ML032450469
| ML032450469 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 03/07/2003 |
| From: | Ernstes M Operator Licensing and Human Performance Branch |
| To: | Scalice J Tennessee Valley Authority |
| Shared Package | |
| ML032461208 | List: |
| References | |
| 50-327/03-301, 50-328/03-301 | |
| Download: ML032450469 (44) | |
See also: IR 05000327/2003301
Text
Draft Submittal
(Pink Paper)
-7
SEQUOYAH RETAKE EXAM
50-327& 50-328/2003-301
FEBRUARY 27,2003
1. Administrative Questions/JPMs
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4. Administrative Topics Outline ES-301-1
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ES-301 Administrative Topics Outline Form ES-301-1
Facility: Seauovah Date of Examination: 2/27/2003
Examination Level (circle one): RO Operating Test Number: 1
Describe method of evaluation:
2. TWO Administrative Questions
A. 1 Conduct Of JPM # 161-2 - Calculate Subcooling Margin (Neither SPDS
Operations nor Subcooling Margin Monitors are available.) (New)
(Perform in Simulator))
Plant JPM # 017 - Determine if SI Termination Criteria is Met
Parameter (Perform in Simulator)
Verification
Equipment JPM # 022, Calibrate Power Range NI (Perform in
A.2
Control Simulator)
Radiation JPM # 165-2 - Perform a Shielding Calculation. (New)
Control
Emergency JPM # 157 - Monitor Status Trees, Pressurized Thermal
Plan Shock (Perform in Simulator)
JPM #161-2
Page 1 of 6
REV. 1
SEQUOYAH NUCLEAR PLANT
JPM # 161-2
Calculate Subcooling Margin
PREPARED1
REVISED B Y Date/
VALIDATED B Y * Date/
APPROVED B Y Date/
(Operations Training Manager)
CONCURRED ** Date/
(Operations Representative)
- Validation not required for minor enhancements, procedure Rev changes that do not affect the
JPM, or individual step changes that do not affect the flow of the JPM.
not driven by a procedure revision).
JPM #161-2
Page 2 of 6
REV. 1
NUCLEAR TRAINING
REVlSlONlUSAGE LOG
I
DATE PAGES PREPARED1
.EVISION DESCRIPTION OF
IUMBER REVISION
Initial Issue 11130103
0
V - Specify if the JPM change will require another Validation (Y or N)
See cover sheet for criteria.
JPM#161-2
Page 3 of 6
REV. 1
SEQUOYAH NUCLEAR PLANT
ROISRO
Task
Calculate Subcooling with no Subcooling Monitors and NO Plant computers available.
J M A task # : (ROISRO)
KIA Ratings: 002K5.09 (3.71412)
002A1.04 (3.914.1)
Performer:
NAME Start Time
Performance Rating : SAT -UNSAT __ Performance Time - Finish Time
Evaluator: I
SIGNATURE DATE
COMMENTS
JPM#161-2
Page 4 of 6
REV. 1
SPECIAL INSTRUCTIONS TO EVALUATOR
1. Critical steps identified by an asterisk (*)
2. Sequenced steps identified by an "s"
3. Any requires comments
4. Initialize the simulator in IC-92. Trip the Re :tor. and FREEZE th simulator when RCS
-
pressure is -2050 psig and RCS HL temperature is 547°F (if necessary open PZR spray
valve to lower pressure). Place covers over the Saturation Monitor Displays.
5. Supply Examinee with a Steam Table and hand held calculator.
Validation Time: CR. 15 mins Local
ToolslEquipmenVProceduresNeeded:
READ TO OPERATOR
Directions to Trainee:
I will explain the initial conditions, and state the task to be performed. All steps shall be simulated for
this JPM. 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. Ensure you
indicate to me when you understand your assigned task. To indicate that you have completed your
assigned task return the handout sheet Iprovided you.
INITIAL CONDITIONS
The Unit has tripped from 100% power and all system have responded normally.
The ICs computers and Saturation Monitor Displays were out of service just before the trip and have not
been returned to service.
INITIATING CUES:
You are the Unit 1 RO and the US has directed you to determine the amount of Subcooling in the RCS if
any. Report your findings to the US when your calculations are complete.
JPM # I 6 1 2
Page 5 of 6
REV. 1
Job Performance Checklist:
STEPISTANDARD SATIUNSAT
STEP 1.: Operator obtains a copy of Steam Tables and a Hand held
calculator.
-SAT
UNSAT
-
I
NOTE: Calculator and Steam Tables are located on Simulator Desk.
Start Time-
NOTE: If JPM is performed in the Main Control Room, the examiner
should provide a Calculator and Steam Tables.
STANDARD: Operator locates Steam Tables and a Hand held calculator
STEP 2.: Obtain RCS Hot Leg Temperature -SAT
Cue:
-UNSAT
If JPM is performed in the Main Control Room, Examiner will
give the examinee a temperature of 547°F.
Critical Step
STANDARD: Operator observes RCS Hot Leg Temperature Indicators marked
as PAM and determines HL Temperature is approximately 547
degrees F. (I-TI-68-1, I-TI-68-24, 1-Tl-6843, 1-Tl-68-65)
STEP 3.: Obtain RCS Pressure. -SAT
Cue: If JPM is performed in the Main Control Room, Examiner will -UNSAT
-
give the examinee a pressure of 2025 2075 psig.
STANDARD: Operator observes RCS Pressure Indicators marked as PAM and Critical Step
-
determines RCS Pressure is approximately 2025 2075 psig. (1-
PI-68-66A, 1-P1-68-62, 1-Pl-68-69) (2040 - 2090 psia)
STEP 4.: Determine Saturation Temperature for RCS Pressure of 2050 -SAT
psig (2035 psia).
-UNSAT
STANDARD: MCR calculation: Operator refers to Steam Tables and Critical Step
determines Saturation temperature for 2025 - 2075 psig is
-
approximately 639 642 degrees.
