL ROOM -
REFERENCES/PROCEDURES NEEDED: 2-EO1 APPENDIX 12, REV. 2
VALIDATION TIME: CONTROL ROOM: 12:OO LOCAL:
MAX. TIME ALLOWED: (Completed for Time Critical JPMs only)
PERFORMANCE TIME: CONTROL ROOM LOCAL -
COMMENTS :
Additional comment sheets attached? YES - NO -
JPM NO. 51F
REV. NO. 10
PAGE 5 OF 21
RESULTS : SATISFACTORY UNSATISFACTORY
SIGNATURE: DATE :
f EXAMINER ~ ~~-
-
... ..... ... . ...... ....BROrnS..FERRY. NUCLEm.PLANT . .. ..
- '**X * *-*-** *~****X*.* * *~**** * *-*-*x-*-ww***-* **-**-****rr*.rmmrww-* * ** *~*IR-.
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 a Unit 2 Operator. Unit 2 reactor has
scrammed. A small leak exists in primary containment. EOI-2 has
been followed to PC/P-1.
INITIATING CUES: The UNIT SUPERVISOR directs you to vent
containment in accordance with 2-EO1 Appendix 12.
JPM NO. 51F
REV. NO. 10
PAGE 7 OF 27
~
START TIME
EXAMINER'S NOTE: EXACT STEP SEQUENCE IS REQUIRED.
.................................................................
Performance Step: Critical- Not C r i t i c a l X
WHEN REQUESTED BY EXAMINER identify/obtain copy of required
EO1 Appendix.
Standard:
IDENTIFIED OR OBTAINED copy of 2-EO1 Appendix 12.
SAT-UNSAT-N/A- COMMENTS :
.................................................................
CAUTION
Stack release rates exceeding 1.4 x lo' pCi/sec, or 0-SI
4.8.B.l.a.l release fraction above 1.0 will result in ODCM
release limits being exceeded.
.................................................................
............................................................
Performance Step: Critical- Not CriticalX
1. VERIFY at least one SGTS train in service.
Standard :
VERIFIED A, B or C SGT Trains in service by illuminated red
SGT status indicating lamps on Panel 2-9-20.
SAT-UNSAT-N/A- COMMENTS :
JPM NO. 51F
REV. NO. 10
PAGE 0 OF 27
............................................................
Performance Stew: Critical- Not Critical2
2. VERIFY CLOSED the following valves (Panel 2-9-3 or
Panel 2-9-54):
B 2-FCV-64-31,DRYWELL INBOARD ISOLATION VLV,
P@ 2-FCV-64-29,DRYWELL VENT INBD ISOL VALVE,
,# 2-FCV-64-34,SUPPR CHBR INBOARD ISOLATION VLV,
B 2-FCV-64-32,SUPPR CHBR VENT INBD ISOL VALVE.
Standard:
VERIFIED 2-FCV-64-31,29, 34, AND 32 are closed by
illuminated green status indicating lamps on Panel 2-9-3 or
Panel 2-9-54.
SAT-UNSAT-N/A- COMMENTS :
JPM NO. 51F
REV. NO. 10
PAGE 9 O F 2 7
............................................................
Performance Stew: Critical- Not C r i t i c a l X
3. IF. . . . While executing this procedure to vent the
Suppression Chamber, Suppression Pool water
levelcan not be determined to be below 2 0 ft,
THEN. . . PERFORM step 13 to secure the vent path and
re-enter this procedure if further venting is
required.
Standard:
VERIFIED level c 20 ft on narrow or wide range
indicators/recorder on Panel 2 - 9 - 3 , i.e. 2 - L I - 6 4 - 1 5 9 A or 2 -
LI- 6 4 - 5 4 A and CONTINUED with Step 4.
SAT-UNSAT-N/A- COMMENTS :
JPM NO. 51F
REV. NO. 10
PAGE 10 OF 27
- c** c . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
Performance Step: Critical- Not C r i t i c a l X
4. IF. . . . While executing this procedure the desired
vent path is lost or can not be established,
THEN. . . PERFORM step 13 to secure the vent path and
re-enter this procedure if further venting is
required.
Standard:
NONE: Operator read step 4 and continued to step 5.
SAT-TJNSAT-N/A- COMMENTS :
..................................................................
CAUTION
Venting Primary Containment during CAD addition is outside the CAD
system FSAR design basis.
..................................................................
CUE: EO16 ARE THE GOVERNING PROCEDURE
............................................................
JPM NO. 51F
REV. NO. 10
PAGE 11 OF 27
Performance SteD: Critical- Not C r i t i c a l X
5. IF. . . . While executing this procedure, CAD addition
per SAMG-2, Step G-4 OR G-9, is to begin,
THEN. . . BEFORE CAD is initiated, PERFORM Step 13 to
secure the vent path.
NOTE : Venting may be accomplished using EITHER:
/ 2-FIC-84-19,PATH B VENT FLOW CONT,
/ 2-FIC-84-20,PATH A VENT FLOW CONT.
NOTE : Unless the TSC recommends otherwise, venting
the Drywell DIRECTLY should be performed ONLY
if the Suppression Chamber can be vented.
Standard :
Operator determines that since EOIs are in effect the SAMG's
are not continued to step 6.
SAT_UNSAT-N/A- COMMENTS :
............................................................
Performance SteD: Critical- Not C r i t i c a l X
6. IF .....ANY of the following exists:
/ Suppression Pool water level can not be determined to
be below 20 ft,
JPM NO. 51F
REV. NO. 10
PAGE 12 OF 27
/ Suppression Chamber can NOT be vented,
/ SRO orders DIRECT drywell venting
THEN ...CONTINUE in this procedure at:
/Step 10 to vent the Drywell through 2-FCV-84-19,
- 'Step 11 to vent the Drywell through 2-FCV-84-20.
Standard:
VERIFIED level c 20 ft on narrow or wide range
indicators/recorder on Panel 2-9-3, i.e. 2-LI-64-159Aor 2-
LI- 64-54A and CONTINUED with Step 7.
SAT-UNSAT-N/A- COMMENTS :
JPM NO. 51F
REV. NO. 10
PAGE 13 OF 27
............................................................
Performance Step: Critical- Not Critical&
. .. . .
. ,
~ ~~
7. CONTINUE in this procedure at:
B Step 8 to vent the Suppression Chamber through 2-
FCV-84-19,
B Step 9 to vent the Suppression Chamber through
2-FCV-84-20.
Standard :
CONTINUED in this procedure at Step 8 to vent the Suppression
Chamber through 2-FCV-84-19.
SAT-UNSAT-N/A- COMMENTS :
8. VENT. the Suppression Chamber using 2-FIC-84-19, PATH E
FLOW CONT, as follows:
.............................................................
Performance Step : CriticalX Not Critical
a. PLACE keylock switch 2-HS-84-35,SUPPR CHBR/DW VENT ISOL
BYP SELECT, to SUPPR-CHBR position (Panel 2-9-54).
Standard :
PLACED 2-HS-84-35in the SUPPR-CHBR position.
SAT- UNSAT-N/A- COMMENTS :
JPM NO. 51F
REV. NO. 10
PAGE 14 OF 27
JPM NO. 51F
REV. NO. 10
PAGE 15 OF 27
.............................................................
