ML091030682
| ML091030682 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 03/27/2009 |
| From: | Brian Larson Operations Branch IV |
| To: | Omaha Public Power District |
| References | |
| 50-285/09-301, ES-301, ES-301-1 50-285/09-301 | |
| Download: ML091030682 (401) | |
Text
ES-301 Administrative Topics Outline Form ES-301-1 Facility: __Fort Calhoun______________ Date of Examination: __3/30/09_____
Examination Level: RO Revision Number: 2 Administrative Topic Type Describe activity to be performed (see Note) Code*
A-1 M, R Calculate Shutdown Margin with inoperable CEA Conduct of Operations KA 2.1.37 (RO Imp 4.3)
A-2 N, R Determine Pressurizer Level During Cooldown Conduct of Operations KA 2.1.25 (RO Imp 3.9)
A-3 N, R Determine Equipment Lost by Tagout of an MCC Equipment Control KA 2.2.41 (RO Imp 3.5)
A-4 D RCA Entry and Exit with PCM Alarms Radiation Control KA 2.3.13 (RO Imp 3.4)
Emergency Procedures/Plan NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.
- Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes)
(N)ew or (M)odified from bank ( 1)
(P)revious 2 exams ( 1; randomly selected)
ES-301 Administrative Topics Outline Form ES-301-1 Facility: __Fort Calhoun_______________ Date of Examination: _3/30/09____
Examination Level: SRO Revision Number: 2 Administrative Topic Type Describe activity to be performed (see Note) Code*
A-5 M, R Review Shutdown Margin Calculation with inoperable CEA Conduct of Operations KA 2.1.37 (SRO Imp 4.6)
A-6 M, R Determine Shift Staffing Conduct of Operations KA 2.1.5 (SRO Imp 3.9)
A-7 D, R Determine RW System Operability Equipment Control KA 2.2.37 (SRO Imp 4.6)
A-8 D, R Authorize Release of Monitor Tank WD-22B Radiation Control KA 2.3.6 (SRO Imp 3.6)
A-9 M, R Emergency Classification and PARs Emergency Procedures/Plan KA's 2.4.41 (SRO Imp 4.6) and 2.4.44 (SRO Imp 4.4)
NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.
- Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes)
(N)ew or (M)odified from bank ( 1)
(P)revious 2 exams ( 1; randomly selected)
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: __Fort Calhoun_____________________ Date of Examination: 3/30/09__
Exam Level: RO Revision Number.: 2 Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)
System / JPM Title Type Code* Safety Function S-1. 001000 A4.03 / Control Element Assembly Movement Test S, N, A 1 S-2. 004000 A4.08 / Establish Charging Flow via the HPSI Header S, N 2 S-3 006000 A1.11 / Simultaneous Hot and Cold Leg Injection S,A, M, EN, L 3 S-4. 003000 A4.06 / Start a Reactor Coolant Pump S, A, L,M 4P S-5 061000 A2.04 / Initiate AFW to SGs S, EN, A, N, L 4S S-6 028000 A1.01 / Operate the Containment Hydrogen Analyzer S, D 5 S-7 062000 A4.01 / Transfer 4160 volt busses from 345 KV to 161 S, D 6 KV S-8. 012000 A4.02 / RPS Power Adjustment S, N 7 In-Plant Systems (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
P-1 022000 A2.05 / Provide Raw Water Backup Cooling to E,R,M 5 Containment Coolers P-2 000055 EA1.07 / Energize 480 volt buses from 13.8 KV E, N 6 P-3 086000 A2.04 / Local Emergency Manual Start of the Diesel Fire E,A,D 8 Pump
@ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
- Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank 9/8/4 (E)mergency or abnormal in-plant 1/1/1 (EN)gineered safety feature - / - / 1 (control room system)
(L)ow-Power / Shutdown 1/1/1 (N)ew or (M)odified from bank including 1(A) 2/2/1 (P)revious 2 exams 3 / 3 / 2 (randomly selected)
(R)CA 1/1/1 (S)imulator
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: __Fort Calhoun_____________________ Date of Examination: 3/30/09__
Exam Level: ISRO Revision Number.: 2 Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)
System / JPM Title Type Code* Safety Function S-1. 001000 A4.03 / Control Element Assembly Movement Test S, N, A 1 S-2. 004000 A4.08 / Establish Charging Flow via the HPSI Header S, N 2 S-3 006000 A1.11 / Simultaneous Hot and Cold Leg Injection S,A, M, EN, L 3 S-4. 003000 A4.06 / Start a Reactor Coolant Pump S, A, L,M 4P S-5 061000 A2.04 / Initiate AFW to SGs S, EN, A, N, L 4S S-7 062000 A4.01 / Transfer 4160 volt busses from 345 KV to 161 S, D 6 KV S-8. 012000 A4.02 / RPS Power Adjustment S, N 7 In-Plant Systems (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
P-1 022000 A2.05 / Provide Raw Water Backup Cooling to E,R,M 5 Containment Coolers P-2 000055 EA1.07 / Energize 480 volt buses from 13.8 KV E, N 6 P-3 086000 A2.04 / Local Emergency Manual Start of the Diesel Fire E,A,D 8 Pump
@ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
- Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank 9/8/4 (E)mergency or abnormal in-plant 1/1/1 (EN)gineered safety feature - / - / 1 (control room system)
(L)ow-Power / Shutdown 1/1/1 (N)ew or (M)odified from bank including 1(A) 2/2/1 (P)revious 2 exams 3 / 3 / 2 (randomly selected)
(R)CA 1/1/1 (S)imulator
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: __Fort Calhoun_____________________ Date of Examination: 3/30/09__
Exam Level: USRO Revision Number.: 2 Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)
System / JPM Title Type Code* Safety Function S-3 006000 A1.11 / Simultaneous Hot and Cold Leg Injection S,A, M, EN, L 3 S-5 061000 A2.04 / Initiate AFW to SGs S, EN, A, N, L 4S In-Plant Systems (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
P-1 022000 A2.05 / Provide Raw Water Backup Cooling to E,R,M 5 Containment Coolers P-2 000055 EA1.07 / Energize 480 volt buses from 13.8 KV E, N 6 P-3 086000 A2.04 / Local Emergency Manual Start of the Diesel Fire E,A,D 8 Pump
@ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
- Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank 9/8/4 (E)mergency or abnormal in-plant 1/1/1 (EN)gineered safety feature - / - / 1 (control room system)
(L)ow-Power / Shutdown 1/1/1 (N)ew or (M)odified from bank including 1(A) 2/2/1 (P)revious 2 exams 3 / 3 / 2 (randomly selected)
(R)CA 1/1/1 (S)imulator
Appendix D Scenario Outline Form ES-D-1 Facility: Fort Calhoun Scenario No: 2009-2 Revision: 3 Examiners: _________________________ Operators: _________________________
Initial Conditions: 100% Power DG-1 Out of Service replacing contactors for 2CR relays.
Turnover: Rotate Condenser Evacuation Pumps, then rotate Containment Cooling Units.
Event Malf Event Event No. No. Type* Description 1 N-BOPO Rotate Condenser Evacuation Pumps per OI-CE-1, Attachment (2 min) 3.
2 N-ATCO Rotate Containment Cooling Units In accordance with OI-VA-1.
(10 min) 3 C-ATCO Dropped CEA - Tech Spec Entry.
LE CUE C-BOPO 4 R-ATCO AOP-05 shutdown to 70% Power.
N-BOPO 5 I-ATCO Controlling Pressurizer Pressure Transmitter, PT-103Y, Fails LE CUE High.
6 C-BOPO Loss of 161 KV - Tech Spec Entry.
LE CUE 7 C-ATCO Another Dropped CEA - Manual Reactor Trip Required.
LE CUE 8 M-ALL Circulating Water Pump, CW-1C, Breaker fails to open preventing DG from loading onto bus 1A4 - Station Blackout.
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Target Quantitative Attributes (Per Scenario; See Section D.5.d) Actual Attributes
- 1. Total malfunctions (5-8) 5
- 2. Malfunctions after EOP entry (1-2) 1
- 3. Abnormal events (2-4) 3
- 4. Major transients (1-2) 1
- 5. EOPs entered/requiring substantive actions (1-2) 1
- 6. EOP contingencies requiring substantive actions (0-2) 1
- 7. Critical tasks (2-3) 2
Appendix D Scenario Outline Form ES-D-1 Facility: Fort Calhoun Scenario No: 2009-4 Revision: 4 Examiners: _________________________ Operators: _________________________
Initial Conditions: 50% Power, Diesel Driven AFW Pump, FW-54, Out of Service, Main Feed Pumps, FW-4A and FW-4C, Out of Service.
Turnover: Maintain 50% operation. Rotate CCW Pumps.
Event Malf Event Event No. No. Type* Description 1 N-ATCO Rotate CCW Pumps.
(2 min) 2 C-BOPO Isolated Phase Bus Duct Cooling Fan Motor Trips.
LE CUE 3 I-ATCO Pressurizer Pressure Safety Channel fails Low - Tech Spec LE CUE TS-CRS Entry.
4 C - ATCO 10-15 gpm leak to containment - Tech Spec Entry.
LE CUE TS-CRS 5 I-BOPO Steam header pressure transmitter, PT-910 Fails High.
LE CUE 6 C - ATCO Feedwater Pump Trips, Reactor Trip.
LE CUE 7 C-BOPO Blowdown fails to isolate automatically.
8 M - ALL Pipe from EFWST to FW-6 and FW-10 breaks. Total Loss of LE CUE Feedwater.
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Target Quantitative Attributes (Per Scenario; See Section D.5.d) Actual Attributes
- 1. Total malfunctions (5-8) 7
- 2. Malfunctions after EOP entry (1-2) 2
- 3. Abnormal events (2-4) 2
- 4. Major transients (1-2) 1
- 5. EOPs entered/requiring substantive actions (1-2) 1
- 6. EOP contingencies requiring substantive actions (0-2) 1
- 7. Critical tasks (2-3) 2 or 3
Appendix D Scenario Outline Form ES-D-1 Facility: Fort Calhoun Scenario No: 2009-1 (SPARE) Revision: 3 Examiners: _________________________ Operators: _________________________
Initial Conditions: 100% Power. Diesel Driven AFW Pump, FW-54, is out of service. Air Compressor, CA-1A, is out of service.
Turnover: Transfer Letdown Control Valves from LCV-101-1 to LCV-101-2. After that rotate running EHC Pumps.
Event Malf Event Event No. No. Type* Description 1 N-ATCO Transfer Letdown Flow Control Valves.
(2 min) 2 N-BOPO Rotate EHC Pumps.
(14 min) 3 I-ATCO Power Range NI Channel B fails - Tech Spec Entry.
LE CUE 4 C-BOPO Running Bearing Cooling Water Pump, AC-9A, trips.
LE CUE 5 I-ATCO Loop Two Hot Leg RTD, TT-122H, Fails High - Tech Spec LE CUE Entry 6 C-All Loss of Instrument Air.
LE CUE 7 C-ATCO Manual Reactor Trip Required.
8 M-All Steam Generator Safety Valve Fails Open.
LE CUE
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Target Quantitative Attributes (Per Scenario; See Section D.5.d) Actual Attributes
- 1. Total malfunctions (5-8) 5
- 2. Malfunctions after EOP entry (1-2) 1
- 3. Abnormal events (2-4) 2
- 4. Major transients (1-2) 1
- 5. EOPs entered/requiring substantive actions (1-2) 1
- 6. EOP contingencies requiring substantive actions (0-2) 1
- 7. Critical tasks (2-3) 3
ES-301 Transient and Event Checklist Form ES-301-5 Facility: Fort Calhoun Date of Exam: 3/30/09 Revision Number.: 3 A E Scenarios P V 1 2 3 4 T M P E O I L N CREW CREW CREW CREW POSITION T N I T POSITION POSITION POSITI A I
ON M C L U A T C A B C A B C A B C A B M(*)
N Y R T O R T O R T O R T O R I U T P S C P S C P S C P S C P E O O O O O O O O RX 4 1 1 1 0 NOR 1,2,4 3 1 1 1 USRO- I/C 3,5,6,7 2,5,7 7 4 4 2 1,2 MAJ 8 8 2 2 2 1 TS 3,6 2 0 2 2 RX 4 1 1 1 0 NOR 2 1 2 1 2 1 ISRO-1,2 I/C 3,5,7 2,3,4,5,6,7 9 4 4 2 MAJ 8 8 2 2 2 1 TS 3,4 2 0 2 2 RX 1 1 0 NOR 1,4 1 3 1 1 1 RO-1,2 I/C 3,6 3,4,6 5 4 4 2 MAJ 8 8 2 2 2 1 TS 0 2 2 RX 1 1 0 NOR 1 1 1 I/C 4 4 2 MAJ 2 2 1 TS 0 2 2 Instructions:
- 1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.
