ML091490496
| ML091490496 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 03/27/2009 |
| From: | Brian Larson Operations Branch IV |
| To: | Omaha Public Power District |
| References | |
| 50-285/09-301 50-285/09-301 | |
| Download: ML091490496 (158) | |
Text
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No:A-1 Rev 0 JPM
Title:
Shutdown margin with inoperable CEA Approximate Time: 20 minutes Actual Time: _________________
Reference(s): K/A 2.1.37 RO Importance 4.3 TDB-V.9, "SHUTDOWN MARGIN WORKSHEET" TDB-II, "REACTIVITY CURVES" JPM Prepared by: Jerry Koske Date: 01/31/09 Page 1 of 5
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No:A-1 Rev 0 JPM
Title:
Shutdown margin with inoperable CEA Operators Name: _____________________ Employee # ______________
All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):
SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________
Reason, if unsatisfactory:
Tools & Equipment: TDB, ruler. calculator Safety Considerations: None Comments:
Page 2 of 5
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No:A-1 Rev 0 JPM
Title:
Shutdown margin with inoperable CEA INITIATING CUE: The plant is operating at 60% power with group 4 CEAs at 110 inches withdrawn. Group A CEA #36 and Group 2 CEA #24 have been declared inoperable (untrippable).
You have been requested to perform an instantaneous shutdown margin calculation to determine if technical specification requirements for shutdown margin are being met.
The RCS boron concentration is 400 ppm. The burnup is 12000 MWD/MTU Critical Steps shown in gray STEP ELEMENT STANDARD 1 Obtain a copy of TDB-V.9. After candidate locates TDB-V.9 in the Technical Data Book, provide a copy of TDB-V.9 Part I.
[ SAT ] [ UNSAT ]
2 Obtain a copy of TDB section Obtains copy of TDB-II.
II, Reactivity Curves.
[ SAT ] [ UNSAT ]
3 Determines part I of TDB Performs calculation using part procedure should be used. 1.
[ SAT ] [ UNSAT ]
4 Performs calculation of the Difference calculated on line difference between actual and 11 of TDB-V.9, section 1 is required shutdown margin. +0.7 [between +0.5, +0.9]
[ SAT ] [ UNSAT ]
Page 3 of 5
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No:A-1 Rev 0 JPM
Title:
Shutdown margin with inoperable CEA STEP ELEMENT STANDARD 5 Determines if SDM is Determines Shutdown Margin adequate. is inadequate
[ SAT ] [ UNSAT ]
Termination Criteria: Shutdown Margin determination has been made and TDB V.9, Part One has been filled out.
Page 4 of 5
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-1 Rev 0 INITIATING CUE: The plant is operating at 60% power with group 4 CEAs at 110 inches withdrawn. Group A CEA #36 and Group 2 CEA #24 have been declared inoperable (untrippable).
You have been requested to perform an instantaneous shutdown margin calculation to determine if technical specification requirements for shutdown margin are being met.
The RCS boron concentration is 400 ppm. The burnup is 12000 MWD/MTU Page 5 of 5
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-2 JPM
Title:
Determine Pressurizer Level During Cooldown Approximate Time: 10 minutes Actual Time: _________________
Reference(s): K/A# 2.1.25 RO Importance 3.9 TDB-III.1.a, "TEMPERATURE CORRECTION FOR PRESSURIZER LEVEL INDICATORS LI-101X/Y".
TDB-III.2, "ACTUAL LEVEL IN PRESSURIZER VS. INDICATED LEVEL IN PRESSURIZER.
JPM Prepared by: Jerry Koske Date: 02/01/09 Page 1 of 5
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-2 JPM
Title:
Determine Pressurizer Level During Cooldown Operators Name: _____________________ Employee # ______________
All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):
SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________
Reason, if unsatisfactory:
Tools & Equipment: TDB, Ruler, Steam Tables Safety Considerations:
Comments:
Page 2 of 5
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-2 JPM
Title:
Determine Pressurizer Level During Cooldown INITIATING CUE: The RCS is being cooled down per OP-3A. RCS pressure is at 250 psia.
A dummy level signal has been placed on pressurizer level channel LI-101X and it is selected as the controlling channel.
The pressurizer level indications are as follows:
LI-101X = 48%
LI-101Y = 50%
LI-106 = 34%
The CRS has asked you to determine that actual pressurizer level using both LI-101Y and LI-106 to determine if the pressurizer heaters need to be turned off?
Critical Steps shown in gray STEP ELEMENT STANDARD 1 Refers to TDB-III.1.a and Level based on LR-101Y is determines that the actual approximately 40% (35 - 45%)
pressurizer level based on LR-101Y. [ SAT ] [ UNSAT ]
2 Refers to TDB-III.2 and Level based on LI-106 is determines that the actual approximately 40% (35 - 45%)
pressurizer level based on LI-106. [ SAT ] [ UNSAT ]
3 Determines if heaters need to Determines that heaters do not be turned off. have to be turned off because actual level is above 32%
[ SAT ] [ UNSAT ]
Page 3 of 5
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-2 JPM
Title:
Determine Pressurizer Level During Cooldown Termination Criteria: Actual level has been determined both channels and a determination has been made on the need to turn off the heaters.
Page 4 of 5
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No:A-2 Rev 0 INITIATING CUE: The RCS is being cooled down per OP-3A. RCS pressure is at 250 psia.
A dummy level signal has been placed on pressurizer level channel LI-101X and it is selected as the controlling channel.
The pressurizer level indications are as follows:
LI-101X = 48%
LI-101Y = 50%
LI-106 = 34%
The CRS has asked you to determine that actual pressurizer level using both LI-101Y and LI-106 to determine if the pressurizer heaters need to be turned off?
NAME: ________________________________________
Actual Level based on LR-101-Y: ______________%
Actual Level based on LI-106: _______________%
Do Heaters Need to be turned off: YES NO Page 5 of 5
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-3 Rev 0 JPM
Title:
Determine equipment lost by tagout of an MCC.
Approximate Time: 10 minutes Actual Time: _________________
Reference(s): K/A# 2.2.15 RO Importance 3.9 P&ID Figure 8.1-1 (File 12234)
JPM Prepared by: Jerry Koske Date: 02/02/09 Page 1 of 5
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-3 Rev 0 JPM
Title:
Determine equipment lost by tagout of an MCC.
Operators Name: _____________________ Employee # ______________
All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):
SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________
Reason, if unsatisfactory:
Tools & Equipment: P&ID Books Safety Considerations:
Comments:
Page 2 of 5
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-3 Rev 0 JPM
Title:
Determine equipment lost by tagout of an MCC.
INITIATING CUE: Maintenance is requesting that MCC-3B2 be taken out of service for some repairs. The CRS has directed you to determine what equipment would be affected by tagout of MCC-3B2.
Critical Steps shown in gray STEP ELEMENT STANDARD 1 Refers to P&ID to determine Note:
affected equipment. If candidate requests copy of the ELDL, "Electrical Load Distribution List",
Inform him that the ELDL is not available.
Uses P&ID Figure 8.1-1 (File 12234) to determine affected equipment.
[ SAT ] [ UNSAT ]
Page 3 of 5
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-3 Rev 0 JPM
Title:
Determine equipment lost by tagout of an MCC.
STEP ELEMENT STANDARD 2 Provides list of affected List includes:
equipment. VD-7A AC-9A EHC-3A EE2G-1A VD-5A CF-4 CF-5 CF-7A VA-151C VA-158A,C,E,G,H,K,M LO-7 LO-6 LO-2 VA-766
[ SAT ] [ UNSAT ]
Termination Criteria: List of affected equipment has been provided.
Page 4 of 5
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-3 Rev 0 INITIATING CUE: Maintenance is requesting that MCC-3B2 be taken out of service for some repairs. The CRS has directed you to determine what equipment would be affected by tagout of MCC-3B2.
Equipment affected:
Page 5 of 5
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-4 Rev 0 JPM
Title:
RCA Entry and Exit with PCM Alarms Approximate Time: 12 minutes Actual Time: _________________
Reference(s): K/A# 2.3.7 RO Importance 3.5 GET-Radiation Worker Training.
Standing Order G-101, "RADIATION WORKER PRACTICES."
JPM Prepared by: Jerry Koske Date: 02/01/09 Page 1 of 7
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-4 Rev 0 JPM
Title:
RCA Entry and Exit with PCM Alarms Operators Name: _____________________ Employee # ______________
All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):
SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________
Reason, if unsatisfactory:
Tools & Equipment: EAD, TLD, PCM-1, G-M with pancake probe Safety Considerations:
Comments: Can be conducted in GET trailer or during actual RCA Entry Page 2 of 7
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-4 Rev 0 JPM
Title:
RCA Entry and Exit with PCM Alarms INITIATING CUE: A plant procedure that you are performing requires entry into the RCA.
Critical Steps shown in gray STEP ELEMENT STANDARD 1 Review the RWP. Reads RWP.
[ SAT ] [ UNSAT ]
2 Determine Radiological Checks survey maps or Conditions. discusses radiological conditions with RP personnel.
[ SAT ] [ UNSAT ]
3 Obtains Dosimetry. Obtain TLD and EAD.
[ SAT ] [ UNSAT ]
4 Sign on to appropriate RWP. Insert EAD in reader. Scan PID and RWP number.
[ SAT ] [ UNSAT ]
[ SAT ] [ UNSAT ]
6 CUE: Your task is complete, exit the RCA.
Page 3 of 7
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-4 Rev 0 JPM
Title:
RCA Entry and Exit with PCM Alarms STEP ELEMENT STANDARD 7 Exits RCA. Returns to RCA access point.
[ SAT ] [ UNSAT ]
8 Monitor for personnel Monitor for contamination contamination prior to exiting using PCM-1.
RCA.
[ SAT ] [ UNSAT ]
CUE: After examinee has completed counting on a PCM-1, tell him to assume that the PCM-1 alarmed-zone 6.
9 Monitor for contamination a Monitor for contamination second time. again using a different PCM-1.
[ SAT ] [ UNSAT ]
CUE: After examinee has completed counting on another PCM-1, tell him to assume that this PCM-1 also alarmed- zone 6.
[ SAT ] [ UNSAT ]
CUE: RP directs that you to monitor for contamination using frisker.
Page 4 of 7
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-4 Rev 0 JPM
Title:
RCA Entry and Exit with PCM Alarms STEP ELEMENT STANDARD 11 Uses Frisker to monitor for Slowly moves pancake probe contamination. over hands, shoes and body surface.
CUE: Frisker cpm as read.
[ SAT ] [ UNSAT ]
Termination Criteria: RCA has been exited.
Page 5 of 7
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-4 Rev 0 JPM
Title:
RCA Entry and Exit with PCM Alarms NOTE to RP Tech As a part of this candidates NRC license exam, he must enter and exit the RCA.
During RCA exit, he has been given verbal Cues that he has received a zone 6 alarm on two separate PCM-1 monitors.
As a part of this JPM, we would like you to direct him to perform a whole body frisk on himself.
Page 6 of 7
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-4 Rev 0 INITIATING CUE: A plant procedure that you are performing requires entry into the RCA.
Page 7 of 7
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-5 Rev 0 JPM
Title:
Review Shutdown Margin Calculation Approximate Time: 25 minutes Actual Time: _________________
Reference(s): K/A 2.1.37 SRO Importance 4.6 TDB-V.9, "SHUTDOWN MARGIN WORKSHEET" TDB-II, "REACTIVITY CURVES" JPM Prepared by: Jerry Koske Date: 01/31/09 Page 1 of 5
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-5 Rev 0 JPM
Title:
Review Shutdown Margin Calculation Operators Name: _____________________ Employee # ______________
All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):
SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________
Reason, if unsatisfactory:
Tools & Equipment: TDB, ruler, calculator Safety Considerations:
Comments:
Page 2 of 5
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-5 Rev 0 JPM
Title:
Review Shutdown Margin Calculation INITIATING CUE: The plant is operating at 60% power with group 4 CEAs at 110 inches withdrawn. Group A CEA #36 and Group 2 CEA #24 have been declared inoperable (untrippable).
The RCS boron concentration is 400 ppm. The burnup is 12000 MWD/MTU.
The STA has performed a shutdown margin calculation and determined that Shutdown Margin is adequate. The Shift Manager has requested that you review the shutdown margin calculation and , if there are any mistakes, correct them.
Critical Steps shown in gray STEP ELEMENT STANDARD Note to Examiner:
Provide Shutdown Margin Calculation to candidate with initiating cue.
1 Reviews shutdown margin Determines that there was an calculation. error in step 7.a due to reading the value from the wrong row.
5.238 (Shutdown Group A+B worth was entered instead of shutdown group B worth).
[ SAT ] [ UNSAT ]
2 Determines that in step 8, the 100% power defect was used instead of the 60% power defect.
[ SAT ] [ UNSAT ]
Page 3 of 5
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-5 Rev 0 JPM
Title:
Review Shutdown Margin Calculation STEP ELEMENT STANDARD 3 Performs calculation of the Difference calculated on line difference between actual and 11 of TDB-V.9, section 1 is required shutdown margin +0.7 [between +0.5, +0.9].
using corrected values.
[ SAT ] [ UNSAT ]
4 Determines if SDM is Determines Shutdown Margin adequate. is inadequate.
[ SAT ] [ UNSAT ]
Termination Criteria: SRO has determined that shutdown margin is not adequate and has corrected the SDM calculation.
Page 4 of 5
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-5 Rev 0 INITIATING CUE: The plant is operating at 60% power with group 4 CEAs at 110 inches withdrawn. Group A CEA #36 and Group 2 CEA #24 have been declared inoperable (untrippable).
The RCS boron concentration is 400 ppm. The burnup is 12000 MWD/MTU.
The STA has performed a shutdown margin calculation and determined that Shutdown Margin is adequate. The Shift Manager has requested that you review the shutdown margin calculation and , if there are any mistakes, correct them.
Page 5 of 5
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-6 Rev 0 JPM
Title:
Determine Shift Staffing Approximate Time: 12 minutes Actual Time: _________________
Reference(s): K/A# 2.1.5 SRO Importance 3.9 Technical Specifications Table 5.2-1 SO-O-1, "CONDUCT OF OPERATIONS" SO-G-52, "PLANT STAFF WORKING HOURS" JPM Prepared by: Jerry Koske Date: 02/02/09 Page 1 of 5
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-6 Rev 0 JPM
Title:
Determine Shift Staffing Operators Name: _____________________ Employee # ______________
All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):
SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________
Reason, if unsatisfactory:
Tools & Equipment:
Safety Considerations:
Comments:
Page 2 of 5
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-6 Rev 0 JPM
Title:
Determine Shift Staffing INITIATING CUE: The plant is operating at full power. You are the Shift Manager. Your crew consists of yourself, your CRS, your STA (who is also CRS qualified), two RO's, a EONA, a EONT, a AON (who is also Communicator qualified) and a Control Room Communicator.
Half way through your shift, your CRS and your Control Room Communicator become sick and need to go home.
Your STA suggests that he can serve as both CRS and STA for the remainder of the shift since he is qualified for both positions.
