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{{#Wiki_filter:Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE
{{#Wiki_filter:}}
 
JPM No: AJPM-RO-CO-1
 
JPM Title: Shutdown margin with inoperable CEA Page 1 of 4
 
Approximate Time: 20 min Actual Time: _________________
 
Reference(s):  TDB-V.9 "Shutdown Margin Worksheet"  R35 TDB-II  "Reactivity Curves"  R28
 
JPM Prepared by: Jerry Koske Date: 05/11/05    JPM Reviewed by:  Date:
JPM Approved by:  Date: 
 
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE
 
JPM No: AJPM-RO-CO-1
 
JPM Title: Shutdown margin with inoperable CEA Page 2 of 4 Operators' Name
: _____________________  Employee # ______________
 
All Critical Steps (shaded) must be per formed or simulated in accordance with the standards contained in this JPM
 
The Operator's performance wa s evaluated as (circle one):
 
SATISFACTORY  UNSATISFACTORY
 
Evaluator's Signature:
________________________
_____  Date: __________
 
Reason, if unsatisfactory:
 
Tools & Equipment: Technical Data Book, calculator
 
Safety Considerations: None
 
Comments: 
 
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE
 
JPM No: AJPM-RO-CO-1
 
JPM Title: Shutdown margin with inoperable CEA Page 3 of 4 INITIATING CUE: The plant is operating at 100% power with all CEAs fully withdrawn. Group 2 CEA #27 has 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 700 ppm. The burnup
 
is 7000 MWD/MTU
 
Critical Steps shown in gray
 
STEP ELEMENT STANDARD 1 Obtain a copy of TDB-V.9 Provide a copy of TDB-V.9 2 Obtain a copy of TDB section II, Reactivity Curves.
 
Obtains copy of TDB-II 3 Determines part I of TDB procedure should be used.
 
Performs calculation using part
: 1. 4 Performs calculation of the difference between actual and required shutdown margin.
Difference calculated on line 11 of TDB-V.9, section 1 is  -0.42  [between  -0.22, -0.62]
5 Determines if SDM is adequate Shutdown margin is adequate
 
Termination Criteria:
Shutdown Margin determi nation has been made
 
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE
 
JPM No: AJPM-RO-CO-1 Page 4 of 4
 
INITIATING CUE: The plant is operating at 100% power with all CEAs fully withdrawn. Group 2 CEA #27 has 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 700 ppm. The burnup
 
is 7000 MWD/MTU
 
FORT CALHOUN STATIONTDB-V.9TECHNICAL DATA BOOKPAGE 1 OF 15R35SHUTDOWN MARGIN WORKSHEETPART I -Instantaneous Shutdown Margin for use prior to a Reactor Trip or immediatelyfollowing a Reactor trip. No changes are assumed for either boron or xenon, since this worksheet is only applicable for calculation of an instantaneous shutdown margin.
NOTE:  Enter values exactly as determined from the figures in the Technical DataBook and carry the algebraic signs through the calculations.Condition1.Present Date/Time:              /          2.Reactor Power (before trip):                     
%3.CEA Positions:Group 1                                        inchesGroup 2                                        inchesGroup 3                                        inchesGroup 4                                        inches4.Reactor Coolant System Boron Concentration prior to shutdown:  (Boron concentrationanalysis must have been performed within the past 24 hours or more recently if boration or dilution has occurred.)
 
ppm 45.Burnup (Take the most recent burnup from the Control Room Log and add 30 MWD/MTUper EFPD.)
MWD/MTU 5Calculation of Shutdown Margin6.Enter Regulating Group Worth, based on burnup (Step 5) and CEA positions (Step 3)  usingTDB Figure II.B.2.
 
% p                    TDB Figure used:
6 FORT CALHOUN STATIONTDB-V.9TECHNICAL DATA BOOKPAGE 2 OF 15R357.Enter Shutdown Group Worths, based on burnup (Step 5) using TDB Figure II.B.1.a.a.Shutdown Group B                                       
% pb.Shutdown Group A                                       
% pc.Total Shutdown Worth
                              +                            =                         
% p              7.a                    7.b                            7.c          8.Determine Power DefectEnter Power Defect based on Reactor power level (Step 2) and burnup (Step 5) usingTDB Figure II.C.2.
 
% p 8        9.Determination of Stuck CEA Allowance (3 cases)
NOTE:  Consider dropped CEAs which can not be verified to be fully inserted asinoperable.(Enter N/A if this case is not applicable.)a.Case I - All CEAs are assumed to be operable.  (No known inoperable CEAs)Assume the highest worth CEAs will stick out of the core upon a Reactor trip. Enterthe value of the most reactive CEA, based on burnup (Step 5), from TDB Figure II.B.1.b., lines (1) thru (3) for the pre-trip configuration. Select the higher value.                                       
% p 9.a FORT CALHOUN STATIONTDB-V.9TECHNICAL DATA BOOKPAGE 3 OF 15R35 NOTE:  The worth of one inoperable CEA is dependent on the configuration of thewithdrawn group(s) and the inoperable CEA.9. b.Case II - One CEA is known to be inoperable (per Technical Specification2.10.2(4) a.)(Enter N/A if this case is not applicable.)
Account for this defective CEA (and the highest worth stuck CEA) by entering only thevalue from lines (4) thru (17) of TDB Figure II.B.1.b. for the inoperable  CEA, based on burnup (Step 5). Select the higher value.
 
%p 9.b NOTE:  The worth of more than one inoperable CEA is calculated by multiplyingthe most conservative Stuck CEA plus Ejected CEA Worth (TDB Figure II.B.1.b. lines  4-17 by the number of inoperable CEAs.
NOTE:  The values of lines (4) thru (17) of TDB FIGURE II.B.1.b. Include the totalreactivity associated with the known inoperable CEA and the highest worth CEA which is assumed to stick out of the core upon a Reactor trip.c.Case III - More than one CEA is known to be inoperable (per TechnicalSpecification 2.10.2.(4)a.).(Enter N/A if this case is not applicable.)
(1)Enter total number of CEA's which are known to be inoperable per TechnicalSpecification 2.10.2.(4) a.).
#
9.c.(1)(2)Enter the most conservative defective CEA worth from TDBFIGURE II.B.1.b. Lines (4) thru (17) depending on defective CEA(s) location, based on burnup (Step 5). Select the higher value.
 
%p 9.c.(2) (#              ) X (                 
%p)  =                         
%p      9.c.(1)    9.c.(2) 9.c FORT CALHOUN STATIONTDB-V.9TECHNICAL DATA BOOKPAGE 4 OF 15R359.d.Enter total available CEA worth from TDB Figure II.B.1.a. based on burnup (Step 5)
 
% p 9.de.Determine the maximum stuck CEA worth by selecting the minimum of either 9.c or 9.d and record that value.
 
% p 9.ef.Enter value from 9.a or 9.b or 9.e as appropriate                           
%p 9.f10.Calculation of the Total Instantaneous Shutdown Margin (SDM I):SDM I =  Stuck CEAs + Power Defect - S/D CEAs worth - Regulating CEA worthSDM I =                 
% +               
% -             
% -               
%  =                 
% Total  9.f      8 7.c61011.Calculate difference from required 3.6% p Shutdown Margin.(                     
%  p) + 3.6%  p =                       
% p          10        11 NOTE:  A 3.6% p shutdown margin must be maintained in a Hot Shutdowncondition, Tc > 210F (Technical Specification 2.10.2(1) and TDB-VI Item 13.0).12.Shutdown Margin check:a.If Step 11 is less than or equal to zero, the shutdown margin is adequate.
b.If Step 11 is greater than zero, use OI-ERFCS-1, Procedure 32 to determine thenumber of gallons of acid to add.REMARKS                                                                                                                       
 
Completed by                                                                                        Date/Time              /         
 
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE
 
JPM No: AJPM-RO-CO-2
 
JPM Title:  Minimum HPSI flow with Containment Sump Blockage Page 1 of 4
 
Approximate Time: 15 minutes Actual Time: _________________
 
Reference(s): EOP-AOP Attachments  R 17
 
JPM Prepared by: Jerry Koske Date: 05/12/05    JPM Reviewed by:  Date:
JPM Approved by:  Date: 
 
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE
 
JPM No: AJPM-RO-CO-2
 
JPM Title:  Minimum HPSI flow with Containment Sump Blockage Page 2 of 4 Operators' Name
: _____________________  Employee # ______________
 
All Critical Steps (shaded) must be per formed or simulated in accordance with the standards contained in this JPM
 
The Operator's performance wa s evaluated as (circle one):
 
SATISFACTORY  UNSATISFACTORY
 
Evaluator's Signature:
________________________
_____  Date: __________
 
Reason, if unsatisfactory:
 
Tools & Equipment: EOP-AOP Attachments
 
Safety Considerations: None
 
Comments: 
 
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE
 
JPM No: AJPM-RO-CO-2
 
JPM Title:  Minimum HPSI flow with Containment Sump Blockage Page 3 of 4 INITIATING CUE: Following a loss of coolant accident, containment sump blockage has restricted the available HPSI and Containment Spray flow. Efforts are underway to provide makeup water to the SIRWT. The CRS has directed you to determine the minimum HPSI flow required to remove decay heat.
 
2 hours and 20 minutes have elapsed since the reactor
 
tripped due to the LOCA.
 
START Critical Steps shown in gray
 
STEP ELEMENT STANDARD 1 Obtains a copy of EOP/AOP attachments.
 
Locates EOP/AOP attachments 2 Refers to the proper attachment
 
Refers to the second page of Attachment 26 (EOP/AOP
 
attachments page 149 of 150)
 
3 Determines required HPSI flow.
Determines that 132 gpm HPSI flow is the minimum required to remove decay heat
[values between128 - 136 gpm are acceptable]
 
Termination Criteria:
Candidate has determined HPSI flow required to remove decay heat.
 
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE
 
JPM No:  AJPM-RO-CO-2 Page 4 of 4
 
INITIATING CUE: Following a loss of coolant accident, containment sump blockage has restricted the available HPSI and Containment Spray flow. Efforts are underway to provide makeup water to the SIRWT. The CRS has directed you to determine the minimum HPSI flow required to remove decay heat.
 
2 hours and 20 minutes have elapsed since the reactor
 
tripped due to the LOCA.
 
START
 
EOP/AOP ATTACHMENTSPage 148 of 150R17 Attachment 26Total SI Pump Flow to Match Decay Heat vs. Time  6Total SI Pump Flow to Match Decay Heat vs. TimeEOP/AOP ATTACHMENTSPage 149 of 150R17  6Total SI Pump Flow to Match Decay Heat vs. TimeEOP/AOP ATTACHMENTSPage 150 of 150R17 Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE
 
JPM No: AJPM-RO-EC-1
 
JPM Title: Boration paths wit h equipment out of service Page 1 of 5
 
Approximate Time: 20 min Actual Time: _________________
 
Reference(s): SO-O-21 TDB-VI One line electrical drawing 
 
JPM Prepared by: Jerry Koske Date: 05/12/05    JPM Reviewed by:  Date:
JPM Approved by:  Date: 
 
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE
 
JPM No: AJPM-RO-EC-1
 
JPM Title: Boration paths wit h equipment out of service Page 2 of 5 Operators' Name
: _____________________  Employee # ______________
 
All Critical Steps (shaded) must be per formed or simulated in accordance with the standards contained in this JPM
 
The Operator's performance wa s evaluated as (circle one):
 
SATISFACTORY  UNSATISFACTORY
 
Evaluator's Signature:
________________________
_____  Date: __________
 
Reason, if unsatisfactory:
 
Tools & Equipment: SO's, TDB and plant drawings
 
Safety Considerations: None
 
Comments: 
 
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE
 
JPM No: AJPM-RO-EC-1
 
JPM Title: Boration paths wit h equipment out of service Page 3 of 5 INITIATING CUE: The plant is in SO-O-21, Shutdown Condition 1, "Refueling Cavity Water Level Greater than or Equal to 23 feet above the top of the core with UGS removed"
 
CH-11A and CH-11B levels are both 30% with a boron concentration of 3.5 WT % Boric Acid. The SIRWT level is 24" with a boron concentration of 2150 ppm.
Charging pump CH-1C has been tagged out of service.
 
480 volt buses 1B3A and 1B3A-4A will be deenergized to allow some work to be performed on BT-1B3A.
 
You have been requested to determine if 2 independent boration paths will be available once the buses are deenergized. If so, identify the borated water source(s) and pump for each boration path.
 
START Critical Steps shown in gray
 
STEP ELEMENT STANDARD  Note: steps 1-3 may be performed in any order:
 
1 Determine equipment that will be affected by deenergizing the
 
busses Refers to plant one line electrical drawing (or other
 
suitable plant reference) and
 
determines that there will be
 
no power to CH-1A, SI-1A and
 
SI-2C.
2 Determines BAST suitability as a boric acid source Refers to TDB-VI (COLR) figure 9 and determines that with 2150 PPM in the SIRWT 
 
and BAST boron at 3.5%,
BAST level must be greater
 
than 32%. With a level of 30%
 
in each BAST, neither BAST Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE
 
JPM No: AJPM-RO-EC-1
 
JPM Title: Boration paths wit h equipment out of service Page 4 of 5  STEP ELEMENT STANDARD can be a source by itself, but together they can count as one
 
source.
3 Determines SIRWT suitability as a boric acid source
 
Determine that the SIRWT can not be used as a source with the charging pumps because
 
the level is less that 80" but
 
that it can be used as a source for the HPSI pump.
 
4 Determines if two independent boration paths are available with the buses deenergized and identifies them.
Determines that 2 independent boration paths are available: 1. CH-11A AND CH-11B through CH-1B
: 2. SIRWT through SI-2B
 
Termination Criteria:
Boration paths have been identified.
 
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE
 
JPM No: AJPM-RO-EC-1 Page 5 of 5
 
INITIATING CUE: The plant is in SO-O-21, Shutdown Condition 1, "Refueling Cavity Water Level Greater than or Equal to 23 feet above the top of the core with UGS removed"
 
CH-11A and CH-11B levels are both 30% with a boron concentration of 3.5 WT % Boric Acid. The SIRWT level is 24" with a boron concentration of 2150 ppm.
Charging pump CH-1C has been tagged out of service.
 
480 volt buses 1B3A and 1B3A-4A will be deenergized to allow some work to be performed on BT-1B3A.
 
You have been requested to determine if 2 independent boration paths will be available once the buses are deenergized. If so, identify the borated water source(s) and pump for each boration path.
 
START
 
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE
 
JPM No: AJPM-RO-RC-1
 
JPM Title: RCA Entry and Exit with spill Page 1 of 5
 
Approximate Time: 12 minutes Actual Time: _________________
 
Reference(s): GET-Radiation Worker Training Standing Order G-101 K/A 2.3.1  (RO Imp 2.6)
 
JPM Prepared by:  Jerry Koske Date: 05/12/05    JPM Reviewed by:  Date:
JPM Approved by:  Date: 
 
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE
 
JPM No: AJPM-RO-RC-1
 
JPM Title: RCA Entry and Exit with spill Page 2 of 5 Operators' Name
: _____________________  Employee # ______________
 
All Critical Steps (shaded) must be per formed or simulated in accordance with the standards contained in this JPM
 
The Operator's performance wa s evaluated as (circle one):
 
SATISFACTORY  UNSATISFACTORY
 
Evaluator's Signature:
________________________
_____  Date: __________
 
Reason, if unsatisfactory:
 
Tools & Equipment: None
 
Safety Considerations: None
 
Comments: This JPM will be per formed during RCA entrance and exit during conduct of in-plant JPMs. 
 
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE
 
JPM No: AJPM-RO-RC-1
 
JPM Title: RCA Entry and Exit with spill Page 3 of 5 INITIATING CUE: You have been direct ed to enter Room 13 to ensure that blowdown tank transfer pump, FW-34A is operating properly.
 
START Critical Steps shown in gray
 
STEP ELEMENT STANDARD Note to Examiner:
Provide Initiating CUE to
 
candidate prior to RCA entry.
 
1 Review RWP Reads RWP 2 Determine Radiological Conditions in Room 13.
Checks survey maps and/or discusses radiological
 
conditions with RP personnel.
 
3 Obtains Dosimetry Verify TLD attached to security badge. Obtain EAD.
4 Sign in on appropriate RWP Insert EAD in reader. Scan PID and RWP number 5 Enter RCA RCA entered 6 Enter Room 13 Enters Room 13 As soon as candidate clears shield wall while entering
 
room 13:
CUE: Floor covered with water.
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE
 
JPM No: AJPM-RO-RC-1
 
JPM Title: RCA Entry and Exit with spill Page 4 of 5  STEP ELEMENT STANDARD 7 Exits Room and Contacts Control Room.
Leaves Room Immediately and Contacts Control Room.
CUE:  Control Room contacted RP. RP has determined that spill is not contaminated. The spill has been cleaned up.
8  Enter Room 13 Enters room CUE: All parameters for FW-34A are normal 9 Exits Room 13 Exits room Note to Examiner:
In-plant JPMs that are conducted in the RCA may be
 
performed at this time.
 
Steps 10 and 11 are
 
performed during RCA exit.
 
10 Monitor for personnel contamination prior to exiting RCA  Monitor for contamination using PCM 11 Sign out of RCA Insert EAD in reader, enter PID number and confirm dose
 
Termination Criteria:
RCA has been exited
 
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE
 
JPM No: AJPM-RO-RC-1 Page 5 of 5
 
INITIATING CUE: You have been direct ed to enter Room 13 to ensure that blowdown tank transfer pump, FW-34A is operating properly.
 
START Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE
 
JPM No: AJPM-SRO-CO-1
 
JPM Title: Shutdown Margin Review with Boron Depletion Page 1 of 5
 
Approximate Time: 20 min Actual Time: _________________
 
Reference(s):  TDB-V.9 "Shutdown Margin Worksheet"  R35 TDB-II  "Reactivity Curves"  R28
 
JPM Prepared by: Jerry Koske Date: 05/11/05    JPM Reviewed by:  Date:
JPM Approved by:  Date: 
 
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE
 
JPM No: AJPM-SRO-CO-1
 
JPM Title: Shutdown Margin Review with Boron Depletion Page 2 of 5 Operators' Name
: _____________________  Employee # ______________
 
All Critical Steps (shaded) must be per formed or simulated in accordance with the standards contained in this JPM
 
The Operator's performance wa s evaluated as (circle one):
 
SATISFACTORY  UNSATISFACTORY
 
Evaluator's Signature:
________________________
_____  Date: __________
 
Reason, if unsatisfactory:
 
Tools & Equipment: Technical Data Book, calculator
 
Safety Considerations: None
 
Comments: 
 
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE
 
JPM No: AJPM-SRO-CO-1
 
JPM Title: Shutdown Margin Review with Boron Depletion Page 3 of 5 INITIATING CUE: The plant has been tripped due to RCP seal failures. One reactor coolant pump has been tripped. All CEAs, including group "N", have be en inserted and boration has taken place. The plant is being cooled down. The RCS is currently at 420°F and a boron concentration of
 
830 ppm.
 
Prior to shutdown, the plant was operating at full power with all CEAs fully withdrawn and a boron
 
concentration of 710 ppm. Burnup is 7000 MWD/MTU.
 
The STA has performed a shutdown margin calculation
 
and determined that, at the current boron concentration, there is adequate shutdown margin as long as the RCS temperature remains above 400°F.
 
The Shift Manager has directed you, the CRS, to review the STA's Shutdown Margin Calculation.
 
START Critical Steps shown in gray
 
STEP ELEMENT STANDARD 1 Obtain a copy of TDB section II, Reactivity Curves.
 
Obtains copy of TDB-II 2 Reviews the shutdown margin calculation
 
Reviews the shutdown margin calculation
 
3 Identifies error on line d(1)
Entered value should be 0 ppm rather than 510 ppm.
 
Current power level, rather than power level before trip was used when reading TDB
 
figure.
 
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE
 
JPM No: AJPM-SRO-CO-1
 
JPM Title: Shutdown Margin Review with Boron Depletion Page 4 of 5  STEP ELEMENT STANDARD 4 Corrects calculation and determines SDM Determines that shutdown margin is inadequate because previous error resulted in adding zero for the boron depletion correction in the required boron concentration.
Boron need to be 20 ppm (10 to 30 ppm) greater than current value.
Termination Criteria:
Shutdown Margin calculation has been reviewed
 
and corrected.
 
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE
 
JPM No: AJPM-SRO-CO-1 Page 5 of 5
 
INITIATING CUE: The plant has been tripped due to RCP seal failures. One reactor coolant pump has been tripped. All CEAs, including group "N", have be en inserted and boration has taken place. The plant is being cooled down. The RCS is currently at 420°F and a boron concentration of
 
830 ppm.
 
Prior to shutdown, the plant was operating at full power with all CEAs fully withdrawn and a boron
 
concentration of 710 ppm. Burnup is 7000 MWD/MTU.
 
The STA has performed a shutdown margin calculation
 
and determined that, at the current boron concentration, there is adequate shutdown margin as long as the RCS temperature remains above 400°F.
 
The Shift Manager has directed you, the CRS, to review the STA's Shutdown Margin Calculation.
 
START
 
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE
 
JPM No: AJPM-SRO-CO-2
 
JPM Title: Equipment Operability Requirements during Mode Change Page 1 of 4
 
Approximate Time: 15 minutes Actual Time: _________________
 
Reference(s): Technical Specifications TDB-III.42  R1
 
JPM Prepared by:  Jerry Koske Date: 05/14/05    JPM Reviewed by:  Date:
JPM Approved by:  Date: 
 
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE
 
JPM No: AJPM-SRO-CO-2
 
JPM Title: Equipment Operability Requirements during Mode Change Page 2 of 4 Operators' Name
: _____________________  Employee # ______________
 
All Critical Steps (shaded) must be per formed or simulated in accordance with the standards contained in this JPM
 
The Operator's performance wa s evaluated as (circle one):
 
SATISFACTORY  UNSATISFACTORY
 
Evaluator's Signature:
________________________
_____  Date: __________
 
Reason, if unsatisfactory:
 
Tools & Equipment: None
 
Safety Considerations: None
 
Comments: 
 
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE
 
JPM No: AJPM-SRO-CO-2
 
JPM Title: Equipment Operability Requirements during Mode Change Page 3 of 4 INITIATING CUE: You are an SRO assigned to the One Stop Shop during a refueling outage. The reactor has been shutdown for 24 hours and a RCS cooldown is in progress. The RCS
 
temperature is 450°F and the pressure is 1250 psia.
 
To allow for some emergent maintenance, outage management has asked you to determine if Safety Injection Tank Isolation valve, HCV-2974 could be closed and deenergized at this time.
 
START Critical Steps shown in gray
 
STEP ELEMENT STANDARD 1 Checks Technical Specifications
 
Refers to Tech Sec section 2.3 and determines that this condition is allowed by Tech
 
Specs.
2 Refers to TDB-III.42 Refers to TDB-III.42 and determines that HCV-2974 (SIT Isolation valve) must remain locked open until RCS pressure is below 400 psia.
 
Termination Criteria:
Candidate determines if condition is allowable or
 
not.
 
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE
 
JPM No: AJPM-SRO-CO-2 Page 4 of 4
 
INITIATING CUE: You are an SRO assigned to the One Stop Shop during a refueling outage. The reactor has been shutdown for 24 hours and a RCS cooldown is in progress. The RCS
 
temperature is 450°F and the pressure is 1250 psia.
 
To allow for some emergent maintenance, outage management has asked you to determine if Safety Injection Tank Isolation valve, HCV-2974 could be closed and deenergized at this time.
 
START
 
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE
 
JPM No: AJPM-SRO-EC-1
 
JPM Title:  Review of OP-ST-SHIFT-0001 Page 1 of 4
 
Approximate Time: 20 min Actual Time: _________________
 
Reference(s): OP-ST-SHIFT-0001  R90
 
JPM Prepared by: Jerry Koske Date: 05/15/05    JPM Reviewed by:  Date:
JPM Approved by:  Date: 
 
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE
 
JPM No: AJPM-SRO-EC-1
 
JPM Title:  Review of OP-ST-SHIFT-0001 Page 2 of 4 Operators' Name
: _____________________  Employee # ______________
 
All Critical Steps (shaded) must be per formed or simulated in accordance with the standards contained in this JPM
 
The Operator's performance wa s evaluated as (circle one):
 
SATISFACTORY  UNSATISFACTORY
 
Evaluator's Signature:
________________________
_____  Date: __________
 
Reason, if unsatisfactory:
 
Tools & Equipment: None
 
Safety Considerations: None
 
Comments: 
 
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE
 
JPM No: AJPM-SRO-EC-1
 
JPM Title:  Review of OP-ST-SHIFT-0001 Page 3 of 4 INITIATING CUE: You are acting as Sh ift Manager. Complete the Shift Manager review for Monday 1900 of the attached portion of OP-ST-SHIFT-0001. Determine if any actions must be taken as a result of the log readings.
 
START Critical Steps shown in gray
 
STEP ELEMENT STANDARD 1 Reviews portion of OP-ST-SHIFT-0001
 
Reviews each Monday 1900 reading on provided portion of
 
OP-ST-SHIFT-0001
 
2 Determines that RCS Cold Leg Temperature does not meet acceptance criteria.
On page 9 of 49, determines that the maximum difference between Tcold cal on AI-31A and the highest T cold is greater than 0.2°F. Determines that calibration is required using OI-RPS-2.
3 Determines that the acceptance criteria for RM-057 are not met.
On page 14 of 49, determines that counts have doubled on RM-057. Determines that SO-G-105 must be entered and contacts the Shift Chemist for a primary-secondary sample.
 
Termination Criteria:
The Shift Manager review of the provided portion of OP-ST SHIFT-0001 has been completed.
 
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE
 
JPM No:  AJPM-SRO-EC-1 Page 4 of 4
 
INITIATING CUE: You are acting as Sh ift Manager. Complete the Shift Manager review for Monday 1900 of the attached portion of OP-ST-SHIFT-0001. Determine if any actions must be taken as a result of the log readings.
 
START   
 
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE
 
JPM No: AJPM-SRO-RC-1
 
JPM Title: Approve Gas Decay Tank Release Page 1 of 5
 
Approximate Time: 15 min Actual Time: _________________
 
Reference(s): OI-WDG-2 Form FC-213
 
JPM Prepared by: Jerry Koske Date: 05/17/05    JPM Reviewed by:  Date:
JPM Approved by:  Date: 
 
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE
 
JPM No: AJPM-SRO-RC-1
 
JPM Title: Approve Gas Decay Tank Release Page 2 of 5 Operators' Name
: _____________________  Employee # ______________
 
All Critical Steps (shaded) must be per formed or simulated in accordance with the standards contained in this JPM
 
The Operator's performance wa s evaluated as (circle one):
 
SATISFACTORY  UNSATISFACTORY
 
Evaluator's Signature:
________________________
_____  Date: __________
 
Reason, if unsatisfactory:
 
Tools & Equipment: None
 
Safety Considerations: None
 
Comments: 
 
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE
 
JPM No: AJPM-SRO-RC-1
 
JPM Title: Approve Gas Decay Tank Release Page 3 of 5 INITIATING CUE: You are the Shift Manager. A release of Waste Gas Decay Tank WD-29D has been scheduled using OI-
 
WDG-2, Attachment 1. You have been requested to
 
authorize the release.
 
START Critical Steps shown in gray
 
STEP ELEMENT STANDARD 1 Review Release Package Reviews the partially filled out portion of OI-WDG-2, Attachment One and the FC-213 Release Permit.
 
2 Authorize the release Determines that the recommended flow rate on OI-WDG-2, Attachment 1 line 12 is not at least 30 SCFH below the maximum release rate (line
: 11) as required.
Refuses to authorize the release                OR corrects the value in line 12 to at least 30 SCFH less than the value in line 11 prior to authorizing release.
 
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE
 
JPM No: AJPM-SRO-RC-1
 
JPM Title: Approve Gas Decay Tank Release Page 4 of 5 Termination Criteria:
Shift Manager has made a decision on release authorization
 
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE
 
JPM No:  AJPM-SRO-RC-1 Page 5 of 5
 
INITIATING CUE: You are the Shift Manager. A release of Waste Gas Decay Tank WD-29D has been scheduled using OI-
 
WDG-2, Attachment 1. You have been requested to
 
authorize the release.
 
START   
 
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE
 
JPM No: AJPM-SRO-EP-1
 
JPM Title: Emergency Classification and PARs Page 1 of 5
 
Approximate Time: 15 minutes Actual Time: _________________
 
Reference(s): EPIP-OSC-1  R37 EPIP-EOF-7  R15
 
JPM Prepared by: Jerry Koske Date: 05/15/05    JPM Reviewed by:  Date:
JPM Approved by:  Date: 
 
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE
 
JPM No: AJPM-SRO-EP-1
 
JPM Title: Emergency Classification and PARs Page 2 of 5 Operators' Name
: _____________________  Employee # ______________
 
All Critical Steps (shaded) must be per formed or simulated in accordance with the standards contained in this JPM
 
The Operator's performance wa s evaluated as (circle one):
 
SATISFACTORY  UNSATISFACTORY
 
Evaluator's Signature:
________________________
_____  Date: __________
 
Reason, if unsatisfactory:
 
Tools & Equipment: None
 
Safety Considerations: None
 
Comments: 
 
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE
 
JPM No: AJPM-SRO-EP-1
 
JPM Title: Emergency Classification and PARs Page 3 of 5 INITIATING CUE: The plant is shutdown following a steam generator tube rupture. The ruptured steam generator has been isolated. All safeguards equipment operated as
 
designed. One RCP is operating in each loop. The primary to secondary leakage rate is 54 gpm. RCS Dose
 
equivalent Iodine-131 is 200 uCi/g. 100°F subcooling is
 
indicated on all CETs and RCS RTDs.
 
The meteorological indications are as follows:  Indicated 10m wind speed
- 17 mph,  14 mph  Indicated wind dire ction - 330°,  330°  Indicated T  is -1.7°C/100m ,  -1.4°C/100m  It is raining, 0.9 inches daily total
 
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
 
STEP ELEMENT STANDARD 1 Refer to Emergency Plan Refer to EPIP-OSC-1 2 Classify the event The event should be classified as a Site Area Emergency per EAL 1.13 (Failure/Challenge to two fission product barriers) on form FC-1188.
Note: Attachment 6.3 indicates that the fuel cladding barrier has failed due to the high DEI (F1) and the reactor coolant system has failed due to the leakage rate (R1)
 
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE
 
JPM No: AJPM-SRO-EP-1
 
JPM Title: Emergency Classification and PARs Page 4 of 5  STEP ELEMENT STANDARD 3 Determine Protective Action Recommendations Refer to EPIP-EOF-7 and determine that there are no PARs for this situation. Document on form FC-1188 Termination Criteria:
The event has been classified. PARS have been determined and FC-1188 has been completed.
 