- 2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis.
- 3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.
ES-301 Competencies Checklist Form ES-301-6 Facility: Fort Calhoun Date of Examination: 3/30/09 Revision No: 3 APPLICANTS USRO-1,2 ISRO-1,2 RO-1,2 Competencies SCENARIO SCENARIO SCENARIO SCENARIO 1 2 3 4 1 2 3 4 1 2 3 4 1 2 3 4 Position (A-ATCO, C B A C B A B-BOPO,C-CRS)
Interpret/Diagnose 3,5, 2,5, 3,5, 2,3, 6,8 3,4 6,7, 6,7, 7 4,5, Events and Conditions 8 8 6,8 Comply With and 3,4, 2,5, 2,3, 3,4, 3,4 1,3 6,7, 6,7, 4,5, 6,7, ,6, ,4, Use Procedures (1) 8 8 7 8 7 6,8 Operate Control 2,5, 2,4, 1,3 1,3 6,7, 5,8 ,4, ,4, Boards (2) 8 6,7 6,8 Communicate 3,4, 2,5, 3,4, 3,4, 1,3 1,3 6,7, 6,7, 5,7, 5,6, ,4, ,4, and Interact 8 8 8 7,8 6,8 6,8 Demonstrate 3,4, 3,4, 6,7, 5,6, Supervisory Ability (3) 8 7,8 Comply With and 3,6 3,4 Use Tech. Specs. (3)
Notes:
(1) Includes Technical Specification compliance for an RO.
(2) Optional for an SRO-U.
(3) Only applicable to SROs.
Instructions:
Check the applicants license type and enter one or more event numbers that will allow the examiners to evaluate every applicable competency for every applicant.
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-1 Rev 3 JPM
Title:
Calculate Shutdown Margin with inoperable CEAs Approximate Time: 20 minutes Actual Time: _________________
Reference(s): K/A 2.1.37 RO Importance 4.3 TDB-V.9, "SHUTDOWN MARGIN WORKSHEET" TDB-II, "REACTIVITY CURVES" Handout(s) TDB-V.9, "SHUTDOWN MARGIN WORKSHEET" Time Critical: NO Alternate Path: NO JPM Prepared by: Jerry Koske Date: 03/23/09 Page 1 of 5
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-1 Rev 3 JPM
Title:
Calculate Shutdown Margin with inoperable CEAs Operators Name: _____________________ Employee # ______________
All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):
SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________
Reason, if unsatisfactory:
Tools & Equipment: TDB, ruler. calculator Safety Considerations: None Comments:
Page 2 of 5
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-1 Rev 3 JPM
Title:
Calculate Shutdown Margin with inoperable CEAs TASK The candidate has calculated the shutdown margin in STANDARD: accordance with TDB-V.9 and determined that it is inadequate.
INITIAL The plant is operating at 60% power with group 4 CEAs CONDITIONS: at 110 inches withdrawn. Group A CEA #36 and Group 2 CEA #24 have been declared inoperable (untrippable).
The RCS boron concentration is 400 ppm. The burnup is 12000 MWD/MTU.
INITIATING CUE: You have been requested to perform an instantaneous shutdown margin calculation using TDB-V.9 to determine if technical specification requirement for shutdown margin is being met.
Page 3 of 5
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-1 Rev 3 JPM
Title:
Calculate Shutdown Margin with inoperable CEAs 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-V.9. Performs calculation using part procedure should be used. 1.
[ SAT ] [ UNSAT ]
4 Performs calculation of the Difference calculated on line difference between actual and 11 of TDB-V.9, section 1 is required shutdown margin. +0.7 [between +0.6, +0.8]
[ SAT ] [ UNSAT ]
5 Determines if SDM is Determines Shutdown Margin adequate. is inadequate
[ SAT ] [ UNSAT ]
Termination Criteria: Shutdown Margin determination has been made and TDB V.9, Part One has been filled out.
Page 4 of 5
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-1 Rev 3 INITIAL The plant is operating at 60% power with group 4 CEAs CONDITIONS: at 110 inches withdrawn. Group A CEA #36 and Group 2 CEA #24 have been declared inoperable (untrippable).
The RCS boron concentration is 400 ppm. The burnup is 12000 MWD/MTU INITIATING CUE: You have been requested to perform an instantaneous shutdown margin calculation using TDB-V.9 to determine if technical specification requirement for shutdown margin is being met.
Operator Name: _________________________________
Shutdown Margin adequate? (circle one) YES NO Page 5 of 5
PAGE 1 OF 16 Fort Calhoun Station Unit 1 TDB-V.9 TECHNICAL DATA BOOK SHUTDOWN MARGIN WORKSHEET Change No. EC 40685 Reason for Change Added new power defect figure to TDB-II; base percent power on 1500 MWth. Made editorial changes for consistency.
Requestor M. Rybenski Preparer D. Weis Issue Date 05-18-08 8:30 pm R39
FORT CALHOUN STATION TDB-V.9 TECHNICAL DATA BOOK PAGE 2 OF 16 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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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.
% TDB Figure used:
6 R39
FORT CALHOUN STATION TDB-V.9 TECHNICAL DATA BOOK PAGE 3 OF 16
- 7. Enter Shutdown Group Worths, based on burnup (Step 5) using TDB Figure II.B.1.a.
- a. Shutdown Group B %
- b. Shutdown Group A %
- c. Total Shutdown Worth
+ = %
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.a or Figure II.C.2.b.
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.
9.a R39
FORT CALHOUN STATION TDB-V.9 TECHNICAL DATA BOOK PAGE 4 OF 16 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.
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.
9.c(2)
- (# )X( %) = %
9.c(1) 9.c(2) 9.c R39
FORT CALHOUN STATION TDB-V.9 TECHNICAL DATA BOOK PAGE 5 OF 16 9
- d. Enter total available CEA worth from TDB Figure II.B.1.a. based on burnup (Step 5) 9.d
- e. Determine the maximum stuck CEA worth by selecting the minimum of either 9.c or 9.d and record that value.
9.e
- f. Enter value from 9.a or 9.b or 9.e as appropriate %
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.
( % ) + 3.6% = %
10 11 NOTE: A 3.6% shutdown margin must be maintained in a Hot Shutdown condition, Tc > 210 F (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, to determine the number of gallons of acid to add.
REMARKS Completed by Date/Time /
R39
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-2 Rev 3 JPM
Title:
Determine Pressurizer Level During Cooldown Approximate Time: 10 minutes Actual Time: _________________
Reference(s): K/A# 2.1.25 RO Importance 3.9 TDB-III.1.a, "TEMPERATURE CORRECTION FOR PRESSURIZER LEVEL INDICATORS LI-101X/Y".
TDB-III.2, "ACTUAL LEVEL IN PRESSURIZER VS. INDICATED LEVEL IN PRESSURIZER.
Handouts(s): None Time Critical: NO Alternate Path: NO JPM Prepared by: Jerry Koske Date: 03/24/09 Page 1 of 5
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-2 Rev 3 JPM
Title:
Determine Pressurizer Level During Cooldown Operators Name: _____________________ Employee # ______________
All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):
SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________
Reason, if unsatisfactory:
Tools & Equipment: TDB, Ruler, Steam Tables Safety Considerations:
Comments:
Page 2 of 5
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-2 Rev 3 JPM
Title:
Determine Pressurizer Level During Cooldown TASK The candidate has determined the actual pressurizer STANDARD level from LI-101Y using TDB-III.1.a and from LI-106 using TDB-III.2 and has recommended that the pressurizer heaters not be turned off.
INITIAL The RCS is being cooled down per OP-3A. RCS CONDITIONS pressure is at 250 psia.
A dummy level signal has been placed on pressurizer level channel LI-101X and it is selected as the controlling channel.
The pressurizer level indications are as follows:
o LI-101X = 48%
o LI-101Y = 50%
o LI-106 = 34%
INITIATING CUE: The CRS has directed you to determine actual pressurizer level using both LI-101Y and LI-106 and recommend if the pressurizer heaters need to be turned off?
Page 3 of 5
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-2 Rev 3 JPM
Title:
Determine Pressurizer Level During Cooldown Critical Steps shown in gray STEP ELEMENT STANDARD 1 Refers to TDB-III.1.a and Level based on LR-101Y is determines that the actual approximately 40% (39 - 40%)
pressurizer level based on LR-101Y. [ SAT ] [ UNSAT ]
2 Refers to TDB-III.2 and Level based on LI-106 is determines that the actual approximately 40% (39 - 41%)
pressurizer level based on LI-106. [ SAT ] [ UNSAT ]
3 Determines if heaters need to Determines that heaters do not be turned off. have to be turned off because actual level is above 32%
[ SAT ] [ UNSAT ]
Termination Criteria: Actual level has been determined both channels and a determination has been made on the need to turn off the heaters.
Page 4 of 5
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No:A-2 Rev 3 INITIAL The RCS is being cooled down per OP-3A. RCS CONDITIONS pressure is at 250 psia.
A dummy level signal has been placed on pressurizer level channel LI-101X and it is selected as the controlling channel.
The pressurizer level indications are as follows:
o LI-101X = 48%
o LI-101Y = 50%
o LI-106 = 34%
INITIATING CUE: The CRS has directed you to determine actual pressurizer level using both LI-101Y and LI-106 and recommend if the pressurizer heaters need to be turned off?
NAME: ________________________________________
Actual Level based on LR-101Y: ______________%
Actual Level based on LI-106: _______________%
Do Heaters Need to be turned off: YES NO Page 5 of 5
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-3 Rev 2 JPM
Title:
Determine equipment lost by tagout of an MCC.
Approximate Time: 20 minutes Actual Time: _________________
Reference(s): K/A# 2.2.15 RO Importance 3.9 P&ID Figure 8.1-1 (File 12234)
Handout(s) None Time Critical: NO Alternate Path: NO JPM Prepared by: Jerry Koske Date: 03/05/09 Page 1 of 8
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-3 Rev 2 JPM
Title:
Determine equipment lost by tagout of an MCC.
Operators Name: _____________________ Employee # ______________
All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):
SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________
Reason, if unsatisfactory:
Tools & Equipment: P&ID Books Safety Considerations:
Comments:
Page 2 of 8
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-3 Rev 2 JPM
Title:
Determine equipment lost by tagout of an MCC.
TASK The candidate has referred to plant electrical drawing STANDARD: Figure 8.1-1 (File 12234) and has listed the electrical loads powered from MCC-3B2. In addition, the candidate has provided a list of the breakers that would need to be ensured closed to supply power from bus 1B3C to FW-54 Fuel Oil Transfer Pump, FO-37.
INITIAL The plant is operating at full power.
CONDITIONS:
You are working in the Operations Control Center (OCC).
Maintenance is requesting that MCC-3B2 be taken out of service for some equipment repairs.
The OCC Supervisor is working on a change to procedure EOP-07, "STATION BLACKOUT" INITIATING CUE: The OCC Supervisor has directed you to determine what equipment would be affected by tagout of MCC-3B2.
The OCC Supervisor has directed you to list the breakers that you would need to ensure closed to be able to supply power to FW-54 Fuel Oil Transfer Pump, FO-37, if bus 1B3C were energized from 13.8 KV and FW-54's shaft driven generator, EE-54, failed.
Page 3 of 8
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-3 Rev 2 JPM
Title:
Determine equipment lost by tagout of an MCC.
Critical Steps shown in gray STEP ELEMENT STANDARD 1 Refers to P&ID to determine Note:
affected equipment. If candidate requests copy of the ELDL, "Electrical Load Distribution List",
Inform him that the ELDL is not available.
Uses P&ID Figure 8.1-1 (File 12234) to determine affected equipment.
[ SAT ] [ UNSAT ]
2 Provides list of affected List includes:
equipment. VD-7A AC-9A EHC-3A EE2G-1A VD-5A CF-4 CF-5 CF-7A VA-151C VA-158A,C,E,G,H,K,M LO-7 LO-6 LO-2 VA-766
[ SAT ] [ UNSAT ]
Page 4 of 8
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-3 Rev 2 JPM
Title:
Determine equipment lost by tagout of an MCC.