Your AON suggests that he can serve as both AON and Control Room Communicator for the remainder of the shift since he is qualified for both positions.
Determine if each of these suggestions is acceptable. If not, specify what actions must be taken and when they must be taken.
Critical Steps shown in gray STEP ELEMENT STANDARD 1 Determine if the STA may fill Refers to Technical both the CRS and the STA Specifications Table 5.2-1 and position for the remainder of Standing Order SO-O-1.
the shift.
Determines that 2 SROs and an STA are required and this suggestion is not acceptable.
[ SAT ] [ UNSAT ]
Page 3 of 5
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-6 Rev 0 JPM
Title:
Determine Shift Staffing STEP ELEMENT STANDARD 2 Determine if the AON may fill Refers to Technical both the AON and the Control Specifications Table 5.2-1 and Room Communicator position Standing Order SO-O-1.
for the remainder of the shift.
Determines that 2 NLOs are required and this suggestion is acceptable.
[ SAT ] [ UNSAT ]
3 Determine what actions must Determines that the CRS must be taken and when these turnover to the CRS qualified actions must be taken. STA and that immediate action must be taken to call in another qualified STA or another qualified CRS and the called in STA or CRS must be in position within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
[ SAT ] [ UNSAT ]
Termination Criteria: Candidate has determined shift staffing requirements, actions that must be taken and required time frame for these actions.
Page 4 of 5
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-6 rev 0 INITIATING CUE: The plant is operating at full power. You are the Shift Manager. Your crew consists of yourself, your CRS, your STA (who is also CRS qualified), your RO's, a EONA, a EONT, a AON (who is also Communicator qualified) and a Control Room Communicator.
Half way through your shift, your CRS and your Control Room Communicator become sick and need to go home.
Your STA suggests that he can serve as both CRS and STA for the remainder of the shift since he is qualified for both positions.
Your AON suggests that he can serve as both AON and Control Room Communicator for the remainder of the shift since he is qualified for both positions.
Determine if each of these suggestions is acceptable. If not specify what actions must be taken and when they must be taken.
Can the STA serve as both CRS and STA? YES NO Can the AON serve as both AON and Control Room Communicator YES NO What action, if any, must be taken? When must it be taken?
Page 5 of 5
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-7 Rev 0 JPM
Title:
Determine RW System Operability Approximate Time: 12 minutes Actual Time: _________________
Reference(s): K/A# 2.2.22 SRO Importance 4.7 TDB VIII, "EQUIPMENT OPERABILITY GUIDANCE" Technical Specification 2.4 Technical Specification 2.0.1 JPM Prepared by: Jerry Koske Date: 02/02/09 Page 1 of 4
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-7 Rev 0 JPM
Title:
Determine RW System Operability Operators Name: _____________________ Employee # ______________
All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):
SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________
Reason, if unsatisfactory:
Tools & Equipment:
Safety Considerations:
Comments:
Page 2 of 4
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-7 Rev 0 JPM
Title:
Determine RW System Operability INITIATING CUE: The plant is operating at full power.
It has been determined that RW/CCW Backup Header Isolation Valves, HCV-2893 and HCV-2894, are both inoperable. They are both closed and cannot be opened.
Determine the applicable Technical Specification and required actions, if any, to be taken.
START Critical Steps shown in gray STEP ELEMENT STANDARD 1 Refers to TDB-VIII. Enters TDB-VIII.
[ SAT ] [ UNSAT ]
2 Refers to Table 2-1 to Determines that T.S. 2.0.1 determine applicable LCO. applies with these conditions.
[ SAT ] [ UNSAT ]
3 Determines Tech Spec. 2.0.1 Plant must be in Hot Shutdown required Action Statement. within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
[ SAT ] [ UNSAT ]
Termination Criteria: Technical Specification 2.0.1 has been entered.
Page 3 of 4
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-7 Rev 0 INITIATING CUE: The plant is operating at full power.
It has been determined that RW/CCW Backup Header Isolation Valves, HCV-2893 and HCV-2894, are both inoperable. They are both closed and cannot be opened.
Determine the applicable Technical Specification and required actions, if any, to be taken.
START Technical Specification Entered, if any:
Required Action, if any:
Page 4 of 4
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-8 Rev 0 JPM
Title:
Authorize Release of Monitor Tank WD-22B Approximate Time: 10 minutes Actual Time: _________________
Reference(s): K/A# 2.3.6 SRO Importance 3.8 OI-WDL-3, "LIQUID WASTE DSPOSAL RELEASE FC-211, "WASTE LIQUID TANK RELEASE PERMIT" JPM Prepared by: Jerry Koske Date: 02/02/09 Page 1 of 4
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-8 Rev 0 JPM
Title:
Authorize Release of Monitor Tank WD-22B Operators Name: _____________________ Employee # ______________
All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):
SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________
Reason, if unsatisfactory:
Tools & Equipment:
Safety Considerations:
Comments:
Page 2 of 4
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-8 Rev 0 JPM
Title:
Authorize Release of Monitor Tank WD-22B INITIATING CUE: You are the Shift Manager. A release of Monitor Tank, WD-22B, is planned. The EONA has brought OI-WDL-3 and a Release Permit to you and asked that you authorize the release. Make any corrections, if required.
START Critical Steps shown in gray STEP ELEMENT STANDARD 1 Reviews partially filled out OI- Examines procedure and WDL-3 and associated FC-211 Release Permit.
Release Permit.
[ SAT ] [ UNSAT ]
2 Determines that the maximum Maximum release rate should release rate and administrative be 84.6 gpm. Administrative release rate recorded on the release rate should be 76.1 procedure do not agree with gpm.
the Release Permit.
[ SAT ] [ UNSAT ]
3 Release Authorization. Does not authorize release as written.
Corrects maximum (84.6 gpm) and administrative (76.1 gpm) release rates prior to authorizing release.
[ SAT ] [ UNSAT ]
Termination Criteria: Candidate has made correction and authorized release.
Page 3 of 4
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-8 Rev 0 INITIATING CUE: You are the Shift Manager. A release of Monitor Tank, WD-22B, is planned. The EONA has brought OI-WDL-3 and a Release Permit to you and asked that you authorize the release. Make any corrections, if required.
START Page 4 of 4
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-9 Rev 0 JPM
Title:
Emergency Classification and PARs Approximate Time: 10 minutes Actual Time: _________________
Reference(s): K/A# 2.4.41 SRO Importance 4.6 K/A# 2.4.44 SRO Importance 4.4 EPIP-OSC-1, "EMERGENCY CLASSIFICATION" EPIP-EOF-7, "PROTECTIVE ACTION GUIDELINES TDB-IV.8, "AREA MONITORING SETPOINTS" JPM Prepared by: Jerry Koske Date: 1/29/09 Page 1 of 5
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-9 Rev 0 JPM
Title:
Emergency Classification and PARs Operators Name: _____________________ Employee # ______________
All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):
SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________
Reason, if unsatisfactory:
Tools & Equipment: Blank FC-1188 Safety Considerations: None Comments: SRO , Time Critical - 15 minutes Page 2 of 5
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-9 Rev 0 JPM
Title:
Emergency Classification and PARs INITIATING CUE: This is a Time Critical JPM - 15 minutes A refueling outage is in progress. Spent fuel assemblies were being moved using FH-12 when a fuel assembly fell from FH-12 and landed on a spent fuel rack. High radiation alarms were received on RM-085 and RM-087. RM-085 is reading 1200 mrem/hr and RM-087 is reading 1100 mrem/hr. Radiation levels on RM-052 and RM-062 are also rising.
There is no precipitation.
Your Shift HP has run EAGLE and has provided you with the output.
You are directed to enter the Emergency Plan, classify the event and determine offsite Protective Action Recommendations.
Complete page 1 of form FC-1188.
Critical Steps shown in gray Critical Steps shown in gray STEP ELEMENT STANDARD 1 Refer to Emergency Plan. Refer to EPIP-OSC-1 and EPIP-EOF-7.
[ SAT ] [ UNSAT ]
Page 3 of 5
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-9 Rev 0 JPM
Title:
Emergency Classification and PARs STEP ELEMENT STANDARD 2 Classify the event This Event should be classified as a SITE AREA EMERGENCY, EAL 7.3, "MAJOR IRRADIATED FUEL ACCIDENT" RM-087 is reading more than 1000 times its normal refueling shutdown value per TDB-IV.8 MUST be Classified within 15 minutes.
[ SAT ] [ UNSAT ]
3 Determine Protective Action The Protective Action Recommendations Recommendation should be:
NONE.
[ SAT ] [ UNSAT ]
Termination Criteria: The event has been classified within 15 minutes.
PARS have been determined and FC-1188 has been filled out.
Page 4 of 5
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No:A-9 Rev 0 INITIATING CUE: This is a Time Critical JPM - 15 minutes A refueling outage is in progress. Spent fuel assemblies were being moved using FH-12 when a fuel assembly fell from FH-12 and landed on a spent fuel rack. High radiation alarms were received on RM-085 and RM-087. RM-085 is reading 1200 mrem/hr and RM-087 is reading 1100 mrem/hr. Radiation levels on RM-052 and RM-062 are also rising.
There is no precipitation.
Your Shift HP has run EAGLE and has provided you with the output.
You are directed to enter the Emergency Plan, classify the event and determine offsite Protective Action Recommendations.
Complete page 1 of form FC-1188.
Page 5 of 5
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: J-1 Rev 0 JPM
Title:
Control Element Assembly Movement Test Location: Simulator Approximate Time: 18 minutes Actual Time: _________________
Reference(s): K/A: 001000 A4.03 OP-ST-CEA-0003, "CONTROL ELEMENT ASSEMBLY (CEA)
PARTIAL MOVEMENT TEST" JPM Prepared by: Jerry Koske Date: 1/28/09 Page 1 of 8
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: J-1 Rev 0 JPM
Title:
Control Element Assembly Movement Test Operators Name: _____________________ Employee # ______________
All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):
SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________
Reason, if unsatisfactory:
Tools & Equipment: None Safety Considerations:
Comments: Alternate Path Page 2 of 8
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: J-1 Rev 0 JPM
Title:
Control Element Assembly Movement Test INITIATING CUE: The plant is operating at full power with all CEAs fully withdrawn.
You have been directed to perform the CEA Partial Movement Check for group 3 CEAs (2, 3, 4 and 5) using OP-ST-CEA-0003.
All prerequisites have been met.
Critical Steps shown in gray STEP ELEMENT STANDARD 1 Record the initial position of Records position of CEAs each group 3 CEA. 2,3,4 and 5 as 128 inches on OP-ST-CEA-003, attachment 1.
[ SAT ] [ UNSAT ]
2 Rotate the Mode selector CB-4 switch to Manual Individual Places Mode Selector Switch position. (M/M) to the Manual Individual Position (M/I).
[ SAT ] [ UNSAT ]
3 Rotate the Group Selector CB-4 Switch (M/G) to the group Rotate Group Selector Switch containing the CEA to be (M/G) to the "Group 3" moved. position.
[ SAT ] [ UNSAT ]
Page 3 of 8
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: J-1 Rev 0 JPM
Title:
Control Element Assembly Movement Test STEP ELEMENT STANDARD 4 Verify on the DCS display CB-4 CEA_ALL that the group button Ensure CEA-ALL is displayed is DARK GREY. and that Group 3 is DARK GREY.
[ SAT ] [ UNSAT ]
5 Rotate the Rod Selector Switch CB-4 to the CEA to be moved. Rotate Rod Selector Switch to CEA #2 position.
[ SAT ] [ UNSAT ]
6 Insert CEA a minimum of 6 CB-4 inches then return to normal Push IN-OUT-HOLD switch in position. until CEA#2 position is 122 inches or less. Then Pull IN-OUT-HOLD switch until CEA
- 2 is fully withdrawn.
[ SAT ] [ UNSAT ]
7 Record Information on Record inserted and returned Attachment 1. to position for CEA#2 on Attachment 1.
[ SAT ] [ UNSAT ]
8 Rotate the Rod Selector Switch CB-4 to the CEA to be moved. Rotate Rod Selector Switch to CEA #3 position.
[ SAT ] [ UNSAT ]
Page 4 of 8
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: J-1 Rev 0 JPM
Title:
Control Element Assembly Movement Test STEP ELEMENT STANDARD 9 Insert CEA a minimum of 6 CB-4 inches then return to normal Push IN-OUT-HOLD switch in position. until CEA#3 position is 122 inches or less. Then Pull IN-OUT-HOLD switch until CEA
- 3 is fully withdrawn.
[ SAT ] [ UNSAT ]
10 Record Information on Record inserted and returned Attachment 1. to position for CEA#3 on Attachment 1.
[ SAT ] [ UNSAT ]
11 Rotate the Rod Selector Switch CB-4 to the CEA to be moved. Rotate Rod Selector Switch to CEA #4 position.
[ SAT ] [ UNSAT ]
12 Insert CEA a minimum of 6 CB-4 inches then return to normal Push IN-OUT-HOLD switch in position. until CEA#4 position is 122 inches or less. Then Pull IN-OUT-HOLD switch until CEA
- 4 is fully withdrawn.
[ SAT ] [ UNSAT ]
CEA will continue to insert 13 Place Mode Selector Switch in CB-4 OFF. Return Mode Selector Switch to OFF position. Verify CEA motion has stopped.
[ SAT ] [ UNSAT ]
Page 5 of 8
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: J-1 Rev 0 JPM
Title:
Control Element Assembly Movement Test STEP ELEMENT STANDARD CUE: Electrical Maintenance has repaired the problem with the CRDM circuitry.
Continue the test.
14 Rotate the Mode selector CB-4 switch to Manual Individual Places Mode Selector Switch position. (M/M) to the Manual Individual Position (M/I).
[ SAT ] [ UNSAT ]
15 Return CEA to normal position. Then Pull IN-OUT-HOLD switch until CEA #4 is fully withdrawn.
[ SAT ] [ UNSAT ]
16 Record Information on Record inserted and returned Attachment 1. to position for CEA#4 on Attachment 1.
[ SAT ] [ UNSAT ]
17 Rotate the Rod Selector Switch CB-4 to the CEA to be moved. Rotate Rod Selector Switch to CEA #5 position.
[ SAT ] [ UNSAT ]
18 Insert CEA a minimum of 6 CB-4 inches then return to normal Push IN-OUT-HOLD switch in position. until CEA#5 position is 122 inches or less. Then Pull IN-OUT-HOLD switch until CEA
- 5 is fully withdrawn.
[ SAT ] [ UNSAT ]
Page 6 of 8
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: J-1 Rev 0 JPM
Title:
Control Element Assembly Movement Test STEP ELEMENT STANDARD 19 Record Information on Record inserted and returned Attachment 1. to position for CEA#4 on Attachment 1.
[ SAT ] [ UNSAT ]
20 Place Mode Selector Switch in CB-4 OFF. Return Mode Selector Switch to OFF position.
[ SAT ] [ UNSAT ]
21 Request independent CUE:
verification of each CEA Independent verification has returned to initial position. been performed.
Termination Criteria: Partial CEA movement test has been completed for Group 3 CEAs.