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE
 
JPM No: AJPM-SRO-EP-1 Page 5 of 5
 
INITIATING CUE: The plant is shutdown following a steam generator tube rupture. The ruptured steam generator has been isolated. All safeguards equipment operated as
 
designed. One RCP is operating in each loop. The primary to secondary leakage rate is 54 gpm. RCS Dose
 
equivalent Iodine-131 is 200 uCi/g. 100°F subcooling is
 
indicated on all CETs and RCS RTDs.
 
The meteorological indications are as follows:  Indicated 10m wind speed
- 17 mph,  14 mph  Indicated wind dire ction - 330°,  330°  Indicated T  is -1.7°C/100m ,  -1.4°C/100m  It is raining, 0.9 inches daily total
 
You are directed to enter the Emergency Plan, classify the event and determine offsite Protective Action
 
Recommendations.
 
Complete page 1 of form FC-1188.
 
FORT CALHOUN STATION FC-1188 GENERAL FORM R18  FORT CALHOUN STATION - EMER GENCY NOTIFICATION FORM Off-Site Contact Time: Person Making Off-Site Report: Contactor's Call Back #:
 
THE COMMAND AND CONTROL POSITION MUST:
Ensure initiation and completion of the FC-1188 form, but may obtain assistance from other personnel as needed. Ensure that all offsite notifications are performed as required.
: 1.    [  ]  Initial Declaration
- for Initial declaration of any emergency classification
        [  ]  Hourly - When completing Hourly updates, one hour from time of the most recent event    notification and  on an hourly basis until event termination.
 
        [  ]
PAR Change
- Any change in Protective Action Recommendations (PARs) and a new    classification is not being declared.
        [  ]  Termination Classification:        [  ]  NOUE    [  ]  Alert    [  ]  Site Area    [  ]  General EAL #: Time Event Declared: Time Event Terminated: 2. Wind From Degrees (10m):
Weather Wind Speed MPH  (Use Slowest 10m): Precipitation:  [  ] Yes  [  ] No Stability Class_____ (use most positive T) -[  ] A  -1.9 [  ] B >-1.9 to  -1.7 [  ] C >-1.7 to  -1.5 [  ] D >-1.5 to  -0.5[  ] E >-0.5 to  1.5 [  ] F >1.5 to  4.0 [  ] G+> 4.0 3. There    [  ]  is
[  ]  was
 
[  ]  will be
[  ]  no [  ]  an airborne
[  ]  a liquid release of radioactive effluent to the environment that is the result of or associated with this event 4. Protective Action Recommendations (PARs)  OPPD General Emergency Automatic PAR = Evacuate 2 mile radius Review EPIP-EOF-7 for additional guidance on PARs  None Evacuate Sectors Shelter Sectors 0-2 Miles 2-5 Miles 5-10 Miles 5. Prognosis    [  ]  Stable    [  ]  Unstable Plant Status    [  ] at Power    [  ] Shutdown
: 6. Remarks Approved: Date: Time:
FORT CALHOUN STATION FC-1188 GENERAL FORM R18    Notify the following agencies: (refer to Emergency Phone Book for alternate phone numbers)  Name of contact (optional)
State of Iowa State of Nebraska Harrison County Pottawattamie County Washington County Record any comments, difficulties or observations you had while making this notification
 
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE
 
JPM No: JPM-0329
 
JPM Title: Fill Safety Injection Tanks Page 1 of 8
 
Location: Simulator    Approximate Time: 18 minutes Actual Time: _________________
 
Reference(s): OI-SI-1 , R77 NRC K/A 006000 A3.01 (RO 4.0 / SRO 3.9)
 
JPM Prepared by: Jerry Koske Date: 05/04/05    JPM Reviewed by:  Date:
JPM Approved by:  Date: 
 
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE
 
JPM No: JPM-0329
 
JPM Title: Fill Safety Injection Tanks Page 2 of 8
 
Operators' Name
: _____________________  Employee # ______________
 
All Critical Steps (shaded) must be per formed or simulated in accordance with the standards contained in this JPM
 
The Operator's performance wa s evaluated as (circle one):
 
SATISFACTORY  UNSATISFACTORY
 
Evaluator's Signature:
________________________
_____  Date: __________
 
Reason, if unsatisfactory:
 
Tools & Equipment: Key for HCV-2928
 
Safety Considerations: None
 
Comments: Run MFP SIS05A 5% until alarm comes in
 
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE
 
JPM No: JPM-0329
 
JPM Title: Fill Safety Injection Tanks Page 3 of 8 INITIATING CUE: You have been directed to fill only SI-6A to 72% using HPSI pump SI-2A, HCV-312 an d PCV-2909. Flushing of SI tank fill and drain lines is not required. Recirculation with all leakage cooler valves closed is desired.
 
All prerequisites are met.
 
START Critical Steps shown in gray
 
STEP ELEMENT STANDARD 1  (1) Ensure SIRWT Tank Recirculation Valves are open:
 
HCV-385    HCV-386 
 
AI-30A Valve OPEN and RED light lit.
 
AI-30B Valve OPEN and RED light lit.
 
2  (2) Ensure HCV-2983, SI Check valve leakage Header CVCS
 
Isolation valve is closed
 
AI-30A GREEN light lit 3 (3.a.1) Place the selected leakage cooler discharge valves in
 
manual:  PCV-2929  PCV-2909  PCV-2949  PCV-2969 AI-30A PCV-2949 CS to MANUAL AMBER light OFF
 
PCV-2909 CS to MANUAL AMBER light OFF
 
AI-30B PCV-2929 CS to MANUAL AMBER light OFF
 
PCV-2969 CS to MANUAL AMBER light OFF
 
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE
 
JPM No: JPM-0329
 
JPM Title: Fill Safety Injection Tanks Page 4 of 8  STEP ELEMENT STANDARD 4 (3.a.2) Close the leakage cooler discharge valve controller(s):  PCV-2929  PCV-2909  PCV-2949  PCV-2969 AI-30A PCV-2949 POT to 100%
output, GREEN light lit
 
PCV-2909 POT to 100%
output, GREEN light lit
 
AI-30B PCV-2929 POT to 100%
output, GREEN light lit
 
PCV-2969 POT to 100%
output, GREEN light lit
 
5 (3.b) Start SI-2A AI-30A SI-2A CS to START and RED light lit Verify amps return to normal after start 6 (3.c) Recirculate for 15 minutes CUE: 15 minutes have elapsed 7  (5.a) Open HCV-545 CB-1,2,3 HCV-545 CS to OPEN, RED
 
light lit
 
8  (5.b) Open HCV-312 AI-30B HCV-312 CS held to OPEN until RED light lit
 
9  (5.c.2)
Throttle open PCV-2909 AI-30A Adjust POT to throttle open 10 (6) Open SI Tank Drain valve, HCV-2916  CB-1,2,3 HCV-2956 CS to OPEN, RED light lit 11 (7)
Close HCV-545 CB-1,2,3 HCV-545 CS to CLOSE, Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE
 
JPM No: JPM-0329
 
JPM Title: Fill Safety Injection Tanks Page 5 of 8  STEP ELEMENT STANDARD GREEN light lit 12 (10) When SI-6C level = 72%:
Close PCV-2909
 
Note: PCV-2909 should be closed before HCV-2916 because HCV-2916 is the last
 
SIT drain valve open 
 
AI-30A PCV-2909 POT to 100%
output, GREEN light lit
 
13 (11) Close HCV-2916 CB-1,2,3 HCV-2916 CS to CLOSE, GREEN light lit
 
14 (12) Close HCV-312 AI-30B HCV-312 CS held to CLOSE until GREEN light lit
 
15 (13) Stop SI-2A AI-30A SI-2A CS to STOP and GREEN light lit, GREEN Flag 16 (14) Open HCV-545 CB-1,2,3 HCV-545 CS to OPEN, RED
 
light lit
 
17  (15) Lower leakage cooler pressure to less than 350 psig by
 
cracking open PCV-2949
 
AI-30A Adjust POT to throttle open
 
until pressure less than 350
 
psig on PIC-2949
 
18  (16.a) Throttle closed PCV-2909 AI-30A PCV-2909 POT to 100%
output, GREEN light lit
 
19  (16.b)
Place PCV-2909 in AUTO AI-30A Momentarily place PCV-2909 CS in OVERIDE and return to Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE
 
JPM No: JPM-0329
 
JPM Title: Fill Safety Injection Tanks Page 6 of 8  STEP ELEMENT STANDARD AUTO, AMBER light lit 20  (17) Close HCV-545 CB-1,2,3 HCV-545 CS to CLOSE, GREEN light lit
 
21 (18) Ensure the leakage cooler discharge valve controllers are in AUTO  PCV-2929  PCV-2909  PCV-2949  PCV-2969 AI-30A Momentarily place PCV-2949 CS in OVERIDE and return to AUTO, AMBER light lit Verify PCV-2909 is in AUTO, AMBER light lit AI-30B Momentarily place PCV-2929 CS in OVERIDE and return to AUTO, AMBER light lit Momentarily place PCV-2969 CS in OVERIDE and return to AUTO, AMBER light lit 22 (19) Verify Operability of all HPSI loop injection valves by
 
confirming amber light is on:  HCV-314  HCV-315  HCV-311  HCV-312  HCV-317  HCV-318  HCV-320  HCV-321  AI-30A AMBER lights on for:  HCV-317  HCV-314  HCV-320  HCV-311  AI-30B AMBER lights on for:  HCV-315  HCV-318  HCV-312  HCV-321 Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE
 
JPM No: JPM-0329
 
JPM Title: Fill Safety Injection Tanks Page 7 of 8  STEP ELEMENT STANDARD 23 (20.b) When both HPSI header pressures are between 250
 
psig and 140 psig:
 
Close HCV-2928
 
CUE: HPSI header pressures are 200 psig.
Tech Spec logging is being
 
performed by another operator
 
Provide key for HCV-2928
 
AI-128A Place key in HCV-2928 CS and turn to Close position, GREEN light lit
 
24 (20.c) Open HCV-2928 AI-128A Place HCV-2928 CS in OPEN position, RED light lit, Remove
 
key
 
AI-30A Reset and acknowledge "SI Pumps Valves Off-Normal
 
Alarm" 25 (20.d) Verify HPSI header pressures:  HPSI header #1 approximately 0 psig  HPSI Header #2 approximately 250 psig AI-30A CUE: PI-309 indicates 0 psig
 
AI-30B CUE: PI-310 indicates 250
 
psig 
 
Termination Criteria:
SI Tank SI-6A has been filled. HPSI pumps and
 
valves have been restored to normal. 
 
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE
 
JPM No: JPM-0329 Page 8 of 8
 
INITIATING CUE: You have been directed to fill only SI-6A to 72% using HPSI pump SI-2A, HCV-312 an d PCV-2909. Flushing of SI tank fill and drain lines is not required. Recirculation with all leakage cooler valves closed is desired.
 
All prerequisites are met.
 
START C Continuous UseFORT CALHOUN STATIONOI-SI-1OPERATING INSTRUCTIONPAGE 14 OF 153  - Filling SI Tank(s) Using HPSI Pumps PROCEDURE (continued)()INITIALS R77 NOTES1.If successive fills are going to be performed:
!Successive fill operations must not last longer than four hours
!Recirculation is only required to be performed once for each suction header2.Recirculation is not required if flushing is performed.
3.Recirculation may be N/A'd if filling Safety Injection Tanks to clear Technical Specification 2.3(2)f LCO.3.IF recirculation is desired, THEN complete the following:a.IF it is desired to manually clos e leakage cooler discharge valve(s), THEN complete the following:1)Place the selected leakage cooler discharge valve(s) in MANUAL:
!  PCV-2929, Leakage Clr SI-4B Discharge Valve
!  PCV-2909, Leakage Clr SI-4A Discharge Valve
!  PCV-2949, Leakage Clr SI-4C Discharge Valve
!  PCV-2969, Leakage Clr SI-4D Discharge Valve 2)Close the leakage cooler discharge valve controller(s):
!  PCV-2929, Leakage Clr SI-4B Disch Vlv Cntrlr
!  PCV-2909, Leakage Clr SI-4A Disch Vlv Cntrlr
!  PCV-2949, Leakage Clr SI-4C Disch Vlv Cntrlr
!  PCV-2969, Leakage Clr SI-4D Disch Vlv Cntrlr b.Start one of the following HPSI Pumps:
!  SI-2A!  SI-2B!  SI-2C                  c.Recirculate the HPSI through the minimum flow lines for 15 minutes.
C Continuous UseFORT CALHOUN STATIONOI-SI-1OPERATING INSTRUCTIONPAGE 15 OF 153  - Filling SI Tank(s) Using HPSI Pumps PROCEDURE (continued)()INITIALS R773d.IF no other evolutions are desired, THEN complete the following:1)Stop the running HPSI Pump:
!  SI-2A!  SI-2B!  SI-2C                  2)Ensure the selected Leakage Cooler Discharge Valve Controller(s) in CLOSE:!  PCV-2929
!  PCV-2909
!  PCV-2949
!  PCV-2969 3)Ensure the selected Leakage Cool er Discharge Valve(s) control switch(es) in AUTO:
!  PCV-2929
!  PCV-2909
!  PCV-2949
!  PCV-2969 4)Ensure the Leakage Cooler Discharge Valve Controller(s) are in AUTO by checking the amber light is on. If amber light is not on, momentarily place hand control s witch in OVERRIDE position to reset the AUTO circuitry:
!  PCV-2929
!  PCV-2909
!  PCV-2949
!  PCV-2969 5)GO TO Step 20.
C Continuous UseFORT CALHOUN STATIONOI-SI-1OPERATING INSTRUCTIONPAGE 16 OF 153  - Filling SI Tank(s) Using HPSI Pumps PROCEDURE (continued)()INITIALS R774.IF flushing is desired, THEN complete the following: (AI-30A/B)
NOTE Opening HCV-545 prevents lifting SI-222.a.Open HCV-545, SIRWT/Lkg Hdr to RCDT Isolation Valve. (CB-1,2,3)              b.Open the loop injection valve for each safety injection tank line to be used:!  HCV-314, Loop 1A HPSI Injection Valve
!  HCV-315, Loop 1A HPSI Injection Valve
!  HCV-311, Loop 1B HPSI Injection Valve
!  HCV-312, Loop 1B HPSI Injection Valve
!  HCV-317, Loop 2A HPSI Injection Valve
!  HCV-318, Loop 2A HPSI Injection Valve
!  HCV-320, Loop 2B HPSI Injection Valve
!  HCV-321, Loop 2B HPSI Injection Valve
 
NOTE At a minimum the leakage CLR discharge valve(s) for the associated HPSI loop injection valve(s) opened in Step 4.b will be opened.c.Open/close the desired leakage CL R discharge valve(s) as follows (AI-30A/B):1)IF in AUTO, THEN place the selected leakage cooler discharge valve(s) in
 
MANUAL:!  PCV-2929, Leakage Clr SI-4B Discharge Valve
!  PCV-2909, Leakage Clr SI-4A Discharge Valve
!  PCV-2949, Leakage Clr SI-4C Discharge Valve
!  PCV-2969, Leakage Clr SI-4D Discharge Valve
 
C Continuous UseFORT CALHOUN STATIONOI-SI-1OPERATING INSTRUCTIONPAGE 17 OF 153  - Filling SI Tank(s) Using HPSI Pumps PROCEDURE (continued)()INITIALS R77 CAUTION Throttling of leakage cooler PCVs may be required to prevent HPSI Pump runout and limit flow to RCDT from SI-222, Safety Injection
 
Tanks SI-6A/B/C/D Fill/Drain Line Relief Valve.4.c2)Throttle the selected leakage c ooler discharge valve controller(s) open/closed as desired to flush the fill and drain lines:
!  PCV-2929, Leakage Clr SI-4B Disch Vlv Cntrlr
!  PCV-2909, Leakage Clr SI-4A Disch Vlv Cntrlr
!  PCV-2949, Leakage Clr SI-4C Disch Vlv Cntrlr
!  PCV-2969, Leakage Clr SI-4D Disch Vlv Cntrlr
 
NOTE Flush duration is determined by the Shift Manager.d.Ensure the desired HPSI pump is running:
!  SI-2A!  SI-2B!  SI-2C                                5.IF flushing is not desired, THEN complete the following: (AI-30A/B)
NOTE Opening HCV-545 prevents lifting SI-222.a.IF a HPSI Pump is running, THEN open HCV-545, SIRWT/Lkg Hdr to RCDT Isolation Valve.
(CB-1,2,3)
C Continuous UseFORT CALHOUN STATIONOI-SI-1OPERATING INSTRUCTIONPAGE 18 OF 153  - Filling SI Tank(s) Using HPSI Pumps PROCEDURE (continued)()INITIALS R775b. Open one or more of the following valves:
!  HCV-314, Loop 1A HPSI Injection Valve
!  HCV-315, Loop 1A HPSI Injection Valve
!  HCV-311, Loop 1B HPSI Injection Valve
!  HCV-312, Loop 1B HPSI Injection Valve
!  HCV-317, Loop 2A HPSI Injection Valve
!  HCV-318, Loop 2A HPSI Injection Valve
!  HCV-320, Loop 2B HPSI Injection Valve
!  HCV-321, Loop 2B HPSI Injection Valve
 
NOTE At a minimum the leakage CLR discharge valve(s) for the associated HPSI loop injection valve(s) opened in Step 5.b will be opened.c.Open/close the desired leakage cooler discharge valve(s) as follows:1)IF in AUTO, THEN place the selected leakage cooler discharge valve(s) in
 
MANUAL:!  PCV-2929, Leakage Clr SI-4B Discharge Valve
!  PCV-2909, Leakage Clr SI-4A Discharge Valve
!  PCV-2949, Leakage Clr SI-4C Discharge Valve
!  PCV-2969, Leakage Clr SI-4D Discharge Valve
 
CAUTION Throttling of the leakage cooler PCVs may be required to prevent HPSI pump runout and limit flow to RCDT from SI-222, Safety Injection Tanks SI-6A/B/C/D Fill /Drain Line Relief Valve.2)Throttle the selected leakage cooler discharge valve controller(s) open/closed as desired:
!  PCV-2929, Leakage Clr SI-4B Disch Vlv Cntrlr
!  PCV-2909, Leakage Clr SI-4A Disch Vlv Cntrlr
!  PCV-2949, Leakage Clr SI-4C Disch Vlv Cntrlr
!  PCV-2969, Leakage Clr SI-4D Disch Vlv Cntrlr
 
C Continuous UseFORT CALHOUN STATIONOI-SI-1OPERATING INSTRUCTIONPAGE 19 OF 153  - Filling SI Tank(s) Using HPSI Pumps PROCEDURE (continued)()INITIALS R77 NOTE More than one tank at a time may be filled through one leakage control valve.6.Open the SI Tank Drain Valve(s) for the tank(s) to be filled: (CB-1,2,3):
!  HCV-2916, SI-6A
!  HCV-2936, SI-6B
!  HCV-2956, SI-6C
!  HCV-2976, SI-6D 7.Ensure that HCV-545 is closed.              8.Ensure the desired HPSI pump is running:
!  SI-2A!  SI-2B!  SI-2C CAUTION To prevent lifting Relief Valve SI-222, the drain valve on the last SI tank to be filled must remain open until the Leakage Cooler Discharge Valve Controllers are in CLOSE per Step 10.9.WHEN the desired level is reached in an SI Tank, THEN close the Drain Valve for that tank:
!  HCV-2916, SI-6A
!  HCV-2936, SI-6B
!  HCV-2956, SI-6C
!  HCV-2976, SI-6D
 
C Continuous UseFORT CALHOUN STATIONOI-SI-1OPERATING INSTRUCTIONPAGE 20 OF 153  - Filling SI Tank(s) Using HPSI Pumps PROCEDURE (continued)()INITIALS R77 NOTE The following Step may be N/Aed if plant conditions require the valve to remain in MANUAL as determined by Shift Manager.10.WHEN the desired level is reached in the last SI Tank, THEN place the opened Leakage Cooler Discharge Valve Controller(s) in
 
CLOSE:!  PCV-2929
!  PCV-2909
!  PCV-2949
!  PCV-2969 11.Close the last SI tank drain valve.                12.Close the HPSI loop injection valve(s) opened in Step 4.b or 5.b:
!  HCV-314, Loop 1A HPSI Injection Valve
!  HCV-315, Loop 1A HPSI Injection Valve
!  HCV-311, Loop 1B HPSI Injection Valve
!  HCV-312, Loop 1B HPSI Injection Valve
!  HCV-317, Loop 2A HPSI Injection Valve
!  HCV-318, Loop 2A HPSI Injection Valve
!  HCV-320, Loop 2B HPSI Injection Valve
!  HCV-321, Loop 2B HPSI Injection Valve 13.Stop the running HPSI Pump:
!  SI-2A!  SI-2B!  SI-2C NOTE Steps 14 thru 17 may be N/A'd if plant conditions require the valve to remain in MANUAL as determined by Shift Manager.14.Open HCV-545, SIRWT/Lkg Hdr to RCDT Isolation Valve.
C Continuous UseFORT CALHOUN STATIONOI-SI-1OPERATING INSTRUCTIONPAGE 21 OF 153  - Filling SI Tank(s) Using HPSI Pumps PROCEDURE (continued)()INITIALS R7715.Lower Leakage Cooler Pressure to less than 350 psig by cracking open the selected Leakage Cooler Discharge Valve Controller:
!  PCV-2929
!  PCV-2909
!  PCV-2949
!  PCV-2969 16.WHEN pressure on the selected leakage Clr Indicator is below 350 psig, THEN close the associated SI tank valves as follows (AI-30A/B):a.Throttled closed the selected Leakage Cooler Discharge Valve Controller(s):
!  PCV-2929
!  PCV-2909
!  PCV-2949
!  PCV-2969 b.Place the selected Leakage Cooler Discharge Valve in AUTO:
!  PCV-2929
!  PCV-2909
!  PCV-2949
!  PCV-2969 17.Close HCV-545.              18.Ensure the Leakage Cooler Discharge Valve Controller(s) are in AUTO by checking the amber light is on. If amber light is not on, momentarily place hand control switch in OVERRIDE position to reset the AUTO circuitry:
!  PCV-2929
!  PCV-2909
!  PCV-2949
!  PCV-2969
 
C Continuous UseFORT CALHOUN STATIONOI-SI-1OPERATING INSTRUCTIONPAGE 22 OF 153  - Filling SI Tank(s) Using HPSI Pumps PROCEDURE (continued)()INITIALS R7719.Verify operability of all HPSI loop injection valves opened by confirming the amber light is on for each valve:
!  HCV-314, Loop 1A HPSI Injection Valve
!  HCV-315, Loop 1A HPSI Injection Valve
!  HCV-311, Loop 1B HPSI Injection Valve
!  HCV-312, Loop 1B HPSI Injection Valve
!  HCV-317, Loop 2A HPSI Injection Valve
!  HCV-318, Loop 2A HPSI Injection Valve
!  HCV-320, Loop 2B HPSI Injection Valve
!  HCV-321, Loop 2B HPSI Injection Valve 20.WHEN both HPSI header pressures have dropped back to between 250 psig and 140 psig following completion of SI Tank fill, 
 
THEN perform the following:a.Close HCV-2928, HPSI Pump 2A Disch, observing all applicable TechSpec LCO requirements regarding HPSI pump operability.              b.WHEN HCV-2928 indicates closed, THEN open HCV-2928.              c.WHEN HCV-2928 has fully opened, THEN restore SI-2A to operable st atus and log out of applicable TechSpec LCOs.              d.Verify HPSI Header #1 pressure drops to approximately 0 psig andHPSI Header #2 rises to approximately 250 psig.
Completed by Date/Time:              /
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE
 
JPM No: JPM-0718
 
JPM Title: Place a Containment Cooling Unit in Service Page 1 of 5
 
Location: Simulator    Approximate Time: 12 minutes Actual Time: _________________
 
Reference(s): OI-VA-1, Attachment 2  R55 NRC K/A 022000 A4.01  (RO 3.6 / SRO 3.6)
 
JPM Prepared by: Jerry Koske Date: 05/05/05    JPM Reviewed by:  Date:
JPM Approved by:  Date: 
 
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE
 
JPM No: JPM-0718
 
JPM Title: Place a Containment Cooling Unit in Service Page 2 of 5
 
Operators' Name
: _____________________  Employee # ______________
 
All Critical Steps (shaded) must be per formed or simulated in accordance with the standards contained in this JPM
 
The Operator's performance wa s evaluated as (circle one):
 
SATISFACTORY  UNSATISFACTORY
 
Evaluator's Signature:
________________________
_____  Date: __________
 
Reason, if unsatisfactory:
 
Tools & Equipment: None
 
Safety Considerations: None
 
Comments: 
 
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE
 
JPM No: JPM-0718
 
JPM Title: Place a Containment Cooling Unit in Service Page 3 of 5 INITIATING CUE: You have been direct ed to place VA-7C and VA-8A in service.
 
All prerequisites are met.
 
START Critical Steps shown in gray
 
STEP ELEMENT STANDARD 1.  (1.a.1)
Open HCV-402B/D CB-1,2,3 Momentarily place HCV-402B/D in OPEN. Verify RED lights lit for both valves.
2  (1.a.2) Ensure HCV-402C is closed CB-1,2,3 Ensure controller POT  in closed position (100% output),
GREEN light lit
 
3  (1.a.3)
Place HCV-402A/C in CIRC CB-1,2,3 Momentarily place HCV-402A/C in CIRC position and release HCV-402A RED light lit 4 (1.a.4)
Throttle open HCV-402C maintaining CCW discharge header pressure greater than or equal to 70 psig CB-1,2,3 Adjust POT for HCV-402C toward OPEN position.
ENSURE pressure on PI-499 does not go below 70 psig.
5 (1.a.5) Monitor the following parameters:  VA-8A Flow  VA-8A Temperature  CCW Discharge Header CB-1,2,3  FI-418  TIC-422  PI-499 Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE
 
JPM No: JPM-0718
 
JPM Title: Place a Containment Cooling Unit in Service Page 4 of 5  STEP ELEMENT STANDARD Press  CCW Discharge Header Temp    TIC-2800 6 (1.b) Start VA-7C AI-30A VA-7C CS to AFTER-START (Red flag), RED light lit 7 (1.b) Monitor Parameters:  VA-7C amps
 
VA-7C DP  VA-7C cooling coil DP  VA-7C Outlet Temp AI-30A  VA-7C ammeter AI-44 Monitor:  PIC-702  PI-710  TI-719    Termination Criteria:
VA-7C is running and CCW is being supplied to VA-8A
 
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE
 
JPM No: JPM-0718 Page 5 of 5
 
INITIATING CUE: You have been direct ed to place VA-7C and VA-8A in service.
 
All prerequisites are met.
 
START C Continuous UseFORT CALHOUN STATIONOI-VA-1OPERATING INSTRUCTIONPAGE 9 OF 120 R55 Attachment 2 - Containment C ooling Operation VA-7C & VA-7D PREREQUISITES () INITIALS1.Procedure Revision Verification:
Revision No.
Date:
2.OI-VA-1-CL-A has been completed per OP-1.              3.IF Containment Cooling is desired, THEN CCW is in service and at least one of the following Containment
 
Cooling Coils is operable:
!VA-8A !VA-8B                          4.Electrical power is available to the desired fan(s):
!VA-7C, Containment Air Cooling Fan, 1B3C-4C-3
!VA-7D, Containment Air Cooling Fan, 1B3B-4B-4
 
PROCEDURE1.IF VA-7C, Cntmt Vent Fan, is to be started, THEN perform the following:a.IF Containment Cooling is desired, THEN initiate CCW to VA-8A as follows:  1)Momentarily place HCV-402B/D, Cntmt Clg Coil VA-8A AC VlvsControl SW to OPEN.      2)Ensure HCV-402C, Cntmt Clg Coil VA-8A Outlt Isol Vlv Cntrlr isclosed.      3)Momentarily place HCV-402A/C, Cntmt Clg Coil VA-8A Isol VlvsControl SW to CIRC.      4)Throttle open HCV-402C maintaining PI-499, CCW DischargeHeader Pressure, greater than or equal to 70 psig.
C Continuous UseFORT CALHOUN STATIONOI-VA-1OPERATING INSTRUCTIONPAGE 10 OF 120  - Containment C ooling Operation VA-7C & VA-7D PROCEDURE (continued)()INITIALS R551.a5)Monitor the following parameters:
!FI-418, VA-8A Flow
!TIC-422, VA-8A Temp
!PI-499, CCW Discharge Header Press
!TIC-2800, CCW Discharge Header Temp
 
CAUTION Running a fan for extended period with the CCW isolated to the cooling coil can cause the water to heatup inside the coil and possibly lift or
 
cause the reliefs to weep.b.Start VA-7C and monitor the following (AI-30A):
!VA-7C amps
!PIC-702, Fan VA-7C Diff Press (AI-44)
!PI-710, Fan VA-7C Clg Coil Diff Press (AI-44)
!TI-719, Fan VA-7C Outlt Temp (AI-44) 2.IF VA-7D, Cntmt Vent Fan, is to be started, THEN perform the following:a.IF Containment Cooling is desired, THEN initiate CCW to VA-8B as follows:  1)Momentarily place HCV-403B/D, Cntmt Clg Coil VA-8B AC VlvsControl SW to OPEN.      2)Ensure HCV-403C, Cntmt Clg Coil VA-8B OUTLT Isol Vlv Cntrlr isclosed.      3)Momentarily place HCV-403A/C, Cntmt Clg Coil VA-8B Isol VlvsControl SW to CIRC.      4)Throttle open HCV-403C maintaining PI-499, CCW DischargeHeader Pressure, greater than or equal to 70 psig.
C Continuous UseFORT CALHOUN STATIONOI-VA-1OPERATING INSTRUCTIONPAGE 11 OF 120  - Containment C ooling Operation VA-7C & VA-7D PROCEDURE (continued)()INITIALS R552.a5)Monitor the following parameters:
!FI-419, VA-8B Flow
!TIC-423, VA-8B Temp
!PI-499, CCW Discharge Header Press
!TIC-2800, CCW Discharge Header Temp
 
CAUTION Running a fan for extended period with the CCW isolated to the cooling coil can cause the water to heatup inside the coil and possibly lift or cause
 
the reliefs to weep.b.Start VA-7D and monitor the following (AI-30B):
!VA-7D amps
!PIC-703, Fan VA-7D Diff Press (AI-44)
!PI-711, Fan VA-7D Clg Coil Diff Press (AI-44)
!TI-721, Fan VA-7D Outlt Temp (AI-44) 3.IF VA-7C, Cntmt Vent Fan, is to be shutdown, THEN perform the following:a.Stop VA-7C (AI-30A).              b.IF CCW Flow to the cooler is to be secured, THEN isolate CCW to VA-8A as follows:  1)Throttle close HCV-402C, Cntmt Clg Coil VA-8A Outlt Isol Vlv Cntrlr maintaining PI-499, CCW Discharge Header Pressure, less than 125 psig.      2)Momentarily place HCV-402A/C, Cntmt Clg Coil VA-8A Isol VlvsControl SW to ISOL.      3)Momentarily place HCV-402B/D, Cntmt Clg Coil VA-8A Vlvs ControlSW to CLOSE.     
 
