ML033421057
| ML033421057 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna |
| Issue date: | 08/01/2003 |
| From: | Roush K Susquehanna |
| To: | Conte R NRC/RGN-I/DRS/OSB |
| Conte R | |
| References | |
| 50-387/OL-03-301, 50-388/OL-03-301 | |
| Download: ML033421057 (138) | |
Text
ES-30 I Control Room/ln-Plant Systems Outline Form ES-301-2 Facility:
Susquehanna Date of Examination: 8111-8/15 2003
- a. 215005 A2.02 3.613.7 Bypass an APRM Channel Trip Input Exam Level (circle one): RO Operating Test No.:
D, s 7
~~
Control Room Systems (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U)
- b. 264000 A2.01 3.513.6 Start D/G for surveillance Venting Suppression Chamber within off-site release limits - ES-173-001, Section 4.2, Vent Suppression Chamber using two inch vent bypass to SGTS.73.EO.001.IO1 RESET Recirc Pump Limiter #2 Runback in accordance with ON-I 64-002
- c. 223001 A2.07 (4.214.3)
- d. 202002 A2.05 (3.814.0)
System / JPM Title N, A, s 6
D, s, E 5
s, A 4
Type Safety 1
Code*
1 Function
- f. 202001 A2.10 3.5/3.9 Respond To A Reactor Recirc Pump Dual Seal Failure IAW ON-I 64-003
- g. 209001 A2.01 3.813.7
- h. 239001 A4.01 (4.2/4.0)
Perform Manual S/U of Core Spray IAW OP-151-001 Main Steam Line Isolation and Quick Recovery in Accordance with ON-181 -001 D, S, E/A, L 1
D, A, s, 2
E/A, E D, s 3
- e. 290003 A3.013.313.5 I
N S, A I 9
Complete Monthly Control Room Emergency Outside Air Supply System OperabiliW Test (I)
In-Plant Systems (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)
- i. 262001 K4.04 2.813.1 Perform Monthly Surveillance of 4KV Bus Undervoltage Relays Perform manual operation of the SRVs Valves from the Remote Shutdown Panel as required by ON-I 00-00900.ON.015.103
- j. 29501 6 AA1.08 (4.0/4.0)
- k. 217000 A2.01 3.8/3.7 Bypass of All RClC Isolation Signals in Accordance With ES-150-001 D, R, E/A, A
6 7
4
- Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)ltemate path, (C)ontrol room, (S)imulator,
&)ow-Power, (R)CA, (E/A)Emergency/Abnormal, (E)SF (1) Last Minute Replacement - See AR 492171492171NUREG-1021, Drat? Rev 9 2003 NRC Exam Rev. 3 Susquehanna Facsimil :
Exam Level (circle one): SRO-1
- a. 21 5005 A2.02 3.613.7 Bypass an APRM Channel Trip Input Start DIG for surveillance Venting Suppression Chamber within off-site release limits - ES-173-001, Section 4.2, Vent Suppression Chamber using two inch vent bypass to SGTS.73.EO.001.IO1 RESET Recirc Pump Limiter #2 Runback in accordance with ON-164-002
- b. 264000 A2.01 333.6
- c. 223001 A2.07 (4.2/4.3)
- d. 202002 A2.05 (3.814.0)
Operating Test No.:
D, s 7
N, A, s 6
Dt s, E 5
s, A 4
Control Room Systems (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U)
- f. 202001 A2.10 3.513.9
- g. 209001 A2.01 3.813.7 Respond To A Reactor Recirc Pump Dual Seal Failure IAW ON-164-003 Perform Manual S/U of Core Spray IAW OP-151-001 System / JPM Title D, S, /At L 1
D, A, s, 2
E/A, E Type Safety I
Code*
1 Function 11
- h. 262001 K4.04 2.813.1 N,R,A I 6
- e. 290003 A3.013.3i3.5 Perform Monthly Surveillance of 4KV Bus Undervoltage Relays
- i. 295016 AA1.08 (4.014.0)
Perform manual operation of the SRVs Valves from the Remote Shutdown Panel as required by ON-I 00-00900.ON.015.103 Complete Monthly Control Room Emergency Outside Air Supply System Operability Test (I)
D, R, E/A, 7
A
~~~
- j. 217000 A2.01 3.8/3.7 Bypass of All RClC Isolation Signals in Accordance With ES-150-001
- 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, (E/A)Emergency/Abnormal, (E)SF (1) Last Minute Replacement - See AR 492171492171NUREG-1021, Draft Rev 9 2003 NRC Exam Rev. 3 Susquehanna Facsimil~
i
ES-301 Control Room/ln-Plant Systems Outline Form ES-301-2 Facility:
Susquehanna Date of Examination: 8111-8/15 2003 Exam Level (circle one): SR0-U Operating Test No.:
System / JPM Title Type Safety Code*
Function
- c. 223001 A2.07 (4.214.3)
Venting Suppression Chamber within off-site release limits - ES-173-001, Section 4.2, Vent Suppression Chamber using two inch vent bypass to SGTS.73.EO.001. I O 1 D, S, E 5
In-Plant Systems (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)
- e. 290003 A3.013.3/3.5 Complete Monthly Control Room Emergency Outside Air Supply System Operability Test (I)
- g. 209001 A2.01 3.813.7 Perform Manual S/U of Core Spray IAW OP-151-001 N, s, A 9
D, A, S I
2 E/A, E
- 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, (E/A)Emergency/Abnormal, (E)SF (1) Last Minute Replacement - See AR 492171492171: i.
262001 K4.04 2.8/3.1 Perform Monthly Surveillance of 4KV Bus Undervoltage Relays
- j.
295016 AA1.08 (4.0/4.0)
Perform manual operation of the SRVs Valves from the Remote Shutdown Panel as required by ON-100-00900.ON.015.103 NUREG-1021, Draft Rev 9 2003 NRC Exam Rev. 3 N, R, A 6
D, R, E/A, 7
A Susquehanna Facsimil!
PENNSYLVANIA POWER & LIGHT COMPANY JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET S/RO 78.AR.004.103 0
06/17/03 21 5005 A2.02 3.6/3.7 Appl. To JPM Number Rev. No.
Date NUREG 1123 Sys. No.
WA Task
Title:
Bypass an APRM Channel B/D/F Trip Input to RPS Completed By:
Reviews :
Russ Halm 06/17/03 Writer Date InstructorNVriter Date Approval:
Requesting Supv./C.A.
Date Nuclear Trng. Supv.
Date Head 15 Date of Performance:
Allowed Time (Min.)
Time Taken (Min.)
JPM Performed By:
Student Name:
Last First M.I.
Employee #/S.S.
Perform an ce Evaluation:
(
)
Satisfactory
(
)
Unsatisfactory Evaluator Name:
Signature Typed or Printed Comments:
Form STCP-QA-I25A Rev. 4, (05/00)
Page I of 1 2003 NRC Exam Rev. 2 File No. A14-5B
REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE SlRO 78.AR.004.103 L
- 1.
SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.
B. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example:
- 1. Whenever any electrical panel is opened for inspection during JPM performance.
- 2. Whenever entering any plant area where specific safety equipment; such as hearing or eye protection, safety shoes, hardhats, etc; is required and/or posted as being necessary.
C. If in the judgement of the evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.
II. REFERENCES A.
AR-103-001, RPS Division 1 IC651 (Rev. 22)
- 6. AR-104-001, RPS Division 2 IC651 (Rev. 17)
C.
OP-158-001 RPS System (Rev. 26) 111. REACTIVITY MANIPULATIONS
....=
This JPM satisfies the requirements of Operational Activity@):
None IV. TASK CONDITIONS A. The plant is operating at 100% power.
- 6. You are the PCOM.
V. INITIATING CUE Respond to alarm conditions.
VI. TASK STANDARD D APRM input to RPS bypassed and half scram signal reset.
VII.TASK SAFETY SIGNIFICANCE Bypassing D APRM would allow resetting of RPS half scram. Failure to complete the task would result in the inability to remove the half scram signal.
Form STCP-QA-IZSA Rev 4, (OS/OO)
Page I of I 2003 NRC Exam Rev. 2
Appl. To/JPM No.: S/RO 78.AR.004.103 Step 1
l; PERFORMANCE CHECKLIST Action EVALUATOR NOTE:
This JPM must be performed in the simulator.
Establish task conditions as directed on attached setup instructions.
When candidate is ready to begin JPM, place the simulator in RUN.
EVALUATOR NOTE:
The upscale failure of D APRM will cause the following annunciators to alarm:
104-A04, and AR-104-H03 It is acceptable for the candidate to refer to any or all of these AR procedures. The necessary guidance to respond to the failure is contained in AR-103-A06. The JPM is written to follow this guidance.
AR-103-A06, AR-103-B06, AR-104-AOI, AR-BOOTH OPERATOR:
30 seconds after the candidate is ready to begin the JPM, Depress P-2.
Candidate locates procedure and refers to appropriate section.
- Critical Step
- Critical Sequence Student Name:
Standard Obtains procedure AR-103-001 and refers to Window A06.
Eva1 Page 3 of 5 Comments Form STCP-QA-IZ5A Rev 4, (OYOO)
Pape I of I
PERFORMANCE CHECKLIST Page 4 of 5 Appl. To/JPM No.: S/RO 78.AR.004.103 Step 2
3 4
5
- 6
~
Action Determines Probable cause.
Ensures automatic actions occurred.
Determines reactor power reduction is not necessary.
Determines D APRM is affected.
EVALUATOR CUE Candidate may inform Unit Supervisor about the instrument failure before bypassing.
Grant permission to Bypass 'D' APRM Bypass D APRM.
- Critical Step
- Critical Sequence Student Name:
Standard Determines D APRM is failed upscale high Verifies:
0 CRT No. 6 D APRM reading 125%.
0 Status light D APRM UPSC TR OR INOP D UPSCALE ALARM - LIT.
AR-104-A01 RPS CHANNEL BllB2 AUTO SCRAM - LIT.
AR-104-H03 ROD OUT BLOCK - LIT.
Verifies:
0 Trip to Reactor Protection System channel B.
Rod block to Reactor Manual Control System.
Determines flow bias setpoint has not been exceeded on any of the unaffected channels.
Determine APRM channel causing the trip Verifies:
0 D APRM reading 125%.
0 All other APRMs reading 100%.
Places the Division 2 APRM BYPASS joystick to the D position.
Eva1 Comments
Appl. To/JPM No.: S/RO 78.AR.004.103 Step
- 7 8
i PERFORMANCE CHECKLIST Action
- Critical Step EVALUATOR NOTE:
It does not matter which position is selected first in the next step.
Reset RPS trip system.
Observe alarms clear.
EVALUATOR NOTE:
This completes the JPM.
- Critical Sequence Student Name:
Standard Places the RX SCRAM RESET switch to the GRP 1/4 position then to the GRP 2/3 position and returns to the NORM position.
Verifies the following alarm is clear RPS CHANNEL BI/B2 AUTO SCRAM, AR-1 04-AOI.
Eva1 Page 5 of 5 Comments Form STCP-QA-125A Rcv 4, (OYOO)
- vu> L.A../
-......I A_-.. -
TASK CONDITIONS L-A. The plant is operating at 100% power.
B. You are the PCOM.
INITIATING CUE Respond to alarm conditions.
Form STCP-QA-125A Rev 4, (OYOO)
Page 1 of I 2003 NRC Exam Rev. 2 Page 1 of 2
TASK CONDITIONS A. The plant is operating at 100% power.
B. You are the PCOM.
INITIATING CUE Respond to alarm conditions.
Page 2 of 2 Form STCP-QA-I25A Rev 4, (05lOO)
Page I of 1 2003 NRC Exam Rev. 2
PENNSYLVANIA POWER & LIGHT COMPANY JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET S/RO 24.S0.002.151 0
06/18/03 264000 A2.01 3.5/3.6 Appl. To JPM Number Rev. No.
Date.
NUREG 1123 Sys. No.
KIA Task
Title:
Perform the Monthly Diesel Generator Operability Test for D D/G in Accordance With SO-024-001 Completed By:
Reviews:
R. Halm 06/18/03 Writer Date InstructorMlriter Date Ap prova I:
Requesting Supv./C.A.
Date Nuclear Trng. Supv.
Date Head 30/40 Min Date of Performance:
Allowed Time (Min.)
Time Taken (Min.)
JPM Performed By:
Student Name:
Last First M.I.
Employee #/S.S.
Perform an ce Evaluation:
(
)
Satisfactory
(
)
Unsatisfactory Evaluator Name:
Signature Typed or Printed Comments:
Form STCP-QA-125A STCP-QA-1258 Rev. 2. (9193)
Page 1 of 1 2003 NRC Exam Rev. 2 File No. A14-5B
REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE SlRO 24.S0.002.151 I. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.
B. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example:
- 1. Whenever any electrical panel is opened for inspection during JPM performance.
- 2. Whenever entering any plant area where specific safety equipment; such as hearing or eye protection, safety shoes, hardhats, etc; is required and/or posted as being necessary.
C. If in the judgement of the evaluator any safety issue occurs during the performance of a JPM, the JPlW will be terminated until the issue is resolved.
II. REFERENCES A.
SO-024-00 I
, Diesel Generators (Rev. 37)
B. OP-024-005, Diesel Generator Start Log (SPS 01-024-002) (Rev. 4)
C.
OP-030-002, Control Structure HVAC (Rev. 20)
D. AR-016-001, D/G D, ESW, RWMU, AND MlSC LOAD CENTER OC653 (Rev. 35)
E. LA-0521-004, DIESEL GENERATOR D OC521 (Rev. 14) 111. REACTIVITY MAN1 PU LATIONS This JPM satisfies the requirements of Operational Activity(s):
None IV. TASK CONDITIONS The Plant is in Condition 1.
A.
B.
C.
D.
E.
F.
Perform the Monthly Diesel Generator Operability Test for D D/G in Accordance With S0-024-001.
The ESW System is in service.
The prerequisites for the surveillance have been completed, an operator is stationed at the diesel generator and prelube operation is complete per step 6.1.5.
Recording data on the strip chart recorder per step 6.1.6 is NOT required.
Recording START times per steps 6.1.8, 6.1.9 and 6.1.IO are NOT required.
Communications with the local operator have been established (the evaluator will provide all local information)
V. INITIATING CUE Perform the Monthly Diesel Generator Operability Test for D D/G in Accordance With S0-024-001 beginning at step 6.1.7 (page 11).
Form STCP-QA-125A Rev. 4. (05100)
Page 1 of 1 2003 NRC Exam Rev. 2
VI. TASK STANDARD Synchronize the Diesel Generator to the grid and shutdown D/G based on Generator terminal voltage decay.
VII.TASK SAFETY SIGNIFICANCE Demonstration of Diesel Generator operability.
Failure to synchronize the Diesel Generator to the grid would prevent the Technical Specification required Demonstration of Diesel Generator operability.
Inability to identify the need to trip the Diesel Generator and then have it shutdown would result in equipment damage to a Safety related piece of equipment.
Form STCP-QA-125A STCP-QA-125B Rev. 2. (9193)
Page i bt 1 '
2003 NRC Exam Rev. 2 File No. A14-5B
Appl. To/JPM No.: S/RO 24.S0.002.151 Step 1
Action EVALUATOR NOTE:
This JPM must be performed in the simulator.
Establish task conditions as directed on attached setup instructions.
Provide turnover to candidate as follows:
Layout procedure on monitoring console marked with prerequisites complete and tabs showing start of JPM at step 6.1.7.
Show candidate that prerequisites have been signed.
Instruct candidate that the evaluator will act as the field operator Tell candidate to review procedure and let the evaluator know when you are to begin the JPM.
The FAULTED step in this JPM is preceded by a fault statement in BOLD TYPE WITH ALL CAPITAL LETTERS.
When candidate is ready to begin JPM, place the simulator in RUN.
Candidate is given the procedure as part of turnover and is referred to appropriate section.
PERFORMANCE CHECKLIST Page 3 of 12 Student Name:
Standard Given procedure SO-024-001, Diesel Generator 6.1.7.
Eva1 Comments
- Critical Step
- Critical Sequence Form STCP-QA-tZ5A Rev 4, (0900)
LUUJ I Y, \\ U L*Olll b \\ c, ".
L
Appl. To/JPM No.: S/RO 24.S0.002.151 Step 2
3
- 4 PERFORMANCE CHECKLIST Page 4 of 12 Action Reviews prerequisites.
EVALUATOR NOTE:
All alarms on AR015, Columns 0, 13, 16, Rows A through G will be extinguished.
0 All alarms on AR016, Column 3, Rows A through G will be extinguished.
0 Diesels A, B, C and D will be in Standby with each diesels associated instruments and indications reading as follows: DG D Watts XI-00032D - Downscale Amps -
Downscale Freq - 60 to 61 Hz Volts -
Downscale Ready to Run Light illuminated Voltage Regulator Auto light illuminated 0 Synchroscope XS-00037 will be OFF.
0 Diesel Gen Bus Diff Voltmeter XI-00036 will be reading zero.
0 The Diesel Generator output breakers for each generator will be open.
Review the precautions and procedure up to step 6.1.7 Start the DG.
Student Name:
Stand a rd Reviews prerequisites Follows precautions as applicable.
Depresses DG D start HS-00051 D pushbutton.
Observes DG frequency and voltage Eva1 Comments
- Critical Step Form STCP-QA-125A Rev. 4. (05/00)
- Critical Sequence
Appl. TolJPM No.: S/RO 24.S0.002.151 Step 5
6 PERFORMANCE CHECKLIST Action 3ecord DIG Air Start Receiver pressures EVALUATOR CUE:
As local operator at the D/G report:
Left Bank Pressure: 190 psig Right Bank Pressure: 195 psig Air Start Receivers are properly aligned The Air Start Receivers are within 10 psig o each other Both #I and #2 Air Compressors started.
Log the DG start time.
EVALUATOR NOTE:
D/G will run for a few minutes and a Low Priority alarm will be received. The alarm is from the Standpipe High Level alarm at the local panel. The alarm is due to jacket water heating up and is an expected alarm during startup.