Page 7 of 8
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: J-1 Rev 0 INITIATING CUE: The plant is operating at full power with all CEAs fully withdrawn.
You have been directed to perform the CEA Partial Movement Check for group 3 CEAs (2, 3, 4 and 5) using OP-ST-CEA-0003.
All prerequisites have been met.
Page 8 of 8
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: J-2 Rev 0 JPM
Title:
Establish Charging Flow via the HPSI Header Location: Simulator Approximate Time: 12 minutes Actual Time: _________________
Reference(s): K/A# 004000 A4.08 AOP-33, Attachment B, "CHARGING FROM THE HPSI HEADER."
JPM Prepared by: Jerry Koske Date: 1/28/09 Page 1 of 6
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: J-2 Rev 0 JPM
Title:
Establish Charging Flow via the HPSI Header Operators Name: _____________________ Employee # ______________
All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):
SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________
Reason, if unsatisfactory:
Tools & Equipment: None Safety Considerations:
Comments:
Page 2 of 6
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: J-2 Rev 0 JPM
Title:
Establish Charging Flow via the HPSI Header INITIATING CUE: AOP-33 has been entered due to a leak in the charging header. Charging and letdown have been isolated.
The CRS has directed you to reestablish charging pump flow via the HPSI header using HPSI loop injection valve, HCV-318 per AOP-33, Attachment B.
Critical Steps shown in gray STEP ELEMENT STANDARD 1 Close CH-194, "CHARGING Direct EONA to close CH-194.
PUMPS CH-1A/B/C DISCHARGE HEADER [ SAT ] [ UNSAT ]
CONTAINMENT OUTBOARD ISOLATION VALVE" (Room CUE: EONA reports that CH-13). 194 is closed.
2 Open HCV-308, Charging CB-1,2,3 Pump HPSI Header Isolation Hold HCV-308 Control Switch Valve. in OPEN until GREEN light goes OFF. Then Release and allow it to return to NORM.
Verify RED light ON and GREEN light OFF.
[ SAT ] [ UNSAT ]
3 Ensure HCV-2987, HPSI CB-1,2,3 Header Isolation Valve, is Hold HCV-2987 Control Switch open. in OPEN until RED light is ON and GREEN light is OFF.
[ SAT ] [ UNSAT ]
Page 3 of 6
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: J-2 Rev 0 JPM
Title:
Establish Charging Flow via the HPSI Header STEP ELEMENT STANDARD 4 Ensure HCV-307, HPSI Header AI-30B Isolation Valve, is open. Key Switch to OPEN.
RED light ON.
GREEN light OFF.
[ SAT ] [ UNSAT ]
5 Ensure HCV-305, SI-2A and AI-30B SI-2C Discharge Cross- Key Switch to OPEN.
Connect Valve, is open. RED light ON.
GREEN light OFF.
[ SAT ] [ UNSAT ]
6 Ensure HCV-304, SI-2B and AI-30A SI-2C Discharge Cross- Key Switch to OPEN.
Connect Valve, is open. RED light ON.
GREEN light OFF.
[ SAT ] [ UNSAT ]
7 Ensure HCV-306, HPSI Header AI-30A Isolation Valve, is open. Key Switch to OPEN.
RED light ON.
GREEN light OFF.
[ SAT ] [ UNSAT ]
8 Close the SI Tank Leakage AI-30A Cooler Pressure Control Valves Adjust PCV-2949 Controller on the loop in which the HPSI such that needle indicates valve(s) will be opened, 100% (full right).
PCV-2949. GREEN light ON.
RED light OFF.
[ SAT ] [ UNSAT ]
Page 4 of 6
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: J-2 Rev 0 JPM
Title:
Establish Charging Flow via the HPSI Header STEP ELEMENT STANDARD 9 Open HCV-318 (Loop 2A). AI-30B HCV-318 Control Switch to OPEN. RED light ON, GREEN light OFF.
(Note: may also PULLOUT switch, but not required)
[ SAT ] [ UNSAT ]
10 Ensure a charging pump CB-1,2,3 suction source is available. Ensure LCV-218-2 open RED light ON and VCT level indicated on chart or indicator.
OR Ensure LCV-218-3 open RED light ON.
[ SAT ] [ UNSAT ]
11 Operate any available CB-1,2,3 Charging Pumps as necessary Start at least one charging to maintain PZR level within pump, CH-1A/B/C by taking 4% of programmed level. Control switch out of Pull-To-Lock, taking to AFTER-START and verifying RED light ON.
[ SAT ] [ UNSAT ]
Termination Criteria: A charging pump is supplying water to the RCS via the HPSI header.
Page 5 of 6
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: J-2 Rev 0 INITIATING CUE: AOP-33 has been entered due to a leak in the charging header. Charging and letdown have been isolated.
The CRS has directed you to reestablish charging pump flow via the HPSI header using HPSI loop injection valve HCV-318 per AOP-33, Attachment B.
Page 6 of 6
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: J-3 Rev 0 JPM
Title:
Simultaneous Hot and Cold Leg Injection Location: Simulator Approximate Time: 15 minutes Actual Time: _________________
Reference(s): K/A# 006000 A1.11 EOP/AOP Attachment 9, "SIMULTANEUOS HOT AND COLD LEG INJECTION" EOP/AOP Attachment 10, SIMULTANEUOS HOT AND COLD LEG INJECTION WITHOUT INSTRUMENT AIR" JPM Prepared by: Jerry Koske Date: 1/28/09 Page 1 of 6
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: J-3 Rev 0 JPM
Title:
Simultaneous Hot and Cold Leg Injection Operators Name: _____________________ Employee # ______________
All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):
SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________
Reason, if unsatisfactory:
Tools & Equipment: None Safety Considerations: None Comments: Alternate Path Page 2 of 6
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: J-3 Rev 0 JPM
Title:
Simultaneous Hot and Cold Leg Injection INITIATING CUE: A LOCA occurred 5.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> ago. HPSI pumps, SI-2A and SI-2B, are operating. There are no signs of containment sump blockage.
The Control Room Supervisor has directed you to initiate Simultaneous Hot and Cold Leg Injection.
Critical Steps shown in gray STEP ELEMENT STANDARD Note to Examiner:
Do Not provide Attachment 10 to candidate until he makes the transition prior to step 4.
1 Open at least one of the CB-1,2,3 Charging Pumps HPSI Header Isolation Valves: At least one valves control HCV-308. switch to OPEN with RED light HCV-2988. ON.
[ SAT ] [ UNSAT ]
2 Open at least one of the CB-1,2,3 following PZR Auxiliary Spray Isolation Valves: At least one valves control
- HCV-240. switch to OPEN with RED light
- HCV-249. ON.
[ SAT ] [ UNSAT ]
Page 3 of 6
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: J-3 Rev 0 JPM
Title:
Simultaneous Hot and Cold Leg Injection STEP ELEMENT STANDARD 3 Ensure ALL of the following CB-1,2,3 Charging Isolation Valves are For each valve:
closed: GREEN light ON.
- HCV-238. RED light OFF.
- HCV-239.
- HCV-247. [ SAT ] [ UNSAT ]
- HCV-248.
4 IF HPSI Pump, SI-2A, is AI-30B operating,THEN close HCV- Key Switch to CLOSE.
305, SI-2A and SI-2C GREEN light ON.
Discharge Cross-Connect RED light OFF.
Valve.
Determines that HCV-305 will not close. Goes to EOP/AOP Attachment 10.
[ SAT ] [ UNSAT ]
5 Close ALL of the following AI-30A/B HPSI Loop Injection Valves:
- HCV-315. Control Switches to CLOSE
- HCV-318. (pull out, counter-clockwise)
- HCV-312. until GREEN lights ON.
- HCV-321.
[ SAT ] [ UNSAT ]
6 Close HCV-2987, HPSI Header AI-30A/B Isolation Valve.
Control Switch to CLOSE.
GREEN light ON.
RED light OFF.
[ SAT ] [ UNSAT ]
Page 4 of 6
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: J-3 Rev 0 JPM
Title:
Simultaneous Hot and Cold Leg Injection STEP ELEMENT STANDARD 7 IF evidence of containment AI-30A/B sump blockage does NOT exist, THEN throttle the HPSI Throttle one or more of the Loop Injection Valves until ALL following valves:
of the following criteria are HCV-314.
satisfied: HCV-317.
Charging flow is greater HCV-311.
than180 gpm (FIA-236). HCV-311.
Total HPSI flow is Verify greater than 200 gpm greater than 200 gpm. total flow on FI-313, FI-316, FI-319 and FI-322.
CB-1,2,3 Verify greater than 180 gpm flow on FIA-236.
Note: Plant computer may also be used to verify flows.
[ SAT ] [ UNSAT ]
Termination Criteria: Simultaneous Hot and Cold Leg Injection has been established with greater than 180 gpm flow through charging (Hot Leg) and greater than 200 gpm flow through the HPSI Header (Cold Legs).
Page 5 of 6
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: J-3 Rev 0 INITIATING CUE: A LOCA occurred 5.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> ago. HPSI pumps, SI-2A and SI-2B, are operating. There are no signs of containment sump blockage.
The Control Room Supervisor has directed you to initiate Simultaneous Hot and Cold Leg Injection.
Page 6 of 6
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: J-4 Rev 0 JPM
Title:
Start a Reactor Coolant Pump Location: Simulator Approximate Time: 7 minutes Actual Time: _________________
Reference(s): K/A# 003000 A4.06 OI-RC-9, "REACTOR COOLANT PUMP OPERATION" JPM Prepared by: Jerry Koske Date: 1/29/09 Page 1 of 6
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: J-4 Rev 0 JPM
Title:
Start a Reactor Coolant Pump Operators Name: _____________________ Employee # ______________
All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):
SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________
Reason, if unsatisfactory:
Tools & Equipment: None Safety Considerations: None Comments: Alternate Path Page 2 of 6
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: J-4 Rev 0 JPM
Title:
Start a Reactor Coolant Pump INITIATING CUE: A plant startup is in progress. RC-3C is running. You are directed to place RC-3A in service. All prerequisites are met.
Critical Steps shown in gray STEP ELEMENT STANDARD Simulator Operator fail 90%
speed switch for RC-3A 1 Setup ERF Display for RC-3A. ERF Type [440] [DSP]
RC-3A Page displays.
[ SAT ] [ UNSAT ]
2 Station operator to respond to CUE: Operator is at AI-270.
vibration alarms.
[ SAT ] [ UNSAT ]
3 Verify controlled Bleed-off flow. ERF page 342 Verify positive bleed-off flow.
[ SAT ] [ UNSAT ]
4 Ensure RCP NPSH. Use Figure TDB III.25.
[ SAT ] [ UNSAT ]
5 Ensure 86/RC-3A reset. CB-1/2/3 86/RC-3A AMBER light ON.
[ SAT ] [ UNSAT ]
Page 3 of 6
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: J-4 Rev 0 JPM
Title:
Start a Reactor Coolant Pump STEP ELEMENT STANDARD 6 Verify RCP Reverse rotation is CB-1/2/3 cleared. ANN A-6, D-5 clear.
[ SAT ] [ UNSAT ]
7 Start RC-3A oil lift pump. CB-1/2/3 RC-3A-1 in START and RED light ON.
[ SAT ] [ UNSAT ]
8 Verify AARD oil flow for RC-3A. ERF Page 342.
[ SAT ] [ UNSAT ]
CUE: The oil lift pump has been running for two minutes 9 Start RC-3A. CB-1/2/3 RC-3A CS in AFTER START and RED light ON.
[ SAT ] [ UNSAT ]
10 Verify oil pump stops. CB-1/2/3 RC-3A-1 GREEN light lit NOTE: Pump will not stop automatically and GREEN light will not come on due to 90% speed switch failure
[ SAT ] [ UNSAT ]
Page 4 of 6
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: J-4 Rev 0 JPM
Title:
Start a Reactor Coolant Pump STEP ELEMENT STANDARD 11 Trip RC-3A oil lift pump. CB-1/2/3 RC-3A-1 in STOP and GREEN light lit.
[ SAT ] [ UNSAT ]
12 Monitor Amps. Ammeter on CB-1/2/3 drops below 425 amps within 17 seconds.
[ SAT ] [ UNSAT ]
13 Verify Controlled Bleedoff flow. ERF Page 342
[ SAT ] [ UNSAT ]
14 Monitor RCP parameters. ERF Computer Display
[ SAT ] [ UNSAT ]
Termination Criteria: RC-3A is running normally Page 5 of 6
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: J-4 Rev 0 INITIATING CUE: A plant startup is in progress. RC-3C is running. You are directed to place RC-3A in service. All prerequisites are met.
Page 6 of 6
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: J-5 Rev 0 JPM
Title:
Initiate AFW to SGs via the AFW nozzles using FW-10 Location: Simulator Approximate Time: 10 minutes Actual Time: _________________
Reference(s): K/A# 061000 A2.04 EOP-06, "LOSS OF ALL FEEDWATER" JPM Prepared by: Jerry Koske Date: 1/29/09 Page 1 of 6
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: J-5 Rev 0 JPM
Title:
Initiate AFW to SGs via the AFW nozzles using FW-10 Operators Name: _____________________ Employee # ______________
All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):
SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________
Reason, if unsatisfactory:
Tools & Equipment: None Safety Considerations: None Comments: Alternate Path Page 2 of 6
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: J-5 Rev 0 JPM
Title:
Initiate AFW to SGs via the AFW nozzles using FW-10 INITIATING CUE: A reactor trip has occurred following a rupture of the Condensate Pumps' common discharge header. FW-54 is out of service. The CRS has entered EOP-6.
You have been directed to feed both steam generators from FW-10, via the AFW Nozzles.
Critical Steps shown in gray STEP ELEMENT STANDARD NOTE to Examiner: If the candidate requests an EONT or other In-plant Operator to take any actions during the performance of this JPM, inform him that the EONT is not available.
1 Start FW-10. AI-66B Place YCV-1045 switch in OPEN, verify RED light ON Verify YCV-1045A and /or YCV-1045B OPEN -RED light ON.
[ SAT ] [ UNSAT ]
2 Verify FW-10 Recirculation AI-66B Flow. Verify FCV-1369 is OPEN.
RED light ON.
Verify FIC-1369 indicates flow.
[ SAT ] [ UNSAT ]
Page 3 of 6
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: J-5 Rev 0 JPM
Title:
Initiate AFW to SGs via the AFW nozzles using FW-10 STEP ELEMENT STANDARD 3 Ensure HCV-1384 is closed. CB-10,11 Control Switch in AFTER CLOSE, GREEN light ON.
[ SAT ] [ UNSAT ]
4 Place Control Switches for AI-66A/B BOTH of the following AFW Place switches in CLOSE.
Isolation Valves in "CLOSE": GREEN LIGHT ON.
- HCV-1107B. RED light OFF.
- HCV-1108B.
[ SAT ] [ UNSAT ]
5 Open BOTH of the following AI-66A/B AFW Isolation Valves: Place switches in OPEN.
- HCV-1107A. RED LIGHT ON.
- HCV-1108A. GREEN light OFF.