C Continuous UseFORT CALHOUN STATIONOI-VA-1OPERATING INSTRUCTIONPAGE 12 OF 120  - Containment C ooling Operation VA-7C & VA-7D PROCEDURE (continued)()INITIALS R554.IF VA-7D, Cntmt Vent Fan, is to be shutdown, THEN perform the following:a.Stop VA-7D (AI-30B).              b.IF CCW Flow to the cooler is to be secured, THEN isolate CCW to VA-8B as follows:  1)Throttle close HCV-403C, Cntmt Clg Coil VA-8B Outlt Isol Vlv Cntrlr maintaining PI-499, CCW Discharge Header Pressure, less than 125 psig.      2)Momentarily place HCV-403A/C, Cntmt Clg Coil VA-8B Isol VlvsControl SW to ISOL.      3)Momentarily place HCV-403B/D, Cntmt Clg Coil VA-8B Vlvs ControlSW to CLOSE.     
 
Completed by Date/Time                /
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE
 
JPM No: JPM-0726
 
JPM Title: Restore Control Room Ventilation following Smoke Detector Trip Page 1 of 7
 
Location: Simulator    Approximate Time: 20 minutes Actual Time: _________________
 
Reference(s): OI-VA-3  Attachments 1 and 9  R28  K/A 000067 AA1.05  (RO 3.0 / SRO 3.1)
 
JPM Prepared by: Jerry Koske Date: 05/05/05    JPM Reviewed by:  Date:
JPM Approved by:  Date: 
 
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE
 
JPM No: JPM-0726
 
JPM Title: Restore Control Room Ventilation following Smoke Detector Trip Page 2 of 7
 
Operators' Name
: _____________________  Employee # ______________
 
All Critical Steps (*) must be performed or simulated in accordance with the standards contained in this JPM
 
The Operator's performance wa s evaluated as (circle one):
 
SATISFACTORY  UNSATISFACTORY
 
Evaluator's Signature:
________________________
_____  Date: __________
 
Reason, if unsatisfactory:
 
Tools & Equipment: None
 
Safety Considerations: None
 
Comments: This is an alternate path JPM COP RCCH898A 0%  COP RCCH898B 0%
Ensure VA-46A & B are tripped
 
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE
 
JPM No: JPM-0726
 
JPM Title: Restore Control Room Ventilation following Smoke Detector Trip Page 3 of 7 INITIATING CUE: A smoke detector has tripped the Control Room ventilation system following a fire in the kitchen area. The fire has been extinguished and smoke has been
 
cleared from the area.
 
You are directed to restore the Control Room ventilation system to the normal mode of operation, with VA-46A as the running unit. START
 
CRITICAL STEP ELEMENT STANDARD    1 Obtain copy of OI-VA-3 Locates OI-VA 3 Provide candidate with a copy of OI-VA-3
 
2  (Att-9  1) Ensure the following:  All ventilation dampers closed  Operating ventilation units tripped (VA-46A/B)
AI-106A/B GREEN lights
 
Control switch in AUTO or STOP position GREEN light
 
ON 3 ( 2 ) Place Smoke Detector Override switches in override AI-106A/B HC-VA46A-3 and HC-VA46B-3 in OVERRIDE
: 4.   
 
Turns to OI-VA-3, attachment 1 Acknowledge Smoke Detector Override Annunciators CUE: All prerequisites are met  5.  (att-1  2) Ensure VA-46A/B are in stop AI-106A/B HC-VA46-A-2 and HC-VA B-2 in STOP with GREEN
 
lights lit Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE
 
JPM No: JPM-0726
 
JPM Title: Restore Control Room Ventilation following Smoke Detector Trip Page 4 of 7 CRITICAL STEP ELEMENT STANDARD 6  (3) Verify filter fan control switch position AI-106A/B HC-VA63A and HC-VA63B in
 
AUTO
 
7 (4)
Ensure third-stage cooling VIAS Override control switch in
 
normal AI-106A HC-VA-46A, VA-46A 3 rd stage cooling VIAS override switch in
 
NORMAL 8 (5.a) Start VA-46A AI-106A  HC-VA 46A-2 to START then release. RED light lit 9 (5.b) Verify valve alignment All of the following are OPEN:
AI-106A  PCV 840B (RED Light lit)  PCV-840A-1(RED Light lit)  PCV-840A-2 (RED Light lit)
CB-1,2,3  HCV-2898A (RED Light lit)  HCV-2898B (RED Light lit)  CUE : GREEN lights are ON for HCV-2898A and HCV-2898B. They are closed and will not open.
 
When reported, candidate is
 
directed to restore CR cooling using available
 
equipment.
 
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE
 
JPM No: JPM-0726
 
JPM Title: Restore Control Room Ventilation following Smoke Detector Trip Page 5 of 7 CRITICAL STEP ELEMENT STANDARD 10  Shut Down VA-46A AI-106A HC-VA 46A-2 to STOP and GREEN light lit 11 (4)  Ensure third-stage cooling VIAS Override control switch in normal  AI-106B HC-VA-46B, VA-46B 3 rd stage cooling VIAS override switch in NORMAL  12 (5.a) Start VA-46B AI-106B HC-VA 46B-2 to START then release. RED light lit 13 (5.b) Verify valve alignment All of the following are OPEN AI-106B  PCV 841B (RED Light lit)  PCV-841A-1 (RED Light lit)  PCV-841A-2 (RED Light lit)
CB-1,2,3  HCV-2899A (RED Light lit)  HCV-2899B (RED Light lit)  CUE : The ductwork is clear of smoke    14 (att-9 4)
Place smoke detector override switches in normal AI-106A/B HC-VA-46A-3 and HC-VA-46B-3 in NORMAL
 
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE
 
JPM No: JPM-0726
 
JPM Title: Restore Control Room Ventilation following Smoke Detector Trip Page 6 of 7 Termination Criteria:
CR Ventilation in normal operation with VA-46B
 
running Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE
 
JPM No: New CR Vent (rev 1)
Page 7 of 7
 
INITIATING CUE: A smoke detector has tripped the Control Room ventilation system following a fire in the kitchen area. The fire has been extinguished and smoke has been
 
cleared from the area.
 
You are directed to restore the Control Room ventilation system to the normal mode of operation, with VA-46A as the running unit. START
 
C Continuous UseFORT CALHOUN STATIONOI-VA-3OPERATING INSTRUCTIONPAGE 4 OF 29 R28 Attachment 1 - VA-46A/46B Normal Startup PREREQUISITES
()INITIALS1.Procedure Revision Verification Revision Number Date:
2.Electrical power is available to the following components as required:
!VA-46A, Control Room Air Conditioner, MCC-3B1-FO2
!VA-63A, Control Room Emergency Air Supply Fan, MCC-3B1-CO1
!VA-64A, Control Room Emergency Suppl y Filter Heater, MCC-3B1-C2R
!VA-46B, Control Room Air Cond. Unit, MCC-4A1-DO1
!VA-63B, Control Room Air Supply Fan, MCC-4C2-BO1
!VA-64B, Control Room Air F ilter Heater, MCC-4A1-CO3
!VA-49, Control Room Toilet Exhaust Fan, MPP-1C3A-1 Bkr 7 (MCC-3B1-AO2) 3.Component Cooling Water is in service per OI-CC-1.              4.Verify that humidification is availabl e in the Control Room by installed orportable means.              5.Instrument Air is in service per OI-CA-1.              6.Fire Protection System is in service per OI-FP-1 Attachment 30 for VA-64Aand Attachment 31 for VA-64B.              7.VA-46A and VA-46B air filters are in place.
SE8.VA-64A and VA-64B prefilters, HEPA f ilters, and charcoal media are in place.
SE9.Manual Dampers are lined up per IC-ST-VA-0027.
SE10.Checklist OI-VA-3-CL-A complete per OP-1.
C Continuous UseFORT CALHOUN STATIONOI-VA-3OPERATING INSTRUCTIONPAGE 5 OF 29 R28 Attachment 1 - VA-46A/46B Normal Startup PROCEDURE ()INITIALS NOTES1.By placing both HC-VA-46A/B-1, Cont Rm Ventilation "A"/"B" Mode Switches,  in NORMAL, the running Ventilation unit will operate on a fixed amount of fresh  air makeup (1000 cfm) with system dampers positioned as follows:
!  PCV-6681A/B, Fresh Air Inlet Dampers, open
!  PCV-6680A-1/2, VA-63A Filtered Air Inlet / Outlet Dampers closed
!  PCV-6680B-1/2, VA-63B Filtered Air Inlet / Outlet Dampers closed
!  PCV-6682, Recirculating Air Damper closed2.The NORMAL Mode of operation is automatically overridden by the following:
!  Toxic Gas actuation
!  Smoke Detector actuation
!  VIAS actuation
!  Opening of MS-291 or 292, Main Steam Safety valves
!  Manually placing HC-VA-46A/B-1, Cont Rm Ventilation "A"/"B" Mode Switch in FILT-AIR or RECIRC.3.HCV-2898A/B and HCV-2899A/B close on VIAS, isolating the economizers.1.IF the unit being started has been de-energized for greater than 24 hours and the unit was not pumped down or the compressor was not isolated, THEN perform the following prior to startup:a.Verify power has been applied for at least 24 hours:
!VA-46A!VA-46B Maintb.Verify the Compressor Isolation Valves are open.
Maint C Continuous UseFORT CALHOUN STATIONOI-VA-3OPERATING INSTRUCTIONPAGE 6 OF 29  - VA-46A/46B Normal Startup PROCEDURE (continued)()INITIALS R282.Verify the non-operating unit is in STOP (AI-106A/B):
!HC-VA-46-A-2, Cont Room A/C VA-46-A
!HC-VA-46-B-2, Cont Room A/C VA-46-B 3.Verify both Filter Fan Control Swit ches are in the same position based on Plant conditions (AI-106A/B):
!HC-VA-63A, VA-63A Control Switch
!HC-VA-63B, VA-63B Control Switch 4.For the desired Ventilation Air Un it ensure Third-stage Cooling VIAS Override control switch is in NORMAL (AI-106A/B):
!HC-VA-46A, VA-46A 3 rd Stage Cooling VIAS Override
!HC-VA-46B, VA-46B 3 rd Stage Cooling VIAS Override
 
NOTE If cooling water temperature is bel ow the preset limit (normally 70
°F), the CCW flows thru the economizer and condenser sections via a three-way plug valve.5.If VA-46A, Control Room Air Conditioner is to be rotated on, complete the following:a.Place HC-VA-46A-2, Cont Room A/C VA-46A, in the START position.      b.Verify the following open:
!PCV-840B, VA-46A Inlet
!PCV-840A-1, VA-46A Outlet
!PCV-840A-2, VA-46A Outlet
!HCV-2898A, CR Air Cond VA-46A AC Inlet Valve
!HCV-2898B, CR Air Cond VA-46A AC Outlet Valve 6.If VA-46B Control Room Air Conditioner is to be rotated on, complete the following:a.Place HC-VA-46B-2, Cont Room A/C VA-46B, in the START position.
C Continuous UseFORT CALHOUN STATIONOI-VA-3OPERATING INSTRUCTIONPAGE 7 OF 29  - VA-46A/46B Normal Startup PROCEDURE (continued)()INITIALS R286b.Verify the following open:
!PCV-841B, VA-46B Inlet
!PCV-841A-1, VA-46B Outlet
!PCV-841A-2, VA-46B Outlet
!HCV-2899A, CR Air Cond VA-46B AC Inlet Valve
!HCV-2899B, CR Air Cond VA-46B AC Outlet Valve 7.IF the remaining unit needs to be shutdown,THEN GO TO Attachment 2.
Completed by Date/Time              /
C Continuous UseFORT CALHOUN STATIONOI-VA-3OPERATING INSTRUCTIONPAGE 23 OF 29 R28 Attachment 9 - System Restorati on Following a Smoke Detector Trip PREREQUISITES
()INITIALS1.Procedure Revision Verification Revision Number Date:             
 
PROCEDURE CAUTION Before restarting the Control Room Ventila tion Unit, the source of smoke in the Ventilation System must be identified and corrected.1.IF smoke is detected in the Control Room Ventilation Duct, THEN verify the following:
!All ventilation dampers are closed (AI-106A/B)
!The operating Ventilation Units VA-46A/B tripped.
!The operating Filtered Air Units VA-63A/B tripped.
2.Place the following Smoke Detector Auto Trip Override switches in OVERRIDE to override all Zone 25 and Zone 31 detector trips:
!HC-VA-46A-3, Smoke Detector Auto Trip Override (AI-106A)
!HC-VA-46B-3, Smoke Detector Auto Trip Override (AI-106B) 3.Manually align the Control Room Vent ilation System to the desired mode per Attachment  1 (NORMAL), 4 (FILT-AIR), or 5 (RECIRC).              4.WHEN the smoke has been flushed from the duct, THEN return the Smoke Detector Auto Trip Override switches to NORMAL:
!HC-VA-46A-3, Smoke Detector Auto Trip Override (AI-106A)
!HC-VA-46B-3, Smoke Detector Auto Trip Override (AI-106B)
 
Completed by Date/Time              /
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE
 
JPM No:  JPM-0778
 
JPM Title:  RPS T-Cold Calibration Page 1 of 6
 
Location: Simulator    Approximate Time: 10 minutes Actual Time: _________________
 
Reference(s): OI-RPS-2,  R6 NRC K/A 012000 A1.01  (RO 2.9 / SRO 3.4)
 
JPM Prepared by: Jerry Koske Date: 05/05/05    JPM Reviewed by:  Date:
JPM Approved by:  Date: 
 
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE
 
JPM No:  JPM-0778
 
JPM Title:  RPS T-Cold Calibration Page 2 of 6
 
Operators' Name
: _____________________  Employee # ______________
 
All Critical Steps (shaded) must be per formed or simulated in accordance with the standards contained in this JPM
 
The Operator's performance wa s evaluated as (circle one):
 
SATISFACTORY  UNSATISFACTORY
 
Evaluator's Signature:
________________________
_____  Date: __________
 
Reason, if unsatisfactory:
 
Tools & Equipment: Bypass key for trip unit #9
 
Safety Considerations: NONE
 
Comments: Simulator JPM
 
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE
 
JPM No:  JPM-0778
 
JPM Title:  RPS T-Cold Calibration Page 3 of 6 INITIATING CUE: The plant is operating at 100% power. The channel "A" T-cold Cal is indicating low.
The other channel T-cold values are within 0.
1°F of each other.
 
The Shift Manager has directed you to adjust the
 
channel "A" T-cold Cal.
 
All prerequisites have been met
 
START Critical Steps shown in gray
 
STEP ELEMENT STANDARD  CUE: Provide a copy of OI-RPS-2 1  (1.a) Record T-cold DVM readings on all four RPS channels
 
AI-31A/B/C/D Select T-Cold on selector
 
switch and record value in
 
procedure
 
2 (1.b) Record T-cold cal DVM readings on all four RPS
 
channels AI-31A/B/C/D For each channel, Select T-Cold CAL on selector
 
switch and record value in
 
procedure
 
3 (1.c) Record T-cold cal pot settings for all four channels
 
AI-31A/B/C/D For each channel, 
 
Record POT setting in
 
procedure
 
4 (1.d) Obtain the RPS Trip Unit #9 bypass key CUE: Provide key 5. (1.e) Log into Tech Spec 2.15(1) 48 hour LCO for channel "A" CUE: Log entry has been made 6 (1.f) Bypass RPS TM/LP Trip Unit AI-30A Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE
 
JPM No:  JPM-0778
 
JPM Title:  RPS T-Cold Calibration Page 4 of 6  STEP ELEMENT STANDARD on channel "A" Insert key in RPS channel "A" Trip Unit #9 bypass switch and place in  BYPASS (clockwise) position. AMBER light lit 7 (1.g) Adjust T-cold cal POT on RPS channel "A" until the T-cold cal reading on the DVM equals the highest RPS channel T-cold AI-30A Adjust T-cold cal POT on RPS channel "A" until the T-cold cal reading on the DVM equals the highest RPS channel T-cold recorded in step 1 (1.a) 8 (1.h) Ensure TM/LP Trip unit is reset AI-30A Place RPS channel "A" Trip Unit #9 bypass switch in RESET (counterclockwise) position. AMBER light off.
9 (1.i) Remove bypass key AI-30A Remove key
 
Cue: Accept key
 
10 (1.j) Exit Tech Spec 2.15(1) Cue: Log entry has been made 11 (1.l) Record T-cold DVM readings on all four RPS channels
 
AI-31A/B/C/D For each channel, 
 
Select T-Cold on selector
 
switch and record value in
 
procedure
 
12 (1.m) Record T-cold cal pot settings for all four channels
 
AI-31A/B/C/D For each channel, 
 
Record POT setting in
 
procedure
 
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE
 
JPM No:  JPM-0778
 
JPM Title:  RPS T-Cold Calibration Page 5 of 6 Termination Criteria:
RPS channel "A" T-cold has been calibrated and no RPS Trip Units are bypassed 
 
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE
 
JPM No: JPM-0778 Page 6 of 6
 
INITIATING CUE: The plant is operating at 100% power. The channel "A" T-cold Cal is indicating low.
The other channel T-cold values are within 0.
1°F of each other.
 
The Shift Manager has directed you to adjust the
 
channel "A" T-cold Cal.
 
All prerequisites have been met
 
START WP8 Fort Calhoun Station Unit No. 1 OI-RPS-2 OPERATING INSTRUCTION Title: REACTOR PROTECTIVE SYSTEM - TM/LP TCOLD CAL CALIBRATION
 
FC-68 Number: DCR 10481  Reason for Change:Reformat per FCSG-9.
Initiator:J. Borger/S. Lindquist  Preparer:Stan Heyden Correction (a):Page 1 and 2  (01-25-01)ISSUED:  04-20-99  3:00 pmR6 FORT CALHOUN STATIONOI-RPS-2OPERATING INSTRUCTIONPAGE 1 OF 4 R6 REACTOR PROTECTIVE SYSTEM - TM/LP TCOLD CAL CALIBRATION ATT PURPOSE PAGE 1 - Adjust the T cold cal POT(s)......................................................2 PRECAUTIONS1.The selected RPS TM/LP Trip Unit is placed in BYPASS prior to adjusting the T cold cal Pot to prevent an inadvertent channel trip.2.T cold DVM readings while at a steady state power are normally kept within close tolerances.
Hence, if while at steady state power readi ngs differ by greater than 1.0 °F, the System Engineer should be consulted prior to adjus tment to ensure operability of the affected channel.REFERENCES/COMMITMENT DOCUMENTS1.Technical Specifications:
!1.1: Safety Limits - Reactor Core
!1.3: Table 1-1: RPS Limiting Safety System Settings
!2.15:  Instrumentati on and Control Systems
!2.15: Table 2-2:  Instrument Operating Requirements for Reactor Protective System
!3.1: Table 3-3: Item 17:  Reactor Coolant Inlet Temperature
!3.1: Table 3-1: Minimum Frequencies fo r Checks, Calibrations and Testing of Miscellaneous Instrumentation and Controls
!3.10(7)a: DNB Parameters2.USAR:!7.2: Reactor Protective System
!7.5: Instrumentation Systems3.Others:!OP-ST-SHIFT-0001
!SO-G-100: Operability Disposit ions When Calibrating, Testing or Operating Safety Related Equipment
!EAR 94-130, Appropriate Acceptance Criteria or Requirements to TCOLD Cal C Continuous UseFORT CALHOUN STATIONOI-RPS-2OPERATING INSTRUCTIONPAGE 2 OF 4 R6 Attachment 1 - Adjust the T cold cal POT(s)PREREQUISITES
() INITIAL 1.Procedure Revision Verification Revision Number Date:
2.Reactor is at steady state conditions.                3.Reactor power is greater than 15%.              4.Adjustment is requested by the Sh ift Manager OR the difference between the highest T cold DVM reading and any T cold cal DVM reading for the applicable Reactor power level is as follows:
!greater than 75% to 100% power greater than or equal to 0.2°F
!greater than 50% to less than or equal to 75% power greater than or equal to 0.5°F
!greater than or equal to 15% to le ss than or equal to 50% power greaterthan or equal to 1.0°F              5.IF T cold DVM readings differ by more than 1.0°F,THEN contact the System Engineer prior to adjustment.              6.Shift Manager notified prior to adjustment.
Shift Mgr PROCEDURE1.Perform the following:a.Record T cold DVM readings on all four RPS channels.
!AI-31A           
°F!AI-31B           
°F!AI-31C           
°F!AI-31D           
°F C Continuous UseFORT CALHOUN STATIONOI-RPS-2OPERATING INSTRUCTIONPAGE 3 OF 4  - Adjust the T cold cal POT(s)PROCEDURE (continued)() INITIAL R61b.Record T cold cal DVM readings on all four RPS channels.
!AI-31A           
°F!AI-31B           
°F!AI-31C           
°F!AI-31D           
°F                                      c.Record T cold cal POT settings.
!AI-31A           
!AI-31B           
!AI-31C           
!AI-31D d.Obtain the RPS TM/LP Trip Unit # 9 Bypass Key.
CAUTION Only ONE channel shall be adjusted at a time.e.Log into Technical Specification 2.15(1) 48 hour LCO for selected channel:!AI-31A!AI-31B!AI-31C!AI-31D                                      f.Bypass TM/LP trip unit on the selected channel:
!AI-31A!AI-31B!AI-31C!AI-31D                                      g.Adjust T cold cal POT on the selected channel until the T cold cal DVM reading equals highest RPS channel T cold recorded in Step a.              h.Ensure selected TM/LP Trip Unit #9 is RESET.
C Continuous UseFORT CALHOUN STATIONOI-RPS-2OPERATING INSTRUCTIONPAGE 4 OF 4  - Adjust the T cold cal POT(s)PROCEDURE (continued)() INITIAL R61i.Remove Bypass Key for selected TM/LP Trip Unit.              j.Exit Technical Specificati on 2.15(1) for the selected channel
!AI-31A!AI-31B!AI-31C!AI-31D                                      k.Repeat Steps e. through j. for any remaining channels out of specification.
l.Record T cold cal DVM readings:
!AI-31A           
°F!AI-31B           
°F!AI-31C           
°F!AI-31D           
°F                                      m.Record new T cold cal POT settings:
!AI-31A           
!AI-31B           
!AI-31C           
!AI-31D           
 
Completed by Date/Time                  /
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE
 
JPM No:  JPM-0042
 
JPM Title: Transfer Clutch Power Supply Page 1 of 5
 
Location: Simulator    Approximate Time: 12 Minutes Actual Time: _________________
 
Reference(s): OI-EE-4, Atta chments 7 and 1    R30  NRC K/A 062000 A2.10  (RO 3.0 / SRO 3.3)
 
JPM Prepared by: Jerry Koske Date: 05/05/05    JPM Reviewed by:  Date:
JPM Approved by:  Date: 
 
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE
 
JPM No:  JPM-0042
 
JPM Title: Transfer Clutch Power Supply Page 2 of 5
 
Operators' Name
: _____________________  Employee # ______________
 
All Critical Steps (shaded) must be per formed or simulated in accordance with the standards contained in this JPM
 
The Operator's performance wa s evaluated as (circle one):
 
SATISFACTORY  UNSATISFACTORY
 
Evaluator's Signature:
________________________
_____  Date: __________
 
Reason, if unsatisfactory:
 
Tools & Equipment: None
 
Safety Considerations: None
 
Comments: Cross Tie Instrum ent busses A&C, Open Supply breaker for instrument bus A. Place PS1&PS3 supply to bus "B"
 
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE
 
JPM No:  JPM-0042
 
JPM Title: Transfer Clutch Power Supply Page 3 of 5 INITIATING CUE: The plant is in an outage. Maintenance has been completed on Instrument Bus A and will begin on instrument bus B. You have been directed to transfer Clutch Power Supply PS1 & PS 3 from Instrument Bus B to Instrument Bus A.
 
Inverter "A" has been bypassed
 
START Critical Steps shown in gray
 
STEP ELEMENT STANDARD 1 (1 a) Ensure Instrument Bus A is not cross-tied to Instrument Bus C
 
AI-40A, AI-40C Checks position of Instrument Bus Tie Breakers and
 
determines that the Buses are
 
cross-tied.
 
CUE: If Candidates reports that the buses are cross tied, then say "The Shift
 
Manager states that the
 
cross-tie is no longer needed and directs you to
 
hot bus transfer the Instrument Bus A loads connected to Instrument Bus C back to Instrument
 
Bus A (Provide OI-EE-4,  )
2 (Att 1-7.e.1)
Close 1-BUS-1A-1, Instrument Bus "A" Supply Breaker AI-40A Instrument Bus "A" supply breaker to CLOSE
 
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE
 
JPM No:  JPM-0042
 
JPM Title: Transfer Clutch Power Supply Page 4 of 5  STEP ELEMENT STANDARD 3 ( 7.e.2 )
Open I-BUS-AC-2, Instrument Bus C Tie Breaker AI-40C Instrument Bus "C" tie breaker to OPEN  4 ( 7.e.3)
Open I-BUS-AC-1, Instrument Bus A Tie Breaker AI-40A Instrument Bus "A" tie breaker to OPEN  5 (Att-7 1.c) Verify Clutch Power Supply breaker RPS/CB-CD is closed
 
AI-57 Breaker in ON position 6  (1.d) Place Clutch Power Supply Transfer Switch RPS/TS-AB in the Instrument Bus A position
#1  AI-57 Turn switch to position 1 (left) 7  (1.e,f)
Verify Clutch Power Supply breaker RPS/CB-AB is closed.
If in trip free position, the reset and close AI-57 RESET and CLOSE Clutch Power Supply Breaker RPS/BC-AB 8  (1.g) Verify all four Clutch Power Supply ammeters read
 
upscale.
AI-3 Ammeters read upscale 9  (1.h) Verify proper indicating lights in Clutch Power Supply Cabinet are energized.
 
AI-3 WHITE lights ON CUE: Inverter A has been placed in normal operation
 
Termination Criteria:
Clutch Power Supply PS1 & PS3 are supplied from
 
Instrument Bus A. Inst rument busses A&C are not cross-tied
 
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE
 
JPM No:  JPM-0042 Page 5 of 5
 
INITIATING CUE: The plant is in an outage. Maintenance has been completed on Instrument Bus A and will begin on instrument bus B. You have been directed to transfer Clutch Power Supply PS1 & PS 3 from Instrument Bus B to Instrument Bus A.
 
Inverter "A" has been bypassed
 
START
 
CContinuous UseFORT CALHOUN STATIONOI-EE-4OPERATING INSTRUCTIONPAGE 3 OF 105R30Attachment 1 - Inverter A (EE-8H) OperationPREREQUISITES
()INITIALS1.Procedure Revision VerificationRevision No.
Date:
2.125 VDC Bus 1 (EE-8F) is in service per OI-EE-3.              3.IF RCS temperature is greater than 300°F,THEN verify Checklist OI-EE-4-CL-A has been completed.
PROCEDURE NOTES1.Instrument bus panels AI-40A has a pair of white lights for indicatinggrounds. Both lights will be dimly lit when no grounds are present on thebus. If a ground occurs, one light will become brighter than the other untilthe ground is removed. The lights automatically reset to the normal mode (both lights dimly lit) after ground removal.2.A hard ground will cause an invert er trouble alarm to annunciate onCB-20. However, it is possible for the white lights to indicate a ground without the trouble alarm being in. The voltage sensing alarm relay only actuates on a hard ground signal.1.IF short-term bypass of Inverter A (EE-8H) is desired,THEN perform the following:
NOTEOnce Inverter A (EE-8H) is in reverse transfer it is inoperable because itcan not forward transfer automatically back to its instrument bus.a.Declare Inverter A (EE-8H) inoperable per TechnicalSpecification 2.7(2)(o).
SM/CRS CContinuous UseFORT CALHOUN STATIONOI-EE-4OPERATING INSTRUCTIONPAGE 4 OF 105Attachment 1 - Inverter A (EE-8H) Operation PROCEDURE (continued)()INITIALSR30 NOTEInstrument Bus voltage may be lower than normal 117.6 - 122.4 VoltsAC when being fed from a bypass transformer.1b.Ensure MCC-3B1-E3R, EE-4N Inverter A Bypass transformer Breaker isclosed.      c.Verify sync loss light is off.      d.Push the reverse transfer button.      e.Verify sync loss light is off.      f.Verify reverse transfer light is on.
2.IF restoration from short-term bypass of Inverter A (EE-8H) is desired,THEN perform the following:a.Verify reverse transfer light is on.      b.Verify EE-8H-S1, Inverter A, EE-8H Manual Transfer Switch, is in theINVERTER position.      c.Ensure sync loss light is off.      d.Push the forward transfer button.      e.Verify reverse transfer light is off.      f.Verify forward transfer light is on.g.Ensure EE-8H-CB3, Inverter A EE-8H Vent Fans Breaker is closed.
 
CContinuous UseFORT CALHOUN STATIONOI-EE-4OPERATING INSTRUCTIONPAGE 5 OF 105Attachment 1 - Inverter A (EE-8H) Operation PROCEDURE (continued)()INITIALSR30CAUTIONAdjustments to inverter output frequency or output voltage shall only bemade by Electrical Maintenance. Guidance from EM-PM-EX-0800 may be referenced as necessary.2h.Verify Inverter A Output Frequency is between 59.4 and 60.6 Hz(normal 60.0 Hz).      i.Verify Inverter A Output Voltage is between 117.6 and 122.4 Volts AC(normal 120.0 Volts AC).
j.Once Inverter A is operable and has been returned to its bus (i.e.forward transferred) declare Inverter A (EE-8H) operable.
SM/CRS3.IF switching Inverter A (EE-8H) from normal operation to bypass power isdesired, THEN perform the following:
NOTEInstrument Bus voltage may be lower than normal 117.6 - 122.4 VoltsAC when being fed from a bypass transformer.a.Ensure MCC-3B1-E3R, EE-4N Inverter A Bypass Transformer Breakeris closed.      b.Verify sync loss light is off.
NOTEOnce Inverter A (EE-8H) is in reverse transfer it is inoperable because it can not forward transfer automatically back to its instrument bus.c.Declare Inverter A (EE-8H) inoperable per TechnicalSpecification 2.7(2)(o).
 
