Text

07-2005-Final Operating Exam
	ML061070599
Person / Time
Site:	Fort Calhoun
Issue date:	05/11/2005
From:	; NRC Region 4
To:	; Omaha Public Power District
References
	50-285/05-301
	Download: ML061070599 (316)
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Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: AJPM-RO-CO-1 JPM

Title:

Shutdown margin with inoperable CEA 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:

Page 1 of 5

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: AJPM-RO-CO-1 JPM

Title:

Shutdown margin with inoperable CEA Operators Name: _____________________ Employee # ______________

All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):

SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________

Reason, if unsatisfactory:

Tools & Equipment: Technical Data Book, calculator Safety Considerations: None Comments:

Page 2 of 5

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: AJPM-RO-CO-1 JPM

Title:

Shutdown margin with inoperable CEA INITIATING CUE: The plant is operating at 100% power with all CEAs fully withdrawn.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 After candidate locates TDB-V.9 in the Technical Data Book, provide a copy of TDB-V.9 Part I.

[ SAT ] [ UNSAT ]

2 Obtain a copy of TDB section Obtains copy of TDB-II II, Reactivity Curves.

[ SAT ] [ UNSAT ]

3 Determines part I of TDB Performs calculation using part procedure should be used. 1.

[ SAT ] [ UNSAT ]

4 Performs calculation of the Difference calculated on line difference between actual and 11 of TDB-V.9, section 1 is required shutdown margin. -0.42 [between -0.22, -0.62]

[ SAT ] [ UNSAT ]

5 Determines if SDM is adequate Shutdown margin is adequate

[ SAT ] [ UNSAT ]

Page 3 of 5

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: AJPM-RO-CO-1 JPM

Title:

Shutdown margin with inoperable CEA Termination Criteria: Shutdown Margin determination has been made Page 4 of 5

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: AJPM-RO-CO-1 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 Page 5 of 5

FORT CALHOUN STATION TDB-V.9 TECHNICAL DATA BOOK PAGE 1 OF 15 SHUTDOWN MARGIN WORKSHEET PART I - Instantaneous Shutdown Margin for use prior to a Reactor Trip or immediately following 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 Data Book and carry the algebraic signs through the calculations.

Condition

1. Present Date/Time: /

2. Reactor Power (before trip): %

3. CEA Positions: Group 1 inches Group 2 inches Group 3 inches Group 4 inches

4. Reactor Coolant System Boron Concentration prior to shutdown: (Boron concentration analysis must have been performed within the past 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or more recently if boration or dilution has occurred.)

ppm 4

5. Burnup (Take the most recent burnup from the Control Room Log and add 30 MWD/MTU per EFPD.)

MWD/MTU 5

Calculation of Shutdown Margin

6. Enter Regulating Group Worth, based on burnup (Step 5) and CEA positions (Step 3) using TDB Figure II.B.2.

% p TDB Figure used:

6 R35

FORT CALHOUN STATION TDB-V.9 TECHNICAL DATA BOOK PAGE 2 OF 15

7. Enter Shutdown Group Worths, based on burnup (Step 5) using TDB Figure II.B.1.a.

a. Shutdown Group B % p

b. Shutdown Group A % p

c. Total Shutdown Worth

+ = % p 7.a 7.b 7.c

8. Determine Power Defect Enter Power Defect based on Reactor power level (Step 2) and burnup (Step 5) using TDB 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 as inoperable.

(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. Enter the 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 R35

FORT CALHOUN STATION TDB-V.9 TECHNICAL DATA BOOK PAGE 3 OF 15 NOTE: The worth of one inoperable CEA is dependent on the configuration of the withdrawn group(s) and the inoperable CEA.

9. b. Case II - One CEA is known to be inoperable (per Technical Specification 2.10.2(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 the value 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 multiplying the 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 total reactivity 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 Technical Specification 2.10.2.(4)a.).

(Enter N/A if this case is not applicable.)

(1) Enter total number of CEAs which are known to be inoperable per Technical Specification 2.10.2.(4) a.).

9.c.(1)

(2) Enter the most conservative defective CEA worth from TDB FIGURE 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 R35

FORT CALHOUN STATION TDB-V.9 TECHNICAL DATA BOOK PAGE 4 OF 15

9. d. Enter total available CEA worth from TDB Figure II.B.1.a. based on burnup (Step 5)

% p 9.d

e. Determine the maximum stuck CEA worth by selecting the minimum of either 9.c or 9.d and record that value.

% p 9.e

f. Enter value from 9.a or 9.b or 9.e as appropriate %p 9.f

10. Calculation of the Total Instantaneous Shutdown Margin (SDMI):

SDMI = Stuck CEAs + Power Defect - S/D CEAs worth - Regulating CEA worth SDMI = % + % - % - % = % Total 9.f 8 7.c 6 10

11. 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 Shutdown condition, Tc > 210EF (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 the number of gallons of acid to add.

REMARKS Completed by Date/Time /

R35

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: AJPM-RO-CO-2 JPM

Title:

Minimum HPSI flow with Containment Sump Blockage 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:

Page 1 of 5

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: AJPM-RO-CO-2 JPM

Title:

Minimum HPSI flow with Containment Sump Blockage Operators Name: _____________________ Employee # ______________

All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):

SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________

Reason, if unsatisfactory:

Tools & Equipment: EOP-AOP Attachments Safety Considerations: None Comments:

Page 2 of 5

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: AJPM-RO-CO-2 JPM

Title:

Minimum HPSI flow with Containment Sump Blockage 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 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and 20 minutes have elapsed since the reactor tripped due to the LOCA.

The CRS has also asked you to determine when 3 charging pumps would be able to provide adequate injection flow to remove decay heat.

START Critical Steps shown in gray STEP ELEMENT STANDARD 1 Obtains a copy of EOP/AOP Locates EOP/AOP attachments. attachments. (Do not provide)

[ SAT ] [ UNSAT ]

2 Refers to the proper Refers to the second page of attachment Attachment 26 (EOP/AOP attachments page 149 of 150)

[ SAT ] [ UNSAT ]

3 Determines required HPSI flow. Determines that 132 gpm HPSI flow is the minimum required to remove decay heat

[acceptable range - 128 to 136 gpm]

[ SAT ] [ UNSAT ]

Page 3 of 5

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: AJPM-RO-CO-2 JPM

Title:

Minimum HPSI flow with Containment Sump Blockage STEP ELEMENT STANDARD 4 Determines when 3 charging Determines that the flow from pumps will be able to provide 3 charging pumps (120 gpm) the required charging flow. will be adequate 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months and 50 minutes after the trip.

[acceptable range- 3 hour3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months 45 minutes to 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months s]

[ SAT ] [ UNSAT ]

Termination Criteria: Candidate has determined HPSI flow required to remove decay heat and time when charging pump flow will be adequate.

Page 4 of 5

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: AJPM-RO-CO-2 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 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and 20 minutes have elapsed since the reactor tripped due to the LOCA.

The CRS has also asked you to determine when 3 charging pumps would be able to provide adequate injection flow to remove decay heat.

START Page 5 of 5

EOP/AOP ATTACHMENTS Page 148 of 150 Attachment 26 Total SI Pump Flow to Match Decay Heat vs. Time R18

EOP/AOP ATTACHMENTS Page 149 of 150 Attachment 26 Total SI Pump Flow to Match Decay Heat vs. Time R18

EOP/AOP ATTACHMENTS Page 150 of 150 Attachment 26 Total SI Pump Flow to Match Decay Heat vs. Time R18

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: AJPM-RO-EC-1 JPM

Title:

Boration paths with equipment out of service 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:

Page 1 of 5

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: AJPM-RO-EC-1 JPM

Title:

Boration paths with equipment out of service Operators Name: _____________________ Employee # ______________

All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):

SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________

Reason, if unsatisfactory:

Tools & Equipment: SOs, TDB and plant drawings Safety Considerations: None Comments:

Page 2 of 5

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: AJPM-RO-EC-1 JPM

Title:

Boration paths with equipment out of service 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:

(1) the borated water source(s) and (2) 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 Refers to plant one line be affected by deenergizing the electrical drawing (or other busses suitable plant reference) and determines that there will be no power to CH-1A, SI-2A and SI-2C.

[ SAT ] [ UNSAT ]

Page 3 of 5

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: AJPM-RO-EC-1 JPM

Title:

Boration paths with equipment out of service STEP ELEMENT STANDARD 2 Determines BAST suitability as Refers to TDB-VI (COLR) a boric acid source 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 can be a source by itself, but together they can count as one source.

[ SAT ] [ UNSAT ]

3 Determines SIRWT suitability Determine that the SIRWT can as a boric acid source 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.

[ SAT ] [ UNSAT ]

4 Determines if two independent Determines that 2 independent boration paths are available boration paths are available:

with the buses deenergized 1. CH-11A AND CH-11B and identifies them. (source) through (pump) CH-1B

2. SIRWT (Source) through pump SI-2B

[ SAT ] [ UNSAT ]

Termination Criteria: Boration paths have been identified.

Page 4 of 5

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: AJPM-RO-EC-1 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:

(1) the borated water source(s) and (2) pump for each boration path.

START Page 5 of 5

FORT CALHOUN STATION TDB-VI TECHNICAL DATA BOOK PAGE 19 OF 19 100 90 80 MINIMUM BAST LEVEL (PERCENT INDICATOR) 70 60 50 40 30 20 10 0

2.5 2.7 2.9 3.1 3.3 3.5 3.7 3.9 4.1 4.3 4.5 STORED BAST CONCENTRATION (WT % BORIC ACID) 1800 PPM 1900 PPM 2000 PPM 2150 PPM 2300 PPM IN SIRWT IN SIRWT IN SIRWT IN SIRWT IN SIRWT CYCLE 23 MINIMUM BAST LEVEL vs. STORED FIGURE COLR BAST CONCENTRATION 9 R30

Fort Calhoun Station SO-O-21 R21 Page 21 of 36 Attachment 7.1 - Shutdown Condition 1 - Refueling Cavity Water Level Greater Than or Equal to 23 feet Above the Top of the Core (elev. 1025.2 feet) with UGS Removed Key Safety Function Minimum Options Initial (Available unless otherwise specified) Required (Circle available trains and place check mark next to each operating train.)

Reactivity Control Borated Water Source (operable) 1 CH-11A CH-11B CH-11A + SIRWT >6" SIRWT >14" (Charging) (Charging) CH-11B (1 HPSI) (2 HPSI)

(TDB-VI) (TDB-VI) (Charging)

(TDB-VI)

Boration Pumps (1 operable) 2 CH-1A CH-1B CH-1C SI-2A SI-2B SI-2C Wide Range NI (operable) 1 AI-31A AI-31B AI-31C AI-31D Containment Containment Fan with Cooling Water 1 VA-3A VA-3B VA-7C VA-7D Radiation Monitor 1 RM-051 RM-052 RM-062 CRHS/VIAS Channels 1 86A/CRHS 86B/CRHS 86A/VIAS 86B/VIAS

Only available if RCS temperature is less than 120º F

- Only available if continuously monitored

- - Although indication may be pegged high, credit may be taken if channel would respond to significant lowering of refueling cavity water level Performed by STA: Date/Time: /_____

Reviewed by SSA: Date/Time: /_____

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: AJPM-RO-RC-1 JPM

Title:

RCA Entry and Exit with spill 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:

Page 1 of 6

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: AJPM-RO-RC-1 JPM

Title:

RCA Entry and Exit with spill Operators Name: _____________________ Employee # ______________

All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):

SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________

Reason, if unsatisfactory:

Tools & Equipment: None Safety Considerations: None Comments: This JPM will be performed during RCA entrance and exit during conduct of in-plant JPMs.

Page 2 of 6

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: AJPM-RO-RC-1 JPM

Title:

RCA Entry and Exit with spill INITIATING CUE: You have been directed 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

[ SAT ] [ UNSAT ]

2 Determine Radiological Checks survey maps and/or Conditions in Room 13. discusses radiological conditions with RP personnel.

[ SAT ] [ UNSAT ]

3 Obtains Dosimetry Verify TLD attached to security badge. Obtain EAD.

[ SAT ] [ UNSAT ]

4 Sign in on appropriate RWP Insert EAD in reader. Scan PID and RWP number

[ SAT ] [ UNSAT ]

Page 3 of 6

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: AJPM-RO-RC-1 JPM

Title:

RCA Entry and Exit with spill STEP ELEMENT STANDARD 5 Enter RCA RCA entered

[ SAT ] [ UNSAT ]

6 Enter Room 13 Enters Room 13 As soon as candidate clears shield wall while entering room 13:

CUE: Floor covered with water.

7 Exits Room and Contacts Leaves Room Immediately Control Room. and Contacts Control Room.

[ SAT ] [ UNSAT ]

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

[ SAT ] [ UNSAT ]

CUE: All parameters for FW-34A are normal 9 Exits Room 13 Exits room

[ SAT ] [ UNSAT ]

Note to Examiner:

In-plant JPMs that are conducted in the RCA may be performed at this time.

Steps 10 and 11 are Page 4 of 6

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: AJPM-RO-RC-1 JPM

Title:

RCA Entry and Exit with spill STEP ELEMENT STANDARD performed during RCA exit.

10 Monitor for personnel Monitor for contamination contamination prior to exiting using PCM RCA

[ SAT ] [ UNSAT ]

11 Sign out of RCA Insert EAD in reader, enter PID number and confirm dose

[ SAT ] [ UNSAT ]

Termination Criteria: RCA has been exited Page 5 of 6

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: AJPM-RO-RC-1 INITIATING CUE: You have been directed to enter Room 13 to ensure that blowdown tank transfer pump, FW-34A is operating properly.

START Page 6 of 6

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: AJPM-SRO-CO-1 JPM

Title:

Shutdown Margin Review with Boron Depletion 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:

Page 1 of 5

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: AJPM-SRO-CO-1 JPM

Title:

Shutdown Margin Review with Boron Depletion Operators Name: _____________________ Employee # ______________

All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):

SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________

Reason, if unsatisfactory:

Tools & Equipment: Technical Data Book, calculator Safety Considerations: None Comments:

Page 2 of 5

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: AJPM-SRO-CO-1 JPM

Title:

Shutdown Margin Review with Boron Depletion 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 been 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 STAs Shutdown Margin Calculation.

START Critical Steps shown in gray STEP ELEMENT STANDARD 1 Obtain a copy of TDB section Obtains copy of TDB-II II, Reactivity Curves.

[ SAT ] [ UNSAT ]

2 Reviews the shutdown margin Reviews the shutdown margin calculation 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.

[ SAT ] [ UNSAT ]

Page 3 of 5

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: AJPM-SRO-CO-1 JPM

Title:

Shutdown Margin Review with Boron Depletion STEP ELEMENT STANDARD 4 Corrects calculation and Determines that shutdown determines SDM 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.

[ SAT ] [ UNSAT ]

Termination Criteria: Shutdown Margin calculation has been reviewed and corrected.

Page 4 of 5

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: AJPM-SRO-CO-1 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 been 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 STAs Shutdown Margin Calculation.

START Page 5 of 5

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: AJPM-SRO-CO-2 JPM

Title:

Equipment Operability Requirements during Mode Change 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:

Page 1 of 4

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: AJPM-SRO-CO-2 JPM

Title:

Equipment Operability Requirements during Mode Change Operators Name: _____________________ Employee # ______________

All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):

SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________

Reason, if unsatisfactory:

Tools & Equipment: None Safety Considerations: None Comments:

Page 2 of 4

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: AJPM-SRO-CO-2 JPM

Title:

Equipment Operability Requirements during Mode Change INITIATING CUE: The reactor has been shutdown for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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 a procedure change could be made to OP-3A, step 25 and OI-SI-1, prerequisite 2 to allow Safety Injection Tanks to be isolated when RCS pressure is below 1000 psia. They would like to isolate HCV-2954 and HCV-2974.

START Critical Steps shown in gray STEP ELEMENT STANDARD 1 Checks Technical Refers to Tech Sec section 2.3 Specifications and determines that this condition is allowed by Tech Specs.

[ SAT ] [ UNSAT ]

2 Refers to TDB-III.42 Refers to TDB-III.42 and determines that SIT Isolation valves must remain locked open until RCS pressure is below 400 psia.

[ SAT ] [ UNSAT ]

Termination Criteria: Candidate determines if condition is allowable or not.

Page 3 of 4

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: AJPM-SRO-CO-2 INITIATING CUE: You are an SRO assigned to the One Stop Shop during a refueling outage. The reactor has been shutdown for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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 Page 4 of 4

TECHNICAL SPECIFICATIONS 2.0 LIMITING CONDITIONS FOR OPERATION 2.3 Emergency Core Cooling System Applicability Applies to the operating status of the emergency core cooling system.

Objective To assure operability of equipment required to remove decay heat from the core.

Specifications (1) Minimum Requirements The reactor shall not be made critical unless all of the following conditions are met:

a. The SIRW tank contains not less than 283,000 gallons of water with a boron concentration of at least the refueling boron concentration at a temperature not less than 50oF.

b. One means of temperature indication (local) of the SIRW tank is operable.

c. All four safety injection tanks are operable and pressurized to at least 240 psig and a maximum of 275 psig with tank level of at least 116.2 inches (67%) and a maximum level of 128.1 inches (74%) with refueling boron concentration.

d. One level and one pressure instrument is operable on each safety injection tank.

e. One low-pressure safety injection train is operable on each associated 4,160 V engineered safety feature bus.

f. One high-pressure safety injection pump is operable on each associated 4,160 V engineered safety feature bus.

g. Both shutdown heat exchangers are operable.

h. Piping and valves shall be operable to provide two flow paths from the SIRW tank to the reactor coolant system.

i. All valves, piping and interlocks associated with the above components and required to function during accident conditions are operable. HCV-2914, 2934, 2974, and 2954 shall have power removed from the motor operators by locking open the circuit breakers in the power supply lines to the valve motor operators.

FCV-326 shall be locked open.

2.3 - Page 1 Amendment No. 17,32,43,103,117, 119,133,141,157,175,217,221

TECHNICAL SPECIFICATIONS 2.0 LIMITING CONDITIONS FOR OPERATION 2.3 Emergency Core Cooling System (Continued)

(1) j. One high-pressure safety injection pump is operable on each safety injection refueling water tank-containment sump header.

2.3 - Page 2 Amendment No. 17

TECHNICAL SPECIFICATIONS 2.0 LIMITING CONDITIONS FOR OPERATION 2.3 Emergency Core Cooling System (Continued)

(2) Modification of Minimum Requirements During power operation, the Minimum Requirements may be modified to allow one of the following conditions to be true at any one time. If the system is not restored to meet the minimum requirements within the time period specified below, the reactor shall be placed in a hot shutdown condition within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . If the minimum requirements are not met within an additional 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months the reactor shall be placed in a cold shutdown condition within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

a. One low-pressure safety injection train may be inoperable provided the train is restored to operable status within seven (7) days.

b. One high-pressure safety injection pump may be inoperable provided the pump is restored to operable status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

c. One shutdown heat exchanger may be inoperable for a period of no more than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

d. Any valves, interlocks or piping directly associated with one of the above components and required to function during accident conditions shall be deemed to be part of that component and shall meet the same requirements as listed for that component.