STEP ELEMENT STANDARD 3 Refers to P&ID to determine Uses P&ID Figure 8.1-1 (File breakers that must be ensured 12234) to determine breakers closed to supply power from that must be ensured closed.
bus 1B3C to FO-37.
[ SAT ] [ UNSAT ]
4 Provides list of breakers Breakers include:
BT-1B3C BT-1B4C 1B4C-1 EE-55 Feeder breaker on MCC-4C5 FO-37 Feeder Breaker on MCC-4C6 Note: he may also list Auto Transfer Switch, EE-55, position, but this is not required.
[ SAT ] [ UNSAT ]
Termination Criteria: List of affected equipment from MCC-3B2 has been provided and a list of breakers that must be ensured closed to power FO-37 from bus 1B3C has been provided.
Page 5 of 8
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-3 Rev 2 INITIAL The plant is operating at full power.
CONDITIONS:
You are working in the Operations Control Center (OCC).
Maintenance is requesting that MCC-3B2 be taken out of service for some equipment repairs.
The OCC Supervisor is working on a change to procedure EOP-07, "STATION BLACKOUT" INITIATING CUE: The OCC Supervisor has directed you to determine what equipment would be affected by tagout of MCC-3B2.
The OCC Supervisor has directed you to list the breakers that you would need to ensure closed to be able to supply power to FW-54 Fuel Oil Transfer Pump, FO-37, if bus 1B3C were energized from 13.8 KV and FW-54's shaft driven generator, EE-54, failed.
Page 6 of 8
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-3 Rev 2 Operator Name:_______________________________________
Equipment affected by tagout of MCC-3B2:
Page 7 of 8
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-3 Rev 2 Operator Name:_______________________________________
Breakers that must be ensured closed to power FO-37 from bus 1B3C:
Page 8 of 8
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-4 Rev 2 JPM
Title:
RCA Entry and Exit with PCM Alarms Approximate Time: 12 minutes Actual Time: _________________
Reference(s): K/A# 2.3.7 RO Importance 3.5 GET-Radiation Worker Training.
Standing Order G-101, "RADIATION WORKER PRACTICES."
Handouts: None Time Critical: NO Alternate Path: NO JPM Prepared by: Jerry Koske Date: 03/05/09 Page 1 of 8
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-4 Rev 2 JPM
Title:
RCA Entry and Exit with PCM Alarms Operators Name: _____________________ Employee # ______________
All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):
SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________
Reason, if unsatisfactory:
Tools & Equipment: EAD, TLD, PCM-1, G-M with pancake probe Safety Considerations:
Comments: Can be conducted in GET trailer or during actual RCA Entry Page 2 of 8
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-4 Rev 2 JPM
Title:
RCA Entry and Exit with PCM Alarms TASK The candidate has entered and started to exit the STANDARD: Radiation Control Area (RCA). After receiving an alarm on the first PCM-1 that was used to monitor for contamination, he used a different PCM-1 to monitor again for contamination. After receiving the second alarm, he contacted Radiation Protection and frisked himself using a pancake probe, as directed. After determining that he was not contaminated, he exited the RCA.
INITIAL The plant is operating at full power. Charging Pump, CONDITIONS: CH-1A is running but its motor current is higher than expected. The CRS is planning to place CH-1B in service and shutdown CH-1A.
INITIATING CUE: The CRS has directed you to enter the RCA and place the Packing Cooling Pump for CH-1B in service. After starting the pump, you are to return to the Control Room.
Page 3 of 8
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-4 Rev 2 JPM
Title:
RCA Entry and Exit with PCM Alarms Critical Steps shown in gray STEP ELEMENT STANDARD 1 Review the RWP. Reads RWP.
[ SAT ] [ UNSAT ]
2 Determine Radiological Checks survey maps or Conditions. discusses radiological conditions with RP personnel.
[ SAT ] [ UNSAT ]
3 Obtains Dosimetry. Obtain TLD and EAD.
[ SAT ] [ UNSAT ]
4 Sign on to appropriate RWP. Insert EAD in reader. Scan PID and RWP number.
[ SAT ] [ UNSAT ]
[ SAT ] [ UNSAT ]
6 CUE: The Packing Cooling Pump for CH-1B has been started , exit the RCA.
NOTE: Do not actually enter room 6 for ALARA reasons.
7 Exits RCA. Returns to RCA access point.
[ SAT ] [ UNSAT ]
Page 4 of 8
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-4 Rev 2 JPM
Title:
RCA Entry and Exit with PCM Alarms STEP ELEMENT STANDARD 8 Monitor for personnel Monitor for contamination contamination prior to exiting using PCM-1.
RCA.
[ SAT ] [ UNSAT ]
CUE: After examinee has completed counting on a PCM-1, tell him to assume that the PCM-1 alarmed-zone 6.
9 Monitor for contamination a Monitor for contamination second time. again using a different PCM-1.
[ SAT ] [ UNSAT ]
CUE: After examinee has completed counting on another PCM-1, tell him to assume that this PCM-1 also alarmed- zone 6.
[ SAT ] [ UNSAT ]
CUE: RP directs you to monitor for contamination using frisker.
11 Uses Frisker to monitor for Slowly moves pancake probe contamination. over hands, shoes and body surface.
CUE: Frisker cpm as read.
[ SAT ] [ UNSAT ]
Page 5 of 8
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-4 Rev 2 JPM
Title:
RCA Entry and Exit with PCM Alarms Termination Criteria: RCA has been exited.
Page 6 of 8
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-4 Rev 2 JPM
Title:
RCA Entry and Exit with PCM Alarms NOTE to RP Tech As a part of this candidates NRC license exam, he must enter and exit the RCA.
During RCA exit, he has been given verbal Cues that he has received a zone 6 alarm on two separate PCM-1 monitors.
As a part of this JPM, we would like you to direct him to perform a whole body frisk on himself.
Page 7 of 8
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-4 Rev 2 INITIAL The plant is operating at full power. Charging Pump, CONDITIONS: CH-1A is running but its motor current is higher than expected. The CRS is planning to place CH-1B in service and shutdown CH-1A.
INITIATING CUE: The CRS has directed you to enter the RCA and place the Packing Cooling Pump for CH-1B in service. After starting the pump, you are to return to the Control Room.
Page 8 of 8
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-5 Rev 3 JPM
Title:
Review Shutdown Margin Calculation with inoperable CEAs Approximate Time: 25 minutes Actual Time: _________________
Reference(s): K/A 2.1.37 SRO Importance 4.6 TDB-V.9, "SHUTDOWN MARGIN WORKSHEET" TDB-II, "REACTIVITY CURVES" Handout(s): Completed TDB-V.9 Time Critical: NO Alternate Path: NO JPM Prepared by: Jerry Koske Date: 03/23/09
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-5 Rev 3 Operators Name: _____________________ Employee # ______________
All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):
SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________
Reason, if unsatisfactory:
Tools & Equipment: TDB, ruler, calculator Safety Considerations:
Comments:
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-5 Rev 3 TASK The candidate reviewed the Shutdown Margin STANDARD: calculation that was prepared by the STA and found 2 errors in the calculation, corrected the errors and determined that the Shutdown Margin is inadequate.
INITIAL The plant is operating at 60% power with group 4 CONDITIONS: CEAs at 110 inches withdrawn. Group A CEA #36 and Group 2 CEA #24 have been declared inoperable (untrippable).
The RCS boron concentration is 400 ppm. The burnup is 12000 MWD/MTU.
INITIATING CUE: The STA has performed a shutdown margin calculation and determined that Shutdown Margin is adequate. The Shift Manager has directed you to review the shutdown margin calculation and, if there are any mistakes, correct them.
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-5 Rev 3 Critical Steps shown in gray STEP ELEMENT STANDARD Note to Examiner:
Provide Shutdown Margin Calculation to candidate with initiating cue.
1 Reviews shutdown margin Determines that there was an calculation. error in step 7.a due to reading the value from the wrong row.
5.238 (Shutdown Group A+B worth was entered instead of shutdown group B worth).
[ SAT ] [ UNSAT ]
2 Determines that in step 8, the 100% power defect was used instead of the 60% power defect.
[ SAT ] [ UNSAT ]
3 Performs calculation of the Difference calculated on line difference between actual and 11 of TDB-V.9, section 1 is required shutdown margin +0.7 [between +0.6, +0.8].
using corrected values.
[ SAT ] [ UNSAT ]
4 Determines if SDM is Determines Shutdown Margin adequate. is inadequate.
[ SAT ] [ UNSAT ]
Termination Criteria: The SRO has determined that shutdown margin is not adequate and has corrected the SDM calculation.
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-5 Rev 3 INITIAL The plant is operating at 60% power with group 4 CONDITIONS: CEAs at 110 inches withdrawn. Group A CEA #36 and Group 2 CEA #24 have been declared inoperable (untrippable).
The RCS boron concentration is 400 ppm. The burnup is 12000 MWD/MTU.
INITIATING CUE: The STA has performed a shutdown margin calculation and determined that Shutdown Margin is adequate. The Shift Manager has directed you to review the shutdown margin calculation and, if there are any mistakes, correct them.
Operator Name: _________________________________
Shutdown Margin adequate? (circle one) YES NO
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-6 Rev 3 JPM
Title:
Determine Shift Staffing Approximate Time: 15 minutes Actual Time: _________________
Reference(s): K/A# 2.1.5 SRO Importance 3.9 Technical Specifications Table 5.2-1 SO-O-1, "CONDUCT OF OPERATIONS" SO-G-52, "PLANT STAFF WORKING HOURS" SO-G-28, "STATION FIRE PLAN" Handout(s): None Time Critical: NO Alternate Path: NO JPM Prepared by: Jerry Koske Date: 03/23/09 Page 1 of 6
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-6 Rev 3 JPM
Title:
Determine Shift Staffing Operators Name: _____________________ Employee # ______________
All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):
SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________
Reason, if unsatisfactory:
Tools & Equipment: None Safety Considerations:
Comments:
Page 2 of 6
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-6 Rev 3 JPM
Title:
Determine Shift Staffing TASK The candidate has reviewed the staffing suggestions STANDARD: made by his STA and his AON and has determined that either a qualified STA or a qualified CRS must be called in and be in position within two hours. He has also determined that the AON cannot also serve as Control Room Communicator due to Fire Brigade manning requirements.
INITIAL The plant is operating at full power.
CONDITIONS:
You are the Shift Manager. Your crew consists of:
o you o a CRS o a STA (who is also CRS qualified) o two RO's o an EONA, o an EONT, o an AON (who is also Communicator qualified) o a Control Room Communicator.
Half way through your shift, your CRS and your Control Room Communicator became sick and needed to go home.
INITIATING CUE: Your STA suggests that he can serve as both CRS and STA for the remainder of the shift since he is qualified for both positions.
Your AON suggests that he can serve as both AON and Control Room Communicator for the remainder of the shift since he is qualified for both positions.
Determine if each of these suggestions is acceptable. If not, specify what actions must be taken and when they must be taken.
Page 3 of 6
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-6 Rev 3 JPM
Title:
Determine Shift Staffing Critical Steps shown in gray STEP ELEMENT STANDARD 1 Determine if the STA may fill Refers to Technical both the CRS and the STA Specifications Table 5.2-1 and position for the remainder of Standing Order SO-O-1.
the shift.
Determines that 2 SROs and an STA are required and this suggestion is not acceptable.
[ SAT ] [ UNSAT ]
2 Determine if the AON may fill Refers to Technical both the AON and the Control Specifications Table 5.2-1 and Room Communicator position Standing Order SO-G-28.
for the remainder of the shift.
Determines that an AON, an EONT and a communicator are required for the Fire Brigade.
[ SAT ] [ UNSAT ]
3 Determine what actions must Determines that the CRS must be taken and when these turnover to the CRS qualified actions must be taken. STA and that immediate action must be taken to call in another qualified STA or another qualified CRS and another plant Operator or Communicator and the called in Operators must be in position within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
[ SAT ] [ UNSAT ]
Page 4 of 6
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-6 Rev 3 JPM
Title:
Determine Shift Staffing Termination Criteria: Candidate has determined shift staffing requirements, actions that must be taken and required time frame for these actions.
Page 5 of 6
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-6 Rev 3 INITIAL The plant is operating at full power.