SM/CRS CContinuous UseFORT CALHOUN STATIONOI-EE-4OPERATING INSTRUCTIONPAGE 6 OF 105Attachment 1 - Inverter A (EE-8H) Operation PROCEDURE (continued)()INITIALSR303d.Push the reverse transfer button.      e.Verify sync loss light remains off.      f.Verify reverse transfer light is on.      g.Place EE-8H-S1, Inverter A, EE-8H Manual Transfer Switch, inBYPASS.      h.Verify sync loss light is on.      i.Open EE-8H-CB1, Inverter A, EE-8H DC Input Breaker.
4.IF Bypass Transformer EE-4N is in operation AND Inverter A (EE-8H)startup is desired, THEN perform the following: a.Ensure EE-8H-CB1, Inverter A, EE-8H DC Input Breaker is open.      b.Ensure EE-8F-CB24, Inverter A, EE-8H Breaker on DC Bus 1 is closed.      c.Ensure EE-8H-S1, Inverter A, EE-8H Manual Transfer Switch, is inBYPASS.      d.Momentarily push the precharge button, then wait ten (10) seconds.      e.Close EE-8H-CB1, Inverter A, EE-8H DC Input Breaker.      f.Verify sync loss light is on.      g.Verify reverse transfer light is on.      h.Place EE-8H-S1, Inverter A, EE-8H Manual Transfer Switch, in theINVERTER position.      i.Ensure sync loss light is off.      j.Push the forward transfer button.
CContinuous UseFORT CALHOUN STATIONOI-EE-4OPERATING INSTRUCTIONPAGE 7 OF 105Attachment 1 - Inverter A (EE-8H) Operation PROCEDURE (continued)()INITIALSR304k.Verify reverse transfer light is off.      l.Verify forward transfer light is on.      m.Ensure EE-8H-CB3, Inverter A EE-8H Vent Fans Breaker is closed.      CAUTIONAdjustments to inverter output frequency or output voltage shall only bemade by Electrical Maintenance. Guidance from EM-PM-EX-0800 may be referenced as necessary.n.Verify Inverter A Output Frequency is between 59.4 and 60.6 Hz(normal 60.0 Hz).      o.Verify Inverter A Output Voltage is between 117.6 and 122.4 Volts AC(normal 120.0 Volts AC).
p.Once Inverter A is operable and has been returned to its bus (i.e.forward transferred) declare Inverter A (EE-8H) operable.
SM/CRSCAUTIONStep 5 isolates Instrument Bus AI-40A from Instrument Bus AI-40C if cross-tied.5.IF EE-4N, Bypass Transformer is not available AND Inverter A (EE-8H)startup is desired, THEN perform the following: a.Remove all loads from 120 Volt AC Instrument Bus A (AI-40A).      b.Remove all loads from 120 Volt AC Instrument Bus A1 (AI-40A).      c.Open I-BUS-AC-2, Instrument Bus C Tie Breaker (AI-40C).      d.Open I-BUS-AC-1, Instrument Bus A Tie Breaker (AI-40A).
CContinuous UseFORT CALHOUN STATIONOI-EE-4OPERATING INSTRUCTIONPAGE 8 OF 105Attachment 1 - Inverter A (EE-8H) Operation PROCEDURE (continued)()INITIALSR305e.Ensure EE-8H-CB1, Inverter A, EE-8H DC Input Breaker is open.      f.Place EE-8H-S1, Inverter A, EE-8H Manual Transfer Switch, in theINVERTER position.      g.Momentarily push the precharge button, then wait ten (10) seconds.      h.Close EE-8H-CB1, Inverter A, EE-8H DC Input Breaker.      i.Verify reverse transfer light is on.      j.Push the forward transfer button.      k.Verify forward transfer light is on.l.Ensure EE-8H-CB3, Inverter A EE-8H Vent Fans Breaker is closed.
CAUTIONAdjustments to inverter output frequency or output voltage shall only bemade by Electrical Maintenance. Guidance from EM-PM-EX-0800 may be referenced as necessary.m.Verify Inverter A Output Frequency is between 59.4 and 60.6 Hz(normal 60.0 Hz).      n.Verify Inverter A Output Voltage is between 117.6 and 122.4 Volts AC(normal 120.0 Volts AC).      o.Close I-BUS-IA-1, Instrument Bus A Supply Breaker (AI-40A).      p.Ensure EE-8H-CB2, Inverter A, EE-8H AC Output Breaker is closed.      q.Sequentially load 120 Volt AC Instrument Bus A (AI-40A).      r.Sequentially load 120 Volt AC Instrument Bus A1 (AI-40A).     
 
CContinuous UseFORT CALHOUN STATIONOI-EE-4OPERATING INSTRUCTIONPAGE 9 OF 105Attachment 1 - Inverter A (EE-8H) Operation PROCEDURE (continued)()INITIALSR305s.Once Inverter A is operable and has been returned to its bus (i.e.forward transferred) declare Inverter A (EE-8H) operable.
SM/CRS NOTEUpon loss of an Instrument Bus implement AOP-16, Loss of InstrumentBus Power.6.IF hot bus transfer of Instrument Buses A and A1 feed to Instrument BusAI-40C is desired, THEN perform the following:a.Ensure the following plant conditions are met:
!Reactor Coolant System temperature is less than 300°F
!All Fuel movement has been secured
!All core alterations have been secured
!No work is being performed that requires electrical power fromAI-57 on the Control Element Drive Mechanisms (CEDM)
Shift Mgrb.Verify that there are no hard grounds on either Instrument Bus A orInstrument Bus C.              c.Block the PPLS/BLOCK A relay (device #817) in the PICKED-UPposition (located behind CB-3).
EM Ind Verif CContinuous UseFORT CALHOUN STATIONOI-EE-4OPERATING INSTRUCTIONPAGE 10 OF 105Attachment 1 - Inverter A (EE-8H) Operation PROCEDURE (continued)()INITIALSR306d.Transfer the load on Instrument Inverter C to the bypass source byperforming the following:
NOTEInstrument Bus voltage may be lower than normal 117.6 - 122.4Volts AC when being fed from a bypass transformer.1)Ensure MCC-3C1-A4R, EE-4Q Inverter C Bypass Transformer, Breaker is closed.      2)Verify sync loss light is off.      3)Push the reverse transfer button.      4)Verify sync loss light is off.      5)Verify reverse transfer light is on.
e.Transfer the load on Instrument Inverter A to the Bypass source byperforming the following:
NOTEInstrument Bus voltage may be lower than normal 117.6 - 122.4Volts AC when being fed from a bypass transformer.1)Ensure MCC-3B1-E3R, EE-4N Inverter A Bypass Transformer, Breaker is closed.      2)Verify sync loss light is off.      3)Push the reverse transfer button.      4)Verify sync loss light is off.      5)Verify reverse transfer light is on.     
 
CContinuous UseFORT CALHOUN STATIONOI-EE-4OPERATING INSTRUCTIONPAGE 11 OF 105Attachment 1 - Inverter A (EE-8H) Operation PROCEDURE (continued)()INITIALSR30CAUTIONMaximum Inverter load is 62.5 amps. Non-essential loading may needto be reduced to prevent an overload condition following the load transfer.6f.Hot bus transfer loads from Instrument Bus A to Instrument Bus C byperforming the following in the sequence listed:1)Close I-BUS-AC-2, Instrument Bus C Tie Breaker (AI-40C).      2)Close I-BUS-AC-1, Instrument Bus A Tie Breaker (AI-40A).      3)Open I-BUS-IA-1, Instrument Bus A Supply Breaker (AI-40A).      4)Ensure Inverter C load is less than 62.5 amps.
g.IF restoration from short-term bypass of Inverter C (EE-8K) is desired,THEN perform the following:1)Verify reverse transfer light is on.      2)Verify EE-8K-S1, Inverter C, EE-8K Manual Transfer Switch, is inthe INVERTER position.      3)Ensure sync loss light is off.      4)Push the forward transfer button.      5)Verify reverse transfer light is off.      6)Verify forward transfer light is on.      7)Ensure EE-8K-CB3, Inverter C EE-8K Vent Fans Breaker is closed.
CContinuous UseFORT CALHOUN STATIONOI-EE-4OPERATING INSTRUCTIONPAGE 12 OF 105Attachment 1 - Inverter A (EE-8H) Operation PROCEDURE (continued)()INITIALSR30CAUTIONAdjustments to inverter output frequency or output voltage shall onlybe made by Electrical Maintenance. Guidance from EM-PM-EX-0800 may be referenced as necessary.6.g8)Verify Inverter C Output Frequency is between 59.4 and 60.6 Hz(normal 60.0 Hz).      9)Verify Inverter C Output Voltage is between 117.6 and 122.4 VoltsAC (normal 120.0 Volts AC).
h.IF desired,THEN open EE-8H-CB2, Inverter A, EE-8H AC Output Breaker.              i.IF desired,THEN open EE-8H-CB1, Inverter A, EE-8H DC Input Breaker.              j.IF desired,THEN open MCC-3B1-E3R, EE-4N Inverter A Bypass Transformer Breaker.
NOTEUpon loss of an Instrument Bus implement AOP-16, Loss of Instrument Bus Power.7.IF hot bus transfer of Instrument Buses A and A1 feed back to normalalignment is desired, THEN perform the following:a.Ensure the following plant conditions are met:
!Reactor Coolant System temperature is less than 300°F
!All Fuel movement has been secured
!All core alterations have been secured
!No work is being performed, that requires electrical power fromAI-57, on the Control Element Drive Mechanisms (CEDM)
Shift Mgr CContinuous UseFORT CALHOUN STATIONOI-EE-4OPERATING INSTRUCTIONPAGE 13 OF 105Attachment 1 - Inverter A (EE-8H) Operation PROCEDURE (continued)()INITIALSR307b.Verify that there are no hard grounds on either Instrument Bus A orInstrument Bus C.              CAUTIONMaximum Inverter load is 62.5 amps. Non-essential loading may need to be reduced to prevent an overload condition following the load transfer.c.Transfer Instrument Inverter A to the bypass source by performing thefollowing:
NOTEInstrument Bus voltage may be lower than normal 117.6 - 122.4Volts AC when being fed from a bypass transformer.1)Ensure MCC-3B1-E3R, EE-4N Inverter A Bypass Transformer Breaker, is closed.      2)Verify sync loss light is off.      3)Push the reverse transfer button.      4)Verify sync loss light is off.      5)Verify reverse transfer light is on.
d.Transfer the load on Instrument Inverter C to the bypass source byperforming the following:
NOTEInstrument Bus voltage may be lower than normal 117.6 - 122.4Volts AC when being fed from a bypass transformer.1)Ensure MCC-3C1-A4R, EE-4Q Inverter C Bypass Transformer, Breaker is closed.      2)Verify sync loss light is off.
CContinuous UseFORT CALHOUN STATIONOI-EE-4OPERATING INSTRUCTIONPAGE 14 OF 105Attachment 1 - Inverter A (EE-8H) Operation PROCEDURE (continued)()INITIALSR307.d3)Push the reverse transfer button.      4)Verify sync loss light is off.      5)Verify reverse transfer light is on.
e.Hot bus transfer the Instrument Bus A loads connected to InstrumentBus C from Instrument Bus C to Instrument Bus A by positioning thefollowing breakers in the sequence listed:1)Close I-BUS-IA-1, Instrument Bus A Supply Breaker (AI-40A).      2)Open I-BUS-AC-2, Instrument Bus C Tie Breaker (AI-40C).      3)Open I-BUS-AC-1, Instrument Bus A Tie Breaker (AI-40A).
f.WHEN restoration from short-term bypass of Inverter A (EE-8H) isdesired, THEN perform the following:1)Verify reverse transfer light is on.      2)Verify EE-8H-S1, Inverter A, EE-8H Manual Transfer Switch, is inthe INVERTER position.      3)Ensure sync loss light is off.      4)Push the forward transfer button.      5)Verify reverse transfer light is off.      6)Verify forward transfer light is on.      7)Ensure EE-8H-CB3, Inverter A EE-8H Vent Fans Breaker is closed.
CContinuous UseFORT CALHOUN STATIONOI-EE-4OPERATING INSTRUCTIONPAGE 15 OF 105Attachment 1 - Inverter A (EE-8H) Operation PROCEDURE (continued)()INITIALSR30CAUTIONAdjustments to inverter output frequency or output voltage shallonly be made by Electrical Maintenance. Guidance from EM-PM-EX-0800 may be referenced as necessary.7.f8)Verify Inverter A Output Frequency is between 59.4 and 60.6 Hz(normal 60.0 Hz).      9)Verify Inverter A Output Voltage is between 117.6 and 122.4 VoltsAC (normal 120.0 Volts AC).
g.IF restoration from short-term bypass of Inverter C (EE-8K) is desired,THEN perform the following:1)Verify reverse transfer light is on.      2)Verify EE-8K-S1, Inverter C, EE-8K Manual Transfer Switch, is inthe INVERTER position.      3)Ensure sync loss light is off.      4)Push the forward transfer button.      5)Verify reverse transfer light is off.      6)Verify forward transfer light is on.      7)Ensure EE-8K-CB3, Inverter C EE-8K Vent Fans Breaker is closed.      CAUTIONAdjustments to inverter output frequency or output voltage shall only be made by Electrical Maintenance. Guidance from EM-PM-EX-0800 may be referenced as necessary.8)Verify Inverter C Output Frequency is between 59.4 and 60.6 Hz(normal 60.0 Hz).
CContinuous UseFORT CALHOUN STATIONOI-EE-4OPERATING INSTRUCTIONPAGE 16 OF 105Attachment 1 - Inverter A (EE-8H) Operation PROCEDURE (continued)()INITIALSR307.g9)Verify Inverter C Output Voltage is between 117.6 and 122.4 VoltsAC (normal 120.0 Volts AC).
h.Remove the block from the PPLS/BLOCK A relay (device #817), locatedbehind CB-3.
EM Ind Verif8.IF dead bus transfer of instrument Buses A and A1 back to normalalignment is desired, THEN perform the following:a.Ensure no grounds are present on Instrument Bus A.      b.Ensure I-BUS-IA-1, Instrument Bus A Supply Breaker, is open (AI-40A).      c.Ensure EE-8H-CB1, Inverter A, EE-8H DC Input Breaker is open.      d.Ensure EE-8H-S1, Inverter A, EE-8H Manual Transfer Switch, is inBYPASS.      e.Ensure MCC-3B1-E3R, EE-4N Inverter A Bypass Transformer, Breakeris closed.      f.Remove all loads from Buses A and A1.      g.Close EE-8H-CB2, Inverter A, EE-8H AC Output Breaker.      h.Open I-BUS-AC-2, Instrument Bus C Tie Breaker (AI-40C).      i.Open I-BUS-AC-1, Instrument Bus A Tie Breaker (AC-40A).      j.Close I-BUS-IA-1, Instrument Bus A Supply Breaker (AI-40A).
CContinuous UseFORT CALHOUN STATIONOI-EE-4OPERATING INSTRUCTIONPAGE 17 OF 105Attachment 1 - Inverter A (EE-8H) Operation PROCEDURE (continued)()INITIALSR30 NOTEIf desired then startup inverter A otherwise N/A all remaining steps.8k.Ensure EE-8F-CB24, EE-8H Inverter A, Breaker on DC Bus No. 1 isclosed.
NOTEThe following steps will place Inverter A in service.l.Momentarily push the precharge button on Inverter A, then waitten (10) seconds.      m.Close EE-8H-CB1, Inverter A, EE-8H DC Input Breaker.      n.Verify sync loss light is on.      o.Verify reverse transfer light is on.      p.Place EE-8H-S1, Inverter A, EE-8H Manual Transfer Switch, in theINVERTER position.      q.Ensure sync loss light is off.      r.Push the forward transfer button.      s.Verify reverse transfer light is off.      t.Verify forward transfer light is on.      u.Ensure EE-8H-CB3, Inverter A EE-8H Vent  Fans Breaker, is closed.
CContinuous UseFORT CALHOUN STATIONOI-EE-4OPERATING INSTRUCTIONPAGE 18 OF 105Attachment 1 - Inverter A (EE-8H) Operation PROCEDURE (continued)()INITIALSR30CAUTIONAdjustments to inverter output frequency or output voltage shall only bemade by Electrical Maintenance. Guidance from EM-PM-EX-0800 may be referenced as necessary.8v.Verify Inverter A Output Frequency is between 59.4 and 60.6 Hz(normal 60.0 Hz).      w.Verify Inverter A Output Voltage is between 117.6 and 122.4 Volts AC(normal 120.0 Volts AC).
x.Once Inverter A is operable and has been returned to its bus (i.e.forward transferred) declare Inverter A (EE-8H) operable.
SM/CRS9.IF Inverter A (EE-8H) is in service AND removal from operation of Bypasstransformer is desired, THEN perform the following: a.IF Clutch Power Supply is being fed from Instrument Bus A,THEN transfer Clutch power per OI-EE-4, Attachment 7.      b.Ensure sync loss light is off.      c.Verify reverse transfer light is off.      d.Verify forward transfer light is on.      e.Inform the Control Room that INVERTER A TROUBLE (CB-20, A15, A-6) will alarm when MCC-3B1-E3R, EE-4N Inverter ABypass Transformer breaker is opened.      f.Open breaker MCC-3B1-E3R.      g.Verify Sync loss light is on.
CContinuous UseFORT CALHOUN STATIONOI-EE-4OPERATING INSTRUCTIONPAGE 19 OF 105Attachment 1 - Inverter A (EE-8H) Operation PROCEDURE (continued)()INITIALSR30CAUTIONAdjustments to inverter output frequency or output voltage shall only bemade by Electrical Maintenance. Guidance from EM-PM-EX-0800 may be referenced as necessary.9h.Verify Inverter A Output Frequency is between 59.4 and 60.6 Hz(normal 60.0 Hz).      i.Verify Inverter A Output Voltage is between 117.6 and 122.4 Volts AC(normal 120.0 Volts AC).      10.IF Inverter A (EE-8H) is in service AND return to service of Bypasstransformer EE-4N is desired, THEN perform the following:  a.Ensure the following:1)Inverter A is in operation.      2)MCC-3B1-E3R, EE-4N Inverter A Bypass Transformer breaker isopen.      3)Inverter A sync loss light is on.      b.Inform the Control Room INVERTER A TROUBLE (CB-20, A15, A-6)alarm will clear when break er MCC-3B1-E3R, breaker is closed.      c.Close breaker MCC-3B1-E3R.      d.Verify the sync loss light is off at the Inverter.      e.Verify with Control Room that INVERTER A TROUBLE (CB-20, A15, A-6) alarm is clear.      f.Verify reverse transfer light is off.      g.Verify forward transfer light is on.
CContinuous UseFORT CALHOUN STATIONOI-EE-4OPERATING INSTRUCTIONPAGE 20 OF 105Attachment 1 - Inverter A (EE-8H) Operation PROCEDURE (continued)()INITIALSR30CAUTIONAdjustments to inverter output frequency or output voltage shall only bemade by Electrical Maintenance. Guidance from EM-PM-EX-0800 may be referenced as necessary.10h.Verify Inverter A Output Frequency is between 59.4 and 60.6 Hz(normal 60.0 Hz).      i.Verify Inverter A Output Voltage is between 117.6 and 122.4 Volts AC(normal 120.0 Volts AC).
Completed by                                                                        Date/Time                  /
CContinuous UseFORT CALHOUN STATIONOI-EE-4OPERATING INSTRUCTIONPAGE 91 OF 105R30Attachment 7 - Clutch Power SuppliesPREREQUISITES ()INITIALS1.Procedure Revision VerificationRevision No.
Date:
2.125 VDC Bus 1 (EE-8F) and Bus 2 (EE-8G) are in service per OI-EE-3.              3.IF RCS temperature is greater than 300°F,THEN verify Checklist OI-EE-4-CL-A has been completed.
PROCEDURECAUTIONS1.Only one power supply transfer switch may be transferred at a time.2.This procedure may cause a Reactor Trip if performed incorrectly.1.IF transferring Clutch Power Supply to 120 Volt AC Instrument Bus A,THEN perform the following:a.Ensure Instrument Bus A is not cross-tied to Instrument Bus C.      b.Bypass Inverter A per Attachment 1.      c.Verify Clutch Power Supply breaker RPS/CB-CD is closed.
NOTEBreaker RPS/CB-AB may go to the trip free position when Clutch PowerSupply Transfer Switch RPS/TS-AB is placed in the Bus A position due to momentary undervoltage.d.Place Clutch Power Supply Transfer Switch RPS/TS-AB in theInstrument Bus A position #1.      e.Verify Clutch Power Supply Breaker RPS/CB-AB is closed.      f.IF Breaker RPS/CB-AB is in the trip free position,THEN reset and close Breaker RPS/CB-AB.
CContinuous UseFORT CALHOUN STATIONOI-EE-4OPERATING INSTRUCTIONPAGE 92 OF 105Attachment 7 - Clutch Power Supplies PROCEDURE (continued)()INITIALSR301g.Verify all four Clutch Power Supply ammeters read upscale.      h.Verify proper indicating lights in Clutch Power Supply Cabinet areenergized.      i.Place Inverter A in normal operation per Attachment 1.
CAUTIONS1.Only one power supply transfer switch may be transferred at a time.2.This procedure may cause a Reactor Trip if performed incorrectly..2.IF transferring Clutch Power Supply to 120 Volt AC Instrument Bus B,THEN perform the following:a.Ensure Instrument Bus B is not cross-tied to Instrument Bus D.
b.Bypass Inverter B per Attachment 2.      c.Verify Clutch Power Supply Breaker RPS/CB-CD is closed.
NOTEBreaker RPS/CB-AB may go to the trip free position when Clutch PowerSupply Transfer Switch RPS/TS-AB is placed in the Bus B position due to momentary undervoltage.d.Place Clutch Power Supply Transfer Switch RPS/TS-AB in theInstrument Bus B position #2.      e.Verify Clutch Power Supply Breaker RPS/CB-AB is closed.      f.IF Breaker RPS/CB-AB is in the trip free position,THEN reset and close Breaker RPS/CB-AB.      g.Verify all four Clutch Power Supply ammeters read upscale.
CContinuous UseFORT CALHOUN STATIONOI-EE-4OPERATING INSTRUCTIONPAGE 93 OF 105Attachment 7 - Clutch Power Supplies PROCEDURE (continued)()INITIALSR302h.Verify proper indicating lights in Clutch Power Supply Cabinet areenergized.      i.Place Inverter B in normal operation per Attachment 2.
CAUTIONS1.Only one power supply transfer switch may be transferred at a time.2.This procedure may cause a Reactor Trip if performed incorrectly..3.IF transferring Clutch Power Supply to 120 Volt AC Instrument Bus C,THEN perform the following:a.Ensure Instrument Bus C is not cross-tied to Instrument Bus A.
b.Bypass Inverter C per Attachment 3.      c.Verify Clutch Power Supply Breaker RPS/CB-AB is closed.
NOTEBreaker RPS/CB-CD may go to the trip free position when Clutch PowerSupply Transfer Switch RPS/TS-CD is placed in the Bus C position due to momentary undervoltage.d.Place Clutch Power Supply Transfer Switch RPS/TS-CD in theInstrument Bus C position #3.      e.Verify Clutch Power Supply breaker RPS/CB-CD is closed.      f.IF Breaker RPS/CB-CD is in the trip free position,THEN reset and close Breaker RPS/CB-CD.      g.Verify all four Clutch Power Supply ammeters read upscale.      h.Verify proper indicating lights in Clutch Power Supply Cabinet areenergized.
CContinuous UseFORT CALHOUN STATIONOI-EE-4OPERATING INSTRUCTIONPAGE 94 OF 105Attachment 7 - Clutch Power Supplies PROCEDURE (continued)()INITIALSR303i.Place Inverter C in normal operation per Attachment 3.
CAUTIONS1.Only one power supply transfer switch may be transferred at a time.2.This procedure may cause a Reactor Trip if performed incorrectly..4.IF transferring Clutch Power Supply to 120 Volt AC Instrument Bus D,THEN perform the following:a.Ensure Instrument Bus D is not cross-tied to Instrument Bus B.
b.Bypass Inverter D per Attachment 4.      c.Verify Clutch Power Supply breaker RPS/CB-AB is closed.
NOTEBreaker RPS/CB-CD may go to the trip free position when Clutch PowerSupply Transfer Switch RPS/TS-CD is placed in the Bus D position due to momentary undervoltage.d.Place Clutch Power Supply Transfer Switch RPS/TS-CD in theInstrument Bus D position #4.
e.Verify Clutch Power Supply breaker RPS/CB-CD is closed.      f.IF Breaker RPS/CB-CD is in the trip free position,THEN reset and close Breaker RPS/CB-CD.      g.Verify all four Clutch Power Supply ammeters read upscale.      h.Verify proper indicating lights in Clutch Power Supply Cabinet areenergized.      i.Place Inverter D in normal operation per Attachment 4.
Completed by                                                                                            Date/Time            /
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE
 
JPM No: JPM-0387
 
JPM Title: AFW Functional Te st of Circuits and Components Page 1 of 9
 
Location: Simulator    Approximate Time: 25 minutes Actual Time: _________________
 
Reference(s): OP-ST-AFW-3007  R12 NRC K/A  061000 K4.02  (RO 4.5 / SRO 4.6)
 
JPM Prepared by: Jerry Koske Date: 05/05/05    JPM Reviewed by:  Date:
JPM Approved by:  Date: 
 
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE
 
JPM No: JPM-0387
 
JPM Title: AFW Functional Te st of Circuits and Components Page 2 of 9
 
Operators' Name
: _____________________  Employee # ______________
 
All Critical Steps (shaded) must be per formed or simulated in accordance with the standards contained in this JPM
 
The Operator's performance wa s evaluated as (circle one):
 
SATISFACTORY  UNSATISFACTORY
 
Evaluator's Signature:
________________________
_____  Date: __________
 
Reason, if unsatisfactory:
 
Tools & Equipment: AI-66 Keys
 
Safety Considerations: None
 
Comments: 
 
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE
 
JPM No: JPM-0387
 
JPM Title: AFW Functional Te st of Circuits and Components Page 3 of 9 INITIATING CUE: The plant is in cold shutdown. You have been directed to perform a portion of A ttachment 1 of OP-ST-AFW-3007, "Auxiliary Feedwater Functional Test of Circuits and Components" starting wi th step 3 and ending at step 11.
 