Performance Step : Critical- Not Critical&
b. VERIFY OPEN 2-FCV-64-32,SUPPR CHBR VENT INBD ISOL VALVE
(PaneL2- 9- 54) ,
Standard :
VERIFIED illuminated RED valve position indicating lamp above
2-HS-64- 32 .
SAT- UNSAT N/A COMMENTS :
.............................................................
Performance Step : Critical& Not Critical-
c. PLACE 2-FIC-84-19,PATH B VENT FLOW CONT, in AUTO with
setpoint at 100 scfm (Panel 2-9-55).
Standard :
PLACED 2-FIC-84-19in AUTO at 100 scfm.
SAT- UNSAT-N/A- COMMENTS :
.............................................................
Performance Step : CriticalX Not Critical-
d. PLACE keylock switch 2-HS-84-19,2-FCV-84-19 CONTROL, in
OPEN (Panel 2-9-55).
Standard:
PLACED 2-HS-84-19in the OPEN position.
SAT- UNSAT-N/A- COMMENTS :
JPM NO. 51F
REV. NO. 10
PAGE 16 OF 27
JPM NO. 51F
REV. NO. 10
PAGE 17 OF 27
.............................................................
Performance Step : CriticalX Not Critical-
_ _ ~ -~.
~~ ~ ~
e. VERIFY.2-FIC-84-19,PATH B VENT FLOW CONT, is indicating
approximately 100 scfm.
Standard:
OBSERVED 2-FIC-84-19and DETERMINED flow was being
developed . DETERMINED THAT PSC COULD NOT BE VENTED VIA
2-FCV-84-19AND OPERATOR WENT TO STEP 13 AS DIRECTED BY
STEP 4 . [FAULT]
SAT- UNSAT-N/A- COMMENTS :
.............................................................
Performance Step : CriticalX Not Critical
13. WHEN . . . .ANY of the following exist:
/ Venting is no longer required,
/ Pressure in the space being vented approaches zero,
/Directed by SRO,
/Directed by Step 3 , 4, or 5,
THEN. . .SECURE venting as follows:
JPM NO. 51F
REV. NO. 10
PAGE 18 OF 27
...............................................................
Performance Step : Critical-Not Critical&
a. VERIFY the following keylock switches in OFF
(Panel 2-9-54):
/ 2-HS-84-35,SUPPR CUBR/DW VENT ISOL BYP SELECT,
/ 2-HS-84-36,SUPPR CUBR/DW VENT ISOL BYP SELECT.
Standard :
VERIFIED 2-US-84-35and 36, SUPPR CUBR/DW VENT ISOL BYP
SELECT in OFF position.
SAT- UNSAT-N/A- COMMENTS :
.............................................................
Performance Steo : Critical- Not CriticalX
b. VaRIFY keylock switch 2-HS-84-20,2-FCV-84-20
ISOLATION BYPASS, in NORMAL (Panel 2-9-55).
Standard :
VERIFIED keylock switch 2-HS-84-20,2-FCV-84-20ISOLATION
BYPASS, in NORMAL on Panel 2-9-55.
SAT- UNSAT-N/A- COMMENTS :
JPM NO. 51F
REV. NO. 10
PAGE 19 OF 27
.............................................................
Performance Step : CriticalXNot Critical-
c. VERIFY keylock switch 2-HS-84-19,2-FCV-84-19
CONTROL, in CLOSE (Panel 2-9-55).
Standard :
VERIFIED keylock switch 2-HS-84-19,2-FCV-84-19CONTROL, in
CLOSE on Panel 2-9-55.
SAT- UNSAT-N/A- COMMENTS :
-
.............................................................
Performance Step : Critical- Not C r i t i c a l X
d. VERIFY CLOSED the following valves (Panel 2-9-3 or
Panel 2-9-54):
/ 2-FCV-64-31,DRYWELL INBOARD ISOLATION VLV,
/ 2-FCV-64-29,DRYWELL VENT INBD ISOL VALVE,
JPM NO. 51F
REV. NO. 10
PAGE 20 OF 27
/ 2-FCV-64-34, SUPPR CHBR INBOARD ISOLATION VLV,
/ 2-FCV-64-32, SUPPR CHBR VENT INBOARD ISOL VLV,
Standard :
VERIFIED CLOSED 2-FCV-64-31, 29, 34, AND 32 by VERIFYING
position indicating light GREEN on all the listed valves.
SAT- UNSAT- N/A- COMMENTS :
JPM NO. 51F
REV. NO. 10
PAGE 21 OF 27
.............................................................
Performance SteE : Critical- Not CriticalX
e. VERIFY CLOSED 2-FCV-64-141,DRYWELL DP COMP BYPASS
VALVE (Panel 2-9-3).
Standard :
VERIFIED CLOSED 2-FCV-64-141,DRYWELL DP COMP BYPASS VALVE
on Panel 2-9-3 by VERIFYING GREEN position indicating light
on said valve.
SAT- UNSAT-N/A- COMMENTS :
INSTRUCTOR NOTE: STUDENT RE-ENTERS APPENDIX AND PROCEEDS TO
VENT THE PSC VIA FCV 8 4 - 2 0 PER STEP 9. RECHECK ALL STEPS UP
THROUGH STEP 9 AND PROCEED WITH STEP 9 BELOW.
.............................................................
Performance Step : CriticalX Not Critical-
9. VENT the Suppression Chamber using 2-FIC-84-20,PATH A
VENT FLOW CONT, as follows:
a. VERIFY OPEN 2-FCV-64-141,DRYWELL DP COMP BYPASS
VALVE (Panel 2-9-3).
Standard :
PLACED 2-HS-64-141,Panel 2-9-3, in the OPEN position and
VERIFIED illuminated RED valve position indicating lamp above
associated hand switch.
JPM NO. 51F
REV. NO. 10
PAGE 22 OF 27
SAT- UNSAT__N/A- COMMENTS :
.............................................................
Performance Stev : CriticalX Not Critical -
b. PLACE keylock switch 2-HS-84-36,SUPPR CHBR/DW VENT
ISOL BYP SELECT, to SUPPR-CHBR position (Panel 2-9-54).
Standard :
PLACED 2-HS-84-36 in the SUPPR-CHBR position.
SAT- UNSAT-N/A- COMMENTS :
.............................................................
Performance Stev : Critical- Not CriticalX
C. VERIFY OPEN 2-FCV-64-34,SUPPR CHBR INBOARD ISOLATION
VLV (Panel 2-9-54)
Standard :
VERIFIED illuminated RED valve position indicating lamp above
2-HS-64-34.
SAT- UNSAT- N/A- COMMENTS :
..................................................................
JPM NO. 51F,
REV. NO. 10
PAGE 23 OF 27
~~~~~ ~~ ~~
'Performance-Stew : Critical Not C r i t i c a l X
d. VERIFY 2-FIC-84-20,PATH A VENT FLOW CONT, in AUTO with
setpoint at 100 scfm (Panel 2-9-55).
~.~ .. . - . .
Standard :
PLACED 2-FIC-84-20 in AUTO at 100 scfm.
SAT- UNSAT- N/A- COMMENTS :
.................................................................
Performance SteD: C r i t i c a l X Not Critical-
e. PLACE keylock switch 2-HS-84-20, 2-FCV-84-20 ISOLATION
BYPASS, IN BYPASS, (Panel 2-9-55).
Standard :
PLACED 2-HS-84-20 in the BYPASS position
SAT- UNSAT- N/A- COMMENTS :
..................................................................