- - e. Any valve, interlock or piping associated with the safety injection and shutdown cooling system which is not covered under d. above but which is required to function during accident conditions may be inoperable for a period of no more than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

f. One safety injection tank may be inoperable for reasons other than g. or h. below for a period of no more than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

g. Level and/or pressure instrumentation on one safety injection tank may be inoperable for a period of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

h. One safety injection tank may be inoperable due to boron concentration not within limits for a period of no more than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

- - SEE TDB-VIII 2.3 - Page 3 Amendment No. 49,171,175,186,206,217, 223

TECHNICAL SPECIFICATIONS 2.0 LIMITING CONDITIONS FOR OPERATION 2.3 Emergency Core Cooling System (Continued)

(3) Protection Against Low Temperature Overpressurization The following limiting conditions shall be applied during scheduled heatups and cooldowns. Disabling of the HPSI pumps need not be required if the RCS is vented through at least a 0.94 square inch or larger vent.

Whenever the reactor coolant system cold leg temperature is below 350EF, at least one (1) HPSI pump shall be disabled.

Whenever the reactor coolant system cold leg temperature is below 320EF, at least two (2) HPSI pumps shall be disabled.

Whenever the reactor coolant system cold leg temperature is below 270EF, all three (3) HPSI pumps shall be disabled.

In the event that no charging pumps are operable when the reactor coolant system cold leg temperature is below 270EF, a single HPSI pump may be made operable and utilized for boric acid injection to the core, with flow rate restricted to no greater than 120 gpm.

(4) Trisodium Phosphate (TSP)

During operating Modes 1 and 2, the TSP baskets shall contain a volume of active TSP that is within the area of acceptable operation shown in Figure 2-3.

a. With the above TSP requirements not within limits, the TSP shall be restored within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

b. With Specification 2.3(4)a required action and completion time not met, the plant shall be in hot shutdown within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and cold shutdown within the following 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

Basis The normal procedure for starting the reactor is to first heat the reactor coolant to near operating temperature by running the reactor coolant pumps. The reactor is then made critical. The energy stored in the reactor coolant during the approach to criticality is substantially equal to that during power operation and therefore all engineered safety features and auxiliary cooling systems are required to be fully operable.

2.3 - Page 4 Amendment No. 17,39,43,47,64,74,77, 100,103,133,141,157,161,179,201,221, 232

PAGE 1 OF 12 Fort Calhoun Station Unit 1 TDB-III.42 TECHNICAL DATA BOOK REQUIREMENTS FOR ECCS AND CONTAINMENT COOLING EQUIPMENT OPERATION IN MODE 3, TRANSITION BETWEEN MODES 3 AND 4 AND MODE 4 AND 5 Change No. EC 36060 Reason for Change Converted from WordPerfect to Word.

Requestor N/A Preparer J. Collier Editorial Correction N/A Issue Date 06-16-05 3:00 pm R2

FORT CALHOUN STATION TDB-III.42 TECHNICAL DATA BOOK PAGE 2 OF 12 REQUIREMENTS FOR ECCS AND CONTAINMENT COOLING EQUIPMENT OPERATION IN MODE 3, TRANSITION BETWEEN MODES 3 AND 4 AND MODE 4 AND 5 The purpose of this TDB section is to clarify the ESF, ECCS and Containment Cooling Equipment required in mode 3, the transitional conditions between mode 3 and mode 4 and modes 4 and 5. The transitional conditions are divided into four groupings, as defined below, and subsections are presented for each.

Applicability Statement for Startup The applicability of the requirements contained herein differ between plant startup and plant shutdown. Since the decay heat and RCS energy during startup is considerably lower (following subcritical operation > 24 hrs) the following guidance is provided for plant startup conditions.

HPSI Pumps must be available for manual actuation between Tave>300EF and Tave<450EF. At or above 450EF and prior to unblocking PPLS, at least one (1) HPSI Pump must be available for CPHS auto initiation and Operations Personnel must be prepared to manually start this pump.

Safety Injection Tanks (SITs) are required to be unisolated before reaching an RCS temperature and pressure of 515EF and 1700 psia.

LPSI/CS systems must be aligned and operable prior to mode 3.

All other requirements per table 1 & 2 apply.

Section Description Page Table 1 - ECCS Equipment Summary ..........................................................................................3 Table 2 - Containment Cooling Equipment Summary...................................................................4

1. MODE 3 AND MODE 3-4 TRANSITION 1 (PPLS ENABLED)...............................................5

2. MODE 3 - 4 TRANSITION 2 ..................................................................................................6

3. MODE 3 - 4 TRANSITION 3 ..................................................................................................9

4. MODE 3-4 TRANSITION 4 AND MODE 4 AND 5 ...............................................................12 R2

FORT CALHOUN STATION TDB-III.42 TECHNICAL DATA BOOK PAGE 3 OF 12 Table 1 - ECCS Equipment Summary Mode 3 and Transition 1 Transition 2 Transition 3 Transition 4 and Mode 4-5 Tave Mode 3 < 515 EF < 515 EF < 515 EF < 300 EF Equipment >515EF 300 EF 300 EF 300 EF RCS 1700 psia < 1700 psia < 400 psia < 400 psia Press 400 psia ECCS Equipment SIRWT 218,000 Gallons Total (122) 218,000 Gallons Total (122") 218,000 Gallons Total (122)

Refueling Boron Concentration Refueling Boron Concentration Refueling Boron Concentration Ref. SO-O-21 50EF 50EF 50EF SIRWT Instr. 1 Temp Indicator 1 Temp Indicator 1 Temp Indicator SIRWT Path 2 1 1 SIT 4 (1) 4 N/A 1 OOS for 24 hrs 1 OOS for 24 hrs SIT Instr. 1-Press (1) 1-Press N/A 1-Level 1-Level 1 SIT OOS for 72 hrs if inoperable (1) 1 SIT OOS for 72 hrs if inoperable due to level/pressure instrument or due to level/pressure instrument or boron concentration boron concentration SIT Isolation Locked Open (1) Locked Open Closed LPSI Pumps 1 on each bus N/A N/A 1 OOS for 7 days HPSI Pumps 1 on each bus, (1) 1 Available 1 Available 1 on each header 1 OOS for 24 hrs 1

SDC Hx 2 N/A N/A 1 OOS for 24 hrs Actions Cold S/D within 24 hrs if not Cold S/D within 24 hrs if not restored Cold S/D within 24 hrs if not restored within 48 hrs within 48 hrs restored within 48 hrs (1) See Applicability Statement for Startup requirements R2

FORT CALHOUN STATION TDB-III.42 TECHNICAL DATA BOOK PAGE 4 OF 12 Table 2 - Containment Cooling Equipment Summary Mode 3 and Transition 1 Transition 2 Transition 3 Transition 4 and Mode 4-5 Tave Mode 3 < 515 EF < 515 EF < 515 EF < 300 EF Equipment >515EF 300 EF 300 EF 300 EF RCS 1700 psia < 1700 psia < 400 psia < 400 psia Press 400 psia Containment Cooling Equipment On DG-1 Bus AC-10A (3) One component AC-10A (3) One component AC-10A (3) One component Refer to SOPP, SO-O-21 AC-10C listed may be AC-10C listed may be AC-10C listed may be AC-3A unavailable for not AC-3A unavailable for not AC-3A unavailable for not AC-3C more than seven days. AC-3C more than seven days. AC-3C more than seven days.

1 SI-3A Two components may VA-3A Two components may VA-3A Two components may VA-3A be unavailable for not VA-7C be unavailable for not VA-7C be unavailable for not VA-7C more than 24 hrs. more than 24 hrs. more than 24 hrs.

On DG-2 Bus AC-10B Same as DG-1 Bus AC-10B Same as DG-1 Bus AC-10B Same as DG-1 Bus AC-10D AC-10D AC-10D AC-3B AC-3B AC-3B VA-3B VA-3B VA-3B VA-7D VA-7D VA-7D (2) SI-3B (2) SI-3C CCW Hx 3 3 3 2 oos for 48 hrs 2 oos for 48 hrs 2 oos for 48 hrs Action Cold S/D within 24 hrs if not Cold S/D within 24 hrs if not Cold S/D within 24 hrs if not restored within 48 hrs restored within 48 hrs restored within 48 hrs (2) See Applicability Statement for Startup requirements (3) If the river water temperature is below 60 degrees Fahrenheit, one Raw Water pump may be unavailable indefinitely without applying any LCO action statement. When the river water temperature is greater than 60 degrees Fahrenheit, an unavailable Raw Water pump shall be restored to operability within nine days.

R2

FORT CALHOUN STATION TDB-III.42 TECHNICAL DATA BOOK PAGE 5 OF 12 Mode 3, Hot Shutdown Tavg > 515F; Reactor Sub-Critical Mode 3-4 Transition 1, 515EF > Tavg $300EF; RCS Pressure $1700 psia Reactor Sub-Critical

1. MODE 3 AND MODE 3-4 TRANSITION 1 (PPLS ENABLED) 1.1 ECCS Equipment 1.1.1 Requirements 1.1.1.A During Mode 3 and Transition 1 the SIRWT contains not less than 218,000 gallons of water with a boron concentration of at least the refueling concentration at a temperature not less than 50EF.

1.1.1.B Per Technical Specification 2.3(1) (Reference Applicability Statement for Startup requirements) 1.1.2 Allowable Out of Service Times Per Technical Specification 2.3 (2); the requirements of 1.1.1 above may be modified to allow one of the following conditions to be true at any one time. If the system is not restored to meet the minimum requirements within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , the Reactor shall be placed in a Cold Shutdown condition within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

See T.S. 2.3(2)a through h 1.2 Containment Cooling Equipment 1.2.1 Requirements Per Technical Specification 2.4(1) (Reference Applicability Statement for Startup requirements) In Mode 3 (Hot Shutdown) or lower, only three Component Cooling heat exchangers are required to be operable.

1.2.2 Allowable Out of Service Times Per Technical Specification 2.4 (2); the requirements of 1.2.1 above may be modified to allow one of the following conditions to be true at any one time. If the system is not restored to meet the minimum requirements within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , the Reactor shall be placed in a Cold Shutdown condition within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

See T.S. 2.4(2)a through d R2

FORT CALHOUN STATION TDB-III.42 TECHNICAL DATA BOOK PAGE 6 OF 12 Mode 3-4 Transition 2, 515F > Tavg $300F; 1700 psia > RCS Pressure $400 psia Reactor Sub-Critical

2. MODE 3 - 4 TRANSITION 2 2.1 ECCS Equipment 2.1.1 Requirements (Reference Applicability Statement for Startup requirements)

The following ensures ECCS equipment will be available to provide the required amount of water injection during an accident:

2.1.1.A The SIRW tank contains not less than 218,000 gallons of water with a boron concentration of at least the refueling boron concentration at a temperature not less than 50F.

2.1.1.B One means of local temperature indication on the SIRW tank is operable.

2.1.1.C All four Safety Injection Tanks are un-isolated with pressure and level per Tech Spec 2.3(1)c with at least the refueling boron concentration.

2.1.1.D One level and one pressure instrument is available on each Safety Injection Tank.

2.1.1.E One High-Pressure Safety Injection pump is available for automatic actuation.

2.1.1.F Piping and valves shall provide one flow path from the SIRW tank to the Reactor Coolant System.

2.1.1.G All valves, piping and interlocks associated with the above components and required to function during accident conditions are available for automatic actuation.

2.1.2 Allowable Out of Service Times The requirements of 2.1.1 may be modified to allow one of the following conditions to be true at any one time. If the system is not restored to meet the minimum requirements within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , the Reactor shall be placed in a Cold Shutdown condition within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

2.1.2.A One Safety Injection Tank may be inoperable for reasons other than 2.1.2.B and 2.1.2.C below for a period of not more than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

2.1.2.B Level and/or pressure instrumentation on one Safety Injection Tank may be inoperable for a period of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

2.1.2.C One Safety Injection Tank may be inoperable due to boron concentration not within limits for a period of no more than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

R2

FORT CALHOUN STATION TDB-III.42 TECHNICAL DATA BOOK PAGE 7 OF 12 Mode 3-4 Transition 2, 515F > Tavg $300F; 1700 psia > RCS Pressure $400 psia Reactor Sub-Critical (continued) 2.2 Containment Cooling Equipment 2.2.1 Requirements (Reference Applicability Statement for Startup requirements)

The following ensures containment cooling equipment will be available for automatic actuation to reduce the containment building pressure and to remove decay heat from Containment.

2.2.1.A The following equipment normally associated with Diesel-Generator DG-1 (4.16-kV bus 1A3 and associated non-automatically transferring 480-Volt bus sections) is available for automatic actuation to provide containment cooling:

Raw water pump . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .AC-10A Raw water pump . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . AC-10C Component cooling water pump . . . . . . . . . . . . . . . . . . . . . .AC-3A Component cooling water pump . . . . . . . . . . . . . . . . . . . . . .AC-3C Containment air cooling and filtering unit . . . . . . . . . . . . . . . VA-3A Containment air cooling unit . . . . . . . . . . . . . . . . . . . . . . . . .VA-7C 2.2.1.B The following equipment normally associated with Diesel-Generator DG-2 (4.16-kV 1A4 and associated non-automatically transferable 480 Volt bus sections) is available for automatic actuation to provide containment cooling:

Raw water pump . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .AC-10B Raw water pump . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . AC-10D Component cooling water pump . . . . . . . . . . . . . . . . . . . . . .AC-3B Containment air cooling and filtering unit . . . . . . . . . . . . . . . VA-3B Containment air cooling unit . . . . . . . . . . . . . . . . . . . . . . . . .VA-7D 2.2.1.C Three Component Cooling heat exchangers shall be available to provide containment cooling.

2.2.1.D All valves, piping and interlocks associated with the above components and required to function during accident conditions are available for automatic actuation to provide containment cooling.

R2

FORT CALHOUN STATION TDB-III.42 TECHNICAL DATA BOOK PAGE 8 OF 12 Mode 3-4 Transition 2, 515F > Tavg $300F; 1700 psia > RCS Pressure $400 psia Reactor Sub-Critical (continued) 2.2.2 Allowable Out of Service Times The requirements of 2.2.1 above may be modified to allow one of the following conditions to be true at any one time. If the system is not restored to meet the minimum requirements within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , the Reactor shall be placed in a Cold Shutdown condition within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

2.2.2.A One of the components listed in 2.2.1.A and 2.2.1.B may be unavailable for not more than seven days.

2.2.2.B For cases involving Raw Water pump unavailability, if the river water temperature is below 60 degrees Fahrenheit, one Raw Water pump may be unavailable indefinitely without applying any LCO action statement. When the river water temperature is greater than 60 degrees Fahrenheit, an unavailable Raw Water pump shall be restored to operability within seven days.

2.2.2.C The minimum requirements may be modified to allow a total of two of the components listed in 2.2.1.A and 2.2.1.B to be unavailable at any one time for not more than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . (this does not include one Raw Water pump which may be unavailable as described above if the river water temperature is below 60 degrees Fahrenheit). Only two Raw Water pumps may be out of service.

2.2.2.D Two Component Cooling heat exchangers may be unavailable for up to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

2.2.2.E Any valves, interlocks and piping directly associated with one of the above components and required to function during accident conditions shall be deemed to be part of that component and shall meet the same requirements as for that component.

R2

FORT CALHOUN STATION TDB-III.42 TECHNICAL DATA BOOK PAGE 9 OF 12 Mode 3-4 Transition 3, 515F > Tavg $300F; RCS Pressure < 400 psia Reactor Sub-Critical

3. MODE 3 - 4 TRANSITION 3 3.1 ECCS Equipment 3.1.1 Requirements (Reference Applicability Statement for Startup requirements)

The following ensures ECCS equipment will be available to provide the required amount of water injection during an accident.

3.1.1.A The SIRW tank contains not less than 218,000 gallons of water with a boron concentration of at least the refueling boron concentration at a temperature not less than 50F.

3.1.1.B One means of local temperature indication on the SIRW tank is operable.

3.1.1.C One High-Pressure Safety Injection pump is available.

3.1.1.D Piping and valves shall provide one flow path from the SIRWT to the Reactor Coolant System.

3.1.1.E All valves, piping and interlocks associated with the above components and required to function during accident conditions are available.

3.1.2 Allowable Out of Service Times If the system Is not restored to meet the minimum requirements as stated above within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , the Reactor shall be placed in a Cold Shutdown condition within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

R2

FORT CALHOUN STATION TDB-III.42 TECHNICAL DATA BOOK PAGE 10 OF 12 Mode 3-4 Transition 3, 515F > Tavg $300F; RCS Pressure < 400 psia Reactor Sub-Critical (continued) 3.2 Containment Cooling Equipment 3.2.1 Requirements The following ensures containment cooling equipment will be available to reduce the Containment Building pressure and to remove decay heat from Containment.

3.2.1.A The following equipment normally associated with Diesel-Generator DG-1 (4.16-kV bus 1A3 and associated non-automatically transferring 480-Volt bus sections) is available to provide containment cooling:

Raw water pump . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .AC-10A Raw water pump . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . AC-10C Component cooling water pump . . . . . . . . . . . . . . . . . . . . . .AC-3A Component cooling water pump . . . . . . . . . . . . . . . . . . . . . .AC-3C Containment air cooling and filtering unit . . . . . . . . . . . . . . . VA-3A Containment air cooling unit . . . . . . . . . . . . . . . . . . . . . . . . .VA-7C 3.2.1.B The following equipment normally associated with Diesel-Generator DG-2 (4.16-kV 1A4 and associated non-automatically transferable 480 Volt bus sections) is available to provide containment cooling:

Raw water pump . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .AC-10B Raw water pump . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . AC-10D Component cooling water pump . . . . . . . . . . . . . . . . . . . . . .AC-3B Containment air cooling and filtering unit . . . . . . . . . . . . . . . VA-3B Containment air cooling unit . . . . . . . . . . . . . . . . . . . . . . . . .VA-7D 3.2.1.C Three Component Cooling heat exchangers shall be available to provide containment cooling.

3.2.1.D All valves, piping and interlocks associated with the above components and required to function during accident conditions are available to provide containment cooling.

R2

FORT CALHOUN STATION TDB-III.42 TECHNICAL DATA BOOK PAGE 11 OF 12 Mode 3-4 Transition 3, 515F > Tavg $300F; RCS Pressure < 400 psia Reactor Sub-Critical (continued) 3.2.2 Allowable Out of Service Times The requirements of 3.2.1 above may be modified to allow one of the following conditions to be true at any one time. If the system is not restored to meet the minimum requirements within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , the Reactor shall be placed in a Cold Shutdown condition within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

3.2.2.A One of the components listed in 3.2.1.A and 3.2.1.B may be unavailable for not more than seven days.

3.2.2.B For cases involving Raw Water pump unavailability, if the river water temperature is below 60 degrees Fahrenheit, one Raw Water pump may be unavailable indefinitely without applying any LCO action statement. When the river water temperature is greater than 60 degrees Fahrenheit, an unavailable Raw Water pump shall be restored to operability within seven days.

3.2.2.C The minimum requirements may be modified to allow a total of two of the components listed in 3.2.1A and 3.2.1B to be unavailable at any one time for not more than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . (this does not include one Raw Water pump which may be unavailable as described above if the river water temperature is below 60 degrees Fahrenheit). Only two Raw Water pumps may be out of service.

3.2.2.D Two Component Cooling heat exchangers may be unavailable for up to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

3.2.2.E Any valves, interlocks and piping directly associated with one of the above components and required to function during accident conditions shall be deemed to be part of that component and shall meet the same requirements as for that component.