[ SAT ] [ UNSAT ]
6 Manually control BOTH of CB-10,11 the following AFW Isolation Adjust controllers to open Valves: valves.
- HIC-1107B. Determines that valves will not
- HIC-1108B. open and that he must establish AFW flow via the feed ring.
[ SAT ] [ UNSAT ]
7 Ensure BOTH of the Feed CB-10,11 Reg Block Valves are GREEN lights ON.
closed:
- HCV-1103. [ SAT ] [ UNSAT ]
- HCV-1104.
Page 4 of 6
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: J-5 Rev 0 JPM
Title:
Initiate AFW to SGs via the AFW nozzles using FW-10 STEP ELEMENT STANDARD 8 Open HCV-1384, AFW/FW CB-10,11 Header Cross-Connect Control Switch to OPEN.
Valve. RED light ON.
GREEN light OFF.
[ SAT ] [ UNSAT ]
9 Ensure BOTH of the Feed CB-10,11 Header Isolation Valves are RED lights ON open:
- HCV-1386. [ SAT ] [ UNSAT ]
- HCV-1385.
10 Manually control feed flow CB-10,11 via BOTH of the Feed Reg DCS Panel Bypass Valves:
- HCV-1105. Manually open HCV-1105 and
- HCV-1106. HCV-1106 to establish flow.
[ SAT ] [ UNSAT ]
11 Verify AFW Flow established to CB-10,11 or ERF both S/Gs. Flow indicated on meters or ERF computer.
[ SAT ] [ UNSAT ]
Termination Criteria: Flow established from FW-10 to both Steam Generators Page 5 of 6
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: J-5 Rev 0 INITIATING CUE: A reactor trip has occurred following a rupture of the Condensate Pumps' common discharge header. FW-54 is out of service. The CRS has entered EOP-6.
You have been directed to feed both steam generators from FW-10, via the AFW Nozzles.
Page 6 of 6
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: J-6 Rev 0 JPM
Title:
Operate the Containment Hydrogen Analyzer Location: Simulator Approximate Time: 15 minutes Actual Time: _________________
Reference(s): K/A 028000 A1.01 EOP/AOP Attachment 16, "CONTAINMENT HYDROGEN ANALYZER STARTUP" JPM Prepared by: Jerry Koske Date: 1/29/09 Page 1 of 6
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: J-6 Rev 0 JPM
Title:
Operate the Containment Hydrogen Analyzer Operators Name: _____________________ Employee # ______________
All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):
SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________
Reason, if unsatisfactory:
Tools & Equipment: None Safety Considerations: None Comments:
Page 2 of 6
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: J-6 Rev 0 JPM
Title:
Operate the Containment Hydrogen Analyzer INITIATING CUE: A LOCA has occurred and an analysis for hydrogen concentration is required. You are directed to place the Hydrogen analyzers in service per the EOP/AOP Attachments and sample the upper level of containment via HCV-820C and HCV-883C.
Critical Steps shown in gray STEP ELEMENT STANDARD 1 Open HCV-820C. AI-65A/B Control switch to OPEN.
RED light ON.
[ SAT ] [ UNSAT ]
2 Open HCV-883C. AI-65A/B Control switch to OPEN.
RED light ON.
[ SAT ] [ UNSAT ]
3 Place all of the following AI-43A/B switches in Override: Control switches to ORIDE.
HCV-820A/821A. RED lights ON.
HCV-883A/884A.
HCV-820B/821B.
HCV-883B/884B. [ SAT ] [ UNSAT ]
4 Place recorders, HR-81A/B in AI-65A/B service. Turn recorders on.
[ SAT ] [ UNSAT ]
Page 3 of 6
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: J-6 Rev 0 JPM
Title:
Operate the Containment Hydrogen Analyzer STEP ELEMENT STANDARD 5 Ensure Range Selector AI-65A/B switches are in 0-10%. Selector switch in 0-10%
position.
[ SAT ] [ UNSAT ]
6 Place the Hydrogen Analyzer AI-65A/B Power On Selector Switches to Switches to ANALYZE ANALYZE. position.
[ SAT ] [ UNSAT ]
7 Ensure the Function Selector AI-65A/B Switches are in SAMPLE. Switches in SAMPLE position.
[ SAT ] [ UNSAT ]
8 Press REMOTE selector AI-65A/B pushbuttons. Depress pushbuttons.
[ SAT ] [ UNSAT ]
9 Verify the following: AI-65A/B Containment H2 Alarm Window ON.
Sampling System Remote/Local Off Normal Annunciator in Alarm.
0-10% Range Amber AMBER light ON.
indicating light is ON.
The Sample Indicating Light is ON.
light is ON.
[ SAT ] [ UNSAT ]
Page 4 of 6
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: J-6 Rev 0 JPM
Title:
Operate the Containment Hydrogen Analyzer STEP ELEMENT STANDARD 10 Press Alarm Reset Push AI-65A/B buttons. Depress push buttons.
[ SAT ] [ UNSAT ]
CUE: 5 minutes have elapsed 11 Obtain hydrogen concentration AI-65A/B reading.
Report reading from meters.
[ SAT ] [ UNSAT ]
Termination Criteria: Containment hydrogen concentration has been determined Page 5 of 6
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: J-6 Rev 0 INITIATING CUE: A LOCA has occurred and an analysis for hydrogen concentration is required. You are directed to place the Hydrogen analyzers in service per the EOP/AOP Attachments and sample the upper level of containment via HCV-820C and HCV-883C.
Page 6 of 6
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: J-7 Rev 0 JPM
Title:
4160V Buses 1A3 and 1A4 from 345KV to 161 KV Location: Simulator Approximate Time: 8 minutes Actual Time: _________________
Reference(s): K/A 000062 A4.01 AOP-31,Section II, "ALL 4160 V BUSES FED FROM 22 KV."
OI-EE-1, Attachment 1, "FEED VITAL/NON-VITAL BUSES FROM 161 KV."
JPM Prepared by: Jerry Koske Date: 02/03/09 Page 1 of 7
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: J-7 Rev 0 JPM
Title:
4160V Buses 1A3 and 1A4 from 345KV to 161 KV Operators Name: _____________________ Employee # ______________
All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):
SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________
Reason, if unsatisfactory:
Tools & Equipment: None Safety Considerations: None Comments:
Page 2 of 7
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: J-7 Rev 0 JPM
Title:
4160V Buses 1A3 and 1A4 from 345KV to 161 KV INITIATING CUE: A loss of 161 KV has occurred due to a grid problem.
Busses 1A3 and 1A4 transferred to 345 KV. AOP-31, section II has been entered and appropriate actions taken The 161 KV grid problem has been fixed and 161 KV is available.
You are directed to restore normal power to busses 1A3 and 1A4 beginning with AOP-31, section II, step 10.
Critical Steps shown in gray STEP ELEMENT STANDARD 1 Ensure Lockout Relay 86/161 AI-22 is reset. 86 Relay RESET.
[ SAT ] [ UNSAT ]
2 Ensure all of the following AI-24, AI-25, AI-46 Lockout Relays are reset: Relays RESET.
86-1/T1A-4.
86-2/T1A-4.
86-1/T1A-3.
86-2/T1A-3.
86X/FT161. [ SAT ] [ UNSAT ]
3 Synchronize and Close at least CB-20 one of the following breakers: Insert Sync switch handle and Breaker 110. turn to ON.
Breaker 111. Breaker switch to AFTER CLOSE.
RED light ON.
[ SAT ] [ UNSAT ]
4 Enter OI-EE-1, Attachment 1. CUE: Provide copy of OI-EE-1, Attachment 1 Page 3 of 7
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: J-7 Rev 0 JPM
Title:
4160V Buses 1A3 and 1A4 from 345KV to 161 KV STEP ELEMENT STANDARD 5 Ensure both fast Transfer CB-20 switches in manual: Both switches in MANUAL.
43/1A1-1A3.
43/1A2-1A4. [ SAT ] [ UNSAT ]
6 Turn 1A33 Synchroscope ON. CB-20 Insert Sync switch handle and turn to ON.
[ SAT ] [ UNSAT ]
7 Verify incoming and running CB-20 voltages are matched. Verify voltages within 25 volts.
[ SAT ] [ UNSAT ]
8 Verify Synchroscope at 12 CB-20 o,clock. Indicator at 12 o,clock.
[ SAT ] [ UNSAT ]
9 Close Breaker 1A33. CB-20 Breaker 1A33 in AFTER CLOSE, RED light ON.
[ SAT ] [ UNSAT ]
10 Open Breaker 1A13 CB-20 Breaker 1A13 in AFTER TRIP.
GREEN light ON
[ SAT ] [ UNSAT ]
11 Turn Off Synchroscope. CB-20 Sync switch handle to OFF Verify loads still energized
[ SAT ] [ UNSAT ]
Page 4 of 7
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: J-7 Rev 0 JPM
Title:
4160V Buses 1A3 and 1A4 from 345KV to 161 KV STEP ELEMENT STANDARD 12 Turn 1A44 Synchroscope ON. CB-20 Insert Sync switch handle and turn to ON.
[ SAT ] [ UNSAT ]
13 Verify incoming and running CB-20 voltages are matched. Verify voltages within 25 volts.
[ SAT ] [ UNSAT ]
14 Verify Synchroscope at 12 CB-20 o,clock. Indicator at 12 o,clock.
[ SAT ] [ UNSAT ]
15 Close Breaker 1A44. CB-20 Breaker 1A44 in AFTER CLOSE, RED light ON.
[ SAT ] [ UNSAT ]
16 Open Breaker 1A24. CB-20 Breaker 1A24 in AFTER TRIP.
GREEN light ON.
[ SAT ] [ UNSAT ]
17 Turn Off Synchroscope. CB-20 Sync switch handle to OFF Verify loads still energized.
[ SAT ] [ UNSAT ]
Page 5 of 7
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: J-7 Rev 0 JPM
Title:
4160V Buses 1A3 and 1A4 from 345KV to 161 KV STEP ELEMENT STANDARD 18 Verify conditions for fast CB-20 transfer met:
Lock-out relays amber AMBER lights lights on. ON(vertical panel).
Appropriate 4160V Control Switches not in breakers not in pull-to- PULL-TO-LOCK.
lock. Voltmeters show proper Power is available. voltages.
[ SAT ] [ UNSAT ]
19 Place Fast Transfer switches in CB-20 AUTO Both Switches in AUTO.
43/1A1-1A3.
43/1A2-1A4. [ SAT ] [ UNSAT ]
Termination Criteria: Busses 1A3 and 1A4 powered from 161 KV Page 6 of 7
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: J-7 Rev 0 INITIATING CUE: A loss of 161 KV has occurred due to a grid problem.
Busses 1A3 and 1A4 transferred to 345 KV. AOP-31, section II has been entered and appropriate actions taken The 161 KV grid problem has been fixed and 161 KV is available.
You are directed to restore normal power to busses 1A3 and 1A4 beginning with AOP-31, section II, step 10.
Page 7 of 7
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: J-8 Rev 0 JPM
Title:
RPS Power Adjustment Location: Simulator Approximate Time: 12 minutes Actual Time: _________________
Reference(s): K/A# 012000 A4.02 OP-ST-RPS-0005, JPM Prepared by: Jerry Koske Date: 1/29/09 Page 1 of 9
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: J-8 Rev 0 JPM
Title:
RPS Power Adjustment Operators Name: _____________________ Employee # ______________
All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):
SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________
Reason, if unsatisfactory:
Tools & Equipment: RPS Trip Unit Bypass Keys 1, 9 and 12 Safety Considerations: None Comments:
Page 2 of 9
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: J-8 Rev 0 JPM
Title:
RPS Power Adjustment INITIATING CUE: The plant is operating at full power. XC-105 is valid and indicates the reactor is operating at 1497.5 MWt.
You have been directed to perform OP-ST-RPS-0005, "RPS POWER ADJUSTMENT", AND ADJUST ANY CHANNELS THAT NEED ADJUSTMENT.
The Scaling Amp offsets on the Power Range Safety Drawers have been verified to be correct.
Critical Steps shown in gray STEP ELEMENT STANDARD 1 Record all four (4) Channel T AI-31A/B/C/D Scaling Amp Offsets from the Records Channel T Scaling RPS Scaling Amplifier Offset Amp Offsets for all channels Measurement Record (Control on test data sheet 1.
Room File drawer) on Test Data Sheet 1 and verify the [ SAT ] [ UNSAT ]
Scaling Amp Offset values on the Power Range Safety Drawers.
2 Record all four (4) Channel NI AI-31A/B/C/D Scaling Amp Offsets from the Records Channel NI Scaling RPS Scaling Amplifier Offset Amp Offsets for all channels Measurement Record (Control on test data sheet 1 Room File drawer) on Test Data Sheet 1 and verify the [ SAT ] [ UNSAT ]
Scaling Amp Offset values on the Power Range Safety Drawers.
Page 3 of 9
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: J-8 Rev 0 JPM
Title:
RPS Power Adjustment STEP ELEMENT STANDARD 3 Record all four (4) channels AI-31A/B/C/D Initial T Power readings from Records Initial T Power RPSCIP DVM on Test Data readings for all channels on Sheet 1. test data sheet 1.
[ SAT ] [ UNSAT ]
4 Record all four (4) channels AI-31A/B/C/D Initial NI Power readings from Records Initial NI Power RPSCIP DVM on Test Data readings for all channels on Sheet 1. test data sheet 1.
[ SAT ] [ UNSAT ]
5 Subtract the Scaling Amp AI-31A/B/C/D Offset from Initial T Power Records Initial T Power reading for all four (4) channels readings - scaling amp offset and record on Test Data Sheet for all channels on test data
- 1. sheet 1.
[ SAT ] [ UNSAT ]
6 Subtract the Scaling Amp AI-31A/B/C/D Offset from the Initial NI Power Records Initial NI Power reading for all four (4) channels readings - scaling amp offset and record on Test Data Sheet for all channels on test data
- 1. sheet 1.
[ SAT ] [ UNSAT ]
7 Record all four (4) channels AI-31A/B/C/D Initial T Pwr Calibrate and Records Initial T Pwr Nuclear Pwr Calibrate dial Calibrate and Nuclear Pwr (Power Range Monitor Drawer) Calibrate dial settings for all settings on Test Data Sheet 1. channels on test data sheet 1.
[ SAT ] [ UNSAT ]
Page 4 of 9
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: J-8 Rev 0 JPM
Title:
RPS Power Adjustment STEP ELEMENT STANDARD 8 Determine Channel that need Determines Channel "D" adjustment. differs with XC-105 by more than 1% and must be adjusted.
[ SAT ] [ UNSAT ]
9 Place RPSCIP DVM Meter AI-31D Input Switch to METER INPUT Places DVM Meter Input position. Switch to METER INPUT position.
[ SAT ] [ UNSAT ]
10 Push +10V pushbutton and AI-31D verify DVM reads +9.800 to Pushes +10V pushbutton and
+10.200V. verifies reading.
[ SAT ] [ UNSAT ]
11 Push -10V pushbutton and AI-31D verify DVM reads -9.800 to Pushes -10V pushbutton and
-10.200V. verifies reading.