Simulator Calculation: May be different based on simulator RCS
pressure and temperature. (2025psig = 2040 psia, 2075 psig =
2090psia)
JPM #161-2
Page 6 of 6
REV. 1
Job Performance Checklist:
STEPISTANDARD SAT/UNSAT
I I
STEP 5.: Determine subcooling margin for given parameters
NOTE: -
Subcooling calculation results in 93.5 degrees F
subcooled. (92 to 95 degrees will be acceptable if no cues
for temperature orpressure are given by the examiner.)
Critical Step
STANDARD: Operator determines subcooling is approximately 93.5 degrees F.
based on calculation from given information. Stop Time-
I I
End of JPM
JPM # 17
Page 1 of 8
Rev. 6
SEQUOYAH NUCLEAR PLANT
JPM # 17
Determine if SI Termination
Criteria is Met
Original Signatures on File
PREPARED1
REVISED BY: Datel
VALIDATED BY: * Datel
APPROVED BY: Datel
(Operations Training Manager)
CONCURRED: ** Datel
(Operations Representative)
- Validation not required for minor enhancements, procedure Rev changes that
do not affect the JPM, or individual step changes that do not affect the flow of
the JPM.
- Operations Concurrence required for new JPMs and changes that affect the
flow of the JPM (if not driven by a procedure revision).
JPM # 17
Page 2 of 8
Rev. 6
NUCLEAR TRAINING
REVlSlONlUSAGE LOG
REVISION DESCRIPTION OF V DATE PAGES PREPARED/
NUMBER REVISION AFFECTED REVISED B Y
2 rransfer from WP. E-0 Rev change. N 9110194 HJ Birch
3 5-0 Rev- rearrange two steps N 10127194 HJ Birch
4 ncorporate Rev B changes. N 9/12/95 HJ Birch
penlink :hgd performance time based on N 11/15/95 HJ Birch
ralidation time. Added step to check
3/G level for tube integrity. Minor
mhancements.
5-0 Rev chg only. N 2/6/97 HJ Birch
5 5-0 revision had no impact. Revised N 811 1/98 JP Kearney
ask numbers and KIA ratings.
?eformattedcritical steps
penlink f-0 Rev chg only. N 9/23/99 SR Taylor
penlink f-0 Rev 22 some minor changes in N 09/05/01 WR Ramsey
wording.
6 ncorporated penlink changes N 8/22/02 J P Kearney
Penlink E-0 Rev chg only N 02/12/03 G.S. Poteet
V - Specify if the JPM change will require another Validation (Y or N).
See cover sheet for criteria.
JPM # 17
Page 3 of 8
Rev. 6
SEQUOYAHNUCLEARPLANT
ROISRO
Task:
Determine If SI Termination Criteria Is Met
JA/TA Task # :
0060150101 (RO)
0060150102 3410410302 (SRO)
WA Ratings:
009EK3.24 (4.1/4.6)
Task Standard:
Determine when SI Termination criteria is completely satisfied.
Evaluation Method : Simulator X In-Plant
Performer:
NAME Start Time
Performance Rating : SAT -UNSAT ~ Performance Time ~ Finish Time
Evaluator: I
SIGNATURE DATE
COMMENTS
JPM # 17
Page 4 of 8
Rev. 6
SPECIAL INSTRUCTIONSTO EVALUATOR
1. Seauenced stem identified by an "s"
Reference Title I RevNo.
READ TO OPERATOR
Directions to Trainee:
I will explain the initial conditions, and state the task to be performed. 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. Ensure you indicate to me when you
understand your assigned task. To indicate that you have completed your assigned task return
the handout sheet Iprovided you.
INITIAL CONDITIONS:
Unit 1 was operating at 100% power when it experienced a reactor trip and safety injection. All
equipment operated as expected.
INITIATfNG CUES:
The actions of E-0 have been completed through step #14.
You are the Unit 1 OATC and are to start at Step 15 and determine if SI Termination criteria has
been met.
Inform the Unit SRO when you have made your determination.
JPM # 17
Page 5 of 8
Rev. 6
Job Performance Checklist:
STEPISTANDARD SAT/UNSAT
STEP 1.: Operator obtains appropriate procedure. -SAT
-UNSAT
NOTE: The first 14 steps have been completed as stated in the Initiating
Cues. Start Time-
STANDARD: Operator obtains a copy of E-0 and continues actions at step #15.
STEP 2.. MONITOR RCS temperatures: T-avg stable at or trending to between -SAT
547°F and 552OF.
-UNSAT
-
Cue: If T-avg is outside this band, cue that T-avg is 54gCF
STANDARD: Operator checks T-avg indicators TI-68-2E, 25E, 44E, 67E and ensures
T-avg is trending to between 547OF and 552OF.
STEP 3.: DISPATCH personnel to perform EA-0-1, -SAT
-UNSAT
-
Cue: The CRO will perform this EA.
STANDARD: Operator dispatches someone to perform EA-0-1.
STEP 4.: CHECK Pzr PORVs CLOSED. -SAT
-UNSAT
STANDARD: Operator checks PCV-68-340A &334A closed, green light on respective
handswitches ON.
STEP 5.: CHECK Pzr Safety Valves CLOSED. -SAT
-UNSAT
STANDARD: Operator checks acoustic monitor XX-68-363 has no lights illuminated
(XE-68-363,-364,-365), and/or tail pipe temperatures reading normal
(TI-68-328,-329,-330).
JPM # 17
Page 6 of 8
Rev. 6
Job Performance Checklist:
STEPISTANDARD SAT/UNSAT
STEP 6.: CHECK Normal spray valves CLOSED. -SAT
-UNSAT
STANDARD: Operator checks FCV-68-340B & 340D closed red lights above controllers
are OFF. IF pressure is > 2260, operator verifies trending down and
leaves sprays in auto, open. (verifies bulbs are not bad by depressing test
switches).
STEP 7.: CHECK Power to at least one block valve AVAILABLE. -SAT
-UNSAT
STANDARD: Operator checks HS-68-332A & 333A for power on indicating lights.
STEP 8.: CHECK At least one block valve OPEN. -SAT
-UNSAT
STANDARD: Operator checks HS-68-332A or 333A for RED indicating light LIT on at
least one block valve.