R2

FORT CALHOUN STATION TDB-III.42 TECHNICAL DATA BOOK PAGE 12 OF 12 Mode 3-4 Transition 4, 300F > Tavg; RCS Pressure < 400 psia, and Mode 4 and 5 Reactor Sub-Critical

4. MODE 3-4 TRANSITION 4 AND MODE 4 AND 5 4.1 ECCS Equipment 4.1.1 Requirements Per T.S. 2.1.1 (3) and T.S. 2.8 and Standing Order O-21 (SOPP) 4.2 Containment Cooling Equipment 4.2.1 Requirements Standing Order SO-O-21 (Shutdown Operations Protection Plan) provides guidance related to equipment required during shutdown conditions.

R2

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: AJPM-SRO-EC-1 JPM

Title:

Review of OP-ST-SHIFT-0001 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:

Page 1 of 5

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: AJPM-SRO-EC-1 JPM

Title:

Review of OP-ST-SHIFT-0001 Operators Name: _____________________ Employee # ______________

All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):

SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________

Reason, if unsatisfactory:

Tools & Equipment: None Safety Considerations: None Comments:

Page 2 of 5

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: AJPM-SRO-EC-1 JPM

Title:

Review of OP-ST-SHIFT-0001 INITIATING CUE: You are acting as Shift 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- Reviews each Monday 1900 SHIFT-0001 reading on provided portion of OP-ST-SHIFT-0001

[ SAT ] [ UNSAT ]

2 Determines that RCS Cold Leg On page 9 of 49, determines Temperature does not meet that the maximum difference acceptance criteria. between Tcold cal on AI-31A and the highest Tcold is greater than 0.2°F. Determines that calibration is required using OI-RPS-2.

[ SAT ] [ UNSAT ]

3 Determines that the On page 14 of 49, determines acceptance criteria for RM-057 that counts have doubled on are not met. RM-057. Determines that SO-G-105 must be entered and contacts the Shift Chemist for a primary-secondary sample.

[ SAT ] [ UNSAT ]

Page 3 of 5

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: AJPM-SRO-EC-1 JPM

Title:

Review of OP-ST-SHIFT-0001 Termination Criteria: The Shift Manager review of the provided portion of OP-ST SHIFT-0001 has been completed.

Page 4 of 5

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: AJPM-SRO-EC-1 INITIATING CUE: You are acting as Shift 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 Page 5 of 5

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: AJPM-SRO-RC-1 JPM

Title:

Approve Gas Decay Tank Release Approximate Time: 15 min Actual Time: _________________

Reference(s): OI-WDG-2 Form FC-213 JPM Prepared by: Jerry Koske Date: 06/21/05 JPM Reviewed by: Date:

JPM Approved by: Date:

Page 1 of 5

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: AJPM-SRO-RC-1 JPM

Title:

Approve Gas Decay Tank Release Operators Name: _____________________ Employee # ______________

All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):

SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________

Reason, if unsatisfactory:

Tools & Equipment: None Safety Considerations: None Comments:

Page 2 of 5

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: AJPM-SRO-RC-1 JPM

Title:

Approve Gas Decay Tank Release INITIATING CUE:

You are the Shift Manager. A release of Waste Gas Decay Tank WD-29A 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.

[ SAT ] [ UNSAT ]

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.

[ SAT ] [ UNSAT ]

Determines that the radiation monitor used in the release permit is RM-062 while the radiation monitor in operation on OI-WDG-2 is RM-052

[ SAT ] [ UNSAT ]

Page 3 of 5

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: AJPM-SRO-RC-1 JPM

Title:

Approve Gas Decay Tank Release STEP ELEMENT STANDARD Refuses to authorize the release

[ SAT ] [ UNSAT ]

Termination Criteria: Shift Manager has made a decision on release Authorization Page 4 of 5

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: AJPM-SRO-RC-1 INITIATING CUE:

You are the Shift Manager. A release of Waste Gas Decay Tank WD-29A has been scheduled using OI-WDG-2, Attachment 1. You have been requested to authorize the release.

START Page 5 of 5

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: AJPM-SRO-EP-1 JPM

Title:

Emergency Classification and PARs Approximate Time: 15 minutes Actual Time: _________________

Reference(s): EPIP-OSC-1 R37 EPIP-EOF-7 R15 JPM Prepared by: Jerry Koske Date: 06/21/05 JPM Reviewed by: Date:

JPM Approved by: Date:

Page 1 of 5

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: AJPM-SRO-EP-1 JPM

Title:

Emergency Classification and PARs Operators Name: _____________________ Employee # ______________

All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):

SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________

Reason, if unsatisfactory:

Tools & Equipment: None Safety Considerations: None Comments:

Page 2 of 5

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: AJPM-SRO-EP-1 JPM

Title:

Emergency Classification and PARs INITIATING CUE: The plant was tripped following a RCS leak to containment. The RCS pressure has stabilized at 1050 psia. The pressurizer is empty. RVLMS level is 63%. All Safeguards equipment operated as designed. One RCP is operating in each loop. RCS Dose equivalent Iodine-131 is 200 uCi/g. 40°F subcooling is indicated on all CETs and RCS RTDs.

The meteorological indications are as follows:

A B

Indicated 10m wind speed (mph): 17 14

Indicated wind direction: 330° 330°

Indicated T (°C/100m) -1.7° -1.4°

It is raining, 0.9 inches daily total Two hour doses from EAGLE are all less than 1 mrem.

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

[ SAT ] [ UNSAT ]

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.

[ SAT ] [ UNSAT ]

Page 3 of 5

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: AJPM-SRO-EP-1 JPM

Title:

Emergency Classification and PARs STEP ELEMENT STANDARD 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) 3 Determine Protective Action Refer to EPIP-EOF-7 and Recommendations determine that there are no PARs for this situation.

Document on form FC-1188

[ SAT ] [ UNSAT ]

Termination Criteria: The event has been classified. PARS have been determined and FC-1188 has been completed.

Page 4 of 5

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: AJPM-SRO-EP-1 INITIATING CUE: The plant was tripped following a RCS leak to containment. The RCS pressure has stabilized at 1050 psia. The pressurizer is empty. RVLMS level is 63%. All Safeguards equipment operated as designed. One RCP is operating in each loop. RCS Dose equivalent Iodine-131 is 200 uCi/g. 40°F subcooling is indicated on all CETs and RCS RTDs.

The meteorological indications are as follows:

A B

Indicated 10m wind speed (mph): 17 14

Indicated wind direction: 330° 330°

Indicated T (°C/100m) -1.7° -1.4°

It is raining, 0.9 inches daily total Two hour doses from EAGLE are all less than 1 mrem.

You are directed to enter the Emergency Plan, classify the event and determine offsite Protective Action Recommendations.

Complete page 1 of form FC-1188.

Page 5 of 5

FORT CALHOUN STATION FC-1188 GENERAL FORM R18 FORT CALHOUN STATION - EMERGENCY NOTIFICATION FORM Off-Site Contact Time: Person Making Off-Site Report: Contactors 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 Weather Wind Speed MPH Precipitation: [ ] Yes [ ] No Degrees (10m): (Use Slowest 10m):

-[ ] A [ ]B [ ]C [ ]D [ ]E [ ]F [ ] G+

Stability Class_____

(use most positive T) -1.9 >-1.9 to -1.7 >-1.7 to -1.5 >-1.5 to -0.5 >-0.5 to 1.5 >1.5 to 4.0 > 4.0

3. There [ ] is [ ] no release of radioactive effluent to the

[ ] was [ ] an airborne environment that is the result of or

[ ] will be [ ] a liquid 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 (a)

JPM

Title:

Fill Safety Injection Tanks Location: Simulator Approximate Time: 18 minutes Actual Time: _________________

Reference(s): OI-SI-1 , R79 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:

Page 1 of 10

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0329 (a)

JPM

Title:

Fill Safety Injection Tanks Operators Name: _____________________ Employee # ______________

All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):

SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________

Reason, if unsatisfactory:

Tools & Equipment: Key for HCV-2928 Safety Considerations: None Comments: Run MFP SIS05A 5% until alarm comes in. Use Exam Load IC# 106.

Page 2 of 10

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0329 (a)

JPM

Title:

Fill Safety Injection Tanks INITIATING CUE: You have been directed to fill only SI-6A to 72% using HPSI pump SI-2A, HCV-312 and 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 AI-30A Valve OPEN and RED light lit.

HCV-386 AI-30B Valve OPEN and RED light lit.

[ SAT ] [ UNSAT ]

2 (2) Ensure HCV-2983, SI Check AI-30A valve leakage Header CVCS GREEN light lit Isolation valve is closed

[ SAT ] [ UNSAT ]

3 (3.a.1) Place the selected leakage AI-30A cooler discharge valves in PCV-2949 CS to MANUAL manual: AMBER light OFF

PCV-2929 PCV-2909 CS to MANUAL

PCV-2909 AMBER light OFF

PCV-2949

PCV-2969 AI-30B PCV-2929 CS to MANUAL AMBER light OFF PCV-2969 CS to MANUAL AMBER light OFF Page 3 of 10

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0329 (a)

JPM

Title:

Fill Safety Injection Tanks STEP ELEMENT STANDARD

[ SAT ] [ UNSAT ]

4 (3.a.2) Close the leakage cooler AI-30A discharge valve controller(s): PCV-2949 POT to 100%

PCV-2929 output, GREEN light lit

PCV-2909

PCV-2949 PCV-2909 POT to 100%

PCV-2969 output, GREEN light lit AI-30B PCV-2929 POT to 100%

output, GREEN light lit PCV-2969 POT to 100%

output, GREEN light lit

[ SAT ] [ UNSAT ]

5 (3.b) Start SI-2A AI-30A SI-2A CS to START and RED light lit Verify amps return to normal after start

[ SAT ] [ UNSAT ]

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

[ SAT ] [ UNSAT ]

Page 4 of 10

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0329 (a)

JPM

Title:

Fill Safety Injection Tanks STEP ELEMENT STANDARD 8 (5.b) Open HCV-312 AI-30B HCV-312 CS held to OPEN until RED light lit

[ SAT ] [ UNSAT ]

9 (5.c.2) Throttle open PCV-2909 AI-30A Adjust POT to throttle open

[ SAT ] [ UNSAT ]

10 (6) Open SI Tank Drain valve, CB-1,2,3 HCV-2916 HCV-2916 CS to OPEN, RED light lit

[ SAT ] [ UNSAT ]

11 (7) Close HCV-545 CB-1,2,3 HCV-545 CS to CLOSE, GREEN light lit

[ SAT ] [ UNSAT ]

12 (10) When SI-6A level is 72%: Note: PCV-2909 should be Close PCV-2909 closed before HCV-2916 because HCV-2916 is the last SIT drain valve open. Level should be 72% or greater but below the high level alarm.

AI-30A PCV-2909 POT to 100%

output, GREEN light lit

[ SAT ] [ UNSAT ]

Note: If the SI-6A high pressure alarm comes in, CUE: Another Operator will adjust the SI Tank pressure.

Page 5 of 10

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0329 (a)

JPM

Title:

Fill Safety Injection Tanks STEP ELEMENT STANDARD 13 (11) Close HCV-2916 CB-1,2,3 HCV-2916 CS to CLOSE, GREEN light lit

[ SAT ] [ UNSAT ]

14 (12) Close HCV-312 AI-30B HCV-312 CS held to CLOSE until GREEN light lit

[ SAT ] [ UNSAT ]

15 (13) Stop SI-2A AI-30A SI-2A CS to STOP and GREEN light lit, GREEN Flag

[ SAT ] [ UNSAT ]

16 (14) Open HCV-545 CB-1,2,3 HCV-545 CS to OPEN, RED light lit

[ SAT ] [ UNSAT ]

17 (15) Lower leakage cooler pressure AI-30A to less than 350 psig by Adjust POT to throttle open cracking open PCV-2909 until pressure less than 350 psig on PIC-2909

[ SAT ] [ UNSAT ]

18 (16.a) Throttle closed PCV-2909 AI-30A PCV-2909 POT to 100%

output, GREEN light lit

[ SAT ] [ UNSAT ]

Page 6 of 10

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0329 (a)

JPM

Title:

Fill Safety Injection Tanks STEP ELEMENT STANDARD 19 (16.b) Place PCV-2909 in AUTO AI-30A Momentarily place PCV-2909 CS in OVERIDE and return to AUTO, AMBER light lit

[ SAT ] [ UNSAT ]

20 (17) Close HCV-545 CB-1,2,3 HCV-545 CS to CLOSE, GREEN light lit

[ SAT ] [ UNSAT ]

21 (18) Ensure the leakage cooler AI-30A discharge valve controllers are Momentarily place PCV-2949 in AUTO CS in OVERIDE and return to

PCV-2929 AUTO, AMBER light lit

PCV-2909

PCV-2949 Verify PCV-2909 is in AUTO,

PCV-2969 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

[ SAT ] [ UNSAT ]

22 (19) Verify Operability of all HPSI AI-30A loop injection valves by AMBER lights on for:

confirming amber light is on:

HCV-317

HCV-314

HCV-314

HCV-315

HCV-320

HCV-311

HCV-311

HCV-312 Page 7 of 10

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0329 (a)

JPM

Title:

Fill Safety Injection Tanks STEP ELEMENT STANDARD

HCV-317 AI-30B

HCV-318 AMBER lights on for:

HCV-320

HCV-315

HCV-321

HCV-318

HCV-312

HCV-321

[ SAT ] [ UNSAT ]

23 (20.b) When both HPSI header CUE: HPSI header pressures pressures are between 250 are 200 psig.

psig and 140 psig:

CUE: Tech Spec logging is being performed by another operator Close HCV-2928 Provide key for HCV-2928 AI-128A Place key in HCV-2928 CS and turn to Close position, GREEN light lit

[ SAT ] [ UNSAT ]

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

[ SAT ] [ UNSAT ]

Page 8 of 10

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0329 (a)

JPM

Title:

Fill Safety Injection Tanks STEP ELEMENT STANDARD 25 (20.d) Verify HPSI header pressures: AI-30A

HPSI header #1 CUE: PI-309 indicates 0 psig approximately 0 psig

HPSI Header #2 AI-30B approximately 250 psig CUE: PI-310 indicates 250 psig

[ SAT ] [ UNSAT ]

Termination Criteria: SI Tank SI-6A has been filled. HPSI pumps and valves have been restored to normal.

Page 9 of 10

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0329 (a)

INITIATING CUE: You have been directed to fill only SI-6A to 72% using HPSI pump SI-2A, HCV-312 and 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 Page 10 of 10

FORT CALHOUN STATION OI-SI-1 OPERATING INSTRUCTION PAGE 13 OF 147 C

Continuous Use Attachment 4 - Filling SI Tank(s) Using HPSI Pumps PREREQUISITES (T) INITIALS

1. Procedure Revision Verification Revision No. Date:

2. Instrument Air System is in service per OI-CA-1.

3. The Component Cooling Water System is in operation per OI-CC-1.

4. The SIRWT has been filled to normal operating level with at least Refueling Boron Concentration plus 50 ppm.

5. Reactor Coolant System Pressure is greater than 1600 psia.

6. IF WD-2B is not aligned for automatic operation, THEN station an Operator at AI-100 to maintain the RCDT Level as required.

7. Ensure one of the following:

! HCV-507A/B, Vent Header Isolation Valves, are open (AI-100 or AI-43A/B)

! An Operator is stationed at AI-100 to maintain RCDT level and pressure as required PROCEDURE

1. Ensure the following SIRWT Tank Recirculation Valves are open.

! HCV-385 (AI-30B)

! HCV-386 (AI-30A)

2. Ensure HCV-2983, SI Check Vlv Lkg Hdr CVCS Isol Valve, is closed.

(AI-30A)

R79

FORT CALHOUN STATION OI-SI-1 OPERATING INSTRUCTION PAGE 14 OF 147 C

Continuous Use Attachment 4 - Filling SI Tank(s) Using HPSI Pumps PROCEDURE (continued) (T) INITIALS NOTES

1. 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 header

2. Recirculation is not required if flushing is performed.

3. Recirculation may be N/Ad 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 close 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.

R79

FORT CALHOUN STATION OI-SI-1 OPERATING INSTRUCTION PAGE 15 OF 147 C

Continuous Use Attachment 4 - Filling SI Tank(s) Using HPSI Pumps PROCEDURE (continued) (T) INITIALS 3 d. 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 Cooler 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 switch in OVERRIDE position to reset the AUTO circuitry:

! PCV-2929

! PCV-2909

! PCV-2949

! PCV-2969

5) GO TO Step 20.

R79

FORT CALHOUN STATION OI-SI-1 OPERATING INSTRUCTION PAGE 16 OF 147 C

Continuous Use Attachment 4 - Filling SI Tank(s) Using HPSI Pumps PROCEDURE (continued) (T) INITIALS

4. 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 CLR 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 R79

FORT CALHOUN STATION OI-SI-1 OPERATING INSTRUCTION PAGE 17 OF 147 C

Continuous Use Attachment 4 - Filling SI Tank(s) Using HPSI Pumps PROCEDURE (continued) (T) INITIALS 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.c 2) Throttle the selected leakage cooler 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)

R79

FORT CALHOUN STATION OI-SI-1 OPERATING INSTRUCTION PAGE 18 OF 147 C

Continuous Use Attachment 4 - Filling SI Tank(s) Using HPSI Pumps PROCEDURE (continued) (T) INITIALS 5 b. 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 R79

FORT CALHOUN STATION OI-SI-1 OPERATING INSTRUCTION PAGE 19 OF 147 C

Continuous Use Attachment 4 - Filling SI Tank(s) Using HPSI Pumps PROCEDURE (continued) (T) INITIALS 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 R79

FORT CALHOUN STATION OI-SI-1 OPERATING INSTRUCTION PAGE 20 OF 147 C

Continuous Use Attachment 4 - Filling SI Tank(s) Using HPSI Pumps PROCEDURE (continued) (T) INITIALS 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/Ad 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.

R79

FORT CALHOUN STATION OI-SI-1 OPERATING INSTRUCTION PAGE 21 OF 147 C

Continuous Use Attachment 4 - Filling SI Tank(s) Using HPSI Pumps PROCEDURE (continued) (T) INITIALS

15. 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 R79

FORT CALHOUN STATION OI-SI-1 OPERATING INSTRUCTION PAGE 22 OF 147 C

Continuous Use Attachment 4 - Filling SI Tank(s) Using HPSI Pumps PROCEDURE (continued) (T) INITIALS

19. 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 Tech Spec 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 status and log out of applicable Tech Spec LCOs.

d. Verify HPSI Header #1 pressure drops to approximately 0 psig and HPSI Header #2 rises to approximately 250 psig.

Completed by Date/Time: /

R79

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0718 (b)

JPM

Title:

Place a Containment Cooling Unit in Service Location: Simulator Approximate Time: 12 minutes Actual Time: _________________

Reference(s): OI-VA-1, Attachment 2 R57 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:

Page 1 of 6

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0718 (b)

JPM

Title:

Place a Containment Cooling Unit in Service Operators Name: _____________________ Employee # ______________

All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):

SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________

Reason, if unsatisfactory:

Tools & Equipment: None Safety Considerations: None Comments:

Page 2 of 6

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0718 (b)

JPM

Title:

Place a Containment Cooling Unit in Service INITIATING CUE: You have been directed 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.