All prerequisites are met. The keys required for this test have been placed in the appropriate switches. The required jumpers and blocks have been placed on relay A1/RC-2A/AFWS
 
START Critical Steps shown in gray
 
STEP ELEMENT STANDARD 1 (3.1) Reset HCV-1107A AI-66A HCV-1107A CS to RESET
 
then to AUTO
 
2 (3.2) Reset HCV-1107B AI-66A HCV-1107B CS to RESET
 
then to AUTO
 
3 (3.3) Place FW-6 recirculation valve, FCV-1368 in auto
 
AI-66A FCV-1368 CS in AUTO 4 (3.4) Place S/G RC-2A Chan "A" auto Sig Override SW AFW
 
Pumps FW-6/FW-10 control
 
switch to normal
 
AI-66A S/G RC-2A Chan "A" auto Sig
 
Override SW AFW Pumps
 
FW-6/FW-10 control switch to
 
NORMAL 5 (3.5) Place S/G RC-2B Chan "A" auto Sig Override SW AFW
 
Pumps FW-6/FW-10 control
 
switch to normal
 
AI-66A S/G RC-2B Chan "A" auto Sig
 
Override SW AFW Pumps
 
FW-6/FW-10 control switch to
 
NORMAL
 
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE
 
JPM No: JPM-0387
 
JPM Title: AFW Functional Te st of Circuits and Components Page 4 of 9  STEP ELEMENT STANDARD 6 (3.6) Place S/G RC-2A Chan A Auto Sig Override Relay Test SW to
 
NORM AI-66A S/G RC-2A Chan A Auto Sig
 
Override Relay Test SW to
 
NORM 7 (3.7) Place S/G RC-2B Chan A Auto Sig Override Relay Test SW to
 
NORM AI-66A S/G RC-2B Chan A Auto Sig
 
Override Relay Test SW to
 
NORM 8 (3.8) Place Chan A AFW Auto Sig Overide S/G Feed Valves
 
switch to Normal
 
AI-66A Chan A AFW Auto Sig Overide
 
S/G Feed Valves switch to
 
NORMAL 9 (4.1) Reset HCV-1108A AI-66B HCV-1108A CS to RESET
 
then to AUTO
 
10 (4.2) Reset HCV-1108B AI-66B HCV-1108B CS to RESET
 
then to AUTO
 
11 (4.3) Reset YCV-1045 AI-66B YCV-1045 CS to RESET then
 
to AUTO 12 (4.4) Place FW-10 Auto Start Relay Test Switch to Normal
 
AI-66B  FW-10 Auto Start Relay Test
 
Switch to NORMAL
 
13 (4.5) Place FW-10 recirculation valve, FCV-1369, in auto
 
AI-66B  FW-10 recirculation valve, FCV-1369, in AUTO
 
14 (4.6)
Place YCV-1045A Isolation valve override switch to normal
 
AI-66B  YCV-1045A Isolation valve
 
override switch to NORMAL
 
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE
 
JPM No: JPM-0387
 
JPM Title: AFW Functional Te st of Circuits and Components Page 5 of 9  STEP ELEMENT STANDARD 15 (4.7) Place YCV-1045A CS to close then normal
 
AI-66B  YCV-1045A CS to CLOSE
 
then  to NORMAL
 
16 (4.8) Place YCV-1045B Isolation valve override switch to normal
 
AI-66B  YCV-1045B Isolation valve
 
override switch to NORMAL
 
17 (4.9) Place YCV-1045B CS to close then normal
 
AI-66B  YCV-1045B CS to close then
 
NORMAL 18 (4.10) Place S/G RC-2A Chan "B" auto Sig Override SW AFW
 
Pumps FW-6/FW-10 control
 
switch to normal
 
AI-66B  S/G RC-2A Chan "B" auto Sig
 
Override SW AFW Pumps
 
FW-6/FW-10 control switch to
 
NORMAL 19 (4.11) Place S/G RC-2B Chan "B" auto Sig Override SW AFW
 
Pumps FW-6/FW-10 control
 
switch to normal
 
AI-66B  S/G RC-2B Chan "B" auto Sig
 
Override SW AFW Pumps
 
FW-6/FW-10 control switch to
 
NORMAL 20 (4.12) Place S/G RC-2A Chan B Auto Sig Override Relay Test SW to
 
NORM AI-66B  S/G RC-2A Chan B Auto Sig
 
Override Relay Test SW to
 
NORM 21 (4.13) Place S/G RC-2B Chan B Auto Sig Override Relay Test SW to
 
NORM AI-66B  S/G RC-2B Chan B Auto Sig
 
Override Relay Test SW to
 
NORM 22 (4.14) Place Chan B AFW Auto Sig Overide S/G Feed Valves
 
switch to Normal
 
AI-66B  Chan B AFW Auto Sig Overide
 
S/G Feed Valves switch to
 
NORMAL
 
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE
 
JPM No: JPM-0387
 
JPM Title: AFW Functional Te st of Circuits and Components Page 6 of 9  STEP ELEMENT STANDARD 23 (5) Place FW-6 control switch in AFTER STOP CB-10 HC-1367, FW-6 CS [laced in AFTER STOP (Green flag) 24 (6) Initiate and AFW actuation from AI-66A  AI-66A Place and HOLD S/G RC-2A Chan A Auto Sig Override Relay Test Switch in TEST 25 (7) Verify actions/indications
 
HCV-1107A and B open  FW-6 starts YCV-1045 opens  YCV-1045A and B open  AFW flow to RC-2A AFWS STEAM GEN RC-2A CHANNEL A ACTUATED alarm  AFWS RC-2A CH A MATRIX TS-A/RC-2A/AFWS TEST
 
SWITCH OFF NORMAL
 
alarm  S/G RC-2A Chan A light  S/G RC-2A Chan A1 light  AI-66A While holding switch in
 
TEST,verify:  RED lights lit  RED and WHITE lights lit  RED light lit  RED lights lit  Flow indicated on FI-1109-1  Annuciator A66A, 44 lit Annunciator A66A, 24 lit
 
AMBER light lit  AMBER light lit 26 (8)  Record values: CUE: Provide flows from CB-10 FI-1109 = 295 gpm
 
FW-6 amp = 34 amps
 
FI-1368 = 300 gpm
 
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE
 
JPM No: JPM-0387
 
JPM Title: AFW Functional Te st of Circuits and Components Page 7 of 9  STEP ELEMENT STANDARD AI-66  Reads and records flow from
 
FI-1109-1 (should read approximately 300 gpm)
 
27 (8.1) Verifies flow is al least 200 gpm for ISI requirement Initials procedure step 8.1 29 (9) Place S/G RC-2A Chan A auto sig Override relay test SW to
 
NORM AI-66A S/G RC-2A Chan A auto sig Override relay test SW to
 
NORM 30 (10.1)
Place FW-6 CS in pull-to-lock CB-10 HC-1367, FW-6 CS placed in PULL-TO-LOCK 31 (10.2)
Reset HCV-1107A AI-66A HCV-1107A CS to RESET then to AUTO 32 (10.3)
Reset HCV-1107B AI-66A HCV-1107B CS to RESET then to AUTO 33 (10.4)
Reset YCV-1045 AI-66A YCV-1045 CS to RESET then to CLOSE then to RESET then to AUTO  34 (10.5)
Reset YCV-1045A AI-66A YCV-1045A CS to CLOSE then to NORMAL 35 (10.6)
Reset YCV-1045B AI-66A YCV-1045B CS to CLOSE then to NORMAL 36 (10.7) Verify AFWS STEAM GEN RC-2A CHANNEL A ACTUATED AI-66A Annunciator A66A, 44 OFF Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE
 
JPM No: JPM-0387
 
JPM Title: AFW Functional Te st of Circuits and Components Page 8 of 9  STEP ELEMENT STANDARD alarm is clear 37 (10.8) Verify AFWS RC-2A CH A MATRIX TS-A/RC-2A/AFWS
 
TEST SWITCH OFF NORMAL
 
alarm is clear
 
AI-66A Annunciator A66A, 24 OFF 38 (10.9) Verify S/G RC-2A Chan A amber light is off
 
AI-66A S/G RC-2A Chan A amber
 
light is OFF
 
39 (10.10) Verify S/G RC-2A Chan A1 amber light is off
 
AI-66A S/G RC-2A Chan A1 amber
 
light is OFF
 
CUE: Electricians have removed the jumpers and
 
blocks from relay A1/RC-
 
2A/AFWS
 
Termination Criteria:
OP-ST-AFW-3007, Attachment 1, has been
 
completed through step 11
 
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE
 
JPM No: JPM-0387 Page 9 of 9
 
INITIATING CUE: The plant is in cold shutdown. You have been directed to perform a portion of A ttachment 1 of OP-ST-AFW-3007, "Auxiliary Feedwater Functional Test of Circuits and Components" starting wi th step 3 and ending at step 11.
 
All prerequisites are met. The keys required for this test have been placed in the appropriate switches. The required jumpers and blocks have been placed on relay A1/RC-2A/AFWS
 
START
 
WP12 Fort Calhoun Station Unit No. 1 OP-ST-AFW-3007 SURVEILLANCE TESTTitle:AUXILIARY FEEDWATER FUNCTIONAL TEST OF CIRCUITS AND COMPONENTS
 
FC-68 Number:EC 34913Reason for Change:Add power supplies Requestor:Christopher Verdoni Preparer:Daniel A HochsteinCorrection (a):Page 1 (03-08-05)ISSUED:    09-09-04  3:00 pmR12 FORT CALHOUN STATIONOP-ST-AFW-3007SURVEILLANCE TESTPAGE 1 OF 32 R12 AUXILIARY FEEDWATER FUNCTIONAL TEST OF CIRCUITS AND COMPONENTS SAFETY RELATED1.PURPOSE1.1This test is to verify operability of FW-6 , through its normal flow paths, in order to satisfy the requirements of Technical Spec ifications 2.5(1), 2.5(2) and 3.9(5).1.2This test shall be performed each Cold S hutdown in accordance with the Fort Calhoun Station (FCS) Inservice Inspection (ISI) Program Plan.1.3This test verifies the operability of Aux iliary Feedwater Check Valves FW-163, FW-164 and FW-173 as required in USAR 4.5.6.5.1.4The test satisfies the requirements of Technical Specifications 3.1, Table 3-2 Item 23b(1) and 24a, for functional testing of Auxiliary Feedwater initiation circuits each refueling.2.REFERENCES/COMMITMENT DOCUMENTS2.1Technical Specifications
!2.5, Steam and Feedwater Systems
!2.15, Instrumentati on and Control Systems
!3.1, Table 3-2:  Minimum Frequencies for Checks, Calibrations and Testing of Engineered Safety Features, Instrumentation and Controls
!3.9, Auxiliary Feedwater System2.2USAR 4.5.6.5:  In-service Inspecti on of ASME Code Class 1, Class 2, and Class 3 Components2.3Fort Calhoun Station ISI Program Plan3.DEFINITIONS None4.EQUIPMENT LIST4.1Tools!  Electrical Jumpers (2)
!  Mechanical Blocks (2) (Suitable for prev enting HFA relay contact from closing.)
!  Digital Multimeter (1)
FORT CALHOUN STATIONOP-ST-AFW-3007SURVEILLANCE TESTPAGE 2 OF 32 R125.PRECAUTIONS AND LIMITATIONS5.1All anomalies and deficiencies shall be r eported immediately to the immediate Supervisor and the Shift Manager, and noted on the Comment Sheet. An immediate check shall be made to verify Limiting C onditions for Operation, per Technical Specifications, have not been exceeded.5.2The System Engineer shall be notified within 24 hours of the completion of this test, of any marginal, unexpected or unacceptable results.5.3If this test cannot be completed by the end of shift, and will not be continued by thenext shift, the loop must be placed in a conditi on as directed by the Shift Manager. All actions taken for temporarily stopping and for resuming the test shall be documented
 
in detail (including SO-O-25 as applicable) on the Comment Sheet.5.4The following may alarm during this Surveillance Test.
!AFWS RC-2A CH A MATRIX TS-A/RC-2A/AFWS TEST SWITCH OFF NORMAL (AI-66A, A66A, 24)
!AFWS RC-2B CH A MATRIX TS-A/RC-2B/AFWS TEST SWITCH OFF NORMAL (AI-66A, A66A, 25)
!AFWS STEAM GEN RC-2A CHANNEL A ACTUATED (AI-66A, A66A, 44)
!AFWS STEAM GEN RC-2B CHANNEL A ACTUATED (AI-66A, A66A, 45)
!AFWS RC-2A CH B MATRIX TS-B/RC-2A/AFWS TEST SWITCH OFF NORMAL (AI-65B, A65B, 21)
!AFWS RC-2B CH B MATRIX TS-B/RC-2B/AFWS TEST SWITCH OFF NORMAL (AI-65B, A65B, 22)
!AFWS STEAM GEN RC-2A CHANNEL B ACTUATED (AI-65B, A65B, 41)
!AFWS STEAM GEN RC-2B CHANNEL B ACTUATED (AI-65B, A65B, 42)
!FW-10 TURBINE DRIVEN FEEDWATER PUMP TROUBLE (AI-66B, A66B,18)6.PREREQUISITES6.1Procedure Revision Verification.
Revision No.
INITIALS/DATE
            /          6.2A Lead Person qualified to a minimum of Electrician category E08Cis available for the performance of this test.              /
EM Supv/ Crew
 
Leader6.3There is sufficient volume ava ilable in the Steam Generators toaccept AFW flow.              /
FORT CALHOUN STATIONOP-ST-AFW-3007SURVEILLANCE TESTPAGE 3 OF 32 R126.4There is sufficient volume in the Emergency Feedwater StorageTank to support operation of FW-6.              /          6.5Electrical power is available to FW-6 via 4160 V Bus 1A3.              /          6.6Ensure that BKR 1A3-16, Breaker Unit Auxiliary Feedwater PumpFW-6, is properly racked up.              /          6.7Ensure the 69 Permissive Switch is red flagged with Red or Greenlight indication and Amber light lit.              /
NOTE: During the performance of this test, YCV-1045A and YCV-1045B are actuated open.6.8Verify steam is not available to FW-10.              /          6.9Applicable portions of OI-AFW-1-CL-A and OI-AFW-1-CL-B arecompleted.              /        6.10A prejob briefing has been conducted prior to the start of this test.                /          6.11No other test is in progress whic h could potentially affect this test, or if this test were performed, could have an effect on that test.              /        6.12The Shift Manager has authorized the performance of this test.
Shift Manager Date/Time              /          7.PROCEDURE NOTE:  Step 7.1 can be performed at anytime and repeated as necessary.7.1IF this Surveillance Test is turned over, a prejob briefing must beconducted prior to the continuation of this test.              /          7.2Perform Attachment 1 as required.
ATTACHMENT PAGE 1 - Aux Feedwater Functional Test of Circuits/Components.....5              /
FORT CALHOUN STATIONOP-ST-AFW-3007SURVEILLANCE TESTPAGE 4 OF 32 R128.RESTORATION8.1Shift Manager has been notified this test has been completed.
Shift Manager Date/Time              /          9.ACCEPTANCE CRITERIA9.1All components and indications functioned as described in the body of this procedure.10.TEST RECORD10.1This entire procedure11.PERFORMANCE AND REVIEW11.1Test data shall be evaluated by the Shift Technical Advisor (STA) and reviewed by the Shift Manager for acceptability within 24 hour s of the completion of this test.
Evaluated by Date/Time                /
STA Signature Reviewed by Date/Time                /
Shift Manager11.2The ISI Coordinator is responsible for re viewing the test for compliance with the FCS ISI Program Plan. This test has been reviewed and found acceptable or the
 
deficiencies have been noted in the Comment Sheet.
ISI Coordinator                                                                           
                /
Signature                                        Date        Time11.3The System Engineer is responsible for re viewing this Surveillance Test. Test data has been evaluated and found to be acceptable, or deficiencies identified and actions taken have been noted on the Comment Sheet.
System Engineer                                                                       
                /
Signature                            Date        Time
 
FORT CALHOUN STATIONOP-ST-AFW-3007SURVEILLANCE TESTPAGE 5 OF 32 R12 Attachment 1 - Aux Feedwater Func tional Test of Circuits/Components PROCEDURE () INITIALS 1.Obtain appropriate keys, as requir ed for the manipulation of AI-66A andAI-66B switches, from the Shift Managers key lockbox.              2.Place the following jumpers and blocks on relay A1/RC-2A/AFWS (Device 25) in AI-66A:
!Jumper Contact 1-2 EM
 
Con Verif!Block Open Contact 3-4 EM
 
Con Verif!Jumper Contact 5-6 EM
 
Con Verif!Block Open Contact 11-12 EM
 
Con Verif3.Align AI-66A as follows:3.1Place HCV-1107A, Aux FW to S/G RC-2A Isolation Valve Inbd,control switch to RESET, then to AUTO.              3.2Place HCV-1107B, Aux FW to S/G RC-2A Isolation Valve Outbdcontrol switch to RESET, then to AUTO.              3.3Place FCV-1368, Aux FW Pump FW-6 Recirculation Valve control switch to AUTO.
3.4Place S/G RC-2A Chan "A"  Auto Sig Override SW AFW PumpsFW-6/FW-10 control switch to NORMAL.                  - Aux Feedwater Func tional Test of Circuits/Components PROCEDURE (continued) () INITIALSFORT CALHOUN STATIONOP-ST-AFW-3007SURVEILLANCE TESTPAGE 6 OF 32 R123.5Place S/G RC-2B Chan A Auto Sig Override SW AFW PumpsFW-6/FW-10 control switch to NORMAL.              3.6Place S/G RC-2A Chan A Auto Sig Override Relay Test SW toNORM.              3.7Place S/G RC-2B Chan A Auto Sig Override Relay Test SW toNORM.              3.8Place Chan A AFW Auto Sig Override S/G Feed Valves switch toNORMAL.              4.Align AI-66B as follows:4.1Place HCV-1108A, Aux FW to S/G RC-2B Isolation Valve Inbdcontrol switch to RESET, then to AUTO.              4.2Place HCV-1108B, Aux FW to S/G RC-2B Isolation Valve Outbdcontrol switch to RESET, then to AUTO.              4.3Place YCV-1045, STM to Pump FW-10 Control Valve controlswitch to RESET, then to AUTO.              4.4Place Pump FW-10 Auto Start Relay Test Switch to NORMAL.              4.5Place FCV-1369, Aux FW Pump FW
-10 Recirculation Valve controlswitch to AUTO.              4.6Place YCV-1045A, Isolation Valve Override switch to NORMAL.              4.7Place YCV-1045A, S/G RC-2A STM to FW-10 HDR A IsolationValve control switch to CLOSE, then to NORMAL.              4.8Place YCV-1045B Isolation Valve Override switch to NORMAL.              4.9Place YCV-1045B, S/G RC-2B STM to FW-10 HDR B IsolationValve control switch to CLOSE, then to NORMAL.              4.10Place S/G RC-2A Chan B Auto Sig Override SW AFW PumpsFW-6/FW-10 switch to NORMAL.                  - Aux Feedwater Func tional Test of Circuits/Components PROCEDURE (continued) () INITIALSFORT CALHOUN STATIONOP-ST-AFW-3007SURVEILLANCE TESTPAGE 7 OF 32 R124.11Place S/G RC-2B Chan B AFWS Auto Sig Override SW AFWPumps FW-6/FW-10 switch to NORMAL.              4.12Place S/G RC-2A Chan B Auto Sig Override Relay Test SW toNORM.              4.13Place S/G RC-2B Chan B Auto Sig Override Relay Test SW toNORM.              4.14Place Chan B AFW Auto Sig Override SG Feed Valves switch toNORMAL.              5.Place HC-1367, FW-6 Control Switch to AFTER STOP. (CB-10)
NOTE:  The test switch must be held in the test position until component status is verified.6.Initiate an AFW actuation from AI-66A by placing and holding the S/G RC-2A Chan A Auto Sig Override Relay Test Switch to TEST.              7.Verify the following action/indications occur:
!HCV-1107A and B open.
!FW-6 starts.
!YCV-1045 opens.
!YCV-1045A and B open.
!AFW flow to RC-2A is indicated on FI-1109-1.
!AFWS STEAM GEN. RC-2A CHANNEL A ACTUATED (AI-66A, A66A, 44) is in alarm.
!AFWS RC-2A CH A MATRIX TS-A/RC-2A/AFWS TEST SWITCH
 
OFF NORMAL (AI-66A, A66A, 24) is in alarm
!S/G RC-2A Chan A amber light is on.
!S/G RC-2A Chan A1 amber light is on.
8.Record following values:
 
gpm gpm FI-1109 (CB-10)            FI-1109-1 (AI-66)
 
gpm FW-6 Amps (CB-10)      FI-1368 (CB-10)
                  - Aux Feedwater Func tional Test of Circuits/Components PROCEDURE (continued) () INITIALSFORT CALHOUN STATIONOP-ST-AFW-3007SURVEILLANCE TESTPAGE 8 OF 32 R128.1Flow of 200 gpm satisfies the ISI requirement for opening of AFWcheck valve FW-164 and FW-173.              9.Place S/G RC-2A Chan A Auto Sig Override Relay Test SW to NORM.              10.Restore AFW system as follows:10.1Place HC-1367, FW-6 Control Switch in PULL TO LOCK (CB-10).              10.2Place HCV-1107A control switch to RESET, then to AUTO.              10.3Place HCV-1107B control switch to RESET, then to AUTO.              10.4Place YCV-1045 control switch to RESET, CLOSE, RESET, andthen to AUTO.              10.5Place YCV-1045A control switch to CLOSE, then to NORMAL.              10.6Place YCV-1045B control switch to CLOSE, then to NORMAL.              10.7Verify AFWS STEAM GEN. RC-2A CHANNEL A ACTUATEDis clear (AI-66A, A66A, 44)              10.8Verify AFWS RC-2A CH A MATRIX TS-A/RC-2A/AFWS TEST SWITCH OFF NORMAL is clear (AI-66A, A66A, 24)              10.9Verify S/G RC-2A Chan A amber light is off.              10.10Verify S/G RC-2A Chan A1 amber light is off.                  - Aux Feedwater Func tional Test of Circuits/Components PROCEDURE (continued) () INITIALSFORT CALHOUN STATIONOP-ST-AFW-3007SURVEILLANCE TESTPAGE 9 OF 32 R1211.Remove the following jumpers and blocks on relay A1/RC-2A/AFWS (Device 25) in AI-66A:
!Jumper Contact 1-2 EM
 
Ind Verif!Block Contact 3-4 EM
 
Ind Verif!Jumper Contact 5-6 EM
 
Ind Verif!Block Contact 11-12 EM
 
Ind Verif Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE
 
JPM No: JPM-0613A
 
JPM Title: Shutdown a Reactor Coolant Pump Page 1 of 5
 
Location: Simulator Control Room    Approximate Time: 8 minutes Actual Time: _________________
 
Reference(s): OI-RC-9, Attachment 2 (R56)
K/A 003000 A4.06  ( RO 2.9 / SRO2.9 )
 
JPM Prepared by: Jerry Koske Date: 05/05/05    JPM Reviewed by:  Date:
JPM Approved by:  Date: 
 
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE
 
JPM No: JPM-0613A
 
JPM Title: Shutdown a Reactor Coolant Pump Page 2 of 5
 
Operators' Name
: _____________________  Employee # ______________
 
All Critical Steps (shaded) must be per formed or simulated in accordance with the standards contained in this JPM
 
The Operator's performance wa s evaluated as (circle one):
 
SATISFACTORY  UNSATISFACTORY
 
Evaluator's Signature:
________________________
_____  Date: __________
 
Reason, if unsatisfactory:
 
Tools & Equipment: Zero Power Mode Bypass Keys
 
Safety Considerations: None
 
Comments: Fail RC-3D's 90% speed switch COP JOB3171L As is
 
This is an Alternate Path JPM
 
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE
 
JPM No: JPM-0613A
 
JPM Title: Shutdown a Reactor Coolant Pump Page 3 of 5 INITIATING CUE: The reactor is in Hot Shutdown and is being cooled down to go into refueling. The RCS T-cold is 505°F and lowering approximately 30°F per hour.
 
You, the LO, are directed to shutdown Reactor Coolant Pump RC-3D. You are to verify that the prerequisites are met. The procedure revision has been verified.
 
START Critical Steps shown in gray
 
STEP ELEMENT STANDARD 1  ( prereq 2 ) Ensure the reactor is shutdown prior to stopping a RCP.
 
CB-4 Verify all trippable rods are
 
inserted 2  (prereq 3) Ensure Zero Power Mode Bypass switches are in Bypass
 
AI-31 A/B/C/D
 
Keys installed and AMBER
 
lights lit
 
3  (1) Stop Reactor Coolant Pump RC-3D  CB-1,2,3  RC-3D CS to AFTER-STOP position and release GREEN light lit 4  (2) Ensure the Oil Lift Pump starts automatically as pump speed lowers. CB-1,2,3  Determines pump did not start.
Manually starts lift oil pump by placing Oil Lift Pump CS, RC-3D-1, in START position and verifying RED light on. 
 
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE
 
JPM No: JPM-0613A
 
JPM Title: Shutdown a Reactor Coolant Pump Page 4 of 5  STEP ELEMENT STANDARD 5  (2 ) Holds Oil Lift Pump control switch in the START position If the control switch is released, the lift pump will stop. It should then be returned to the START position.
The control switch should be held in the START position until the zero speed light comes on. (approximately 2 minutes)  6  (3 ) Ensure Reverse Rotation Annunciator is clear.
CB-1,2,3, A6 D-5
 
Annunciator is OFF
 
7 ( 5 ) Confirm Zero Speed light is on CB-1,2,3 RC-3D GREEN light on
 
8  ( 4 ) Confirm RCP tachometer indicates zero
 
CUE: Local Operator reports RC-3D speed is zero rpm. 9  ( 6 ) Stop oil lift pump.
CB-1,2,3 Control switch to AFTER-
 
STOP GREEN light lit
 
Termination Criteria:
Reactor Coolant Pump RC-3D is secured and its Oil Lift pump has been stopped
 
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE
 
JPM No: JPM-0613A Page 5 of 5
 
INITIATING CUE: The reactor is in Hot Shutdown and is being cooled down to go into refueling. The RCS T-cold is 505°F and lowering approximately 30°F per hour.
 
You, the LO, are directed to shutdown Reactor Coolant Pump RC-3D. You are to verify that the prerequisites are met. The procedure revision has been verified.
 
START C Continuous UseFORT CALHOUN STATIONOI-RC-9OPERATING INSTRUCTIONPAGE 14 OF 65 R56 Attachment 2 - Shutdown Reactor Coolant Pumps (Coupled)
PREREQUISITES
()INITIALS1.Procedure Revision Verification Revision No.
Date:
2.The Reactor is Shutdown (Mode 3, Mode 4 or Mode 5).              3.The Zero Power Mode Bypass Switches on AI-31A/B/C/D are in bypass todisable the RPS Low Flow Trip before the first RCP is stopped.
PROCEDURE NOTES1.The order for stopping the RCPs is at the discretion of the Shift Manager.2.When an RCP is shutdown its seal Bleedoff temperature will rise.1.Secure the selected RCP by placing its Control Switch to AFTER STOP:
!RC-3A, RC Pump
!RC-3B, RC Pump
!RC-3C, RC Pump
!RC-3D, RC Pump
 
NOTES1.Oil Lift Pumps start at less than 90% of full speed.2.If RCP Lift Pump fails to start , it will be necessary to hold the RCP Oil Lift Control Switch in START until the RCP is verified stopped.2.Ensure Oil Lift Pump starts (Red indicating light is ON):
!RC-3A-1, Oil Lift Pump
!RC-3B-1, Oil Lift Pump
!RC-3C-1, Oil Lift Pump
!RC-3D-1, Oil Lift Pump
 
C Continuous UseFORT CALHOUN STATIONOI-RC-9OPERATING INSTRUCTIONPAGE 15 OF 65  - Shutdown Reactor Coolant Pumps (Coupled)
PROCEDURE  (continued)()INITIALS R563.For the selected RCP verify the following Annunciator is clear:
!RC-3A REACTOR COOLANT PUMP RC-3A REVERSE ROTATION (CB-1/2/3, A6, A5)
!RC-3B REACTOR COOLANT PUMP RC-3B REVERSE ROTATION (CB-1/2/3, A6, B5)
!RC-3C REACTOR COOLANT PUMP RC-3C REVERSE ROTATION (CB-1/2/3, A6, C5)
!RC-3D REACTOR COOLANT PUMP RC-3D REVERSE ROTATION (CB-1/2/3, A6, D5) 4.Confirm that the RCP tachometer (AI-270, Room 57) indicates zero:
!RC-3A129-1 ZS Tach
!RC-3B149-1 ZS Tach
!RC-3C169-1 ZS Tach
!RC-3D189-1 ZS Tach 5.Confirm that the Zero Speed Light is ON:
!Pump RC-3A Zero Speed
!Pump RC-3B Zero Speed
!Pump RC-3C Zero Speed
!Pump RC-3D Zero Speed 6.WHEN selected RCP has been verified stopped, THEN place the Oil Lift Pump for the selected RCP to AFTER STOP:
!RC-3A-1!RC-3B-1!RC-3C-1!RC-3D-1                                      7.IF other RCPs are to be stopped,THEN repeat Steps 1 through 6 for each RCP to be stopped.
Completed by Date/Time            /
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE
 
JPM No: JPM-0627
 
JPM Title: Reduce RCS Pressure using Aux Spray Page 1 of 6
 
Location: Simulator    Approximate Time: 12 minutes Actual Time: _________________
 
Reference(s): OI-RC-7 attachments 2 and 3  R10 NRC K/A 010000 A4.01  (RO 3.7 / SRO 3.5)
 
JPM Prepared by: Jerry Koske Date: 05/10/05    JPM Reviewed by:  Date:
JPM Approved by:  Date: 
 
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE
 
JPM No: JPM-0627
 
JPM Title: Reduce RCS Pressure using Aux Spray Page 2 of 6
 
Operators' Name
: _____________________  Employee # ______________
 
All Critical Steps (shaded) must be per formed or simulated in accordance with the standards contained in this JPM
 
The Operator's performance wa s evaluated as (circle one):
 
SATISFACTORY  UNSATISFACTORY
 
Evaluator's Signature:
________________________
_____  Date: __________
 
Reason, if unsatisfactory:
 
Tools & Equipment: None
 
Safety Considerations: None
 
Comments: Fail the normal pressurizer spray valves in the closed position. Ensure only B/U heater Bank 2 ON
 
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE
 
JPM No: JPM-0627
 
JPM Title: Reduce RCS Pressure using Aux Spray Page 3 of 6 INITIATING CUE: The Plant is in hot shutdown. The CRS has directed you to reduce RCS pressure to 1900 psia using pressurizer spray.
 
All prerequisites are met
 
START Critical Steps shown in gray
 
STEP ELEMENT STANDARD 1  (2.a) Verify PC-103Y is in automatic CB-1,2,3 PC-103Y controller in AUTO
 
2  (2.b) Ensure proportional heaters control switches are in auto.
CB-1,2,3 Group 6 and Group 7 switches in AUTO  3  (2.c) Ensure backup heater switches in auto CB-1,2,3 Bank 1 Group 1/2/3, Bank 3
 
Group 8/9 and Bank 4 Group 10/11/12 switches in AUTO
 
4  (2.d) Ensure pressurizer spray valves in auto
 
CB-1,2,3 PCV-101-1 and PCV-103-2
 
control switches in AUTO
 
5  (2.e) Lower RCS pressure by adjusting setpoint pushbuttons
 
on PC-103Y
 
CB-1,2,3 Adjust setpoint push buttons in small increments to lower
 
pressure setpoint
 
6 Determines the pressurizer spray valves are not
 
responding
 
CB-1,2,3 PCV-101-1 and PCV-103-2
 
GREEN lights lit
 
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE
 
JPM No: JPM-0627
 
JPM Title: Reduce RCS Pressure using Aux Spray Page 4 of 6  STEP ELEMENT STANDARD 7 (optional) May attempt to use PC-103X in automatic to lower pressure
 
CB-1,2,3 Place channel selector switch
 
in "X" position and repeat step
 
5 using PC-103X
 
8 (optional) May attempt to use manual mode to lower RCS pressure
 
CB-1,2,3 Place controller PC-103Y
 
and/or PC-103X in Manual and
 
move the manual control lever
 
to the right so that the output increases to greater than 67%
 
9  Lower pressure using Aux spray  CB-1,2,3 Perform one or both of the following:  Place HCV-240 in the OPEN position. Place HCV-249 in the OPEN position 10  CB-1,2,3 May place loop charging valves in CLOSE position as
 
needed to divert adequate flow to Aux Spray line  HCV-247  HCV-238  HCV-248  HCV-239  11 When pressure reaches 1900 psia, close the aux spray valves. CB-1,2,3 HCV-240 and HCV-249 both in CLOSE position.   
 
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE
 
JPM No: JPM-0627
 
JPM Title: Reduce RCS Pressure using Aux Spray Page 5 of 6  STEP ELEMENT STANDARD 12 Reopen loop charging valves that may have been closed in
 
step 10 CB-1,2,3 ENSURE at least one loop charging valve is open to provide loop charging flow  HCV-247  HCV-238  HCV-248  HCV-239 Termination Criteria:
The RCS is at 1900 psia and the Aux Spray valves
 
are closed
 
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE
 
JPM No: JPM-0627 Page 6 of 6
 
INITIATING CUE: The Plant is in hot shutdown. The CRS has directed you to reduce RCS pressure to 1900 psia using pressurizer spray.
 