STEP 9.: MONITOR RCP trip criteria: -SAT
-UNSAT
STANDARD: Operator checks, RCS pressure > 1250 psig. Utilizes RNO to go to next
step and not trip RCPs.
STEP 10.: CHECK if S/G secondary pressures boundary are INTACT: -SAT
-UNSAT
STANDARD: Operator checks all pressures controlled or rising (and greater than 140
psig) PI-l-2A, 28, 9A, 9B, 20A, 208,27A, 278.
STEP 11.: CHECK if SIG tubes are INTACT: CHECK all S/G narrow range levels -SAT
controlled or dropping.
-UNSAT
STANDARD: Operator checks S/G levels controlled or dropping
LI-3-43A, 56A, 98A, 111A
JPM # 17
Page 7 of 8
Rev. 6
Job Performance Checklist:
STEPISTANDARD SATIUNSAT
STEP 12.: CHECK the following Rad monitors, including available trends prior to -SAT
isolation: [on listed instruments]
-UNSAT
-
Cue: When operator addresses recorders, cue them that no increasing
trend is evident.
STANDARD: Operator checks the following parameters:
Steam line Rad monitors Rl-90-421,422,423,424, normal -
Condenser exhaust monitors RR-90-119-
S/G BD monitors RR-90-120 (no chg prior to isol).-
Post Accident Main Steam Line Radiation Recorder RR-90-2688, points
3, 4, 5, 6 Normal -
STEP 13.: CHECK if RCS is INTACT: [Verify listed instruments normal] -SAT
-UNSAT
-
Cue: When operator addresses recorders, cue them that no increasing
trend is evident.
STANDARD: Operator checks the following parameters NORMAL:
CNTMT Pressure PDI-30-45 & 44 -
CNTMT Sump level LI-63-176, 177, 178, 179 -
Lwr Cntmt Temp alarm XA-55-5C wind #8 (B-1) DARK -
Upper Cntmt hi range RM-90-271 & 272 NORMAL [M-30]-
Lwr Cntmt hi range RM-90-273 & 274 NORMAL [M-30]-
Radiation RR-90-106 & I 12 normal prior to Is01 -
STEP 11: DETERMINE of ECCS flow should be reduced.
STANDARD: The next few steps will perform the actions of this procedural step.
STEP 14.: CHECK RCS subcooling based on core exit T/Cs greater than 40°F. -SAT
-UNSAT
STANDARD: Operator determines RCS subcooling is > 40°F [Exo Sensors or P-250
trend recorder] - Critical Step
JPM # 17
Page 8 of 8
Rev. 6
Job Performance Checklist:
STEPISTANDARD SAT/U NSAT
STEP 15.: CHECK secondary heat sink: -SAT
Narrow range level in at least one S/G greater than 10% OR
Total feed flow to S/Gs greater than 440 gpm. -UNSAT
STANDARD: Operator checks Secondary heat sink: Critical Step
At least one (1) S/G Narrow Range level > 10% [Ll-3-42,-39,-55, -52,-
97,-94,-110,-107]__
Total AFW flow 2 440 gpm [FI-3-163A,-155A,-147A,-170A] -
STEP 16.: CHECK RCS pressure stable or rising. -SAT
-UNSAT
STANDARD: Operator checks RCS pressure stable or rising [Exo Sensors, PR-68-69
(for trend only), or PI-68-66A, -62,-69]-
Critical Step
STEP 17.: CHECK pressurizer level greater than 10%. -SAT
-UNSAT
STANDARD: Operator checks Pzr level > 10% [LI-68-335A or 320A, LR-68-3391-
Critical Step
STEP 18.: MONITOR status trees and GO TO ES-I . I , -SAT
-UNSAT
-
Cue: STA will monitor status trees.
STANDARD: Operator determines that all SI Termination criteria was met and is now
able to transition to ES-1.I to terminate SI.
STEP 19.: Inform the US/SRO when all termination criteria have been met. -SAT
-UNSAT
STANDARD: Operator informs the US/SRO when all SI Termination criteria has been
satisfied. Stop Time-
JPM # 22
Page 1 of 10
Rev. 7
SEQUOYAH NUCLEAR PLANT
JPM # 22
CALIBRATE POWER RANGE NUCLEAR
INSTR UMENTATl0N
Original Signatures on File
PREPARED1
REVISED BY: Datel
VALIDATED BY: * Datel
APPROVED BY: Datel
(Operations Training Manager)
CONCURRED: Datel
(Operations Representative)
- Validation not required for minor enhancements, procedure Rev changes that
do not affect the JPM, or individual step changes that do not affect the flow of
the JPM.
- Operations Concurrence required for new JPMs and changes that affect the
flow of the JPM (if not driven by a procedure revision).
JPM # 22
Page 2 of 10
Rev. 7
NUCLEAR TRAINING
REVlSlONlUSAGE LOG
-
REVISION DESCRIPTION OF V DATE PAGES PREPARED1
NUMBER REVISION - AFFECTED REVISED BY:
3 Transfer from WP. Minor enhancements. N 8116/94 All HJ Birch
4 JPM enhancements Y 11/2/94 All HJ Birch
5 4dded sign dates to cover page and broke Y 10/2/95 All HJ Birch
jown several large steps into separate
JPM steps. SI-78 Rev change added
several steps that did not change the JPM
Jerformance.
penlink 3-78 Rev Chg: Chgd P-250 to Plant N 6/8/96 4-10 HJ Birch
Zomputer. Added step if NIS inop
penlink Jpdate SI-78 Rev. Chgd wording in N 9116/96 4-1 1 HJ Birch
several steps to match new Rev. Chgd
Jrocedure step numbers in JPM
6 ncorp above penlinks. SI-78 Rev. Deleted Y 5/22/97 ALL HJ Birch
sections and change performance flow in
xocedure. Made step 18 critical
3-78 Rev chg only N 8112/97 4 HJ Birch
7 3evised per recent revisions to O-SI-OPS- N 8119/02 All J P Kearney
192-078.0; No impact on JPM flow
-
V - Specify if the JPM change will require another Validation (Y or N).