Performance Stew: Critical- Not C r i t i c a l X
f. VERIFY 2-FIC-84-20,PATH A VENT FLOW CONT, is
indicating approximately 100 scfm.
Standard :
JPM NO. 51F
REV. NO. 1 0
PAGE 24 OF 27
DETERMINED vent flow was stable at 100 scfm as indicated on
2-FIC-84-20 and continued with the next stepproceeded to
step 12 of this procedure.
SAT-UNSAT- N/A- COMMENTS :
JPM NO. 51F
REV. NO. 10
PAGE 25 OF 27
-
.............................................................
Performance Step : CriticalA ~ o Critical-
t
12. ADJUST 2-FIC-84-19,PATH B VENT FLOW CONTR, or 2-FIC-
84-20, PATH A VENT FLOW CONT, as applicable, to
maintain ALL of the following:
/Stable flow as indicated on controller
AND
/ 2-PA-84-21,VENT PRESS TO SGT HIGH, alarm light
extinguished,
AND
/ Release rates as determined below:
i. IF. .PRIMARY CONTAINMENT FLOODING per
C-1, Alternate Level Control, is in
progress,
THEN. .MAINTAIN release rates below
those specifiedin Attachment 2.
CUE: PRIMARY CONTAINMENT FLOODING IS NOT REQUIRED.
L
ii. IF. . Severe Accident Management Guidelines
are being executed,
THEN. .MAINTAIN release rates below those
specified by the TSC SAM Team.
JPM NO. 51P
REV. NO. 10
PAGE 26 OF 27
4
CUE: EO18 are still in effect.
iii. IF. .Venting for ANy other reason than items
i or ii above,
THEN. . MAINTAIN release rates below
5 Stack release rate of 1.4 x 10
pCi/sec
AND
5 0-SI-4.8.B.l.a.l release fraction
of 1.
Standard :
ADJUSTED 2-FIC-84-20 (as necessary) to obtain maximum
indicated flow without 2-PA-84-21yellow alarm light
illuminating. REQUESTED release rates from Log AUO.
SAT- UNSAT-N/A- COMMENTS :
L
CUE: [WHEN CHECKED] STACK RELEASE RATES ARE 1.0 x 10
UCi/sec AND THE STACK RELEASE FRACTION IS cl.
............................................................
Performance Stew: Critical- Not Critical&
JPM NO. 51F
REV. NO. 10
PAGE 27 OF 2 7
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 N/A COMMENTS:
-
..................................................................
Performance Step: Critical- Not Critical&
PERFORMER demonstrated the use of 3-WAY COMMUNICATION during
this JPM.
Standard :
PERFORMER utilized 3-WAY COMMUNICATION i.e., used phonetic
alphabet, received/solicited and acknowledged repeatbacks.
SAT UNSAT N/A COMMENTS:
-
END OF TASK
STOP TIME:
JPM NO. 35
REV. NO. a
PAGE 1 OF 10
. .. . . -
.-. . . . . ....... . .. . -... . . ..FERRY
EROWNS ... .. .-....NUCLEAR
.. . . P ..
. .L . .. . .,..
A.N . .__ . ..
JPM NUMBER: 35
TITLE : 2-EO1 APPENDIX 8B - REOPENING MSIVS FOLLOWING
GROUP I ISOLATION
TASK NUMBER: U-000-EM-46
SAFETY FUNCTION: 3
TYPE CODE: D
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. 35
REV. NO. 8
PAGE 2 OF 10
BROWNS FERRY NUCLEAR PLANT
A
REVISION LOG
Revision Effective Pages Description
Number Date Affected of Revision
3 11/28/94 1,2,3,4 REVISE TO NEW FORMAT
4 9/5/96 ALL DELETED PLANT INST, ADDED
TOUCH STAAR CRIT. STEP,
CHANGED ASOS TO US.
5 10/23/96 4,12 CHANGED CRIT. STEP TO
NON-CRITICAL ON STAAR.
6 ALL 8/7/97 FORMAT DOCUMENT, ADDED
NON-CRIT. STEP ON 3-WAY
COMM .
7 9/22/00 ALL GENERAL REVISION
JPM NO. 35
REV. NO. 8
PAGE 3 OF 10
BROWNS FERRY NUCLEAR PLANT
OPERATOR : I
JPM NUMBER: 35
TASK NUMBER: U-000-EM-46
TASK TITLE: 2-EO1 APPENDIX 8B - REOPENING MSIVS FOLLOWING A
GROUP I ISOLATION
K/A NUMBER: 223002A4.03 K/A RATING: RO 3.6 SRO: 3.5
..................................................................
TASK STANDARD: PERFORM THE CORRECT EQUIPMENT MANIPULATIONS
REQUIRED TO EQUALIZE AROUND THE MSIVS AND REOPEN
THE MSIVS PER 2-EO1 APPENDIX 8 B
LOCATION OF PERFORMANCE: SIMULATOR PLANT - CONTROL ROOM -
REFERENCES/PROCEDURES NEEDED: 2-EO1 APPENDIX 8 B , REV 4 I
VALIDATION TIME: CONTROL ROOM: 25:OO LOCAL :
MAX. TIME ALLOWED: (Completed for Time Critical JPMs only)
PERFORMANCE TIME: CONTROL ROOM _ _ LOCAL -
COMMENTS :
Additional comment sheets attached? YES ___ NO __
JPM NO. 35
REV. NO. 8
PAGE 4 OF 1 0
RESULTS : SATISFACTORY UNSATISFACTORY
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 Thats Correctur. (OR Thats 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 a Unit 2 Operator. Unit 2 reactor has
scrammed and isolated. EOI-1 has been entered and conditions allow
the MSIVs to be reopened to establish the main condenser as a heat
sink.
INITIATING CUES : The UNIT SUPERVISOR directs you to reopen the
MSIVs as directed by 2-EOI-Appendix 8B.
JPM NO. 35
REV. NO. 8
PAGE 6 OF 10
START TIME ~- ~
I
EXAMINER'S NOTE: EXACT STEP SEQUENCE IS REQUIRED.
1
1
..................................................
Performance Step: Critical- Not Critical2
WHEN REQUESTED BY EXAMINER identify/obtain copy of required
procedure.
Standard :
IDENTIFIED OR OBTAINED Copy of 2-EOI-APPENDIX 8B.
SAT-UNSAT-N/A- COMMENTS :
.................................................................
Performance Step: C r i t i c a l X N o t Critical-
1. VERIFY MSIV control switches in CLOSE position. I
Standard :
PLACED all eight MSIVs hand switches in the CLOSE position.
SAT- UNSAT-N/A- COMMENTS:
JPM NO. 35
REV. NO. ' 8
PAGE 7 OF 10
.................................................................
Performance SteD: C r i t i c a l X N o t Critical-
2. RESET PCIS logic (Panel 9-4).
Standard:
PLACED both PCIS reset switches on Panel 9-4 to the left and
right position and VERIFIED that four RED light above the
reset switches were illuminated.
SAT- UNSAT N/A COMMENTS :
............................................................
Performance SteD: CriticalX Not Critical-
3. DEPRESS the following pushbuttons to trip
2-HS-3-125,RFPT A MANUAL TURBINE TRIP
2-HS-3-151,RFPT B MANUAL TURBINE TRIP
0 2-HS-3-176,RFPT C MANUAL TURBINE TRIP
Standard:
DEPRESSED 2-HS-3-125,151, 176.