[ SAT ] [ UNSAT ]
12 Push ZERO pushbutton and AI-31D verify DVM reads -0.200 to Pushes ZERO pushbutton and
+0.200V. verifies reading.
[ SAT ] [ UNSAT ]
13 Enter Technical Specification CUE: Another Operator has Limiting Condition for logged into Technical Operation 2.15, Table 2-2, Speciifications.
Items 2, 3 and 9 for RPS Trip Units 1, 9 and 12. [ SAT ] [ UNSAT ]
Page 5 of 9
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: J-8 Rev 0 JPM
Title:
RPS Power Adjustment STEP ELEMENT STANDARD 14 Bypass trip units 1, 9 and 12. CUE: Provide TU bypass keys to candidate.
AI-31D Inserts Keys in Trip Units 1, 9 and 12 and turns to BYPASS position.
[ SAT ] [ UNSAT ]
15 Place the DVM selector switch AI-31D to NUCLEAR PWR. Selects NUCLEAR PWR on DVM selector switch
[ SAT ] [ UNSAT ]
16 Adjust the Power Range AI-31D Monitor NUCLEAR PWR Adjusts Potentiameter such CALIBRATE potentiometer that DVM reading equals 99.8 until the DVM equals the plus the NI scaling amp offset.
Thermal Power plus the NI Scaling Amp Offset. [ SAT ] [ UNSAT ]
17 Place the DVM selector switch AI-31D to T PWR. Selects T PWR on DVM selector switch
[ SAT ] [ UNSAT ]
18 Adjust T PWR CALIBRATE AI-31D potentiometer until the Adjusts Potentiometer such NUCLEAR PWR-T PWR (%) that zero deviation indicated sigma meter is nulled on sigma meter.
(0 deviation).
[ SAT ] [ UNSAT ]
Page 6 of 9
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: J-8 Rev 0 JPM
Title:
RPS Power Adjustment STEP ELEMENT STANDARD 19 Verify trip units are RESET, AI-31D then remove the Bypass Keys Trip Units 1, 9 and 12 not for Trip Units 1, 9 and 12. bypassed with keys removed.
[ SAT ] [ UNSAT ]
20 Exit Technical Specification CUE: Another Operator has LCO 2.15, for trip units 1, 9 and logged out of the Technical
- 12. Specification.
[ SAT ] [ UNSAT ]
21 Record all four (4) channels AI-31A/B/C/D Final NUCLEAR PWR Record Final NUCLEAR PWR CALIBRATE Dial CALIBRATE Dial settings for settings on Test Data Sheet 1. all four channels.
[ SAT ] [ UNSAT ]
22 Record all four (4) channels AI-31A/B/C/D Final T PWR CALIBRATE Record Final T PWR Dial settings CALIBRATE Dial settings for on Test Data Sheet 1. all four channels.
[ SAT ] [ UNSAT ]
23 Record all four (4) channels AI-31A/B/C/D FINAL T Power readings on Record Final T Power Test Data Sheet 1. readings for all four channels.
[ SAT ] [ UNSAT ]
24 Record all four (4) channels AI-31A/B/C/D FINAL NI Power readings on Record Final T Power Test Data Sheet 1. readings for all four channels.
[ SAT ] [ UNSAT ]
Page 7 of 9
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: J-8 Rev 0 JPM
Title:
RPS Power Adjustment Termination Criteria: RPS channel 'D" NI Power and T Power have been adjusted to agree with XC-105 per OP-ST-RPS-0005.
Page 8 of 9
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: J-8 Rev 0 INITIATING CUE: The plant is operating at full power. XC-105 is valid and indicates the reactor is operating at 1497.5 MWt.
You have been directed to perform OP-ST-RPS-0005, "RPS POWER ADJUSTMENT", AND ADJUST ANY CHANNELS THAT NEED ADJUSTMENT.
The Scaling Amp offsets on the Power Range Safety Drawers have been verified to be correct.
Page 9 of 9
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-9 Rev 0 JPM
Title:
Provide Raw Water backup cooling to Containment Coolers Location: Auxiliary Building Room 68 (RCA)
Approximate Time: 15 minutes Actual Time: _________________
Reference(s): K/A 022000 A2.05 AOP-11, "LOSS OF COMPONENT COOLING WATER" OI-AOV-1, "AIR OPERATED VALVE MANUAL OPERATION" JPM Prepared by: Jerry Koske Date: 1/29/09 Page 1 of 6
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-9 Rev 0 JPM
Title:
Provide Raw Water backup cooling to Containment Coolers Operators Name: _____________________ Employee # ______________
All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):
SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________
Reason, if unsatisfactory:
Tools & Equipment: None Safety Considerations: This JPM requires entry into the RCA Comments:
Page 2 of 6
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-9 Rev 0 JPM
Title:
Provide Raw Water backup cooling to Containment Coolers INITIATING CUE: The reactor has tripped from full power. A total loss of all CCW pumps has occurred. You are directed, by the CRS, to establish Raw water Backup to containment cooling per AOP-11 and OI-AOV-1.
VA-3A and VA-3B are both in operation. VA-7A and VA-7B are NOT in operation.
Critical Steps shown in gray STEP ELEMENT STANDARD 1 Obtain copies of AOP-11 and Cue: Provide copies of AOP-OI-AOV-1. 11 and OI-AOV-1.
[ SAT ] [ UNSAT ]
2 Place CNTMT CLG COIL CUE: Control Room VA-1A AC VLVS CONTROL Operator reports that HCV-SW HCV-400B/D in CLOSE. 400B/D is in CLOSE.
[ SAT ] [ UNSAT ]
3 Unlock and release the Room-69 hand-jacks from BOTH of the Remove the locking following RW Interface mechanisms and covers from Valves: BOTH HCV-400E and HCV-HCV-400E, CNTMTVA- 400F. Use the ratchet to 1A COOLING COIL release the handjacks by RAW WATER INLET turning the locking nut VALVE. CLOCKWISE until it reaches HCV-400F, CNTMTVA- the bottom.
1A COOLING COILBACK-UP RAW WATER OUTLET [ SAT ] [ UNSAT ]
VALVE.
Page 3 of 6
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-9 Rev 0 JPM
Title:
Provide Raw Water backup cooling to Containment Coolers STEP ELEMENT STANDARD 4 Locally open both VA-1A RW Room-69 Interface Valves, HCV-400E/F IA-HCV-400E-TV 4-way by placing the following valves manual control valve in OPEN.
to OPEN:
IA-HCV-400E-TV, 4- IA-HCV-400F-TV 4-way WAY MANUAL manual control valve in OPEN.
CONTROL VALVE.
IA-HCV-400F-TV, 4-WAY MANUAL [ SAT ] [ UNSAT ]
CONTROL VALVE.
5 Place CNTMT CLG COIL CUE: RO reports that HCV-VA-1B AC VLVS CONTROL 401B/D is in CLOSE.
SW HCV-401B/D in CLOSE.
[ SAT ] [ UNSAT ]
6 Unlock and release the Room-69 hand-jacks from BOTH of the Remove the locking following RW Interface Valves: mechanisms and covers from HCV-401E, CNTMTVA- BOTH HCV-401E and HCV-1B COOLING COIL 401F. Use the ratchet to BACK-UP RAW release the handjacks by WATERINLET VALVE. turning the locking nut HCV-401F, CNTMTVA- CLOCKWISE until it reaches 1B COOLING COIL the bottom.
BACK-UP RAW WATER OUTLET VALVE. [ SAT ] [ UNSAT ]
7 Locally open both VA-1B RW Room-69 Interface Valves, HCV-401E/F IA-HCV-401E-TV 4-way by placing the following valves manual control valve in OPEN.
in OPEN:
IA-HCV-401E-TV, 4- IA-HCV-401F-TV 4-way WAY MANUAL manual control valve in OPEN.
CONTROL VALVE.
IA-HCV-401F-TV, 4-WAY MANUAL [ SAT ] [ UNSAT ]
CONTROL VALVE.
Page 4 of 6
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-9 Rev 0 JPM
Title:
Provide Raw Water backup cooling to Containment Coolers Termination Criteria: Raw Water Backup Cooling is being provided to Containment Coolers , VA-1A and VA-1B.
Page 5 of 6
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-9 Rev 0 INITIATING CUE: The reactor has tripped from full power. A total loss of all CCW pumps has occurred. You are directed, by the CRS, to establish Raw water Backup to containment cooling per AOP-11 and OI-AOV-1.
VA-3A and VA-3B are both in operation. VA-7A and VA-7B are NOT in operation.
Page 6 of 6
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-10 Rev 0 JPM
Title:
Energize 480 volt buses from 13.8 KV Location: Switchgear Rooms Approximate Time: 20 miutes Actual Time: _________________
Reference(s): K/A 000055 EA1.07 EOP/AOP Attachment 5 JPM Prepared by: Jerry Koske Date: 1/29/09 Page 1 of 7
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-10 Rev 0 JPM
Title:
Energize 480 volt buses from 13.8 KV Operators Name: _____________________ Employee # ______________
All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):
SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________
Reason, if unsatisfactory:
Tools & Equipment: None Safety Considerations: Be careful not to bump equipment in switchgear rooms Comments:
Page 2 of 7
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-10 Rev 0 JPM
Title:
Energize 480 volt buses from 13.8 KV INITIATING CUE: A station blackout has occurred. Both 161 KV and 345 KV supplies to the station have been lost. Both Diesel Generators have failed to start.
Energy Marketing reports that 13.8 KV power is available to the plant. You have been directed to energize 480 volt buses 1B3C, 1B3C-4C and 1B4C using EOP/AOP attachment 5. The Control Room Operators have completed steps 1 and 2.
Critical Steps shown in gray STEP ELEMENT STANDARD 1 Trip ALL of the following 480 V East Switchgear room breakers : Trip breakers.
1B3C, "T1B-3C MAIN Verify breaker position SECONDARY FEED TO indicators display "OPEN."
480 VAC BUS 1B3C."
1B3C-2, "MCC-3C2 [ SAT ] [ UNSAT ]
AUX BUILDING (CORR.
26)."
1B3C-7, "TURBINE BUILDING CRANE HE-3."
1B3C-6, "CONTAINMENT SPRAY PUMP SI-3A."
1B3C-3, "OUTDOOR LIGHTING XFMR T1C-3B."
1B3C-5, "MCC-3C3 SERVICE BLDG (3RD FLOOR)."
1B3C-8, "AIR COMPRESSORCA-1A FEED TO LOCAL CONTACTOR."
Page 3 of 7
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-10 Rev 0 JPM
Title:
Energize 480 volt buses from 13.8 KV STEP ELEMENT STANDARD 2 Trip ALL of the following 480 V East Switchgear room breakers: Trip breakers.
1B3C-4C-2, "BREAKER Verify breaker position UNIT MCC-3C4C-2 indicators display "OPEN."
TURBINE BLDG (MEZZANINE)." [ SAT ] [ UNSAT ]
1B3C-4C-3, "BREAKER UNIT CONTAINMENT COOLING FAN VA-7C."
1B3C-4C-4, "BREAKER UNIT COMPONENT COOLING WATER PUMP AC-3C."
3 Trip ALL of the following 480 V West Switchgear room breakers : Trip breakers.
1B4C, "T1B-4C MAIN Verify breaker position SECONDARY FEED TO indicators display "OPEN."
480 VAC BUS 1B4C."
"CONTAINMENT COOLING & FILTER FAN VA-3B."
1B4C-3, "MCC-4C2 AUX BLDG (CORR 4)."
1B4C-4, "MCC-4C3 TURB BLDG (MEZZANINE)."
1B4C-7, "MCC-4C4 INTAKE STRUCTURE."
1B4C-5, "HI PRESS SAFETY INJ. PUMP SI-2B."
1B4C-2, "MCC-4C1 ELECT PENET. AREA (RM 57W)."
1B4C-1, "MCC-4C5 MCC TURBINE BUILDING."
Page 4 of 7
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-10 Rev 0 JPM
Title:
Energize 480 volt buses from 13.8 KV STEP ELEMENT STANDARD 4 Place ALL of the following East Upper Electrical breakers in "OFF" Penetration Room MCC-3C1-A01, "PCV-102-1 PZR POWER MCC breakers placed in OFF OPERATED RELIEF position.
VALVE."
MCC-3C1-A2R, "AUX BLDG ROOF-DS, AUX [ SAT ] [ UNSAT ]
BLDG ROOF STRESS TEST DISC SWITCH."
MCC-3C1-A3L, "MPP-58/EE-98 MOTOR PROTECTION PANEL TRANSFORMER."
MCC-3C1-A3R, HE DS/STRESS GALL-DS, ROOM 66 HOIST &
STRESS GALLERY TEST DISC SWITCHES.
MCC-3C1-A4L, "SPARE.
MCC-3C1-A4R, "EE-4Q INVERTER "C" EE-8K BYPASS TRANSFORMER."
MCC-3C1-A05, "TRANSFORMER T1B-3C COOLING FANS."
5 Obtain the circuit breaker CUE: You have obtained the handle from the Shift Manager circuit breaker handle or the AOP-06 Cabinet.
[ SAT ] [ UNSAT ]
Page 5 of 7
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-10 Rev 0 JPM
Title:
Energize 480 volt buses from 13.8 KV STEP ELEMENT STANDARD 6 Close breaker 1B3C-4, East Switchgear room "EMERG. FEED TO BUS 1B3C Close breaker 1B3C-4 and FROM 13.8KV/480V XFMR verify breaker position T1B-3C-1." indicators display CLOSED.
[ SAT ] [ UNSAT ]
7 Check that Bus 1B3C is CUE: Bus 1B3C bus voltage energized. is 480 Volts.
[ SAT ] [ UNSAT ]
8 Close BT-1B3C, "BUS TIE East Switchgear room 1B3C & 1B3C-4C NORMALLY Close breaker BT-1B3C and CLOSED." verify breaker position indicators display CLOSED.
[ SAT ] [ UNSAT ]
9 Close BT-1B4C, "BUS TIE West Switchgear room 1B4C & 1B3C-4C NORMALLY Close breaker BT-1B4C and OPEN." verify breaker position indicators display CLOSED.
[ SAT ] [ UNSAT ]
CUE: Another Operator will place Battery Charger #3 in service and transfer DC control power.
Termination Criteria: 480 volt buses 1B3C, 1B3C-4C and 1B4C are energized from 13.8 KV.
Page 6 of 7
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-10 Rev 0 INITIATING CUE: A station blackout has occurred. Both 161 KV and 345 KV supplies to the station have been lost. Both Diesel Generators have failed to start.
Energy Marketing reports that 13.8 KV power is available to the plant. You have been directed to energize 480 volt buses 1B3C, 1B3C-4C and 1B4C using EOP/AOP attachment 5. The Control Room Operators have completed steps 1 and 2.
Page 7 of 7
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-11 Rev 0 JPM
Title:
Emergency Start of the Diesel Fire Pump Location: Intake Structure Approximate Time: 10 minutes Actual Time: _________________
Reference(s): K/A# 086000 A2.04 OI-FP-1, Attachment 3, "FP-1B, DIESEL FIRE PUMP AND FP-6B DIESEL FIRE PUMP STRANER OPERATION."