Student Name:
Page 5 of 12 Standard Request local operator check:
Air pressure System properly aligned Both #I & #2 compressors started Notes the DG start time AND Completes the Diesel Generator Start Log.
Eva1 Comments
- Critical Step Form STCP-QA-1Z5A Rev 4. (0300)
- ___..._-.- -~
- Critical Sequence
Appl. To/JPM No.: S/RO 24.S0.002.151 Step 7
8 9
Action i
PERFORMANCE CHECKLIST Page 6 of 12 DG A PANEL OC521 D LO PRIORITY TROUBLE received (AR-016-C03)
Review Alarm Response Procedure EVALUATOR CUE:
Report that local alarm is E01 Standpipe High Level Alarm, normal Expected alarm received during startup.
Perform post start checks of the running Diesel generator.
EVALUATOR CUE:
Report as the field operator that post start checks of the Diesel Generator are satisfactory, temperatures are normal and starting air pressure is 250 psig on local gages.
Student Name:
Standard Request local Operator to perform LA-0521 -004 Diesel Generator D OC521 D (Attached)
Review AR-016-C03 which contains the following steps: (Attached)
COMPLY with TS 3.8.1 and 3.8.3.
OBSERVE Generator Voltage; If 2600V(+ 200V):
DO NOT adjust Voltage Regulator, AND PROMPTLY SHUTDOWN Diesel Generator.
Repeat back Expected high level alarm due to Standpipe high level.
Request local Operator to perform post start checks of Diesel Generator D OC521 D Eva1 Comments
- Critical Step Form STCP-QA-125A Rev 4 (05/00)
- Critical Sequence L"""..I \\-
i Appl. To/JPM No.: S/RO 24.S0.002.151
-~
Step 10 11
- I 2
13
- I4
- I 5
PERFORMANCE CHECKLIST Action Monitor and record parameters Ensure all Synchroscope switches OFF SYNCHRONIZE Diesel Generator D to 4.1 6KV Bus 1 D. Step 6.1.I7 a.- I Check for excessive sparking of the generator brushes.
EVALUATOR CUE:
Report as the field operator that no sparking of the generator brushes has been observed.
Adjust DG D Voltage Adjust DG D Speed
- Critical Step Form STCP-QA-125A Rev 4. (OUOO) n _ _ _
1 _ I.
- Critical Sequence Student Name:
i Page 7 of 12 Standard When steady state conditions reached, takes current values of frequency and voltage and records on attachment A Verifies all synchroscope switches OFF PLACE DG D to Bus I D Sync Sel HS-00042A keyswitch switch to ON.
Requests local operator to check for excessive sparking of the generator brushes ADJUST DG D Voltage Adjust HS-00053 D so Diff AC Volts XI-00036 indicates slightly right of 0 and not exceeding 35 volts AC.
ADJUST DG D Speed Governor HS-00054 D so Synchroscope XI-00037 rotating in FAST (clockwise) direction at - 1 (one) revolution per 60 seconds.
Eva1 Comments
Appl. To/JPM No.: S/RO 24.S0.002.151 Step
- I 6
- I 7
Action PERFORMANCE CHECKLIST Page 8 of 12 CLOSE DG D output breaker Faulted Step - 'D' DIG @IO00 KW, Generator output breaker trips and Generator Terminal voltage decays.
Raise load on DG D BOOTH NOTE:
Monitor DG output breaker. If DG D PANEL OC521 D LO PRIORITY TROUBLE (C03) does not alarm when DG output breaker OPENS, then Depress PB#8 which will trigger a local alarm that will cause DG D PANEL OC521D LO PRIORITY TROUBLE (C03) to alarm Student Name:
Standard CLOSE DG D to Bus I D Bkr 1A20404 when synchroscope at or slightly before "1 2 o'clock
position.
PROMPTLY go to RAISE and SLOWLY increase load to 1000 KW over a 30-45 second period using DG D Speed Governor HS-00054 D switch.
Eva1 Comments
- Critical Step Form STCP-QA-125A Rev 4, (05lOO)
I,.
- Critical Sequence
PERFORMANCE CHECKLIST Page 9 of 12 Appl. To/JPM No.: S/RO 24.S0.002.151 Step 18 Action EVALUATOR NOTE:
The D D/G output breaker will trip open with no alarm.
Then the DG D PANEL OC521D LO PRIORITY TROUBLE (C03) will annunciate, and DG voltage should be slowly dropping to -2600 volts.
Respond to:
DG D PANEL OC521D LO PRIORITY TROUBLE (C03) Alarm response: AR-016-C03 EVALUATOR CUE:
As local Operator report the following alarm received at panel OC521 D:
GENERATOR FIELD GROUND (alarm) (F06)
- Critical Step Form STCP-QA-125A Rev 4. (05100)
- Critical Sequence Student Name:
Standard Request local Operator to investigate LA-0521 -004 Diesel Generator D OC521 D (Attached)
Eva1 Comments
i PERFORMANCE CHECKLIST Page Appl. To/JPM No.: S/RO 24.S0.002.151 Student Name:
Step
- I 9 20
- 2 1 Action Review AR-0 1 6-C03 EVALUATOR CUE:
If candidate request local operator to check DG D voltage locally, report DG D voltage as
- 2600 volts Monitor Voltage D/G meter: OX100035D for change in voltage Trip DG D BOOTH OPERATOR Depress PB#7 CAE+! DGDStop (Trips DIG locally)
Stand a rd Review AR-016-C03 which contains the following steps:
COMPLY with TS 3.8.1 and 3.8.3.
OBSERVE Generator Voltage; If 2600V(k 200V):
DO NOT adjust Voltage Regulator, AND PROMPTLY SHUTDOWN Diesel Generator Checks:
voltage decreasing, as voltage approaches 2600V Request local operator to trip DG D Eva1 Oof 12 Comments
- Critical Step
- Critical Sequence Form STCP-QA-125A Rev 4, (05/00)
LUUd I,\\
LP.UIII D \\ b.
L
N I
h cn 0
a, Q
v) c 0 e 8
2 Q) cn C
Q) 5 2
rc cn 0
a, Q
v) c 0
P a,
0 a
5
\\c 8
m cn c
m E 0 d
hl
Appl. To/JPM No.: S/RO 24.S0.002.151 Step
- 25 PERFORMANCE CHECKLIST Action letermines required actions EVALUATOR CUE:
This completes the JPM.
Page 12 of 12 Student Name:
Standard Determines the following actions will be required:
Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and 1/8 hours thereafter Perform SR 3.8.1.I for Operable offsite circuits Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Determine th Operable DGs are not inoperable due to a common cause fai I ure OR Perform SR 3.8.1.7 for operable DGs Within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and 6 days of discovery of failure to meet the LCO:
Restore the DG to operable status Eva1 Comments
- Critical Step Form STCP-QA-125A Rev 4, (05/00)
I,, >
- Critical Sequence
SRO ONLY TASK CONDITIONS The Plant is in Condition 1, A.
B.
The D Diesel Generator has just failed its Monthly Diesel Generator Operability Test SO-The E Diesel Generator is unavailable as a replacement for the D Diesel Generator.
024-00 1.
INITIATING CUE What Technical Specifications action(s), including time limits, idare required as a result of this failure.
Page 1 of 4 Form STCP-QA-125A Rev. 4. (05/00)
Page 1 of 1 2003 NRC Exam Rev. 2
SRO ONLY TASK CONDITIONS The Plant is in Condition 1 A.
The D Diesel Generator has just failed its Monthly Diesel Generator Operability Test SO-024-001.
B.
The E Diesel Generator is unavailable as a replacement for the D Diesel Generator INITIATING CUE What Technical Specifications action(s), including time limits, idare required as a result of this failure.
Page 2 of 4 Form STCP-QA-125A Rev. 4. (05/00)
Page 1 of 1 2003 NRC Exam Rev. 2
TASK CONDITIONS The Plant is in Condition 1 A.
B.
C.
D.
E.
F.
Perform the Monthly Diesel Generator Operability Test for D D/G in Accordance With SO-The ESW System is in service.
The prerequisites for the surveillance have been completed, an operator is stationed at the diesel generator and prelube operation is complete per step 6.1.5.
Recording data on the strip chart recorder per step 6.1.6 is NOT required.
Recording START times per steps 6.1.8, 6.1.9 and 6.1.IO are NOT required.
Communications with the local operator have been established (the evaluator will provide all local information) 024-00 1.
INITIATING CUE Perform the Monthly Diesel Generator Operability Test for D D/G in Accordance With SO-024-001 beginning at step 6.1.7 (page 11).
Page 3 of 4 Form STCP-QA-125A Rev 4. (05/00)
Page 1 of 1 2003 NRC Exam Rev. 2
TASK CONDITIONS The Plant is in Condition 1.
A.
B.
C.
D.
E.
F.
Perform the Monthly Diesel Generator Operability Test for D D/G in Accordance With SO-The ESW System is in service.
The prerequisites for the surveillance have been completed, an operator is stationed at the diesel generator and prelube operation is complete per step 6.1 5.
Recording data on the strip chart recorder per step 6.1.6 is NOT required.
Recording START times per steps 6.1.8, 6.1.9 and 6.1.10 are NOT required.
Communications with the local operator have been established (the evaluator will provide all local information) 024-00 I.
INITIATING CUE Perform the Monthly Diesel Generator Operability Test for D D/G in Accordance With SO-024-001 beginning at step 6.1.7 (page 11).
Page 4 of 4 Form STCP-QA-lZ5A Rev. 4. (05/00)
Page 1 of 1 2003 NRC Exam Rev. 2
PENNSYLVANIA POWER & LIGHT COMPANY JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET S/RO 73.E0.001.101 2
06/17/03 223001 A2.07 4.214.2 Appl. To JPM Number Rev. No.
Date NUREG 1123 Sys. No.
KIA Task
Title:
Venting Suppression Chamber Within Offsite Release Limits - ES-173-001, Section 4.2 Vent Suppression Chamber Using Two Inch Vent Bypass to SGTS Completed By:
Reviews:
06/17/03 06/20/0 1 Russ Halm Writer Date Instructor/Writer Date Approval:
Requesting Supv./C.A.
Date Nuclear Trng. Supv.
Date Head Date of Performance:
JPM Performed By:
20 Allowed Time (Min.)
Time Taken (Min.)
Student Name:
Last First M.I.
Employee #/S.S. #
Pe rfo r man ce Evaluation:
(
)
Satisfactory
(
)
Unsatisfactory Evaluator Name:
Sign at ure Typed or Printed Comments:
STCP-QA-125A Rev 2. (9/93)
Page 1 of 1 2003 NRC Exam Rev. 2 File No. A14-56
REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE SlRO 73.E0.001.I 01
- 1.
SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.
B. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example:
- 1. Whenever any electrical panel is opened for inspection during JPM performance.
- 2. Whenever entering any plant area where specific safety equipment; such as hearing or eye protection, safety shoes, hardhats, etc; is required and/or posted as being necessary.
C. If in the judgement of the evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.
- 11. REFERENCES A. ES-173-001 Venting Suppression Chamber Within Offsite Release Limits (Rev. 4) 111. REACTIVITY MANIPULATIONS This JPM satisfies the requirements of Operational Activity(s):
None IV. TASK CONDITIONS A. A small break LOCA has occurred.
B. The Reactor is shut down with all control rods full in.
C. The TSC has determined it is necessary to vent the Suppression Chamber restricted to TS release limits.
D. ES-173-001, Section 4.2, is completed by the US up to and including step 4.2.4.b(1)
E. Per Step 4.2.1:of procedure, Chemistry has obtained a Suppression Chamber Noble Gas sample and the Sample result are 3E-7ucikc.
F. SGTS SPECIAL PARTICULATE IODINE & NOBLE GAS (SPING) is operable.
G. SGTS is operating per OP-070-001.
V. INITIATING CUE Vent the Suppression Chamber (restricted to TS Release Limits) per ES-173-001, Section 4.2, beginning at step 4.2.4.c VI. TASK STANDARD Suppression Chamber vent path established.
2003 NRC Exam Rev. 2
VI I. TASK SAFETY SIGN I Fl CAN C E Establishing a Suppression Chamber vent path, under these conditions, is necessary to maintain Primary Containment integrity.
Failure to establish a Suppression Chamber vent path could lead to Primary Containment failure.
2003 NRC Exam Rev. 2
Appl. TolJPM No.: SlRO 73.E0.003.101 Step 1
2 3
PERFORMANCE CHECKLIST Action EVALUATOR NOTE:
Prior to performing this JPM, obtain a copy of the latest revision of ES-173-001 and mark it as if it was actually to be performed. For step 4.1 indicate (initial) that section 4.2 be performed and N/A section 4.3. Complete the signature, date, and time. Indicate steps 4.2.1, 4.2.2, 4.2.3, and 4.2.4 are complete. Provide it to the student along with the Task Conditionsllnitiating Cue Sheet.
0 If this JPM is performed in the simulator establish task conditions as directed on attached setup instructions.
When student is ready to begin JPM, place the Simulator in RUN.
0 Review Sections 1.O through 3.0 Notes Shift Manager approval to perform uiep 4.2 (page 2 of 23).
Obtain the required equipment.
EVALUATOR NOTE:
If a containment isolation signal is not present, then steps 4.2.4.c(1) & (2) are not required and should not be performed. Mark signoffs NA.
Student Name:
Standard Review all sections.
Follows all precautions as applicable.
Observes Shift Manager signature, date, and time in the appropriate location (to perform section 4.2) in Section 4.1 of the procedure.
Obtains two (2) keys.
Eva1 Page 4 of 7 Comments
- Critical Step
- Critical Sequence STCP-QA-125B Rev 2. (9/93)
I,.
L"",
,. A. b LIIIU.....~.. -
Appl. To/JPM No.: S/RO 73.E0.003.101 Step
- 4
- 5
- 6 Actinn EVALUATOR NOTE:
31acina the key switches to the SC position in the
'allowing steps will cause AR127(8)-D-7 to alarm.
4cknowledging these alarms is not critical.
3ver-ride 45 minute time delay Div 1.
Over-ride 45 minute time delay Div 2.
EVALUATOR CUE:
If asked, inform the student that venting is restricted to TS release limits; N/A step 4.2.4.d.
At Panel IC68 line up vent path.
i PERFORMANCE CHECKLIST i'
Page 5 of 7 Student Name:
~
Standard PLACE keylock switch for DrwI/Supp Chmbr Dmp HD-17508A Is0 Signal Byps (HD17508A, HV-15703) in SC position.
Inserts key and rotates clockwise to place keylock switch HD-17508A in SC position.
PLACE keylock switch for Drwl/Supp Chmbr Dmp HD-17508B Is0 Signal Byps (HD17508B, HV-15705) in SC position.
Inserts key and rotates clockwise to place keylock switch HD-17508B in SC position.
Determines step 4.2.4.d is not applicable.
Open DrwlM/etwell Burp Dmp HD-17508A.
Places Control Switch for HD-17508A to OPEN AND Verifies RED Light LIT, AMBER Light NOT LIT Eva1 Comments
- Critical Step
- Critical Sequence STCP-QA-1256 Rev 2. (9193) 03-0 1 nf 1
i PERFORMANCE CHECKLIST Appl. To/JPM No.: S/RO 73.E0.003.101 Step
- 7
- 8
- 9 10 Action At Panel IC681 line up vent path.
At Panel IC601 line up vent path.
At Panel IC601 line up vent path.
Verify vent path complete.
- Critical Step
- Critical Sequence Student Name:
1; Page 6 of 7 Stand a rd Open DrwlNVetwell Burp Dmp HD-17508B.
Places Control Switch for HD-17508B to OPEN AND Verifies RED Light LIT, AMBER Light NOT LIT Open SUPP CHMBR VENT IB IS0 HV-15703.
Places Control Switch for HV-15703 to OPEN AND Verifies RED Light LIT, AMBER Light NOT LIT Open SUPP CHMBR VENT OB IS0 HV-15705.
Places Control Switch for HV-15705 to OPEN AND Verifies RED Light LIT, AMBER Light NOT LIT MONITOR Suppression Chamber pressure on CONTAINMENT PRESSURE PR-1571 OA(B).
Eva1 Com men ts STCP-QA-1258 Rev 2 (9/93)
Page 1 of 1
Appl. To/JPM No.: S/RO 73.E0.003.101 Step Action 11 Monitor Radiation release rates.
PERFORMANCE CHECKLIST Page 7 of 7 Standard MONITOR SBGT SPING release rates.
Student Name:
Using any of the following:
PlCSY (yellow-no alarms)
SPING Terminal.
AND Determine SGTS SPING release rates remain stable and NO alarms are present.
EVALUATOR CUE:
This completes the JPM.
- Critical Step
- Critical Seq uence STCP-QA-125B Rev 2. (9193)
Paqe 1 of 1
TASK CONDITIONS A.
B.
C.
D.
E.
F.
G.
A small break LOCA has occurred.
The Reactor is shut down with all control rods full in.
The TSC has determined it is necessary to vent the Suppression Chamber restricted to TS release limits.
ES-173-001, Section 4.2, is completed by the US up to and including step 4.2.4.b(1)
Per Step 4.2.1 :of procedure, Chemistry has obtained a Suppression Chamber Noble Gas sample and the Sample result are 3E-7ucilcc.
SGTS SPECIAL PARTICULATE IODINE & NOBLE GAS (SPING) is operable.
SGTS is operating per OP-070-001.
INITIATING CUE Vent the Suppression Chamber (restricted to TS Release Limits) per ES-173-001, Section 4.2, beginning at step 4.2.4.c Page 1 of 2 2003 NRC Exam Rev. 2
TASK CONDITIONS A.
B.
C.
D.
E.
F.
G.
A small break LOCA has occurred.
The Reactor is shut down with all control rods full in.
The TSC has determined it is necessary to vent the Suppression Chamber restricted to TS release limits.
ES-173-001, Section 4.2, is completed by the US up to and including step 4.2.4.b(1)
Per Step 4.2.1:of procedure, Chemistry has obtained a Suppression Chamber Noble Gas sample and the Sample result are 3E-7ucilcc.