JPM NO. 35
REV. NO. 8
PAGE 8 OF 1 0
SAT- UNSAT-N/A- COMMENTS :
JPM NO. 35
REV. NO. 8
PAGE 9 OF 10
..................................................................
Performance Step: C r i t i c a l X N o t Critical-
~ ~
4. VERIFY CLOSED the following drain valves(Pane1 9-3):
NOTE : To prevent auto opening of 2-FCV-1-58, handswitch
2-HS-1-58A must be held in the CLOSE position
until main turbine speed decreases to below 1700
RPM .
b 2-FCV-1-58,UPSTREAM MSL DRAIN TO CONDENSER
a 2-FCV-1-59,DOWN STREAM MSL DRAIN TO CONDENSER.
Standard :
VERIFIED illuminated GREEN valve position indicating lights
above 2-HS-1-59 [NOT CRITICAL]. PLACED 2-HS-1-58 in the CLOSE
position [CRITICAL] and VERIFIED illuminated GREEN valve
position indicating lamp above associated control switch [NOT
CRITICAL].
SAT- UNSAT- N/A- COMMENTS :
............................................................
Performance Step: CriticalX Not Critical-
5. OPEN the following outboard MSIVs(Pane1 9-3):
e 2-FCV-1-15,MSIV LINE A OUTBOARD
b 2-FCV-1-27,MSIV LINE B OUTBOARD
b 2-FCV-1-38,MSIV LINE C OUTBOARD
b 2-FCV-1-52,MSIV LINE D OUTBOARD
Standard :
JPM NO. 35
REV. NO. 8
PAGE 1 0 OF 1 0
PLACED 2-HS-1-15, 27, 38 and 52 in the OPEN position and
VERIFIED illuminated RED valve position indicating lamps
above the associated control switches.
SAT- UNSAT-N/A- COMMENTS :
JPM NO. 35
REV. NO. 8
PAGE 11 OF 10
...........................................................
Performance Step: Critical Not Critical X
6. VERIFY EHC is in HEADER PRESSURE CONTROL with SETPOINT
above reactor pressure.
Standard:
DEPRESSED 2-HS-1-16 and/or VERIFIED illuminated. VERIFIED
SETPOINT as indicated on 2-PI-47-162indicates greater than
reactor pressure.
SATUNSAT_N/A- COMMENTS :
.............................................................
............................................................
Performance Step: CriticalX Not Critical-
7. OPEN the following drain valves(Pane1 9-3):
2-FCV-1-55, MN STM LINE DRAIN INBD ISOLATION VLV
2-FCV-1-56, MN STM LINE DRAIN OUTBD ISOLATION VLV
0 2-FCV-1-57, MSIV DOWNSTREAM DRAINS SHUTOFF.
Standard:
PLACED 2-HS-1-55 and 2-HS-1-56 in the OPEN position and
VERIFIED illuminated RED valve position indicating lamps
above the associated control switches. VERIFIED illuminated
RED valve position indicating lamp above 2-HS-1-57 [NOT
CRITICAL].
SAT- UNSAT-N/A- COMMENTS :
JPM NO. 35
REV. NO. 8
PAGE 12 OF 10
JPM NO. 35
REV. NO. 8
PAGE 13 OF 10
.................................................................
CAUTION
Opening MSIVs when differential pressure is above 50 psid may
result in piping system damage.
..............................................................
Performance Stew: CriticalX Not Critical-
8. WHEN ... Main steam pressure is within 50 psig of
RPV pressure,
THEN ...OPEN the following inboard MSIVs(Pane1 9-3):
0 2-FCV-1-14,MSIV LINE A INBOARD
0 2-FCV-1-26,MSIV LINE B INBOARD
0 2-FCV-1-37,MSIV LINE C INBOARD
0 2-FCV-1-51,MSIV LINE D INBOARD
Standard :
When main steam pressure as indicated by 2-PI-47-99 on Panel
9-7 is within 50 psig of reactor pressure, PLACED HS-1-14,
26, 37 and 51 in the AUTO/OPEN position and VERIFIED RED
valve position indicating lamps above associated hand
switches.
SAT- UNSAT-N/A- COMMENTS :
JPM NO. 35
REV. NO. 8
PAGE 14 OF 10
............................................................
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- N/A- COMMENTS:
..................................................................
Performance SteD: Critical- Not Critical2
PERFORMER demonstrated the use of 3-WAY COMMUNICATION during
this JPM.
Standard :
PERFORMER utilized 3-WAY communications ,ie used phonetic
alphabet, received/solicited and acknowledged repeat backs.
SAT- UNSAT N/A- COMMENTS :
END OF TASK
STOP TIME:
JPM NO. 201
REVISION NO. 0
PAGE 1 OF 21
BROWNS FERRY NUCLEAR PLANT
JPM NUMBER: 201
TITLE : LOSS OF SHUTDOWN COOLING
TASK NUMBER: 0 - 74 -AB-01
SAFETY FUNCTION: 4
TYPE CODE: N, L
SUBMITTED BY: DATE :
VALIDATED BY: DATE :
APPROVED : DATE :
TRAINING
PLANT CONCURRENCE: DATE :
OPERATIONS
JPM NO. 201
REVISION NO. 0
PAGE 2 OF 21
- Examination JPMs Require Operations Training Manager or Designee Approval and
Plant Concurrence
JPM NO. 201
REVISION NO. 0
PAGE 3 OF 21
BROWNS FERRY NUCLEAR PLANT
i
REVISION LOG
Revision Effective Pages Description
Number Date Affected of Revision
0 8/8/02 A1 1 New
JPM NO. 201
REVISION NO. 0
PAGE 4 OF 21
BROWNS FERRY NUCLEAR PLANT
OPERATOR :
JPM NUMBER: 201
TASK NUMBER: U-074-AB-01
TASK TITLE: RESPOND TO LOSS OF SHUTDOWN COOLING
KIA NUMBER: 295021 AA1.02 KIA RATING: R 0 3 SRO: 3.5
..................................................................
TASK STANDARD: SUCCESSFULLY RESTORE SHUTDOWN COOLING FOLLOWING
LOSS DUE TO INADVERTENT RPS ACTUATION.
LOCATION OF PERFORMANCE: SIMULATOR - PLANT - CONTROL ROOM -
REFERENCES/PROCEDURES NEEDED:2-AOI-74-1, LOSS OF SHUTDOWN COOLING,
REVISION 26
VALIDATION TIME: CONTROL ROOM: 19:OO LOCAL:
MAX. TIME ALLOWED: (Completed for Time Critical JPMs only)
PERFORMANCE TIME: CONTROL ROOM LOCAL -
-
COMMENTS :
~ ~~
Additional comment sheets attached? YES - NO -
JPM NO. 201
REVISION NO. 0
PAGE 5 OF 21
RESULTS: SATISFACTORY UNSATISFACTORY
EXAMINER SIGNATURE: DATE :
BROWNS FERRY NUCLEAR PLANT
J O B PERFORMANCE MEASURE
._
..............................................................
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 a Unit 2 operator. Unit 2 is in
Mode 4 for a refueling outage. RHR Loop I1 using 2 B RHR Pump
is in shutdown cooling. A n inadvertent loss of 2 B R P S bus
resulted in a partial isolation of RHR shutdown cooling. RPS
2 B has been restored. Another operator is assisting with
recovery from the loss of 2 B R P S . The US has notified the
Shift Manager of the problem.