CONDITIONS:
You are the Shift Manager. Your crew consists of:
o you o a CRS o a STA (who is also CRS qualified) o two RO's o an EONA, o an EONT, o an AON (who is also Communicator qualified) o a Control Room Communicator.
Half way through your shift, your CRS and your Control Room Communicator became sick and needed to go home.
INITIATING CUE: Your STA suggests that he can serve as both CRS and STA for the remainder of the shift since he is qualified for both positions.
Your AON suggests that he can serve as both AON and Control Room Communicator for the remainder of the shift since he is qualified for both positions.
Determine if each of these suggestions is acceptable. If not, specify what actions must be taken and when they must be taken.
NAME:_____________________________________________
Can the STA serve as both CRS and STA? YES NO Can the AON serve as both AON and Control Room Communicator YES NO What action, if any, must be taken? When must it be taken?
Page 6 of 6
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-7 Rev 1 JPM
Title:
Determine RW System Operability Approximate Time: 12 minutes Actual Time: _________________
Reference(s): K/A# 2.2.22 SRO Importance 4.7 TDB VIII, "EQUIPMENT OPERABILITY GUIDANCE" Technical Specification 2.4 Technical Specification 2.0.1 Handout(s): None Time Critical: NO Alternate Path: NO JPM Prepared by: Jerry Koske Date: 02/20/09 Page 1 of 5
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-7 Rev 1 JPM
Title:
Determine RW System Operability Operators Name: _____________________ Employee # ______________
All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):
SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________
Reason, if unsatisfactory:
Tools & Equipment: None Safety Considerations:
Comments:
Page 2 of 5
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-7 Rev 1 JPM
Title:
Determine RW System Operability TASK The candidate has reviewed TDB-VIII and Technical STANDARD: Specifications and has determined that the action statement for Technical Specification 2.0.1 applies. The plant must be in hot shutdown within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
INITIAL The plant is operating at full power.
CONDITIONS:
It has been determined that RW/CCW Backup Header Isolation Valves, HCV-2893 and HCV-2894, are both inoperable. They are both closed and cannot be opened.
INITIATING CUE: Determine the applicable Technical Specification and required actions, if any, to be taken.
Page 3 of 5
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-7 Rev 1 JPM
Title:
Determine RW System Operability Critical Steps shown in gray STEP ELEMENT STANDARD 1 Refers to TDB-VIII. Enters TDB-VIII.
[ SAT ] [ UNSAT ]
2 Refers to Table 2-1 to Determines that T.S. 2.0.1 determine applicable LCO. applies with these conditions.
[ SAT ] [ UNSAT ]
3 Determines Tech Spec. 2.0.1 Plant must be in Hot Shutdown required Action Statement. within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
[ SAT ] [ UNSAT ]
Termination Criteria: Technical Specification 2.0.1 has been entered.
Page 4 of 5
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-7 Rev 1 INITIAL The plant is operating at full power.
CONDITIONS:
It has been determined that RW/CCW Backup Header Isolation Valves, HCV-2893 and HCV-2894, are both inoperable. They are both closed and cannot be opened.
INITIATING CUE: Determine the applicable Technical Specification and required actions, if any, to be taken.
Name: ________________________________________
Technical Specification Entered, if any:
Required Action, if any:
Page 5 of 5
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-8 Rev 3 JPM
Title:
Authorize Release of Monitor Tank WD-22B Approximate Time: 10 minutes Actual Time: _________________
Reference(s): K/A# 2.3.6 SRO Importance 3.8 OI-WDL-3, "LIQUID WASTE DISPOSAL RELEASE" FC-211, "WASTE LIQUID TANK RELEASE PERMIT" Handout(s): Partially filled out OI-WDL-3 Approved FC-211 Time Critical: NO Alternate Path: NO JPM Prepared by: Jerry Koske Date: 03/23/09 Page 1 of 5
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-8 Rev 3 JPM
Title:
Authorize Release of Monitor Tank WD-22B Operators Name: _____________________ Employee # ______________
All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):
SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________
Reason, if unsatisfactory:
Tools & Equipment: Calculator Safety Considerations:
Comments:
Page 2 of 5
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-8 Rev 3 JPM
Title:
Authorize Release of Monitor Tank WD-22B TASK The SRO candidate reviewed OI-WDL-3 and the FC-211 STANDARD: release permit and determined that the EONA used the wrong maximum release rate when filling out OI-WDL-3 and that the chemist specified the wrong flow rate in the release permit, section VII. Special Instructions. The release was not authorized as written.
INITIAL The plant is operating at full power.
CONDITIONS: Three Circulating Water Pumps are running.
Two Raw Water Pumps are operating.
All Radiation Monitors are operable.
A release of Monitor Tank, WD-22B is planned.
INITIATING CUE: You are the Shift Manager. The EONA has given you a copy of OI-WDL-3 and a Release Permit for the release of WD-22B. Review the permit and, if acceptable, authorize the release. If not acceptable, make any required corrections.
Page 3 of 5
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-8 Rev 3 JPM
Title:
Authorize Release of Monitor Tank WD-22B Critical Steps shown in gray STEP ELEMENT STANDARD 1 Reviews partially filled out OI- Examines procedure and WDL-3 and associated FC-211 Release Permit.
Release Permit.
[ SAT ] [ UNSAT ]
2 Determines that the maximum Maximum release rate should release rate and administrative be 84.6 gpm. Administrative release rate recorded on the release rate should be 76.1 procedure do not agree with gpm.
the Release Permit.
[ SAT ] [ UNSAT ]
3 Determines that the Chemist Unloader should be set to has used the wrong flow rate allow a flow rate of 76.1 gpm.
on the FC-211 release rate, section VII. Special Instructions, item B. [ SAT ] [ UNSAT ]
4 Release Authorization. Does not authorize release as written.
Corrects maximum (84.6 gpm) and administrative (76.1 gpm) release rates.
[ SAT ] [ UNSAT ]
Termination Criteria: Candidate has reviewed the procedure and release permit and has refused to authorize the release as written.
Page 4 of 5
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-8 Rev 3 INITIAL The plant is operating at full power.
CONDITIONS: Three Circulating Water Pumps are running.
Two Raw Water Pumps are operating.
All Radiation Monitors are operable.
A release of Monitor Tank, WD-22B is planned.
INITIATING CUE: You are the Shift Manager. The EONA has given you a copy of OI-WDL-3 and a Release Permit for the release of WD-22B. Review the permit and, if acceptable, authorize the release. If not acceptable, make any required corrections.
Page 5 of 5
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-9 Rev 4 JPM
Title:
Emergency Classification and PARs Approximate Time: 20 minutes Actual Time: _________________
Reference(s): K/A# 2.4.41 SRO Importance 4.6 K/A# 2.4.44 SRO Importance 4.4 EPIP-OSC-1, "EMERGENCY CLASSIFICATION" EPIP-EOF-7, "PROTECTIVE ACTION GUIDELINES TDB-IV.8, "AREA MONITORING SETPOINTS" EAGLE 6.0.0 Users Manual Handouts(s): FC-1188 EAGLE OUTPUT Time Critical: YES (Cue# 2)
Alternate Path: NO JPM Prepared by: Jerry Koske Date: 3/25/09 Page 1 of 7
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-9 Rev 4 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: SRO , Time Critical - 15 minutes after determining EAL Page 2 of 7
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-9 Rev 4 JPM
Title:
Emergency Classification and PARs TASK The SRO candidate reviewed the plant conditions, STANDARD: referred to EPIP-OSC-1 and TDB-IV.8 and classified the event as a SITE AREA EMERGENCY, EAL 7.3.
Within 15 minutes of classifying the event, the candidate used the EAL and the data from the EAGLE output to determine there are no Protective Action Recommendations and completed page one of form FC-1188 so that offsite notifications can be made.
INITIAL A refueling outage is in progress.
CONDITIONS: Spent fuel assemblies were being moved using FH-12 when a fuel assembly fell from FH-12 and landed on a spent fuel rack.
High radiation alarms were received on RM-085 and RM-087.
RM-085 is reading 1200 mrem/hr.
RM-087 is reading 1100 mrem/hr.
Radiation levels on RM-052 and RM-062 are also rising.
There is no precipitation.
Your Shift HP is running EAGLE INITIATING CUE: You are the Shift Manager. Determine the appropriate EAL, if any, in accordance with EPIP-OSC-1.
CUE #2: ***** TIME CRITICAL*****
Your Shift HP has run EAGLE and has provided you with the output. You are directed to complete page 1 of form FC-1188 so your Communicator can make the required notifications.
Page 3 of 7
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-9 Rev 4 JPM
Title:
Emergency Classification and PARs Critical Steps shown in gray STEP ELEMENT STANDARD Examiner Note:
Provide only the initiating cue to the candidate at this time.
1 Refer to Emergency Plan. Refer to EPIP-OSC-1.
[ SAT ] [ UNSAT ]
2 Classify the event. This Event should be classified as a SITE AREA EMERGENCY, EAL 7.3, "MAJOR IRRADIATED FUEL ACCIDENT" RM-087 is reading more than 1000 times its normal refueling shutdown value per TDB-IV.8
[ SAT ] [ UNSAT ]
Examiner Note: Provide cue#2, EAGLE output and Blank FC-1188 form to candidate. Note the time Start Time:______________
Page 4 of 7
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-9 Rev 4 JPM
Title:
Emergency Classification and PARs STEP ELEMENT STANDARD 3 Determine Protective Action ***** TIME CRITICAL *****
Recommendations and fill out Form FC-1188 must be filled form FC-1188 for notifications. out within 15 minutes and must contain the following information:
Initial Declaration Site Area EAL 7.3 Wind from 122° Wind Speed10 MPH No Precipitation Temperature difference 1°C/100m Stability Class "E" There is an airborne release There are no PARs Plant Status: shutdown Approval Signature, date and time.
End Time:____________
Elapsed Time:__________
[ SAT ] [ UNSAT ]
Termination Criteria: PARS have been determined and FC-1188 has been filled out within 15 minutes of classifying the event.
Page 5 of 7
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No:A-9 Rev 4 INITIAL A refueling outage is in progress.
CONDITIONS: Spent fuel assemblies were being moved using FH-12 when a fuel assembly fell from FH-12 and landed on a spent fuel rack.
High radiation alarms were received on RM-085 and RM-087.
RM-085 is reading 1200 mrem/hr.
RM-087 is reading 1100 mrem/hr.
Radiation levels on RM-052 and RM-062 are also rising.
There is no precipitation.
Your Shift HP is running EAGLE INITIATING CUE: You are the Shift Manager. Determine the appropriate EAL, if any, in accordance with EPIP-OSC-1.
Name:_________________________________________________
Event Classification (circle one)
NONE Notice of Unusual Event Alert Site Area Emergency General Emergency EAL# ___________________
Page 6 of 7
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No:A-9 Rev 4 CUE #2: ***** TIME CRITICAL*****
Your Shift HP has run EAGLE and has provided you with the output. You are directed to complete page 1 of form FC-1188 so your Communicator can make the required notifications.
Page 7 of 7
FORT CALHOUN STATION FC-1188 GENERAL FORM R22 PAGE 1 OF 2 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:
OBTAIN METEOROLOGICAL DATA FROM ERF PAGE 197 (see Note 1 on page 2, if ERFCS is unavailable)
- 2. Wind From Weather Wind Speed MPH (Use Precipitation: [ ] Yes [ ] No Degrees (10m): Slowest 10m):
Temperature Difference °C/100m (use most positive T)
Stability Class -[ ] A [ ]B [ ]C [ ]D [ ]E [ ]F [ ] G+
-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 environment
[ ] was [ ] an airborne that is the result of or associated with this event
[ ] will be [ ] a liquid REVIEW EPIP-EOF-7 FOR GUIDANCE ON PARS
- 4. Protective Action Recommendations (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 R22 PAGE 2 OF 2 Notify the following agencies: (refer to Emergency Phone Book for alternate phone numbers) 3 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 NOTE 1: If on-site meteorological data is not available, contact the National Weather Service (number in the Emergency Phone Book), and request wind speed and direction. For night time (sunset to sunrise) with no precipitation, use a T of +2.0 and a stability class F. For all other conditions, use a T of -1.0 and a stability class D.