[ SAT ] [ UNSAT ]

2 (1.a.2) Ensure HCV-402C is closed CB-1,2,3 Ensure controller POT in closed position (100% output),

GREEN light lit

[ SAT ] [ UNSAT ]

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

[ SAT ] [ UNSAT ]

Page 3 of 6

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0718 (b)

JPM

Title:

Place a Containment Cooling Unit in Service STEP ELEMENT STANDARD 4 (1.a.4) Throttle open HCV-402C CB-1,2,3 maintaining CCW discharge Adjust POT for HCV-402C header pressure greater than toward OPEN position.

or equal to 70 psig ENSURE pressure on PI-499 does not go below 70 psig.

[ SAT ] [ UNSAT ]

5 (1.a.5) Monitor the following parameters: CB-1,2,3

VA-8A Flow

FI-418

VA-8A Temperature

TIC-422

CCW Discharge Header

PI-499 Press

CCW Discharge Header

TIC-2800 Temp

[ SAT ] [ UNSAT ]

6 (1.b) Start VA-7C AI-30A VA-7C CS to AFTER-START (Red flag), RED light lit

[ SAT ] [ UNSAT ]

7 (1.b) Monitor Parameters: AI-30A

VA-7C amps

VA-7C ammeter AI-44 Monitor:

VA-7C DP

PIC-702

VA-7C cooling coil DP

PI-710

VA-7C Outlet Temp

TI-719

[ SAT ] [ UNSAT ]

Page 4 of 6

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0718 (b)

JPM

Title:

Place a Containment Cooling Unit in Service Termination Criteria: VA-7C is running and CCW is being supplied to VA-8A Page 5 of 6

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0718 (b)

INITIATING CUE: You have been directed to place VA-7C and VA-8A in service.

All prerequisites are met.

START Page 6 of 6

FORT CALHOUN STATION OI-VA-1 OPERATING INSTRUCTION PAGE 9 OF 120 C

Continuous Use Attachment 2 - Containment Cooling Operation VA-7C & VA-7D PREREQUISITES (%) INITIALS

1. 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 PROCEDURE

1. 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 Vlvs Control SW to OPEN.

2) Ensure HCV-402C, Cntmt Clg Coil VA-8A Outlt Isol Vlv Cntrlr is closed.

3) Momentarily place HCV-402A/C, Cntmt Clg Coil VA-8A Isol Vlvs Control SW to CIRC.

4) Throttle open HCV-402C maintaining PI-499, CCW Discharge Header Pressure, greater than or equal to 70 psig.

R57

FORT CALHOUN STATION OI-VA-1 OPERATING INSTRUCTION PAGE 10 OF 120 C

Continuous Use Attachment 2 - Containment Cooling Operation VA-7C & VA-7D PROCEDURE (continued) (T) INITIALS 1.a 5) 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 Vlvs Control SW to OPEN.

2) Ensure HCV-403C, Cntmt Clg Coil VA-8B OUTLT Isol Vlv Cntrlr is closed.

3) Momentarily place HCV-403A/C, Cntmt Clg Coil VA-8B Isol Vlvs Control SW to CIRC.

4) Throttle open HCV-403C maintaining PI-499, CCW Discharge Header Pressure, greater than or equal to 70 psig.

R57

FORT CALHOUN STATION OI-VA-1 OPERATING INSTRUCTION PAGE 11 OF 120 C

Continuous Use Attachment 2 - Containment Cooling Operation VA-7C & VA-7D PROCEDURE (continued) (T) INITIALS 2.a 5) 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 Vlvs Control SW to ISOL.

3) Momentarily place HCV-402B/D, Cntmt Clg Coil VA-8A Vlvs Control SW to CLOSE.

R57

FORT CALHOUN STATION OI-VA-1 OPERATING INSTRUCTION PAGE 12 OF 120 C

Continuous Use Attachment 2 - Containment Cooling Operation VA-7C & VA-7D PROCEDURE (continued) (T) INITIALS

4. 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 Vlvs Control SW to ISOL.

3) Momentarily place HCV-403B/D, Cntmt Clg Coil VA-8B Vlvs Control SW to CLOSE.

Completed by Date/Time /

R57

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0778 (c)

JPM

Title:

RPS T-Cold Calibration 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:

Page 1 of 6

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0778 (c)

JPM

Title:

RPS T-Cold Calibration Operators Name: _____________________ Employee # ______________

All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):

SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________

Reason, if unsatisfactory:

Tools & Equipment: Bypass key for trip unit #9 Safety Considerations: NONE Comments: Simulator JPM Exam Load IC# 106 Page 2 of 6

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0778 (c)

JPM

Title:

RPS T-Cold Calibration 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 AI-31A/B/C/D on all four RPS channels Select T-Cold on selector switch and record value in procedure

[ SAT ] [ UNSAT ]

2 (1.b) Record T-cold cal DVM AI-31A/B/C/D readings on all four RPS For each channel, channels Select T-Cold CAL on selector switch and record value in procedure

[ SAT ] [ UNSAT ]

3 (1.c) Record T-cold cal pot settings AI-31A/B/C/D for all four channels For each channel, Record POT setting in procedure

[ SAT ] [ UNSAT ]

Page 3 of 6

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0778 (c)

JPM

Title:

RPS T-Cold Calibration STEP ELEMENT STANDARD 4 (1.d) Obtain the RPS Trip Unit #9 CUE: Provide key bypass key

5. (1.e) Log into Tech Spec 2.15(1) 48 Notify CR Operator that Tech hour LCO for channel A Spec Log Entry must be made.

[ SAT ] [ UNSAT ]

CUE: Log entry has been made 6 (1.f) Bypass RPS TM/LP Trip Unit AI-30A on channel A Insert key in RPS channel A Trip Unit #9 bypass switch and place in BYPASS (clockwise) position. AMBER light lit

[ SAT ] [ UNSAT ]

7 (1.g) Adjust T-cold cal POT on RPS AI-30A channel A until the T-cold cal Adjust T-cold cal POT on RPS reading on the DVM equals the channel A until the T-cold cal highest RPS channel T-cold reading on the DVM equals the highest RPS channel T-cold recorded in step 1 (1.a)

[ SAT ] [ UNSAT ]

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.

[ SAT ] [ UNSAT ]

Page 4 of 6

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0778 (c)

JPM

Title:

RPS T-Cold Calibration STEP ELEMENT STANDARD 9 (1.i) Remove bypass key AI-30A Remove key

[ SAT ] [ UNSAT ]

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 AI-31A/B/C/D on all four RPS channels For each channel, Select T-Cold on selector switch and record value in procedure

[ SAT ] [ UNSAT ]

12 (1.m) Record T-cold cal pot settings AI-31A/B/C/D for all four channels For each channel, Record POT setting in procedure

[ SAT ] [ UNSAT ]

Termination Criteria: RPS channel A T-cold has been calibrated and no RPS Trip Units are bypassed Page 5 of 6

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0778 (c)

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 Page 6 of 6

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 pm R6

FORT CALHOUN STATION OI-RPS-2 OPERATING INSTRUCTION PAGE 1 OF 4 REACTOR PROTECTIVE SYSTEM - TM/LP TCOLD CAL CALIBRATION ATT PURPOSE PAGE 1 - Adjust the Tcold cal POT(s) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 PRECAUTIONS

1. The selected RPS TM/LP Trip Unit is placed in BYPASS prior to adjusting the Tcold cal Pot to prevent an inadvertent channel trip.

2. Tcold DVM readings while at a steady state power are normally kept within close tolerances.

Hence, if while at steady state power readings differ by greater than 1.0 °F, the System Engineer should be consulted prior to adjustment to ensure operability of the affected channel.

REFERENCES/COMMITMENT DOCUMENTS

1. Technical Specifications:

! 1.1: Safety Limits - Reactor Core

! 1.3: Table 1-1: RPS Limiting Safety System Settings

! 2.15: Instrumentation 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 for Checks, Calibrations and Testing of Miscellaneous Instrumentation and Controls

! 3.10(7)a: DNB Parameters

2. USAR:

! 7.2: Reactor Protective System

! 7.5: Instrumentation Systems

3. Others:

! OP-ST-SHIFT-0001

! SO-G-100: Operability Dispositions When Calibrating, Testing or Operating Safety Related Equipment

! EAR 94-130, Appropriate Acceptance Criteria or Requirements to TCOLD Cal R6

FORT CALHOUN STATION OI-RPS-2 OPERATING INSTRUCTION PAGE 2 OF 4 C

Continuous Use Attachment 1 - Adjust the Tcold cal POT(s)

PREREQUISITES (T) 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 Shift Manager OR the difference between the highest Tcold DVM reading and any Tcold 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 less than or equal to 50% power greater than or equal to 1.0°F

5. IF Tcold 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 PROCEDURE

1. Perform the following:

a. Record Tcold DVM readings on all four RPS channels.

! AI-31A °F

! AI-31B °F

! AI-31C °F

! AI-31D °F R6

FORT CALHOUN STATION OI-RPS-2 OPERATING INSTRUCTION PAGE 3 OF 4 C

Continuous Use Attachment 1 - Adjust the Tcold cal POT(s)

PROCEDURE (continued) (T) INITIAL 1 b. Record Tcold cal DVM readings on all four RPS channels.

! AI-31A °F

! AI-31B °F

! AI-31C °F

! AI-31D °F

c. Record Tcold 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 hour5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months 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 Tcold cal POT on the selected channel until the Tcold cal DVM reading equals highest RPS channel Tcold recorded in Step a.

h. Ensure selected TM/LP Trip Unit #9 is RESET.

R6

FORT CALHOUN STATION OI-RPS-2 OPERATING INSTRUCTION PAGE 4 OF 4 C

Continuous Use Attachment 1 - Adjust the Tcold cal POT(s)

PROCEDURE (continued) (T) INITIAL 1 i. Remove Bypass Key for selected TM/LP Trip Unit.

j. Exit Technical Specification 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 Tcold cal DVM readings:

! AI-31A °F

! AI-31B °F

! AI-31C °F

! AI-31D °F

m. Record new Tcold cal POT settings:

! AI-31A

! AI-31B

! AI-31C

! AI-31D Completed by Date/Time /

R6

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0726 (d)

JPM

Title:

Restore Control Room Ventilation following Smoke Detector Trip Location: Control Room 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:

Page 1 of 8

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0726 (d)

JPM

Title:

Restore Control Room Ventilation following Smoke Detector Trip Operators Name: _____________________ Employee # ______________

All Critical Steps (*) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):

SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________

Reason, if unsatisfactory:

Tools & Equipment: None Safety Considerations: None Comments:

Page 2 of 8

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0726 (d)

JPM

Title:

Restore Control Room Ventilation following Smoke Detector Trip 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. The system has been shutdown for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

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 ELEMENT STANDARD STEP 1 Obtain copy of OI-VA-3 Locates OI-VA 3

[ SAT ] [ UNSAT ]

Provide candidate with a copy of OI-VA-3 2 (Att-9 1) Ensure the following: AI-106A/B

All ventilation dampers GREEN lights closed

Operating ventilation Control switch in AUTO or units tripped (VA-46A/B) STOP position GREEN light ON

[ SAT ] [ UNSAT ]

3(2) Place Smoke Detector AI-106A/B Override switches in override HC-VA46A-3 and HC-VA46B-3 in OVERRIDE

[ SAT ] [ UNSAT ]

Page 3 of 8

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0726 (d)

JPM

Title:

Restore Control Room Ventilation following Smoke Detector Trip CRITICAL ELEMENT STANDARD STEP

4. Acknowledge Smoke Detector Override Annunciators

[ SAT ] [ UNSAT ]

Turns to OI-VA-3, attachment 1 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

[ SAT ] [ UNSAT ]

6 (3) Verify filter fan control switch AI-106A/B position HC-VA63A and HC-VA63B in AUTO

[ SAT ] [ UNSAT ]

7 (4) Ensure third-stage cooling AI-106A VIAS Override control switch in HC-VA-46A, VA-46A 3rd stage normal cooling VIAS override switch in NORMAL

[ SAT ] [ UNSAT ]

8 (5.a) Start VA-46A AI-106A HC-VA 46A-2 to START then release. RED light lit

[ SAT ] [ UNSAT ]

Page 4 of 8

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0726 (d)

JPM

Title:

Restore Control Room Ventilation following Smoke Detector Trip CRITICAL ELEMENT STANDARD STEP 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 and RED lights are OFF for HCV-2898A and HCV-2898B.

When reported, candidate is directed to restore CR cooling using available equipment.

[ SAT ] [ UNSAT ]

Note: It is acceptable for the candidate to perform step 10 out of sequence.

10 Shut Down VA-46A AI-106A HC-VA 46A-2 to STOP and GREEN light lit

[ SAT ] [ UNSAT ]

Page 5 of 8

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0726 (d)

JPM

Title:

Restore Control Room Ventilation following Smoke Detector Trip CRITICAL ELEMENT STANDARD STEP 11 (4) Ensure third-stage cooling AI-106B VIAS Override control switch in HC-VA-46B, VA-46B 3rd stage normal cooling VIAS override switch in NORMAL

[ SAT ] [ UNSAT ]

12 (5.a) Start VA-46B AI-106B HC-VA 46B-2 to START then release. RED light lit

[ SAT ] [ UNSAT ]

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)

[ SAT ] [ UNSAT ]

CUE : The ductwork is clear of smoke 14 (att-9 4) Place smoke detector override AI-106A/B switches in normal HC-VA-46A-3 and HC-VA-46B-3 in NORMAL

[ SAT ] [ UNSAT ]

Page 6 of 8

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0726 (d)

JPM

Title:

Restore Control Room Ventilation following Smoke Detector Trip Termination Criteria: CR Ventilation in normal operation with VA-46B running Page 7 of 8

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0726 (d)

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. The system has been shutdown for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

You are directed to restore the Control Room ventilation system to the normal mode of operation, with VA-46A as the running unit. START Page 8 of 8

FORT CALHOUN STATION OI-VA-3 OPERATING INSTRUCTION PAGE 23 OF 29 C

Continuous Use Attachment 9 - System Restoration Following a Smoke Detector Trip PREREQUISITES (T) INITIALS

1. Procedure Revision Verification Revision Number Date:

PROCEDURE CAUTION Before restarting the Control Room Ventilation 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 Ventilation 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 /

R28

FORT CALHOUN STATION OI-VA-3 OPERATING INSTRUCTION PAGE 4 OF 29 C

Continuous Use Attachment 1 - VA-46A/46B Normal Startup PREREQUISITES (T) INITIALS

1. 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 Supply 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 Filter 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 available in the Control Room by installed or portable 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-64A and Attachment 31 for VA-64B.

7. VA-46A and VA-46B air filters are in place.

SE

8. VA-64A and VA-64B prefilters, HEPA filters, and charcoal media are in place.

SE

9. Manual Dampers are lined up per IC-ST-VA-0027.

SE

10. Checklist OI-VA-3-CL-A complete per OP-1.

R28

FORT CALHOUN STATION OI-VA-3 OPERATING INSTRUCTION PAGE 5 OF 29 C

Continuous Use Attachment 1 - VA-46A/46B Normal Startup PROCEDURE (T) INITIALS NOTES

1. 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 closed

2. 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 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months s:

! VA-46A

! VA-46B Maint

b. Verify the Compressor Isolation Valves are open.

Maint R28

FORT CALHOUN STATION OI-VA-3 OPERATING INSTRUCTION PAGE 6 OF 29 C

Continuous Use Attachment 1 - VA-46A/46B Normal Startup PROCEDURE (continued) (T) INITIALS

2. 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 Switches 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 Unit ensure Third-stage Cooling VIAS Override control switch is in NORMAL (AI-106A/B):

! HC-VA-46A, VA-46A 3rd Stage Cooling VIAS Override

! HC-VA-46B, VA-46B 3rd Stage Cooling VIAS Override NOTE If cooling water temperature is below 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.

R28

FORT CALHOUN STATION OI-VA-3 OPERATING INSTRUCTION PAGE 7 OF 29 C

Continuous Use Attachment 1 - VA-46A/46B Normal Startup PROCEDURE (continued) (T) INITIALS 6 b. 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 /

R28

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0042 (e)

JPM

Title:

Transfer Clutch Power Supply Location: Simulator Approximate Time: 12 Minutes Actual Time: _________________

Reference(s): OI-EE-4, Attachments 7 and 1 R31 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:

Page 1 of 6

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0042 (e)

JPM

Title:

Transfer Clutch Power Supply Operators Name: _____________________ Employee # ______________

All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):

SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________

Reason, if unsatisfactory:

Tools & Equipment: None Safety Considerations: None Comments: Cross Tie Instrument busses A&C, Open Supply breaker for instrument bus A. Place PS1&PS3 supply to bus B (Use exam load IC #105)

Page 2 of 6

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0042 (e)

JPM

Title:

Transfer Clutch Power Supply 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 & PS3 from Instrument Bus B to Instrument Bus A.

Inverter A has been bypassed by an Operator in the Switchgear Room.

All prerequisites are met. RCS Temperature is less than 300°F.

START Critical Steps shown in gray STEP ELEMENT STANDARD 1 (1 a) Ensure Instrument Bus A is not AI-40A, AI-40C cross-tied to Instrument Bus C Checks position of Instrument Bus Tie Breakers and determines that the Buses are cross-tied.

[ SAT ] [ UNSAT ]

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, Attachment 1)

Page 3 of 6

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0042 (e)

JPM

Title:

Transfer Clutch Power Supply STEP ELEMENT STANDARD CUE: Inverter C has been placed on bypass transformer. No fuel movement or core alterations are in progress.

No work is being performed that requires electrical power from AI-57.

2 (Att 1-7.e.1) Close 1-BUS-1A-1, Instrument AI-40A Bus A Supply Breaker Instrument Bus A supply breaker to CLOSE

[ SAT ] [ UNSAT ]

3 ( 7.e.2 ) Open I-BUS-AC-2, Instrument AI-40C Bus C Tie Breaker Instrument Bus C tie breaker to OPEN

[ SAT ] [ UNSAT ]

4 ( 7.e.3) Open I-BUS-AC-1, Instrument AI-40A Bus A Tie Breaker Instrument Bus A tie breaker to OPEN

[ SAT ] [ UNSAT ]

5 (Att-7 1.c) Verify Clutch Power Supply AI-57 breaker RPS/CB-CD is closed Breaker in ON position

[ SAT ] [ UNSAT ]

6 (1.d) Place Clutch Power Supply AI-57 Transfer Switch RPS/TS-AB in Turn switch to position 1 (left) the Instrument Bus A position

1 [ SAT ] [ UNSAT ]

Page 4 of 6

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0042 (e)

JPM

Title:

Transfer Clutch Power Supply STEP ELEMENT STANDARD 7 (1.e,f) Verify Clutch Power Supply AI-57 breaker RPS/CB-AB is closed. RESET and CLOSE Clutch If in trip free position, the reset Power Supply Breaker and close RPS/BC-AB

[ SAT ] [ UNSAT ]

8 (1.g) Verify all four Clutch Power AI-3 Supply ammeters read Ammeters read upscale upscale.

[ SAT ] [ UNSAT ]

9 (1.h) Verify proper indicating lights in AI-3 Clutch Power Supply Cabinet WHITE lights ON are energized.

[ SAT ] [ UNSAT ]

10 (1.i) Place Inverter A in normal Contacts Operator in operation per Attachment 1. switchgear room to place Inverter A in normal operation.

[ SAT ] [ UNSAT ]

CUE: Inverter A has been placed in normal operation Termination Criteria: Clutch Power Supply PS1 & PS3 are supplied from Instrument Bus A. Instrument busses A&C are not cross-tied Page 5 of 6

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0042 (e)

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 & PS3 from Instrument Bus B to Instrument Bus A.