INITIATING CUES: The US directs you to restore shutdown
cooling using 2 B RHR pump in accordance with 2-AOI-74-1.
JPM NO. 201
REVISION NO. 0
PAGE 7 OF 21
START TIME
kOTE: UNLESS OTHERWISE NOTED., ALL CONTROLS AND
INSTRUMENTATION ARE LOCATED ON PANEL 2-9-3.
3.0 AUTOMATIC ACTIONS
None.
4.0 OPERATOR ACTIONS
4.1 Immediate Actions
None.
4.2 Subsequent Actions
NOTE :
The blanks to the side of steps contained in Section
4.0 Operator Actions are intended for place keeping
- required. If necessary,
only. Initials are NOT
place keeping marks may be made directly in the
Control Room copy of this instruction. Contact DCRM
f o r a replacement copy when time permits.
.............................................................
CAUTION
Reactor vessel stratification may occur until Shutdown
Cooling is restored or a Reactor Recirculation Pump is placed
in service.
.............................................................
EXAMINER'S NOTE: EXACT STEP SEQUENCE IS REQUIRED.
Performance Stew: Critical- Not Critical&
4.2.1 IF any EO1 entry condition is met, THEN
ENTER the appropriate EOI ( s ) . (Otherwise
N/A)
Standard :
DETERMINES no EO1 entry conditions have been met and N/As
step.
JPM NO. 201
REVISION NO. 0
PAGE 8 OF 2 1
SAT-UNSAT-N/A- COMMENTS :
JPM NO. 201
REVISION NO. 0
PAGE 9 OF 21
...........................................................
Standard :
None. Given in the initiating cue
SAT-UNSAT-N/A x COMMENTS:
.............................................................
...........................................................
Performance Step: Critical- Not Critical X
4.2.3 IF Refueling is in progress, THEN
NOTIFY the Refueling Floor SRO.
Standard :
Mode 4 given in initial conditions. Not required to notify
Refueling Floor SRO immediately.
SAT UNSAT N/A X COMMENTS :
.............................................................
JPM NO. 201
REVISION NO. 0
PAGE 10 OF 21
...........................................................
Performance Step: Critical Not Critical X
4.2.4 REVIEW EPIP-1, Emergency Plan
Classification Logic, for entry
conditions.
Standard :
None
SAT-UNSAT-N/A__ X COMMENTS :
Cue: The Shift Manager and STA are reviewing the EPIPs.
.............................................................
1
JPM NO. 201
REVISION NO. 0
PAGE 11 OF 21
...........................................................
Performance Step: Critical Not Critical X
4.2.5 IF Shutdown Cooling isolates on low RPV water
level or high Drywell press (GROUP 2 ISOL)
AND RPV water level needs restoring using
LPCI, THEN
PERFORM the following before reaching -122
inches RPV water level:
Standard :
Determines water level does NOT need restoring at this time.
SAT-UNSAT-N/A_ COMMENTS :
.............................................................
...........................................................
Performance Step: Critical Not Critical X
4.2.6 IF Primary Containment Integrity is required, THEN
VERIFY RHR system discharge piping pressure is
being maintained >TRM 3.5.4 Limits. REFER TO
2-01-74.
Standard :
DETERMINES Primary Containment NOT required in Mode 4.
SAT UNSAT N/A- COMMENTS :
.............................................................
JPM NO. 201
REVISION NO. 0
PAGE 12 OF 21
NOTES :
(1) With the Reactor in Cold Shutdown Condition (Mode
4 or Mode 5), reactor coolant stratification may
be indicated by one of the following:
Reactor pressure above 0 psig with any reactor
coolant temperature indication reading at or
below 212°F.
Differential temperatures of 50°F or greater
between either F Z VESSEL BOTTOM HEAD (FLANGE DR
LINE) 2-TE-56-29 ( 8 ) temperatures and RX VESSEL
FW NOZZLE N4B END (N4B INBD) (N4B END) (N4D INBD)
2-TE-56-13(14)(15)(16) temperatures from the
REACTOR VESSEL
METAL TEMPERATURE recorder, 2-TR-56-4.
With recirculation pumps and shutdown cooling
out of service, a Feedwater sparger temperature
of 200°F or greater on any RX VESSEL FW NOZZLE
(N4B END (N4B INBD) (N4D END) (N4D INBD)
2-TE-56-13(14)(15)(16) temperatures from the
REACTOR VESSEL
METAL TEMPERATURE recorder, 2-TR-56-4.
(2 [NER/C] For purposes of thermal stratification
monitoring, the bottom head drain line is more
representative as long as there is flow in the
line. [GE SIL 251 and 4301
- . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
Performance Step: Critical- Not Critical X
4.2.7 PLOT heatup/cooldown rate as necessary.
REFER TO 2-SR-3.4.9.1(1).
Standard :
SELECTS HUR on SPDS.
SAT-UNSAT-N/A- COMMENTS :
Cue: Another operator is performing 2-SR-3.4.9.1(1).
I
.............................................................
JPM NO. 201
REVISION NO. 0
PAGE 13 OF 21
...........................................................
Performance Step: Critical- Not Critical- X
4.2.8 DIRECT the STA to ESTIMATE the
following times at least once per shift
until a method of decay heat removal is
restored :
4.2.8.1 DETERMINE the time since shutdown.
4.2.8.2 .DETERMINE the current RPV heat-up rate from
2-SR-3.4.9.1(1), or, if reactor coolant
stratification is suspected, use
Illustration 1.If additional information is
required to determine the heat-up rates,
contact Reactor Engineer
4.2.8.3..DETERMINE the reactor coolant temperature
or use the last valid reactor coolant
temperature available.
4.2.8.4..ESTIMATE the time for reactor coolant
temperature to reach 212OF, using data
obtained in Steps 4.2.8.1 through 4.2.8.3.
4.2.8.5 IF the Reactor Vessel head is removed
and the cavity is flooded with the fuel
pool gates installed, (Otherwise N/A)
THEN ESTIMATE the time for reactor coolant
temperature to reach 125OF and 150°F using
a plot of the actual heatup rate or
Illustration 1.
Standard:
DIRECTS STA to estimate the 'time to boil'.
SAT-UNSAT-N/A- COMMENTS :
.............................................................
JPM NO. 201
REVISION NO. 0
PAGE 14 OF 21
................................. **************
Performance Step: Critical Not Critical X
4.2.9 IF the loss of Shutdown Cooling is due to
inadequate RHRSW flow, THEN START the standby
RHRSW pump for the appropriate header. REFER
TO 0-01-23. (Otherwise N/A)
Standard :
N/AS Step 4.2.9.
SAT-UNSAT N/A_ COMMENTS :
.............................................................
...........................................................
Performance Step: Critical X
~ Not Critical-
4.2.10.IF the loss of Shutdown Cooling is due to Group 2
PCIS isolation, WHEN conditions which permit
resetting Group 2 PCIS isolation are met, THEN
(Otherwise N/A)
PERFORM the following:
4.2.10.1 RESET Group 2 isolation by momentarily
PLACING PCIS DIV I RESET,2-HS-64-16A-S32,
in reset, and PCIS DIV I1 RESET,
2-HS-16A-S33, in reset.
Standard :
On Panel 2-9-4, RESETS Group 2 isolation by momentarily
PLACING PCIS DIV I RESET,2-HS-64-16A-S32,in reset.