FORT CALHOUN STATION FC-1188 GENERAL FORM KEY R22 PAGE 1 OF 2 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. [ X] 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 [X ] Site Area [ ] General EAL #: 7.3 Time Event Declared: Time Event Terminated:
OBTAIN METEOROLOGICAL DATA FROM ERF PAGE 197 (see Note 1 on page 2, if ERFCS is unavailable)
- 2. Wind From Weather Wind Speed MPH (Use Precipitation: [ ] Yes [X] No Degrees (10m): 122 Slowest 10m): 10 Temperature Difference °C/100m (use most positive T)
Stability Class -[ ] A [ ]B [ ]C [ ]D [X ] E [ ]F [ ] G+
-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 [X ] is [ ] no release of radioactive effluent to the environment
[ ] was [X] an airborne that is the result of or associated with this event
[ ] will be [ ] a liquid REVIEW EPIP-EOF-7 FOR GUIDANCE ON PARS
- 4. Protective Action Recommendations (PARs)
None Evacuate Sectors Shelter Sectors 0-2 Miles X 2-5 Miles X 5-10 Miles X
- 5. Prognosis: [X ] Stable [ ] Unstable Plant Status: [ ] at Power [X ] Shutdown
- 6. Remarks Approved: Date: Time:
FORT CALHOUN STATION FC-1188 GENERAL FORM R22 PAGE 2 OF 2 Notify the following agencies: (refer to Emergency Phone Book for alternate phone numbers) 3 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 NOTE 1: If on-site meteorological data is not available, contact the National Weather Service (number in the Emergency Phone Book), and request wind speed and direction. For night time (sunset to sunrise) with no precipitation, use a T of +2.0 and a stability class F. For all other conditions, use a T of -1.0 and a stability class D.
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-1 Rev 3 JPM
Title:
Provide Raw Water Backup Cooling to Containment Coolers Location: Auxiliary Building (RCA) and Room 81 Approximate Time: 30 minutes Actual Time: _________________
Reference(s): K/A 022000 A2.05 AOP-11, "LOSS OF COMPONENT COOLING WATER" OI-AOV-1, "AIR OPERATED VALVE MANUAL OPERATION" Handout(s): AOP-11, "LOSS OF COMPONENT COOLING WATER", Step 12.
OI-AOV-1, "AIR OPERATED VALVE MANUAL OPERATION" Time Critical: NO Alternate Path: NO JPM Prepared by: Jerry Koske Date: 3/23/09 Page 1 of 8
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-1 Rev 3 JPM
Title:
Provide Raw Water Backup Cooling to Containment Coolers Operators Name: _____________________ Employee # ______________
All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):
SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________
Reason, if unsatisfactory:
Tools & Equipment: None Safety Considerations: This JPM requires entry into the RCA.
Climbing of a ladder may be required.
Comments:
Page 2 of 8
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-1 Rev 3 JPM
Title:
Provide Raw Water Backup Cooling to Containment Coolers TASK The Candidate placed Raw Water Backup cooling in STANDARD: service for Containment Cooling Coil, VA-1A and Shutdown Cooling Heat Exchanger, AC-4B in accordance with AOP-11.
INITIAL A LOCA occurred 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> ago.
CONDITIONS: EOP-AOP Attachment 8, "COOLED SI FLOW WITH RAS" has been implemented.
15 minutes ago, a total loss of CCW occurred.
The CRS is implementing AOP-11.
Containment temperature is 120°F.
The river level is 990 feet.
INITIATING CUE: The CRS has directed you to establish Raw Water Backup to Containment Cooling Coil, VA-1A, per AOP-11 step 12.c. and OI-AOV-1.
CUE #2: The CRS has directed you to establish Raw Water Backup to Shutdown Cooling Heat Exchanger, AC-4B, per AOP-11 step 12.h.
Page 3 of 8
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-1 Rev 3 JPM
Title:
Provide Raw Water Backup Cooling to Containment Coolers Critical Steps shown in gray STEP ELEMENT STANDARD 1 Obtain copies of AOP-11 and Cue: Provide copies of AOP-OI-AOV-1. 11, step 12 and OI-AOV-1.
[ SAT ] [ UNSAT ]
2 Place CNTMT CLG COIL CUE: Control Room VA-1A AC VLVS CONTROL Operator reports that HCV-SW HCV-400B/D in CLOSE. 400B/D is in CLOSE.
[ SAT ] [ UNSAT ]
3 Unlock and release the Room-69 hand-jacks from BOTH of the Remove the locking following RW Interface mechanisms and covers from Valves: BOTH HCV-400E and HCV-HCV-400E, CNTMT 400F. Use the ratchet to VA-1A COOLING COIL release the handjacks by RAW WATER INLET turning the locking nut VALVE. CLOCKWISE until it reaches HCV-400F, CNTMT the bottom.
VA-1A COOLING COIL BACK-UP RAW WATER [ SAT ] [ UNSAT ]
OUTLET VALVE.
CUE: Another Operator will make the entry in the Locked Components Log.
4 Locally open both VA-1A RW Room-69 Interface Valves, HCV-400E/F IA-HCV-400E-TV 4-way by placing the following valves manual control valve in OPEN.
to OPEN:
IA-HCV-400E-TV, 4- IA-HCV-400F-TV 4-way WAY MANUAL manual control valve in OPEN.
CONTROL VALVE.
IA-HCV-400F-TV, 4-WAY MANUAL CONTROL VALVE. [ SAT ] [ UNSAT ]
Page 4 of 8
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-1 Rev 3 JPM
Title:
Provide Raw Water Backup Cooling to Containment Coolers STEP ELEMENT STANDARD Note to Examiner: Provide Cue #2 to Candidate.
5 Close Both AC-4B CCW CUE: The Control Room Isolation Valves: Operator reports that HCV-HCV-481 481 and HCV-485 are closed.
HCV-485 6 Unlock and release the Corridor 4 hand-jacks from BOTH of the following RW Interface Unlock and release the hand-Valves (Corridor 4): jacks from both:
HCV-483A, HCV-483A SHUTDOWN HCV-483B COOLING HT EXCH AC-4B BACK-UP RAW WATER INLET VALVE HCV-483B, [ SAT ] [ UNSAT ]
SHUTDOWN COOLING HT EXCH AC-4B BACK-UP RAW WATER OUTLET VALVE 7 Locally open both AC-4B RW Corridor 4 Interface Valves,HCV-483A/B, by placing the following valves IA-HCV-483A-TV 3-way to OPEN: manual control valve in OPEN.
IA-HCV-483A-TV, 3-WAY MANUAL IA-HCV-483B-TV 3-way CONTROL VALVE manual control valve in OPEN.
IA-HCV-483B-TV, 3-WAY MANUAL CONTROL VALVE [ SAT ] [ UNSAT ]
Page 5 of 8
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-1 Rev 3 JPM
Title:
Provide Raw Water Backup Cooling to Containment Coolers Termination Criteria: Raw Water Backup Cooling is being provided to VA-1A and AC-4B.
Page 6 of 8
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-1 Rev 3 INITIAL A LOCA occurred 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> ago.
CONDITIONS: EOP-AOP Attachment 8, "COOLED SI FLOW WITH RAS" has been implemented.
15 minutes ago, a total loss of CCW occurred.
The CRS is implementing AOP-11.
Containment temperature is 120°F.
The river level is 990 feet.
INITIATING CUE: The CRS has directed you to establish Raw Water Backup to Containment Cooling Coil, VA-1A, per AOP-11 step 12.c. and OI-AOV-1.
Page 7 of 8
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-1 Rev 3 CUE #2: The CRS has directed you to establish Raw Water Backup to Shutdown Cooling Heat Exchanger, AC-4B, per AOP-11 step 12.h.
Page 8 of 8
AOP-11 Page 20 of 49 INSTRUCTIONS CONTINGENCY ACTIONS
- a. IF SIAS/CIAS has occurred, THEN ensure ALL of the following switches are in OVRRD:
- HC-400/403, CNTMT CLR AC VLVS CIAS OVERRIDE SWITCH
- b. Ensure BOTH RW/CCW Backup Header Isolation Valves are open:
- HCV-2893
- HCV-2894 (continue)
R14
AOP-11 Page 21 of 49 INSTRUCTIONS CONTINGENCY ACTIONS
- 12. (continued)
NOTE The RW Interface Valves are locally opened and closed using a local IA Supply Valve.
Positions on the local valve correspond to the position of the RW Interface Valve.
CAUTIONS
- 1. To prevent Raw Water Pump damage, maintain flowrates between 1700 and 8500 gpm per pump.
- 2. Backup cooling should not be used on Containment Cooling Coils with river level less than 983.5 ft or Containment temperatures greater than 150°F.
Flashing and potential water hammer in the Containment Coils may be present with Raw Water aligned under low river conditions (<983.5 ft) and at higher temperatures.
- 3. To prevent seal degradation, it is desirable to align RW to operating HPSI, LPSI and CS Pumps. During Shutdown Cooling operations, it should be aligned within one hour. However, after a RAS, a loss of cooling water can be tolerated with no loss of pump performance.
- c. IF VA-3A, Containment Vent Fan, is in service, THEN establish RW Flow to VA-1A by performing the following steps:
(continue)
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AOP-11 Page 22 of 49 INSTRUCTIONS CONTINGENCY ACTIONS 12.c. (continued)
- 2) Unlock and release the hand-jacks from BOTH of the following RW Interface Valves (Room 69):
- HCV-400E, CNTMT VA-1A COOLING COIL RAW WATER INLET VALVE
- HCV-400F, CNTMT VA-1A COOLING COIL BACK-UP RAW WATER OUTLET VALVE
- 3) Locally open both VA-1A RW Interface Valves, HCV-400E/F by placing the following valves to OPEN (Room 69):
- IA-HCV-400E-TV, 4-WAY MANUAL CONTROL VALVE
- IA-HCV-400F-TV, 4-WAY MANUAL CONTROL VALVE (continue)
R14
AOP-11 Page 23 of 49 INSTRUCTIONS CONTINGENCY ACTIONS
- 12. (continued)
- d. IF VA-3B, Containment Vent Fan, is in service, THEN establish RW Flow to VA-1B by performing the following steps:
- 2) Unlock and release the hand-jacks from BOTH of the following RW Interface Valves (Room 69):
- HCV-401E, CNTMT VA-1B COOLING COIL BACK-UP RAW WATER INLET VALVE
- HCV-401F, CNTMT VA-1B COOLING COIL BACK-UP RAW WATER OUTLET VALVE (continue)
R14
AOP-11 Page 24 of 49 INSTRUCTIONS CONTINGENCY ACTIONS 12.d (continued)
- 3) Locally open both VA-1B RW Interface Valves, HCV-401E/F by placing the following valves in OPEN (Room 69):
- IA-HCV-401E-TV, 4-WAY MANUAL CONTROL VALVE
- IA-HCV-401F-TV, 4-WAY MANUAL CONTROL VALVE
- e. IF VA-7C, Containment Vent Fan, is in service, THEN establish RW Flow to VA-8A by performing the following steps:
(continue)
R14
AOP-11 Page 25 of 49 INSTRUCTIONS CONTINGENCY ACTIONS 12.e (continued)
- 2) Unlock and release the hand-jacks from BOTH of the following RW Interface Valves (Room 69):
- HCV-402E, CNTMT VA-8A COOLING COIL BACK-UP RAW WATER INLET VALVE
- HCV-402F, CNTMT VA-8A COOLING COIL BACK-UP RAW WATER OUTLET VALVE
- 3) Locally open both VA-8A RW Interface Valves, HCV-402E/F by placing the following valves to OPEN (Room 69):
- IA-HCV-402E-TV, 4-WAY MANUAL CONTROL VALVE
- IA-HCV-402F-TV, 4-WAY MANUAL CONTROL VALVE (continue)
R14
AOP-11 Page 26 of 49 INSTRUCTIONS CONTINGENCY ACTIONS
- 12. (continued)
- f. IF VA-7D, Containment Vent Fan, is in service, THEN establish RW Flow to VA-8B by performing the following steps:
- 2) Unlock and release the hand-jacks from BOTH of the following RW Interface Valves (Room 69):
FILTERING ISOLATION VALVE
- HCV-403F, CNTMT VA-8B COOLING COIL BACK-UP RAW WATER OUTLET VALVE (continue)
R14
AOP-11 Page 27 of 49 INSTRUCTIONS CONTINGENCY ACTIONS 12.f (continued)
- 3) Locally open both VA-8B RW Interface Valves, HCV-403E/F by placing the following valves to OPEN (Room 69):
- IA-HCV-403E-TV, 4-WAY MANUAL CONTROL VALVE
- IA-HCV-403F-TV, 4-WAY MANUAL CONTROL VALVE
- g. IF AC-4A, SDC HX, is in service, THEN establish RW flow to AC-4A by performing the following steps:
- 1) Close BOTH AC-4A CCW Isolation Valves:
- HCV-480
- HCV-484 (continue)
R14
AOP-11 Page 28 of 49 INSTRUCTIONS CONTINGENCY ACTIONS 12.g (continued)
NOTE The operator may need assistance during performance of the next step as the handwheel may be difficult to reach. Climbing on wall-mounted accumulators to reach the handwheel should be avoided.