See cover sheet for criteria.
JPM # 22
Page 3 of 10
Rev. 7
SEQUOYAHNUCLEARPLANT
ROISRO
Task
Calibrate the Power Range Nuclear Instrumentation
JPJTA t a s k
- 0150050201 (RO)
WA Ratings:
015000 A I .01 (3.5 - 3.8) 015020 G9 (3.4 - 3.3)
-
015020 G13 (3.3 3.6) 015000 A4.02 (3.9 - 3.9)
Task Standard:
1) Each channel of Power Range instrumentation (on its power range " A drawer) will indicate
within acceptance criteria tolerances of the calorimetric.
2) The unit is not tripped by a power range neutron flux rate trip.
Evaluation Method : Simulator X In-Plant
Performer:
NAME Start Time
Performance Rating : SAT ~ UNSAT ~ Performance Time ~ Finish Time
Evaluator: I
SIGNATURE DATE
COMMENTS
JPM # 22
Page 4 of 10
Rev. 7
1, 0-SI-OPS-092-078.0 Power Range Neutron Flux Channel Calibration By 15
Heat Balance Comparison
Directions to Trainee:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be
performed for this JPM. 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.
Ensure you indicate to me when you understand your assigned task. To indicate that you have completed
your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
1. The unit is at steadv state conditions with all NIS channel operable.
2. ICs and the LEFM i r e not available. TRM 3.3.3.15 have been entered. A WR has been initiated.
INITIATING CUES:
1. You are the CRO and the US has directed you to perform 0-SI-OPS-092
2. Notify the US when the SI has been completed and any necessary adjustments have been
made.
JPM # 22
Page 5 of 10
Rev. 7
Job Performance Checklist
STEPISTANDARD SATIUNSAT
STEP 1.: Obtain the appropriate procedure. -SAT
-UNSAT
STANDARD: Operator identifies 0-SI-OPS-092-078.0 and goes to section 6.0
"Performance". Start Time-
STEP 2.: VERIFY availability of LEFM calorimetric power... -SAT
Cue: Per initial conditions, LEFM calorimetric power unavailable. -UNSAT
STANDARD: Operator annotates procedure that LEFM calorimetric power is
unavailable.
STEP 3.: IF LEFM calorimetric power NOT available OR ICs computer NOT -SAT
available, THEN
PERFORM the following:
-UNSAT
[a] ENTER applicable action of TRM 3.3.3.15.
[b] ENSURE work order initiated as required.
[c] IF LEFM calorimetric power CANNOT be restored in time to
complete this surveillance, THEN PERFORM the following:
1. REDUCE reactor power to 98.7% (3411 MWt) or less USING
U1118 (if available) or NIS.
2. WHEN reactor power is less than 98.7%, THEN CONTINUE this
instruction using alternate power indications as specified below.
Cue: Per initial conditions, ICs and LEFM calorimetric power unavailable,
TRM has been entered, and a WR has been issued..
STANDARD: Operator verifies power is less than 98.7 using NIS.
-4.: DETERMINE reactor core power level by performing the applicable -SAT
appendix below.
-UNSAT
STANDARD: Operator goes to Appendix D.
JPM # 22
Page 6 of 10
Rev. 7
Job Performance Checklist
STEPISTANDARD SATIUNSAT
NOTE: The following step is from Appendix D. -SAT
STEP 5.: IF 0-PI-SXX-000-022.0will be used for calorimetric data, THEN -UNSAT
PERFORM the following:
[a] NOTIFY Systems Engineering to perform manual calorimetric
calculation using 0-PI-SXX-000-022.0.
[b] MARK remaining steps '"/A" in this appendix.
Cue: Systems Engineering indicates that a calorimetric has been
performed and Reactor Thermal Power is 58%.
STANDARD: Operator notifies Systems Engineering.
NOTE: The following steps are from Section 6.1. -SAT
STEP 6.: RECORD below (N/A power if using printout from ICs): -UNSAT
% Rated Core Thermal Power
STANDARD: Operator Records Reactor power given by Systems Engineering.
STEP 7.: RECORD "AS FOUND" power level from each of the four NIS A Channel -SAT
drawers.
-UNSAT
STANDARD: Operator records NIS power range readings from the A channel drawers.
STEP 8.: COMPARISON of NIS indication with core thermal power level. -SAT
CHECK appropriate box to indicate whether the following "as-found -UNSAT
ACCEPTANCE CRITERIA were satisfied.
Critical Step
NOTE: During simulator set up N41 was manually adjusted t o read 55% and
N43 was adjusted to read 61%.
STANDARD: Operator CHECKS to determine if NIS channels are within & 2%. Checks
NO for NIS 41 & NIS 43, Checks YES for NIS 42, & NIS 44
JPM # 22
Page7of 10
Rev. 7
Job Performance Checklist
STEPISTANDARD SATIUNSAT
STEP 9.: IF any NIS channels were inoperable during the performance of this -SAT
Instruction, THEN:
-UNSAT
STANDARD: Since all were operable per the initiating conditions, the operator should
N/A this step.
STEP 10.: VERIFY that all NIS channel indicationsare within 3 % of the -SAT
determined core thermal power level.
-UNSAT
-
Cue: Depending on instrument errors the operator may determine that
one or more channels exceed 3 percent.
STANDARD: Operator checks the appropriate box
STEP 11.: IF a NIS channel was more than 3 percent in error in the non- -SAT
conservative direction (core thermal > NIS) THEN ...
-UNSAT
Cue: If the operator selected YES in the previous step, Play SRO and
inform them that you will make the appropriate notifications.
STANDARD: Operator addresses this step as needed
STEP 12.: CHECK appropriate box to indicate whether the following "as-found -SAT
acceptance criteria were satisfied. The indicated NIS power level
recorded in step [2] is less than or equal to 100.5 percent -UNSAT
STANDARD: The operator checks YES for all channels
STEP 13.: IF any channel does not meet acceptance criteria, THEN.PERFORM -SAT
adjustment of section 6.2.