SAT UNSAT N/A- COMMENTS :
.............................................................
JPM NO. 201
REVISION NO. 0
PAGE 15 OF 21
...........................................................
Performance Step: Critical-X Not Critical
4.2.10.2 Momentarily DEPRESS RHR SYS I(I1) SD CLG
INBD INJECT ISOL RESET, 2-XS-74-126 and
2-XS-74-132. VERIFY 2-IL-74-126 and
2-IL-74-132 extinguished.
Standard :
Momentarily DEPRESSES RHR SYS I1 SD CLG INBDINJECT ISOL
RESET, 2-XS-74-132. VERIFY 2-IL-74-132 extinguished.
SAT UNSAT-N/A- COMMENTS :
.............................................................
JPM NO. 201
REVISION NO. 0
PAGE 16 OF 21
...........................................................
Performance Step: Critical Not Critical&
4.2.11 IF the loss of Shutdown Cooling is due
- the isolation
to Group 2 PCIS AND
signal fails to reset or remain reset
due to invalid and/or sporadic signals,
THEN (Otherwise N/A)
PERFORM the following:
Standard:
N/AS Step 4.2.11.
SAT UNSAT_N/A- COMMENTS:
.............................................................
...........................................................
Performance Step: Critical- X Not Critical-
Subsequent Actions (continued) )
4.2.12 IF the Group 2 PCIS Isolation has been
reset, THEN
RETURN the affected loop of RHR to
Shutdown Cooling as follows:
4.2.12.1 CLOSE RHR SYS I(I1) LPCI OUTBD INJECT
VALVE, 2-FCV-74-52(66).
Standard:
PLACES 2-HS-74-66in close until ONLY GREEN valve
position indicating lamp is illuminated.
SAT-UNSAT N/A- COMMENTS:
.............................................................
JPM NO. 201
REVISION NO. 0
PAGE 17 OF 21
...........................................................
Performance Step: Critical Not Critical X
4.2.12.2 OPEN RHR SYS I(I1) LPCI INBD INJECT
VALVE, 2-FCV-74-53(67).
Standard:
VERIFIES 2-FCV-74-67ONLY RED valve position indicating lamp
illuminated.
SAT UNSAT N/A- COMMENTS :
.............................................................
...........................................................
Performance Step: Critical-X Not Critical
4.2.12.3 OPEN RHR SHUTDOWN COOLING SUCT OUTBD and
INBD ISOL VLVs, 2-FCV-74-47- and 2-FCV-74-48.
Standard:
PLACES 2-HS-74- 47 in Open and verified 2-FCV-74-48ONLY RED
valve position indicating lamp is illuminated.
SAT-UNSAT N/A- COMMENTS :
.............................................................
JPM NO. 201
REVISION NO. 0
PAGE 18 OF 21
...........................................................
Performance Step: Critical-X Not Critical
4.2.12.4 RESTARTtripped RHR pump ( s ) RHR PUMP
2A(2C) (2B)(2D) using 2-HS-74-
5A(16A) (28A)(39A)
Standard :
PLACES 2-HS-74-28A in Start.
SAT UNSAT N/A- COMMENTS :
.............................................................
JPM NO. 201
REVISION NO. 0
PAGE 19 OF 21
............................................................
Performance Step: Critical-X Not Critical-
4.2.12.5 THROTTLE RHR SYS I ( I 1 ) LPCI
OUTBD INJECTION VALVE,
2-FCV-74-52(66), to establish and
maintain RHR flow as indicated by
2-FI-74-50(64), RHR SYS I(I1)
FLOW,
as follows:
2
Loop Flow 7,000 to 10,000 14,000 to I
Loop Flow (1 or
more
__
+ fuel bundles% 6,000 to 6,500
e&. Cff,
removed rom
core-
)-
Standard :
MANIPULATES 2-HS-74-66 to obtain RHR System I1 Loop flow
between 7,000 and 10,000 GPM.
SAT UNSAT N/A- COMMENTS :
.............................................................
JPM NO. 201
REVISION NO. 0
PAGE 20 OF 21
. ~~ ~~ ~~~ ~~ ~~~~~ .~ ~ . ~ ~ . ~ ~~ ~. ~.
~~~ ~~ i ~ ; ~ ~
~ ~ ~ ~.~ . . ~ ~~
~~
~ ~~ ~.~
...........................................................
Performance Step: Critical Not Critical X
4.2.12.6 VJHEN time permits after RHR
pump is started, THEN
VERIFY RHR Pump Breaker
charging spring recharged by
observing amber breaker spring
charged light is on and closing
spring target indicates
charged.
Standard :
DISPATCHED personnel to verify RHR Pump 2B breaker closing
spring recharged.
SAT-UNSAT N/A- COMMENTS:
.............................................................
CUE: ANOTHER OPERATOR WILL COMPLETE THE TASK. THIS ENDS
THE JPM .
I
JPM NO. 201
REVISION NO. 0
PAGE 21 OF 21
~~
~ . ~ ~~
~ ~~
~~ ~~ ~ ~
.~
. ~~
~.
~~~~~ ~ ~~
............................................................
Performance Step: - . Not Critical- X
.~ ~ . Critical
. :. ,.i.:. . .
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 N/A COMMENTS:
..............................................................
Performance Step:
PERFORMER demonstrated the use of 3-WAY COMMUNICATION during
this JPM.
Standard:
PERFORMER utilized 3-WAY COMMUNICATION (Standard is subjective
and instructor must evaluate the need or additional training
on 3-WAY COMMUNICATION to maintain plant standards).
SAT UNSAT N/A COMMENTS :
...........................................................
END OF TASK
STOP TIME
JPM NO. 148F,
REV. NO. 0
PAGE 1 OF 13
BROWNS FERRY NUCLEAR PLANT
JPM NUMBER: 148F
TITLE: PERFORM IMMEDIATE OPERATOR ACTIONS FOR CRD
PUMP TRIP
TASK NUMBER: U-085-AB-03
SAFETY FUNCTION: 1
TYPE CODE: N.A
SUBMITTED BY: DATE :
VALIDATED BY: DATE :
APPROVED : DATE :
TRAINING
PLANT CONCURRENCE: DATE :
OPERATIONS
JPM NO. 148F
REV. NO. 0
PAGE 2 OF 13
- Examination JPMs Require Operations Training Manager or Designee Approval and
Plant Concurrence
JPM NO. 148F
REV. NO. 0
PAGE 3 OF 13
BROWNS FERRY NUCLEAR PLANT
JOB PERFORMANCE I4EASURE
REVISION LOG
Revision Effective Pages Description
Number Date Affected of Revision
0 8/15/02 ALL NEW
JPM NO. 148F
REV. NO. 0
PAGE 4 OF 13
BROWNS FERRY NUCLEAR PLANT
OPERATOR : I
JPM NUMBER: 148F
TASK NUMBER: U-085-AB-03
TASK TITLE: RESPOND TO CRD SYSTEM FAILURE
K/A NUMBER: 295022AA1.01 K/A RATING: RO 3.1 SRO: 3.2
..................................................................
TASK STANDARD: PERFORM IMMEDIATE OPEWTOR ACTIONS FOR CRD PUMP 2A
TRIP AS DIRECTED BY 2-AOI-85-3.