- 2) Unlock and release the hand-jacks from BOTH of the following SDC HX RW Interface Valves (Corridor 4):
- HCV-482A, SHUTDOWN COOLING HT EXCH AC-4A BACK-UP RAW WATER INLET VALVE
- HCV-482B, SHUTDOWN COOLING HT EXCH AC-4A BACK-UP RAW WATER OUTLET VALVE
- 3) Locally open both AC-4A RW Interface Valves by placing the following valves to OPEN (Corridor 4):
- IA-HCV-482A-TV, 3-WAY MANUAL CONTROL VALVE
- IA-HCV-482B-TV, 3-WAY MANUAL CONTROL VALVE R14
AOP-11 Page 29 of 49 INSTRUCTIONS CONTINGENCY ACTIONS
- 12. (continued)
- h. IF AC-4B, SDC HX, is in service, THEN establish RW flow to AC-4B by performing the following steps:
- 1) Close BOTH AC-4B CCW Isolation Valves:
- HCV-481
- HCV-485
- 2) Unlock and release the hand-jacks from BOTH of the following RW Interface Valves (Corridor 4):
- HCV-483A, SHUTDOWN COOLING HT EXCH AC-4B BACK-UP RAW WATER INLET VALVE
- HCV-483B, SHUTDOWN COOLING HT EXCH AC-4B BACK-UP RAW WATER OUTLET VALVE (continue)
R14
AOP-11 Page 30 of 49 INSTRUCTIONS CONTINGENCY ACTIONS 12.h (continued)
- 3) Locally open both AC-4B RW Interface Valves, HCV-483A/B, by placing the following valves to OPEN (Corridor 4):
- IA-HCV-483A-TV, 3-WAY MANUAL CONTROL VALVE
- IA-HCV-483B-TV, 3-WAY MANUAL CONTROL VALVE
- i. IF VA-46A, Control Room Ventilation Fan, is in service, THEN establish RW flow to VA-46A, by performing the following steps:
NOTE Manual isolation of RW direct cooling is required when LAS-2898 alarms.
- 1) Close HCV-2898A/B, CCW Valves.
(continue)
R14
AOP-11 Page 31 of 49 INSTRUCTIONS CONTINGENCY ACTIONS 12.i (continued)
- 2) Unlock and release the hand-jacks from BOTH of the following RW Interface Valves (Room 81):
- 3) Open BOTH HCV-2898C/D, VA-46A RW Valves by placing the following valves to OPEN (Room 81):
- IA-HCV-2898C-TV, 3-WAY MANUAL CONTROL VALVE
- IA-HCV-2898D-TV, 3-WAY MANUAL CONTROL VALVE (continue)
R14
AOP-11 Page 32 of 49 INSTRUCTIONS CONTINGENCY ACTIONS
- 12. (continued)
- j. IF VA-46B, Control Room Ventilation Fan, is in service, THEN establish RW flow to VA-46B by performing the following steps:
NOTE Manual isolation of RW direct cooling is required when LAS-2899 alarms.
- 1) Close HCV-2899A/B, VA-46B CCW Valves.
- 2) Unlock and release the hand-jacks from BOTH of the following RW Interface Valves (Room 81):
R14
AOP-11 Page 33 of 49 INSTRUCTIONS CONTINGENCY ACTIONS 12.j (continued)
- 3) Open BOTH HCV-2899C/D, VA-46B RW Valves by placing the following valves to OPEN (Room 81):
- IA-HCV-2899C-TV, 3-WAY MANUAL CONTROL VALVE
- IA-HCV-2899D-TV, 3-WAY MANUAL CONTROL VALVE
- k. IF SI-3A, CS Pump, is in service, THEN establish RW flow to SI-3A by performing the following steps:
- 1) Close HCV-2813A/B, Spray Pump SI-3A Bearing Cooler CCW Valves.
(continue)
R14
AOP-11 Page 34 of 49 INSTRUCTIONS CONTINGENCY ACTIONS 12.k (continued)
- 2) Unlock and release the hand-jacks from BOTH of the following RW Interface Valves (Room 21):
- 3) Locally open HCV-2813C/D, Spray Pump SI-3A Bearing Cooler RW Valves by placing the following valves to OPEN (Room 21):
- IA-HCV-2813C-TV, 3-WAY MANUAL CONTROL VALVE
- IA-HCV-2813D-TV, 3-WAY MANUAL CONTROL VALVE (continue)
R14
AOP-11 Page 35 of 49 INSTRUCTIONS CONTINGENCY ACTIONS
- 12. (continued)
- l. IF SI-1A, LPSI Pump, is in service, THEN establish RW flow to SI-1A by performing the following steps:
- 2) Unlock and release the hand-jacks from BOTH of the following RW Interface Valves (Room 21):
R14
AOP-11 Page 36 of 49 INSTRUCTIONS CONTINGENCY ACTIONS 12.l (continued)
- 3) Open HCV-2808C/D, SI-1A Bearing Cooler CCW Valves by placing the following valves to OPEN (Room 21):
- IA-HCV-2808C-TV, 3-WAY MANUAL CONTROL VALVE
- IA-HCV-2808D-TV, 3-WAY MANUAL CONTROL VALVE
- m. IF SI-2A, HPSI Pump, is in service, THEN establish RW flow to SI-2A by performing the following steps:
(continue)
R14
AOP-11 Page 37 of 49 INSTRUCTIONS CONTINGENCY ACTIONS 12.m (continued)
- 2) Unlock and release the hand-jacks from BOTH of the following RW Interface Valves (Room 21):
- 3) Open HCV-2810C/D, SI-2A Bearing Cooler RW Valves by placing the following valves to OPEN (Room 21):
- IA-HCV-2810C-TV, 3-WAY MANUAL CONTROL VALVE
- IA-HCV-2810D-TV, 3-WAY MANUAL CONTROL VALVE (continue)
R14
AOP-11 Page 38 of 49 INSTRUCTIONS CONTINGENCY ACTIONS
- 12. (continued)
- n. IF SI-2C, HPSI Pump, is in service, THEN establish RW flow to SI-2C by performing the following steps:
- 2) Unlock and release the hand-jacks from BOTH of the following RW Interface Valves (Room 21):
R14
AOP-11 Page 39 of 49 INSTRUCTIONS CONTINGENCY ACTIONS 12.n (continued)
- 3) Open HCV-2812C/D, SI-2C Bearing Cooler RW Valves by placing the following valves to OPEN (Room 21):
- IA-HCV-2812C-TV, 3-WAY MANUAL CONTROL VALVE
- IA-HCV-2812D-TV, 3-WAY MANUAL CONTROL VALVE
- o. IF SI-3B, Containment Spray Pump, is in service, THEN establish RW flow to SI-3B by performing the following steps:
- 1) Close HCV-2814A/B, Spray Pump SI-3B Bearing Cooler CCW Valves.
(continue)
R14
AOP-11 Page 40 of 49 INSTRUCTIONS CONTINGENCY ACTIONS 12.o (continued)
- 2) Unlock and release the hand-jacks from BOTH of the following RW Interface Valves (Room 22):
- 3) Open HCV-2814C/D, SI-3B Bearing Cooler RW Valves by placing the following valves to OPEN (Room 22):
- IA-HCV-2814C-TV, 3-WAY MANUAL CONTROL VALVE
- IA-HCV-2814D-TV, 3-WAY MANUAL CONTROL VALVE (continue)
R14
AOP-11 Page 41 of 49 INSTRUCTIONS CONTINGENCY ACTIONS
- 12. (continued)
- p. IF SI-3C, Containment Spray Pump, is in service, THEN establish RW flow to SI-3C by performing the following steps:
- 1) Close HCV-2815A/B, Spray Pump SI-3C Bearing Cooler CCW Valves.
- 2) Unlock and release the hand-jacks from BOTH of the following RW Interface Valves (Room 22):
R14
AOP-11 Page 42 of 49 INSTRUCTIONS CONTINGENCY ACTIONS 12.p (continued)
- 3) Open HCV-2815C/D, SI-3C Bearing Cooler RW Valves by placing the following valves to OPEN (Room 22):
- IA-HCV-2815C-TV, 3-WAY MANUAL CONTROL VALVE
- IA-HCV-2815D-TV, 3-WAY MANUAL CONTROL VALVE
- q. IF SI-1B, LPSI Pump, is in service, THEN establish RW flow to SI-1B by performing the following steps:
(continue)
R14
AOP-11 Page 43 of 49 INSTRUCTIONS CONTINGENCY ACTIONS 12.q (continued)
- 2) Unlock and release the hand-jacks from BOTH of the following RW Interface Valves (Room 22):
- 3) Open HCV-2809C/D, SI-1B Bearing Cooler RW Valves by placing the following valves to OPEN (Room 22):
- IA-HCV-2809C-TV, 3-WAY MANUAL CONTROL VALVE
- IA-HCV-2809D-TV, 3-WAY MANUAL CONTROL VALVE (continue)
R14
AOP-11 Page 44 of 49 INSTRUCTIONS CONTINGENCY ACTIONS
- 12. (continued)
- r. IF SI-2B, HPSI Pump, is in service, THEN establish RW flow to SI-2B by performing the following steps:
- 2) Unlock and release the hand-jacks from BOTH of the following RW Interface Valves (Room 22):
R14
AOP-11 Page 45 of 49 INSTRUCTIONS CONTINGENCY ACTIONS 12.r (continued)
- 3) Open HCV-2811C/D, SI-2B Bearing Cooler RW Valves by placing the following valves to OPEN (Room 22):
- IA-HCV-2811C-TV, 3-WAY MANUAL CONTROL VALVE
- IA-HCV-2811D-TV, 3-WAY MANUAL CONTROL VALVE
- s. IF SIAS relays are tripped, THEN override the open signals on RW/CCW Heat Exchanger Isolation Valves by placing BOTH of the following switches in OVERRIDE:
WP12 Fort Calhoun Station Unit No. 1 OI-AOV-1 OPERATING INSTRUCTION
Title:
AIR OPERATED VALVE MANUAL OPERATION FC-68 Number: EC 43771 Reason for Change: Provided guidance for handjacking HCV-341.
Requestor: K. Kingston Preparer: L. Hautzinger ISSUED: 07-31-08 3:00 pm R12
FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 1 OF 69 AIR OPERATED VALVE MANUAL OPERATION SAFETY RELATED ATT PURPOSE PAGE 1 - Operation of Raw Water Air Operated Valves . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 2 - Operation of Component Cooling Water Air Operated Valves . . . . . . . . . . . . . . . . . . . . . . . . . 13 3 - Operation of Safety Injection Air Operated Valves . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 34 4 - Operation of Chemical Volume Control System Air Operated Valves . . . . . . . . . . . . . . . . . . . 50 5 - Operation of Turbine Plant Cooling Water Air Operated Valves . . . . . . . . . . . . . . . . . . . . . . . 51 6 - Operation of Containment Instrument Air Supply Outboard Pressure Control Valve . . . . . . . . 54 7 - Operation of Main Steam Air Operated Valves . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 56 8 - Operation of Feed Water Heater Level Control Air Operated Valves . . . . . . . . . . . . . . . . . . . 58 9 - Operation of Feed Water Air Operated Valves . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 62 PRECAUTIONS
- 1. This procedure contains attachments to manually operate AOVs (Air Operated Valves) throughout the plant. Consideration should always be given to current plant conditions prior to operation of any of these valves manually.
- 2. This procedure should only be used with proper planning and pre-operation briefings.
Contact the AOV Engineer with concerns prior to its use.
- 3. This procedure is for guidance only and should not be used to mitigate plant transients unless authorized by the Shift Manger.