-UNSAT
STANDARD: Operator goes to section 6.2 to make adjustments.
JPM # 22
Page 8 of 10
Rev. 7
Job Performance Checklist
STEPISTANDARD SATIUNSAT
NOTE: The following steps are from section 6.2 NIS Channel Adjustment. -SAT
STEP 14.: IF calculated average power in Section 6.1 .... and average RCS delta T -UNSAT
differ by more than approximately 3% THEN ...
-
Cue: Depending on instrument errors the operator may have determined
that one or more channels exceed 3 percent. IF asked state
notification has been made.
STANDARD: Operator N/As this step or ensures notifications were made.
~
STEP 15.: VERJFY reactor power has remained constant (+ 0.5%) since -SAT
performance of section 6.2.
-UNSAT
STANDARD: Operator ensures power has remained stable since he/she took the
readings.
STEP 16.: IF NIS power range channel is inoperable THEN.... -SAT
-UNSAT
STANDARD: Operator N/As this step since all are operable.
STEP 17.: ENSURE all NIS power range channels are operable or bypassed with no -SAT
bistables tripped.
-UNSAT
STANDARD: Operator verifies no bistables tripped. (Initial conditions had all channels
STEP 18.: ENSURE rod control system is in MANUAL in accordance with 0-SO-85-1 -SAT
-UNSAT
STANDARD: Operator turns 1-15-85-5110 to the MANUAL position.
Critical Step
JPM # 22
Page 9 of 10
Rev. 7
Job Performance Checklist
STEPISTANDARD SATIUNSAT
I
STEP 19.: IF rate trip exists (or occurs) on the NIS channel being calibrated, THEN -SAT
CLEAR that channel's trip signal (momentarily set RATE MODE switch to
RESET position) and annunciator XA-55-6A. -UNSAT
-
Cue: For this step and the following steps, inform the operator that "for
JPM purposes the CV is not required.
STANDARD: Operator verifies NO rate trip signals are in on ANY of the PR and the
annunciator is clear. * CRITICAL PORTION: If rate trip occurs helshe Critical Step
resets it prior to continuing to the next channel.
STEP 20.: ADJUST gain potentiometer on associated channel's power range B -SAT
drawer to bring that channel's indicated power level to within 2.5% of the
calorimetric power recorded in section 6.2, step [I]. -UNSAT
-
NOTE: The step on adjusting coarse adjust was omitted from JPM.
STANDARD : Operator must adjust N41 and N43 to satisfy criteria. The operator should
repeat the above step prior to adjusting the second PR. Critical Step
STEP 21.: WHEN NIS adjustments have been completed, THEN, RECORD the "as -SAT
left' power level from NIS power range channels.
-UNSAT
STANDARD: Operator records the readings from each PR NI; N 1 4 1 3 , N 1 4 2 3 ,
N1433, N1443.
STEP 22.: IF NIS power range channel is inoperable THEN.... -SAT
-UNSAT
STANDARD: Operator N/As this step since all are operable.
STEP 23.: CHECK appropriate box to indicate whether the following "as left" -SAT
acceptance criteria were satisfied.
-UNSAT
STANDARD: Operator checks YES box for N41, N42, N43, & N44, all being within
+ .5% (of 58%).
-
JPM # 22
Page 10 of 10
Rev. 7
Job Performance Checklist
STEPISTANDARD SATIUNSAT
I I
I STEP24.: IF acceptance criteria were NOT satisfied..... I - SAT
-UNSAT
STANDARD: Operator N/As this step.
STEP 25.: RETURN rod control system to AUTO in accordance with 0-50-85-1. -SAT
-UNSAT
STANDARD: Operator places control rod bank selector switch to the AUTO
STEP 26.: Notify SRO that the NIS channels have been calibrated. -SA7
-UNSAT
STANDARD: Operator notifies the SRO that the SI has been completed and all power
range nuclear instruments have been adjusted to meet the acceptance Stop Time-
criteria.
JPM #165-2
Page 1 of 6
Rev. 0
SEQUOYAHNUCLEARPLANT
JPM # 165-2
Perform A Shielding Calculation
PREPARED1
REVISED BY: Datel
VALIDATED BY: Datel
APPROVED BY: Datel
(Operations Training Manager)
CONCURRED: *I Datel
(Operations Representative)
- Validation not required for minor enhancements, procedure Rev changes that do not
affect the JPM, or individual step changes that do not affect the flow of the JPM.
- Operations Concurrence required for new JPMs and changes that affect the flow of
the JPM (if not driven by a procedure revision).
JPM #I652
Page 2 of 6
Rev. 0
NUCLEAR TRAINING
REVlSlONlUSAGE LOG
I I
3EVISION
NUMBER
0 I Initial Issue
DESCRIPTION OF
REVISION
IvN
PAGES
AFFECTE
PREPARED/
REVISED BY:
V Specify if the JPM change will require another Validation (Y or N).
~
See cover sheet for criteria.
JPM #165-2
Page 3 of 6
Rev. 0
SEQUOYAHNUCLEARPLANT
RO/SRO
JOBPERFORMANCEMEASURE
Task:
Perform a Shielding Calculation
JA/TA task # : 3430290302 (RO)
WA Ratings: 2.3.2 (2.5/2.9) 2.3.10 (2.9/3.3)
Task Standard:
The examinee will determine the Tenth value layer and the Half value layer of shielding required
for adequate protection of a worker.
Evaluation Method : Simulator X In-Piant
Performer:
NAME Start Time
Performance Rating : SAT -UNSAT - Performance Time - Finish Time
Evaluator: I
SIGNATURE DATE
COMMENTS
JPM #165-2
Page 4 of 6
Rev. 0
SPECIAL INSTRUCTIONS TO EVALUATOR:
1. Sequenced steps identified by an "s"
2. Any UNSAT requires comments
3. Initializethe simulator in IC-IO and leave in FREEZE. Simulator is NOT required to
complete this JPM.