Inverter A has been bypassed by an Operator in the Switchgear Room.

All prerequisites are met. RCS Temperature is less than 300°F.

START Page 6 of 6

FORT CALHOUN STATION OI-EE-4 OPERATING INSTRUCTION PAGE 91 OF 105 C

Continuous Use Attachment 7 - Clutch Power Supplies PREREQUISITES (T) INITIALS

1. Procedure Revision Verification Revision 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.

PROCEDURE CAUTIONS

1. 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.

NOTE Breaker RPS/CB-AB may go to the trip free position when Clutch Power Supply 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 the Instrument 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.

R31

FORT CALHOUN STATION OI-EE-4 OPERATING INSTRUCTION PAGE 92 OF 105 C

Continuous Use Attachment 7 - Clutch Power Supplies PROCEDURE (continued) (T) INITIALS 1 g. Verify all four Clutch Power Supply ammeters read upscale.

h. Verify proper indicating lights in Clutch Power Supply Cabinet are energized.

i. Place Inverter A in normal operation per Attachment 1.

CAUTIONS

1. 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.

NOTE Breaker RPS/CB-AB may go to the trip free position when Clutch Power Supply 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 the Instrument 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.

R31

FORT CALHOUN STATION OI-EE-4 OPERATING INSTRUCTION PAGE 93 OF 105 C

Continuous Use Attachment 7 - Clutch Power Supplies PROCEDURE (continued) (T) INITIALS 2 h. Verify proper indicating lights in Clutch Power Supply Cabinet are energized.

i. Place Inverter B in normal operation per Attachment 2.

CAUTIONS

1. 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.

NOTE Breaker RPS/CB-CD may go to the trip free position when Clutch Power Supply 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 the Instrument 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 are energized.

R31

FORT CALHOUN STATION OI-EE-4 OPERATING INSTRUCTION PAGE 94 OF 105 C

Continuous Use Attachment 7 - Clutch Power Supplies PROCEDURE (continued) (T) INITIALS 3 i. Place Inverter C in normal operation per Attachment 3.

CAUTIONS

1. 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.

NOTE Breaker RPS/CB-CD may go to the trip free position when Clutch Power Supply 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 the Instrument 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 are energized.

i. Place Inverter D in normal operation per Attachment 4.

Completed by Date/Time /

R31

FORT CALHOUN STATION OI-EE-4 OPERATING INSTRUCTION PAGE 3 OF 105 C

Continuous Use Attachment 1 - Inverter A (EE-8H) Operation PREREQUISITES (T) INITIALS

1. Procedure Revision Verification Revision 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 NOTES

1. Instrument bus panels AI-40A has a pair of white lights for indicating grounds. Both lights will be dimly lit when no grounds are present on the bus. If a ground occurs, one light will become brighter than the other until the 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 inverter trouble alarm to annunciate on CB-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:

NOTE Once Inverter A (EE-8H) is in reverse transfer it is inoperable because it can not forward transfer automatically back to its instrument bus.

a. Declare Inverter A (EE-8H) inoperable per Technical Specification 2.7(2)(o).

SM/CRS R31

FORT CALHOUN STATION OI-EE-4 OPERATING INSTRUCTION PAGE 4 OF 105 C

Continuous Use Attachment 1 - Inverter A (EE-8H) Operation PROCEDURE (continued) (T) INITIALS NOTE Instrument Bus voltage may be lower than normal 117.6 - 122.4 Volts AC when being fed from a bypass transformer.

1 b. Ensure MCC-3B1-E3R, EE-4N Inverter A Bypass transformer Breaker is closed.

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 the INVERTER 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.

R31

FORT CALHOUN STATION OI-EE-4 OPERATING INSTRUCTION PAGE 5 OF 105 C

Continuous Use Attachment 1 - Inverter A (EE-8H) Operation PROCEDURE (continued) (T) INITIALS CAUTION Adjustments 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.

2 h. 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/CRS

3. IF switching Inverter A (EE-8H) from normal operation to bypass power is desired, THEN perform the following:

NOTE Instrument Bus voltage may be lower than normal 117.6 - 122.4 Volts AC when being fed from a bypass transformer.

a. Ensure MCC-3B1-E3R, EE-4N Inverter A Bypass Transformer Breaker is closed.

b. Verify sync loss light is off.

NOTE Once 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 Technical Specification 2.7(2)(o).

SM/CRS R31

FORT CALHOUN STATION OI-EE-4 OPERATING INSTRUCTION PAGE 6 OF 105 C

Continuous Use Attachment 1 - Inverter A (EE-8H) Operation PROCEDURE (continued) (T) INITIALS 3 d. 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, in BYPASS.

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 in BYPASS.

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 the INVERTER position.

i. Ensure sync loss light is off.

j. Push the forward transfer button.

R31

FORT CALHOUN STATION OI-EE-4 OPERATING INSTRUCTION PAGE 7 OF 105 C

Continuous Use Attachment 1 - Inverter A (EE-8H) Operation PROCEDURE (continued) (T) INITIALS 4 k. 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.

CAUTION Adjustments 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.

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/CRS CAUTION Step 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).

R31

FORT CALHOUN STATION OI-EE-4 OPERATING INSTRUCTION PAGE 8 OF 105 C

Continuous Use Attachment 1 - Inverter A (EE-8H) Operation PROCEDURE (continued) (T) INITIALS 5 e. 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 the INVERTER 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.

CAUTION Adjustments 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.

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).

R31

FORT CALHOUN STATION OI-EE-4 OPERATING INSTRUCTION PAGE 9 OF 105 C

Continuous Use Attachment 1 - Inverter A (EE-8H) Operation PROCEDURE (continued) (T) INITIALS 5 s. Once Inverter A is operable and has been returned to its bus (i.e.

forward transferred) declare Inverter A (EE-8H) operable.

SM/CRS NOTE Upon loss of an Instrument Bus implement AOP-16, Loss of Instrument Bus Power.

6. IF hot bus transfer of Instrument Buses A and A1 feed to Instrument Bus AI-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 from AI-57 on the Control Element Drive Mechanisms (CEDM)

Shift Mgr

b. Verify that there are no hard grounds on either Instrument Bus A or Instrument Bus C.

c. Block the PPLS/BLOCK A relay (device #817) in the PICKED-UP position (located behind CB-3).

EM Ind Verif R31

FORT CALHOUN STATION OI-EE-4 OPERATING INSTRUCTION PAGE 10 OF 105 C

Continuous Use Attachment 1 - Inverter A (EE-8H) Operation PROCEDURE (continued) (T) INITIALS 6 d. Transfer the load on Instrument Inverter C to the bypass source by performing the following:

NOTE Instrument Bus voltage may be lower than normal 117.6 - 122.4 Volts 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 by performing the following:

NOTE Instrument Bus voltage may be lower than normal 117.6 - 122.4 Volts 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.

R31

FORT CALHOUN STATION OI-EE-4 OPERATING INSTRUCTION PAGE 11 OF 105 C

Continuous Use Attachment 1 - Inverter A (EE-8H) Operation PROCEDURE (continued) (T) INITIALS CAUTION Maximum Inverter load is 62.5 amps. Non-essential loading may need to be reduced to prevent an overload condition following the load transfer.

6 f. Hot bus transfer loads from Instrument Bus A to Instrument Bus C by performing 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 in the 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.

R31

FORT CALHOUN STATION OI-EE-4 OPERATING INSTRUCTION PAGE 12 OF 105 C

Continuous Use Attachment 1 - Inverter A (EE-8H) Operation PROCEDURE (continued) (T) INITIALS CAUTION Adjustments 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.

6.g 8) 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 Volts AC (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.

NOTE Upon 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 normal alignment 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 from AI-57, on the Control Element Drive Mechanisms (CEDM)

Shift Mgr R31

FORT CALHOUN STATION OI-EE-4 OPERATING INSTRUCTION PAGE 13 OF 105 C

Continuous Use Attachment 1 - Inverter A (EE-8H) Operation PROCEDURE (continued) (T) INITIALS 7 b. Verify that there are no hard grounds on either Instrument Bus A or Instrument Bus C.

CAUTION Maximum 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 the following:

NOTE Instrument Bus voltage may be lower than normal 117.6 - 122.4 Volts 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 by performing the following:

NOTE Instrument Bus voltage may be lower than normal 117.6 - 122.4 Volts 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.

R31

FORT CALHOUN STATION OI-EE-4 OPERATING INSTRUCTION PAGE 14 OF 105 C

Continuous Use Attachment 1 - Inverter A (EE-8H) Operation PROCEDURE (continued) (T) INITIALS 7.d 3) 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 Instrument Bus C from Instrument Bus C to Instrument Bus A by positioning the following 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) is desired, THEN perform the following:

1) Verify reverse transfer light is on.

2) Verify EE-8H-S1, Inverter A, EE-8H Manual Transfer Switch, is in the 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.

R31

FORT CALHOUN STATION OI-EE-4 OPERATING INSTRUCTION PAGE 15 OF 105 C

Continuous Use Attachment 1 - Inverter A (EE-8H) Operation PROCEDURE (continued) (T) INITIALS CAUTION Adjustments 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.

7.f 8) 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 Volts AC (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 in the 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.

CAUTION Adjustments 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).

R31

FORT CALHOUN STATION OI-EE-4 OPERATING INSTRUCTION PAGE 16 OF 105 C

Continuous Use Attachment 1 - Inverter A (EE-8H) Operation PROCEDURE (continued) (T) INITIALS 7.g 9) Verify Inverter C Output Voltage is between 117.6 and 122.4 Volts AC (normal 120.0 Volts AC).

h. Remove the block from the PPLS/BLOCK A relay (device #817), located behind CB-3.

EM Ind Verif

8. IF dead bus transfer of instrument Buses A and A1 back to normal alignment 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 in BYPASS.

e. Ensure MCC-3B1-E3R, EE-4N Inverter A Bypass Transformer, Breaker is 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).

R31

FORT CALHOUN STATION OI-EE-4 OPERATING INSTRUCTION PAGE 17 OF 105 C

Continuous Use Attachment 1 - Inverter A (EE-8H) Operation PROCEDURE (continued) (T) INITIALS NOTE If desired then startup inverter A otherwise N/A all remaining steps.

8 k. Ensure EE-8F-CB24, EE-8H Inverter A, Breaker on DC Bus No. 1 is closed.

NOTE The following steps will place Inverter A in service.

l. Momentarily push the precharge button on Inverter A, then wait ten (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 the INVERTER 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.

R31

FORT CALHOUN STATION OI-EE-4 OPERATING INSTRUCTION PAGE 18 OF 105 C

Continuous Use Attachment 1 - Inverter A (EE-8H) Operation PROCEDURE (continued) (T) INITIALS CAUTION Adjustments 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 v. 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/CRS

9. IF Inverter A (EE-8H) is in service AND removal from operation of Bypass transformer 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 A Bypass Transformer breaker is opened.

f. Open breaker MCC-3B1-E3R.

g. Verify Sync loss light is on.

R31

FORT CALHOUN STATION OI-EE-4 OPERATING INSTRUCTION PAGE 19 OF 105 C

Continuous Use Attachment 1 - Inverter A (EE-8H) Operation PROCEDURE (continued) (T) INITIALS CAUTION Adjustments 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.

9 h. 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 Bypass transformer 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 is open.

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 breaker 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.

R31

FORT CALHOUN STATION OI-EE-4 OPERATING INSTRUCTION PAGE 20 OF 105 C

Continuous Use Attachment 1 - Inverter A (EE-8H) Operation PROCEDURE (continued) (T) INITIALS CAUTION Adjustments 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.

10 h. 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 /

R31

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0613A (f)

JPM

Title:

Shutdown a Reactor Coolant Pump Location: Simulator Control Room Approximate Time: 8 minutes Actual Time: _________________

Reference(s): OI-RC-9, Attachment 2 (R59)

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:

Page 1 of 6

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0613A (f)

JPM

Title:

Shutdown a Reactor Coolant Pump Operators Name: _____________________ Employee # ______________

All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):

SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________

Reason, if unsatisfactory:

Tools & Equipment: Zero Power Mode Bypass Keys Safety Considerations: None Comments: Fail RC-3Ds 90% speed switch COP JOB3171L As is This is an Alternate Path JPM Exam Load IC# 107 Page 2 of 6

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0613A (f)

JPM

Title:

Shutdown a Reactor Coolant Pump 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 CB-4 prior to stopping a RCP.

Verify all trippable rods are inserted

[ SAT ] [ UNSAT ]

2 (prereq 3) Ensure Zero Power Mode AI-31 A/B/C/D Bypass switches are in Bypass Keys installed and AMBER lights lit

[ SAT ] [ UNSAT ]

3 (1) Stop Reactor Coolant Pump CB-1,2,3 RC-3D RC-3D CS to AFTER-STOP position and release GREEN light lit

[ SAT ] [ UNSAT ]

Page 3 of 6

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0613A (f)

JPM

Title:

Shutdown a Reactor Coolant Pump STEP ELEMENT STANDARD 4 (2) Ensure the Oil Lift Pump starts CB-1,2,3 automatically as pump speed lowers. Determines pump did not start.

Manually starts lift oil pump within 25 seconds by placing Oil Lift Pump CS, RC-3D-1, in START position and verifying RED light on.

[ SAT ] [ UNSAT ]

5 (2 ) Holds Oil Lift Pump control If the control switch is switch in the START position released, the lift pump will stop. It should then be returned to the START position. Control switch may only be released and restarted once.

The control switch should be held in the START position until the zero speed light comes on. (approximately 2 minutes)

[ SAT ] [ UNSAT ]

6 (3 ) Ensure Reverse Rotation CB-1,2,3, A6 D-5 Annunciator is clear.

Annunciator is OFF

[ SAT ] [ UNSAT ]

7(5) Confirm Zero Speed light is on CB-1,2,3 RC-3D GREEN light on

[ SAT ] [ UNSAT ]

Page 4 of 6

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0613A (f)

JPM

Title:

Shutdown a Reactor Coolant Pump STEP ELEMENT STANDARD 8 (4) Confirm RCP tachometer CUE: Local Operator reports indicates zero RC-3D speed is zero rpm.

9 (6) Stop oil lift pump. CB-1,2,3 Control switch to AFTER-STOP GREEN light lit

[ SAT ] [ UNSAT ]

Termination Criteria: Reactor Coolant Pump RC-3D is secured and its Oil Lift pump has been stopped Page 5 of 6

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0613A (f)

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 Page 6 of 6

FORT CALHOUN STATION OI-RC-9 OPERATING INSTRUCTION PAGE 14 OF 65 C

Continuous Use Attachment 2 - Shutdown Reactor Coolant Pumps (Coupled)

PREREQUISITES (T) INITIALS

1. 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 to disable the RPS Low Flow Trip before the first RCP is stopped.

PROCEDURE NOTES

1. 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 NOTES

1. 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 R59

FORT CALHOUN STATION OI-RC-9 OPERATING INSTRUCTION PAGE 15 OF 65 C

Continuous Use Attachment 2 - Shutdown Reactor Coolant Pumps (Coupled)

PROCEDURE (continued) (T) INITIALS

3. 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-3A 129-1 ZS Tach

! RC-3B 149-1 ZS Tach

! RC-3C 169-1 ZS Tach

! RC-3D 189-1 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 /

R59

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-R (g)

JPM

Title:

AFW Operability Verification From AI-179 Location: Simulator ASD panels Approximate Time: 20 minutes Actual Time: _________________

Reference(s): OP-ST-AFW-0006 JPM Prepared by: Jerry Koske Date: 06/21/2005 JPM Reviewed by: Date:

JPM Approved by: Date:

Page 1 of 8

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-R (g)

JPM

Title:

AFW Operability Verification From AI-179 Operators Name: _____________________ Employee # ______________

All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):

SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________

Reason, if unsatisfactory:

Tools & Equipment:

Safety Considerations:

Comments:

Page 2 of 8

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-R (g)

JPM

Title:

AFW Operability Verification From AI-179 INITIATING CUE:

The Plant is mode 5. OP-ST-AFW-0006 is to be conducted. You have been directed to perform the AI-179 portions of OP-ST-AFW-0006. (steps 3.3 - 3.13 and steps 3.29 through 3.45)

All prerequisites are met. The test has been completed through step 3.2.

START Critical Steps shown in gray STEP ELEMENT STANDARD 1 (3.3) Place Transfer switches in the LOCAL position. Both Switches placed in

43/RC-2A LOCAL

43/RC-2B

[ SAT ] [ UNSAT ]

2 (3.4) Verify:

AUX FW System Local Control Contact control room for alarm in Alarm status:

CUE: Control room reports AUX FW SYSTEM LOCAL CONTROL alarm is in..

43X/RC-2A transfers

Relay trips

43X/RC-2B transfers

Relay trips

HCV-1107A open

Red light ON

HCV-1107B open

Red light ON

HCV-1108A open

Red light ON

HCV-1108B open

Red light ON

FCV-1368 open

Red light ON

FCV-1369 open

Red light ON

YCV-1045 Note: Procedure does not give position for YCV-1045. If Page 3 of 8

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-R (g)

JPM

Title:

AFW Operability Verification From AI-179 STEP ELEMENT STANDARD questioned, direct candidate to record position and proceed.

YCV-1045A open

Red light ON

YCV-1045B open

Red light ON

[ SAT ] [ UNSAT ]

3 (3.5) Close HCV-1107A Control switch to close.

Green light ON

[ SAT ] [ UNSAT ]

4 (3.6) Close HCV-1107B Place control switch to THROTTLE. Turn air loader until valve closes.

[ SAT ] [ UNSAT ]

5 (3.7) Close HCV-1108A Control switch to close.

Green light ON

[ SAT ] [ UNSAT ]

6 (3.8) Close HCV-1108B Place control switch to THROTTLE. Turn air loader until valve closes.

[ SAT ] [ UNSAT ]

7 (3.9) Close FCV-1368 Control switch to CLOSE Green light ON 8 (3.10) Close FCV-1369 Control switch to CLOSE Green light ON

[ SAT ] [ UNSAT ]

Page 4 of 8

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-R (g)

JPM

Title:

AFW Operability Verification From AI-179 STEP ELEMENT STANDARD 9 (3.11) Close YCV-1045 Control switch to STOP Green light ON

[ SAT ] [ UNSAT ]

10 (3.12) Close YCV-1045B Control switch to CLOSE Green light ON

[ SAT ] [ UNSAT ]

11 (3.13) Close YCV-1045A Control switch to CLOSE Green light ON

[ SAT ] [ UNSAT ]

CUE: Control Room has completed steps 3.14 through 3.28.

12 (3.29) Open YCV-1045A Control switch to OPEN and release to NORMAL.

Red light ON

[ SAT ] [ UNSAT ]

13 (3.30) Open YCV-1045B Control switch to OPEN and release to NORMAL.

Red light ON

[ SAT ] [ UNSAT ]

CUE: steps 3.31 and 3.32 have been completed 14 (3.33) Open HCV-1107A Control switch to OPEN Red light ON

[ SAT ] [ UNSAT ]

Page 5 of 8

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-R (g)

JPM

Title:

AFW Operability Verification From AI-179 STEP ELEMENT STANDARD 15 (3.34, Open HCV-1107B Turn air loader to open 3.35) Control switch to OPEN Red light ON

[ SAT ] [ UNSAT ]

16 (3.36) Open FCV-1368 Control switch to OPEN Red light ON

[ SAT ] [ UNSAT ]

17 (3.37, Open HCV-1108B Turn air loader to open 3.38) Control switch to OPEN Red light ON

[ SAT ] [ UNSAT ]

18 (3.39) Open HCV-1108A Control switch to OPEN Red light ON

[ SAT ] [ UNSAT ]

19 (3.40) Open FCV-1369 Control switch to OPEN Red light ON

[ SAT ] [ UNSAT ]

20 (3.41) Place transfer switch 43/RC-2A Transfer switch in REMOTE in REMOTE position.