SGTS SPECIAL PARTICULATE IODINE & NOBLE GAS (SPING) is operable.
SGTS is operating per OP-070-001.
- 1.
INITIATING CUE Vent the Suppression Chamber (restricted to TS Release Limits) per ES-173-001, Section 4.2, beginning at step 4.2.4.c Page 2 of 2 2003 NRC Exam Rev. 2
PENNSYLVANIA POWER & LIGHT COMPANY JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET S/RO 64.0P.004.153 0
0611 7/03 202002 A2.05 3.814.0 Appl. To JPM Number Rev. No.
Date NUREG 1123 Sys. No.
KIA Task
Title:
Completed By:
Reviews:
Reset Recirculation Pump Limiter #2 Runback IAW ON-I 64-002 Russ Halm 0611 7/03 Writer Date Instructor/Writer Date Approval:
Requesting Supv./C.A.
Date Nuclear Trng. Supv.
Date Head Date of Perform an ce :
JPM Performed By:
20 Allowed Time (Min.)
Time Taken (Min.)
Student Name:
Last First M.I.
Employee #/S.S. #
Performance Eva hat ion :
)
Satisfactory
(
)
Unsatisfactory Evaluator Name:
Signature Typed or Printed Comments:
STCP-QA-125A Rev. 2, (9/93)
Page 1 of 1 2003 NRC Exam Rev. 2 File No. A14-56
REQUIRED TASK INFORMATION JOBPERFORMANCEMEASURE SlRO 64.0P.004.153 I.
SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.
B. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example:
- 1. Whenever any electrical panel is opened for inspection during JPM performance.
- 2. Whenever entering any plant area where specific safety equipment; such as hearing or eye protection, safety shoes, hardhats, etc; is required and/or posted as being necessary.
C. If in the judgement of the evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.
II. REFERENCES ON-164-002, Loss Of Reactor Recirculation Flow (Rev. 20)
I II. REACTIVITY MAN1 PULATIONS This JPM satisfies the requirements of Operational Activity(s):
36 Reset recirc pump runback IV. TASK CONDITIONS A. The plant is in Mode 1.
B. Rods 18-23, 18-39, 42-23, and 42-39, are fully inserted to support HCU maintenance on Rod 1%:
C. A trip of CWP I D has caused a Reactor Recirculation runback to occur.
D. NO Operator actions have been taken.
V. INITIATING CUE Respond to a loss of reactor recirculation flow and reset recirculation pump runback in accordance with appropriate Off Normal procedure.
VI. TASK STANDARD Recirc pump limiter #2 reset and scoop tube locked for B recirc pump 2003 NRC Exam Rev. 2
VII. TASK SAFETY SIGNIFICANCE Resetting the limiter would regain control of Recirculation Pump speed.
Failure to recognize a failure of the speed control for Recirculation Pump would allow a power excursion and potential scram.
2003 NRC Exam Rev. 2
Appl. To/JPM No.: S/RO 64.0P.004.153 Step 1
2 3
4 5
PERFORMANCE CHECKLIST Action EVALUATOR NOTE:
This JPM must be performed in the simulator.
Establish task conditions as directed on attached setup instructions.
The FAULTED step in this JPM is preceded by a fault statement in BOLD TYPE WITH ALL CAPITAL LETTERS.
When student is ready to begin JPM, place the simulator in RUN.
Obtain a controlled copy of ON-164-002, Loss Of Reactor Recirculation Flow.
Record date and time of event.
Selects the correct section to perform.
Plot position on Power/Flow Map.
Perform appropriate action specified on Power/Flow Map.
Student Name:
Page 3 of 13 Stand a rd Controlled copy obtained.
Records date and time of event.
Selects section 3.4.
In the event of Reactor Recirculation Pump runback:
Plot position on Power/Flow Map, Form NDAP-QA-0338-10 (Rev-5).
Determines NOT to be in Region 1 or 2.
Perform appropriate action specified on Power/Flow Map.
Determines NO action required for current region.
Eva1
~~
Comments
- Critical Step
- Critical Sequence STCP-QA-1258 Rev 2(9/93)
Page 1 of 1
i Appl. To/JPM No.: S/RO 64.0P.004.153 Step 6
7 PERFORMANCE CHECKLIST Page 4 of 13 Action
'lace mode switch to SHUTDOWN if operating in any of these powerlflow map conditions.
Determine which limiter initiated runback.
- Critical Step
- Critical Sequence Student Name:
Standard PowerlFlow Map indicates 2peration in Region 1 or Core Flow s < Natural Recirculation Line Dperation in any region not bounded by Power/Flow map, Place MODE SWITCH to SHUTDOWN.
Determines NO action required.
Limiter #I (30%) limiting by Green light ILLUMINATED above RX RECIRC LIMITER #I RUNBK push button.
RESET HS-B31-1 SI 5A(B)
Verifies:
Green lights NOT LIT Limiter #2 (45%) limiting by Green light ILLUMINATED above LOSS B31-1 S12A(B) pushbutton.
OF FW PP RUNBK RESET HS-Verifies:
Green lights LIT Eva1 Comments STCP-QA-1258 Rev 2 (9/93) on,.*.,
n, I
Appl. To/JPM No.: S/RO 64.0P.004.153 Step 8
9
/
PERFORMANCE CHECKLIST Page 5 of 13 Student Name:
Action Ensure both pumps have run back to value sssociated with controlling limiter.
As core flow decreases, core flux instabilities are more likely to occur.
Monitor neutron instrumentation for indication of core instability.
IF required, Perform ON-178-002, Core Flux Oscillations.
- Critical Step
- Critical Sequence Standard For RRP A verifies:
Input meter SY-B31-1 R621A is
-45%
OR Gen 1A Speed is -45 % on SI-14032A and Gen 1A Demand is
-45% on XI-14032A.
AND For RRP B verifies:
Input meter SY-B31-1 R621 B is
-45%
OR Gen 1B Speed is -45% on Sl-14032B and Gen 1 B Demand is
-45% on XI-14032B.
Select a Control Rod and monitors for LPRM/APRM oscillations and determines they are not unstable.
ON-178-002 is NOT required.
Eva1 Comments STCP-QA-1233 Rev 2 (993)
D^-n 4,.' 4
-~
PERFORMANCE CHECKLIST Page 6 of 13 Appl. To/JPM No.: S/RO 64.0P.004.153 Step 10 11 12 Action CAUTION Power reduction will further reduce amount of feedwater heating which will cause reactor power to increase.
Continue Monitoring position on Power/Flow map.
Monitor changes in radiation levels.
EVALUATOR CUE:
If questioned about Rad Monitor readin candidate that the radiation level were, 100% reactor power values and have now lowered and stabilized at the values indicated.
inform ieir IF Main Steam Line Radiation Monitor or Offgas Pretreatment Log Radiation Monitor increases, Direct Chemistry to sample per CH-ON-003.
Student Name:
Standard Plot position on Power/Flow map for changes in reactor power or core flow.
On 1 C600, Monitor the following:
Main Steam Line Radiation Monitor, RR-D12-I R603.
Offgas Pretreatment Log Radiation Monitor, RR-D12-I R601.
Determines values are NORMAL for this power level.
Determines Chemistry notification is NOT required.
Eva1 Comments
- Critical Step
- Critical Sequence STCP-QA-1258 Rev 2 (9/93)
L""U,.I.Y L A U I, I I.".. L
Appl. To/JPM No.: S/RO 64.0P.004.153 Step 13 14 15 i
PERFORMANCE CHECKLIST i
Page 7 of 13 Action Monitors parameters for new power level.
Determine signal that initiated runback.
EVALUATOR NOTE:
CWP 1 D trip was given in initial conditions.
Ensure recirc speed controllers are in manual.
Student Name:
Standard Observe following plant parameters WITHIN LIMITS corresponding to new power level:
- a. Power to flow limits
- b. Condenser vacuum
- c. Feedwater flow/steam flow
- d. RPV water level Determines WITHIN LIMITS for the new power level.
Determines:
Limiter #2 (45%) runback initiated by Circulating Water Pump 1 D protective trip.
Ensure REACTOR RECIRC PUMP IN MANUAL.
A(B) SPEEDS SY-B31-1R621A(B)
Verifies amber M (manual) light LIT on the following:
Reactor Recirc Pump A SY-B31-1 R621A Reactor Recirc Pump B SY-B31-1 R621 B Eva1 Comments
- Critical Step
- Critical Sequence STCP-QA-1258 Rev 2 (9/93)
PlP 1 Of 1
Appl. To/JPM No.: S/RO 64.0P.004.153 Step i
PERFORMANCE CHECKLIST Page 8 of 13 Action CAUTION When establishing control with the recirc pump speed controllers, minimize lowering core flow to avoid inadvertent entry into Regions I or II of the power/flow map.
EVALUATOR NOTE:
If minor speed oscillations occur for RRP A, acknowledge candidate concerns and direct candidate to continue with FW PP Runback Resets. Speed oscillations will be addressed subsequent to the reset.
EVALUATOR CUE:
If necessary provide candidate with INITIAL recirc pump RPM select MPS (Monitored Parameter Summary) to view speed values. Booth operator to provide to examiner when student requests speeds. (IMP RRNl P401A and IMP RRNI P401 B)
- Critical Step
- Critical Sequence Student Name:
Standard Eva1 Comments STCP-QA-1258 Rev 2 (9193) n---. ^I 4 L"""....- -,.."...
/
Appl. To/JPM No.: SlRO 64.0P.004.153 Step
- I 6A
- I 7A 18A PERFORMANCE CHECKLIST Page 9 of 13 Action Establish speed control for RRP A.
EVALUATOR CUE:
If necessary provide candidate with recirc pump RPM select MPS (Monitored Parameter Summary) to view speed values. Booth operator to provide to examiner when student requests speeds. (IMP RRNlP401A and IMP RRNlP401B)
Candidate may observe loop flow to confirm control.
Reset limiter #2 runback for RRP A.
Monitor GEN I A speed.
Student Name:
Standard For Limiter #2 runback Perform following for one or both pumps as required:
To prevent pump speed from changing when Limiter #2 reset, Ensure GEN 1A DEMAND adjusted such that GEN 1A SPEED decreases when controller DEMAND is decreased.
For RRP A:
Depresses the DEC pushbutton on Reactor Recirc Pump A SY-B31-1 R621A controller until Gen 1A Demand XI-14032A and Gen 1A Speed SI-14032A start to decrease.
Depress LOSS OF FW PP RUNBK pushbutton.
RESET HS-B31-1 S I 2A Monitor GEN 1A SPEED SI-14032A.
Determines speed is stable.
Eva1
~
Comments
- Critical Step
- Critical Sequence STCP-QA-125B Rev 2 (9/93)
!%ne 1 of 1
Appl. To/JPM No.: S/RO 64.0P.004.153
~
Step 19A 20A
- Critical Step PERFORMANCE CHECKLIST Page 10 of 13 Action If RRP A speed increases rapidly, lock scoop tube.
Verify RRP A limiter #2 is reset by light indication.
EVALUATOR NOTE:
If minor speed oscillations occur for RRP B, acknowledge candidate concerns and direct candidate to continue with FW PP Runback Resets. Speed oscillations will be addressed subsequent to the reset.
- Critical Sequence Student Name:
Standard IF speed increases rapidly, Trip scoop tube on affected generator by depressing SCOOP TUBE A TRIP pushbutton.
LOCK OR RESET HS-B31-1S30A Determines speed is not increasing rapidly and locking scoop tube is NOT required.
Observe Green light above LOSS B31-1S12A pushbutton EXTl NGU I SHED.
OF FW PP RUNBK RESET HS-Verifies:
Green light NOT LIT
~
~~
Comments STCP-CIA-I 256 Rev 2 (9193)
. 1 LV"*
t. 8. U L,\\U,,, I \\".. -
Appl. To/JPM No.: S/RO 64.0P.004.153 Step
- ?6B
- 17B 18B I
PERFORMANCE CHECKLIST Page 11 of 13 Action
-~
Establish speed control for RRP B.
EVALUATOR CUE:
If necessary provide candidate with recirc pump RPM select MPS (Monitored Parameter Summary) to view speed values. Booth operator to provide to examiner when student requests speeds. (IMP RRN!P401A and IMP RRNI P401 B)
Candidate may observe loop flow to confirm control.
FAULT STATEMENT:
RRP B WILL EXPERIENCE AN UNCONTROLLED SPEED INCREASE AFTER THE CANDIDATE HAS RESET THE RUNBACK.
Reset limiter #2 runback for RRP B.
Monitor GEN 1 B speed.
Student Name:
Standard To prevent pump speed from changing when Limiter #2 reset, Ensure GEN 1B DEMAND adjusted such that GEN 1B SPEED decreases when controller DEMAND is decreased.
For RRP B:
Depresses the DEC pushbutton on Reactor Recirc Pump B SY-B31-1 R621 B controller until Gen 1 B Demand XI-14032B and Gen 1 B Speed SI-14032B start to decrease.
Depress LOSS OF FW PP RUNBK pushbutton.
RESET HS-B31-1 SI 2B Monitor GEN 1 B SPEED SI-14032B.
Determines RRP B speed is increasing.
Eva1 Comments
- Critical Step
- Critical Sequence STCP-CIA-1258 Rev 2 (9193)
O""",.., 3
Appl. To/JPM No.: S/RO 64.0P.004.153 Step
- I 9B 20B
- Critical Step
/I PERFORMANCE CHECKLIST Page 12 of 13 Action If RRP B speed increases rapidly, lock scoop tube.
Verify RRP B limiter #2 is reset by light indication.
- Critical Sequence Student Name:
Standard IF speed increases rapidly, Trip scoop tube on affected generator by depressing SCOOP TUBE B TRIP pushbutton.
LOCK OR RESET HS-B31-1S03B Depresses the SCOOP TUBE B TRIP pushbutton.
LOCK OR RESET HS-B31-1S03B AND Verifies annunciator AR-102-D05, RECIRC MG B SCOOP TUBE DRIVE LOCK is LIT.
Observe Green light above LOSS B31-1S12B pushbutton EXTl N G U ISH ED.
OF FW PP RUNBK RESET HS-Verifies:
Green light NOT LIT.
Eva1 Comments STCP-QA-1256 Rev 2(9/93)
Page 1 of 1
i PERFORMANCE CHECKLIST Page 13 of 13 Step 21 Appl. To/JPM No.: S/RO 64.0P.004.153 Action Check annunciator status.
EVALUATOR CUE:
This completes the JPM.
- Critical Step
- Critical Sequence Student Name:
Standard Check RECIRC A(B) FLOW LIMIT RUNBACK annunciator CLEARED.
Verifies annunciator SLOW FLASH for :
LIMIT RUNBACK.
AR-102-COI RECIRC A FLOW AND AR-102-CO4 RECIRC B FLOW LIMIT RUNBACK Eva1 Comments STCP-QA-1258 Rev 2.(9/93)
Paqe 1 of 1
TASK CONDITIONS:
i-A. The plant is in Mode 1.
B. Rods 18-23, 18-39,42-23, and 42-39, are fully inserted to support HCU maintenance on Rod 18-23.
C. A trip of CWP I D has caused a Reactor Recirculation runback to occur.
D. NO Operator actions have been taken.
INITIATING CUE:
Respond to a loss of reactor recirculation flow and reset recirculation pump runback in accordance with appropriate Off Normal procedure.
2003 NRC Exam Rev. 2 I
of2
TASK CONDITIONS:
--I A. The plant is in Mode 1.
B. Rods 18-23, 18-39, 42-23, and 42-39, are fully inserted to support HCU maintenance on Rod 18-23.
C. A trip of CWP I D has caused a Reactor Recirculation runback to occur.
D. NO Operator actions have been taken.
INITIATING CUE:
Respond to a loss of reactor recirculation flow and reset recirculation pump runback in accordance with appropriate Off Normal procedure.
2003 NRC Exam Rev. 2 2 of 2
PENNSYLVANIA POWER & LIGHT COMPANY JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET SIR0 30.S0.001.I51 0
811 4/03 290003 A3.01 3.313.5 Appl. To JPM Number Rev. No.
Date NUREG 1123 Sys. No.
K/A Task
Title:
COMPLETE MONTHLY CONTROL ROOM EMERGENCY OUTSIDE AIR SUPPLY SYSTEM OPERABILITY TEST Completed By:
Reviews:
Russ Halm 811 4/03 811 4/03 Writer Date InstructorNVriter Date Ap p rova I:
Requesting Supv.1C.A.
Date Nuclear Trng. Supv.
Date Head Date of Performance:
JPM Performed By:
10 Allowed Time (Min.)
Time Taken (Min.)
Student Name:
Last First M.I.
Employee #/S.S. #
Performance Eva I u a t i o n :
(
)
Satisfactory
) Unsatisfactory Evaluator Name:
Signature Typed or Printed Comments:
STCP-QI-1258 Rev. 2. ( 9 B )
Page1 of1 2003 NRC Exam Rev. 2
REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE SlRO 30.S0.001.I 51
- 1.
SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.
B. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example:
- 1. Whenever any electrical panel is opened for inspection during JPM performance.
- 2. Whenever entering any plant area where specific safety equipment; such as hearing or eye protection, safety shoes, hardhats, etc; is required and/or posted as being necessary.
C. If in the judgement of the evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.
II. REFERENCES A. SO-030-001 B. AR-029-001 Control Structure, SGTS, DG and ESW PH Ventilation (Rev. 21)
Monthly Control Room Emergency Outside Air Supply System Operability Test (Rev
- 11) 111. REACTIVITY MANIPULATIONS This JPM satisfies the requirements of Operational Activity(s):
None IV. TASK CONDITIONS A. Unit I and Unit 2 are operating normally in Mode 1.
B. The A CREOASS charcoal has been replaced.
C. The A train of CREOASS has successfully completed 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> of run time per the monthly surveillance.
V. INITIATING CUE Shutdown the A CREOASS Fan per SO-030-001 Monthly Control Room Emergency Outside Air Supply System Operability Test.