LOCATION OF PERFORMANCE: SIMULATOR PLANT - CONTROL ROOM -
REFERENCES/PROCEDURES NEEDED: 2-~01-85-3, REV 20
VALIDATION TIME: CONTROL ROOM: 4:OO LOCAL:
MAX. TIME ALLOWED: (Completed f o r Time Critical JPMs only)
PERFORMANCE TIME: CONTROL ROOM ~ LOCAL -
COMMENTS :
Additional comment sheets attached? YES NO -
RESULTS : SATISFACTORY UNSATISFACTORY
JPM NO. 148F
REV. NO. 0
PAGE 5 OF 13
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 j o b 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 a Unit 2 Operator. Unit 2 is at 100%
power with no equipment out of service
INITIATING CUES: Respond to the next event. Let me know when you
are ready to assume shift.
JPM NO. 148F
REV. NO. 0
PAGE 7 OF 13
START TIME
INSTRUCTOR CUES: HAVE CONSOLE 0PERATOR.TRIP 2A CRD PUMP. (IMF
RDOlA FOR CRD PUMP 2A)
4.0 OPERATOR ACTIONS
4.1 Immediate Actions
4.1.1 IF operating CRD PUMP has TRIPPED AND STANDBY CRD
PUMP IS AVAILABLE, THEN
PERFORM the following at Panel 2-9-5:
.............................................................
Performance Step : C r i t i c a l X Not Critical-
4.1.1.1 PLACE CRD SYSTEM FLOW CONTROL, 2-FIC-85-11,
in MAN at minimum setting.
Standard :
PLACED 2-FIC-85-11 in MAN. TURNED manual potentiometer Until
0 (zero) manual demand signal obtained
SAT- UNSAT N/A COMMENTS :
JPM NO. 148F
REV. NO. 0
PAGE 8 OF 13
.............................................................
Performance Step : CriticalX Not Critical-
4.1.1.2 START associated standby CRD Pump using one
of the following:
k CRD PUMP lB, using 2-HS-85-2A.
k CRD PUMP 2A, using 2-HS-85-1A.
Standard :
PLACED 2-HS-85-2A in the START position. DETERMINED 1B CRD
Pump failed to start.
SAT- UNSAT-N/A- COMMENTS :
Performance Step : Critical- Not C r i t i c a l l
4.1.2 IF operating CRD PUMP has TRIPPED AND BACKUP CRD
PUMP is NOT AVAILABLE, THEN (Otherwise N/A)
PERFORM the following at Panel 2-9-5:
4.1.2.1 PLACE CRD SYSTEM FLOW CONTROL, 2-FIC-85-11,
in MRN at minimum setting.
Standard :
VERIFIED CRD SYSTEM FLOW CONTROL, 2-FIC-85-11,in MAN at
minimum setting.
SAT- UNSAT-N/A- COMMENTS :
JPM NO. 148F
REV. NO. 0
PAGE 9 OF 13
...........................................................
Performance Step: Critical- X Not Critical-
4.1.2.2 ATTEMPT to RESTART tripped CRD Pump using one
. . ._ .... - .. . .- - -. ...
-of.the following':.
- CRD PUMP lB, using 2-HS-85-2A.
- CRD PUMP 2A, using 2-HS-85-1A.
Standard :
RESTARTED CRD PUMP 2A, using 2-HS-85-1A.
SAT UNSAT N/A- COMMENTS :
.............................................................
JPM NO. 148F
REV. NO. 0
PAGE 10 OF 13
.............................................................
Performance Stew : C r i t i c a l X Not Critical-
4.1.2.3 ADJUST CRD SYSTEM FLOW CONTROL, 2-FIC-85-11,
to establish the following conditions:
CRD CLG WTR HDR DP, 2-PDI-85-18A,
approximately 20 psid
CRD SYSTEM FLOW CONTROL, 2-FIC-85-11,
BETWEEN 40 AND 65 GPM.
Standard :
ADJUSTED manual potentiometer on 2-FIC-85-11until:
/ 2-PDI-85-18A indicating -20 psid
/ 2-FIC-85-11indicating 40 to 65 gpm
SAT- UNSAT-N/A- COMMENTS :
Performance Stew : Critical- Not C r i t i c a l X
4.1.2.4 BALANCE CRD SYSTEM FLOW CONTROL, 2-FIC-85-11,
AND PLACE in AUTO or BALANCE.
Standard:
ADJUSTED 2-FIC-85-11 tape setpoint until red pointer was
under green window and then PLACED controller in AUTO or
BALANCE.
SAT- UNSAT-N/A- COMMENTS :
JPM NO. 148F
REV. NO. 0
PAGE 11 OF 13
JPM NO. 148F
REV. NO. 0
PAGE 12 OF 13
Performance Step: Critical- Not Critical&
-
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 N/A COMMENTS :
Performance Step: Critical Not C r i t i c a l X
PERFORMER demonstrated the use of 3-WAY COMMUNICATION during
this 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 N/A COMMENTS
-
JPM NO. 148F.
REV. NO. 0
PAGE 13 O F 1 3
END OF TASK
-~ ~
STOP TIME:
JPM NO. 84
REV. NO. 4
PAGE 1 OF 11
BROWNS FERRY NUCLEAR PLANT
z
JPM NUMBER: 84
TITLE : ENERGIZE A UNIT 1/2 4KV SHUTDOWN BOARD VIA A UNIT
3 DG IN ACCORDANCE WITH O-AOI-57-1A,ATTACHMENT 7
TASK NUMBER: U-57A-1A-AB-01
SAFETY FUNCTION: 6
TYPE CODE: D
SUBMITTED BY: DATE :
VALIDATED BY: DATE :
APPROVED : DATE :
TRAINING
PLANT CONCURRENCE: DATE :
OPERATIONS
JPM NO. a4
REV. NO. 4
PAGE 2 OF 11
- Examination JPMs Require Operations Training Manager or Designee Approval and
Plant Concurrence
JPM NO. 04
REV. NO. 4
PAGE 3 OF 11
.
BROWNS FERRY NUCLEAR PLANT
REVISION LOG
Revision Effective Pages Description
Number Date Affected of Revision
0 10/14/94 ALL NEW JPM
1 10/14/95 A11 Revised procedure
2 10/30/96 ALL PROCEDURE REVISION, ADDED
NON-CRITICAL STEP ON
TOUCH STILAR, CHANGED ASOS
TO US.
3 11/12/99 2,3,4,6,11 PROCEDURE REVISION,
FORMAT, CHANGED MGT.
EXPECT. TO PLANT WORK
EXPECT., ADDED NON-CRIT.
STEP 3-WAY COMM.
4 10/16/02 3, REMOVE SS#, CHG PROC REV
JPM NO. 84
REV. NO. 4
PAGE 4 OF 11
BROWNS FERRY NUCLEAR PLANT
JOB PERFORMANCE MEASUR
OPERATOR :
JPM NUMBER: 84
TASK NUMBER: U-057A-AB-01
TASK TITLE: RESPOND TO LOSS OF OFFSITE POWER
K/A NUMBER: 262001A4.04 K/A RATING: ROX SRO: 3 .7
..................................................................