All prerequisites are met
 
START WP10Fort Calhoun StationUnit No. 1 OI-RC-7OPERATING INSTRUCTION Title:REACTOR COOLANT SYSTEM PRESSURE CONTROL NORMALOPERATION FC-68 Number:EC 34293Reason for Change:Clarify Attachments for taking pressure control to automatic.
Requestor:Joseph Braun Preparer:Daniel A HochsteinISSUED:    05-04-04  3:00 pmR10 FORT CALHOUN STATIONOI-RC-7OPERATING INSTRUCTIONPAGE 1 OF 28R10REACTOR COOLANT SYSTEM PRESSURE CONTROL NORMAL OPERATIONSAFETY RELATEDATT PURPOSE PAGE1 - Pressurizer Steam Bubble Formation............................................42 - Manual RCS Pressure Control with a Steam Bubble in the Pressurizer..................83 - Automatic RCS Pressure Control with a Steam Bubble in the Pressurizer...............124 - Maximum Pressurizer Spray for Mixing..........................................15 5 - Pressurizer Pressure Control MANUAL to AUTOMATIC Transfer for the Selected                            Channel..................................................................186 - Pressurizer Pressure Control MANUAL to AUTOMATIC Transfer for the Non-Selected Channel......................................................207 - Pressurizer Pressure Control AUTOMATIC to MANUAL Transfer.....................21 8 - Pressurizer Pressure Controlling Channel Transfer in AUTOMATIC...................229 - Pressurizer Pressure Controlling Channel Transfer in MANUAL......................2410 - Pressurizer Spray Operation when the Difference between Spray Line      Temperature and Pressurizer Temperature is Greater Than 200°F...................26PRECAUTIONS1.Whenever the Pressurizer Heaters are to be energized, the water level in the Pressurizershall be above an actual level of 41.5%. 2.Reactor Coolant System allowable pressure versus temperature conditions shall be incompliance with Technical Specifications 2.1.2 or TDB-III.7.a and TDB-III.7.d, whichever ismore conservative.3.Power Operated Relief Valve Set points shall be within the limits established in TDB-III.7.a.4.Pressurizer maximum heat up rate is 100°F/hour and the maximum cooldown rate is200°F/hour.
FORT CALHOUN STATIONOI-RC-7OPERATING INSTRUCTIONPAGE 2 OF 28R10PRECAUTIONS  (continued)5.When the differential temperature between the Pressurizer and the Spray Line is greaterthan 200°F, refer to Attachment 10 of this Operating Instruction. 6.Reactor Coolant System Pressure shall meet the requirements of TDB-III.7.a and/orTDB-III.7.d for Reactor Coolant Pump Operation to satisfy NPSH requirements and less than250 psia for Shutdown Cooling System operation.7.Reactor Coolant System pressure of 2750 psia shall not be exceeded with fuel in theReactor.8.Reactor Coolant System pressure of 2500 psia shall not be exceeded for Reactor CoolantPump operation.9.Any deviations or discrepancies shall be immediately reported to the Shift Manager.
10.Main PZR Spray flow will be reduced with less than four-pump operati on. Pressure shouldbe controlled using Main and Auxiliary PZR Spray whenever less than four Reactor CoolantPumps are in operation.REFERENCES/COMMITMENTS1.Technical Specifications:
!Section 1.2, Safety Limit, Reactor Coolant System Pressure
!Section 2.1.2, LCO, Reactor Coolant System, Heat up and Cooldown
!Section 2.1.6, LCO, Reactor Coolant System, Pressurizer and Steam System SafetyValves!Section 2.1.7, LCO, Reactor Coolant System, Pressurizer Operability2.USAR:!Section 4.3.7, Reactor Coolant System, Pressurizer
!Section 7.4.1, Regulating Systems, Reactor Coolant Pressure Regulating System
!Section 7.4.2, Regulating Systems, Pressurizer Level Regulating System
!Section 7.5.1, Instrumentation Systems, Process Instrumentation
!Figure 4.6.1, Reactor Coolant System Pressure-Temperature Limitations During PlantCooldown and Heat up After 40 Years Integrated Neutron Flux FORT CALHOUN STATIONOI-RC-7OPERATING INSTRUCTIONPAGE 3 OF 28R10REFERENCES/COMMITMENTS (continued)3.DrawingsFileDescriptionFigure 8.1-112234Simplified One Line Diagram Plant Electrical SystemE-23866-210-11044479Reactor Coolant System Diagram4.Technical Data Book:
!Figure III.6:  Pressurizer Pressure Control Program
!Figure III.7.a:  RCS Pressure and Temperature Limits
!Figure III.7.d:  RCS Pressure and Temperature Limits5.I&C Equipment List:
!EM-103:  Pressurizer Pressure Controls (File No. 1567-1568)
APPENDICESTable 1 - Calculational Procedure for Pressurizer Spray Nozzle Usage Factor..............28 CContinuous UseFORT CALHOUN STATIONOI-RC-7OPERATING INSTRUCTIONPAGE 4 OF 28R10Attachment 1 - Pressurizer Steam Bubble FormationPREREQUISITES
()INITIALS1.Procedure Revision VerificationRevision Number Date:
2.120 VAC Instrument Power is operable from A and B Instrument Buses.              3.Pressurizer Heater Power is operable from the following MCC Panels:
!MCC-3B1 to Proportional Heater Groups
!MCC-4A1 to Proportional Heater Groups
!MCC-3A1 to Heater Groups 1, 2 and 3
!MCC-3C1 to Heater Groups 4 and 5
!MCC-4B1 to Heater Groups 8 and 9
!MCC-4C1 to Heater Groups 10, 11 and 12 4.Instrument Air is available to Pressurizer Spray Valves PCV-103-1 andPCV-103-2.
CContinuous UseFORT CALHOUN STATIONOI-RC-7OPERATING INSTRUCTIONPAGE 5 OF 28R10Attachment 1 - Pressurizer Steam Bubble Formation PROCEDURE ()INITIALS NOTES1.When the manual control lever is moved toward close to less than 17%
output the proportional heaters will come on.
 
2.When the manual control lever is moved toward open to greater than 67%output, the Spray Valves will begin to open (when Spray Valve Switches are in AUTO).3.The Output meter will read approximately 50% when neither ProportionalHeaters or Spray Valves receive action signals.CAUTIONExtreme caution shall be exercised when the RCS is solid in the Pressurizer.1.IF raising RCS pressure,THEN perform the following steps:a.Verify the Selected Controller is in MANUAL.
!PC-103X, Pressurizer Press Controller
!PC-103Y, Pressurizer Press Controller b.Ensure the following RC-4 Spray Valve Control Switches are in CLOSE:
!PCV-103-1, PZR Spray Valve From Loop 2A
!PCV-103-2, PZR Spray Valve From Loop 1B c.Ensure the following Proportional Heater Control Switches are in AUTO:
!75 KW Proportional Htrs Bank P1 Group 6
!75 KW Proportional Htrs Bank P2 Group 7 d.Move the Manual Control Lever for the selected controller, PC-103X orPC-103Y,  left to raise Proportional Heater Output.
CContinuous UseFORT CALHOUN STATIONOI-RC-7OPERATING INSTRUCTIONPAGE 6 OF 28Attachment 1 - Pressurizer Steam Bubble Formation PROCEDURE (continued)()INITIALSR101e.Energize the Backup Heaters as desired by placing the following ControlSwitches in ON:
!225 KW Backup Htrs Bank 1 Group 1/2/3
!150 KW Backup Htrs Bank 2 Group 4/5
!150 KW Backup Htrs Bank 3 Group 8/9
!225 KW Backup Htrs Bank 4 Group 10/11/12 f.WHEN the desired RCS pressure is attained AND if required,THEN place the following Backup Heater Switches in OFF:
!225 KW Backup Htrs Bank 1 Group 1/2/3
!150 KW Backup Htrs Bank 2 Group 4/5
!150 KW Backup Htrs Bank 3 Group 8/9
!225 KW Backup Htrs Bank 4 Group 10/11/12 g.Adjust manual control lever as necessary on the selected controller,PC-103X or PC-103Y, to maintain RCS pressure.              2.IF lowering the RCS pressure,THEN perform the following steps:a.Verify the Selected Controller is in MANUAL.
!PC-103X, Pressurizer Press Controller
!PC-103Y, Pressurizer Press Controller b.Ensure the following RC-4 Spray Valve Control Switches are in CLOSE:
!PCV-103-1, PZR Spray Valve From Loop 2A
!PCV-103-2, PZR Spray Valve From Loop 1B c.IF the Backup Heaters are energized, THEN place the following Backup Heater Control Switches in OFF:
!225 KW Backup Htrs Bank 1 Group 1/2/3
!150 KW Backup Htrs Bank 2 Group 4/5
!150 KW Backup Htrs Bank 3 Group 8/9
!225 KW Backup Htrs Bank 4 Group 10/11/12
 
CContinuous UseFORT CALHOUN STATIONOI-RC-7OPERATING INSTRUCTIONPAGE 7 OF 28Attachment 1 - Pressurizer Steam Bubble Formation PROCEDURE (continued)()INITIALSR102d.Ensure the Proportional Heater Control Switches are in AUTO OR OFF,as required by one of the following conditions:1)IF the RCS is to remain pressurized,THEN place the following Proportional Heater Control Switches for RC-4 in AUTO:
!75 KW Proportional Htrs Bank P1 Group 6
!75 KW Proportional Htrs Bank P2 Group 7 2)IF the RCS is to be depressurized,THEN place the following Proportional Heater Control Switches for RC-4 in OFF:
!75 KW Proportional Htrs Bank P1 Group 6
!75 KW Proportional Htrs Bank P2 Group 7 e.IF the RCS is to be depressurized OR a rapid depressurization isrequired, THEN depressurize the RCS by raising Letdown flow per OI-CH-1 , Increasing Charging and Letdown Flows.              f.Move the Manual Control lever on the selected controller, PC-103X orPC-103Y, right until the Proportional Heaters are OFF.              g.WHEN the desired pressure is attained, THEN adjust the Manual Control Lever as necessary on the selected controller, PC-103X or PC-103Y, to maintain RCS pressure.              Completed by                                                                                            Date/Time            /
CContinuous UseFORT CALHOUN STATIONOI-RC-7OPERATING INSTRUCTIONPAGE 8 OF 28R10Attachment 2 - Manual RCS Pressure Control with a Steam Bubble in the PressurizerPREREQUISITES
()INITIALS1.Procedure Revision VerificationRevision Number Date:
2.120 VAC Instrument Power is operable from A and B Instrument Buses.              3.Pressurizer Heater Power is operable from the following MCC Panels:
!MCC-3B1 to Proportional Heater Groups
!MCC-4A1 to Proportional Heater Groups
!MCC-3A1 to Heater Groups 1, 2 and 3
!MCC-3C1 to Heater Groups 4 and 5
!MCC-4B1 to Heater Groups 8 and 9
!MCC-4C1 to Heater Groups 10, 11 and 12 4.Instrument Air is available to Pressurizer Spray Valves PCV-103-1 andPCV-103-2.
PROCEDURE NOTES1.When the manual control lever is moved toward close to less than 17%
output the proportional heaters will come on.
 
2.When the manual control lever is moved toward open to greater than 67%output AND the Spray Valve Switches are in AUTO, the Spray Valves will begin to open.3.The Output meter will read approximately 50% when neither ProportionalHeaters or Spray Valves receive action signals.1.IF raising RCS pressure,THEN perform the following steps:a.Verify the Selected Controller is in MANUAL.
!PC-103X, Pressurizer Press Controller
!PC-103Y, Pressurizer Press Controller
 
CContinuous UseFORT CALHOUN STATIONOI-RC-7OPERATING INSTRUCTIONPAGE 9 OF 28Attachment 2 - Manual RCS Pressure Control with a Steam Bubble in the Pressurizer PROCEDURE (continued)()INITIALSR101b.Ensure the following RC-4 Spray Valve Control Switches are in AUTO:
!PCV-103-1, PZR Spray Valve From Loop 2A
!PCV-103-2, PZR Spray Valve From Loop 1B c.Ensure the following Proportional Heater Control Switches for RC-4  arein AUTO:!75 KW Proportional Htrs Bank P1 Group 6
!75 KW Proportional Htrs Bank P2 Group 7 d.Place the Backup Heater Bank Control Switches in ON as desired:
!225 KW Backup Htrs Bank 1 Group 1/2/3
!150 KW Backup Htrs Bank 2 Group 4/5
!150 KW Backup Htrs Bank 3 Group 8/9
!225 KW Backup Htrs Bank 4 Group 10/11/12 e.Move the Manual Control Lever for the selected controller, PC-103X orPC-103Y, left to raise the Proportional Heater Output.              f.WHEN the desired RCS pressure is attained, THEN place the Backup Heater Control Switches as required by one ofthe following:1)IF the RCS is at normal operating pressure,THEN place the following switches in AUTO or ON:
!225 KW Backup Htrs Bank 1 Group 1/2/3
!150 KW Backup Htrs Bank 2 Group 4/5
!150 KW Backup Htrs Bank 3 Group 8/9
!225 KW Backup Htrs Bank 4 Group 10/11/12
 
CContinuous UseFORT CALHOUN STATIONOI-RC-7OPERATING INSTRUCTIONPAGE 10 OF 28Attachment 2 - Manual RCS Pressure Control with a Steam Bubble in the Pressurizer PROCEDURE (continued)()INITIALSR101.f2)IF the RCS is at less than normal operating pressure,THEN place the following switches in OFF:
!225 KW Backup Htrs Bank 1 Group 1/2/3
!150 KW Backup Htrs Bank 2 Group 4/5
!150 KW Backup Htrs Bank 3 Group 8/9
!225 KW Backup Htrs Bank 4 Group 10/11/12 g.Adjust manual control lever as necessary on the selected controller,PC-103X or PC-103Y, to maintain RCS pressure.              2.To lower the RCS pressure, then perform the following steps:
NOTE Refer to Attachment 10 if the temperature differential between Pressurizerand Spray Line is greater than 200°F.a.Verify the Selected Controller is in MANUAL.
!PC-103X, Pressurizer Press Controller
!PC-103Y, Pressurizer Press Controller b.Ensure the following Spray Control Switches are in AUTO:
!PCV-103-1, PZR Spray Valve From Loop 2A
!PCV-103-2, PZR Spray Valve From Loop 1B c.IF the RCS pressure is to be reduced below 2060 psia, THEN place the following Backup Heater Switches in OFF:
!225 KW Backup Htrs Bank 1 Group 1/2/3
!150 KW Backup Htrs Bank 2 Group 4/5
!150 KW Backup Htrs Bank 3 Group 8/9
!225 KW Backup Htrs Bank 4 Group 10/11/12 d.Move the Manual Control Lever right on the selected controller,PC-103X or PC-103Y to greater than 67% to open the Spray Valves.
CContinuous UseFORT CALHOUN STATIONOI-RC-7OPERATING INSTRUCTIONPAGE 11 OF 28Attachment 2 - Manual RCS Pressure Control with a Steam Bubble in the Pressurizer PROCEDURE (continued)()INITIALSR102e.WHEN the desired RCS pressure is attained, THEN place the Backup Heater Control Switches as required by one ofthe following:1)IF the RCS is at normal operating pressure,THEN place the following switches in AUTO or ON:
!225 KW Backup Htrs Bank 1 Group 1/2/3
!150 KW Backup Htrs Bank 2 Group 4/5
!150 KW Backup Htrs Bank 3 Group 8/9
!225 KW Backup Htrs Bank 4 Group 10/11/12 2)IF the RCS is at less than normal operating pressure,THEN place the following switches in OFF:
!225 KW Backup Htrs Bank 1 Group 1/2/3
!150 KW Backup Htrs Bank 2 Group 4/5
!150 KW Backup Htrs Bank 3 Group 8/9
!225 KW Backup Htrs Bank 4 Group 10/11/12 f.Adjust Manual Control Lever as necessary on selected controller,PC-103X or PC-103Y, to maintain RCS pressure.              Completed by                                                                                            Date/Time            /
CContinuous UseFORT CALHOUN STATIONOI-RC-7OPERATING INSTRUCTIONPAGE 12 OF 28R10Attachment 3 - Automatic RCS Pressure Control with a Steam Bubble in the PressurizerPREREQUISITES
()INITIALS1.Procedure Revision VerificationRevision Number Date:
2.120 VAC Instrument Power is operable from A and B Instrument Buses.              3.Pressurizer Heater Power is operable from the following MCC Panels:
!MCC-3B1 to Proportional Heater Groups
!MCC-4A1 to Proportional Heater Groups
!MCC-3A1 to Heater Groups 1, 2 and 3
!MCC-3C1 to Heater Groups 4 and 5
!MCC-4B1 to Heater Groups 8 and 9
!MCC-4C1 to Heater Groups 10, 11 and 12 4.Instrument Air is available to Pressurizer Spray Valves PCV-103-1 andPCV-103-2.
PROCEDURE NOTERCS Pressure Control should automatically maintain setpoint for normal operation at 2100 (2080 to 2145) psia.1.IF raising the RCS pressure,THEN perform the following steps:a.Verify the Selected Controller is in AUTOMATIC.
!PC-103X, Pressurizer Press Controller
!PC-103Y, Pressurizer Press Controller b.Ensure the following Proportional Heater Control Switches are in AUTO:
!75 KW Proportional Htrs Bank P1 Group 6
!75 KW Proportional Htrs Bank P2 Group 7
 
CContinuous UseFORT CALHOUN STATIONOI-RC-7OPERATING INSTRUCTIONPAGE 13 OF 28Attachment 3 - Automatic RCS Pressure Control with a Steam Bubble in the Pressurizer PROCEDURE (continued)()INITIALSR10 NOTEDuring normal operation, one bank of pressurizer heaters is usually maintainedin the ON position. 1c.IF one Bank of Heaters is in ON,THEN ensure the remaining Backup Heater Switches are in AUTO; OR ensure all of the following switches are in AUTO:
!225 KW Backup Htrs Bank 1 Group 1/2/3
!150 KW Backup Htrs Bank 2 Group 4/5
!150 KW Backup Htrs Bank 3 Group 8/9
!225 KW Backup Htrs Bank 4 Group 10/11/12 d.Ensure the following Spray Control Switches are in AUTO:
!PCV-103-1, PZR Spray Valve From Loop 2A
!PCV-103-2, PZR Spray Valve From Loop 1B e.Raise the RCS pressure by adjusting the Setpoint Push-button(s) onselected controller, PC-103X or PC-103Y, to desired RCS pressure setpoint.              f.Ensure RCS pressure stabilizes at the desired setpoint.              2.IF lowering the RCS pressure,THEN perform the following steps:
NOTEIf the temperature differential between Pressurizer and Spray Line isgreater than 200°F, refer to Attachment 10.a.Verify the Selected Controller is in AUTOMATIC.
!PC-103X, Pressurizer Press Controller
!PC-103Y, Pressurizer Press Controller
 
CContinuous UseFORT CALHOUN STATIONOI-RC-7OPERATING INSTRUCTIONPAGE 14 OF 28Attachment 3 - Automatic RCS Pressure Control with a Steam Bubble in the Pressurizer PROCEDURE (continued)()INITIALSR102b.Ensure the following Proportional Heaters Control Switches are inAUTO:!75 KW Proportional Htrs Bank P1 Group 6
!75 KW Proportional Htrs Bank P2 Group 7
 
NOTEDuring normal operation, one bank of pressurizer heaters is usually maintainedin the ON position. c.IF one (1) Bank of Heaters is in ON, THEN ensure the remaining Backup Heater Switches are in AUTO; OTHERWISE ensure all of the following switches are in AUTO:
!225 KW Backup Htrs Bank 1 Group 1/2/3
!150 KW Backup Htrs Bank 2 Group 4/5
!150 KW Backup Htrs Bank 3 Group 8/9
!225 KW Backup Htrs Bank 4 Group 10/11/12 d.Ensure the following Spray Control Switches are in AUTO:
!PCV-103-1, PZR Spray Valve From Loop 2A
!PCV-103-2, PZR Spray Valve From Loop 1B CAUTIONWhen reducing RCS pressure, decreasing pressure in small incrementswill prevent overshoot from selected setpoint.e.Lower RCS pressure by adjusting the Setpoint Push-button(s) onselected controller, PC-103X or PC-103Y, to the desired RCS pressure setpoint.              f.Ensure RCS pressure stabilizes at the desired setpoint.              Completed by                                                                                            Date/Time            /
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE
 
JPM No: JPM-0225
 
JPM Title:  Initiate Ai r Compressor Backup Cooling Page 1 of 5
 
Location: Room 19    Approximate Time: 8 minutes Actual Time: _________________
 
Reference(s): EOP-20, MVA-IA  R14 NRC K/A 078000  K1.04    (RO 2.6 / SRO 2.9)
 
JPM Prepared by:  Jerry Koske Date: 05/10/05    JPM Reviewed by:  Date:
JPM Approved by:  Date: 
 
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE
 
JPM No: JPM-0225
 
JPM Title:  Initiate Ai r Compressor Backup Cooling Page 2 of 5
 
Operators' Name
: _____________________  Employee # ______________
 
All Critical Steps (shaded) must be per formed or simulated in accordance with the standards contained in this JPM
 
The Operator's performance wa s evaluated as (circle one):
 
SATISFACTORY  UNSATISFACTORY
 
Evaluator's Signature:
________________________
_____  Date: __________
 
Reason, if unsatisfactory:
 
Tools & Equipment: None
 
Safety Considerations: 1. Observe local industrial safety postings 2. Use caution around hot/warm piping
: 3. DO NOT operate any actual plant equipment
 
Comments: Static In-plant JPM
 
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE
 
JPM No: JPM-0225
 
JPM Title:  Initiate Ai r Compressor Backup Cooling Page 3 of 5 INITIATING CUE: A loss of offsite power has occurred. You have been directed to line up the CA-1A local control switches for Control Room Start and then lineup backup cooling to Air Compressor CA-1A. The Control Room has placed the control switch for CA-1A in pull-to lock.
 
START Critical Steps shown in gray
 
STEP ELEMENT STANDARD 1 Place the CA-1A controller switch in the Control Room
 
Start position
 
Room-19 1SS switch in CS position
 
2 Ensure that the CA-1A load transfer switch is either position 1 or 2 Room-19 Ensure Compressor load transfer switch in the 1 or 2
 
position CUE: CA-1A is not running 3  (2.1.a.1)
Isolate Bearing Water to CA-1A Room 19 CLOSE all of the following valves:  AC-584  AC-588  AC-586  AC-589  4 (2.1.a.2)
Align Potable Water to CA-1A Room 19 OPEN all of the following valves:  AC-1042  AC-1043  AC-1044  AC-1045  AC-583 Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE
 
JPM No: JPM-0225
 
JPM Title:  Initiate Ai r Compressor Backup Cooling Page 4 of 5  STEP ELEMENT STANDARD CUE: The Control Room has started CA-1A 5 (2.1.a.4) Verify cooling water flow Room-19 Read FI-1955 to verify flow
 
Termination Criteria:
CA-1A is being cooled by potable water
 
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE
 
JPM No: jPM-0225 Page 5 of 5
 
INITIATING CUE: A loss of offsite power has occurred. You have been directed to line up the CA-1A local control switches for Control Room Start and then lineup backup cooling to Air Compressor CA-1A. The Control Room has placed the control switch for CA-1A in pull-to lock.
 
START 12.0MAINTENANCE OF VITAL AUXILIARIES - IAMVA-IA  INSTRUCTIONSCONTINGENCY ACTIONSEOP-20Page 145 of 496R14  Continuously Applicable or Non-Sequential Step
****************************************************************************************************CAUTIONDo not allow Diesel Generator loads to exceed power and current rating limits.
 
****************************************************************************************************
2.IF any of the Air Compressors havetripped because of low Turbine Plant Cooling Water pressure, THEN restore Turbine Plant CoolingWater by performing the following
 
steps:a.Start ONE Bearing Water Pump,AC-9A/B.b.Verify cooling water headerpressure is approximately 70 psig.c.Start at least one Air Compressor,CA-1A/B/C.(continue) 2.1 IF Turbine Plant Cooling Water is NOTavailable, THEN align Potable Water to the AirCompressors by performing the following steps:a.Align backup Potable Watercooling to CA-1A, Air Compressor, by performing the following steps:(continue) 12.0MAINTENANCE OF VITAL AUXILIARIES - IAMVA-IA  INSTRUCTIONSCONTINGENCY ACTIONSEOP-20Page 146 of 496R14  Continuously Applicable or Non-Sequential Step2.(continued)(continue)2.1.a(continued)1)Close ALL of the followingvalves (Room 19):
!AC-584, "AIRCOMPRESSOR CA-1A INTERCOOLER INLET
 
VALVE"!AC-588, "AIR COMPRESSOR CA-1A OUTLET VALVE"!AC-586, "AIR COMPRESSOR CA-1A AFTERCOOLER CA-2A INLET VALVE"!AC-589, "AIR COMPRESSOR CA-1A AFTERCOOLER CA-2A OUTLET VALVE"(continue) 12.0MAINTENANCE OF VITAL AUXILIARIES - IAMVA-IA  INSTRUCTIONSCONTINGENCY ACTIONSEOP-20Page 147 of 496R14  Continuously Applicable or Non-Sequential Step2.(continued)(continue)2.1.a(continued)2)Open ALL of the followingvalves (Room 19):
!AC-1042, "AIRCOMPRESSOR CA-1A INTERCOOLER POTABLE WATER INLET VALVE"!AC-1043, "AIR COMPRESSOR CA-1A POTABLE WATER OUTLET VALVE"!AC-1044, "AIR COMPRESSOR CA-1A AFTERCOOLER CA-2A POTABLE WATER INLET
 
VALVE"!AC-1045, "AIR COMPRESSOR CA-1A AFTERCOOLER CA-2A POTABLE WATER OUTLET VALVE"!AC-583, "AIR COMPRESSOR CA-1A INTERCOOLER INLET PRESS INDICATOR PI-1942A ROOT VALVE"3)Start CA-1A, Air Compressor.(continue) 12.0MAINTENANCE OF VITAL AUXILIARIES - IAMVA-IA  INSTRUCTIONSCONTINGENCY ACTIONSEOP-20Page 148 of 496R14  Continuously Applicable or Non-Sequential Step2.(continued)2.1.a(continued)4)Check for flow throughFI-1955A (Room 19).b.Align backup Potable Watercooling to CA-1B, Air Compressor, by performing the following steps:(continue)1)Close ALL of the followingvalves (Room 19):
!AC-577, "AIRCOMPRESSOR CA-1B INTERCOOLER INLET
 
VALVE"!AC-581, "AIR COMPRESSOR CA-1B OUTLET VALVE"!AC-582, "AIR COMPRESSOR CA-1B AFTERCOOLER CA-2B OUTLET VALVE"!AC-579, "AIR COMPRESSOR CA-1B AFTERCOOLER CA-2B INLET VALVE"(continue)
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE
 
JPM No:  JPM-0356
 
JPM Title:  Emergency Star t of Diesel-Generator D-1 Page 1 of 5
 
Location: DG-1 Room    Approximate Time: 12 minutes Actual Time: _________________
 
Reference(s): EOP/AOP Attachments, Attachment 12  R17  NRC K/A 064000 A4.06  (RO 3.9 / SRO 3.9)
 
JPM Prepared by:  Jerry Koske Date: 05/10/05    JPM Reviewed by:  Date:
JPM Approved by:  Date: 
 
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE
 
JPM No:  JPM-0356
 
JPM Title:  Emergency Star t of Diesel-Generator D-1 Page 2 of 5
 
Operators' Name
: _____________________  Employee # ______________
 
All Critical Steps (shaded) must be per formed or simulated in accordance with the standards contained in this JPM
 
The Operator's performance wa s evaluated as (circle one):
 
SATISFACTORY  UNSATISFACTORY
 
Evaluator's Signature:
________________________
_____  Date: __________
 
Reason, if unsatisfactory:
 
Tools & Equipment: None
 
Safety Considerations: Observe Industrial Safety practices  DO NOT operate and plant equipment Comments: In Plant alternate path JPM
 
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE
 
JPM No:  JPM-0356
 
JPM Title:  Emergency Star t of Diesel-Generator D-1 Page 3 of 5 INITIATING CUE: A station blackout has occurred. D/G-1 did not start and attempts to start D/G-1 from the control room have been unsuccessful.
 
You have been directed to start D/G-1 using EOP/AOP  2.
 
START Critical Steps shown in gray
 
STEP ELEMENT STANDARD 1 (3.a)  Place the "Engine Control 143/SS" switch to local
 
AI-133A behind small door 143/SS Switch to LOCAL 2 (3.b) Press the "Normal Engine Start" push button
 
AI-133A Push NORMAL ENGINE
 
START button
 
CUE: D/G-1 did not start 3 (3.1.a) Place the "Engine Control 143/SS" switch to EMERG
 
AI-133A behind small door 143/SS Switch to EMERG 4 (3.1.b) Press the "Emergency Engine Start" push button
 
AI-133A Push EMERGENCY ENGINE
 
START button
 
CUE: D/G-1 did not start 5  (5) Check primary air receiver tank and secondary air receiver tank
 
pressures.
AI-133A Read indicators
 
CUE: both pressure
 
indicators "as read"
 
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE
 
JPM No:  JPM-0356
 
JPM Title:  Emergency Star t of Diesel-Generator D-1 Page 4 of 5  STEP ELEMENT STANDARD 6  (14) Ensure overspeed trip is reset West end of D/G-1 Ensure trip is reset
 
7  (15.a) Place the Engine Control 143/SS switch in LOCAL
 
AI-133A behind small door Place 143/SS switch in the
 
LOCAL position
 
8  (15.b) Press the "Normal Engine Start" pushbutton
 
AI-133A Press NORMAL ENGINE
 
START pushbutton
 
CUE: D/G-1 did not start 9  (15.1)
Manually override SA-142, Diesel-Generator DG-1 Primary Air System Solenoid valve On top of valve Open the "T" handled valve.
CUE: D/G-1 has started 10  (16) Ensure Engine Control 143/SS switch is in the EMERG AI-133A behind small door 143/SS Switch in EMERG position  11  (17) Check DG-1 speed AI-133A CUE: speed reads 900 rpm
 
Termination Criteria:
D/G-1 is running at full speed.
 
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE
 
JPM No: JPM-0356 Page 5 of 5
 
INITIATING CUE: A station blackout has occurred. D/G-1 did not start and attempts to start D/G-1 from the control room have been unsuccessful.
 
You have been directed to start D/G-1 using EOP/AOP  2.
 