VI. TASK STANDARD Shutdown the A CREOASS Fan, and place the B CREOASS fan in AUTO LEAD.
STCP-QA-125B Rev. 2, (9193)
Page 1 of 1 2003 NRC Exam Rev. 2
VILTASK SIGNIFICANCE Failure to place the B CREOASS Fan to AUTO LEAD would delay or prevent auto initiation of the CREOASS system resulting in unanalyzed plant condition. The unanalyzed condition could result in excessive dose to the Control Room Operators STCP-QA-1256 Rev. 2, (9B3)
Page 1 of 1 2003 NRC Exam Rev. 2
Appl. To/JPM No.: S/RO 30.S0.001.151 Step 1
PERFORMANCE CHECKLIST Page 4 of 7 Action EVALUATOR:
Prior to performing this JPM, obtain a copy of the latest revision of SO-030-001 and mark it as if it was actually to be performed. Fill out surveillance up to the point of shutting down the fan step 5.10 0
If this JPM is performed in the simulator establish task conditions as directed on attached setup instructions.
When student is ready to begin JPM, place the Simulator in RUN.
The FAULTED step in this JPM is preceded by a fault statement in BOLD TYPE WITH ALL CAPITAL LETTERS.
Review surveillance complete with acceptance criteria satisfactorily signed.
- Critical Step
- Critical Sequence Student Name:
Standard Reviews acceptance criteria properly documented.
Reviews system flow indication and reviews the procedure data record is filled out properly.
Eva1 Comments STCP-QA-1256 Rev. 2, (9/93)
~.. _..
-il-2003 NEG Exarri Rev. Z
Appl. To/JPM No.: S/RO 30.S0.001.151 Step
- 2 3
4 PERFORMANCE CHECKLIST Page 5 of 7 Action FAULT STATEMENT: A CREOASS fan will experience a trip of the thermal overloads shortly after the control switch is taken to the STOP pos it ion.
Shutdown operating CREOASS unit by PLACING Selector Switch for CREOASS Fan OVlOlA to STOP.
CS EMERG OA SUP FAN FAILED (AOI) alarm is received.
EVALUATOR NOTE:
Candidate may continue following the surveillance procedure after the above CS EMERG OA SUP FAN FAILED (AOI) alarm is received confirming indications and damper positions. After confirming indications the candidate will investigate the CS EMERG OA SUP FAN FAILED (A01) alarm.
Investigate AR-029-001 alarm by performing the following.
- Critical Step
- Critical Sequence Student Name:
Standard Rotate the A CREOASS fan control switch counterclockwise to the stop positions and notes:
Verifies RED Light NOT LIT, AMBER Light LIT Reviews AR-029-001 (AOI) for probable cause and operator actions (attached).
Eva1 Comments
Appl. To/JPM No.: S/RO 30.S0.001.151 Step 5
6 7
PERFORMANCE CHECKLIST Page 6 of 7
~~
~
Action CHECK CREOASS FAN OV101A tripped.
CHECK EOASS FAN OVIOI B starts (if initiation signal present).
CHECK CEOASS Fan OVIOIA supply breaker MCC OBI 36063, thermal overloads and control power fuse.
EVALUATOR CUE:
Role play as field operator and acknowledge request to check supply breaker at MCC OBI 36063.
Reply: Thermal overloads at supply breaker OBI 36063 are tripped.
- Critical Step
- Critical Sequence Student Name:
I Standard Notes loss of light indication above Selector Switch for CREOASS Fan OV1 OIA, Verifies RED Light NOT LIT, WHITE light NOT LIT, AMBER Light NOT LIT, notes alarm response indicates that a loss of control power will cause the alarm.
Notes no initiation signal present.
Dispatches an operator to check thermal overloads at supply breaker OBI 36063 Eva1 Comments
Appl. To/JPM No.: SIR0 30.S0.001.151 Step 8
9 10
- I 1
PERFORMANCE CHECKLIST Page 7 of 7 Action CHECK HD07812A, HD07814A, HD07811A position.
If fan tripped after starting time delay, CHECK fan integrity if accessible.
COMPLY with TS 3.7.3 and 3.7.4.
If CREOASS Fan OVIOIA was in auto lead, place CREOASS Fan OVIOIB in auto lead.
EVALUATOR:
This completes the JPM.
- Critical Step
- Critical Sequence Student Name:
-~
Standard Verifies dampers are in the correct position for a shutdown CREOASS train.
Verifies closed (Red light out, Amber light lit):
CREOASS A(B) Inlet Dmp HD07812A CREOASS Inlet Dmp HD07814A CREOASS Dsch Dmp HD0781 I A Recognizes fan did not trip after starting time delay.
Informs Unit Supervisor to check the Technical Specification TS 3.7.3 and 3.7.4.
Places OVIOI 6 CREOASS fan in AUTO LEAD.
Comments
PERFORMANCE CHECKLIST Page 7 of 7 Appl. To/JPM No.: SIR0 30.S0.001.151
=
Step 8
9 10
- I I
Action CHECK HD07812A, HD07814A, HD0781 I A position.
If fan tripped after starting time delay, CHECK fan integrity if accessible.
COMPLY with TS 3.7.3 and 3.7.4.
If CREOASS Fan OVlOlA was in auto lead, place CREOASS Fan OVIOI B in auto lead.
EVALUATOR:
This completes the JPM.
- Critical Step Student Name:
~~
Standard Verifies dampers are in the correct position for a shutdown CREOASS train.
Verifies closed (Red light out, Amber light lit):
CREOASS A(B) Inlet Dmp HD07812A CREOASS Inlet Dmp HD07814A CREOASS Dsch Dmp HD07811A Recognizes fan did not trip after starting time delay.
Informs Unit Supervisor to check the Technical Specification TS 3.7.3 and 3.7.4.
Places OVI 01 B CREOASS fan in AUTO LEAD.
Eva1 Comments
- Critical Sequence
TASK CONDITIONS A. Unit 1 and Unit 2 are operating normally in Mode 1.
B. The A CREOASS charcoal has been replaced.
C. The A train of CREOASS has successfully completed 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> of run time per the monthly surveillance.
INITIATING CUE Shutdown the A CREOASS Fan per SO-030-001 Monthly Control Room Emergency Outside Air Supply System Operability Test.
2003 NRC Exam Rev. 1 Page 1 of 2
TASK CONDITIONS A. Unit 1 and Unit 2 are operating normally in Mode 1.
B. The A CREOASS charcoal has been replaced.
C. The A train of CREOASS has successfully completed 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> of run time per the monthly surveillance.
INITIATING CUE Shutdown the A CREOASS Fan per SO-030-001 Monthly Control Room Emergency Outside Air Supply System Operability Test.
2003 NRC Exam Rev. 1 Page 2 of 2
CS EMERG OA SUP FAN FAILED (A01 )
A01 SETPOINT:
5000 cfm ORIGIN:
62FSLX-07811A ( FSLO7811A ) or 74-1 36063 overload
- 1.
PROBABLE CAUSE:
- 1. I Fan Motor overload or electrical fault.
1.2 Mechanical failure of fan.
1.3 Loss of fan control power.
1.4 FD07816A not working properly.
1.5 HD07812A, HD07814A, HD07811A not open.
- 2.
OPERATOR ACTION:
2.1 2.2 2.3 2.4 2.5 2.6 2.7 CHECK EOASS FAN OVIOIA tripped.
CHECK EOASS FAN OVI 01 B starts (if initiation signal present).
CHECK EOASS Fan OVIOIA supply breaker MCC OB136063, thermal overloads and control power fuse.
CHECK HD07812A, HD07814A, HD0781 I A position.
If fan tripped after starting time delay, CHECK fan integrity if accessible.
COMPLY with TS 3.7.3 and 3.7.4.
If creoass fan OV101A was in auto lead, place creoass fan OVIOI B in auto lead.
- 3.
AUTOMATIC ACTION:
3.1 EOASS FAN OVl 01 B starts (if initiation signal present)
- 4.
REFERENCE:
4.1 E-332 4.2 E-I97 4.3 VC-178 4.4 V-178 4.5 TS 3.7.3 and 3.7.4.
2003 NRC Exam Rev. 1
PENNSYLVANIA POWER & LIGHT COMPANY JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET SIR0 64.0N.005.101 2
06/17/03 202001 A2.10 3.513.9 Appl. To JPM Number Rev. No.
Date NUREG 1123 Sys. No.
WA Task
Title:
Respond To A Reactor Recirculation Pump Dual Seal Failure IAW ON-164-003 Completed By:
Reviews:
Russ Halm 0611 7/03 Writer Date InstructorNVriter Date Approval:
Requesting Supv.1C.A.
Date Nuclear Trng. Supv.
Date Head 20/30 Date of Performance:
Allowed Time (Min.)
Time Taken (Min.)
JPM Performed By:
Student Name:
Last First M.I.
Employee #/S.S. #
Performance
(
)
Satisfactory
(
)
Unsatisfactory Evaluation:
Evaluator Name:
Signature Typed or Printed Comments:
STCP-QA-125B Rev. 2, (9/93)
Page 1 of 1 2003 NRC Exam Rev. 2 File No. A14-5B
REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE SlRO 64.0N.005.101
- 1.
SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.
B. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example:
- 1. Whenever any electrical panel is opened for inspection during JPM performance.
- 2. Whenever entering any plant area where specific safety equipment; such as hearing or eye protection, safety shoes, hardhats, etc; is required and/or posted as being necessary.
C. If in the judgement of the evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.
II. REFERENCES A. ON-I 64-003, Reactor Recirculation Pump Dual Seal Failure (Rev. 15)
B. AR-102-GOI, RECIRC PUMP A SEAL LEAKAGE HI FLOW (Rev.21)
C. AR-102-G02, RECIRC PUMP A SEAL STAGE HI-LO FLOW (Rev.21) 111. REACTIVITY MANIPULATIONS This JPM satisfies the requirements of Operational Activity(s):
B. 33 10 Percent Power Change (RoddRecirc)
'v A. 28 Reactor Recirc Pump Dual Seal Failure IV. TASK CONDITIONS A. The plant is in Mode 1 at approximately 44 percent reactor power B. You are the PCOM and will operate all controls for this event.
V. INITIATING CUE Respond to all alarms received on IC651 panel and take appropriate actions.
VI. TASK STANDARD
'A' Reactor Recirculation Pump shutdown and isolated.
VII.TASK SAFETY SIGNIFICANCE Identify and isolate RCS leakage.
Inability to recognize and isolate a dual seal failure would result in excessive leakage into containment with potential for high drywell pressure alarm, ECCS initiation signals and Containment isolations.
.\\-
STCP-QA-1258 Rev. 2. (9193)
Page 1 of 1 2003 NRC Exam Rev. 2
Appl. To/JPM No.: S/RO 64.0N.005.101 Step PERFORMANCE CHECKLIST Action EVALUATOR NOTE:
0 This JPM must be performed in the simulator.
Establish task conditions as directed on attached setup instructions.
When candidate is ready to begin JPM, place the simulator in RUN and Depress P-I.
0 Acknowledge and respond to alarms.
EVALUATOR NOTE:
Candidate should use the alarm response procedures to diagnose the dual seal failure.
The candidate will need the next evaluator cue to make this diagnosis.
EVALUATOR CUE:
Inform the candidate when investigating leak rate by looking at the recorders for Drywell leakage that leakage indicates greater than I GPM
- Critical Step
- Critical Sequence Student Name:
Page 3 of 11 Standard Checks RECIRC PP A and B SEAL CAVITY 2 pressure indicators PI-B31-I R602A and 3A.
Refers to AR-102-GO1 and AR-102-G02.
Determines that 'A RRP has the dual seal failure.
Eva1 Comments STCP-QA-1258 Rev. 2. (9/93)
Page 1 of 1
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Appl. To/JPM No.: S/RO 64.0N.005.101 Step 3
4 5
PERFORMANCE CHECKLIST Page 4 of 11
~
Action Sandidate locates procedure and refers to appropriate section.
Has Unit Supervisor record the date and time.
EVALUATOR CUE:
Inform the candidate the Unit Supervisor has signed and dated the procedure.
EVALUATOR NOTE:
Step 3.2 of the procedure directs the PCO to either determine the leak rate or obtain Shift Supervision approval to continue the procedure. If necessary instruct the student to continue with procedure.
Check if procedure should be continued.
EVALUATOR CUE:
Role play the SRO instruct the candidate to continue with procedure, ON-I 64-003, Reactor Recirculation Pump Dual Seal Failure.
- Critical Step
- Critical Sequence Student Name:
Standard
~~
3btains procedure 3N-164-003, Reactor Recirculation Pump Dual Seal Failure and refers to section 3.1.
Identifies Shift Supervision must sign to authorize implementation.
Informs supervisor that RCS leak rate check should be performed.
(SO-I 00-006 attachments E and F)
AND Requests direction for procedure completion.
Eva1 Comments
Appl. To/JPM No.: S/RO 64.0N.005.101 Step
- Critical Step PERFORMANCE CHECKLIST Action Chack drywell pressure rate of increase EVALUATOR CUE:
IF necessary, Role play the SRO instruct the candidate for the purposes of this JPM, drywell pressure is NOT increasing rapidly.
Selects the correct procedure section.
Checks if power reduction is required.
CAUTl ON WHEN REDUCING RECIRC PUMP SPEED TO 30% RATED, PUMP SPEED SHOULD BE MAINTAINED AT APPROXIMATELY 500 RPM. SPEED OSCILLATIONS ARE POSSIBLE WHEN THE PUMP IS OPERATED 460 - 485 RPM.
- Critical Sequence Student Name:
i:
Page 5 of 11 Standard Checks any drywell pressure indicator and determines drywell pressure is NOT increasing rapidly.
Selects Section 3.4.
Checks APRMs and core flow indications.
Plots position on the Power/Flow Map to ensure power is below the 70 percent Rod Line.
Determines power reduction is not required.
Eva1 Comments STCP-QA-1258 Rev. 2, (9193)
Page 1 of 1 enfir, h l h. ^, 7 m -.
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Appl. To/JPM No.: S/RO 64.0N.005.101 Step
- 9
- I 0 I 1 i'
PERFORMANCE CHECKLIST Page 6 of I 1 Action Redxe I A RRP speed to 30%.
Shutdown I A RRP.
Determine actual core flow.
- Critical Step
- Critical Sequence Student Name:
Standard Depresses DEC pushbutton on REACTOR B31-lR621A until GEN ?A SPEED SI-14032A DECREASES to 30%.
RECIRC PUMP A SPEED CONTROLLER SY-Depresses STOP pushbutton on MG SET A DRV MTR BKR HS-14001A.
Determines position on power to flow map:
0 0
0 0
0 Determines 'B' RRP speed is <75% using GEN I B Speed SI-140-328.
Uses PlCSY display to obtain computer point NJP51-Core PI Press.
Plots core plate d/p on form GO-I 00-009-2, Core Flow vs Core Pressure Drop.
Determines core flow value is 42-43,000 Ibm/hr.
Plots position on Power to Flow Map using above value and current power.
Determines position is below the 70% rod line.
Eva1 Comments STCP-QA-1256 Rev. 2. (9193)
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i' PERFORMANCE CHECKLIST Appl. To/JPM No.: S/RO 64.0N.005.101 Step 12 13 14 Action Jerify 1A RRP stops.
Comply with COLR.
VALUATOR CUE:
Role play the SRO and instruct candidate that you will reference section 8 of the COLR for compliance.
Comply with Tech Spec LCOs 3.4.1.
EVALUATOR CUE:
Role play the SRO and instruct candidate that you will reference Tech Spec LCOs 3.s.I for compliance.
- Critical Step
- Critical Sequence Student Name:
Page 7 of 11 Standard Checks Amber light LIT Red light NOT LIT MG SET A DRV MTR BKR HS-14001A GEN 1A SPEED SI-14032A DECREASES to 20 (Bottom scale)
After -20 seconds GENERATOR 1A FIELD BREAKER Amber light LIT Red light NOT LIT Candidate informs Unit Supervisor of the need to reference section 8 of the COLR for compliance.
Candidate informs Unit Supervisor of the need to reference Tech Spec LCOs 3.4.1 for compliance.
Comments
it' PERFORMANCE CHECKLIST Appl. To/JPM No.: S/RO 64.0N.005.101 Step
- I 5
- I6 "Critical Step Student Name:
Action EVALUATOR NOTE:
The following steps will isolate the leaking seals and they must be completed in the order listed.
Valves HV-143-F023A, HV-144-FIOO, HV-143-F031 A, and HV-143-FO32A have long stroke times (60-120 seconds).
Close suction valve.
Close RWCU suction from loop A.
- Critical Sequence i:
Page 8 of 11 Standard Depresses Close pushbutton on RECIRC PUMP A SUCT HV-143-FO23A.
Verifies Amber light LIT Red light NOT LIT Depresses Close pushbutton on RWCU SUCT LOOP A HV-144-Fl00.
Verifies Amber light LIT Red light NOT LIT Eva1 Comments STCP-QA-125B Rev. 2. (9/93)
Page 1 of 1 3nn3 h i m r c.,,.._.
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Appl. To/JPM No.: S/RO 64.0N.005.101 Step
- I 7
- I 8
- I 9 20 PERFORMANCE CHECKLIST Action Place bypass switch to TEST.
Close discharge valve.
Close discharge bypass.
After 2 minutes Return bypass switch to NORM.
- Critical Step
- Critical Sequence Student Name:
Page 9 of 1 I Standard Locates and inserts key in RECIRC A MOV OL BYPS HV-143-FO31A and places to TEST position.
Verifies:
Status light RECIRC SYS A DISCHARGE Alarm AR-102-102 RECIRC LOOP A DISCHARGE VALVES IN TEST actuated VALVES IN TEST - LIT Depresses Close pushbutton on RECIRC PUMP A DSCH HV-143-FO31A.
Verifies Amber light LIT Red light NOT LIT Depresses Close pushbutton on RECIRC PUMP A DSCH BYPS HV-143-FO32A.