[ SAT ] [ UNSAT ]

21 (3.42) Reset Aux Relay 43X/RC-2A Turn relay to RESET

[ SAT ] [ UNSAT ]

Page 6 of 8

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-R (g)

JPM

Title:

AFW Operability Verification From AI-179 STEP ELEMENT STANDARD 22 (3.43) Place transfer switch 43/RC-2B Transfer switch in REMOTE in REMOTE position.

[ SAT ] [ UNSAT ]

23 (3.44) Reset Aux Relay 43X/RC-2B Turn relay to RESET

[ SAT ] [ UNSAT ]

CUE: Control room reports AUX FW SYSTEM LOCAL CONTROL alarm has cleared.

Termination Criteria: OP-ST-AFW-0006 has been completed through step 3.45 Page 7 of 8

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM -R (g)

INITIATING CUE:

The Plant is mode 5. OP-ST-AFW-0006 is to be conducted. You have been directed to perform the AI-179 portions of OP-ST-AFW-0006. (steps 3.3 - 3.13 and steps 3.29 through 3.45)

All prerequisites are met. The test has been completed through step 3.2.

START Page 8 of 8

WP10 Fort Calhoun Station Unit No. 1 OP-ST-AFW-0006 SURVEILLANCE TEST

Title:

AFW OPERABILITY VERIFICATION FROM AI-179 FC-68 Number: EC 33898 Reason for Change: Add tag number and label for FW-64-RL & FW-64. Delete ST Signature Sheet. Correct label for HC-1045-1.

Requestor: N/A Preparer: Daniel A Hochstein Correction (a): Page 10 (05-19-05)

ISSUED: 05-20-04 3:00 pm R5

FORT CALHOUN STATION OP-ST-AFW-0006 SURVEILLANCE TEST PAGE 1 OF 13 AFW OPERABILITY VERIFICATION FROM AI-179 SAFETY RELATED

1. PURPOSE 1.1 The purpose of this test is to verify operability of the Auxiliary Feedwater valve control circuits from Emergency Auxiliary Feedwater Panel AI-179. This test also provides a negative logic test to verify that equipment operation from the Control Room is not possible when control from AI-179 is selected, and vice versa.

1.2 Performance of this procedure at Mode 5 on a refueling outage basis fully satisfies the requirements of Technical Specification 3.1, Table 3-3A, Item 11.

2. REFERENCES/COMMITMENT DOCUMENTS 2.1 Technical Specifications:

! Section 2.15(5) and (6)

! Section 3.1, Table 3-3a, Item 11 2.2 Drawings File Description 11405-M-252 10458 Steam Flow Diagram 11405-M-253 10459 Steam Generator Feedwater and Blowdown 11405-M-254 10460 Flow Diagram, Condensate 11405-EM-1039 15770 FW-10 Speed Control Loop 161F568, Sh 1 09642 AI-179 Arrangement Drawing GE 161F593 097897 AI-179 Connection Diagram 11405-E-45 12280 YCV 1045A/B Control Circuits 136B2432, Sh 5 05707 43/FW Switch Development 136B2432, Sh 40 05743 HC-1045-1 Switch Development 136B2736, Sh 2 06172 Control Circuit Power Arrangement 136B2736, Sh 15 22125 43X/RC2B Switch Development 136S2432, Sh 44A 20454 43/RC2B Switch Development 11405-E-137 21423 YCV-1045 Schematic Diagram

3. DEFINITIONS None

4. EQUIPMENT LIST None R5

FORT CALHOUN STATION OP-ST-AFW-0006 SURVEILLANCE TEST PAGE 2 OF 13

5. PRECAUTIONS AND LIMITATIONS 5.1 This test shall be conducted in Plant Operating Mode 5. When transferring control from Panel AI-179, the AFW containment isolation valves will open. Ensure that no containment isolation requirements will be violated.

5.2 All anomalies and deficiencies shall be reported immediately to the immediate Supervisor and to the Shift Manager and noted on the Comment Sheet. An immediate check shall be made to verify Limiting Conditions for Operation, per Technical Specifications, have not been exceeded.

5.3 The System Engineer shall be notified within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of the completion of this test of any marginal, unexpected, or unacceptable results.

5.4 The following may alarm during this Surveillance Test.

! FW-10 TURBINE DRIVEN FEEDWATER PUMP TROUBLE (AI-66B, A66B,18)

! AUX FW PUMPS RECIRC VALVES FCV-1368/1369 SWITCH IN CLOSE POSITION (CB10/11, A9, C-1L)

! AUX FW SYSTEM LOCAL CONTROL (CB10/11, A9, C1U)

6. PREREQUISITES INITIALS/DATE 6.1 Procedure Revision Verification Revision No. /

6.2 A RWP has been issued, if required.

RWP No. /

6.3 Plant operating condition is Mode 5. /

6.4 No other test is in progress which could potentially affect this test, or if this test were performed, could have an effect on that test.

/

6.5 A prejob briefing has been conducted prior to the start of this test. /

6.6 Shift Manager authorizes performance of this test to ensure that no containment isolation requirements will be violated by the performance of this test (Reference Step 5.1).

Shift Manager Date/Time /

R5

FORT CALHOUN STATION OP-ST-AFW-0006 SURVEILLANCE TEST PAGE 3 OF 13

7. PROCEDURE NOTE: Step 7.1 can be performed at anytime and repeated as necessary.

7.1 IF this Surveillance Test is turned over, a prejob briefing must be conducted prior to the continuation of this test. /

7.2 Perform the following attachment.

ATTACHMENTS PAGE 1 - AFW Operability Verification from AI-179 . . . . . . . . . . . . . . . . 5 /

Completed by Date/Time /

8. RESTORATION 8.1 Shift Manager has been notified this test has been completed.

Shift Manager Date/Time /

9. ACCEPTANCE CRITERIA 9.1 All controls and indications operate as described in Section 7.0.

10. TEST RECORD 10.1 This entire procedure.

11. REVIEW 11.1 Test data shall be evaluated by the STA and reviewed by the Shift Manager for acceptability within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of the completion of this test.

Evaluated by Date/Time /

STA Reviewed by Date/Time /

Shift Manager R5

FORT CALHOUN STATION OP-ST-AFW-0006 SURVEILLANCE TEST PAGE 4 OF 13 11.2 The ISI Coordinator is responsible for reviewing this test to ensure compliance with the FCS ISI Program Plan and to analyze the trending information. This test, including trending, has been reviewed and found acceptable or the deficiencies have been noted on the Comment Sheet.

ISI Coordinator Date/Time /

11.3 The System Engineer is responsible for reviewing this test data, trending, and identified deficiencies noted within the test. This test has been reviewed and found acceptable or deficiencies and actions taken have been noted on the Comment Sheet.

System Engineer Date/Time /

R5

FORT CALHOUN STATION OP-ST-AFW-0006 SURVEILLANCE TEST PAGE 5 OF 13 Attachment 1 - AFW Operability Verification from AI-179 PROCEDURE INITIALS

1. Record As Found position of the following Valves (AI-66A and AI-66B):

! HCV-1107A, Aux FW to S/G RC-2A Isolation Valve Inbd

! HCV-1107B, Aux FW to S/G RC-2A Isolation Valve Outbd

! HCV-1108A, Aux FW to S/G RC-2B Isolation Valve Inbd

! HCV-1108B, Aux FW to S/G RC-2B Isolation Valve Outbd

! YCV-1045, Stm to Pump FW-10 Control Valve

! YCV-1045B, S/G RC-2B STM to FW-10 Hdr B Isolation Valve

! YCV-1045A, S/G RC-2A STM to FW-10 Hdr A Isolation Valve

! FCV-1368, Aux FW Pump FW-6 Recirculation Valve

! FCV-1369, Aux FW Pump FW-10 Recirculation Valve

2. Verify no control is possible from AI-179 when the 43/RC-2A and 43/RC-2B transfer switches are in REMOTE control by completing the following.

2.1 Verify operable and position valves as follows (AI-66A and AI-66B):

Operable Position (% )

! HCV-1107A CLOSED

! HCV-1107B CLOSED

! HCV-1108A CLOSED

! HCV-1108B CLOSED

! YCV-1045 CLOSED

! YCV-1045B CLOSED

! YCV-1045A CLOSED

! FCV-1368 OPEN

! FCV-1369 OPEN 2.2 To prevent LO-39, FW-10 Aux Oil Pump, from starting place HC/LO-39, Aux Lube Oil Pump LO-39 Override Switch, in TEST. (FW-10, LO-39-MS) 2.3 Verify FW-10 TURBINE DRIVEN FEEDWATER PUMP TROUBLE (AI-66B, A66B,18) is in alarm.

R5

FORT CALHOUN STATION OP-ST-AFW-0006 SURVEILLANCE TEST PAGE 6 OF 13 Attachment 1 - AFW Operability Verification from AI-179 PROCEDURE (continued) INITIALS NOTE: The following switches are located at AI-179 unless otherwise noted.

(%)

2.4 Verify the following:

! 43/RC-2A, AFW Controls Transfer Switch, is in REMOTE position

! 43X/RC-2A, AFW Controls Transfer Relay, is in RESET position

! 43/RC-2B, AFW Controls Transfer Switch, is in REMOTE position

! 43X/RC-2B, AFW Controls Transfer Relay, is in RESET position 2.5 Place the switches for the following valves in OPEN position and verify valves remain closed:

! HCV-1107A, Aux FW to S/G RC-2A Isolation Valve Inbd

! HCV-1108A, Aux FW to S/G RC-2B Isolation Valve Inbd

! YCV-1045A, S/G RC-2A STM to FW-10 Hdr A Isolation Valve

! YCV-1045B, S/G RC-2B STM to FW-10 Hdr B Isolation Valve 2.6 Place the following switches in THROTTLE:

! HCV-1107B, Aux FW to S/G RC-2A Isol Vlv Controller

! HCV-1108B, Aux FW to S/G RC-2B Isol Vlv Controller 2.7 Verify the following valves do not respond to signals from air loaders on AI-179:

! HIC-1107B, Aux FW to S/G RC-2A Isolation Valve Outbd

! HIC-1108B, Aux FW to S/G RC-2B Isolation Valve Outbd 2.8 Place the following switches in OPEN position:

! HIC-1107B

! HCV-1107B

! HIC-1108B

! HCV-1108B 2.9 Place the switches for the following valves to CLOSE and verify valves remain open and verify switches return to NORMAL position.

! FCV-1368, Aux FW Pump FW-6 Recirculation Valve

! FCV-1369, Aux FW Pump FW-10 Recirculation Valve R5

FORT CALHOUN STATION OP-ST-AFW-0006 SURVEILLANCE TEST PAGE 7 OF 13 Attachment 1 - AFW Operability Verification from AI-179 PROCEDURE (continued) INITIALS 2.10 Place Control Switch for YCV-1045, Stm to Pump FW-10 Control Valve, to the After Start (red flag) position and verify the following valves remain

(%)

closed:

! YCV-1045.

! YCV-1045A

! YCV-1045B

3. Test controls associated with Transfer Switch 43/RC-2A and 43/RC-2B by completing the following.

3.1 Close the following valves using Switches on AI-66A and AI-66B.

! FCV-1368 (AI-66A)

! FCV-1369 (AI-66B) 3.2 Verify AUX FW PUMPS RECIRC VALVES FCV-1368/1369 SWITCH IN CLOSE POSITION (CB10/11, A9, C-1L) in alarm.

NOTE: Steps 3.3 through 3.13 are performed from AI-179, unless otherwise noted.

CAUTION Performance of the next step will cause HCV-1107A, HCV-1107B, HCV-1108A, HCV-1108B, YCV-1045, YCV-1045A, YCV-1045B, FCV-1368, and FCV-1369 to open.

3.3 Place the following Transfer Switches in the LOCAL position.

! 43/RC-2A

! 43/RC-2B R5

FORT CALHOUN STATION OP-ST-AFW-0006 SURVEILLANCE TEST PAGE 8 OF 13 Attachment 1 - AFW Operability Verification from AI-179 PROCEDURE (continued) INITIALS

(%)

3.4 Verify the following:

! AUX FW SYSTEM LOCAL CONTROL (CB10/11, A9, C1U) in alarm

! 43X/RC-2A transfers

! 43X/RC-2B transfers

! HCV-1107A open

! HCV-1107B open

! HCV-1108A open

! HCV-1108B open

! FCV-1368 open

! FCV-1369 open

! YCV-1045

! YCV-1045A open

! YCV-1045B open 3.5 Place HCV-1107A Control Switch to CLOSE and verify valve closes.

3.6 Place HCV-1107B Control Switch to THROTTLE and close valve with Air Loader HIC-1107B.

3.7 Place HCV-1108A Control Switch to CLOSE and verify valve closes.

3.8 Place HCV-1108B Control Switch to THROTTLE and close valve with Air Loader HIC-1108B.

3.9 Place FCV-1368 Control Switch to CLOSE and verify valve closes.

3.10 Place FCV-1369 Control Switch to CLOSE and verify valve closes.

3.11 Place YCV-1045 Control Switch to STOP and verify valve closes.

3.12 Place YCV-1045B Control Switch to CLOSE and verify valve closes.

3.13 Place YCV-1045A Control Switch to CLOSE and verify valve closes.

NOTE: Steps 3.14 through 3.28 are performed from the Control Room.

3.14 Place HCV-1107A Control Switch in the OPEN position and verify valve remains closed. (AI-66A)

R5

FORT CALHOUN STATION OP-ST-AFW-0006 SURVEILLANCE TEST PAGE 9 OF 13 Attachment 1 - AFW Operability Verification from AI-179 PROCEDURE (continued) INITIALS 3.15 Place HCV-1107B Control Switch in the OPEN position and verify valve remains closed. (AI-66A) 3.16 Place HCV-1107B Control Switch in CLOSE. (AI-66A) 3.17 Verify HCV-1107B cannot be opened using HIC-1107B, Aux FW to S/G RC-2A Isol Vlv Controller. (CB-10/11) 3.18 Place HCV-1108A Control Switch in the OPEN position and verify valve remains closed. (AI-66B) 3.19 Place HCV-1108B Control Switch in the OPEN position and verify valve remains closed. (AI-66B) 3.20 Place HCV-1108B Control Switch in CLOSE. (AI-66B) 3.21 Verify HCV-1108B cannot be opened using HIC-1108B, Aux FW to S/G RC-2B Isol Vlv Controller. (CB-10/11) 3.22 Place FCV-1368 Control Switch to OPEN position and verify valve remains closed. (AI-66A) 3.23 Place FCV-1368 Control Switch to OPEN and verify valve remains closed.

(CB-10/11) 3.24 Place FCV-1369 Control Switch to OPEN position and verify valve remains closed. (AI-66B) 3.25 Place YCV-1045 Control Switch to the OPEN position and verify valve remains closed. (AI-66B) 3.26 Place YCV-1045 Control Switch in the CLOSE position. (AI-66B) 3.27 Place YCV-1045A Control Switch on AI-66B to the OPEN position and verify valve remains closed and verify switch returns to NORMAL.

3.28 Place YCV-1045B Control Switch to the OPEN position and verify valve remains closed and Verify switch returns to NORMAL. (AI-66B)

R5

FORT CALHOUN STATION OP-ST-AFW-0006 SURVEILLANCE TEST PAGE 10 OF 13 Attachment 1 - AFW Operability Verification from AI-179 PROCEDURE (continued) INITIALS NOTE: Steps 3.29 through 3.44 are performed at AI-179.

3.29 Place YCV-1045A Control Switch to the OPEN position and Verify valve opens and verify switch returns to NORMAL.

3.30 Place YCV-1045B Control Switch to the OPEN position and Verify valve opens and verify switch returns to NORMAL.

3.31 Place HC/LO-39 in OPERATE. (FW-10, LO-39-MS) 3.32 Verify FW-10 TURBINE DRIVEN FEEDWATER PUMP TROUBLE (AI-66B, A66B,18) clears.

3.33 Open HCV-1107A.

3.34 Return the Air Loader and Control Switch for HCV-1107B to the OPEN

(%)

position.

! HIC-1107B

! HCV-1107B 3.35 Verify HCV-1107B opens.

3.36 Open FCV-1368.

3.37 Return the Air Loader and Control Switch for HCV-1108B to the OPEN position.

! HIC-1108B

! HCV-1108B 3.38 Verify HCV-1108B opens.

3.39 Open HCV-1108A.

3.40 Open FCV-1369.

3.41 Place Transfer Switch 43/RC-2A in the REMOTE position.

3.42 Reset Auxiliary Relay 43X/RC-2A.

R5

FORT CALHOUN STATION OP-ST-AFW-0006 SURVEILLANCE TEST PAGE 11 OF 13 Attachment 1 - AFW Operability Verification from AI-179 PROCEDURE (continued) INITIALS 3.43 Place Transfer Switch 43/RC-2B in the REMOTE position.

3.44 Reset Auxiliary Relay 43X/RC-2B.

3.45 Verify AUX FW SYSTEM LOCAL CONTROL (CB10/11, A9, C1U) clears.

4. Test Remaining Off Normal Annunciation and Logic 4.1 Manually actuate FW-64, Aux Feedwater Pump FW-10 Back Pressure

(%)

Trip Latch, and verify the following:

! White light on AI-179 is on

! White light on AI-66B is on

! FW-10 TURBINE DRIVEN FEEDWATER PUMP TROUBLE (AI-66B, A66B,18) in alarm 4.2 Reset FW-64, Aux Feedwater Pump FW-10 Back Pressure Trip Latch by pulling up FW-64-RL, Aux Feedwater Pump FW-10 Back Pressure Trip Latch Reset Lever, and verify trouble lights and annunciators return to normal.

! White light on AI-179 is off

! White light on AI-66B is off

! FW-10 TURBINE DRIVEN FEEDWATER PUMP TROUBLE (AI-66B, A66B,18) is clear

5. Place the following valve control switches in CLOSED:

! HCV-1107A (AI-66A)

! HCV-1107B (AI-66A)

! HCV-1108A (AI-66B)

! HCV-1108B (AI-66B)

! YCV-1045 (AI-66B)

! YCV-1045A (AI-66B)

! YCV-1045B (AI-66B)

! HCV-1107B (CB-10,11)

! HCV-1108B (CB-10,11)

R5

FORT CALHOUN STATION OP-ST-AFW-0006 SURVEILLANCE TEST PAGE 12 OF 13 Attachment 1 - AFW Operability Verification from AI-179 PROCEDURE (continued) INITIALS

(%)

6. In the Control Room verify the following:

! FCV-1368 open in NORM (CB-10/11)

! FCV-1368 open in AUTO (AI-66A)

! FCV-1369 open In AUTO (AI-66B)

Completed by Date/Time /

R5

FORT CALHOUN STATION OP-ST-AFW-0006 SURVEILLANCE TEST PAGE 13 OF 13 Comment Sheet R5

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0627 (h)

JPM

Title:

Reduce RCS Pressure using Aux Spray Location: Simulator Approximate Time: 12 minutes Actual Time: _________________

Reference(s): OI-RC-7 attachments 2 and 3 R12 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:

Page 1 of 7

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0627 (h)

JPM

Title:

Reduce RCS Pressure using Aux Spray Operators Name: _____________________ Employee # ______________

All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):

SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________

Reason, if unsatisfactory:

Tools & Equipment: None Safety Considerations: None Comments: Fail the normal pressurizer spray valves in the closed position. Ensure only B/U heater Bank 2 ON Page 2 of 7

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0627 (h)

JPM

Title:

Reduce RCS Pressure using Aux Spray INITIATING CUE: The Plant is in hot shutdown. The CRS has directed you to reduce RCS pressure to 1900 psia using pressurizer spray and automatic control.