4. Provide Operator with a calculator and equation sheet if required.
5. The simulator is not needed to complete this JPM.
Validation Time: CR. 15 mins Local
Tools/EquipmentlProceduresNeeded:
INITIAL CONDITIONS:
You have been directed to work in an area where the Gamma Radiation intensity is 10,000
RadlHr. with no shielding. You cannot work in the area unless the field is reduced to no greater
than 200 Rad/Hr.
INITIATING CUES:
You are to calculate the minimum number of half-value layers (HVLs) required to reduce the
Gamma level to no greater that 200 Rad/hr.
You are also to calculate the minimum number of tenth-value layers (TVLs) required to reduce the
Gamma level to no greater than 100 Rad/hr.
JPM 165-2
Page 5 of 6
Rev. 0
Job Performance Checklist:
STEPlSTANDARD SATlUNSAT
STEP 1.: Operator Understands the definition of HVL. That thickness of a -SAT
specified substance which, when introduced into the path of a given
beam of radiation, reduces the exposure rate to one-half of its original __ UNSAT
value. Operator determines the number of HVLs based on given
intensity of 10,000 Rad/hr. Start Time-
NOTE: 1 HVL 5000 Radfhr
2 HVL = 2500 Radfhr Critical Step
3 HVL = 1250 Radlhr
4 HVL = 625 Rad/hr
5 HVL = 312 Radfhr
6 HVL = 156 Radlhr
NOTE: Examinee may use intensity equation. If Examinee uses equation
then cue himlher that lead will be used as shielding and the p , the
total linear attenuation coefficient for lead is 0.772 cm-l
STANDARD: Operator determines 6 HVLs are required to reduce intensity to less than
200 Rad/hr.
-SAT
STEP 2.: Operator Understands the definition of TVL. That thickness of a
specified substance which, when introduced into the path of a given -UNSAT
beam of radiation, reduces the exposure rate to one-tenth of its original
value. Operator determines the number of TLVs based on given
intensity of 10,000 Rad/hr.
-
NOTE: 1 TVI = 1000 Radfhr Critical Step
2 TVL = 100 Radlhr
3 TVL = 10 Radlhr
NOTE: Examinee may use intensity equation. If Examinee uses equation Stop Time-
then cue himlher that lead will be used as shielding and the p ,
the total linear attenuation coefficient for lead is 0.772 cm-l
STANDARD: Operator determines 3 TVLs are required to reduce intensity to less
than 100 Rad/hr.
JPM 165-2
Page 6 of 6
Rev. 0
Job Performance Checklist:
STEPISTANDARD SATIUNSAT
THIS BLOCK FOR USE AND REFERENCE BY EXAMINER
Ishielded = I unshielded (1/2) #HVL(l/lO)#TVL
where #HVL = Shield Thickness (cm)
HVL (cm)
and #TVL = Shield Thickness (cm)
TVL (cm)
Shielding Equation
I =Ioe -w
Where:
I - the exposure rate with the shield (Radlhr)
Io the unshieided exposure rate (Radlhr)
x - the shield thickness (cm)
1.1 - the total linear attenuation coefficient (cm-I).
JPM 157
Page 1 of 12
Rev. 0
SEQUOYAHNUCLEARPLANT
JPM # 157
Monitor Status Trees - Pressurized Thermal Shock
PREPARED/
REVISED BY: Datel
VALIDATED BY: Datel
APPROVED BY: Date/
(OperationsTraining Manager)
CONCURRED: ** Datel
(Operations Representative)
- Validation not required for minor enhancements, procedure Rev changes that do not
affect the JPM, or individual step changes that do not affect the flow of the JPM.
- Operations Concurrence required for new JPMs and changes that affect the flow of
the JPM (if not driven by a procedure revision).
JPM 157
Page 2 of 12
Rev. 0
NUCLEAR TRAINING
REVlSlONlUSAGE LOG
REVISION DESCRIPTION OF V DATE PAGES PREPARED1
REVISION -
New JPM Y 2115/01
V - Specify if the JPM change will require another Validation (Y or N).
See cover sheet for criteria.
JPM 157
Page 3 of 12
Rev. 0
SEQUOYAHNUCLEARPLANT
ROISRO
Task: Monitor Status Trees and Identify Pressurized Thermal Shock Conditions
Requiring Implementation FR-P.l
JAlTA task # : 3110450601 (RO) 31 10460602 (SRO) 3520950305 (STA)
WA Ratings:
E14 EA2.1 (3.3/3.8) E08 EA2.1 (3.4/4.2)
Task Standard: Monitor Status Trees and identify Red Path to FR-P.1, Orange Path to FR-Z.1, and determine
that FR-P.l is the higher priority.
Evaluation Method : Simulator X In-Plant
Performer:
NAME Start time
Performance Rating : SAT __ UNSAT ~ Performance Time __ Finish time
Evaluator: I
SIGNATURE DATE
JPM 157
Page 4 of 12
Rev. 0
SPECIAL INSTRUCTIONS TO EVALUATOR:
1. Critical steps identified by the Words "Critical Step" in the SATNNSAT Column.
2. Sequenced steps identified by an "s"
3. Any UNSAT requires comments
4. Initialize Simulator to IC #85 or IC # 10 with steps 5 through 8.
5. Activate malfunction csOla (Containment spray Pump 1A Trip). Pull to lock and Tag
Containment Spray pump 1A-A.
6. Run simulator and Activate Malfunction thola @ 50% severity (LOCA Hot leg break Loop 1)
7. Continue to Run simulator and Control AFW as necessary with total flow greater than 440 gpm.
Stop all RCPs after Phase B.
8. Acknowledge alarms and place Simulator in Freeze when all the following conditions are met: SR
is re-instated, RVLlS lower range is >40%, at least one Tcold is less than 19I0F, all S/G NR levels
are <25%, SAT Margin is inadequate (<4OoF)on both exo-sensors, and both the SR and IR SUR
indications are zero or negative. The Simulator will remain in freeze during performance of
this JPM.