Verifies Amber light LIT Red light NOT LIT After 2 minutes Places RECIRC A MOV OL BYPS HV-143-F031A switch to NORM position.
Eva1 Comments STCP-QA-1 25B Rev. 2, (9/93)
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Page 10 of 11 Standard Contacts NPO on radio or plant page, and requests CRD Water Supply to Unii 1 RRP A IS0 143F008A closed.
Appl. To/JPM No.: S/RO 64.0N.005.101 Student Name:
Step
~
- 2 1 22 Close CRD water supply.
BOOTH CUE:
Acknowledge request to close CRD Water Supply to RRP A IS0 143F008A.
Wait 2 minutes and Depress P-2 Then Contact CR and report CRD Water Supply to Unit I RRP A IS0 143F008A is closed.
EVALUATOR CUE:
This completes the JPM.
EVALUATOR CUE:
FOR SRO CANDIDATES ONLY Give the SRO candidate the second cue sheet that addresses the Tech Spec LCO for Recirculation Loops Operating References Tech Specs Obtains copy of Unit 1 Tech Specs
- Critical Step
- Critical Sequence Eva1 Comments STCP-QA-125B Rev. 2. (9/93)
Page 1 of 1
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Appl. To/JPM Step
- 23
- Critical Step Jo,: S/RO 64.0N.005.101 Action PERFORMANCE CHECKLIST 1;'
Page 11 of 11 Determines Tech Spec 3.4.1 required actions EVALUATOR CUE:
This completes the JPM.
- Critical Sequence Student Name:
Standard Determines Tech Spec 3.4.1 required actions:
Verify the following core thermal power limits within the limits specified in the COLR.
LCO 3.2.1 APLHGR LCO 3.2.2 MCPR LCO 3.2.3 LHGR Verify LCO 3.3.1.I RPS instrumentation function 2.b allowable value of table 3.3.1.1-1 is reset for single loop operation.
Within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> declare the 1A loop inoperable Eva1 Comments STCP-QA-1258 Rev. 2, (9193)
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SRO ONLY TASK CONDITIONS During the performance of this JPM, the procedure directed you to reference Tech Spec LCO 3.4.1 for compliance.
INITIATING CUE Assuming we will remain at the current power level for the next 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />s:
Refer to Tech Spec LCO 3.4.1 and identify all actions necessary to comply with this Tech Spec.
Page I of 4 STCP-QA-1256 Rev. 2. (9193)
Page 1 of 1 2003 NRC Exam Rev. 2
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SRO ONLY TASK CONDITIONS During the performance of this JPM, the procedure directed you to reference Tech Spec LCO 3.4.1 for compliance.
INITIATING CUE Assuming we will remain at the current power level for the next 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />s:
Refer to Tech Spec LCO 3.4.1 and identify all actions necessary to comply with this Tech Spec.
Page 2 of 4 STCP-QA-1258 Rev. 2, (9/93)
Page 1 of 1 2003 NRC Exam Rev. 2
TASK CONDITIONS A. The plant is in Mode 1 at approximately 44 percent reactor power.
B. You are the PCOM and will operate all controls for this event.
INITIATING CUE Respond to all alarms received on 1 C651 panel and take appropriate actions.
'L-'
Page 3 of 4 STCP-QA-1258 Rev. 2. (9/93)
Page 1 of 1 2003 NRC Exam Rev. 2
TASK CONDITIONS A. The plant is in Mode I at approximately 44 percent reactor power.
B. You are the PCOM and will operate all controls for this event.
INITIATING CUE Respond to all alarms received on 1 C651 panel and take appropriate actions.
Page 4 of 4 STCP-QA-125B Rev. 2. (9/93)
Page 1 of 1 2003 NRC Exam Rev. 2
PENNSYLVANIA POWER & LIGHT COMPANY JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET S/RO 51.OP.002.152 1
06/17/03 209001 A2.01 3.813.7 Appl. To JPM Number Rev. No.
Date NUREG 1123 Sys. No.
WA Task
Title:
Perform Manual Startup Component by Component of Core Spray System in Accordance With OP-151-001 Completed By:
Reviews:
Russ Halm 06/17/03 Writer Date InstructorNVriter Date App rova I:
Requesting Supv./C.A.
Date Nuclear Trng. Supv.
Date Head Y-20 Date of Performance:
Allowed Time (Min.)
JPM Performed By:
Student Name:
Last First M.I.
Performance Evaluation:
Time Taken (Min.)
Employee #/S.S. #
(
)
Satisfactory
(
)
Unsatisfactory Evaluator Name:
Signature Typed or Printed Comments:
Form STCP-QA-12SA Rev. 4, (OS/OO)
Page I of 1 2003 NRC Exam Rev. 2 File No. A14-5B
REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE SIR0 51.OP.002.152
- 1.
SAFETY CONSIDERATIONS v
A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.
B. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example:
- 1. Whenever any electrical panel is opened for inspection during JPM performance.
- 2. Whenever entering any plant area where specific safety equipment; such as hearing or eye protection, safety shoes, hardhats, etc; is required and/or posted as being necessary.
C. If in the judgement of the evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.
II. REFERENCES A. OP-I 51-001 Core Spray System (Revision 24)
II I. REACTIVITY MAN I PULATIONS This JPM satisfies the requirements of Operational Activity@):
None IV. TASK CONDITIONS A. The Core Spray System is aligned for automatic initiation in accordance with OP-I 51 -001, B. A LOCA has occurred.
C. Generator lockouts have been reset.
D. CS System failed to auto initiate.
V. INITIATING CUE Manually initiate both loops of core spray.
VI. TASK STANDARD Both loops of core spray injecting into the RPV.
VILTASK SAFETY SIGNIFICANCE Initiate adequate core heat removal.
Failure to perform this task could result in inadequate core decay heat removal and possible fuel clad damage.
FormSTCP-QA-125A Rev. 4, (05/00)
Page I of I 2003 NRC Exam Rev. 2
Appl. To/JPM No.: S/RO 51.OP.002.152 Step 1
2
- 3 PERFORMANCE CHECKLIST Page 3 of 8 Action EVALUATOR NOTE:
0 This JPM must be performed in the simulator.
Establish task conditions as directed on attached setup instructions.
The FAULTED step in this JPM is preceded by a fault statement in BOLD TYPE WITH ALL CAPITAL LETTERS.
When candidate is ready to begin JPM, place the simulator in RUN.
Locates procedure and refers to appropriate section.
Reviews prerequisites and precautions.
Initiate A Loop of Core Spray.
EVALUATOR NOTE:
The following annunciator alarms, AR-109-A01 (Core Spray Loop A Initiation Switch Armed).
Student Name:
Standard Obtains procedure OP-l51-001 Core Spray System and refers to section 3.3.
Reviews prerequisites and precautions.
Rotates the collar on Core Spray Loop A MAN INlT HS-E21-1 S I 6A pushbutton to the ARMED position.
Verifies that AR-109-AOI. Core Spray Loop A Man lnit Switch Armed, annunciator alarms.
Depress Core Spray Loop A MAN INlT HS-E21-1 S16A pushbutton.
Verifies CORE SPRAY LOOP A ACTUATED alarm LIT.
Eva1 Comments
- Critical Step
- Critical Sequence Form STCP-QA-125A Rev. 4, (0900) rnw 1 cf 1
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Appl. TolJPM No.: SlRO 51.OP.002.152 Step r:
PERFORMANCE CHECKLIST Action EVALUATOR NOTE:
In an effort to initiate both loops of core spray as quickly as possible, the candidate may elect to initiate loop B spray by performing steps 7-1 3 of this JPM before completing steps 4-6. This is acceptable.
Observe response of other systems to initiation of core spray.
Observe core spray system response.
- Critical Step Form STCP-QA-IZSA Rev. 4, (OSfOO)
Page I of I T.n h _I.
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- Critical Sequence Student Name:
Standard Verifies:
DG A started by observing DG voltage A DW unit cooler fans running in FAST trip Red high speed fast light-NOT LIT Verifies:
I P206A and C running.
Amber light NOT LIT Red light LIT CORE SPRAY LOOP A INlT SIG RESET HS-E21 -1 S I 7A Green light LIT CORE SPRAY LOOP A IB INJ SHUTOFF HV-152-FO05A open.
Amber light NOT LIT Red light LIT Page 4 of 8 Comments
{"
Appl. TolJPM No.: SlRO 51.OP.002.152 Step 6
r" PERFORMANCE CHECKLIST Page 5 of 8 Action CAUTION AVOID POTENTIAL PUMPlMOTOR DAMAGE, CORE SPRAY LOOP A(B) INJ SHUTOFF HV-152F005A(B) MUST BE THROTTLED AS NECESSARY TO PREVENT EXCEEDING MAXIMUM PUMP RUN OUT CURRENT OF 90 AMPS PER PUMP.
Verifies injection flowrate.
Student Name:
Standard CORE SPRAY LOOP A OB INJ SHUTOFF HV-152-FO04A open.
Amber light NOT LIT Red light LIT CORE SPRAY LOOP A TEST TO SUPP POOL HV-152-FOI 5A closed.
Amber light LIT Red light NOT LIT CORE SPRAY LOOP A MIN FLOW HV-152-F031A closed.
Amber light LIT Red light NOT LIT CS Unit Coolers 1V21 I A and C as indicated on 1 C681 running.
Red light LIT Amber and white lights NOT LIT Observes flowrate on FI-E21-I R601A.
Eva1 Comments
- Critical Step
- Critical Sequence Form STCP-QA-125A Rev 4, (OYOO)
Paee 1 of I
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Appl. To/JPM No.: S/RO 51.0P.002.152 Step Actinn
~. - -. -..
FAULT STATEMENT LOOP B CORE SPRAY FAILS TO INITIATE WHEN THE MANUAL PUSHBUTTON IS ARMED AND DEPRESSED.
Initiate B Loop of Core Spray.
EVALUATOR NOTE:
The following annunciator alarms, ARI 13-A01 (Core Spray-Loop B Initiation Switch Armed).
EVALUATOR CUE As Unit Supervisor acknowledge notification of division 2 Core Spray initiation failure.
Transitions to appropriate section of the procedure.
EVALUATOR NOTE:
Manual startup component by component of B Loop of CS System will be accomplished in the following steps.
PERFORMANCE CHECKLIST Page 6 of 8 Student Name:
Standard Rotates the collar on Core Spray Loop B MAN INlT HS-E2l-ISlGB pushbutton to the ARMED position.
Notes that AR-113-AOI, Core Spray Loop B Man Init Switch Armed, annunciator alarms.
Depress Core Spray Loop B MAN INlT HS -
E21-1S16B pushbutton.
Notes that Core Spray Loop B failed to initiate.
Informs Unit Supervisor division 2 manual initiation has failed.
Notes Manual Startup required for B Loop Core Spray.
Moves to section 3.3.4 of procedure OP-I 51-001 Core Spray System.
Eva1 Comments
- Critical Step
- Critical Sequence Form STCP-QA-IZSA Rev. 4, (OYOO)
Page t of 1 qnn? h-DP F....__
n... q j.....,.. L L.. L *. -,. -
i Appl:To/JPM No.: S/RO 51.OP.002.152 Step 9
10 1 1
- I 2 13 PERFORMANCE CHECKLIST Action Start Core Spray Pumps B and D.
Open or check open OB INJ SHUTOFF HV-152-FO04B.
When Reactor pressure 5436 psig, place LO F U PRESS PERM Switch HS-I 52-1 52498 to BYPASS.
EVALUATOR NOTE:
When HS for HV-152-FO05B taken to OPEN position; red light on.
0 When CS system flow 2635 gpm F031B; amber light on.
THROTTLE OPEN CORE SPRAY LOOP B IB INJ SHUTOFF HV-152-FOO5B to establish loop flow 56,350 gpm for two-pump operation.
Verifies injection flowrate.
- Critical Step Form STCP-QA-125A Rev 4, (OYOO)
Page 1 of 1 1 1 1 1 1 1 X K I I \\,Ill1 t<l\\l I
- Critical Sequence Student Name:
(,
Page 7 of 8 Standard Place the HS for 1 P206B and D to the START position.
Verifies:
Amber lights NOT LIT; Red lights LIT Verifies that HV-152-FOO4B open.
Amber light NOT LIT Red light LIT When Reactor pressure 5436 psig, removes cover and places HS-15249B to BYPASS.
Verifies MIN FLOW HV-152-FO31 B closes dy Checking Amber light LIT Red light NOT LIT Throttles open HV-152-FO05B Observes flowrate on FI-E21-1 R601 B.
Eva1 Comments
Appl. To/JPM No.: S/RO 51.0P.002.152 Step 14 PERFORMANCE CHECKLIST Action Check CS room coolers BID AUTO starts.
EVALUATOR CUE:
This completes the JPM.
- Critical Step Form STCP-QA-IZSA Rev. 4, (OS/oO)
Page I of I
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- Critical Sequence Student Name:
Standard Check CS Unit Coolers 1V21 I B and D AUTO START as indicated on 1 C681.
Verifies:
Red light LIT Amber and white lights NOT LIT 1;
Page 8 of 8 Eva1 I Comments
TASK CONDITIONS A. The Core Spray System is aligned for automatic initiation in accordance with OP-I 51 -001.
B. A LOCA has occurred.
C. Generator lockouts have been reset.
D. CS System failed to auto initiate.
INITIATING CUE Manually initiate both loops of core spray.
Page I of 2 Form STCP-QA-IZSA Rev. 4, (OSlOO) page 1 of 1 2003 NRC Exam Rev. 2
TASK CONDITIONS A. The Core Spray System is aligned for automatic initiation in accordance with OP-151-001.
B. A LOCA has occurred.
C. Generator lockouts have been reset.
D. CS System failed to auto initiate.
INITIATING CUE Manually initiate both loops of core spray.
Page 2 of 2 Form STCP-QA-IZSA Rev 4, (OSIOO)
Page I of I 2003 NRC Exam Rev. 2
-v' PENNSYLVANIA POWER & LIGHT COMPANY JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET S/RO 84.ON.003. I 01 I
06/17/03 239001 A4.01 4.2/4.0 Appl. To JPM Number Rev. No.
Date NUREG 1123 Sys. No.
WA Task
Title:
Main Steam Line Isolation and Quick Recovery in Accordance With ON-184-001 Completed By:
Reviews:
Russ Halm 06/17/03 Writer Date InstructorNVriter Date Approval:
Requesting Su pv./C. A.
Date Nuclear Trng. Supv.
Date Head Date of Performance:
50 Allowed Time (Min.)
Time Taken (Min.)
JPM Performed By:
Student Name:
Last First M.I.
Employee #/S.S. #
Performance
(
)
Satisfactory
(
)
Unsatisfactory Evaluation:
Evaluator Name:
Signature Typed or Printed Comments:
STCP-QA-125A Rev. 2. (9193)
Page 1 of 1 2003 NRC Exam Rev. 2 File No. A14-58
REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE S/RO 84.0N.003.101
- 1.
SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.
B. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example:
- 1. Whenever any electrical panel is opened for inspection during JPM performance.
- 2. Whenever entering any plant area where specific safety equipment; such as hearing or eye protection, safety shoes, hardhats, etc; is required and/or posted as being necessary.
C. If in the judgement of the evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.
II. REFERENCES A. ON-184-001 I MAIN STEAM LINE ISOLATION AND QUICK RECOVERY (Rev. 6)
II I. REACTIVITY MAN1 PULATIONS This JPM satisfies the requirements of Operational Activity(s):
None IV. TASK CONDITIONS A. An MSlV isolation and reactor scram occurred from 100% reactor power.
B. The cause of the MSlV isolation was a faulty isolation logic surveillance test procedure.
C. HPCl and/or RClC injection is controlling reactor water level.
D. Reactor pressure is controlled by manual SRV actuation.
E. Restoration of normal steam loads and turbine bypass system is required for a reactor cooldown.
V. INITIATING CUE Perform a quick recovery from a Main Steam Line Isolation and reopen the MSIVs.
VI. TASK STANDARD MSlVs OPEN VII. TASK SAFETY SIGNIFICANCE Inability to reopen the MSlVs would eliminate a heat sink requiring additional unnecessary energy to be added to the Primary Containment.
\\.--
2003 NRC Exam Rev. 2
PERFORMANCE CHECKLIST Appl. To/JPM No.:
S/RO 84.0N.003.101 Step 1
2
- 3
~~
~
Action EVALUATOR NOTE:
This JPM should be performed in the Simulator.
Establish task conditions as directed on attached setup instructions.
When student is ready to begin JPM, place the Simulator in RUN.
Cdain a controlled copy of ON-I 84-001.
RECORD date and time of this event.
PLACE control switches for following to CLOSE:
0 Mn Stm Line A IB Is0 HV-141-FO22A 0
Mn Stm Line B IB Is0 HV-141-FO22B 0
Mn Stm Line C IB Is0 HV-141-FO22C 0
Mn Stm Line D IB Is0 HV-141-FO22D 0
Mn Stm Line A OB Is0 HV-141-FO28A 0
Mn Stm Line B OB Is0 HV-141-FO28B 0
Mn Stm Line C OB Is0 HV-141-FO28C 0
Mn Stm Line D OB Is0 HV-141-FO28D
- Critical Step
- Critical Sequence
('
page 3 ot 12 Student Name:
Standard Obtains Control copy of C. 00 Places the control switch to CLOSE for the following:
F022A F022B F022C F022D F028A F028B F028C F028D MN STM LINE A IB IS0 HV-141-MN STM LINE B IB IS0 HV-141-MN STM LINE C IB IS0 HV-141-MN STM LINE D IB IS0 HV-141-MN STM LINE A OB IS0 HV-141-MN STM LINE B OB IS0 HV-141-MN STM LINE C OB IS0 HV-141-MN STM LINE D OB IS0 HV-141-Eva1 Comments STCP-QA-1258 Rev. 2, (9/93)
Page 1 of 1
' I J ( J 1 \\ I < (
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r' PERFORMANCE CHECKLIST Page 4 of 12 Appl. To/JPM No.:
SlRO 84.0N.003.101 Step 4
5 6
7 Action ENSURE Mn Stm Line IB Drain HV-141-F016 CLOSED.
ENSURE Mn Stm Line OB Drain HV-141-F019 CLOSED.