All prerequisites are met START Critical Steps shown in gray STEP ELEMENT STANDARD Note: Provide a copy of OI-RC-7, attachment 3 when located by candidate.

1 (2.a) Verify PC-103Y is in automatic CB-1,2,3 PC-103Y controller in AUTO

[ SAT ] [ UNSAT ]

2 (2.b) Ensure proportional heaters CB-1,2,3 control switches are in auto. Group 6 and Group 7 switches in AUTO

[ SAT ] [ UNSAT ]

3 (2.c) Ensure backup heater switches CB-1,2,3 in auto Bank 1 Group 1/2/3, Bank 3 Group 8/9 and Bank 4 Group 10/11/12 switches in AUTO

[ SAT ] [ UNSAT ]

4 (2.d) Ensure pressurizer spray CB-1,2,3 valves in auto PCV-103-1 and PCV-103-2 control switches in AUTO

[ SAT ] [ UNSAT ]

Page 3 of 7

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0627 (h)

JPM

Title:

Reduce RCS Pressure using Aux Spray STEP ELEMENT STANDARD 5 (2.e) Lower RCS pressure by CB-1,2,3 adjusting setpoint pushbuttons Adjust setpoint push buttons in on PC-103Y small increments to lower pressure setpoint

[ SAT ] [ UNSAT ]

6 Determines the pressurizer CB-1,2,3 spray valves are not PCV-103-1 and PCV-103-2 responding GREEN lights lit

[ SAT ] [ UNSAT ]

7 (optional) May attempt to use PC-103X in CB-1,2,3 automatic to lower pressure Place channel selector switch in X position and repeat step 5 using PC-103X 8 (optional) May attempt to use manual Note: Provide a copy of OI-mode to lower RCS pressure RC-7, attachment 2 if located by candidate 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%

CUE: After candidate identifies failure of the spray valves, direct candidate to use aux spray in a controlled manner.

Page 4 of 7

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0627 (h)

JPM

Title:

Reduce RCS Pressure using Aux Spray STEP ELEMENT STANDARD 9 Lower pressure using Aux CB-1,2,3 spray Perform one or both of the following:

Place HCV-240 in the OPEN position.

Place HCV-249 in the OPEN position

[ SAT ] [ UNSAT ]

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 CB-1,2,3 psia, close the aux spray HCV-240 and HCV-249 both in valves. CLOSE position.

[ SAT ] [ UNSAT ]

12 Reopen loop charging valves CB-1,2,3 that may have been closed in ENSURE at least one loop step 10 charging valve is open to provide loop charging flow

HCV-247

HCV-238

HCV-248

HCV-239

[ SAT ] [ UNSAT ]

Page 5 of 7

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0627 (h)

JPM

Title:

Reduce RCS Pressure using Aux Spray Termination Criteria: The RCS is at 1900 psia and the Aux Spray valves are closed Page 6 of 7

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0627 (h)

INITIATING CUE: The Plant is in hot shutdown. The CRS has directed you to reduce RCS pressure to 1900 psia using pressurizer spray and automatic control.

All prerequisites are met START Page 7 of 7

FORT CALHOUN STATION OI-RC-7 OPERATING PROCEDURE C PAGE 9 OF 25 Continuous Use Attachment 2 - Manual RCS Pressure Control with a Steam Bubble in the Pressurizer PREREQUISITES (T) INITIALS

1. Procedure Revision Verification Revision 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 and PCV-103-2. _______

PROCEDURE NOTES

1. 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 Proportional Heaters 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 ___ _______

R12

FORT CALHOUN STATION OI-RC-7 OPERATING PROCEDURE C PAGE 10 OF 25 Continuous Use Attachment 2 - Manual RCS Pressure Control with a Steam Bubble in the Pressurizer PROCEDURE (continued) (T) INITIALS 1

b. 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 are in 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 or PC-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 of the 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 ___ _______

R12

FORT CALHOUN STATION OI-RC-7 OPERATING PROCEDURE C PAGE 11 OF 25 Continuous Use Attachment 2 - Manual RCS Pressure Control with a Steam Bubble in the Pressurizer PROCEDURE (continued) (T) INITIALS 1.f

2) IF the desired RCS pressure is less than normal operating pressure, THEN cycle the following heaters as necessary to maintain desired pressure:

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 Pressurizer and Spray Line is greater than 200EF.

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 ___ _______

R12

FORT CALHOUN STATION OI-RC-7 OPERATING PROCEDURE C PAGE 12 OF 25 Continuous Use Attachment 2 - Manual RCS Pressure Control with a Steam Bubble in the Pressurizer PROCEDURE (continued) (T) INITIALS 2

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. _______

e. WHEN the desired RCS pressure is attained, THEN place the Backup Heater Control Switches as required by one of the 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 desired RCS pressure is less than normal operating pressure, THEN cycle the following heaters as necessary to maintain desired pressure:

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 /____

R12

FORT CALHOUN STATION OI-RC-7 OPERATING PROCEDURE C PAGE 13 OF 25 Continuous Use Attachment 3 - Automatic RCS Pressure Control with a Steam Bubble in the Pressurizer PREREQUISITES (T) INITIALS

1. Procedure Revision Verification Revision Number Date:_________ _______

PROCEDURE NOTE RCS 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 ___ _______

NOTE During normal operation, one bank of pressurizer heaters is usually maintained in the ON position.

c. 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 ___ _______

R12

FORT CALHOUN STATION OI-RC-7 OPERATING PROCEDURE C PAGE 14 OF 25 Continuous Use Attachment 3 - Automatic RCS Pressure Control with a Steam Bubble in the Pressurizer PROCEDURE (continued) (T) INITIALS 1

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) on selected 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:

NOTE If the temperature differential between Pressurizer and Spray Line is greater than 200EF, refer to Attachment 10.

a. Verify the Selected Controller is in AUTOMATIC.

PC-103X, Pressurizer Press Controller ___

PC-103Y, Pressurizer Press Controller ___ _______

b. Ensure the following Proportional Heaters Control Switches are in AUTO:

75 KW Proportional Htrs Bank P1 Group 6 ___

75 KW Proportional Htrs Bank P2 Group 7 ___ _______

R12

FORT CALHOUN STATION OI-RC-7 OPERATING PROCEDURE C PAGE 15 OF 25 Continuous Use Attachment 3 - Automatic RCS Pressure Control with a Steam Bubble in the Pressurizer PROCEDURE (continued) (T) INITIALS NOTE During normal operation, one bank of pressurizer heaters is usually maintained in the ON position.

2

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 ___ _______

CAUTION When reducing RCS pressure, decreasing pressure in small increments will prevent overshoot from selected setpoint.

e. Lower RCS pressure by adjusting the Setpoint Push-button(s) on selected 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 /_____

R12

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0225 (i)

JPM

Title:

Initiate Air Compressor Backup Cooling Location: Room 19 Approximate Time: 10 minutes Actual Time: _________________

Reference(s): EOP-20, MVA-IA R16 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:

Page 1 of 5

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0225 (i)

JPM

Title:

Initiate Air Compressor Backup Cooling Operators Name: _____________________ Employee # ______________

All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):

SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________

Reason, if unsatisfactory:

Tools & Equipment: None Safety Considerations: 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 Page 2 of 5

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0225 (i)

JPM

Title:

Initiate Air Compressor Backup Cooling 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 Room-19 (Operator switch in the Control Room 1SS switch in CS position knowledge) Start position

[ SAT ] [ UNSAT ]

2 Ensure that the CA-1A load Room-19 (Operator transfer switch is either position Ensure Compressor load knowledge) 1 or 2 transfer switch in the 1 or 2 position

[ SAT ] [ UNSAT ]

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

[ SAT ] [ UNSAT ]

Page 3 of 5

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0225 (i)

JPM

Title:

Initiate Air Compressor Backup Cooling STEP ELEMENT STANDARD 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

[ SAT ] [ UNSAT ]

Notify Control Room that Contacts Control Room and Potable Water has been placed reports that potable water has on CA-1A been placed on CA-1A

[ SAT ] [ UNSAT ]

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

[ SAT ] [ UNSAT ]

Termination Criteria: CA-1A is being cooled by potable water Page 4 of 5

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0225 (i)

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 Page 5 of 5

EOP-20 Page 145 of 497 12.0 MAINTENANCE OF VITAL AUXILIARIES - IA MVA-IA INSTRUCTIONS CONTINGENCY ACTIONS CAUTION Do not allow Diesel Generator loads to exceed power and current rating limits.

2. IF any of the Air Compressors have 2.1 IF Turbine Plant Cooling Water is NOT tripped because of low Turbine Plant available, Cooling Water pressure, THEN align Potable Water to the Air THEN restore Turbine Plant Cooling Compressors by performing the Water by performing the following following steps:

steps:

a. Align backup Potable Water

a. Start ONE Bearing Water Pump, cooling to CA-1A, Air Compressor, AC-9A/B. by performing the following steps:

b. Verify cooling water header pressure is approximately 70 psig.

c. Start at least one Air Compressor, CA-1A/B/C. (continue)

(continue)

W Continuously Applicable or Non-Sequential Step R16

EOP-20 Page 146 of 497 12.0 MAINTENANCE OF VITAL AUXILIARIES - IA MVA-IA INSTRUCTIONS CONTINGENCY ACTIONS

2. (continued) 2.1.a (continued)

1) Close ALL of the following valves (Room 19):

! AC-584, "AIR COMPRESSOR CA-1A INTERCOOLER INLET VALVE"

! AC-588, "AIR COMPRESSOR CA-1A OUTLET VALVE" (continue)

! AC-586, "AIR COMPRESSOR CA-1A AFTERCOOLER CA-2A INLET VALVE"

! AC-589, "AIR COMPRESSOR CA-1A AFTERCOOLER CA-2A OUTLET VALVE" (continue)

W Continuously Applicable or Non-Sequential Step R16

EOP-20 Page 147 of 497 12.0 MAINTENANCE OF VITAL AUXILIARIES - IA MVA-IA INSTRUCTIONS CONTINGENCY ACTIONS

2. (continued) 2.1.a (continued)

2) Open ALL of the following valves (Room 19):

! AC-1042, "AIR COMPRESSOR CA-1A INTERCOOLER POTABLE WATER INLET VALVE"

! AC-1043, "AIR COMPRESSOR CA-1A POTABLE WATER OUTLET VALVE" (continue) ! 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)

W Continuously Applicable or Non-Sequential Step R16

EOP-20 Page 148 of 497 12.0 MAINTENANCE OF VITAL AUXILIARIES - IA MVA-IA INSTRUCTIONS CONTINGENCY ACTIONS

2. (continued) 2.1.a (continued)

4) Check for flow through FI-1955A (Room 19).

b. Align backup Potable Water cooling to CA-1B, Air Compressor, by performing the following steps:

1) Close ALL of the following valves (Room 19):

! AC-577, "AIR COMPRESSOR CA-1B INTERCOOLER INLET VALVE"

! AC-581, "AIR (continue)

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)

W Continuously Applicable or Non-Sequential Step R16

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0356 (j)

JPM

Title:

Emergency Start of Diesel-Generator D-1 Location: DG-1 Room Approximate Time: 12 minutes Actual Time: _________________

Reference(s): EOP/AOP Attachments, Attachment 12 R18 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:

Page 1 of 6

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0356 (j)

JPM

Title:

Emergency Start of Diesel-Generator D-1 Operators Name: _____________________ Employee # ______________

All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):

SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________

Reason, if unsatisfactory:

Tools & Equipment: None Safety Considerations: Observe Industrial Safety practices DO NOT operate and plant equipment Comments: In Plant alternate path JPM Page 2 of 6

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0356 (j)

JPM

Title:

Emergency Start of Diesel-Generator D-1 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 Attachment 12.

START Critical Steps shown in gray STEP ELEMENT STANDARD 1 (3.a) Place the Engine Control D1 Engine Control panel 143/SS switch to local 143/SS Switch to LOCAL

[ SAT ] [ UNSAT ]

2 (3.b) Press the Normal Engine D1 Engine Control panel Start push button Push NORMAL ENGINE START button

[ SAT ] [ UNSAT ]

CUE: D/G-1 did not start 3 (3.1.a) Place the Engine Control 143/SS switch to EMERG 143/SS Switch to EMERG

[ SAT ] [ UNSAT ]

4 (3.1.b) Press the Emergency Engine D1 Engine Control panel Start push button Push EMERGENCY ENGINE START button

[ SAT ] [ UNSAT ]

CUE: D/G-1 did not start Page 3 of 6

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0356 (j)

JPM

Title:

Emergency Start of Diesel-Generator D-1 STEP ELEMENT STANDARD 5 (5) Check primary air receiver tank D1 Engine Control panel and secondary air receiver tank Read indicators pressures.

CUE: both pressure indicators as read

[ SAT ] [ UNSAT ]

6 (14) Ensure overspeed trip is reset West end of D/G-1 Ensure trip is reset

[ SAT ] [ UNSAT ]

CUE: Overspeed trip is reset 7 (15.a) Place the Engine Control D1 Engine Control panel 143/SS switch in LOCAL Place 143/SS switch in the LOCAL position

[ SAT ] [ UNSAT ]

8 (15.b) Press the Normal Engine D1 Engine Control panel Start pushbutton Press NORMAL ENGINE START pushbutton

[ SAT ] [ UNSAT ]

CUE: D/G-1 did not start 9 (15.1) Manually override SA-142, On top of valve Diesel-Generator DG-1 Primary Open the T handled valve.

Air System Solenoid valve

[ SAT ] [ UNSAT ]

CUE: D/G-1 has started Page 4 of 6

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0356 (j)

JPM

Title:

Emergency Start of Diesel-Generator D-1 STEP ELEMENT STANDARD 10 (16) Ensure Engine Control 143/SS D1 Engine Control panel switch is in the EMERG 143/SS Switch in EMERG position

[ SAT ] [ UNSAT ]

11 (17) Check DG-1 speed D1 Engine Control panel

[ SAT ] [ UNSAT ]

CUE: speed reads 900 rpm Termination Criteria: D/G-1 is running at full speed.

Page 5 of 6

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0356 (j)

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 Attachment 12.

START Page 6 of 6

EOP/AOP ATTACHMENTS Page 49 of 150 Attachment 12 Emergency Start of Diesel Generator D-1 INSTRUCTIONS CONTINGENCY ACTIONS

1. Start D-1 by pressing the "DIESEL 1.1 IF D-1 did NOT start, NORMAL START" push button. THEN press the "EMERGENCY START" push button.

2. IF D-1 is running, THEN GO TO Step 17.

3. Start D-1 by performing the following 3.1 IF D-1 did NOT start, steps (Engine Control Panel): THEN start D-1 by performing the following steps (Engine Control Panel):

a. Place the "ENGINE CONTROL 143/SS" Switch in "LOCAL". a. Place the "ENGINE CONTROL 143/SS" Switch in "EMERG".

b. Press the "NORMAL ENGINE START" push button. b. Press the "EMERGENCY ENGINE START" push button.

4. IF D-1 is running, THEN GO TO Step 16.

R18

EOP/AOP ATTACHMENTS Page 50 of 150 Attachment 12 Emergency Start of Diesel Generator D-1 INSTRUCTIONS CONTINGENCY ACTIONS NOTE A minimum starting air pressure of 157 psig is required to start D-1.

5. IF "PRIMARY AIR RECEIVER TANK PRESSURE" 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 is 6.1 IF the Secondary Air Start System is available, available, THEN align the Emergency THEN align the Emergency Compressor to the Primary Air Compressor to the Secondary Air Receivers by performing the following Receivers by performing the following steps (D-1 room): steps (D-1 room):

a. Ensure the "ENGINE CONTROL a. Ensure the "ENGINE CONTROL 143/SS" Switch is in "LOCAL". 143/SS" Switch is in "LOCAL".

b. Place "SA-2-1 PRIMARY b. Place "SA-23-1 SECONDARY COMPRESSOR 43/AS2" Switch in COMPRESSOR 43/AS1" Switch in "OFF". "OFF".

(continue) (continue)

R18

EOP/AOP ATTACHMENTS Page 51 of 150 Attachment 12 Emergency Start of Diesel Generator D-1 INSTRUCTIONS CONTINGENCY ACTIONS

6. (continued) 6.1 (continued)

c. Ensure BOTH of the following c. Ensure BOTH of the following valves are closed: valves are closed:

! SA-214, "PRESSURE ! SA-215, "PRESSURE CONTROLLER PC-6040A CONTROLLER PC-6040A SECONDARY AIR SYSTEM PRIMARY AIR SYSTEM ROOT VALVE" ROOT VALVE"

! SA-280, "EMERGENCY ! SA-204, "EMERGENCY COMPRESSOR SA-1-1 COMPRESSOR SA-1-1 SECONDARY AIR SYSTEM PRIMARY AIR SYSTEM ISOLATION VALVE" ISOLATION VALVE"

d. Open BOTH of the following d. Open BOTH of the following valves: valves:

! SA-215, "PRESSURE ! SA-214, "PRESSURE CONTROLLER PC-6040A CONTROLLER PC-6040A PRIMARY AIR SYSTEM SECONDARY AIR SYSTEM ROOT VALVE" ROOT VALVE"

! SA-204, "EMERGENCY ! SA-280, "EMERGENCY COMPRESSOR SA-1-1 COMPRESSOR SA-1-1 PRIMARY AIR SYSTEM SECONDARY AIR SYSTEM ISOLATION VALVE" ISOLATION VALVE" R18

EOP/AOP ATTACHMENTS Page 52 of 150 Attachment 12 Emergency Start of Diesel Generator D-1 INSTRUCTIONS CONTINGENCY ACTIONS

7. 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-HEAT SWITCH" push button for one minute.

R18

EOP/AOP ATTACHMENTS Page 53 of 150 Attachment 12 Emergency Start of Diesel Generator D-1 INSTRUCTIONS CONTINGENCY ACTIONS

11. Start the Diesel Engine by performing the following steps:

a. Press and hold the "PRE-HEAT SWITCH" push button.

b. Press the "PUSH TO START" push button.

c. WHEN the diesel reaches full cranking speed, THEN release the "PRE-HEAT SWITCH" push button.

d. Place the "DECOMP SW" in "RUN".

R18

EOP/AOP ATTACHMENTS Page 54 of 150 Attachment 12 Emergency Start of Diesel Generator D-1 INSTRUCTIONS CONTINGENCY ACTIONS

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 RECEIVER TANK PRESSURE" or "SECONDARY AIR RECEIVER TANK PRESSURE" is greater than 157 psig (Engine Control Panel),

THEN ensure the overspeed trip is reset (West end of D-1).