TASK STANDARD: ENERGIZE 4 KV SHUTDOWN BOARD D VIA 3ED DIESEL
GENERATOR
LOCATION OF PERFORMANCE: SIMULATOR X PLANT - CONTROL ROOM -
REFERENCES/PROCEDURES NEEDED: O-AOI-57-1A,REV 50
VALIDATION TIME: CONTROL ROOM: 1O:OO LOCAL :
MAX. TIME ALLOWED: (Completed for Time Critical JPMs only)
PERFORMANCE TIME: CONTROL ROOM _ _ LOCAL -
-
COMMENTS :
Additional comment sheets attached? YES _ _ NO -
JPM NO. 84
REV. NO. 4
PAGE 5 O F 11
RESULTS : SATISFACTORY UNSATISFACTORY
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 an OPERATOR. The plant has
experienced a loss of off-site power. You have been placed in
charge of carrying out the actions of O-AOI-57-1A,Loss of Offsite
Power. All systems have responded as expected except 'D' Diesel
Generator failed to auto start and cannot be manually started.
INITIATING CUES : The Unit 2 UNIT SUPERVISOR has directed you
to energize 'D' 4kV Shutdown Board via 3D Diesel Generator as
directed by O-AOI-57-1A,Attachment 7.
JPM NO. 84
REV. NO. 4
PAGE 7 OF 11
START TIME ~
EXAMINER'S NOTE: EXACT STEP SEQUENCE REQUIRED.
.................................................................
Performance SteD: Critical- Not Critical2
WHEN REQUESTED BY EXAMINER identify/obtain copy of required
procedure.
Standard :
IDENTIFIED OR OBTAINED copy of O-AOI-57-1A,Attachment 7.
SAT-UNSAT-N/A- COMMENTS:
ENERGIZING A UNIT 1/2 4KV SHUTDOWN BOARD VIA A UNIT 3 DG
The following table identifies the normal feeder breaker,
alternate feeder breaker, diesel generator output breaker and unit
crosstie breaker associated with each 4-KV shutdown board. This
table should be referred to as needed when performing the
subsequent steps in this subsection.
.................................................................
CAUTION
The cross-tie cables for 4160V Shutdown Boards C and 3EC are able
to carry full load current for 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> without exceeding the
90°C rating of the cable. After the 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />, the load must be
reduced to 340 amps. This is a once in a Lifetime Limit for the
cable. [CALC ED-Q0999-8701351
..................................................................
JPM NO. 84
REV. NO. 4
PAGE 8 OF 11
JPM NO. 84
REV. NO. 4
PAGE 9 OF 11
.............................................................
Performance Step : Critical- Not Critical2
1.0 STATION a licensed operator at the diesel generator sections
of the 9-23 panels in both the Units 1 & 2 and Unit 3 Control
Rooms.
Standard :
CONTACTED U-3 Operator to man Panel 3-9-23.
SAT- msAT-N / A- COMMENTS :
CUE: [SIMULATOR OPERATOR WHEN CONTACTED] OPERATOR STANDING
BY AT PANEL 3-9-23.
.............................................................
Performance Step : CriticalX Not Critical-
2.0 To prevent entering an unanalyzed condition ( B and C SBGT
feed from the same power supply), TRANSFER Diesel A u x Board B
to its alternate power supply prior to energizing D 4KV S/D
Bd via 3D Diesel Generator.
Standard:
JPM NO. 84
REV. NO. 4
PAGE 10 OF 11
Momentarily PLACED O-HS-219-BB, 480V DIESEL AUX BD B FDR
TRANSFER, in the ALT position.
SAT- UNSAT N/A COMMENTS :
JPM NO. 84
REV. NO. 4
PAGE 11 OF 11
.............................................................
Performance Steu : Critical- Not Critical2
3.0 PERFORM the following at Panel 9-23 in the Unit 3 Control
Room :
3.1 VERIFY the associated Unit 3 diesel generator has
started and tied to its respective 4KV S/D board.
Standard :
VERIFIED from Unit 3 Operator that 3ED diesel generator
running and tied to 3ED 4kV shutdown board.
SAT-UNSATN/A- COMMENTS :
CUE: [SIMULATOR OPERATOR] 3ED DIESEL GENERATOR IS RUNNING'
AND TIED TO 3ED 4KV SHUTDOWN BOARD.
.............................................................
Performance Stev : Critical- Not Critical2
3.2 VERIFY the D/G MODE SELECT switch is in SINGLE UNIT and
PULL OUT on the switch.
Standard:
VERIFIED from Unit 3 Operator that diesel generator mode
select switch is in SINGLE UNIT position and has PULLED OUT
on the Mode Switch.
SAT- UNSAT N/A COMMENTS :
JPM NO. 84,
REV. NO. 4
PAGE 12 OF 11
JPM NO. 84
REV. NO. 4
PAGE 13 OF 11
Performance SteE : Critical- Not Critical2
3.3 VERIFY the SINGLE UNIT light (left red) is ILLUMINATED.
Standard :
VERIFIED from Unit 3 Operator that red SINGLE UNIT above Mode
Select Switch illuminated.
SAT-UNSAT-N/A- COMMENTS:
CUE: [SIMULATOR OPERATOR] THE RED SINGLE UNIT INDICATING
LAMP (LEFT RED) ABOVE THE 3ED DG MODE SELECT SWITCH IS
ILLUMINATED.
.............................................................
Performance Step : CriticalX Not Critical-
3.4 CLOSE the CROSSTIE to Units 1/2 Breaker.
Standard:
REQUESTED Unit 3 Operator to CLOSE Breaker 1846.
SAT-UNSATN/A- COMMENTS:
CUE: [SIMULATOR OPERATOR ENTER MRF ED06 AND REPORT] BREAKER
1846 HAS BEEN CLOSED.
JPM NO. 84
REV. NO. 4
PAGE 14 OF 11
4.0 PERFORM the following steps at Panel 9-23 in the Unit 1/2
Control Room:
.............................................................
Performance SteD : Critical- Not Critical2
4.1 VERIFY the Unit 1/2 4KV S/D board to be energized from
Unit 3 is DE-ENERGIZED.
Standard :
VERIFIED no feeder breakers closed in to D 4kV Shutdown Board
as indicated by voltmeter or illuminated green breaker
position indicating lamps for breaker numbers 1724, 1618,
1816, 1826 and/or VERIFIED O-EI-211-D,4KV SD BD D VOLTS
indicating 0 volts.
SAT- UNSAT-N/ A- COMMENTS:
.............................................................
Performance SteD : CriticalX Not Critical-
4.2 CLOSE the EMERG. FDR BREAKER to the de-energized board.
Standard:
PLACED Breaker 1826 control switch in the CLOSE position.
SAT- IJNSAT-N/A- COMMENTS:
JPM NO. a4
REV. NO. 4
PAGE 15 OF 11
.............................................................
-Performance Step : Critical- Not Critical2
5.0 MAINTAIN Diesel Generator loading within the limits of
Attachment 6.
Standard :
In conjunction with Unit 3 Operator, VERIFIED D diesel
generator loading within limits of Attachment 6.
SAT- UNSAT N/A COMMENTS :
CUE:[SIMULATOR OPERATOR WHEN ASKED] DG 3ED LOADINQ IS
1800 KW.
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 N/A COMMENTS :
-
JPM NO. 04
REV. NO. 4
PAGE 16 OF 11
................................................................
Performance SteD: Critical Not Critical X
PERFORMER demonstrated the use of 3-WAY COMMUNICATION during
this JPM.
Standard :
PERFORMER utilized 3-WAY COMMUNICATION i.e., used phonetic
alphabet, received/solicited and acknowledged repeat-backs.
SAT UNSAT N/A COMMENTS
-
END OF TASK
STOP TIME