- 4. Inoperability of a Raw Water Header, Raw Water Pump(s) and/or a Raw Water Heat Exchanger requires entry into Technical Specification LCO(s). The LCO entry is dependent on river temperature.
R12
FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 2 OF 69 REFERENCES/COMMITMENTS
- 1. Technical Specifications:
! 2.3: Emergency Core Cooling System
! 2.4: Containment Cooling
- 2. Drawings File Description 11405-M-100 10454 Raw Water System 11405-M-40 44354 Component Cooling System 11405-M-259 10465 Potable Water System
- 3. Others:
! EA-FC-95-012, Effect of Post-DBA CCW Temperature Transient on Components
! OPPD Calculation FC07259, Rev. 0; FCS RW/CCW Gothic Model
! OPPD Calculation FC07238, Rev. 0; FCS RW/CCW Gothic Analyses - Additional Configurations APPENDICES None R12
FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 3 OF 69 C
Continuous Use Attachment 1 - Operation of Raw Water Air Operated Valves PREREQUISITES (%) INITIALS 1 Procedure Revision Verification:
Revision No. Date:
PROCEDURE NOTES
- 1. To minimize RW Pump operation in the run-out condition, the four CCW Heat Exchanger Discharge Isolation Valves are set in a throttled position via the measured exposed valve stem. This throttling is intended to assist the restricting orifaces in limiting flow to approximately 3000-3500 gpm flow through one Hx with one pump running. The measured exposed valve stem is recorded in OI-RW-1-CL-A.
- 2. At the Shift Manager's discretion this throttled position may be adjusted to meet system and/or plant requirements. If so the new measured exposed valve stem shall be documented in the Control Room Log, OI-RW-1-CL-A, and on a new caution tag hung on the valves(s) adjusted.
If the throttle position is adjusted, the System Engineer should be notified in a timely manner to evaluate system flow conditions (i.e., the need for performance of SE-EQT-RW-0001). The Caution Tag may be removed after OI-RW-1-CL-A has been updated.
- 3. The four CCW Hx Discharge Isolation Valves are equipped with a handjack to limit the open position of the valve disc. These valves are handjacked closed when the HX is removed from service for maintenance/cleaning.
R12
FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 4 OF 69 C
Continuous Use Attachment 1 - Operation of Raw Water Air Operated Valves PROCEDURE (continued) (T) INITIALS CAUTIONS
- 1. Limit the time one RW Pump operates in the run out condition (Flows greater than 7500 gpm) to reduce the potential of pump degradation.
- 2. Adjustment of the throttle position may cause limit switch contact mismatch for remote valve position indication.
- 1. If handjacking HCV-2880B, HCV-2881B, HCV-2882B, OR HCV-2883B Closed, complete the following steps:
- a. Ensure the Raw Water Discharge Valve is Closed:
! HCV-2880B, Comp Cooling Ht Exch AC-1A Raw Water Outlet Valve
! HCV-2881B, Comp Cooling Ht Exch AC-1B Raw Water Outlet Valve
! HCV-2882B, Comp Cooling Ht Exch AC-1C Raw Water Outlet Valve
! HCV-2883B, Comp CoolingValve
- b. Loosen the Handjacks stem nut and run it up to contact the bottom face of the handwheel:
! HCV-2880B
! HCV-2881B
! HCV-2882B
! HCV-2883B R12
FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 5 OF 69 C
Continuous Use Attachment 1 - Operation of Raw Water Air Operated Valves PROCEDURE (continued) (T) INITIALS CAUTION Do not force the handwheel if excessive resistance is met before the Handjacks stem nut contacts the bonnet of the actuator housing. It is possible that the valve disc is being forced into or beyond the valve seat.
This condition can cause the valve to be stuck in the closed position.
1 c. Turn the handwheel clockwise until the handjacks stem nut contacts the bonnet of the actuator housing:
! HCV-2880B
! HCV-2881B
! HCV-2882B
! HCV-2883B
- d. If excessive resistance is met before the stem nut contacts the bonnet of the actuator housing, contact the System Engineer.
- 2. If removing the valve handjacks from a RW Discharge Valve, perform the following:
- a. Turn handwheel counter-clockwise until the measured valve stem matches the stem position recorded in OI-RW-1-CL-A:
! HCV-2880B, Comp Cooling Ht Exch AC-1A Raw Water Outlet Valve
! HCV-2881B, Comp Cooling Ht Exch AC-1B Raw Water Outlet Valve
! HCV-2882B, Comp Cooling Ht Exch AC-1C Raw Water Outlet Valve
! HCV-2883B, Comp Cooling Ht Exch AC-1D Raw Water Outlet Valve
- b. Run the Handjacks stem nut down until it contacts the bonnet of the actuator housing:
! HCV-2880B
! HCV-2881B
! HCV-2882B
! HCV-2883B R12
FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 6 OF 69 C
Continuous Use Attachment 1 - Operation of Raw Water Air Operated Valves PROCEDURE (continued) (T) INITIALS 2 c. Verify the exposed threaded shaft measurement and adjust as necessary:
! HCV-2880B
! HCV-2881B
! HCV-2882B
! HCV-2883B
- d. Stroke the valve(s) as necessary to verify proper operation and position indication:
! HCV-2880B
! HCV-2881B
! HCV-2882B
! HCV-2883B NOTES
- 1. The Declutching pin will automatically move out of the outer slot when the hand wheel is pushed in.
- 2. When the worm gear is fully engaging the gear segment, the pin will drop into the inner slot.
- 3. If handjacking HCV-2880A, HCV-2881A, HCV-2882A, or HCV-2883A is desired, complete the following for the applicable valves:
- a. Engage the handwheel by pushing in and turning clockwise:
! HCV-2880A
! HCV-2881A
! HCV-2882A
! HCV-2883A
- b. Place the valve in the desired position:
! HCV-2880A
! HCV-2881A
! HCV-2882A
! HCV-2883A R12
FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 7 OF 69 C
Continuous Use Attachment 1 - Operation of Raw Water Air Operated Valves PROCEDURE (continued) (T) INITIALS
- 4. If removing the handjack, complete the following for the applicable valve:
- a. Simultaneously press declutching spring to push the pin out, and turn the hand wheel counterclockwise until the worm gear disengages the gear segment:
! HCV-2880A, Comp Cooling Ht Exch AC-1A Raw Water Inlet Valve
! HCV-2881A, Comp Cooling Ht Exch AC-1B Raw Water Inlet Valve
! HCV-2882A, Comp Cooling Ht Exch AC-1C Raw Water Inlet Valve
! HCV-2883A, Comp Cooling Ht Exch AC-1D Raw Water Inlet Valve NOTE The pin engages the outer slot to keep the handwheel in the engaged position.
- b. Allow the spring to move the handwheel all of the way out, and release the pin:
! HCV-2880A
! HCV-2881A
! HCV-2882A
! HCV-2883A
- c. Stroke the valve(s) as necessary to verify proper operation and position indication:
! HCV-2880A
! HCV-2881A
! HCV-2882A
! HCV-2883A R12
FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 8 OF 69 C
Continuous Use Attachment 1 - Operation of Raw Water Air Operated Valves PROCEDURE (continued) (T) INITIALS
- 5. If hand jacking HCV-2877A/B, HCV-2878A/B, or HCV-2879A/B, HCV-2893, OR HCV-2894, perform the following:
- a. Ensure selected valve is Closed:
! HCV-2877A, Comp Clg Ht Exchs AC-1A-D Raw Water Inlet Header Isolation Valve
! HCV-2877B, Comp Clg Ht Exchs AC-1A-D Raw Water Inlet Header Isolation Valve
! HCV-2878A, Comp Clg Ht Exchs AC-1A-D Raw Water Inlet Header Isolation Valve
! HCV-2878B, Comp Clg Ht Exchs AC-1A-D Raw Water Inlet Header Isolation Valve
! HCV-2879A, Comp Clg Ht Exchs AC-1A-D Raw Water Inlet Header Isolation Valve
! HCV-2879B, Comp Clg Ht Exchs AC-1A-D Raw Water Inlet Header Isolation Valve
! HCV-2893, Raw Water to CCW Isolation Valve
! HCV-2894, Raw Water to CCW Isolation Valve
- b. Loosen the nut on the hand jack stem for selected valves:
! HCV-2877A
! HCV-2877B
! HCV-2878A
! HCV-2878B
! HCV-2879A
! HCV-2879B
! HCV-2893
! HCV-2894 R12
FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 9 OF 69 C
Continuous Use Attachment 1 - Operation of Raw Water Air Operated Valves PROCEDURE (continued) (T) INITIALS 5 c. Turn the hand wheel CLOCKWISE, counting each turn, until handwheel stop contacts diaphragm for selected valves:
! HCV-2877A, Turns:___________
! HCV-2877B, Turns:___________
! HCV-2878A, Turns:___________
! HCV-2878B, Turns:___________
! HCV-2879A, Turns:___________
! HCV-2879B, Turns:___________
! HCV-2893, Turns:___________
! HCV-2894, Turns:___________
- d. Tighten the hand jack locking nut against diaphragm housing for selected valves:
! HCV-2877A
! HCV-2877B
! HCV-2878A
! HCV-2878B
! HCV-2879A
! HCV-2879B
! HCV-2893
! HCV-2894
- e. Record the number of turns on the danger/caution tag end, and in the tag removal notes of the clearance for selected valves:
! HCV-2877A
! HCV-2877B
! HCV-2878A
! HCV-2878B
! HCV-2879A
! HCV-2879B
! HCV-2893
! HCV-2894 R12
FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 10 OF 69 C
Continuous Use Attachment 1 - Operation of Raw Water Air Operated Valves PROCEDURE (continued) (T) INITIALS
- 6. If removing the handjack from HCV-2877A/B, HCV-2878A/B, or HCV-2879A/B, perform the following:
- a. Ensure air drain on filter regulator for selected valve(s) is closed:
! HCV-2877A, Comp Clg Ht Exchs AC-1A-D Raw Water Inlet Header Isolation Valve
! HCV-2877B, Comp Clg Ht Exchs AC-1A-D Raw Water Inlet Header Isolation Valve
! HCV-2878A, Comp Clg Ht Exchs AC-1A-D Raw Water Inlet Header Isolation Valve
! HCV-2878B, Comp Clg Ht Exchs AC-1A-D Raw Water Inlet Header Isolation Valve
! HCV-2879A, Comp Clg Ht Exchs AC-1A-D Raw Water Inlet Header Isolation Valve
! HCV-2879B, Comp Clg Ht Exchs AC-1A-D Raw Water Inlet Header Isolation Valve
! HCV-2893, Raw Water to CCW Isolation Valve
! HCV-2894, Raw Water to CCW Isolation Valve
- b. Ensure Air Supply Isolation Valve(s) for selected Valve is open:
! HCV-2877A
! HCV-2878B
! HCV-2878A
! HCV-2878B
! HCV-2879A
! HCV-2879B
! HCV-2893
! HCV-2894 R12
FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 11 OF 69 C
Continuous Use Attachment 1 - Operation of Raw Water Air Operated Valves PROCEDURE (continued) (T) INITIALS NOTE On removing power from the valve, the solenoid will fail the valve open.
6 c. Ensure selected valve has a Closed signal:
! HCV-2877A
! HCV-2878B
! HCV-2878A
! HCV-2878B
! HCV-2879A
! HCV-2879B
! HCV-2893
! HCV-2894
- d. Loosen the Locking nut on selected valve handwheel stem:
! HCV-2877A
! HCV-2877B
! HCV-2878A
! HCV-2878B
! HCV-2879A
! HCV-2879B
! HCV-2893
! HCV-2894
- e. Turn handwheel COUNTER-CLOCKWISE the number of turns recorded in step 5.c for selected valves:
! HCV-2877A
! HCV-2877B
! HCV-2878A
! HCV-2878B
! HCV-2879A
! HCV-2879B
! HCV-2893
! HCV-2894 R12
FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 12 OF 69 C
Continuous Use Attachment 1 - Operation of Raw Water Air Operated Valves PROCEDURE (continued) (T) INITIALS 6 f. Tighten lock nut on valve stem against diaphragm housing for selected valve:
! HCV-2877A
! HCV-2877B
! HCV-2878A
! HCV-2878B
! HCV-2879A
! HCV-2879B
! HCV-2893
! HCV-2894
- g. Stroke valve as needed to ensure proper operation and indication for selected valve:
! HCV-2877A
! HCV-2877B
! HCV-2878A
! HCV-2878B
! HCV-2879A
! HCV-2879B
! HCV-2893
! HCV-2894 Completed by Date/Time /
R12
FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 13 OF 69 C
Continuous Use Attachment 2 - Operation of Component Cooling Water Air Operated Valves PREREQUISITES (T) INITIALS
- 1. Procedure Revision Verification Revision No. Date:
PROCEDURE CAUTION Operating a valve hand jack against spring pressure may cause valve damage.