JPM Prepared by: Jerry Koske Date: 1/29/09 Page 1 of 6
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-11 Rev 0 JPM
Title:
Emergency Start of the Diesel Fire Pump Operators Name: _____________________ Employee # ______________
All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):
SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________
Reason, if unsatisfactory:
Tools & Equipment: None Safety Considerations: Potential tripping hazards. Do Not operate any controls.
Comments: Alternate Path Page 2 of 6
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-11 Rev 0 JPM
Title:
Emergency Start of the Diesel Fire Pump INITIATING CUE: The electric fire pump is out of service. Transformer deluge has activated due to a fire but the diesel fire pump did not start automatically.
You are directed to perform an emergency manual start of the diesel fire pump.
Critical Steps shown in gray STEP ELEMENT STANDARD Note to Examiner: Provide candidate with a copy of OI-FP-1, Attachment 3.
1 Ensure the following are on: AI-183 AI-183-CB1, Fire Pump FP-1B Batt 1 Switch. Battery 1 is ON.
AI-183-CB2, Fire Pump FP-1B Batt 2 Switch. Battery 2 is ON.
[ SAT ] [ UNSAT ]
2 Place HC/FP-1B-MS control AI-183 switch to Manual 1.
Select Manual #1.
[ SAT ] [ UNSAT ]
3 Press HC/FP-1B-1, Crank 1 AI-183 start button.
Push Crank 1 pushbutton.
[ SAT ] [ UNSAT ]
CUE: Engine did not turn over or start Page 3 of 6
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-11 Rev 0 JPM
Title:
Emergency Start of the Diesel Fire Pump STEP ELEMENT STANDARD 4 Place HC/FP-1B-MS control AI-183 switch to Manual 2.
Select Manual #2.
[ SAT ] [ UNSAT ]
5 Press HC/FP-1B-1, Crank 2 AI-183 start button.
Push Crank 2 pushbutton.
[ SAT ] [ UNSAT ]
CUE: Engine turned over but did not start 6 Open FO-169, Fuel Oil South side of Engine Solenoid Valve.
Turn Knob clockwise to full-in position.
[ SAT ] [ UNSAT ]
7 Open FP-161, Pressure control South side of Engine valve bypass valve.
Cooling water bypass valve to OPEN.
[ SAT ] [ UNSAT ]
Page 4 of 6
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-11 Rev 0 JPM
Title:
Emergency Start of the Diesel Fire Pump STEP ELEMENT STANDARD 8 Engage the starter using either North side of Engine of the two starter contactors.
Raise lever knob on either:
YS/FP-1B-1.
YS/FP-1B-1.
CUE: Engine has started and is running.
Release lever.
[ SAT ] [ UNSAT ]
Termination Criteria: Diesel Fire Pump has been started Page 5 of 6
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-11 Rev 0 INITIATING CUE: The electric fire pump is out of service. Transformer deluge has activated due to a fire but the diesel fire pump did not start automatically.
You are directed to perform an emergency manual start of the diesel fire pump.
Page 6 of 6
Appendix D Operator Actions Form ES-D-1 Facility: Fort Calhoun Scenario No: 2009-1 Revision: 1 Examiners: _________________________ Operators: _________________________
Initial Conditions: 100% Power. FW-54 is out of service. CA-1C is out of service.
Turnover: Transfer Letdown Control Valves from LCV-101-1 to LCV-101-2. After that rotate running EHC Pumps.
Event Malf Event Event No. No. Type* Description 1 N-ATCO Transfer Letdown Flow Control Valves.
(2 min) 2 N-BOPO Rotate EHC Pumps.
(14 min) 3 I-ATCO Power Range NI Channel B fails - Tech Spec Entry.
(20 min) 4 C-BOPO Running Bearing Water Pump, "AC-9A" trips.
(26 min) 5 I-ATCO Hot Leg RTD Fails High - Tech Spec Entry.
(30 min) 6 C-All Loss of Instrument Air.
(40 min) 7 M-All Manual Reactor Trip Required.
(45 min) 8 M-All Steam Generator Safety Valve Fails Open.
(50 min)
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Target Quantitative Attributes (Per Scenario; See Section D.5.d) Actual Attributes
- 1. Total malfunctions (5-8) 5
- 2. Malfunctions after EOP entry (1-2) 1
- 3. Abnormal events (2-4) 2
- 4. Major transients (1-2) 1
- 5. EOPs entered/requiring substantive actions (1-2) 1
- 6. EOP contingencies requiring substantive actions (0-2) 1
- 7. Critical tasks (2-3) 2
Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-1 Revision: 1 Event No.: 1 Page 2 of 10 Event
Description:
Transfer Letdown Flow Control Valves Time Position Applicants Actions or Behavior CRS Direct the ATCO to transfer letdown control valves from LCV-101-1 to LCV-101-2.
ATCO Enter OI-CH-1, Attachment 1, "STARTUP OF CHARGING AND LETDOWN."
ATCO Place HC-101-3, Limiter Bypass Switch, in BYPASS.
ATCO Place HIC-101-1/101-2 Letdown Throttle Valve Controller in MANUAL.
ATCO Close LCV-101-1.
ATCO Select LCV-101-2 on HC-101-2 selector switch ATCO Place PIC-210, Letdown Pressure Controller, in MANUAL.
ATCO Throttle PIC-210 to approximately 10% open.
ATCO Use HIC-101-1/101-2 to initiate letdown flow while adjusting PCV-210 to maintain approximately 300 psig.
ATCO Balance charging and letdown flow.
ATCO Place HC-101-3, Limiter Bypass Switch, in NORMAL.
ATCO Go to OI-RC-8, Attachment 3. and ensure pressurizer level matches programmed level and PIC-210 200-400 psia.
ATCO Adjust bias on HIC-101-1/101-2 until top scale indicates 50%.
ATCO Place HIC-101-1/101-2 transfer switch to BAL, then to AUTO.
ATCO Place PIC-210 to AUTO.
ATCO Make adjustments to HIC-101-1/101-2 as needed.
Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-1 Revision: 1 Event No.: 2 Page 3 of 10 Event
Description:
Rotate EHC Pumps Time Position Applicants Actions or Behavior CRS Direct BOPO to rotate EHC Pumps.
BOPO Enters OI-ST-12, Attachment 7, "NORMAL ROTATION OF ELECTROHYDRAULIC PUMPS."
BOPO Start standby EHC Pump, EHC-3B.
BOPO Ensure EHC system pressure is stable on PI-2101.
BOPO Ensure EHC-3B motor current is approximately 40 to 50 amps.
BOPO Direct EONT to verify local parameters:
PI-5116 pressure approximately equal to PI-2101pressure.
PI-5116 pressure approximately equal to PI-2101pressure.
No bubbles visible in EHC-3B suction strainer.
BOPO Stop EHC pump, EHC-3A. Ensure pump control switch in AFTERSTOP.
BOPO Verify adequate EHC pressure being maintained.
Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-1 Revision: 1 Event No.: 3 Page 4 of 10 Event
Description:
Power Range NI Channel B fails - Tech Spec Entry Time Position Applicants Actions or Behavior ATCO Identify the failure from the Nuclear Instrumentation Inoperable and other alarms. May enter ARP.
ATCO Determine that Power Range NI Channel B Upper Detector has failed.
CRS Enter Technical Specification 2.15.
(RPS channel B trip units 1, 9 and 12 must be placed in bypass within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. Since this is a detector failure, they may remain in bypass for up to 7 days. If detector operability is not restored by the end of the 7 days, the reactor must be placed in hot shutdown within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />).
CRS Notify Manager - FCS, Manager - Operations or Supervisor - Operation of RPS trip unit bypass.
CRS Obtain the keys and direct the ATC operator to place the 1, 2, 9, 10 and 12 trip units on channel B in bypass.
ATCO Bypass trip units 1, 2, 9, 10 and 12 on RPS channel B.
ATCO Enter channel bypass information in control room log.
or BOPO CRS Inform Work Week Manager of NI Channel Failure.
Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-1 Revision: 1 Event No.: 4 Page 5 of 10 Event
Description:
Running Bearing Water Pump, AC-9A trips Time Position Applicants Actions or Behavior BOPO Respond to Cooling water Pressure Low alarm (CB-10,11 A11 B6U).
BOPO Report that AC-9A has tripped.
CRS Direct BOPO to start AC-9B.
BOPO Start AC-9B.
CRS Direct BOPO to verify status of Instrument Air System.
BOPO Ensure that air compressor is operating and instrument air pressure normal or restoring.
Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-1 Revision: 1 Event No.: 5 Page 6 of 10 Event
Description:
Hot Leg RTD Fails High - Tech Spec Entry Time Position Applicants Actions or Behavior ATCO Responds to numerous alarms on CB-4, panel A-20 and CB-1,2,3, panel A4. Reports that trip units 1, 9 and 12 on channel A are tripped.
ATCO/ Reviews ARP.
BOPO ATCO Checks power, pressure and temperature indications and determines that the alarm is caused by failed T-hot channel (A/T122H).
CRS Enters Tech Spec 2.15 :
Because trip units 1, 9 and 12 are already bypassed on RPS channel B.
The 1, 9 and 12 trip units on channel A must be placed in the tripped condition within one hour.
One of the channels must be repaired within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or else the plant must be placed in hot shutdown within the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
With NI channel B trip units bypassed and Delta-T channel A trip units tripped, power must be reduced to less than 70% (no time limit).
CRS Either direct the ATC to use the Channel A Power Trip Test Interlock to place the trip units in the tripped condition by placing the "Test Enable" switch in "ENABLE" and the "Test Select" switch in "CAL MID" or else notify I&C to trip the trip units with one hour.
ATCO If directed, use the channel A PTTI to trip the trip units on channel A by placing the "Test Enable" switch in "ENABLE" and the "Test Select" switch in "CAL MID."
CRS Notifies Plant or Operations Management and the Work Week Manager or I&C of the failure.
Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-1 Revision: 1 Event No.: 6 Page 7 of 10 Event
Description:
Loss of Instrument Air Time Position Applicants Actions or Behavior BOPO Identify and communicate lowering air pressure.
CRS Direct BOPO to verify STBY compressor operation.
CRS Enter AOP-17, "LOSS OF INSTRUMENT AIR."
CRS Caution BOPO of possible feed reg. Valve failure.
CRS/ Direct EONT to verify compressor and air dryer operations, Direct all BOPO available operators to help locate the leak.
CRS/ Direct EONT to verify PCV-1753 closure when instrument air pressure BOPO drops to less than 80 psig.
CRS/ Direct EONT to verify PCV-1752 opens when instrument air pressure drops BOPO to less than 78 psig.
CRS Direct BOPO to isolate instrument air to containment.
BOPO Close PCV-1849A/B and after verifying air pressure continues to drop, reopen PCV-1849A/B.
ATCO Monitor primary parameters.
CRS Direct manual reactor trip of when air pressure drops to 50 psig.
ATCO Manually trip reactor within 5 minutes of instrument air pressure going below 50 psig.
Direct BOPO to trip all Main Feedwater Pumps.
CRS Trip all Main Feedwater Pumps.
BOPO
Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-1 Revision: 1 Event No.: 7 Page 8 of 10 Event
Description:
Manual Reactor Trip Required Time Position Applicants Actions or Behavior CRS Enters EOP-00. Directs ATCO and BOPO to perform standard post trip actions.
ATCO Perform Standard Post-Trip Actions:
Verify control rod insertion, power lowering, negative startup rate.
Monitors for uncontrolled Cooldown.
BOPO Verify turbine and generator trip.
BOPO Verify electrical status - 4160, D/G, instrument power, 125V DC.
Verify Instrument air status - Reports instrument air pressure is low and continuing to lower.
ATCO Verify CCW and Raw water status.
Verify RCS inventory control.
Verify RCS pressure control - reports RCS pressure.
Verify core heat removal.
BOPO Verify S/G feed - establish auxiliary feedwater flow to the nozzles.
Verify S/G pressure and T-cold - Reports that steam dump and bypass valves are closed.
ATCO Verify containment conditions.
Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-1 Revision: 1 Event No.: 8 Page 9 of 10 Event
Description:
Steam Generator Safety Valve Fails Open Time Position Applicants Actions or Behavior ATCO Reports RCS cooldown in progress.
BOPO Reports S/G pressure is lowering.
CRS Directs ATCO to perform emergency boration.
ATCO Performs Emergency Boration:
Ensure FCV-269X/Y Closed.
Open HCV-268/265/258.
Start Boric Acid Pumps, CH-4A/B.
Start all charging pumps, CH-1A/B/C.
Close LCV-218-2/3 and HCV-257/264.
CRS Perform diagnostic actions and transition to EOP-20, FUNCTIONAL RECOVERY PROCEDURE, due to a loss of instrument air and an excessive heat removal event.
CRS Within EOP-20, go to success path MVA-IA and implement (continue to implement) AOP-17, LOSS OF INSTRUMENT AIR.
Note: Water Plant Operator Reports Instrument air leak in the intake structure.
CRS Direct Water Plant Operator to isolate leak.
CRS Direct BOPO to monitor instrument Air Pressure.
BOPO Reports that Instrument air pressure is now increasing.
CRS Within EOP-20, go to success path HR-3.
CRS Direct ATCO or BOPO to verify PPLS.
ATCO Verify PPLS:
or Ensure emergency boration in progress.
BOPO Ensure acceptable SI flow per EOP/AOP Attachment 3.
Verify 2 HPSI, 2 LPSI and all available charging pumps running.
Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-1 Revision: 1 Event No.: Page 10 of 10 Event
Description:
Steam Generator Safety Valve Fails Open, continued Time Position Applicants Actions or Behavior CRS Identify Affected Steam Generator.
BOPO BOPO Reports that RC-2B is the affected Steam Generator.
BOPO If SGIS actuates, verify MSIVs, MSIV bypass valves, Feed Reg Bypass valves, Feed Reg block valves and Feed Header Isolation Valves have closed.
CRS Direct BOPO to isolate Steam Generator, RC-2B.
BOPO Isolate S/G RC-2B by closing or ensuring closed:
MSIV, HCV-1042A.
MSIV Bypass, HCV-1042C.
Air assisted S.G Safety Valve, MS-292.
Feed Reg Valve, FCV-1102 (may need to reset due to low instrument air pressure).
Feed Reg Bypass valve, HCV-1106.
Feed Header Isolation Valve, HCV-1385.
Feed Reg Block valve, HCV-1104.
Blowdown Isolation Valves, HCV-1387A/B.
AFW Isolation valves, HCV-1108A/B.
Direct EONT to close Packing leakoff line isolation valve, MS-298.
Override and close steam to AFW pump-FW-10, YCV-1045B.
BOPO Establish Steam Flow from RC-2A prior to Wide Range Level on Steam Generator RC-2B falling to 27% by one of the following:
Opening Air assisted safety valve, MS-291. (OR)
Ensure MSIV, HCV-1041A or MSIV Bypass,HCV-1041C is open and use steam dump and bypass valves. (OR)
Ensure MSIV, HCV-1041A or MSIV Bypass,HCV-1041C is open and open atmospheric dump valve, HCV-1040.