NOTE: SAT margin may fluctuate between adequate and inadequate, and Tcold may
fluctuate above and below 191". Also, the SR and IR indicators will be bouncing above
and below zero, therefore care must be taken when freezing the simulator for the exercise
to ensure all the conditions are met at the same time.
9. Insure operator performs the following required actions for SELF-CHECKING;
a. Identifies the correct unit, train, component, etc.
b. Reviews the intended action and expected response.
c. Compares the actual response to the expected response.
Validation Time: CR 8 min. Local
ToolsIEquipmentlProcedures Needed:
FR-0, Status Trees
REFERENCES:
Task Number Task Title Cont TRN
3110450601 Monitor Status Trees to ensure that the Critical Safety Functions are maintained Y
3110460602 Monitor Status Trees to ensure that the Critical Safety Functions are maintained Y
3520950305 Monitor status trees to ensure that the critical safetv functions are maintained Y
I (LICENSE PROGRAM)
JPM 157
Page 5 of 12
Rev. 0
READ TO OPERATOR
Directions to Trainee:
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. All steps shall be simulated for this task and
the simulator will remain in freeze during performance of this JPM. 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. To indicate that you have completed
your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
Approximately 15 minutes ago, Unit 1 was at 100% power with 1-AA Containment Spray Pump tagged out
of service when a LOCA occurred. E-0 has been completed and the Crew is currently in E-1.
INITIATING CUES:
You are an RO and have been assigned to monitor status trees. Monitor the Status trees for the current
conditions and inform the Unit Supervisor of the results.
JPM 157
Page 6 of 12
Rev. 1
Job Performance Checklist:
STEPISTANDARD SATIUNSAT
I- STEP 1: Perform the Subcriticality Status Tree (F-0.1) -SAT
-UNSAT
-
NOTE: The following steps are from performance of the
subcriticality Status Tree.
Start Time-
- 2- Power Range less than 5%. -SAT
-UNSAT
STANDARD: Operator checks power range less than 5% on 1-M-13 Power
Range Drawer Indicators (I-Xl-92-5005B,5006B, 50078, &
5008B) and determines Power Range is less than 5%.
- 3- Intermediate Range SUR Zero or Negative. -SAT
-
Cue: If simulator was not frozen with Zero or Negative SUR cue -UNSAT
that it is when checked.
STANDARD: Operator checks Intermediate Range SUR Zero or Negative
Using 1-M-13 Comparator and Rate Drawer (1-XX-92-5041)
Indicator with the Startup Rate Selector Switch to in both the N35
and N36 positions and determines it is Zero or Negative.
- 4- Source Range Reinstated. -SAT
-UNSAT
STANDARD: Operator checks Source Range Reinstated by observing 1-M-l3
Source Range indicators (1-XC92-5001B & 5002B) responses
and determines it is Reinstated.
Source Range SUR Zero or Negative -SAT
-
Cue: If simulator was not frozen with Zero or Negative SUR cue that it is -UNSAT
when checked.
STANDARD: Operator checks Source Range SUR Zero or Negative Using 1-
M-13 Comparator and Rate Drawer (1-XX-92-5041) Indicator with
the Startup Rate Selector Switch to in both the N31 and N32
positions and determines it is Zero or Negative.
JPM 157
Page 7 of 12
Rev. 1
Job Performance Checklist:
STEPETANDARD SAT/UNSAT
STEP: Perform the Core Cooling Status Tree (F-0.2) -SAT
-UNSAT
-
NOTE: The following steps are from performance of the Core
Cooling Status Tree.
STEP: Core Exit thermocouples less than 1200°F. -SAT
-UNSAT
NOTE: Operator must use the Exo Sensor Next I button to see
page 2 of some T/C quadrants. Quadrants 3 & 4 on 1-XI-94-
101 have 2 pages, Quadrants 1 & 2 on 1-XI-94-102 have 2
pages
STANDARD: Operator Checks thermocouples in all quadrants Exo sensors (1-
XI-94-101 & 102) on 1- M-4 using the Quad buttons to determine
if 5 T/Cs have exceeded 120OoFas follows: One T/C near the
core center and the hottest T/C in each quadrant (this can be
verified by ensuring no T/Cs are above the limit without identifying
a specific T/C near the core center). The Operator should
determine that the limit has not been exceeded.
STEP: RCS Subcooling Based on Core Exit T/C greater than 4OoF. -SAT
-UNSAT
STANDARD: Operator Checks Subcooling on both Exo sensor Margin
Displays (1-XI-94-101 & 102) on 1-M-4 to determine if subcooling
is greater than 4OoF. The Operator should determine that
subcooling is less than 4OoF.
- 9- At least one RCP running. -SAT
-UNSAT
STANDARD: Operator Checks RCPs Running and determines that No RCPs
are running.
JPM 157
Page 8 of 12
Rev. 1
Job Performance Checklist:
STEPETANDARD SAT/UNSAT
STEP 10: Core Exit T/Cs Less than 700'F -SAT
-UNSAT
-
NOTE: Operator must use the Exo Sensor "Next " button to see
page 2 of some T/C quadrants. Quadrants 3 & 4 on 1-XI-94-
101 have 2 pages, Quadrants 1 & 2 on 1-XI-94-102 have 2
pages
STANDARD: Operator Checks thermocouples in all quadrants Exo sensors (1-
-
XI-94-1 01 & 102) on 1 M-4 using the Quad buttons to determine
if 5 T/Cs have exceeded 700'F as follows: One T/C near the
core center and the hottest T/C in each quadrant (this can be
verified by ensuring no T/Cs are above the limit without identifying
a specific T/C near the core center). The Operator should
determine that the limit has not been exceeded.
STEP 11: RVLlS Lower Range Greater than 40%. -SAT
-UNSAT
STANDARD: Operator Checks both PAM RVLlS Lower Range Channels (I-LI-
68-368 & 371) on 1-M-4. Operator should determine RVLIS is
greater than 40% and notes that a yellow Dath to FR-C.3 exists
STEP 12: Perform the Heat Sink Status Tree (F-0.3) -SAT
-UNSAT
_NOTE: The following steps are from performance of the Heat Sink
Status Tree.