ENSURE Mn Stm Line Drain to Cdsr HV-141-F021 CLOSED.
ENSURE following TRIPPED:
0 Main Turbine 0
0 Reactor Feed Pump Turbine A Reactor Feed Pump Turbine B Reactor Feed Pump Turbine C
- Critical Step
- Critical Sequence Student Name:
Standard Checks amber light LIT and red light NOT LIT for:
MN STM LINE IB DRAIN HV-141-FOI 6 Checks amber light LIT and red light NOT LIT for:
MN STM LINE OB DRAIN HV-141-FO19 Checks amber light LIT and red light NOT LIT for:
0 MN STM LINE IB DRAIN TO CDSR HV-141 -F02 1 For the Main Turbine:
0 Checks Main Turbine trip annunciation ON 0 Red Main Turbine Trip status light is LIT and the green Reset status light is NOT LIT.
For each RFP:
0 Checks RFP Trip annunciation LIT 0 Amber light is LIT and red light above the Trip & Reset switch NOT LIT Eva1 Comments
(
PERFORMANCE CHECKLIST Appl. To/JPM No.:
SIR0 84.0N.003.101 1::
Page 5 of 12 Student Name:
Step 8
9 10 Action If isolation due to EHC System malfunction:
0 DEPRESS standby EHC Hyd Fluid Pump 1 P I 13B(A) STOP push button.
0 DEPRESS operating EHC Hyd Fluid Pump I
P I 13A(B) STOP push button.
0 ENSURE Turbine main stop valves CLOSED.
ENSURE Turbine bypass valves CLOSED.
CLOSE following by depressing Drip Leg Drn HS-I 01 12 AUTO push button:
0 Drip Leg Drn HV-10112A1.
0 Drip Leg Drn HV-10112B1.
0 Drip Leg Drn HV-IOl12Cl.
Drip Leg Drn HV-10112D1.
CLOSE BPV Hdr Drip Leg Drn Byps HV-10108A by depressing HS-10108A AUTO push button.
- Critical Step
- Critical Sequence Standard Determines the isolation was not due to an EHC system malfunction.
(Based on initial conditions)
Depresses the AUTO pushbutton on Checks white light LIT and red light NOT LIT.
DRIP LEG DRN HS-10112.
Checks amber light LIT and red light NOT LIT for :
DRIP LEG DRAIN HV-10112A1 DRIP LEG DRAIN HV-10112B1 DRIP LEG DRAIN HV-lOI12C1 DRIP LEG DRAIN HV-10112D1 Depresses the AUTO pushbutton on HS-1 01 08A to CLOSE HV-I 01 08A.
AND Verifies the white light is LIT and the red light is NOT LIT.
Eva1 Comments STCP-CIA-125B Rev. 2, (9/93)
Page 1 of 1 i w 1. 3 !\\I\\!
r..\\iiiii i<c\\v. i
PERFORMANCE CHECKLIST i'
Page 6 of 12
?
Appl. To/JPM No.:
S/RO 84.0N.003.101 Step 11 12 13 14 15 Action CLOSE MSV Bst Drn HV-10101 A,B,C,D bv depressing common CLOSE push button. -
CLOSE SSE Mn Stm Sup CV HV-10703.
ENSURE SSE Mn Stm Sup Ln Drn HV-10767 CLOSED.
ENSURE SSE Mn Stm Sup Ln Drn HV-I0768 CLOSED.
CLOSE SSE Press Ctlr Is0 HV-10704,
- Critical Step
- Critical Sequence Student Name:
Standard Depresses the CLOSE pushbutton for MSV BST DRN HV-IOI~IA,B,C,D.
AND Verifies amber light LIT and red light NOT LIT.
Depress and hold the CLOSE pushbutton for SSE MN STM SUP C\\
HV-10703.
AND Verifies amber light LIT and red light NOT LIT.
Verifies amber light LIT and red light NOT LIT for SSE MN STM SUP LN Verifies amber light LIT and red light NOT LIT for SSE MN STM SUP LN DRN HV-10767.
DRN HV-10768.
Depresses the CLOSE pushbutton for SSE PRESS CTLR IS0 HV-10704.
AND Verifies amber light LIT and red light NOT LIT.
Eva1 Comments STCP-QA-1258 Rev. 2, (9193)
Page 1 of 1 3nn- -.-n~?-..
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Appl. TolJPM No.:
SIR0 84.0N.003.101 Step 16 17 "1 8 PERFORMANCE CHECKLIST Action THROTTLE OPEN SSE Press Ctlr Byps HV-I0705 to establish 0.25 to 0.50 psig on SSE Pressure PI-I 0723.
EVALUATOR CUE:
After HV-I0705 is throttled open several times inform the candidate PI-I0723 is reading 0.4 psig CLOSE Mn Stm SJAE Is0 HV-10107 When directed by Shift Supervision AND initiating event is determined and cleared, RESET NSSSS Main Steam Line Isolation by depressing:
EVALUATOR CUE:
As the Unit Supervisor direct resetting the NSSSS Main Steam Line Isolation.
Mn Stm Line Div 1 Is0 Reset HS-B21-1S32 Reset push button.
- Critical Step
- Critical Sequence Student Name:
~~
Standard THROTTLE OPEN SSE PRESS CTLR BYPS HV-10705 to establish 0.25 to 0.5 psig on SSE Pressure indication PI-10723.
AND Verifies red and amber lights LIT for HV-10705.
Depress the CLOSE pushbutton for MN STM SJAE IS0 HV-10107.
AND Verifies the amber light LIT and red light NOT LIT.
Depresses the RESET pushbutton for:
0 MN STM LINE DIV 1 IS0 RESET HS-B21-1 S32.
Eva1 Comments STCP-QA-1256 Rev. 2, (9193)
Page 1 of 1 1 1, >.,-. 1,
1
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PERFORMANCE CHECKLIST Appl. To/JPM No.:
S/RO 84.0N.003.101 Page 8 of 12 Student Name:
Step
- I 9
~
~
Action Mn Stm Line Div 2 Is0 Reset HS-B21-1 S33 Reset push button.
NOTE:
If primary containment integrity in jeopardy, it is acceptable to open MSIV's (I9 first) with AP > 200 PSID. This action will not damage MSIV's. If conditions permit, equalizing around MSIV's is preferred.
EVALUATOR CUE:
If asked by the candidate if primary containment is in jeopardy reply, " PRIMARY CONTAINMENT INTEGRITY IS IN JEOPARDY"
- Critical Step
- Critical Sequence Standard Depresses the RESET pushbutton for:
0 MN STM LINE DIV 2 IS0 RESET HS-B21-I S33.
AND Verifies that all 4 white status lights are LIT for the MSlV trip logic.
Candidate asks if Primary Containment is in Jeopardy.
Eva1 Comments
Appl. To/JPM No.:
SIR0 84.0N.003.101 Step
- 20
- 21
- Critical Step
- Critical Seq uence PERFORMANCE CHECKLIST Page 9 of 12 Action To OPEN IB MSIV's PLACE following control switches to AUTO:
Mn Stm Line A IB Is0 HV-141-FO22A.
Mn Stm Line B IB Is0 HV-141-FO22B.
Mn Stm Line C IB Is0 HV-141-FO22C.
Mn Stm Line D IB Is0 HV-141-FO22D.
ALIGN for steam line pressurization as follows:
PLACE AC MOV OL BYPS HS-B21-1 S37A to TEST.
PLACE DC MOV OL BYPS HS-B21-lS37B to TEST.
Student Name:
~~
Standard Places the control switch to AUTO for:
MN STM LINE A IB IS0 HV-141-MN STM LINE B IB IS0 HV-141-MN STM LINE C IB IS0 HV-141-MN STM LINE D IB IS0 HV-141-F022A F022B F022C F022D AND Verifies amber light NOT LIT and red light LIT for each valve.
Inserts key and rotates clockwise to place AC MOV OL BYPS HS-B21-1 S37A to TEST.
AND Verifies annunciator AR-I I I
-H03, AC CONTN IS0 VLVS IN TEST is LIT.
Inserts key and rotates clockwise to place DC MOV OL BYPS HS-B21-1S37B to TEST.
AND Verifies annunciator AR-112-HO3, OUTBOARD ISOLATION VLVS IN TEST is LIT.
Eva1 Comments STCP-QA-1258 Rev 2, (9/93)
Page 1 of 1 3 n n - -. - n r r n
3 I,"...
I J I, C I I " *,...
I
i Appl. To/JPM No.:
S/RO 84.0N.003.101 Step PERFORMANCE CHECKLIST Action OPEN Mn Stm Line IB Drain HV-141-F016.
OPEN Mn Stm Line OB Drain HV-141-F019.
ENSURE Mn Steam Line Warm Up HV-141-F020 OPEN.
After 2 minutes, PLACE AC MOV OL Byps HS-B21-1 S37A to NORM.
"Critical Step
- C ri t ica I Seq uence Page 10 of 12 Student Name:
Standard Place switch to OPEN for MN STM LINE IB DRAIN HV-141-F016.
AND Verifies amber light NOT LIT and red light LIT Place switch to OPEN for MN STM LINE OB DRAIN HV-141-F019.
AND Verifies amber light NOT LIT and red light LIT Verifies red light LIT and amber light NOT LIT.
After 2 minutes, place the AC MOV OL BYPS HS-B21-1 S37A to NORM.
AND Verifies annunciator AR-I I 1 -H03, AC CONTN IS0 VLVS IN TEST is NOT LIT Eva1 Comments
('
PERFORMANCE CHECKLIST Appl. To/JPM No.:
S/RO 84.0N.003.101 Step
OBSERVE main steam line pressure INCREASING on Main Stm Press PR-10101C.
CAUTION OPENING MSIV'S WITH LARGE DIFFERENTIAL PRESSURE WILL CAUSE RPV PRESSURE TO DROP RAPIDLY AND RPV LEVEL TO SWELL.
- Critical Step STCPQA-1256 Rev. 2, (9/93)
Page 1 of 1 I n n ? -.-nr-r...._.
n... -
..... I>'.uI..
.. " 1. -
- Critical Sequence Page 11 'ot 12 Student Name:
Standard After 2 minutes, place the DC MOV OL BYPS HS-B21-1 S37B to NORM.
AND Verifies annunciator AR-I 12-H03, OUTBOARD ISOLATION VLVS IN TEST is NOT LIT Verifies main steam line pressure INCREASING on Main Stm Press PR-I0101 C.
Eva1 Comments
Appl. To/JPM No.:
SIR0 84.0N.003.101 Step
- 23 PERFORMANCE CHECKLIST Page 12 of 12 Action When differential pressure across MSlVs is between 50 psid and 200 psid, OPEN OB MSIV's by PLACING following control switches to AUTO:
Mn Stm Line A OB Is0 HV-141-FO28A Mn Stm Line B OB Is0 HV-141-FO28B Mn Stm Line C OB Is0 HV-141-FO28C Mn Stm Line D OB Is0 HV-141-FO28D EVALUATOR CUE:
Inform the student the JPM is complete.
- Critical Step
- Critical Sequence Student Name:
~
~
Standard Compares RPV pressure with steam line pressure on PR-I 01 01 C until the d/p is between 50 and 200 psid AND When outboard MSlV d/p is between 50 and 200 psid, OPENS the outboard MSlVs by placing the control switch to AUTO for:
F028A F028B F028C F028D MN STM LINE A OB IS0 HV-141-MN STM LINE B OB IS0 HV-141-MN STM LINE C OB IS0 HV-141-MN STM LINE D OB IS0 HV-141-AND Verifies amber light NOT LIT and red light LIT for each valve.
Eva1 Comments
TASK CONDITIONS A.
An MSlV isolation and reactor scram occurred from 100% reactor power.
B.
The cause of the MSlV isolation was a faulty isolation logic surveillance test procedure.
C.
HPCl and/or RCIC injection is controlling reactor water level.
D.
Reactor pressure is controlled by manual SRV actuation.
E.
Restoration of normal steam loads and turbine bypass system is required for a reactor cooldown.
INITIATING CUE Perform a quick recovery from a Main Steam Line Isolation and reopen the MSIVs.
2003 NRC Exam Rev. 2 Page 1 of 2
L-TASK CONDITIONS A.
An MSlV isolation and reactor scram occurred from 100% reactor power.
B.
The cause of the MSlV isolation was a faulty isolation logic surveillance test procedure.
C.
HPCl and/or RClC injection is controlling reactor water level.
D.
Reactor pressure is controlled by manual SRV actuation.
E.
Restoration of normal steam loads and turbine bypass system is required for a reactor cooldown.
INITIATING CUE Perform a quick recovery from a Main Steam Line Isolation and reopen the MSIVs.
2003 NRC Exam Rev. 2 Page 2 of 2
PENNSYLVANIA POWER & LIGHT COMPANY JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET S/RO 04.S0.002.251 0
06/15/03 262001 K4.04 2.8/3.1 Appl. To JPM Number Rev. No.
Date NUREG 1123 Sys. No.
WA Task
Title:
MONTHLY 4KV BUS DEGRADED VOLTAGE CHANNEL FUNCTIONAL TEST Completed By:
Reviews:
Russ Halm 06/15/03 Writer Date InstructorNVriter Date Approval:
Requesting Supv./C.A.
Date Nuclear Trng. Supv.
Date Head 30
\\--
Date of Performance:
Allowed Time (Min.)
Time Taken (Min.)
JPM Performed By:
Student Name:
Last First M.I.
Employee #/S.S. #
Performance
(
)
Satisfactory
(
)
Unsatisfactory Eva1 uat ion :
Evaluator Name:
Signature Typed or Printed Comments:
F o
~
STCP-QA-125A Rev. 4, (05100)
Page 1 of 1 2003 NRC Exam Rev. 2 File No. A14-55
REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE SlRO 04.S0.002.251 I. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.
B. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example:
- 1. Whenever any electrical panel is opened for inspection during JPM performance.
- 2. Whenever entering any plant area where specific safety equipment; such as hearing or eye protection, safety shoes, hardhats, etc; is required and/or posted as being necessary.
C. If in the judgement of the evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.
II. REFERENCES A. SO-204-001 MONTHLY 4KV BUS 2A20II2A202, 2A203, AND 2A204 DEGRADED VOLTAGE CHANNEL FUNCTIONAL TEST, REV. 8 111. REACTIVITY MAN I P U LATIONS This JPM satisfies the requirements of Operational Activity(s):
--/
None IV. TASK CONDITIONS A. Unit 2 is in MODE 1.
B. No other testing is being performed on Unit 2.
V. INITIATING CUE Perform SO-204-001, MONTHLY 4KV BUS 2A20I12A202, 2A203, AND 2A204 DEGRADED VOLTAGE CHANNEL FUNCTIONAL TEST.
VI. TASK STANDARD Blocks trip circuit prior to testing and enables trip circuit when testing is complete. Determines acceptance criteria are met for bus 2A201 and acceptance criteria are not met for function 2 on bus 2A202.
VII.TASK SAFETY SIGNIFICANCE Determine operability of 4KV busses.
Failure to perform correctly could result in inoperable 4KV busses.
2003 NRC Exam Rev. 2
Appl. To/JPM No.: S/RO 04.S0.002.251 Step I
2 3
PERFORMANCE CHECKLIST Page 3 of 13 Action EVALUATOR NOTE:
This JPM must be performed in plant.
Ensure the following material is available to support performance of this JPM:
Stopwatch for each evaluator.
The FAULTED step in this JPM is preceded by a fault statement in BOLD TYPE WITH ALL CAPITAL LElTERS.
A COPY Of SO-204-001.
Attach a surveillance authorization coversheet with the appropriate data completed.
EVALUATOR NOTE:
To begin this JPM, provide the candidate with the Task Conditions and Initiating Cue Sheet.
EVALUATOR CUE Give the candidate a copy of the surveillance to be performed.
Reviews the coversheet.
EVALUATOR NOTE:
Provide the candidate time to review the test procedure.
Obtains stopwatch.
Review precautions.
- Critical Step
- Critical Sequence Student Name:
Stand a rd Verif! authorization to commence by SI R Supervision signature with date a time completed.
Stopwatch obtained.
Precautions reviewed.
Eva1 Comments
(
PERFORMANCE CHECKLIST Page 4 of 13 Appl. To/JPM No.: S/RO 04.S0.002.251 Student Name:
Step 4
5 6
7 8
Action Record plant MODE.
EVALUATOR NOTE Candidate may elect to confirm buses are de-energized by contacting the control room.
Verify Unit 2 ESS buses energized.
Document step completion.
identify testing restrictions.
Document step completion.
EVALUATOR NOTE:
Candidate will proceed to Unit 2 Reactor Building inside the RCA to continue.
NOTE I Panel OC653 alarm, 4KV BUS LO VOLTlPROT CKT TROUBLE for affected bus will annunciate and clear periodically during test
- Critical Step
- Critical Sequence Standard Enters 1 for MODE and initials the confirm line.
Observes white light LIT on OC653 for buses:
2A201 2A203 2A202 2A204 Initials confirm space for each bus.
Determines no other testing is permitted on the bus being tested by this surveillance.
initials confirm space.
Eva1 Comments STCP-CIA-1256 Rev. 2. (9193)
Paae 1 of 1
/ l l l l $ IUIi'l, t X;it?l ticv /
i' PERFORMANCE CHECKLIST
{'
Page 5 of 13 Appl. To/JPM No.: S/RO 04.S0.002.251 Student Name:
Step 9
10
- I I
12 Action NOTE 2 Those steps of procedure designated by an asterisk (*)
immediately to left of step number require entry(ies) to be recorded on Data Form.
CAUTION BUS REMAINS ENERGIZED. EXERCISE CAUTION WORKING AROUND ENERGIZED BUSES. CARE MUST BE TAKEN NOT TO PUSH, PULL OR DROP ANY OBJECTS NEAR ENERGIZED EQUIPMENT.