BOPO Ensure Auxiliary Feedwater is being supplied to S/G, RC-2A.
Scenario ends with S/G RC-2B isolated and heat removal established using S/G RC-2A.
Appendix D Operator Actions Form ES-D-2 Appendix D Operator Actions Form ES-D-2 Facility: Fort Calhoun Scenario No: 2009-2 Revision: 1 Examiners: _________________________ Operators: _________________________
Initial Conditions: 100% Power DG-1 Out of Service, Generator Voltage Control On Backup for maintenance.
Turnover: Reestablish normal main generator voltage control then rotate Containment Cooling Units.
Event Malf Event Event No. No. Type* Description 1 N-BOPO Reestablish normal main generator voltage control.
(2 min) 2 N-ATCO Rotate Containment Cooling Units.
(10 min) 3 C-ATCO Dropped CEA - Tech Spec Entry.
(16 min) C-BOPO 4 R-ATCO AOP-05 shutdown to 70% Power.
N-BOPO 5 I-ATCO Controlling Pressurizer Pressure Transmitter, PT-103Y, Fails (28 min) High.
6 C-BOPO Loss of 161 KV - Tech Spec Entry.
(35 min) 7 C-ATCO Another Dropped CEA - Manual Reactor Trip Required.
(48 min) M-ALL 8 C-BOPO Circulating Water Pump, CW-1C, Breaker fails to open M-ALL preventing DG from loading onto bus 1A4 - Station Blackout.
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Target Quantitative Attributes (Per Scenario; See Section D.5.d) Actual Attributes
- 1. Total malfunctions (5-8) 5
- 2. Malfunctions after EOP entry (1-2) 1
- 3. Abnormal events (2-4) 3
- 4. Major transients (1-2) 2
- 5. EOPs entered/requiring substantive actions (1-2) 1
- 6. EOP contingencies requiring substantive actions (0-2) 1
- 7. Critical tasks (2-3) 2
Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-2 Revision: 1 Event No.: 1 Page 2 of 10 Event
Description:
Reestablish normal main generator voltage control.
Time Position Applicants Actions or Behavior CRS Direct the BOPO to return Main Generator Voltage control to AUTO.
BOPO Check the Transfer Voltage Meter (TVM) indication.
BOPO Operate the AC Voltage Control (90P) until the indication on the TVM is "nulled."
BOPO Place the voltage regulator transfer switch in AUTO.
BOPO Monitor the TVM and generator field voltage.
Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-2 Revision: 1 Event No.: 2 Page 3 of 10 Event
Description:
Rotate Containment Cooling Units.
Time Position Applicants Actions or Behavior CRS Direct ATCO to place VA-3B in service and shutdown VA-3A.
ATCO Obtain a copy of OI-VA-1, Attachment 1.
ATCO Momentarily place HCV-401B/D to OPEN.
ATCO Ensure HCV-401C is closed.
ATCO Momentarily place HCV-401A/C to CIRC.
ATCO Throttle open HCV-401C maintaining CCW discharge header pressure at least 70 psig.
ATCO Monitor:
FI-417, VA-1B flow.
TIC-421, VA-1B temperature.
PI-499, CCW Discharge Header Pressure.
TIC-2800, CCW Discharge header temperature.
TI-717 Fan VA-3B outlet temperature.
ATCO Start VA-3B and monitor:
VA-3B Current.
PIC-701, Fan VA-3B filter DP.
PIC-709, Fan VA-3B Cooling Coil DP.
TI-717 Fan VA-3B outlet temperature.
ATCO Stop VA-3A.
ATCO Close HCV-400C maintaining CCW discharge header pressure less than 125 psig.
ATCO Verify CC WATER FROM VA-1A NO FLOW (CB-1,2,3,A1,A1-U) in alarm.
ATCO Momentarily place HCV-400A/C to ISOL.
ATCO Momentarily place HCV-400B/D to CLOSE.
Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-2 Revision: 1 Event No.: 3 Page 4 of 10 Event
Description:
Dropped CEA - Tech Spec Entry.
Time Position Applicants Actions or Behavior ATCO Identify event from Dropped Rod and other alarms (CB-4 A20 E6, CB-4 A8 A5L, B1U, B1L, B2L, B5L, C1U, C2U, C5L).
ATCO Determine that only one rod has dropped (rod #1, grp 4).
CRS Enter AOP-02 (CEDM Malfunction).
CRS Direct BOP Operator to adjust turbine load to match reactor power.
BOPO Reduce turbine load to match reactor power using T-cold indication.
CRS Direct ATC to control pressurizer pressure and level.
ATCO Monitor pressurizer pressure and level.
CRS Direct ATC Operator to reset rod drop bistables.
ATCO Reset rod drop bistables.
CRS Notify Work Week Manager or Reactor Engineer.
CRS Enter Tech Spec Section 2.10.2.
Reactor power must be reduced to less than 70% within one hour. The CEA must be realigned or declared inoperable within one hour following the power reduction. If the CEA is declared inoperable, the reactor must be in hot shutdown within an additional 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.
CRS Inform ATC and BOP operators that Tech Specs require a power reduction to less than 70% within one hour.
CRS Notify energy marketing of the impending power reduction.
Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-2 Revision: 1 Event No.: 4 Page 5 of 10 Event
Description:
AOP-05 shutdown to 70% Power.
Time Position Applicants Actions or Behavior CRS Direct ATCO and BOPO to commence a power reduction using AOP-05 or OP-4.
CRS Direct ATCO on method of boration to use. Options are:
Normal boration.
Aligning charging pumps suction to SIRWT.
ATCO Begin boration using method directed by CRS.
BOPO Reduce turbine load using potentiometer as needed to control RCS T-cold.
ATCO Monitor and control RCS parameters during power reduction.
BOPO Monitor and control secondary parameters.
CRS Direct the shift chemist to sample the RCS due to the power reduction.
ATCO May contact the Aux Building Operator to verify sufficient tank capacity for power reduction.
Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-2 Revision: 1 Event No.: 5 Page 6 of 10 Event
Description:
Controlling Pressurizer Pressure Transmitter, PT-103Y, Fails High.
Time Position Applicants Actions or Behavior ATCO Respond to Pressurizer Pressure Off-Normal HI/LO Channel Y Alarm.
ATCO Identify and report high indication on controlling channel and lowering pressure on other channel.
ATCO/ Refer to ARP.
BOPO CRS Direct ATCO to transfer pressurizer pressure control to channel X or take manual control of pressurizer pressure.
ATCO Transfer pressurizer pressure control to channel X or take manual control of pressurizer pressure, as directed.
ATCO Monitor and control pressurizer pressure.
Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-2 Revision: 1 Event No.: 6 Page 7 of 10 Event
Description:
Loss of 161 KV - Tech Spec Entry.
Time Position Applicants Actions or Behavior BOPO Identify loss of 161 KV from numerous alarms on CB-20. (CB-20 A15 A1, A2, A3) (CB-20 A17 A2, C4, D2) Determine and report that busses 1A3 and 1A4 have fast transferred and are powered.
CRS Enter AOP-31, section II All 4160 busses fed from 22 KV Direct BOPO to verify 1 FW pump, 1 Condensate pump and 1Heater drain pump operating.
BOPO Verify 1 FW pump, 1 Condensate pump and 1, Heater drain pump operating.
CRS Direct BOPO to verify 480 bus voltages greater than 430 volts.
BOPO Verify voltages.
CRS Direct BOPO to match flags on breakers 110, 111, 1A31, 1A33, 1A42, 1A44.
BOPO Match flags on breakers 110, 111, 1A31, 1A33, 1A42, 1A44 (step 5 of AOP-31).
CRS Direct that signs be placed at entrances to switchgear rooms Review EOP-02, EOP-07 and EOP-20.
CRS Enter Tech Spec 2.7.
Due to the loss of 161 KV and D/G-1 being inoperable, Tech Spec 2.0.1 must be entered which requires that the plant be placed in hot shutdown within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. However, taking the main generator off-line will result a loss of offsite power.
The NRC Operations center must be notified within four hours due to the loss of 161 KV.
CRS Report situation to station management.
Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-2 Revision: 1 Event No.: 7 Page 8 of 10 Event
Description:
Another Dropped CEA - Manual Reactor Trip Required.
Time Position Applicants Actions or Behavior ATCO Report that another CEA has fallen into the core.
CRS Direct ATCO to trip the reactor.
ATCO Manually trip the reactor.
CRS Direct the ATCO and BOPO to perform EOP-00, "STANDARD POST-TRIP ACTIONS."
Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-2 Revision: 1 Event No.: 8 Page 9 of 10 Event
Description:
Circulating Water Pump, CW-1C, Breaker fails to open preventing DG from loading onto bus 1A4 - Station Blackout.
Time Position Applicants Actions or Behavior ATCO Perform Standard Post-Trip Actions:
Verify control rod insertion, power lowering, negative startup rate.
BOPO Verify turbine and generator trip.
BOPO Verify electrical status - 4160, D/G, instrument power, 125V DC.
Report that all 4160V busses are deenergized. D/G #2 is running at 900 RPM but its breaker has not closed.
Verify Instrument air status.
ATCO Verify CCW and Raw water status.
Verify RCS inventory control.
Verify RCS pressure control.
Verify core heat removal - Report no reactor coolant pumps running.
BOPO Verify S/G feed - initiate auxiliary feedwater flow.
Verify S/G pressure and T-cold - report steam dump and bypass valves not operating.
Verify containment conditions.
BOPO Report that CW-1C breaker failed to trip within 15 minutes of reactor trip.
(This prevents D/G-2 breaker from closing) Direct EONT to manually trip the breaker for CW-1C.
(NOTE: EONT will trip breaker 2.5 minutes after being directed).
CRS If bus 1A4 is repowered, then enter EOP-02.
If bus 1A4 is not powered, then enter EOP-07.
CRS When D/G-2 output breaker closes, Direct BOPO to verify bus 1A4 voltage.
Continued on next page
Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-2 Revision: 1 Event No.: Page 10 of 10 Event
Description:
Circulating Water Pump, CW-1C, Breaker fails to open preventing DG from loading onto bus 1A4 - Station Blackout, continued.
Time Position Applicants Actions or Behavior CRS Direct ATCO and BOPO to ensure the following:
One CCW Pump running.
One Raw Water Pump running.
One Bearing Water Pump running.
One Air Compressor running.
One Charging Pump running.
One AFW pump running.
ATCO Start:
One CCW Pump.
One Raw Water Pump.
One Charging Pump.
BOPO Start:
One Bearing Water Pump.
One Air Compressor.
One AFW pump.
CRS May direct EONT to supply air compressor cooling with potable water.
ATCO Monitor for establishment of natural circulation:
Delta-T less than 50°F.
Difference between CETs and T-hot less than 10°F.
T-hot and T-cold stable or lowering.
At least 20°F subcooling.
ATCO Monitor and control pressurizer level and pressure.
BOPO Monitor and control S/G steam flow and AFW flow.
Scenario ends with Diesel Generator #2 supplying bus 1A4 and all Safety Functions Satisfied.
Appendix D Operator Actions Form ES-D-2 Facility: Fort Calhoun Scenario No: 2009-3 Revision: 1 Examiners: _________________________ Operators: _________________________
Initial Conditions: Plant at 50% Power FW-4A and FW-4C are OOS. Two CW Pumps are running. Low pressure alarm is in on Safety Injection Tank, SI-6B.
Turnover: Increase pressure in Safety Injection Tank, SI-6B. Then start Circulating Water Pump, CW-1C.
Event Malf Event Event No. No. Type* Description 1 N-ATCO Raise Pressure in Safety Injection Tank, SI-6B.
(2 min) 2 N-BOPO Start Circulating Water Pump, CW-1C.
(10 min) 3 C-ATCO Control Room HVAC Fan Trips - Tech Spec Entry.
(16 min) TS-CRS 4 I-BOPO Steam header pressure transmitter, PT-910 Fails High.
(25 min) 5 TS-CRS Volume Control Tank Level Instrument Fails Low - Tech Spec (31 min) Entry.
6 I-ATCO Controlling Pressurizer Level Channel Fails Low.
(40 min) 7 C - BOPO Turbine high vibration.
(46 min) 8 M-ALL Turbine Trip, Reactor Fails to Trip - ATWS.
(55 min)
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Target Quantitative Attributes (Per Scenario; See Section D.5.d) Actual Attributes
- 1. Total malfunctions (5-8) 6
- 2. Malfunctions after EOP entry (1-2) 1
- 3. Abnormal events (2-4) 3
- 4. Major transients (1-2) 1
- 5. EOPs entered/requiring substantive actions (1-2) 1
- 6. EOP contingencies requiring substantive actions (0-2) 1
- 7. Critical tasks (2-3) 2
Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-3 Revision: 1 Event No.: 1 Page 2 of 10 Event
Description:
Raise Pressure in Safety Injection Tank, SI-6B.
Time Position Applicants Actions or Behavior CRS Direct ATCO to increase pressure in SI-6B to clear alarm.
ATCO Obtain a copy of OI-SI-1, Attachment 27.
ATCO Open HCV-2603A and HCV-2603B.
or BOPO ATCO Open HC-2631.
ATCO Monitor pressure in Safety Injection Tank, SI-6B.
ATCO When pressure is restored, close HC-2631.
ATCO Close HCV-2603A and HCV-2603B.
or BOPO
Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-3 Revision: 1 Event No.: 2 Page 3 of 10 Event
Description:
Start Circulating Water Pump, CW-1C.
Time Position Applicants Actions or Behavior CRS Direct BOPO to start Circulating Water Pump, CW-1C.
BOPO Obtain a copy of OI-CW-1, Attachment 2.
BOPO Direct Water Plant to ensure CW-1C Pump Suction Sluice gate, CW-15C is open.
BOPO Contact Security to be present at Screen F Enclosure.
BOPO Direct Water Plant Operator to ensure Screen Inlet Sluice gates CW-14E and CW-14F are open.
BOPO Direct Water Plant Operator to:
Verify CW Pumps seal water pressure is at least 10 psig.
Verify SW-223/224 are open and SW-225 throttled and seal water has been in service for at least 15 minutes.
Ensure VD-249 is open.
Open VD-266.
Verify oil in all CW-1C bearings.
Ensure CW-1C Cooling Air Damper to upper bearings is open.
BOPO Start CW-1C.
BOPO When CW-1C's Discharge Check Valve starts to open, then open CW-1C's Pump Discharge Valve.
BOPO Verify CW Discharge pressure on PI-1910A/B/C (17-21 psig).
BOPO Notify security they are no longer required at screen F enclosure.
BOPO Monitor upper bearing temperature on ERF computer.
Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-3 Revision: 1 Event No.: 3 Page 4 of 10 Event
Description:
Control Room HVAC Fan Trips - Tech Spec Entry.
Time Position Applicants Actions or Behavior ATCO Respond to "CONTROL ROOM A/C VA-46A AUTO TRIP" alarm on AI-106A.
ATCO Check for Fire Detection alarm or toxic gas alarm. Neither is present.