R18

EOP/AOP ATTACHMENTS Page 55 of 150 Attachment 12 Emergency Start of Diesel Generator D-1 INSTRUCTIONS CONTINGENCY ACTIONS

15. Start D-1 by performing the following ***************************************************

steps (Engine Control Panel):

CAUTION This step may damage the Air Start Motors if

a. Place the "ENGINE CONTROL the manual override is not released after a 143/SS" Switch in "LOCAL". few seconds.

b. Press the "NORMAL ENGINE START" push button.

15.1 IF D-1 did NOT start, AND the Primary Air Receivers are pressurized, 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 start AND the Secondary Air Receivers are pressurized, THEN manually override SA-141, "DIESEL GENERATOR DG-1 SECONDARY AIR SYSTEM SOLENOID VALVE", using the "T" handle located on top of the valve.

R18

EOP/AOP ATTACHMENTS Page 56 of 150 Attachment 12 Emergency Start of Diesel Generator D-1 INSTRUCTIONS CONTINGENCY ACTIONS

16. Ensure the "ENGINE CONTROL 143/SS" Switch in "EMERG" to return D-1 start function to the Control Room.

17. Check that D-1 is operating at greater than or equal to 900 rpm.

End of Attachment 12 R18

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0719M (k)

JPM

Title:

Startup Containment Hydrogen Purge and Makeup Location: Aux Building (RCA)

Approximate Time: 15 min Actual Time: _________________

Reference(s): OI-VA-1 Attachment 5A and 5B R57 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:

Page 1 of 7

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0719M (k)

JPM

Title:

Startup Containment Hydrogen Purge and Makeup Operators Name: _____________________ Employee # ______________

All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):

SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________

Reason, if unsatisfactory:

Tools & Equipment: None Safety Considerations: Observe industrial and radiological safety practices DO NOT operate any plant equipment Comments: This static JPM is conducted inside the RCA Page 2 of 7

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0719M (k)

JPM

Title:

Startup Containment Hydrogen Purge and Makeup 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 to complete the Aux building steps 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 initiated 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 Corr. 26 is closed IA-VA-411-B1 in FILTERED

[ SAT ] [ UNSAT ]

2 Ensure VA-291/VA-279 Corr 26 combined remote operator is VA-291/VA-279 CLOSED closed.

[ SAT ] [ UNSAT ]

3 Ensure VA-282/VA-284 Corr 26 combined remote operator is VA-282/VA-284 CLOSED closed.

[ SAT ] [ UNSAT ]

4 Open hydrogen purge valves Corr 26 for VA-80A: Unlock and OPEN valves

VA-290

VA-292 [ SAT ] [ UNSAT ]

VA-289 Page 3 of 7

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0719M (k)

JPM

Title:

Startup Containment Hydrogen Purge and Makeup STEP ELEMENT STANDARD 5 Contact Control Room

[ SAT ] [ UNSAT ]

CUE: Control room reports procedure steps 8,9 and 10 have been completed 6 Start hydrogen purge fan, VA- AI-100 80A Place VA-80A control switch in PULL TO OVERRIDE Red Light ON Green Light OFF

[ SAT ] [ UNSAT ]

7 Monitor DPI-899D Corr 26 CUE: DPI-899D indicates 10w.g.

[ SAT ] [ UNSAT ]

8 Ensure VA-281/VA-283 Corr 26 combined remote operator is VA-281/VA-283 CLOSED closed.

[ SAT ] [ UNSAT ]

9 Open VA-282/VA-284 VA-80B Corr 26 suction from Aux Bldg/recirc VA-282/VA-284 OPEN valve

[ SAT ] [ UNSAT ]

10 Open VA-280 Corr 26 VA-280 OPEN

[ SAT ] [ UNSAT ]

Page 4 of 7

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0719M (k)

JPM

Title:

Startup Containment Hydrogen Purge and Makeup STEP ELEMENT STANDARD 11 Record initial hydrogen Contact Control Room concentration and sample point in CR log. [ SAT ] [ UNSAT ]

CUE: Procedure steps 11d through 16 will be performed by Control Room; Proceed with Attachment 5B NOTE: Steps 12 and 13 must be done sequentially (within 30 seconds of each other) 12 Start hydrogen purge fan, VA- AI-100 80B Place VA-80B control switch in PULL TO OVERRIDE Red Light ON Green Light OFF

[ SAT ] [ UNSAT ]

13 Contact control room to place Contact control room within HCV-881 in override. 30 seconds of starting VA-80B or coordinate with Control Room to ensure step 13 is completed within 30 seconds of completion of step 12.

[ SAT ] [ UNSAT ]

CUE: The control room has placed HCV-881 in OVERRIDE STOP Page 5 of 7

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0719M (k)

JPM

Title:

Startup Containment Hydrogen Purge and Makeup Termination Criteria: The hydrogen purge system is in operation with VA-80A purging hydrogen from containment and VA-80B supplying makeup air Page 6 of 7

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0719M (k)

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 to complete the Aux building steps 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 initiated and have not been reset OI-VA-1 is complete through step 6. HC-745 has been placed in HAND START Page 7 of 7

FORT CALHOUN STATION OI-VA-1 OPERATING INSTRUCTION PAGE 20 OF 120 C

Continuous Use Attachment 5A - Hydrogen Purge Release VA-80A & VA-80B PREREQUISITES (%) INITIALS

1. 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 (Turbine Building Roof).

7. No Waste Gas Decay Tank Release is in progress.

8. One Noble Gas Radiation Monitor is in operation monitoring the Auxiliary Building 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-site 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) H2 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, Containment Hydrogen Analyzer is in service sampling Containment per OI-VA-6.

R57

FORT CALHOUN STATION OI-VA-1 OPERATING INSTRUCTION PAGE 21 OF 120 C

Continuous Use Attachment 5A - Hydrogen Purge Release VA-80A & VA-80B PREREQUISITES (continued) (T) INITIALS

13. 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 operable 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 monitor at the alert limit. (RM-051 or RM-052)

NOTE The radiation monitor is considered inoperable during the check source.

Remaining stationed at the monitor AND ensuring the monitor returns to normal before leaving the area administratively 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) H2 Analyzer VA-81A(B) Recorder (AI-65)

6. Place HC-745, Post Accident Cntmt Press, to HAND.

R57

FORT CALHOUN STATION OI-VA-1 OPERATING INSTRUCTION PAGE 22 OF 120 C

Continuous Use Attachment 5A - Hydrogen Purge Release VA-80A & VA-80B PROCEDURE (continued) (T) INITIALS

7. 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 Hydrogen Purge Fan VA-80A Suction Valve from Aux Building/Recirc Valve, combined remote operator is closed.

c. Ensure VA-282/VA-284, Cntmt Hydrogen 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 Purge 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 Purge 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.

R57

FORT CALHOUN STATION OI-VA-1 OPERATING INSTRUCTION PAGE 23 OF 120 C

Continuous Use Attachment 5A - Hydrogen Purge Release VA-80A & VA-80B PROCEDURE (continued) (T) INITIALS

9. IF normal startup, THEN place the H2 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 H2 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.

R57

FORT CALHOUN STATION OI-VA-1 OPERATING INSTRUCTION PAGE 24 OF 120 C

Continuous Use Attachment 5A - Hydrogen Purge Release VA-80A & VA-80B PROCEDURE (continued) (T) INITIALS 11.d 3) 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 the FC-212 count rate limit was set in the ERF, THEN record RM-051 or RM-052, Cntmt Noble Gas Radiation Monitor, reading as required by 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 radiation monitor becomes inoperable, THEN notify Chemistry to annotate the release permit.

15. IF RM-051 and/or RM-052 Containment 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 Dose Calculation Manual (ODCM).

b. Table II stop and start readings.

c. Table III release flow readings every four hours by logging Containment pressure and stack flow.

17. Prior to the release expiration, place the running Hydrogen Purge Blower(s)

Control Switch to AFTER STOP (AI-100):

! VA-80A

! VA-80B R57

FORT CALHOUN STATION OI-VA-1 OPERATING INSTRUCTION PAGE 25 OF 120 C

Continuous Use Attachment 5A - Hydrogen Purge Release VA-80A & VA-80B PROCEDURE (continued) (T) INITIALS

18. Place the H2 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) H2 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 Valve 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 Valve 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)

R57

FORT CALHOUN STATION OI-VA-1 OPERATING INSTRUCTION PAGE 26 OF 120 C

Continuous Use Attachment 5A - Hydrogen Purge Release VA-80A & VA-80B PROCEDURE (continued) (T) INITIALS 22 b. 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 /

R57

FORT CALHOUN STATION OI-VA-1 OPERATING INSTRUCTION PAGE 27 OF 120 C

Continuous Use Attachment 5B - Supply of Auxiliary Building Air to Containment VA-80A & VA-80B PREREQUISITES (%) INITIALS

1. 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 Purge Fan VA-80A Suction Valve from Containment/Cntmt Hydrogen Purge Fan VA-80A Discharge Valve

! VA-80B VA-281/VA-283, Cntmt Hydrogen Purge Fan VA-80B Suction Valve from Containment/Cntmt Hydrogen Purge Fan VA-80B Discharge Valve R57

FORT CALHOUN STATION OI-VA-1 OPERATING INSTRUCTION PAGE 28 OF 120 C

Continuous Use Attachment 5B - Supply of Auxiliary Building Air to Containment VA-80A & VA-80B PROCEDURE (continued) (T) INITIALS

3. Open the following valves for the desired unit (Corr. 26):

! VA-80A VA-291/VA-279, Cntmt Hydrogen Purge 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 Purge 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 performed 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 H2 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 R57

FORT CALHOUN STATION OI-VA-1 OPERATING INSTRUCTION PAGE 29 OF 120 C

Continuous Use Attachment 5B - Supply of Auxiliary Building Air to Containment VA-80A & VA-80B PROCEDURE (continued) (T) INITIALS CAUTION Parts a and b of Step 6 must be performed 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 H2 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 H2 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 Blower 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.

R57

FORT CALHOUN STATION OI-VA-1 OPERATING INSTRUCTION PAGE 30 OF 120 C

Continuous Use Attachment 5B - Supply of Auxiliary Building Air to Containment VA-80A & VA-80B PROCEDURE (continued) (T) INITIALS

10. Close the following valves for the affected unit (Corr. 26):

! VA-80A VA-291/VA279, Cntmt Hydrogen Purge Fan VA-80A Suction Valve from Aux Building/recirc Valve

! VA-80B VA-282/VA-284, Cntmt Hydrogen Purge Fan VA-80B Suction Valve from 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 /

R57

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}

Place protected equipment tags on FW-6 and FW-10. Cover simulator fidelity items.

Turnover: CCW-Pump, AC-3A and Diesel Driven AFW pump FW-54 are tagged out of service Maintain Power Operations Event Malf Event Event No. No. Type* Description 1 COP T:F212 I - ATC Letdown flow transmitter fails high - letdown isolates 160 (3:00) 2 COP I - BOP S/G A level transmitter fails low - manual FW flow control T:L903X 0%

(12:00) 60 sec ramp required 3 COP C - BOP IA Compressor trips, standby does not load NCAPCA1C (18:00) TRIP 4 MFP CRD06 C - ATC Dropped CEA - T/S Entry R1G1 (24:00) Deenergized 5 N/A R - ATC TS Required power reduction to 70%

N - BOP 6 MFP C - ATC Instrument Bus Fails - T/S Entry EDS04B (40:00) 7 MSS01A M - ALL Main steam line break inside containment 20%

(50:00) 2 min ramp 8 Preset C - BOP Turbine fails to trip 9 Preset I - ATC CPHS Fails to Actuate or BOP

(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 Applicants Actions or Behavior SRO/ATC Responds to Letdown High Flow and Intermediate Letdown Press HI-LO alarms BOP Acknowledges alarms ATC Reviews ARP-CB-1,2,3/A2 B1L and A1L for appropriate actions ATC Ensures HCV-204 has automatically closed. Close TCV-202 ATC Determines that Flow instrument FI-212 has failed high ATC If XC-105 10 minute average power computer alarm comes in, verify NI and delta-T power.

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-101-1/101-2 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 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 Place 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 Applicants 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 Applicants 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 BOP Direct Water Plant Operator to check out CA-1C trip 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 Applicants 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 <C> Enter Tech Spec Section 2.10.2 Reactor power must be reduced to less than 70% within one hour. The CEA must be realigned or declared inoperable within one hour following the power reduction. If the CEA is declared inoperable, the reactor must be in hot shutdown within an additional 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months .

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 required power reduction to 70%

Time Position Applicants Actions or Behavior SRO <C> 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 Applicants 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 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 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 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

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 Applicants 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 ATC Verify Emergency Boration Flow SRO Diagnose event and enter EOP-05

Appendix D Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 2005-1 Event No.: 9 Page 9 of 9 Event

Description:

CPHS fails to actuate Time Position Applicants Actions or Behavior SRO

Direct chemist to sample both S/Gs

Direct BOP to verify proper S/G isolation following SGIS signal BOP Verify SGIS

MSIVs 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 Manually actuate CPHS

<C>

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 <C> 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 <C> Throttle and/or stop HPSI flow SRO Direct ATC to monitor and control RCS pressure to maintain subcooling between 20° and 200°F.

ATC Monitor and control RCS pressure to maintain subcooling between 20° and 200°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)

Hang protected equipment tags on FW-6 and FW-10.

Turnover: CCW-Pump, AC-3A and Diesel Driven AFW pump FW-54 are tagged out of service Maintain Power Operations Event Malf Event Event No. No. Type* Description 1 MFP I - ATC Power Range NI Channel C Fails - T/S entry NIS04C (3:00) 2 COP I - BOP S/G B level transmitter fails to 55%

T:L906X (10:00) 55%

3 COP C - BOP Bearing Water Pump AC-9A Trips NBWPAC9 (16:00) A trip 4 T:T122H2 I -ATC RCS T-hot fails - T/S entry 665°F (20:00) 5 MFP C - ATC Charging Pump CH-1B degraded performance CVC16B (30:00) 6 MFP M- Steam Generator Tube Rupture SGN01A (40:00) 15% 120s ALL ramp 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 Applicants 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) May enter ARP SRO Enter AOP-15

<C> SRO Enter Technical Specification 2.15 RPS channel C trip units 1, 9 and 12 must be placed in bypass within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . 48 hour5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months 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 Applicants 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 Applicants 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 Applicants 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)

<C> 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 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or else the plant must be placed in hot shutdown within the following 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

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 With NI channel C trip units 1, 9 and 12 bypassed and Delta-T channel A trip units tripped, power must be reduced to less than 70% (no time limit)

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 Applicants 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 <C> 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 Tube Rupture, 2 CEAs fail to insert Time Position Applicants 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 Applicants 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°F BOP Cooldown RCS T-hot to less than 510°F ATC Identify and verify PPLS actuation ATC <C> When RCS pressure reaches 1350 psia, ensure no more than 1 RCP operating in each loop SRO Request Chemistry to perform Rapid Activity Analysis 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)

FW-266 and FW-268 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 psia 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)

Protected equipment tag on FW-5B RunScreens file 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. PCMINT is not available.

Event Malf Event Event No. No. Type* Description 1 MFP C - ATC D/G #1 Radiator Leak - T/S Entry DSG06A (3:00) 100% or BOP 2 COP T:P910 I - BOP PT-910 Fails High 1000 psi (12:00) 3 COP I - ATC Letdown heat exchanger temperature transmitter fails low T:T2897 (18:00) 50°F 4 MFP C - BOP Loss of 161 KV - T/S Entry SWD02B (25:00) 5 COP I - ATC Pressurizer pressure transmitter PT-103Y fails high T:P103Y (35:00) 2556 90 sec ramp 6 COP T: I - BOP S/G B level transmitter LT-906Y fails high (Manual control L906Y (40:00) 100% 60 using Aux controller required) sec ramp 7 MFP C - ATC Raw Water header leak RWS01B (45:00) 25%

8 MFP M - ALL LOCA with Loss of offsite power RCS01C 5%

(55:00) 9 Preset C-BOP Circulating Water Pump Breaker 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 Applicants 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 Applicants 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 Applicants 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°F - 120°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 Applicants 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 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 (step 5 of AOP-31)

SRO Direct that signs be placed at entrances to switchgear rooms Review EOP-02, EOP-07 and EOP-20 SRO <C> Enter Tech Spec 2.7 Due to the loss of 161 KV and D/G-1 being inoperable, Tech Spec 2.0.1 must be entered which requires that the plant be placed in hot shutdown within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . 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 Applicants 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 Applicants 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 Applicants 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-10Bs discharge valve, HCV-2851) May enter AOP-18.

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°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 <C> 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 Applicants 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 its 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 (NOTE: EONT will trip breaker 2.5 minutes after being directed)

SRO If bus 1A4 is repowered, then enter EOP-03.

If bus 1A4 is not powered, then enter EOP-20 and 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}

Protected equipment tags on FW-5B 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. PCMINT is not available.

Event Malf Event Event No. No. Type* Description 1 COP I - ATC VCT Level Transmitter Fails Low JLB218LL (3:00) Fail_set 2 COP I - BOP S/G A Level transmitter fails high T:L903X (8:00) 100% 45 sec ramp 3 COP I - ATC RCS Flow transmitter failure - T/S Entry T:F114YA (15:00) 0 4 MFP I - BOP Inadvertent AFAS actuation - T/S Entry AFW05A (22:00) 5 COP RCAP C - ATC Instrument air to containment isolates 849A&B (30:00) 0%

6 MFP C - BOP Loss of condenser vacuum CND01 30%

(40:00) 300 sec ramp 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 9 Event

Description:

VCT Level Transmitter fails low CB-1,2,3 A2 B2L Time Position Applicants 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 9 Event

Description:

Steam Generator A level transmitter 903X fails high.

Time Position Applicants 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.

Appendix D Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 2005-4 Event No.: 3 Page 4 of 9 Event

Description:

RCS Flow transmitter failure. Tech Spec entry.

Time Position Applicants 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 Verify RCP amps 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 9 Event

Description:

Inadvertent AFAS actuation - Tech Spec Entry Time Position Applicants 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 <C> Refer to Tech Specs 2.5, 2.15 and 2.01 Plant is in a 6 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months LCO with no operable AFW pumps (Note: if requested, all S/G level indication on AI-179 is reading 80-81%)

Appendix D Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 2005-4 Event No.: 5 Page 6 of 9 Event

Description:

Instrument Air Containment Isolation valve fails closed.

Time Position Applicants 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 9 Event

Description:

Loss of Condenser Vacuum, Reactor Trip - no steam dump and bypass valves Time Position Applicants 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 9 Event

Description:

Steam Generator Safety Valve sticks open Time Position Applicants 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: Close the following

HCV-1042A (B MSIV)

HCV-1042C (B MSIV bypass)

MS-292 (atmospheric steam safety valve)

FCV-1102 (FW reg valve)

HCV-1106 ( FW reg bypass valve)

HCV-1385 (FW header isolation)

HCV-1104 (FW reg block valve)

HCV-1387A&B (blowdown isolation valves)

HCV-1108A&B (AFW isolation)

MS-298 (MSIV packing leakoff)

BOP Establish FW flow to good S/G. May need to manually start AFW pump and go to override on valves SRO Direct BOP to establish steam flow from good S/G prior to dryout of affected S/G

Appendix D Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 2005-4 Event No.: 8 cont Page 9 of 9 Event

Description:

Steam Generator Safety Valve sticks open Time Position Applicants Actions or Behavior 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°F subcooling)

SCENARIO ENDS with HPSI stop and throttle and RCS pressure and temperature under control

ML061070599

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