Inform Shift Supervision to enter TS 3.3.8.1.
Document step completion.
CAUTION DEGRADED GRID PROTECTION FOR ESS BUS 2A201 DISABLED DURING PERFORMANCE OF THIS SECT ION.
Block protection circuit.
Document step completion.
- Critical Step Standard Using plant pagehadio contacts control room/Unit Supervisor to enter TS 3.3.8.1 for bus 2A201.
Initials confirm space.
Place Degraded Voltage Trip Enable Test Switch HSE-2A20102B to TRIP BLOCKED position.
Initials confirm space.
- Critical Sequence Eva1 Comments
(
(
PERFORMANCE CHECKLIST Page 6 of 13 Appl. To/JPM No.: S/RO 04.S0.002.251 Student Name:
Step 13 14 15 16 17 18 Action Confirm 4KV BUS ZA(2A201) LO VOLTlPROT CKT TROUBLE ALARM received at panel OC653.
EVALUATOR CUE Inform candidate the alarm was received.
Document step completion.
Perform light test.
EVALUATOR CUE Inform candidate the white lights are LIT.
Document step completion.
Return test switch to normal.
EVALUATOR CUE Inform candidate the white lights are NOT LIT.
Document step completion.
Standard Using plant pagelradio contacts Unit 2 control room to confirm the alarm was received.
Initials confirm space.
Place Degraded Voltage Ckt Test Switch HSE-2A20102A to LIGHT TEST and CONFIRM following Degraded Voltage Ckt Test Light ILLUMINATE:
0 Relay Ckt 27B1/27B2 0
Relay Ckt 27B3/27B4 Verify white lights LIT.
Initials confirm spaces.
Place Test Switch HSE-2A20102A to Normal and CONFIRM following Test lights EXTINGUISH:
0 Relay Ckt 27B1/27B2 0
Relay Ckt 27B3/27B4 Verify white lights are NOT LIT.
Initials confirm spaces.
Eva1
=
Comments
- Critical Step
- Critical Sequence STCP-QA-125B Rev. 2. (9193)
Page 1 of 1
^ ^ ^ ^..-,.
.,\\.It.,<,
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L
PERFORMANCE CHECKLIST
(:
Page 7 of 13 Appl. TolJPM No.: SlRO 04.S0.002.251 Student Name:
Step
- I 9
- 20 21 22 23 Action rest circuit and time relay drop out.
EVALUATOR CUE nform candidate the white lights are LIT with the following
- imes:
D D
Relay Ckt 27B3/27B4 (-3 seconds)
Relay Ckt 27B1/27B2 (-5 minutes)
EVALUATOR NOTE:
Bus 2A201 acceptance criteria for function 2 is 1.a (65%)
and function 3 is 2.a (93%) on data form.
Return test switch to normal.
EVALUATOR CUE Inform candidate the white lights are NOT LIT.
Document step completion.
Reset relay targets 27B1 through 27B4.
Document step completion.
Standard
=lace Test Switch HSE-2A20102A
- o CIRCUIT TEST and simultaneously starts the stop "atch and CONFIRM following rest lights ILLUMINATE:
B Relay Ckt 2783/27B4 (-3 B
Relay Ckt 2781/27B2 (-5 seconds) minutes)
Verify white lights are LIT and note times on stopwatch.
Record acceptance criteria as acceptable on the data form by circling yes and initial the confirm space for function 2 and 3.
Place Test Switch HSE-2A20102A to Normal and CONFIRM following Test lights EXTINGUISH:
Relay Ckt 278112782 Relay Ckt 278312784 Verify white lights are NOT LIT.
Initials confirm space.
Depress the reset button and verify relay target color changes from orange to clear.
Initials confirm space for each relay.
Eva1 Comments
- Critical Step
- Critical Sequence STCP-QA-125B Rev 2, (9/93)
Paae 1 of 1 L I j I j j N W f - I=rini Y P > /
i' Page 8 of 13 PERFORMANCE CHECKLIST Appl. To/JPM No.: S/RO 04.S0.002.251 Student Name:
Step
- 24 25 26 27 28 29 30 31 Action Enable protection circuit.
Document step completion.
Confirm 4KV BUS 2A(2A201) LO VOLTlPROT CKT TROUBLE ALARM cleared at panel 06653.
EVALUATOR CUE inform candidate the alarm was clear Document step completion.
Inform Shift Supervision to clear TS 3.3.8.1.
Document step completion.
EVALUATOR NOTE:
Candidate will proceed to bus 2A202.
Inform Shift Supervision to enter TS 3.3.8.1.
Document step completion.
Standard Place Degraded Voltage Trip Enable Test Switch HSE-2A20102B to TRIP ENABLED position.
Initials confirm space.
Using plant pagehadio contacts control room to confirm the alarm cleared.
Initials confirm space.
Using plant page/radio contacts control room/Unit Supervisor to clear TS 3.3.8.1 for bus 2A201.
Initials confirm space.
Using plant page/radio contacts control room/Unit Supervisor to enter TS 3.3.8.1 for bus 2A202.
Initials confirm space.
Eva1 Comments
- Critical Step
- Critical Sequence STCP-QA-125B Rev. 2, (9/93)
Page 1 of 1 LlilJ.5 I V t i l, ?X,.+ITI Kf?V./
PERFORMANCE CHECKLIST Page 9 of 13 Appl. TolJPM No.: S/RO 04.S0.002.251 Student Name:
Step
- 32 33 34 35 36 37 Action CAUTION DEGRADED GRID PROTECTION FOR ESS BUS 2A202 DISABLED DURING PERFORMANCE OF THIS S ECTlO N.
Block protection circuit.
Document step completion.
Confirm 4KV BUS 2B(2A202) LO VOLT/PROT CKT TROUBLE ALARM received at panel OC653.
EVALUATOR CUE inform candidate the alarm was received.
Document step completion.
Perform light test.
EVALUATOR CUE Inform candidate the white lights are LIT.
Document step completion.
- Critical Step
- Critical Sequence Standard Place Degraded Voltage Trip Enable Test Switch HSE-2A20202B to TRIP BLOCKED position.
Initials confirm space.
Using plant pagelradio contacts control room to confirm the alarm was received.
Initials confirm space.
Place Degraded Voltage Ckt Test Switch HSE-2A20202A to LIGHT TEST and CONFIRM following Degraded Voltage Ckt Test Light ILLUMINATE:
0 Relay Ckt 27B1/27B2 0
Relay Ckt 27B3/27B4 Verify white lights LIT.
Initials confirm spaces.
Eva1 Comments
PERFORMANCE CHECKLIST Page 10 of 13 Appl. To/JPM No.: S/RO 04.S0.002.251 Student Name:
Step 38 39
- Critical Step Action Return test switch to normal.
EVALUATOR CUE Inform candidate the white lights are NOT LIT Document step completion.
FAULT STATEMENT: RELAY CKT 27B3127B4 WILL EXCEED THE TECH SPEC ALLOWABLE VALUE.
- Critical Sequence Standard Place Test Switch HSE-2A20202A to Normal and CONFIRM fallowing Test lights EXTINGUISH:
Relay Ckt 27B1/27B2 0
Relay Ckt 27B3127B4 Verify white lights are NOT LIT.
Initials confirm spaces.
Eva1 Comments
Appl. To/JPM No.: S/RO 04.S0.002.251 Step
- 40 PERFORMANCE CHECKLIST Page 11 of 13 Student Name:
Action Test circuit and time relay drop out.
EVALUATOR CUE Inform candidate the white lights are LIT with the following times:
0 Relay Ckt 2783/27B4 (-6 seconds)
Relay Ckt 2781/27B2 (-5 minutes)
EVALUATOR NOTE:
EVALUATOR Candidate may inform control room about the acceptance criteria failure.
Bus 2A202 acceptance criteria for function 2 is 1.b (65%)
and function 3 is 2.b (93%) on data form.
EVALUATOR CUE If necessary roleplay shift supervision and direct candidate to proceed with surveillance to restore test circuitry for the 2A202 bus.
Standard Place Test Switch HSE-2A20202A to CIRCUIT TEST and simultaneously starts the stop watch and CONFIRM following Test lights ILLUMINATE:
Relay Ckt 2783/27B4 (-3 0
Relay Ckt 27B1127B2 (-5 seconds) minutes)
Verify white lights are LIT and note times on stopwatch.
Record acceptance criteria is not acceptable on the data form by circling no and initial the confirm space for function 2.
Record acceptance criteria is acceptable on the data form by circling yes and initial the confirm space for function 3.
Eva1 Comments
- Critical Step
- Critical Sequence
PERFORMANCE CHECKLIST Page 12 of 13 Appl. To/JPM No.: S/RO 04.S0.002.251 Student Name:
Step
- 4 1 42 43 44
- 45 46 47 48 Action Return test switch to normal.
EVALUATOR CUE Inform candidate the white lights are NOT LIT.
Document step completion.
Reset relay targets 27B1-2A20202 through 27B4-2A20202.
Document step completion.
Enable protection circuit.
Document step completion.
Confirm 4KV BUS 2B(2A202) LO VOLT/PROT CKT TROUBLE ALARM cleared at panel 06653.
EVALUATOR CUE Inform candidate the alarm was clear.
Document step completion.
- Critical Step
- Critical Sequence Standard Place Test Switch HSE-2A20202A to Normal and CONFIRM following Test lights EXTINGUISH:
0 Relay Ckt 27B1/27B2 Relay Ckt 27B3/27B4 Verify white lights are NOT LIT.
Initials confirm space.
Depress the reset button and verify relay target color changes from orange to clear.
Initials confirm space for each relay.
Place Degraded Voltage Trip Enable Test Switch HSE-2A20202B to TRIP ENABLED position.
Initials confirm space.
Using plant page/radio contacts control room to confirm the alarm cleared.
Initials confirm space.
Eva1 Comments STCP-QA-12%
Rev. 2, (9/93)
Page 1 of 1 L"".,
I",,"
L A Y,,,,\\I_".
i
ii PERFORMANCE CHECKLIST Page 13 of 13 Appl. To/JPM No.: S/RO 04.SL.002.251 Student Name:
Action
~
Inform Shift Supervision Bus 2A202 did not meet acceptance criteria.
EVALUATOR CUE This completes the JPM.
- Critical Step
- Critical Sequence
~
Standard Using plant pagelradio contacts Unit 2 control room/Unit Supervisor and informs them bus 2A202 did not meet acceptance criteria for relays 27B3/27B4.
Eva1 I Comments STCP-QA-125B Rev. 2, (9/93)
Page 1 of 1
- " V U
, 1 1 \\ "
L h Y l l l I \\ V, ". '.
TASK CONDITIONS
-d A. Unit 2 is in MODE 1.
B. No other testing is being performed on Unit 2.
INITIATING CUE Perform SO-204-001, MONTHLY 4KV BUS 2A20I12A202, 2A203, AND 2A204 DEGRADED VOLTAGE CHANNEL FUNCTIONAL TEST.
2003 NRC Exam Rev. 2 Page 1 of 2
TASK CONDITIONS A. Unit 2 is in MODE 1.
B. No other testing is being performed on Unit 2.
.-..--I INITIATING CUE Perform SO-204-001, MONTHLY 4KV BUS 2A20II2A202, 2A203, AND 2A204 DEGRADED VOLTAGE CHANNEL FUNCTIONAL TEST.
Page 2 of 2 2003 NRC Exam Rev. 2
PENNSYLVANIA POWER & LIGHT COMPANY JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET S/RO 00.ON.Ol5.153 1
06/13/03 295016 AA1.08 4.0/4.0 Appl. To JPM Number Rev. No.
Date NUREG 1123 Sys. No.
WA Task
Title:
Perform Manual Operation of the ADS Valves from the Remote Shutdown Panels or Relay Rooms as Required by ON-I 00-009 (Alternate Path)
Completed By:
Reviews:
Russ Halm 06/13/03 Writer Date InstructorNVriter Approval:
Requesting Supv./C.A.
Date Nuclear Trng. Supv.
Head Date Date Date of Performance:
25 Allowed Time (Min.)
Time Taken (Min.)
JPM Performed By:
Student Name:
Last First M.I.
Employee #/S.S. #
Performance
(
)
Satisfactory
(
)
Unsatisfactory Evaluation:
c Evaluator Name:
Signature Typed or Printed Comments:
STCP-QA-125A Rev. 2, (9/93)
Page 1 of 1 2003 NRC Exam Rev. 2 File No. A14-5B
REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE SlRO 00.ON.015.153 L
- 1.
SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.
B. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example:
- 1. Whenever any electrical panel is opened for inspection during JPM performance.
- 2. Whenever entering any plant area where specific safety equipment; such as hearing or eye protection, safety shoes, hardhats, etc; is required and/or posted as being necessary.
C. If in the judgement of the evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.
II. REFERENCES A. ON-100-009 CONTROL ROOM EVACUATION (Rev. 8) 111. REACTIVITY MAN I PU LATIONS None IV. TASK CONDITIONS A. An incident has occurred at Unit 1, which has required the Control Room to be Evacuated.
B. Control has been transferred to the Unit 1 RSDP in accordance with ON-100-009.
C. HPCl is operating.
D. Reactor pressure is 875 psig and stable.
E. MSlVs are closed.
F. The Unit Supervisor has directed that SRVs be used for a plant cooldown.
V. INITIATING CUE Lower RPV pressure, from the Unit 1 RSDP, as necessary to initiate a reactor cooldown NOT to exceed 100°F per hour from the present conditions, in accordance with ON-1 00-009 step 4.6.
VI. TASK STANDARD Reactor C/D lowest pressure calculated 2325 psig and at least 1 SRV opened.
VILTASK SAFETY SIGNIFICANCE Commence a reactor coolant system cooldown.
Failure to perform the task would result in an uncontrolled RCS heatup, and a challenge to the RPV pressure control system to function.
2003 NRC Exam Rev. 2
Appl. To/JPM No.: S/RO 00.ON.015.153 Step PERFORMANCE CHECKLIST Action EVALUATOR NOTE:
The FAULTED step in this JPM is preceded by a fault statement in BOLD TYPE WITH ALL CAPITAL LETTERS.
Obtains a controlled copy of ON-I 00-009, including Attachments A and B.
NOTE:
Relief mode of SRV's A, B, and C will not auto initiate when applicable Control Transfer Switches are in EMERG position, however, safety function is always operable. Also when SRV Transfer Switches are in EMERG spurious auto actuation is prevented due to a Control Room fire.
Ensure following valves OPEN:
SV-12651 INSTR GAS TO CONTN ISO.
SV-12605 INSTR GAS CMP OB SUCT ISO.
EVALUATOR CUE:
Inform candidate, Red OPEN lights LIT and amber CLOSED lights NOT LIT for SV-12651 and SV-12605 indication.
- Critical Step STCP-QA-1256 Rev. 2. (9193) As Given Page 1 of 1 2003 NRC Exam Rev. 2
- Critical Sequence Student Name:
i' Page 3 of 8 Standard Obtains a controlled copy ON-I 00-009, including Attachments A and B.
Checks:
SV-12651 indicating lights Red light LIT.
Amber light NOT LIT.
AND SV-I2605 indicating lights Red light LIT.
Amber light NOT LIT.
Eva1 Comments
i PERFORMANCE CHECKLIST r:
Page 4 of 8 Appl. To/JPM No.: S/RO 00.ON.015.153 Step 3
Action CAUTION Level 1 (-129") or high drywell pressure (1.72 psig)
LOCA Isolation Signal is defeated for CIG valves when controlled from the remote shutdown panel.
NOTE:
Placing HSS-15114B Transfer Switch U in EMERG causes lnstr Gas CMP OB suction to cycle possibly tripping CIG compressors on low suction pressure.
IF CIG Compressors tripped, Reset as follows at 1 C239 (25-71 9'):
Depress Logic Reset push button.
Ensure CIG Compressor STARTS.
EVALUATOR CUE:
Role Play as Reactor Building NPO and Inform candidate that the CIG Compressors are running.
CAUTION (1)
If RPV pressure drops below 650 psig, condensate pumps will inject when RPV level <+35 inches.
CAUTION (2)
Wide range level indication becomes less accurate as RPV pressure decreases.
- Critical Step
- Critical Sequence STCPQA-125B Rev. 2. (9193) As Given Page 1 of 1 7003 NRC Exam Rev 2 Student Name:
Standard Simulates contacting Reactor building NPO to determine the status of the CIG compressors.
Eva1 Comments
('
Appl. To/JPM No.: S/RO 00.ON.015.153 Step
- 4 5
PERFORMANCE CHECKLIST Action EVALUATOR NOTE:
Since the SRVs will not open until the candidate is at the relay room, Calculation of allowable cooldown value may be done anytime during the remainder of the JPM.
This is acceptable.
Operate SRV's as follows:
Calculates allowable cooldown value for reactor pressure.
FAULT STATEMENT:
SRV'S A, B, & C WILL NOT OPEN FROM THE RSDP.
Open SRV's A, B, and C as needed.
EVALUATOR CUE:
If asked, indicate RPV pressure is still stable at 875 psig.
- Critical Step
- Critical Sequence Student Name:
Standard Refers to ON-100-009, Attachment A to determine current reactor temperature and desired reactor pressure and temperature to achieve a 100°F/hr cooldown AND Determines RPV pressure at 875 psig, reactor temperature is -530°F. Cooldown rate of 1 OO"F/hr lowers RPV pressure -325 psig.
Should be over 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, so a target pressure 2325 psig is selected.
Places switches for SRVs A, 9, or C to OPEN.
AND Checks for change in RPV pressure Page 5 of 8 Eva1 Comments STCP-QA-125B Rev. 2, (9193) As Given Page I of 1 2003 NRC Exam Rev. 2
Appl. To/JPM No.: S/RO 00.ON.015.153 Step 6
PERFORMANCE CHECKLIST Page 6 of 8 Action EVALUATOR CUE:
Acknowledge as SRO and inform the candidate to perform the necessary procedural actions to complete the task. Inform the operator that permission is granted to leave the RSDP - another operator will assume the RSDP station.