ATCO Direct EONT to check VA-46A breaker for trip.
ATCO Obtain a copy of OI-VA-3 to start VA-46B.
ATCO Direct maintenance to verify:
Power has been applied to VA-46B at least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Compressor isolation Valves are open.
ATCO Ensure:
Both Filter Fan Control Switches are in the same position.
Third stage cooling VIAS override switch in NORMAL.
Refrigeration suction pressure less than 75% of liquid line pressure.
ATCO Start VA-46B.
ATCO Verify the following are open:
PCV-841B.
PCV-841A-1.
PCV-841A-2.
HCV-2899A.
HCV-2899B.
CRS Enter Technical Specification 2.12.
Log into a 30 day LCO. The inoperable train of control room HVAC must be restored to operable status within 30 days. If still inoperable after 30 days then place the plant in hot shutdown within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and cold shutdown within the following 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-3 Revision: 1 Event No.: 4 Page 5 of 10 Event
Description:
Steam header pressure transmitter, PT-910 Fails High.
Time Position Applicants Actions or Behavior BOPO Identify rapid decrease in RCS T-cold (VOPT ANN will alarm if uncorrected).
ATCO/ If VOPT annunciator alarms, refer to ARP.
BOPO BOPO Determine cause as turbine bypass valve, PCV-910, being open (red light on CB-1,2,3).
CRS Direct BOP to take manual control of PCV-910 and close it.
BOPO Monitor RCS T-cold.
ATCO Monitor and control RCS parameters.
CRS Notify Work Week Manager or I&C of the failure of PT-910.
Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-3 Revision: 1 Event No.: 5 Page 6 of 10 Event
Description:
Volume Control Tank Level Instrument, LT-219, Fails Low - Tech Spec Entry Time Position Applicants Actions or Behavior ATCO Respond to alarm.
ATCO Report VCT Level Transmitter, LT-219 has failed low.
ATCO Check that LCV-218-1 VCT inlet valve is aligned to the VCT.
ATCO Verify Pressurizer Level.
CRS Enter Technical Specification 2.15.
Enter a 7 day LCO because LI-219 on AI-185 is inoperable and there are no operable VCT channels on Alternate Shutdown Panel AI-185. This is a 7 day LCO or else be in hot shutdown within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
CRS Report Instrument Failure to the Work Week Manager.
Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-3 Revision: 1 Event No.: 6 Page 7 of 10 Event
Description:
Controlling Pressurizer Level Channel Fails Low.
Time Position Applicants Actions or Behavior ATCO Respond to PZR Pressure Off Normal Hi-Lo Channel Y alarm on CB-1,2,3 A4.
ATCO Refer to ARP.
or BOPO ATCO Identify deviation between pressurizer pressure channels.
CRS Direct PRI to swap controlling channels or to take manual control of pressurizer pressure.
ATCO Switch controlling channel to channel 103X or take manual control of pressurizer pressure.
ATCO Monitor and maintain proper pressurizer pressure.
Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-3 Revision: 1 Event No.: 7 Page 8 of 10 Event
Description:
Turbine high vibration.
Time Position Applicants Actions or Behavior ATCO Respond to plant computer alarm for high turbine vibration.
or BOPO BOPO Report recorder indication of rising vibration on bearing #6, 7 mills and rising.
BOPO Report vibration greater than 8 mills.
CRS Direct power reduction.
BOPO Reduce turbine load.
ATCO Control reactivity during load reduction.
BOPO Report turbine vibration rising.
CRS May direct ATCO to trip the reactor.
ATCO Trip Reactor, if directed.
Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-3 Revision: 1 Event No.: 8 Page 9 of 10 Event
Description:
Turbine Trip, Reactor Fails to Trip - ATWS.
Time Position Applicants Actions or Behavior ATCO Report that Reactor did not trip.
ATCO Manually trip the reactor at:
and CB-4.
BOPO AI-31.
AI-66A/B.
Open breakers at AI-57.
Within 60 seconds after determining reactor did not trip.
CRS Enter EOP-00 and direct ATCO and BOPO to perform Standard Post Trip Actions.
ATCO Report that two CEAs have not inserted.
CRS Direct Emergency Boration.
ATCO Performs Emergency Boration:
Ensure FCV-269X/Y Closed.
Open HCV-268/265/258.
Start Boric Acid Pumps, CH-4A/B.
Start all charging pumps, CH-1A/B/C.
Close LCV-218-2/3 and HCV-257/264.
Complete steps within 3 minutes of determining two CEAs have not inserted.
ATCO Perform Standard Post-Trip Actions:
Verify control rod insertion, power lowering, negative startup rate.
Monitors for uncontrolled Cooldown.
BOPO Verify turbine and generator trip.
BOPO Verify electrical status - 4160, D/G, instrument power, 125V DC.
Verify Instrument air status.
Continued on next page
Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-3 Revision: 1 Event No.: 8, cont. Page 10 of 10 Event
Description:
Turbine Trip, Reactor Fails to Trip - ATWS, continued Time Position Applicants Actions or Behavior ATCO Verify CCW and Raw water status.
Verify RCS inventory control.
Verify RCS pressure control - reports RCS pressure.
Verify core heat removal.
BOPO Verify S/G feed .
Verify S/G pressure and T-cold.
ATCO Verify containment conditions.
Scenario ends with Standard Post Trip Actions completed and Emergency Boration in progress.
Appendix D Operator Actions Form ES-D-2 Facility: Fort Calhoun Scenario No: 2009-4 Revision: 1 Examiners: _________________________ Operators: _________________________
Initial Conditions: 50% Power, FW-54 Out of Service, FW-4A and FW-4C Out of Service.
Turnover: Maintain 50% operation.
Event Malf Event Event No. No. Type* Description 1 N-ATCO Rotate CCW Pumps.
(2 min) 2 N-BOPO Rotate Auxiliary Building Supply Fans.
(10 min) 3 I-ATCO Pressurizer Pressure Safety Channel fails Low - Tech Spec (17 min) TS-CRS Entry.
4 I - ATCO Letdown Temperature Transmitter, TT-2897 fails low.
(25 min) 5 C - ATCO RCP Seal Cooler Leak - Tech Spec Entry.
(34 min) TS-CRS 6 C - BOPO Feedwater Pump Trips, Reactor Trip.
(45 min) M-ALL 7 C-BOPO Blowdown fails to isolate automatically.
8 C-BOPO Pipe from EFWST to FW-6 and FW-10 breaks. Total Loss of (52 min) M - ALL Feedwater.
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Target Quantitative Attributes (Per Scenario; See Section D.5.d) Actual Attributes
- 1. Total malfunctions (5-8) 6
- 2. Malfunctions after EOP entry (1-2) 2
- 3. Abnormal events (2-4) 2
- 4. Major transients (1-2) 1
- 5. EOPs entered/requiring substantive actions (1-2) 2
- 6. EOP contingencies requiring substantive actions (0-2) 1
- 7. Critical tasks (2-3) 2
Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-4 Revision: 1 Event No.: 1 Page 2 of 9 Event
Description:
Rotate CCW Pumps.
Time Position Applicants Actions or Behavior CRS Directs ATCO to switch operating CCW pump from Pump AC-3A to Pump AC-3C.
ATCO Obtains and reviews Procedure OI-CC-1, Attachment 2.
ATCO Directs EONT to Room 69.
ATCO Starts pump AC-3C and directs closure of Valve AC-102 (Pump AC-3A discharge valve).
ATCO Stops pump AC-3A and takes hand switch to pull-to-lock.
ATCO Ensures proper operation of pump AC-3C. Directs EONT to reopen Valve AC-102.
Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-4 Revision: 1 Event No.: 2 Page 3 of 9 Event
Description:
Rotate Auxiliary Building Supply Fans Time Position Applicants Actions or Behavior CRS Direct BOPO to rotate AB Controlled area supply fans. Start VA-35B and shutdown VA-35A.
BOPO Obtain a copy of OI-VA-2 Attachment 1C.
BOPO Place HC-828A, Supply Fan VA-35B Mode Selector Switch to MANUAL.
BOPO Place HC-827A, Supply Fan VA-35A Mode Selector Switch to MANUAL.
BOPO Using HC-827B raise/lower pushbuttons, lower VA-35A fan speed to 0%.
(Note: this step and the next step can be performed simultaneously.)
BOPO Using HC-828B raise/lower pushbuttons, raise VA-35B fan speed until building pressure matches setpoint.
BOPO Place HC-828A to AUTO.
BOPO Verify the building pressure stabilizes at a nominal -0.2 inches of water or desired setpoint.
Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-4 Revision: 1 Event No.: 3 Page 4 of 9 Event
Description:
Pressurizer Pressure Safety Channel fails Low - Tech Spec Entry Time Position Applicants Actions or Behavior ATCO Respond to "PRESSURIZER SAFETY INJ SIGNAL LO-LO PRESSURE C/P102Y" alarm.
ATCO Refer to ARP.
or BOPO ATCO Check redundant channels and report instrument failure.
CRS Enter Technical Specification 2.15.
The Thermal Margin/ Low Pressure channel must be bypassed within one hour. The channel may be bypassed for up to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, after that it must be placed in the tripped position.
CRS Direct the ATCO to bypass channel "C" TM/LP trip unit.
ATCO Place channel "C" TM/LP trip unit in bypass.
Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-4 Revision: 1 Event No.: 4 Page 5 of 9 Event
Description:
Temperature Transmitter, TT-2897 fails low.
Time Position Applicants Actions or Behavior ATCO Respond to Letdown Heat Exchanger Tube Outlet Temp HI Alarm.
ATCO Determine that TCV-211-2 has repositioned to bypass demineralizers.
ATCO Determine high temperature due to reduced CCW flow to letdown heat exchanger following closure of TCV-2897.
CRS Direct ATCO to manually control CCW flow to letdown HX using TCV-2897.
ATCO Manually control TCV-2897to restore letdown temperature.
SRO May direct ATCO to reposition TCV-211-2 and maintain 100°F - 120°F.
ATCO Reposition TCV-211-2 if directed.
ATCO Monitor primary parameters.
BOPO Monitor secondary parameters.
Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-4 Revision: 1 Event No.: 5 Page 6 of 9 Event
Description:
RCP Seal Cooler Leak - Tech Spec Entry.
Time Position Applicants Actions or Behavior ATCO Respond to Water from Seal Cooler RC-3B Seal Cooler Temperature High alarm.
ATCO Identify and communicate lowering pressurizer level and pressure and lowering letdown flow.
ATCO Report RM-053 (CCW HI RAD) in alarm. Report CCW surge tank level and pressure rising.
ATCO Enter ARP. Check CCW temperature from RC-3B seal cooler. Adjust CCW flow as needed.
CRS Enter AOP-22. Direct Shift Chemist to perform a rapid activity analysis.
CRS/ Determine the RCS leak rate to be approximately 15 gpm.
ATCO CRS Direct Shift Chemist to verify primary to secondary leakrate.
CRS Enter Technical Specification 2.1.4.
Identified RCS leakage is greater than 10 gpm. Reduce leakage to within limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or else be in hot shutdown within an additional 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and be in cold shutdown within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
CRS May direct ATCO to isolate letdown and charging.
ATCO Isolate letdown and charging, if directed, and check leakage rate.
CRS/ Restore charging and letdown if isolated.
ATCO CRS Refer to Attachment A, Leak Location Guide, determine leak is to CCW.
CRS Direct plant shutdown using either OP-5 or AOP-05.
Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-4 Revision: 1 Event No.: 6, 7 Page 7 of 9 Event
Description:
Feedwater Pump Trips, Reactor Trip, Blowdown fails to isolate automatically.
Time Position Applicants Actions or Behavior BOPO Detrmine that the running Feedwater Pump has tripped.
CRS Direct the ATCO to manually trip the reactor.
ATCO Manually Trip the reactor.
CRS Enter EOP-00, "STANDARD POST TRIP ACTIONS" and direct ATCO and BOPO to perform Standard Post Trip Actions.
ATCO Perform Standard Post-Trip Actions:
Verify control rod insertion, power lowering, negative startup rate.
Monitors for uncontrolled Cooldown.
BOPO Verify turbine and generator trip.
BOPO Verify electrical status - 4160, D/G, instrument power, 125V DC.
Verify Instrument air status .
ATCO Verify CCW and Raw water status.
Verify RCS inventory control.
Verify RCS pressure control - reports RCS pressure.
Verify core heat removal.
BOPO Determines DCS has not throttled blowdown flow, manually isolates blowdown by closing HCV-1387A/B and HCV-1388A/B within 15 minutes of feedwater pump trip.
BOPO Verify S/G feed - Initiate AFW flow.
Verify S/G pressure and T-cold.
ATCO Verify containment conditions.
CRS Performs diagnostic actions and enters EOP-03, "LOSS OF COOLANT ACCIDENT."
Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-4 Revision: 1 Event No.: 8 Page 8 of 9 Event
Description:
Pipe from EFWST to FW-6 and FW-10 breaks. Total Loss of Feedwater.
Time Position Applicants Actions or Behavior BOPO Reports loss of AFW Flow.
CRS Transitions to EOP-20, "FUNCTIONAL RECOVERY PROCEDURE."
CRS Directs ATCO to trip all Reactor Coolant Pumps.
ATCO Trips all Reactor Coolant Pumps within 10 minutes of a total loss of feedwater being diagnosed.
ATCO Monitor for establishment of natural circulation:
Delta-T less than 50°F.
Difference between CETs and T-hot less than 10°F.
T-hot and T-cold stable or lowering.
At least 20°F subcooling.
CRS Direct BOPO to establish Condensate pump feed to the Steam Generators.
BOPO Establish condensate pump feed to the Steam Generators:
Place all FW Pump Control Switches in Pull-To-Lock.
Direct EONT to open All FW Pump discharge valves.
Ensure FW Pump Recirc valves are closed.
Start All FW Pump Lube Oil Pumps.
Reduce Steam Generator Pressure.
Direct EONT to ensure FCV-1172 is closed.
ATCO Maintain pressurizer pressure and level.
BOPO When S/G pressure is less than 550 psig:
Block SGLS.
Ensure HCV-1385 and HCV-1386 are open.
Ensure HCV-1103 and HCV-1104 are closed.
Reduce pressure to achieve flow through FW bypass Valves, HCV-1105 and HCV-1106.
Continued on next page
Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-4 Revision: 1 Event No.: 8, cont Page 9 of 9 Event
Description:
Pipe from EFWST to FW-6 and FW-10 breaks. Total Loss of Feedwater, continued:
Time Position Applicants Actions or Behavior NOTE: The next two steps are expected only if Wide Range Level in both Steam Generators falls below 27%.
CRS IF WR Level in both S/Gs falls below 27%, THEN go to EOP-20, HR-4 and initiate Once through Cooling.
BOPO IF directed to initiate Once through cooling then:
Deenergize all pressurizer heaters.
Initiate PPLS using test switches.
Ensure HPSI pumps running and injection valves open.
Ensure PORV Block valves are open.
Open both PORVs.
Scenario ends with the Steam Generators being fed by the Condensate Pumps or with Once Through Cooling Established.