START
 
EOP/AOP ATTACHMENTSPage 49 of 150R17 Attachment 12Emergency Start of Diesel Generator D-1INSTRUCTIONSCONTINGENCY ACTIONS1.Start D-1 by pressing the "DIESELNORMAL START" push button.
1.1 IF D-1 did NOT start, THEN press the "EMERGENCYSTART" push button.
2.IF D-1 is running, THEN GO TO Step 17.3.Start D-1 by performing the followingsteps (Engine Control Panel):a.Place the "ENGINE CONTROL143/SS" Switch in "LOCAL".
3.1 IF D-1 did NOT start, THEN start D-1 by performing thefollowing steps (Engine Control Panel):a.Place the "ENGINE CONTROL143/SS" Switch in "EMERG".b.Press the "NORMAL ENGINESTART" push button.b.Press the "EMERGENCY ENGINESTART" push button.
4.IF D-1 is running, THEN GO TO Step 16. 2Emergency Start of Diesel Generator D-1INSTRUCTIONSCONTINGENCY ACTIONSEOP/AOP ATTACHMENTSPage 50 of 150R17 NOTEA minimum starting air pressure of 157 psig is required to start D-1.
5.IF "PRIMARY AIR RECEIVER TANKPRESSURE" or "SECONDARY AIR RECEIVER TANK PRESSURE" is greater than 157 psig (Engine Control Panel),
THEN GO TO Step 14.6.IF the Primary Air Start System isavailable, THEN align the EmergencyCompressor to the Primary AirReceivers by performing the followingsteps (D-1 room):
6.1 IF the Secondary Air Start System isavailable, THEN align the EmergencyCompressor to the Secondary AirReceivers by performing the followingsteps (D-1 room):a.Ensure the "ENGINE CONTROL143/SS" Switch is in "LOCAL".a.Ensure the "ENGINE CONTROL143/SS" Switch is in "LOCAL".b.Place "SA-2-1 PRIMARYCOMPRESSOR 43/AS2" Switch in"OFF".b.Place "SA-23-1 SECONDARYCOMPRESSOR 43/AS1" Switch in "OFF".(continue)(continue)  2Emergency Start of Diesel Generator D-1INSTRUCTIONSCONTINGENCY ACTIONSEOP/AOP ATTACHMENTSPage 51 of 150R176.(continued)6.1(continued)c.Ensure BOTH of the followingvalves are closed:
!SA-214, "PRESSURECONTROLLER PC-6040A SECONDARY AIR SYSTEM ROOT VALVE"!SA-280, "EMERGENCY COMPRESSOR SA-1-1 SECONDARY AIR SYSTEM ISOLATION VALVE"c.Ensure BOTH of the followingvalves are closed:
!SA-215, "PRESSURECONTROLLER PC-6040A PRIMARY AIR SYSTEM ROOT VALVE"!SA-204, "EMERGENCY COMPRESSOR SA-1-1 PRIMARY AIR SYSTEM ISOLATION VALVE"d.Open BOTH of the followingvalves:!SA-215, "PRESSURECONTROLLER PC-6040A PRIMARY AIR SYSTEM ROOT VALVE"!SA-204, "EMERGENCY COMPRESSOR SA-1-1 PRIMARY AIR SYSTEM ISOLATION VALVE"d.Open BOTH of the followingvalves:!SA-214, "PRESSURECONTROLLER PC-6040A SECONDARY AIR SYSTEM ROOT VALVE"!SA-280, "EMERGENCY COMPRESSOR SA-1-1 SECONDARY AIR SYSTEM ISOLATION VALVE"  2Emergency Start of Diesel Generator D-1INSTRUCTIONSCONTINGENCY ACTIONSEOP/AOP ATTACHMENTSPage 52 of 150R177.Unload the compressor by turning the"SA-1-1 UNLOADER CONTROL ASSEMBLY" adjustment nut clockwise (behind compressor).8.Ensure the "DECOMP SW" is in"STOP".9.Cycle the priming lever a minimum of three times.10.Press and hold the "PRE-HEATSWITCH" push button for one minute. 2Emergency Start of Diesel Generator D-1INSTRUCTIONSCONTINGENCY ACTIONSEOP/AOP ATTACHMENTSPage 53 of 150R1711.Start the Diesel Engine by performingthe following steps:a.Press and hold the "PRE-HEATSWITCH" push button.b.Press the "PUSH TO START" push button.
c.WHEN the diesel reaches fullcranking speed, THEN release the "PRE-HEATSWITCH" push button.d.Place the "DECOMP SW" in"RUN". 2Emergency Start of Diesel Generator D-1INSTRUCTIONSCONTINGENCY ACTIONSEOP/AOP ATTACHMENTSPage 54 of 150R17 12.WHEN Diesel Engine starts, THEN release the "PUSH TO START" push button.13.Load the compressor by turning the"SA-1-1 UNLOADER CONTROL ASSEMBLY" adjustment nut counterclockwise.
14.WHEN "PRIMARY AIR RECEIVERTANK PRESSURE" or "SECONDARY AIR RECEIVER TANK PRESSURE" is greater than 157 psig (Engine Control Panel),
THEN ensure the overspeed trip isreset (West end of D-1). 2Emergency Start of Diesel Generator D-1INSTRUCTIONSCONTINGENCY ACTIONSEOP/AOP ATTACHMENTSPage 55 of 150R1715.Start D-1 by performing the followingsteps (Engine Control Panel):a.Place the "ENGINE CONTROL143/SS" Switch in "LOCAL".b.Press the "NORMAL ENGINESTART" push button.
***************************************************CAUTIONThis step may damage the Air Start Motors ifthe manual override is not released after a few seconds.
**************************************************
15.1 IF D-1 did NOT start,AND the Primary Air Receivers arepressurized, THEN manually override SA-142,"DIESEL GENERATOR DG-1 PRIMARY AIR SYSTEM SOLENOID VALVE", using the "T" handle located on top of the valve.
15.2 IF D-1 did NOT startAND the Secondary Air Receivers arepressurized, THEN manually override SA-141,"DIESEL GENERATOR DG-1 SECONDARY AIR SYSTEM SOLENOID VALVE", using the "T" handle located on top of the valve. 2Emergency Start of Diesel Generator D-1INSTRUCTIONSCONTINGENCY ACTIONSEOP/AOP ATTACHMENTSPage 56 of 150R1716.Ensure the "ENGINE CONTROL143/SS" Switch in "EMERG" to return D-1 start function to the Control Room.17.Check that D-1 is operating at greaterthan or equal to 900 rpm.End of Attachment 12 Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE
 
JPM No: JPM-0719M
 
JPM Title: Startup Contai nment Hydrogen Purge and Makeup Page 1 of 5
 
Location: Aux Building  (RCA)    Approximate Time: 15 min Actual Time: _________________
 
Reference(s): OI-VA-1 Attachment 5A and 5B    R55 NRC K/A  028000 A2.02  (RO 3.5 / SRO 3.9)
 
JPM Prepared by: Jerry Koske Date: 05/10/05    JPM Reviewed by:  Date:
JPM Approved by:  Date: 
 
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE
 
JPM No: JPM-0719M
 
JPM Title: Startup Contai nment Hydrogen Purge and Makeup Page 2 of 5
 
Operators' Name
: _____________________  Employee # ______________
 
All Critical Steps (shaded) must be per formed or simulated in accordance with the standards contained in this JPM
 
The Operator's performance wa s evaluated as (circle one):
 
SATISFACTORY  UNSATISFACTORY
 
Evaluator's Signature:
________________________
_____  Date: __________
 
Reason, if unsatisfactory:
 
Tools & Equipment: None
 
Safety Considerations: Observe industrial and radiological safety practices  DO NOT operate any plant equipment Comments: This static JPM is conducted inside the RCA
 
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE
 
JPM No: JPM-0719M
 
JPM Title: Startup Contai nment Hydrogen Purge and Makeup Page 3 of 5 INITIATING CUE: A major LOCA occurred several weeks ago. Containment hydrogen concentration has been slowly increasing and has now reached 3%. A release permit has been prepared and approved. You have been
 
directed the Aux building st eps of OI-VA-1 attachment 5A to purge hydrogen from containment using VA-80A and attachment 5B to use VA-80B to provide makeup
 
air to containment.
 
CIAS and VIAS were initia ted and have not been reset OI-VA-1 is complete through step 6. HC-745 has been
 
placed in HAND
 
START Critical Steps shown in gray
 
STEP ELEMENT STANDARD 1 Ensure VA-411, VA-82 bypass is closed Corr. 26 IA-VA-411-B1 in FILTERED
 
2 Ensure VA-291/VA-279 combined remote operator is
 
closed.
Corr 26 VA-291/VA-279 CLOSED 3 Ensure VA-282/VA-284 combined remote operator is
 
closed.
Corr 26 VA-282/VA-284 CLOSED 4 Open hydrogen purge valves for VA-80A:  VA-290  VA-292  VA-289:  Corr 26 Unlock and OPEN valves 5 Contact Control Room CUE: Control room reports procedure steps 8,9 and 10 have been completed Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE
 
JPM No: JPM-0719M
 
JPM Title: Startup Contai nment Hydrogen Purge and Makeup Page 4 of 5  STEP ELEMENT STANDARD 6 Start hydrogen purge fan, VA-80A AI-100 Place VA-80A control switch in PULL TO OVERRIDE Red Light ON  Green Light OFF  7 Monitor DPI-899D Corr 26 CUE: DPI-899D indicates 10"w.g. 8 Ensure VA-281/VA-283 combined remote operator is closed. Corr 26 VA-281/VA-283 CLOSED 9 Open VA-282/VA-284 VA-80B suction from Aux Bldg/recirc
 
valve Corr 26 VA-282/VA-284 OPEN 10 Open VA-280 Corr 26 VA-280 OPEN
 
11 Start hydrogen purge fan, VA-80B AI-100 Place VA-80B control switch in PULL TO OVERRIDE Red Light ON  Green Light OFF  12 Contact control room to place HCV-881 in override.
CUE: The control room has placed HCV-881 in OVERRIDE STOP    Termination Criteria:
The hydrogen purge system is in operation with VA-80A purging hydrogen from containment and VA-80B supplying makeup air
 
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE
 
JPM No: JPM-0719M Page 5 of 5
 
INITIATING CUE: A major LOCA occurred several weeks ago. Containment hydrogen concentration has been slowly increasing and has now reached 3%. A release permit has been prepared and approved. You have been
 
directed the Aux building st eps of OI-VA-1 attachment 5A to purge hydrogen from containment using VA-80A and attachment 5B to use VA-80B to provide makeup
 
air to containment.
 
CIAS and VIAS were initia ted and have not been reset OI-VA-1 is complete through step 6. HC-745 has been
 
placed in HAND
 
START
 
C Continuous UseFORT CALHOUN STATIONOI-VA-1OPERATING INSTRUCTIONPAGE 20 OF 120 R55 Attachment 5A - Hydrogen Purge Release VA-80A & VA-80B PREREQUISITES () INITIALS1.Procedure Revision Verification Revision No.
Date:
2.Plant is in MODE 4 or 5.              3.OI-VA-1-CL-A has been completed per OP-1.              4.Containment Integrity is not required.              5.At least one VA-40 Fan (Aux Bldg Exhaust) is in operation.              6.Condenser evacuation discharge is aligned to the normal flow path (TurbineBuilding Roof).              7.No Waste Gas Decay Tank Release is in progress.              8.One Noble Gas Radiation Monitor is in operation monitoring the AuxiliaryBuilding Exhaust Stack. (RM-062 or RM-052)(ODCM)              9.One Iodine/Particulate Sampler is in service on the Aux Bldg Stack or Auxiliary Sample Collection Equipment is in service.
(RM-062 or RM-052 Filter)(ODCM).                10.The following recorders are operable or readings will be taken per FC-212 Table I every four hours, per Off-si te Dose Calculation Manual (ODCM):
!RR-049A, Process Rad Mon Rcdr (AI-31E)
!FR-758, Ventilation Stack Total Flow (AI-44)
!PR-745, Post Accident Cntmt Press (AI-44)
!HR-81A(B) H 2 Analyzer VA-81A(B) Recorder (AI-65) 11.Electrical power is available to the desired fan(s):
!VA-80A, Hydrogen Purge Blower, MCC-3C2-C04
!VA-80B, Hydrogen Purge Blower, MCC-4A2-C01 12.At least VA-81 or VA-81B, Containm ent Hydrogen Analyzer is in servicesampling Containment per OI-VA-6.
C Continuous UseFORT CALHOUN STATIONOI-VA-1OPERATING INSTRUCTIONPAGE 21 OF 120 A - Hydrogen Purge Release VA-80A & VA-80B PREREQUISITES (continued)()INITIALS R5513.Containment Release Permit #                    is authorized.
SM/CRS PROCEDURE NOTE RM-051 and/or RM-052, Cntmt Noble Gas Radiation Monitor and the ERF Computer are not required to be operabl e during the hydrogen release but are used for conservative monitoring of Containment during the release. 1.Set the FC-212 count rate limit in the ERF Computer or the radiation monitorat the alert limit. (RM-051 or RM-052)
NOTE The radiation monitor is consider ed inoperable during the check source.
Remaining stationed at the monitor AND ensuring the monitor returns to
 
normal before leaving the area adminis tratively replaces the log entry. 2.Perform check source on all operational Auxiliary Building Exhaust Stack Noble Gas Radiation Monitors (RM-062 and/or RM-052).              3.Verify all operational RM-062 and/or RM-052, Auxiliary Building Exhaust Stack Noble Gas Radiation Monitors, alert and high alarm setpoints are per TBD-IV.7.              4.Ensure Aux Bldg stack flow rate is less than or equal to the FC-212 Value.              5.Record FC-212 initial readings and mark the following operable recorders with the date, time, and release number:
!RR-049A, Process Rad Mon Rcdr (AI-31E)
!FR-758, Ventilation Stack Total Flow (AI-44)
!PR-745, Post Accident Cntmt Press (AI-44)
!HR-81A(B) H 2 Analyzer VA-81A(B) Recorder (AI-65) 6.Place HC-745, Post Accident Cntmt Press, to HAND.
C Continuous UseFORT CALHOUN STATIONOI-VA-1OPERATING INSTRUCTIONPAGE 22 OF 120 A - Hydrogen Purge Release VA-80A & VA-80B PROCEDURE (continued)()INITIALS R557.Perform the following (Corr 26):a.Ensure VA-411, VA-82 Bypass, is closed (IA-VA-411-B1 in FILTERED).      b.Ensure VA-291/VA-279, Cntmt Hy drogen Purge Fan VA-80A Suction Valve from Aux Building/Recirc Valve, combined remote operator is closed.      c.Ensure VA-282/VA-284, Cntmt Hy drogen Purge Fan VA-80B Suction Valve from Aux Building/Recirc Valve, combined remote operator is closed.
CAUTION Do not run both VA-80A and VA-80B in the hydrogen purge release mode at the same time.d.Open the Cntmt Hydrogen Purge valves for the desired unit: 
!VA-80A VA-290/VA-292, Cntmt Hydrogen Pur ge Fan VA-80A Suction Valve from Containment/Cntmt Hydrogen Purge Fan VA-80A Discharge Valve VA-289, Outboard Isolation Valve to Cntmt Hydrogen Purge Fan VA-80A            !VA-80B VA-281/VA-283, Cntmt Hydrogen Pur ge Fan VA-80B Suction Valve from Containment/Cntmt Hydrogen Purge Fan VA-80B Discharge Valve VA-280, Outboard Isolation Valve to Cntmt Hydrogen Purge Fan VA-80B                          8.Record initial hydrogen concentration and sample point in the CR Log.
C Continuous UseFORT CALHOUN STATIONOI-VA-1OPERATING INSTRUCTIONPAGE 23 OF 120 A - Hydrogen Purge Release VA-80A & VA-80B PROCEDURE (continued)()INITIALS R559.IF normal startup, THEN place the H 2 Purge Blower Isolation Valve Inbd Control Switch for the unit to be run to OPEN (AI-43A):
!HCV-882, VA-80A
!HCV-881, VA-80B 10.IF post accident (SIAS tripped) startup, THEN place the H 2 Purge Blower Isolation Valve Inbd Control Switch for the unit(s) to be run to OVRD (AI-43A):
!HCV-882, VA-80A
!HCV-881, VA-80B 11.Perform the following:a.IF normal startup, THEN place the Hydrogen Purge Blower Control Switch to
 
AFTER START for the unit to be started (AI-100): 
!VA-80A!VA-80B            b.IF post accident (SIAS tripped) startup, THEN place the Hydrogen Purge Blower Control Switch in
 
PULL TO OVERRIDE for the unit to be started (AI-100): 
!VA-80A!VA-80B            c.Monitor DPI-899D, Filter Unit Va-82 Differential Pressure Indicator,during the release (Corr 26).      d.IF DPI-899D reading exceeds 25" w.g., THEN perform the following:  1)Notify the Control Room.      2)Obtain TSC permission to open VA-411.
C Continuous UseFORT CALHOUN STATIONOI-VA-1OPERATING INSTRUCTIONPAGE 24 OF 120 A - Hydrogen Purge Release VA-80A & VA-80B PROCEDURE (continued)()INITIALS R5511.d3)Open VA-411, VA-82 Bypass.  (IA-VA-411-B1 to              NON-FILTERED) 12.IF RM-062 and/or RM-052, Auxiliary Building Exhaust Stack Noble Gas Radiation Monitors become inoperable, THEN immediately secure the hydrogen release.                13.IF the ERF becomes inoperable AND t he FC-212 count rate limit was set in the ERF, THEN record RM-051 or RM-052, Cn tmt Noble Gas Radiation Monitor, reading hourly in FC-212 Table 1 and verify the FC-212 count rate limit is not exceeded until the FC-212 count rate limit is set in the radiation monitor.                14.IF the FC-212 Containment radi ation monitor becomes inoperable,THEN notify Chemistry to annotate the release permit.              15.IF RM-051 and/or RM-052 Containm ent Radiation Monitors become inoperable, THEN secure the hydrogen release.
16.During the release, record the following data in FC-212:a.Table I inoperable recorder readings every four hours per Off-site DoseCalculation Manual (ODCM).      b.Table II stop and start readings.      c.Table III release flow readings every four hours by logging Containmentpressure and stack flow.
17.Prior to the release expiration, pl ace the running Hydrogen Purge Blower(s)
Control Switch to AFTER STOP (AI-100):
!VA-80A!VA-80B C Continuous UseFORT CALHOUN STATIONOI-VA-1OPERATING INSTRUCTIONPAGE 25 OF 120 A - Hydrogen Purge Release VA-80A & VA-80B PROCEDURE (continued)()INITIALS R5518.Place the H 2 Purge Blower Isolation Valve Inbd control switches to CLOSE (AI-43A):!HCV-882, VA-80A
!HCV-881, VA-80B 19.Record the FC-212 final readings and mark the following operable recorders with the date, time, and release number:
!RR-049A, Process Rad Mon Rcdr (AI-31E)
!FR-758, Ventilation Stack Total Flow (AI-44)
!PR-745, Post Accident Cntmt Press (AI-44)
!HR-81A(B) H 2 Analyzer VA-81A(B) Recorder (AI-65) 20.Place HC-745, Post Accident Cntmt Press, to AUTO.              21.Log the final hydrogen concentration and sample point in the CR Log.              22.Perform the following (Corr 26):a.Close the following Cntmt Hydrogen Purge valves:
!VA-289, Outboard Isolation Valv e to Cntmt Hydrogen Purge Fan VA-80A!VA-290, VA-80A Suction Valve from Cntmt
!VA-292, VA-80A Discharge Valve
!VA-280, Outboard Isolation Valv e to Cntmt Hydrogen Purge Fan VA-80B!VA-281, VA-80B Suction Valve from Cntmt
!VA-283, VA-80B Discharge Valve
!VA-411, VA-82 Bypass (IA-VA-411-B1 to FILTERED)
 
C Continuous UseFORT CALHOUN STATIONOI-VA-1OPERATING INSTRUCTIONPAGE 26 OF 120 A - Hydrogen Purge Release VA-80A & VA-80B PROCEDURE (continued)()INITIALS R5522b.Lock closed the Cntmt Hydrogen Purge Outboard Isolation Valves to Cntmt Hydrogen Purge Fans: 
!VA-289, VA-80A
!VA-280, VA-80B
 
Ind Verif Completed by Date/Time                /
C Continuous UseFORT CALHOUN STATIONOI-VA-1OPERATING INSTRUCTIONPAGE 27 OF 120 R55 Attachment 5B - Supply of Auxiliary Bu ilding Air to Containment VA-80A & VA-80B PREREQUISITES  () INITIALS1.Procedure Revision Verification Revision No.
Date:
2.Plant is in MODE 4 or 5.              3.OI-VA-1-CL-A has been completed per OP-1.              4.Containment Integrity is not required.              5.Electrical power is available to the desired fan:
!VA-80A, Hydrogen Purge Blower, MCC-3C2-C04
!VA-80B, Hydrogen Purge Blower, MCC-4A2-C01 6.VA-81A or VA-81B is in service per OI-VA-6.
PROCEDURE NOTE One VA-80 Blower may be run supplying Auxiliary Building air to Containment while the other is run for Hydrogen Purge Release.1.Place HC-745, Post Accident Cntmt Press, to HAND.              2.Ensure the following valves combined remote operator is closed, for the desired unit (Corr. 26):
!VA-80A VA-290/VA-292, Cntmt Hydrogen Pur ge Fan VA-80A Suction Valve from Containment/Cntmt Hydrogen Purge Fan VA-80A Discharge Valve             
!VA-80B VA-281/VA-283, Cntmt Hydrogen Pur ge Fan VA-80B Suction Valve from Containment/Cntmt Hydrogen Purge Fan VA-80B Discharge Valve C Continuous UseFORT CALHOUN STATIONOI-VA-1OPERATING INSTRUCTIONPAGE 28 OF 120 B - Supply of Auxiliary Bu ilding Air to Containment VA-80A & VA-80B PROCEDURE (continued)()INITIALS R553.Open the following valves for the desired unit (Corr. 26):
!VA-80A VA-291/VA-279, Cntmt Hydrogen Pur ge Fan VA-80A Suction Valve from Aux Building/recirc Valve VA-289, Outboard Isolation Valve to Cntmt Hydrogen Purge Fan VA-80A                         
!VA-80B VA-282/VA-284, Cntmt Hydrogen Pur ge Fan VA-80B Suction Valve from Aux Building/recirc Valve VA-280, Outboard Isolation Valve to Cntmt Hydrogen Purge Fan VA-80B                          4.Record initial hydrogen concentration and sample point in the CR log.
CAUTION Parts a and b of Step 5 must be per formed in sequence and one immediately following the other to avoid a radiological release to Room 59 and possible
 
damage to VA-80A or VA-80B.5.IF normal startup, THEN:a.Place the Hydrogen Purge Blower control switch to AFTER START for the unit to be started (AI-100):
!VA-80A!VA-80B                          b.Place the H 2 Purge Blower Isolation Valve Inbd control switch for the unit to be run to OPEN (AI-43A):
!HCV-882, VA-80A
!HCV-881, VA-80B
 
C Continuous UseFORT CALHOUN STATIONOI-VA-1OPERATING INSTRUCTIONPAGE 29 OF 120 B - Supply of Auxiliary Bu ilding Air to Containment VA-80A & VA-80B PROCEDURE (continued)()INITIALS R55 CAUTION Parts a and b of Step 6 must be per formed in sequence and one immediately following the other to avoid a radiological release to Room 59 and possible
 
damage to VA-80A or VA-80B.6.IF post accident (SIAS or CIAS tripped) startup, THEN:a.Place the Hydrogen Purge Blower Control Switch in PULL TO OVERRIDE for the unit to be started (AI-100):
!VA-80A!VA-80B                          b.Place the H 2 Purge Blower Isolation Valve Inbd Control Switch for the unit to be run to OVRD (AI-43A):
!HCV-882, VA-80A
!HCV-881, VA-80B 7.When termination is desired:a.Place the H 2 Purge Blower Isolation Valve Inbd Control Switches to CLOSE (AI-43A):
!HCV-882, VA-80A
!HCV-881, VA-80B b.Place the affected Hydrogen Purge Bl ower Control Switch to AFTER STOP (AI-100):
!VA-80A!VA-80B                          8.Place HC-745, Post Accident Cntmt Press, to AUTO.              9.Log the final hydrogen concentration and sample point in CR log.
C Continuous UseFORT CALHOUN STATIONOI-VA-1OPERATING INSTRUCTIONPAGE 30 OF 120 B - Supply of Auxiliary Bu ilding Air to Containment VA-80A & VA-80B PROCEDURE (continued)()INITIALS R5510.Close the following valves for the affected unit (Corr. 26):
!VA-80A VA-291/VA279, Cntmt Hydrogen Purge Fan VA-80A Suction Valve fromAux Building/recirc Valve     
!VA-80B VA-282/VA-284, Cntmt Hydrogen Pur ge Fan VA-80B Suction Valvefrom Aux Building/recirc Valve 11.Lock closed the Cntmt Purge Outboard Isolation Valves to Cntmt Hydrogen Purge Fan:
!VA-289, VA-80A
!VA-280, VA-80B
 
Ind Verif Completed by Date/Time                /
Appendix D Scenario Outline Form ES-D-1 Facility: Fort Calhoun Scenario No: 2005 - 1 Op-Test No. ___________ Examiners:
_________________________
_________________________
 
_________________________  Operators: _________________________
_________________________
 
_________________________
Initial Conditions:
100% Power  IC#1
{ Preset malfunctions: COP RCAF2U1 0%, COP RCAF2U2 0%, MFP EHC02, MFP ESF02A OFF, MFP ESF02B OFF} Turnover: CCW-Pump, AC-3A and Diesel Driven AFW pump FW-54 are tagged out of service Maintain Power Operations Event No. Malf No. Event Type* Event  Description 1 
(3:00) COP T:F212 160 I - ATC Letdown flow transmitter fails high - letdown isolates 2 (10:00) COP T:L903X 0%
60 sec ramp I - BOP S/G "A" level transmitter fails low - manual FW flow control required 3 (15:00) COP NCAPCA1C TRIP C - BOP IA Compressor trips, standby does not load 4 (20:00) MFP CRD06 R1G1 Deenergized C - ATC  Dropped CEA - T/S Entry 5  N/A R - ATC N - BOP TS Required power reduction to 70%
6 (35:00) MFP EDS04B C - ATC Instrument  Bus Fails - T/S Entry 7 (45:00) MSS01A 20% 2 min ramp M - ALL Main steam line break inside containment 8 Preset C - BOP Turbine fails to trip 9 Preset I - ATC or BOP CPHS Fails to Actuate                *        (N)ormal,  (R)eactivity,  (I)nstrument,  (C)omponent,  (M)ajor
 
Appendix D Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 2005-1 Event No.:1 Page 2    of    9 Event
 
== Description:==
Letdown Flow Transmitter Fails High - letdown isolates Time  Position  Applicant's Actions or Behavior  SRO/ATC BOP Responds to  "Letdown High Flow" and "Intermediate Letdown Press HI-LO" alarms  Acknowledges alarms  ATC Reviews ARP-CB-1,2,3/A2 B1L and A1L for appropriate actions  ATC Ensures HCV-204 has automatically closed  ATC Determines that Flow instrument FI-212 has failed high  SRO Directs ATC Operator to override flow interlock and restore letdown flow  ATC Place HC-204-1 "High Flow interlock Override switch" in DEFEAT  ATC Place HC-101-3, Limiter Bypass switch, in BYPASS  ATC Place HIC-101-1/1-1-2 in MANUAL  ATC Close LCV-101-1 and/or LCV-101-2  ATC Place PIC-210 in Manual and throttle to 10% open  ATC Open HCV-204 and (if needed) TCV-202  ATC Initiate letdown flow using HIC-101-1/101-2 while adjusting PCV-210 to maintain letdown pressure approximately 300 psig. Balance charging and letdown flows. ATC  Plsce HC-101-3 in NORMAL  ATC Place HIC-101-1/101-2 and PIC-210 in AUTO  SRO Notify Work Week Manager or I&C of failure with FI-212  ATC Monitor charging and letdown for proper operation Appendix D Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 2005-1 Event No.: 2 Page  3  of    9 Event
 
== Description:==
Steam Generator "A" level transmitter  fails low - manual FW flow control required  Time  Position  Applicant's Actions or Behavior  BOP Identify and communicate lowering indicated level on chart recorder and increased feedwater  flow to the "A" steam generator    SRO Direct BOP to take manual control of feedwater  BOP Take manual control using FIC-1101 and restore steam generator level  BOP Identify LT-903X as the failed instrument  SRO Inform Work Week Manager or I&C of failed instrument  BOP Monitor and control S/G level  BOP If reactor trips, manually throttle feedwater control valve, FIC-1101.
Appendix D Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 2005-1 Event No.: 3 Page  4  of  9  Event
 
== Description:==
Instrument Air compressor "C" trips. Standby (B) does not load.
Time  Position  Applicant's Actions or Behavior  BOP Respond to "Air Compressors BKR trip" and "Plant Air Pressure Low Alarm" and possibly "Instrument Air Pressure Low" alarm  ATC/BOP Refer to ARP CB-10,11 A11 B3L, and A21 B6U (and possibly B6L)  BOP Determine and report instrument air pressure is lowering  SRO May enter AOP-17  SRO Direct BOP to place additional Air Compressor in Service  BOP Start Air Compressor CA-1A. BOP Monitor air pressure and report that air pressure is recovering  SRO  Report Air Compressor failures to Work Week Manager or Maintenance Appendix D Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 2005-1 Event No.: 4 Page  5  of    9 Event
 
== Description:==
Dropped CEA - Tech Spec Entry Time  Position  Applicant's Actions or Behavior  ATC Identify event from "Dropped Rod" and other alarms  (CB-4 A20 E6, CB-4 A8 A5L, B1U, B1L, B2L, B5L, C1U, C2U, C5L)  ATC Determine that only one rod has dropped (rod #1, grp 4)  SRO Enter AOP-02 (CEDM Malfunction)  SRO Direct BOP Operator to adjust turbine load to match reactor power. BOP Reduce turbine load to match reactor power using T-cold indication  SRO Direct ATC to control pressurizer pressure and level  ATC Monitor pressurizer pressure and level  SRO Direct ATC Operator to reset rod drop bistables  ATC Reset rod drop bistables  SRO Notify Work Week Manager or Reactor Engineer  SRO 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 hours. SRO Inform ATC and BOP operators that Tech Specs require a power reduction to less than 70% within one hour. SRO Notify energy marketing of the impending power reduction  BOP Continue manual control of S/G level.
Appendix D Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 2005-1 Event No.: 5 Page  6    of    9 Event
 
== Description:==
Tech Spec re quired power reduction to 70%
Time  Position  Applicant's Actions or Behavior  SRO Direct ATC and BOP to commence a power reduction using AOP-05 or OP-4  SRO Direct ATC operator on method of boration to use. Options are:  Normal boration  Aligning charging pumps suction to SIRWT ATC Begin boration using method directed by SRO  BOP Reduce turbine load using potentiometer as needed to control RCS T-cold  ATC Monitor and control RCS parameters during power reduction  BOP Monitor and control secondary parameters, including manual control of S.G "A" level. SRO Direct the shift chemist to sample the RCS due to the power reduction. ATC May contact the Aux Building Operator to verify sufficient tank capacity for power reduction.
Appendix D Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 2005-1 Event No.: 6 Page  7  of    9 Event
 