Chooses alternate method of SRV operation.
EVALUATOR CUE:
Roleplay SRO as necessary to provide instructions on which SRV is to be opened.
EVALUATOR NOTE:
Operation of the ADS valves from the Relay Room consists of switch manipulation and monitoring cooldown rate while maintaining communication with the RSDP Room. There are six keylock switches in each Relay Room; the operator may select either the Upper or the Lower Relay Room to perform this JPM.
- Critical Step STCP-QA-125B Rev. 2. (9~33)
As Given Page 1 of 1
?nn7 K V C P ru.r.n c,,..
- Critical Sequence Student Name:
Stand a rd Candidate determines that the valves have not opened and reports this to the SRO.
IF pneumatic supply to SRV's A, B, and C not available, Operate SRV's G, J, K, L, M, or N (ADS valves) individually from upper (lower) relay room Panel 1 C628 (1 C631) using keylock switches.
Eva1 Comments
Appl. To/JPM No.: S/RO 00.ON.015.153 Step
- 6 7
8
- 9 PERFORMANCE CHECKLIST Action EVALUATOR NOTE:
Keys to operate SRVs are located in sealed Pink sound powered phone storage box, labeled JP1207, JP1402, JP2201, inside the Remote Shutdown Panel Room.
Use of these keys and the key to the sforage box will be SIMULATED Simulate obtaining keys for SRVs from Pink sound powered phone box, labeled JP1207, JP1402, J P220 1 I.
Go to the selected Relay Room, locates Panel IC631 or Panel 1C628.
Simulates establishing communication with the RSDP Room.
Simulates inserting key and rotating switch to the OPEN position.
EVALUATOR CUE:
inform candidate red light LIT and amber light NOT LIT for each valve place to open.
- Critical Step
- Critical Sequence Student Name:
Standard Demonstrates the ability to find keys in the pink box labeled JPl207 or JP1402.
Proceeds to the selected Relay Room, locates Panel I C631 or Panel I C628.
Establishes communication with the RSDP Room (simulate) using sound-powered phone or page.
Simulates placing any ADS keylock switch in the OPEN position.
AND Verifies Red light LIT and amber light NOT LIT.
Page 7 of 8 Eva1
=
Comments STCP-QA-125B Page 1 of 1 Rev. 2, (9~3)
As Given 2003 NRC Exam Rev. 2
PERFORMANCE CHECKLIST Page 8 of 8 Step Appl. To/JPM No.: S/RO 00.ON.015.153 Student Name:
Standard Eva1 Comments Action EVALUATOR CUE:
Simulates using sound-powered phone page.
To inform SRO at the RSDP the valve indicates 1:'
Acknowledge SRV is OPEN.
This completes the JPM.
I OPEN I
I I
I
- Critical Step
- Critical Sequence STCP-QA-125B Rev. 2. (9193) As Given Page 1 of 1 2007 NRC: Fvnm Rev 3
TASK CONDITIONS A. An incident has occurred at Unit I, which has required the Control Room to be Evacuated.
- 6. Control has been transferred to the Unit 1 RSDP in accordance with ON-100-009.
C. HPCl is operating.
D. Reactor pressure is 875 psig and stable.
E. MSlVs are closed.
F. The Unit Supervisor has directed that SRVs be used for a plant cooldown.
INITIATING CUE Lower RPV pressure, from the Unit 1 RSDP, as necessary to initiate a reactor cooldown NOT to exceed 100°F per hour from the present conditions, in accordance with ON-100-009 step 4.6.
2003 NRC Exam Rev. 2 Page 1 of 2
TASK CONDITIONS A. An incident has occurred at Unit 1, which has required the Control Room to be Evacuated.
B. Control has been transferred to the Unit 1 RSDP in accordance with ON-100-009.
C. HPCl is operating.
D. Reactor pressure is 875 psig and stable.
E. MSlVs are closed.
F. The Unit Supervisor has directed that SRVs be used for a plant cooldown.
INITIATING CUE Lower RPV pressure, from the Unit 1 RSDP, as necessary to initiate a reactor cooldown NOT to exceed 100°F per hour from the present conditions, in accordance with ON-100-009 step 4.6.
2003 NRC Exam Rev. 2 Page 2 of 2
SiRO Appl. To Task
Title:
PENNSYLVANIA POWER & LIGHT COMPANY JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET
- 50.
0.008.101 I
0611 5/03 217000 A2.01 3.8i3.7 JPM Number Rev. No.
Date NUREG 1123 Sys. No.
KIA Bypass of All RClC Isolation Signals in Accordance With ES-150-001 Completed By:
Reviews:
Russ Halm 0611 5/03 Writer Date InstructoriWriter Date Ap prova I:
Requesting Supv./C.A.
Date Nuclear Trng. Supv.
Date Head 40
'ir-Date of Performance:
Allowed Time (Min.)
Time Taken (Min.)
JPM Performed By:
Student Name:
Last First M.I.
Employee #/S.S. #
Performance Evaluation:
(
)
Satisfactory
(
)
Unsatisfactory Evaluator Name:
Signature Typed or Printed Comments:
Form STCP-QA-125A Rev. 4. (05/00)
Page 1 of 1 2003 NRC Exam Rev. 2 File No. A14-58
REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE S/RO 50.E0.008.101
- 1.
SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.
B. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example:
- 1. Whenever any electrical panel is opened for inspection during JPM performance.
- 2. Whenever entering any plant area where specific safety equipment; such as hearing or eye protection, safety shoes, hardhats, etc; is required and/or posted as being necessary.
C. If in the judgement of the evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.
II. REFERENCES A. ES-150-001 RCIC Turbine Isolation and Trip Bypass, Rev. 14 I II. REACTIVITY MAN I P U LATIONS This JPM satisfies the requirements of Operational Activity(s):
None IV. TASK CONDITIONS A. An accident condition exists and Shift Supervision has determined that it is necessary to rapidly depressurize the RPV as required by EO-I 00-1 03, Primary Containment Control.
B. EO-100-1 12, Rapid Depressurization is being executed, and only two SRVs can be opened.
C. A RClC initiation signal is sealed in and RClC started, but tripped and isolated, due to a loss of RB HVAC with a subsequent pipe routing area high temperature.
D. A steam leak does _not exist.
E. RClC is needed for support of reactor depressurization.
F. ES-150-001 Section 4.6 is complete, bypassing and resetting the RClC initiation signal.
V. INITIATING CUE Bypass all of the RClC isolation signals in accordance with ES-150-001, Section 4.2.
VI. TASK STANDARD All RClC isolations signals bypassed.
VII. TASK SAFETY SIGNIFICANCE Provide inventory makeup supply for reactor heat removal.
Failure to complete the task could result in loss of heat removal capability.
2003 NRC Exam Rev. 2
Appl. TolJPM No.: S/RO 50.E0.008.101 Step PERFORMANCE CHECKLIST Page 3 of 9 Action EVALUATOR NOTE:
0 0
This JPid must be performed in the plant.
Obtain permission from Shift Manager to perform this JPM and get access to ES tool box.
Ensure the following material is available to support performance of this JPM:
A copy of the latest revision of ES-150-001.
In section 4.0, initial 4.6 and 4.2 under EO-I 12.
0 Enter NA for all other initial blocks in section 4.0.
0 Authorize the ES by signoff as Shift Manager with date and time.
Signoff confirmed and date for steps 4.6.1.a and 4.6.1.b.
0 Insert NA for steps 4.6.2.a and 4.6.2.b.
Place checkmark at the end of steps 4.6.3 through 4.6.7 indicating their completion.
EVALUATOR NOTE:
To begin this JPM, provide the candidate with the Task Conditions and Initiating Cue Sheet.
Review Sections 1.O through 3.0.
Ensure that Shift Supervision has approved performance of Sections 4.6 and 4.2.
- Critical Step
- Critical Sequence Student Name:
Standard Reviews all sections.
Notes that the approval step for 4.6 and 4.2, under Rapid Depressurization in section 4.0 has been initialed.
Notes that Shift Supervision has signed and dated the appropriate signature line.
Eva1 Comments STCP-QA-1258 Rev. 2, (9/93) 0.,,.,,.,, 1.
..,,,.......,-. I-
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,,.I I
.\\,<.
A,..,,
Appl. To/JPM No.: S/RO 50.E0.008.101 Step i
PERFORMANCE CHECKLIST Action Obtain required support materials.
EVALUATOR NOTE:
Have the candidate show you the support materials, but do not remove them from the Shift Managers office.
Selects correct section.
Place following valve control switches to CLOSE:
STM SUPPLY IB IS0 HV-149-F007 STM SUPPLY OB IS0 HV-149-F008 WARM UP LINE IS0 HV-149-FO88 EVALUATOR CUE After each switch is placed to CLOSE inform the candidate the amber light is LIT and the red light is NOT LIT.
The following steps bypass all isolation signals includinq manual isolation, however, HV-15012 and HV-149-F008 can still be closed manually using the handswitches.
CAUTIO N NOTE: Booting of RClC E51-KI5 and K33 contacts below will allow bypass of all isolations but will not inhibit other functions (Le., Alarm and BIS lights).
However, these may be affected momentarily when the relay fingers are spread to install the boots.
Student Name:
Standard Obtains required support materials from the ES box in the Shift Managers off ice.
Selects section 4.2.
Insert key and rotate counter clockwise to CLOSE for HV-149-007 and F008.
Place control switch to CLOSE for HV-149-F088.
Verify amber light LIT and red light NOT LIT.
Eva1 Page 4 of 9 Comments
- Critical Step
- Critical Sequence STCP-QA-1258 Rev 2, (9/93)
LLLL ;.,A#
Ln;,;,
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~
I
i'
{
1; PERFORMANCE CHECKLIST Page 5 of 9 Appl. To/JPM No.: S/RO 50.E0.008.101 Student Name:
Step 6
7
- 8 9
- I O 11 12 Action Bypass all RClC Div 1 isolations.
EVALUATOR NOTE:
I C621 located Upper Relay Room.
Banana Jacks in this JPM have a GREEN stripe.
Locate relay, loosen relay cover screws, and remove cover.
Boot contacts 314.
Document step completion.
Boot contacts 9/10.
Document step completion.
Locate Terminal Strips - AAA7 and BBBS.
NOTE: Terminal Strip AAA7 is located left side, back row 4 feet high, and terminal strip BBBS is located right side, front row, 3 feet high in rear of panel.
~
Standard Locate 1 C621, RClC RELAY PANEL DIVISION 1.
REMOVE front cover from Relay ISOLATION SIGNAL F008 CONTROL LOGIC.
E51A-Kl5, RClC AUTO/MAN Referring to ATT A, INSTALL boot over 314 contact finger of Relay E51 A-K15.
Signs/initials confirmed space and enters date.
Referring to ATT A, INSTALL boot over 911 0 contact finger of Relay E51A-Kl5.
Signshnitials confirmed space and enters date.
Locate Terminal Strips - AAA7 and BBB9.
Eva1 Comments
- Critical Step
- Critical Sequence STCP-CLA-IZBB RPV 7 (9/93)
Y i (, i j i 1 2003 NKL tXam KeV. L
PERFORMANCE CHECKLIST 1,
Page 6 of 9 Appl. To/JPM No.: S/RO 50.E0.008.101 Student Name:
Step
- I 3 14 15 16
- I 7 18
- I 9
20 21 Action Install jumper.
Document step completion.
Bypass all RCIC Div 2 isolations.
EVALUATOR NOTE:
1 C618 is located in the Lower Relay Room.
Locate relay, loosen relay cover screws, and remove cover.
Boot contacts 314.
Document step completion.
Boot contacts 7/8.
Document step completion.
Locate Terminal Strip - EEE8.
- Critical Step
- Critical Sequence Standard INSTALL a jumper between terminal points AAA7-4 and BBB9-7.
Signs1initial.s confirmed space and enters date.
Locate 1 C618, RHWRCIC RELAY PANEL DIV 2.
REMOVE front cover of Relay TURB EXH DIAPHRAGM HIGH PRESSURE.
E5lA-K33, RCIC IS0 SIGNAL Referring to ATT B, INSTALL boot over 314 contact finger of Relay E51A-K33.
Signshnitials confirmed space and enters date.
Referring to ATT B, INSTALL boot over 7/8 contact finger of Relay E51A-K33.
Signs/initials confirmed space and enters date.
Locate Terminal Strip - EEE8.
Eva1 Comments STCP-QA-1258 Rev 2, (9/93) iSS5 i v n u Lnaiir IIGV.
2
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PERFORMANCE CHECKLIST Page 7 of 9 Appl. To/JPM No.: S/RO 50.E0.008.101 Student Name:
Step
- 22 23 24
- 25 26
- 27 Action NOTE: Terminal Strip EEE8 is located right side, 2 feet high in rear of Panel 1C618, third door from right end of panel.
Install jumper.
Document step completion.
Locate Terminal Strips BBBG and EEE7.
NOTE: Terminal Strip BBBG is located right side, 6 feet high. Terminal Strip EEE7 is located 3 feet high in rear of Panel 1C618, third door from right end of panel.
Install jumper.
Document step completion.
Pressurize RClC steam line.
OPEN STM SUPPLY IB IS0 HV-149-F007.
EVALUATOR CUE Inform the candidate the red light is LIT and the amber light is NOT LIT.
- Critical Step
- Critical Sequence Standard INSTALL jumper between Terminal Points EEE8-14 and EEE8-20.
Signdinitials confirmed space and enters date.
Locate Terminal Strip -BBB6 and Terminal Strip - EEE7.
INSTALL jumper between Terminal Points BBB6-6 and EEE7-14.
Signshnitials confirmed space and enters date.
PLACE STM SUPPLY IB IS0 HV-149-FO07 keyswitch to OPEN.
Verify red light LIT and amber light NOT LIT.
Eva1 Comments STCP-QA-1256 Rev. 2. (9/93)
Page 1 of 1
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i' PERFORMANCE CHECKLIST Page 8 of 9 Appl. To/JPM No.: SlRO 50.E0.008.101 Step
- 28 29 30 Action THROTTLE OPEN STM SUPPLY OB IS0 HV-149-F008.
EVALUATOR CUE Inform the candidate the red light and the amber light are LIT.
OBSERVE steam line pressure increasing.
EVALUATOR CUE Inform the candidate that RCIC Steam Line pressure is rising.
THROTTLE OPEN RClC STM SUPPLY OB IS0 HV-149-F008 to pressurize RClC steam line -1 00 psi/min.
EVALUATOR CUE Inform the candidate that RClC Steam Line is pressurizing at a rate of -80 psi/min.
Student Name:
- Critical Step
- Critical Sequence Standard PLACE STM SUPPLY OB IS0 HV-149-FO08 keyswitch to OPEN for four seconds.
RETURN STM SUPPLY OB IS0 HV-149-F008 keyswitch to STOP position.
Verify red light and amber light LIT.
Observe STM SUP PRESS TO RCIC TURBINE PI-E51-1 R602.
PLACE STM SUPPLY OB IS0 HV-149-FO08 keyswitch to OPEN.
RETURN STM SUPPLY OB IS0 HV-149-FO08 keyswitch to STOP position while monitoring PI-E51-1 R602 Comments STCP-QA-125B Rev. 2. (9193)
Page 1 of 1
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PERFORMANCE CHECKLIST Page 9 of 9 Appl. To/JPM No.: S/RO 50.E0.008.101 Student Name:
Step 31 32 Action When RClC steam line pressure within 50 psig reactor pressure as indicated on STM SUP PRESS TO RClC TURBINE PI-E51-1 R602, FULLY OPEN STM SUPPLY OB IS0 HV-149-F008.
EVALUATOR CUE Inform candidate that pressures are within 50 psig of each other.
Inform the candidate the red light is LIT and the amber light is NOT LIT.
Confirms RClC Steam Lines are drained.
EVALUATOR CUE Inform the candidate the amber light is LIT an(
light is NOT LIT.
EVALUATOR CUE:
This completes the JPM.
the re(
"Critical Step STCP-QA-1250 Rev. 2, (9/93)
Page 1 of 1
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- Critical Sequence Standard Compares any reactor pressure indication to PI-E51-1 R602.
PLACE STM SUPPLY OB IS0 HV-149-FO08 keyswitch to OPEN.
Verify red light LIT and amber light is NOT LIT.
Observes Annunciator AR-108-BO4 is CLEAR.
Check STEAM LINE DRN POT BYPS LV-149-FO54 is CLOSED.
Verify amber light LIT and red light NOT LIT.
Eva1 Comments
TASK CONDITIONS A. An accident condition exists and Shift Supervision has dgtkrmined that it is necessary to rapidly depressurize the RPV as required by EO-100-1 03, Primary Containment Control.
B. EO-I 00-1 12, Rapid Depressurization, is being executed, and only two SRVs can be opened.
C. A RClC initiation signal is sealed in and RClC started, but tripped and isolated, due to a loss of RB HVAC with a subsequent pipe routing area high temperature.
D. A steam leak does not exist.
E. RClC is needed for support of reactor depressurization.
F. ES-150-001 Section 4.6 is complete, bypassing and resetting the RClC initiation signal.
INITIATING CUE Bypass all of the RClC isolation signals in accordance with ES-150-001, Section 4.2.
2003 NRC Exam Rev. 2 Page 1 of 2
TASK CONDITIONS A. An accident condition exists and Shift Supervision has determined that it is necessary to rapidly depressurize the RPV as required by EO-I 00-1 03, Primary Containment Control.
B. EO-I 00-1 12, Rapid Depressurization, is being executed, and only two SRVs can be opened.
C. A RClC initiation signal is sealed in and RClC started, but tripped and isolated, due to a loss of RB HVAC with a subsequent pipe routing area high temperature.
D. A steam leak does not exist.
E. RClC is needed for support of reactor depressurization.
F. ES-150-001 Section 4.6 is complete, bypassing and resetting the RClC initiation signal.
INITIATING CUE Bypass all of the RClC isolation signals in accordance with ES-150-001, Section 4.2.
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Page 2 of 2 2003 NRC Exam Rev. 2