STEP 13: Narrow range level in at least one S/G greater than 10% [25% -SAT
ADV].
-UNSAT
-
NOTE: Adverse Setpoint will be required.
STANDARD: Operator Checks S/G Narrow Range level on all PAM S/G NR
level instruments on 1-M-4 and determines at least one S/G does
not yet have adequate level (25% NR). (i.e. all S/G are less than
25%)
JPM 157
Page 9 of 12
Rev. 1
Job Performance Checklist:
STEPISTANDARD SATIUNSAT
STEP 14: Total Feedwater flow to S/Gs greater than 440 GPM -SAT
-UNSAT
STANDARD: Operator Checks PAM AFW Flow instruments on 1-M-4 and
determines that total flow to SGs is greater than 440 gprn
STEP 15: Pressure in All S/Gs less than 1117 psig -SAT
-UNSAT
STANDARD: Operator Checks S/G Pressure on all PAM S/G Pressure
instruments on 1-M-4 and determines all S/Gs are less than 1117
psig.
STEP 16: Narrow Range level in all S/Gs less than 81%. -SAT
-UNSAT
STANDARD: Operator Checks S/G Narrow Range level on all PAM S/G NR
Level instruments on 1-M-4 and determines that all S/G levels are
less than 81%.
STEP 17: Pressure in All S/Gs less than 1064 psig. -SAT
-UNSAT
STANDARD: Operator Checks S/G Pressure on all S/G PAM Pressure
instruments on 1-M-4 and determines all S/Gs are less than 1064
psig.
STEP 18: Narrow Range level in all S/Gs greater than 10% 125% ADV]. -SAT
-UNSAT
-
NOTE: Adverse Setpoint will be required.
STANDARD: Operator Checks S/G Narrow Range level on all PAM S/G NR
level instruments on 1-M-4 and determines that all S/G levels are
not yet greater than 25% and notes that a yellow uath to FR-H.5
exists.
JPM 157
Page 10 of 12
Rev. 1
Job Performance Checklist:
STEPISTANDARD SATIUNSAT
STEP 19: Perform the Pressurized Thermal Shock Status Tree (F-0.4) -SAT
-UNSAT
-
NOTE: The following steps are from performance of the Pressurized
Thermal Shock Status Tree.
STEP 20: All T-Colds dropped less than 100°F in the last 60 minutes. -SAT
-UNSAT
STANDARD: Operator Checks all RCS PAM T-Cold instruments on 1-M-5 (1.
Tl-68-18,41,60, and 83) and determines that All T-Colds have
not dropped less than 1OO'F in the last 60 minutes. (Le. Any T-
Cold has exceeded the Cooldown limit)
STEP 21: All RCS Pressure Vs T-Cold points to the right of limit A on Curve -SAT
3.
-UNSAT
_NOTE: Operator should report RED path to the SRO at this time, if
so, acknowledge the report and Cue them to
continuelcomplete monitoring of the status trees for any
other conditions.
STANDARD: Operator should use the RCS PAM T-Cold on 1-M-5 (1-TI- Critical Step
68-18, 41, 60, and 83) and highest RCS pressure reading from
Exo sensors or PAM pressure instruments on 1-M-6 (1-PI-68-
66A, 62,& 69) to determine that Limit A has been exceeded on
curve 3 and identifies that an RED Path exists to FR-P.1
STEP 22: Perform the Containment Status Tree (F-0.5) -SAT
-UNSAT
-
NOTE: The following steps are from performance of the
Containment Status Tree.
STEP 23: Containment Pressure Less than 12.0 PSID. -SAT
-UNSAT
STANDARD: Operator Checks PAM Containment pressure instruments on 1-
M-6 (1-PDI-30-45 & 44) and determines that Containment
Pressure is Less than 12.0 PSID.
JPM 157
Page 11 of 12
Rev. 1
Job Performance Checklist:
STEPISTANDARD SATIUNSAT
STEP 24: Containment Pressure Less than 2.81 PSID. -SAT
-UNSAT
STANDARD: Operator Checks PAM Containment pressure instruments on 1-
M-6 (1-PDI-30-45 & 44) and determines that Containment
Pressure is not Less than 2.81 PSID. And Identifies an Oranae Critical Step
Path to FR-2.1 Exixts.
STEP 25: Perform the Inventory Status Tree (F-0.6) -SAT
-UNSAT
-
NOTE: The following steps are from performance of the Inventory
Status Tree.
STEP 26: Pressurizer Level Less than 92% -SAT
-UNSAT
STANDARD: Operator Checks PAM Pressurizer level instruments on 1-M-4 (1-
PI-68-333A, 335A, & 320) and determines that Pressurizer Level
is Less than 92%.
STEP 27: Pressurizer Level Greater than 17%. -SAT
-UNSAT
STANDARD: Operator Checks PAM Pressurizer level instruments on 1-M-4 (1-
PI-68-333A, 335A, & 320) and determines that Pressurizer Level
is not Greater than 17% and notes that a yellow uath to FR-I .2
exists.
JPM 157
Page 12of 12
Rev. 1
Job Performance Checklist:
STEPETANDARD SATNNSAT
STEP 28: Inform the Unit 1 Unit Supervisor that status trees have been -SAT
monitored and that a RED Paths exist on PTS (to FR-P.1) and an
Orange Path exists on Containment (to FR-Z.1) Status trees -UNSAT
requiring transition to FR-P.I .
Stop Time-
-
Cue: UWSRO acknowledges the report.
Critical Step
-
NOTE: Operator may also report Yellow paths on Heat sink (FR-H.5),
Core Cooling (FR-C.3), and Inventory (FR-1.2) status trees.
Reporting the yellow paths to the US/SRO is optional.
STANDARD: Operator Inform the Unit 1 Unit Supervisor that status trees have
been monitored and that a RED Paths exist on PTS (to FR-P.1)
and an Orange Path exists on Containment (to FR-Z.l) Status
trees requiring transition to FR-P.1.