== Description:==
Instrument Bus Failure - Tech Spec Entry.
Time  Position  Applicant's Actions or Behavior  BOP/ATC Identify loss of instrument bus "B" due to "Inverter B Trouble" and "Instrument bus B low voltage" alarms and RPS panel indication (dark panel). SRO Enter AOP-16, Section III "Loss of AI-40B"  SRO Notify Manager-FCS, Manager-Operations or Supervisor-Operations that RPS trip units will be bypassed  SRO Provide RPS trip unit bypass keys to ATC and direct ATC operator to bypass all RPS Channel B Bistable trip units  ATC Bypass all RPS Channel B Bistable trip units  SRO/ATC Place HC-111/121 "Reactor REG System Channel selector switch in "A"  ATC  Ensure at least 1 CCW pump running with pressure at least 60 psig. Ensure at least one Raw water pump running  BOP Ensure instrument air pressure at least 90 psig  ATC  Select pressurizer pressure channel "X" using HC-103  Place HC-101-1 heater cutout switch in channel "X" position  Manually control pressurizer heaters as needed  Ensure pressure being controlled  SRO May direct ATC to close both PORV block valves  ATC If directed, close both PORV block valves  ATC Verify at least one RCP operating  BOP Ensure S/G levels within range. Control FW flow as needed. BOP Confirm containment integrity:  Containment sump  Radiation monitors  Containment pressure  Containment temperature  SRO Refer to listed Tech specs and enter tech spec 2.7 One instrument bus may be inoperable for up to 8 hours as long as RPS and ESF functions on all 3 of the other instrument busses remain operable. If not repaired, the plant must be in hot shutdown within the next 12 hours.
SRO Notify Work Week Manager or Maintenance of the failure.
Appendix D Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 2005-1 Event No.: 7, 8 Page  8  of    9 Event
 
== Description:==
Main Steam Line Break inside Containment, turbine fails to trip Time  Position  Applicant's Actions or Behavior  ATC/BOP Identify and communicate lowering RCS temperature and lowering primary and secondary pressures. SRO May direct ATC to trip the reactor  ATC If directed, trip the reactor  ATC Perform Standard Post-Trip Actions:  Verify control rod insertion, power lowering, negative startup rate.
BOP<C>  Verify turbine and generator trip. Determine that turbine did not trip Attempt manual turbine trip then place both EHC pumps in pull-to lock BOP  Verify electrical status - 4160, D/G, instrument power, 125V DC  Verify Instrument air status  ATC  Verify CCW and Raw water status  Verify RCS inventory control  Verify RCS pressure control  Verify core heat removal  BOP  Verify S/G feed -Manually throttle FCV-1101  Verify S/G pressure and T-cold  Verify containment conditions  SRO Diagnose event and enter EOP-05 Appendix D Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 2005-1 Event No.: 8 Page  9  of  9  Event
 
== Description:==
CPHS fails to actuate Time  Position  Applicant's Actions or Behavior  SRO  Direct chemist to sample both S/G's  Direct BOP to verify proper S/G isolation following SGIS signal  BOP Verify SGIS  MSIV's and bypass valves  FW reg and bypass valves  FW reg block valves  FW header isolation valves  ATC/BOP Monitor containment pressure and determine that CPHS did not actuate at setpoint  SRO Direct ATC or BOP to manually actuate CPHS ATC/BOP <C> Manually actuate CPHS  ATC Verify ECCS and Containment Spray flows ATC <C> When RCS pressure reaches 1350 psia, ensure no more than one RCP operating in each loop within 5 minutes  SRO Direct BOP to establish steam flow from intact S/G prior to dryout of faulted steam generator  BOP Establish steam flow from intact S/G prior to dryout of faulted steam generator  ATC Monitor subcooling and pressurizer level and report when "stop and throttle" criteria are met  SRO Direct ATC to throttle and/or stop HPSI flow  ATC Throttle and/or stop HPSI flow  SRO Direct ATC to monitor and control RCS pressure to maintain subcooling between 20&deg; and 200&deg;F. ATC Monitor and control RCS pressure to maintain subcooling between 20&deg; and 200&deg;F. SCENARIO ENDS when "stop and throttle" criteria have been met and HPSI flow has been reduced.
Appendix D Scenario Outline Form ES-D-1 Facility: Fort Calhoun Scenario No: 2005 - 2 Op-Test No. ___________ Examiners:
_________________________
_________________________
 
_________________________  Operators: _________________________
_________________________
 
_________________________
Initial Conditions: 100
% Power  (IC#1)
{PRESET MFP CRD05I untrip, MFP CRD05H untrip, COP T:R057 69,  Start CH-1B, Stop CH-1C)
Turnover: CCW-Pump, AC-3A and Diesel Driven AFW pump FW-54 are tagged out of service Maintain Power Operations Event No. Malf No. Event Type* Event  Description 1
(3:00) MFP NIS04C I - ATC Power Range NI Channel "C" Fails - T/S entry 2 (10:00) COP T:L906X 55% I - BOP S/G "B" level transmitter fails to 55%
3  (16:00) COP NBWPAC9 A trip C - BOP Bearing Water Pump AC-9A Trips 4 (20:00) T:T122H2 665&deg;F I -ATC RCS T-hot fails - T/S entry 5 (30:00) MFP CVC16B C - ATC Charging Pump CH-1B degraded performance 6 (40:00) MFP SGN01A 25% M - ALL Steam Generator Tube Rupture 7  Preset R - ATC 2 CEAs fail to insert - Emergency Boration Required 8
Preset I - BOP RM-057 (Condenser offgas radiation monitor) fails "as is" (Aux Steam Isolation valve, RC-978, does not get close signal)                    *        (N)ormal,  (R)eactivity,  (I)nstrument,  (C)omponent,  (M)ajor
 
Appendix D Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 2005-2 Event No.: 1 Page  2  of    8 Event
 
== Description:==
Power range NI Channel C Fails - Tech Spec Entry.
Time  Position  Applicant's Actions or Behavior  ATC Identify the failure from the "Nuclear Instrumentation Inoperable" and other alarms (CB-4 A20 A1, A5, B1, B6, B7, D5, E4, E6)  SRO Enter AOP-15  SRO Enter Technical Specification 2.15
 
RPS channel "C" trip units 1, 9 and 12 must be placed in bypass with in 1 hour.
48 hour LCO for repair of the channel, otherwise channels 1, 9 and 12 must be placed in the tripped condition.
 
SRO Notify Manager - FCS, Manager - Operations or Supervisor - Operation of RPS trip unit bypass  SRO Obtain the keys and direct the ATC operator to place the 1, 9 and 12 trip units on channel "C" in bypass  ATC Bypass trip units 1, 9 and 12 on RPS channel "C"  ATC/BOP Enter channel bypass information in control room log Appendix D Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 2005-2 Event No.: 2 Page  3  of    8 Event
 
== Description:==
Steam Generator "B" level transmitter fails to 55%.
Time  Position  Applicant's Actions or Behavior  BOP Respond to "S/G-2A level low alarm"  BOP Identify and communicate lowering FW flows and level in S/G "B"  SRO Direct BOP to take manual control of feedwater (FC-1102 in manual)  BOP Take manual control and restore feedwater level before level  (Respond to RC-2B level high alarm if it occurs, CB-4 A8 C5U)  BOP Identify FT-906X as the failed instrument  SRO Notify Work Week Manager or I&C of the instrument failure  BOP Continue to monitor and control S/G levels  BOP If the reactor trips, manually throttle FIC-1102 Appendix D Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 2005-2 Event No.: 3 Page  4  of    8 Event
 
== Description:==
Bearing water pump, AC-9A, trips.
Time  Position  Applicant's Actions or Behavior  BOP Respond to "Cooling water Pressure Low" alarm (CB-10,11 A11 B6U)  BOP Report that AC-9A has tripped  SRO Direct BOP to start AC-9B BOP<C> Start AC-9B  SRO Direct BOP to verify status of  Instrument Air System  BOP Ensure that air compressor is operating and instrument air pressure normal or restoring  SRO May enter AOP-20                                     
 
Appendix D Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 2005-2 Event No.: 4 Page  5  of    8 Event
 
== Description:==
RCS Hot Leg RTD fails - Tech Spec Entry Time  Position  Applicant's Actions or Behavior  ATC 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. ATC/BOP Reviews ARP  ATC  Checks power, pressure and temperature indications and determines that the alarm is caused by failed T-hot channel (A/T122H)  SRO Enters Tech Spec 2.15 
 
Because trip units 1, 9 and 12 are already bypassed on RPS channel "C". 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 hours or else the plant must be placed in hot shutdown within the following 12 hours.
SRO 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 or else notify I&C to trip the trip units with one hour.
ATC If directed, use the channel "A" PTTI to trip the trip units on channel "A" by placing the test enable switch in ENABLE
 
SRO Notifies Plant or Operations Management and the Work Week Manager or I&C of the failure Appendix D Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 2005-2 Event No.: 5 Page  6  of    8 Event
 
== Description:==
Charging pump, CH-1B, degraded performance. Tech. Spec Entry Time  Position  Applicant's Actions or Behavior  ATC Respond to "Charging Low Flow" alarm (CB-1,2,3 A2 A6L)  ATC Identifies and reports oscillations in charging flow indication  SRO Directs ATC to start another charging pump  ATC Starts additional charging pump and monitors charging and letdown  SRO Directs ATC to have EONA check out charging pump. (EONA reports flow in the discharge to suction relief valve)  ATC Reports open relief valve to SRO  SRO Directs ATC to shutdown charging pump  ATC Shuts down charging pump  SRO Refers to Tech Spec 2.2.4 and Enters  Tech Spec 2.15 paragraph 5 for CH-1B  7 day LCO due to charging pump CH-1B controls on alternate shutdown panel Appendix D Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 2005-2 Event No.: 6, 7 Page  7  of    8 Event
 
== Description:==
Steam Generator T ube Rupture, 2 CEAs fail to insert Time  Position  Applicant's Actions or Behavior  ATC Identify and report RCS inventory loss  ATC/BOP Report rising radiation levels on RM-054A  SRO May direct manual reactor trip  ATC If directed, manually trip reactor ATC<C> Perform Standard Post-Trip Actions: Verify control rod insertion, power lowering, negative startup rate. Determine that 2 CEAs did not insert and begin Emergency Boration:  Ensure FCV-269X and Y are closed  Open  HCV-268, HCV-265 and HCV-258  Start both Boric Acid Pumps  Start all available charging pumps  Close LCV-218-2  Ensure LCV-218-3, HCV-257 and HCV-264 are closed  BOP  Verify turbine and generator trip  Verify electrical status - 4160, D/G, instrument power, 125V DC  Verify Instrument air status  ATC  Verify CCW and Raw water status  Verify RCS inventory control  Verify RCS pressure control  Verify core heat removal  BOP  Verify S/G feed -Manually throttle FCV-1102  Verify S/G pressure and T-cold  Verify containment conditions  SRO Diagnose event and enter EOP-04 Appendix D Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 2005-2 Event No.: 8 Page  8  of    8 Event
 
== Description:==
Condenser Offgas Radiation Monitor, RM-057, fails as is (Aux Steam Isolation valve, RC-978, does not get close signal)
Time  Position  Applicant's Actions or Behavior  BOP Determine that RCV-978 did not close  SRO Direct BOP to close RCV-978 BOP<C> Close RCV-978  SRO Direct RCS cooldown - T-hot less than 510&deg;F  BOP Cooldown RCS T-hot to less than 510&deg;F  ATC Identify and verify PPLS actuation  ATC When RCS pressure reaches 1350 psia, ensure no more than 1 RCP operating in each loop  SRO/BOP Identify most affected S/G as "A"  SRO Direct BOP to isolate S/G "A"  BOP Isolate S/G "A". Close the following  HCV-1041A (A MSIV)  HCV-1041C (A MSIV bypass)  MS-291 (atmospheric steam safety valve)  FCV-1101 (FW reg valve)  HCV-1105 ( FW reg bypass valve)  HCV-1386 (FW header isolation)  HCV-1103 (FW reg block valve)  HCV-1388A&B (blowdown isolation valves)  HCV-1107A&B (AFW isolation)  YCV-1045A (steam supply to AFW pump) Direct the turbine building to close:  MS-298 (MSIV packing leakoff)  SRO Direct ATC to maintain RCS pressure less than 1000 psia and within 50 psi of ruptured S/G  ATC Control RCS pressure less than 1000 pisa and within 50 psi or ruptured S/G  SCENARIO ENDS with  S/G "A"  isolated and RCS pressure reduction in progress Appendix D Scenario Outline Form ES-D-1 Facility: Fort Calhoun Scenario No: 2005 - 3 Op-Test No. ___________ Examiners:
_________________________
_________________________
 
_________________________  Operators: _________________________
_________________________
 
_________________________
Initial Conditions: 49% Power  (IC#4)
{PRESET RFP CWS10N CLOSED} {Power 1A1 and 1A2 from 22KV, S/D CH-1A) Turnover: Heater Drain pumps FW- 5A and FW-5C are tagged out of service. Power held at 50%
pending repair of at least one of the heater drain pumps.
Event No. Malf No. Event Type* Event  Description 1
(3:00) MFP DSG06A 100% C - ATC or BOP D/G #1 Radiator Leak - T/S Entry 2 (12:00) COP T:P910 1000 psi I - BOP PT-910 Fails High 3 (18:00) COP T:T2897 50&deg;F I - ATC Letdown heat exchanger temperature transmitter fails low 4 (25:00) MFP SWD02B C - BOP Loss of 161 KV - T/S Entry 5 (35:00) COP T:P103Y 2556 90 sec ramp I - ATC Pressurizer pressure transmitter PT-103X fails high 6 (40:00) COP T: L906Y 100%  60 sec ramp I - BOP S/G "B" level transmitter LT-906X fails high (Manual control using Aux controller required) 7 (45:00) MFP RWS01B 25% C - ATC Raw Water header leak 8 (55:00) MFP RCS01C 5% M - ALL LOCA with Loss of offsite power 9 Preset C-BOP Circulating Water Pump Br eaker does not open so the D/G breaker does not close.            *        (N)ormal,  (R)eactivity,  (I)nstrument,  (C)omponent,  (M)ajor
 
Appendix D Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 2005-3 Event No.: 1 Page  2  of    9 Event
 
== Description:==
Diesel Generator #1 Radiator Water Leak - Tech Spec Entry Time  Position  Applicant's Actions or Behavior  ATC Identify event from "Diesel Trouble" alarm and low water tank level light (takes about two minutes after malfunction initiated)  ATC/BOP Refer to ARP AI30A A30 A3U LS-4  SRO Direct EONT to check diesel. (EONT reports water on the D/G room floor)  SRO Direct ATC to place D/G 1 mode selecter switch in "OFF-AUTO"  ATC Place D/G 1 mode selecter switch in "OFF-AUTO"  SRO Enter Tech Spec 2.7
 
D/G-1 must be restored to operable within seven days. SRO Notify Work Week Manager or Maintenance of Diesel problem Appendix D Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 2005-3 Event No.: 2 Page  3  of    9 Event
 
== Description:==
Steam Header Pressure Transmitter, PT-910, Fails High causing turbine bypass valve to open.
Time  Position  Applicant's Actions or Behavior  BOP Identify rapid decrease in RCS T-cold (VOPT ANN will alarm if uncorrected)  ATC/BOP If VOPT annunciator alarms, refer to ARP. BOP Determine cause as turbine bypass valve, PCV-910, being open  (red light on CB-1,2,3)  SRO Direct BOP to take manual control of PCV-910 and close it. BOP Monitor RCS T-cold  ATC Monitor and control RCS parameters  SRO Notify Work Week Manager or I&C of the failure of PT-910.
Appendix D Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 2005-3 Event No.: 3 Page  4  of    9 Event
 
== Description:==
Letdown heat exchanger temperature transmitter, T-2897, fails low reducing CCW flow to letdown heat exchanger.
Time  Position  Applicant's Actions or Behavior  ATC Respond to "Letdown Heat Exchanger Tube Outlet Temp HI" alarm  BOP/ATC Refer to ARP  ATC Determine that TCV-211-2 has repositioned to bypass ion exchangers  ATC Determine that high letdown temperature was caused by reduced CCW flow to letdown heat exchanger due to closure of TCV-2897  SRO Direct ATC to manually control CCW flow to letdown heat exchanger using TCV-2897  ATC Manually control TCV-2897 to restore letdown temperature  SRO May direct ATC to reposition TCV-211-2 and maintain 100&deg;F - 120&deg;F  ATC Reposition TCV-211-2 if directed  SRO Report failure of  T-2897 to Work Week Manager or I&C Appendix D Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 2005-3 Event No.: 4 Page  5  of    9 Event
 
== Description:==
Loss of 161 KV offsite power to plant - Tech Spec Entry Time  Position  Applicant's Actions or Behavior  BOP 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. 
 
SRO Enter AOP-31, section II "All 4160 busses fed from 22 KV" Direct BOP to verify 1 FW pump, 1 Condensate pump and 1Heater drain pump operating  BOP Verify 1 FW pump, 1 Condensate pump and 1, Heater drain pump operating  SRO Direct BOP to ensure Main Generator Terminal voltage less than 22,000 Volts  BOP Verifies Main Generator Terminal Voltage - no adjustment needed  SRO Direct BOP to align secondary pumps as needed. BOP Align secondary pumps as directed  SRO Direct BOP to verify 480 bus voltages greater than 430 volts  BOP Verify voltages  SRO Direct BOP to match flags on breakers 110, 111, 1A31, 1A33, 1A42, 1A44  BOP Match flags on breakers 110, 111, 1A31, 1A33, 1A42, 1A44  SRO Direct that signs be placed at entrances to switchgear rooms Review EOP-02, EOP-07 and EOP-20  SRO 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 hours. 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 SRO Report situation to station management.
Appendix D Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 2005-3 Event No.: 5 Page  6  of    9 Event
 
== Description:==
Pressurizer Pressure Transmitter PT-103Y fails high Time  Position  Applicant's Actions or Behavior  ATC Respond to "Pressurizer Pressure Off-Normal HI/LO Channel Y Alarm"  ATC Identify and report high indication on controlling channel and lowering pressure on other channel  ATC/BOP Refer to ARP  SRO Direct ATC to transfer pressurizer pressure control to channel "X" or take manual control of pressurizer pressure  ATC Transfer pressurizer pressure control to channel "X" or take manual control of pressurizer pressure, as directed  ATC Monitor and control pressurizer pressure Appendix D Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 2005-3 Event No.: 6 Page  7  of    9 Event
 
== Description:==
Steam Generator "B" Level Transmitter LT:906Y fails high Time  Position  Applicant's Actions or Behavior  BOP Responds to "Feedwater Control Steam Generator RC-2B Level HI" alarm  ATC/BOP Refers to ARP-CB-4/A8  BOP Determines S/G level  and trend using LR-906X  BOP Identifies and reports that FCV-1102 has closed  SRO Directs BOP to reopen FCV-1102 and manually control FW flow BOP <C> Takes manual control of FCV-1102 Auxiliary controller and opens valve as needed to control S/G level. SRO Notifies Work Week Manager or I&C of failure Appendix D Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 2005-3 Event No.: 7 Page  8  of    9 Event
 
== Description:==
Raw Water Header Leak Time  Position  Applicant's Actions or Behavior  ATC Respond to "Raw Water Pump Room Level Hi" Alarm  CB-1,2,3 A2 D6U, D6L  SRO Direct Water Plant Operator to check out Raw Water pumps. (Water Plant operator reports water leak downstream of AC-10B's discharge valve, HCV-2851)  SRO Direct ATC to trip Raw Water pump, AC-10B. May direct ATC to stop all Raw Water Pumps  ATC Stop Raw Water pumps as directed. Ensure pump discharge vales close Knowledge "Raw Water Supply Header Press LO Alarms", if received  SRO/ATC Verify CCW temperature is less than or equal to 110&deg;F  SRO Direct ATC to isolate the rupture ATC<C> Isolate the rupture by closing:  HCV-2874A/B  HCV-2875A/B  SRO Direct the ATC to start (or ensure running) at least one Raw Water Pump other than AC-10B  ATC Start raw water Pump(s) as directed  ATC Verify "Raw Water Supply Header Pressure LO" alarms have cleared  SRO Enter Tech. Spec 2.4 for Raw Water pump AC-10B being inoperable. With D/G-1 inoperable, only one Raw Water would operate in the event of a loss offsite power.
SRO Report pipe rupture to Work Week Manager or Maintenance Appendix D Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 2005-3 Event No.: 8, 9 Page  9  of    9 Event
 
== Description:==
LOCA with a loss of all offsite power, Circulating Water pump breaker fails to open keeping D/G breaker from closing: Station Blackout Time  Position  Applicant's Actions or Behavior  ATC Identify and communicate lowering pressurizer level and pressure  SRO May direct ATC to trip the reactor  ATC Manually trip the reactor  ATC Perform Standard Post-Trip Actions:  Verify control rod insertion, power lowering, negative startup rate. BOP  Verify turbine and generator trip.
BOP  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 it's breaker has not closed  Verify Instrument air status  ATC  Verify CCW and Raw water status  Verify RCS inventory control  Verify RCS pressure control  Verify core heat removal  BOP  Verify S/G feed  Verify S/G pressure and T-cold  Verify containment conditions  ATC Report PPLS actuated but no SI flow BOP <C> Report that CW-1C breaker failed to trip. (This prevents D/G-2 breaker from closing)  SRO  Direct EONT to manually trip the breaker for CW-1C  SRO Enter EOP-20. Go to MVA-AC  SRO When D/G-2 output breaker closes, Direct BOP to verify bus 1A4 voltage  SRO Direct ATC and BOP to ensure the following:  CCW and Raw Water Pumps operating  HPSI, LPSI and Containment Spray Pumps Operating  Adequate HPSI and Containment Spray flow  Containment Cooling  Reactor Vessel Level  ATC/BOP Ensure the above parameters as directed  SCENARIO ENDS with bus 1A4 energized and adequate SI flow being injected into RCS Appendix D Scenario Outline Form ES-D-1 Facility: Fort Calhoun Scenario No: 2005 - 4 (spare) Op-Test No. ___________ Examiners:
_________________________
_________________________
 
_________________________  Operators: _________________________
_________________________
 
_________________________ Initial Conditions: 49% Power
{Preset MSS02F 100% E1 30 sec delay} { Place 1A1 and 1A2 on 22 KV, S/D CH-1A} Turnover: Heater Drain pumps FW- 5A and FW-5C are tagged out of service. Power held at 50%
pending repair of at least one of the heater drain pumps.
Event No. Malf No. Event Type* Event  Description 1
(3:00) COP JLB218LL Fail_set I - ATC VCT Level Transmitter Fails Low 2 (8:00) COP T:L903X 100% 45 sec ramp I - BOP S/G "A" Level transmitter fails high 3 (15:00) COP T:F114YA 0 I - ATC RCS Flow transmitter failure - T/S Entry 4 (22:00) MFP AFW05A I - BOP Inadvertent AFAS actuation - T/S Entry 5 (30:00) COP RCAP 849A&B 0% C - ATC Instrument air to containment isolates 6 (40:00) MFP CND01 100% 300 sec ramp C - BOP Loss of condenser vacuum 7
N/A M - ALL Reactor Trip - no steam dump and bypass valves 8 Preset C - BOP S/G safety valve sticks open                    *        (N)ormal,  (R)eactivity,  (I)nstrument,  (C)omponent,  (M)ajor
 
Appendix D Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 2005-4 Event No.: 1 Page  2  of    8 Event
 
== Description:==
VCT Level Transmitter fails low CB-1,2,3 A2 B2L Time  Position  Applicant's Actions or Behavior  ATC Respond to "Volume Control  Tank Level LO-LO" alarm  ATC/BOP Refer to ARP-CB-1,2,3/A2 B2L  SRO Direct ATC to check VCT level  ATC Report that level on channel LIC-219 is normal  ATC Report that charging pump suction swapped to SIRWT  SRO/ATC Determine that level switch failed  SRO Direct ATC to open LCV-218-2 and close LCV-218-3 ATC<C> Open LCV-218-2 and close LCV-218-3  ATC Monitor and control primary parameters  BOP Monitor and control secondary parameters  ATC Optional: may place off-normal placards on LCV-218-2 and LCV-218-3 switches  SRO Notify Work Week Manager or I&C of the level switch failure Appendix D Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 2005-4 Event No.: 2 Page  3  of    8 Event
 
== Description:==
Steam Generator "A"  level transmitter 903X fails high.
Time  Position  Applicant's Actions or Behavior  BOP Identify and communicate lowering FW flow and level in S/G "A"  SRO Direct BOP to take manual control of feedwater flow  BOP Take manual control and restore feedwater flow. BOP Identify LT-903X as the failed instrument  SRO Inform Work Week Manager or I&C of the failure of LT-903X  BOP Continue to monitor and control S/G level. BOP If the reactor trips, manually throttle FIC-1101 Appendix D Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 2005-4 Event No.: 3 Page  4  of    8 Event
 
== Description:==
RCS Flow transmitter failure. Tech Spec entry.
Time  Position  Applicant's Actions or Behavior  ATC Responds to "Low Flow Reactor Coolant Channel" trip and pretrip alarms  ATC/BOP Refer to ARP-CB-4/A20 A2,B2  ATC Determines that reactor coolant loop differential pressure transmitter A/114Y on S/G "B" has failed low  SRO Enters Tech Spec 2.15
 
RCS Low Flow trip unit on RPS channel A must be tripped or bypassed within one hour  SRO Notifies Manager-FCS, Manager-OPS or Supervisor-OPS that trip unit will be bypassed  SRO Obtains key and directs ATC to bypass trip unit #3 (low RCS flow trip) on RPS channel "A"  ATC Places "A" Low Flow Trip Unit #3 in bypass  SRO Notifies Work Week Manager or I&C of instrument failure Appendix D Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 2005-4 Event No.:4 Page  5  of    8 Event
 
== Description:==
Inadvertent AF AS actuation - Tech Spec Entry Time  Position  Applicant's Actions or Behavior  BOP Identify AFAS from numerous alarms  A66A C4L,  A66B C3M&U  SRO Enter AOP-28  SRO Direct BOP to isolate AFW to the steam generators  BOP Close HCV-1107A&B  SRO Direct EONT to bypass the affected AFAS channel (RFP ESF10A bypass)  SRO Direct the BOP to secure the AFW pumps  BOP Override and Close YCV-1045, YCV-1045A and YCV-1045B to stop FW-10 Place FW-6 switch in pull-to-lock  SRO Refer to Tech Specs 2.5, 2.15 and 2.01
 
Plant is in a 6 hour LCO with no operable AFW pumps Appendix D Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 2005-4 Event No.: 5 Page  6  of    8 Event
 
== Description:==
Instrument Air Containment Isolation valve fails closed.
Time  Position  Applicant's Actions or Behavior  ATC/BOP Respond to various alarms, loss of letdown flow and S/G blowdown flow  (CB-1,2,3 A1 A6U, A6L, B6U, B6L) (CB-1,2,3 A2 B5U, B5L) (CB-10,11 A21 B2L)  ATC/BOP Determine that letdown and blowdown low flow due to closure of the instrument air containment isolation valves  SRO May enter AOP-17 or refer to AOP-17, attachment "A" for a list of valves affected  SRO Direct ATC to manually control charging pumps to control pressurizer level  ATC Manually control charging pump operation as needed  SRO Dispatch EONA to check out HCV-1849B  SRO Notify Work Week Manager or Maintenance of the problem Appendix D Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 2005-4 Event No.: 6, 7 Page  7  of    8 Event
 
== Description:==
Loss of Condenser Vacuum, Reactor Trip - no steam dump and bypass valves Time  Position  Applicant's Actions or Behavior  BOP Identifies lowering condenser vacuum from "Condenser A/B pressure low" alarm and/or vacuum indication  ATC/BOP Refers to ARP-CB-10,11/A9 A4U, A4L, B6L  SRO Dispatches EONT and/or water plant operator to check vacuum pump operation and then look for vacuum leaks  BOP Ensures backup vacuum pump started  SRO Enters AOP-26  SRO Directs plant shutdown using AOP-05 or OP-4  ATC Begins boration of the RCS using method directed by SRO Must ensure charging pump is running  BOP Reduces turbine load as needed to control RCS T-cold  SRO May direct manual reactor trip  ATC Trip reactor if directed  ATC Perform Standard Post-Trip Actions:  Verify control rod insertion, power lowering, negative startup rate. BOP  Verify turbine and generator trip. Verify electrical status - 4160, D/G, instrument power, 125V DC  Verify Instrument air status ATC  Verify CCW and Raw water status  Verify RCS inventory control  Verify RCS pressure control  Verify core heat removal  BOP  Verify S/G feed -Manually throttle FCV-1102  Verify S/G pressure and T-cold  Verify containment conditions Appendix D Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 2005-4 Event No.: 8 Page  8  of    8 Event
 
== Description:==
Steam Genera tor Safety Valve sticks open Time  Position  Applicant's Actions or Behavior  ATC Identify lowering pressurizer pressure  BOP Identify lowering T-cold and S/G pressure SRO Enter EOP-05  SRO Provide EOP-05 floating steps to ATC and BOP  ATC Report approach to PPLS  SRO Direct ATC to verify proper operation of ESF  ATC Ensure proper safeguards operation and adequate SI flow  ATC If RCS pressure lowers to 1350 psia, ensure no more than one RCP operating in each loop ATC <C> Ensure adequate emergency boration. Will have to reposition LCV-218-2 and LCV-218-3  SRO/BOP Identify affected S/G "B"  SRO Direct BOP to isolate affected S/G  BOP Isolate affected S/G  BOP Establish FW flow to good S/G. May need to manually start AFW pump  SRO Direct BOP to establish steam flow from good S/G prior to dryout of affected S/G BOP <C> Begins steaming good S/G prior to dryout of  affected S/G  ATC Report when "HPSI stop and throttle" criteria are met  SRO Direct ATC to perform "HPSI Stop and Throttle" ATC <C> Throttle HPSI loop injection valves and/or stop HPSI pumps as needed Ensure HPSI "Stop and Throttle" criteria continue to be met (20&deg;F subcooling)    SCENARIO ENDS with HPSI stop and throttle and RCS pressure and temperature under control}}

Latest revision as of 15:58, 15 January 2025

FCS-07/2005-Draft Operating Exam
ML052300144
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 05/11/2005
From: Koske J
Omaha Public Power District
To:
NRC Region 4
References
50-285/05-301, AJPM-RO-CO-1
Download: ML052300144 (280)
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