- 1. If hand jacking HCV-489A, HCV-490A/B, HCV-491B, or HCV-492A/B, Comp Cooling Ht Exchs AC-1A-D CCW Valves, Closed, complete the following:
- a. Ensure valve to be hand jacked is Closed:
! HCV-489A, Comp Cooling Ht Exch AC-1A CCW Inlet Valve
! HCV-490A, Comp Cooling Ht Exch AC-1B CCW Inlet Valve
! HCV-490B, Comp Cooling Ht Exch AC-1B CCW Outlet Valve
! HCV-491B, Comp Cooling Ht Exch AC-1C CCW Outlet Valve
! HCV-492A, Comp Cooling Ht Exch AC-1D CCW Inlet Valve
! HCV-492B, Comp Cooling Ht Exch AC-1D CCW Outlet Valve
- b. Align and insert J-hook into slot on the manual operator side of the valve
! HCV-489A
! HCV-490A
! HCV-490B
! HCV-491B
! HCV-492A
! HCV-492B R12
FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 14 OF 69 C
Continuous Use Attachment 2 - Operation of Component Cooling Water Air Operated Valves PROCEDURE (continued) (T) INITIALS 1 c. Loosen hose clamp and remove J-hook from the air operator side of the valve:
! HCV-489A
! HCV-490A
! HCV-490B
! HCV-491B
! HCV-492A
! HCV-492B
- d. Re-tighten hose clamp around slot to prevent J-hook from entering slot:
! HCV-489A
! HCV-490A
! HCV-490B
! HCV-491B
! HCV-492A
! HCV-492B
- 2. If removing hand jack from HCV-489A, HCV-490A/B, HCV-491B, or HCV-492A/B, Comp Cooling Ht Exch AC-1A CCW Valves, complete the following:
- a. Ensure valve has a Closed signal:
! HCV-489A, Comp Cooling Ht Exch AC-1A CCW Inlet Valve
! HCV-490A, Comp Cooling Ht Exch AC-1B CCW Inlet Valve
! HCV-490B, Comp Cooling Ht Exch AC-1B CCW Outlet Valve
! HCV-491B, Comp Cooling Ht Exch AC-1C CCW Outlet Valve
! HCV-492A, Comp Cooling Ht Exch AC-1D CCW Inlet Valve
! HCV-492B, Comp Cooling Ht Exch AC-1D CCW Outlet Valve
- b. Ensure that the valve is manually hand jacked in the Closed position:
! HCV-489A
! HCV-490A
! HCV-490B
! HCV-491B
! HCV-492A
! HCV-492B R12
FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 15 OF 69 C
Continuous Use Attachment 2 - Operation of Component Cooling Water Air Operated Valves PROCEDURE (continued) (T) INITIALS 2 c. Loosen hose clamp and insert J-hook into slot on air operator side of the valve:
! HCV-489A
! HCV-490A
! HCV-490B
! HCV-491B
! HCV-492A
! HCV-492B
- d. Re-tighten the hose clamp around J-hook and the slot:
! HCV-489A
! HCV-490A
! HCV-490B
! HCV-491B
! HCV-492A
! HCV-492B
- e. Remove J-hook from the slot on the manual operator side of the valve:
! HCV-489A
! HCV-490A
! HCV-490B
! HCV-491B
! HCV-492A
! HCV-492B
- f. Stroke valve as necessary to verify proper operation and position indication:
! HCV-489A
! HCV-490A
! HCV-490B
! HCV-491B
! HCV-492A
! HCV-492B R12
FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 16 OF 69 C
Continuous Use Attachment 2 - Operation of Component Cooling Water Air Operated Valves PROCEDURE (continued) (T) INITIALS
- 3. If hand jacking HCV-489B, Comp Cooling Ht Exch AC-1A CCW Outlet Valve, or HCV-491A, Comp Cooling Ht Exch AC-1C CCW Inlet Valve, Closed, complete the following:
- a. Ensure valve to be hand jacked is Closed:
! HCV-489B, Comp Cooling Ht Exch AC-1A CCW Outlet Valve
! HCV-491A, Comp Cooling Ht Exch AC-1C CCW Inlet Valve
- b. Align notch in pointer to hole in gear on manual operator and insert pin.
! HCV-489B
! HCV-491A
- c. Loosen hose clamp and remove J-hook from the air operator side of the valve.
! HCV-489B
! HCV-491A
- d. Re-tighten hose clamp around slot to prevent J-hook from entering slot.
! HCV-489B
! HCV-491A
- 4. If removing hand jack from HCV-489B, Comp Cooling Ht Exch AC-1A CCW Outlet Valve, or HCV-491A, Comp Cooling Ht Exch AC-1C CCW Inlet Valve, Closed, complete the following:
- a. Ensure valve has a Closed signal:
! HCV-489B, Comp Cooling Ht Exch AC-1A CCW Outlet Valve
! HCV-491A, Comp Cooling Ht Exch AC-1C CCW Inlet Valve
- b. Ensure that the valve is manually hand jacked in the closed position.
! HCV-489B
! HCV-491A R12
FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 17 OF 69 C
Continuous Use Attachment 2 - Operation of Component Cooling Water Air Operated Valves PROCEDURE (continued) (T) INITIALS 4 c. Loosen hose clamp and insert J-hook into slot on air operator side of the valve.
! HCV-489B
! HCV-491A
- d. Re-tighten the hose clamp around J-hook and the slot.
! HCV-489B
! HCV-491A
- e. Remove pin from manual operator.
! HCV-489B
! HCV-491A
- f. Stroke the valve as necessary to verify proper operation and position indication.
! HCV-489B
! HCV-491A
- 5. If hand jacking HCV-497 Comp Clg Ht Exchs AC-1A-D CCW Bypass Line Isolation Valve, complete the following:
- a. Ensure HCV-497 is Open.
- b. Loosen stem nut.
- c. Turn handwheel clockwise until handwheel stem pusher plate contacts diaphragm plate.
- d. Tighten stem nut.
- 6. If removing hand jack from HCV-497 Comp Clg Ht Exchs AC-1A-D CCW Bypass Line Isolation Valve, complete the following:
- a. Ensure HCV-497 has an Open signal.
- b. Loosen stem nut.
R12
FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 18 OF 69 C
Continuous Use Attachment 2 - Operation of Component Cooling Water Air Operated Valves PROCEDURE (continued) (T) INITIALS 6 c. Turn handwheel COUNTER-CLOCKWISE until handwheel stem pusher plate contacts upper diaphragm casing.
- d. Tighten stem nut.
- e. Stroke HCV-497 Comp Clg Ht Exchs AC-1A-D CCW Bypass Line Isolation Valve as necessary to verify proper operation and position indication.
- 7. If hand jacking HCV-425B/D, SI Leakage Coolers SI-4A-D Combined CCW Inlet/Outlet Header Outboard Isolation Valves, or HCV-467B/D, Det Well Cooling Coils VA-14A&B Combined CCW Inlet/Outlet Header Outboard Isolation Valves, Open, complete the following:
- a. Ensure that the valve to be hand jacked is Open:
! HCV-425B, SI Leakage Coolers SI-4A-D Combined CCW Inlet Header Outboard Isolation Valve
! HCV-425D, SI Leakage Coolers SI-4A-D Combined CCW Outlet Header Outboard Isolation Valve
! HCV-467B, Det Well Cooling Coils VA-14A&B Combined CCW Inlet Header Outboard Isolation Valve
! HCV-467D, Det Well Cooling Coils VA-14A&B Combined CCW Outlet Header Outboard Isolation Valve
- b. Turn handwheel counter-clockwise until handwheel contacts stem nut:
! HCV-425B
! HCV-425D
! HCV-467B
! HCV-467D
- c. If excessive resistence is met before handwheel contacts stem nut, contact System Engineer.
R12
FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 19 OF 69 C
Continuous Use Attachment 2 - Operation of Component Cooling Water Air Operated Valves PROCEDURE (continued) (T) INITIALS
- 8. If removing hand jack from HCV-425B/D, SI Leakage Coolers SI-4A-D Combined CCW Inlet/Outlet Header Outboard Isolation Valves, or HCV-467B/D, Det Well Cooling Coils VA-14A&B Combined CCW Inlet/Outlet Header Outboard Isolation Valves, complete the following:
- a. Ensure valve has an Open signal:
! HCV-425B, SI Leakage Coolers SI-4A-D Combined CCW Inlet Header Outboard Isolation Valve
! HCV-425D, SI Leakage Coolers SI-4A-D Combined CCW Outlet Header Outboard Isolation Valve
! HCV-467B, Det Well Cooling Coils VA-14A&B Combined CCW Inlet Header Outboard Isolation Valve
! HCV-467D, Det Well Cooling Coils VA-14A&B Combined CCW Outlet Header Outboard Isolation Valve
- b. Turn handwheel clockwise until handwheel contacts upper diaphragm casing:
! HCV-425B
! HCV-425D
! HCV-467B
! HCV-467D
- c. Stroke valve as necessary to verify proper operation and position indication:
! HCV-425B
! HCV-425D
! HCV-467B
! HCV-467D R12
FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 20 OF 69 C
Continuous Use Attachment 2 - Operation of Component Cooling Water Air Operated Valves PROCEDURE (continued) (T) INITIALS
- 9. If hand jacking HCV-438B/D, Reactor Coolant Pump RC-3A-3D Lube Oil and Seal Coolers Comp Cooling Water Supply/Return Valves, Closed, complete the following:
- a. Ensure valve that is to be hand jacked is Closed:
! HCV-438B, Reactor Coolant Pump RC-3A-3D Lube Oil and Seal Coolers Comp Cooling Water Supply Valve
! HCV-438D, RCP RC-3A-D Lube Oil and Seal Clrs CCW Outlet Outboard Isolation Valve
- b. Loosen stem nut:
! HCV-438B
! HCV-438D
- c. Turn handwheel CLOCKWISE until handwheel stem pusher plate contacts diaphragm plate:
! HCV-438B
! HCV-438D
- d. Tighten stem nut:
! HCV-438B
! HCV-438D
- 10. If removing hand jack from HCV-438B/D, Reactor Coolant Pump RC-3A-3D Lube Oil and Seal Coolers Comp Cooling Water Supply/Return Valves, complete the following:
- a. Ensure valve has a Closed signal:
! HCV-438B, Reactor Coolant Pump RC-3A-3D Lube Oil and Seal Coolers Comp Cooling Water Supply Valve
! HCV-438D, RCP RC-3A-D Lube Oil and Seal Clrs CCW Outlet Outboard Isolation Valve R12
FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 21 OF 69 C
Continuous Use Attachment 2 - Operation of Component Cooling Water Air Operated Valves PROCEDURE (continued) (T) INITIALS 10 b. Loosen stem nut:
! HCV-438B
! HCV-438D
- c. Turn handwheel COUNTER-CLOCKWISE until handwheel stem pusher plate contacts upper diaphragm casing:
! HCV-438B
! HCV-438D
- d. Tighten stem nut:
! HCV-438B
! HCV-438D
- e. Stroke valve as necessary to verify proper operation and position indication:
! HCV-438B
! HCV-438D
- 11. If hand jacking HCV-2895A/B, Waste Evap WD-21 & Ht Exchs DW-46A-2 &
DW-46B-2 Outlet/Inlet Valves, Open, complete the following:
- a. Ensure that the valve to be hand jacked is Open:
! HCV-2895A, Waste Evap WD-21 & Ht Exchs DW-46A-2 &
DW-46B-2 Inlet Valve
! HCV-2895B, Waste Evap WD-21 & Ht Exchs DW-46A-2 &
DW-46B-2 Outlet Valve
- b. Push in handwheel and turn CLOCKWISE until worm-gear fully engages the gear segment:
! HCV-2895A
! HCV-2895B R12
FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 22 OF 69 C
Continuous Use Attachment 2 - Operation of Component Cooling Water Air Operated Valves PROCEDURE (continued) (T) INITIALS 11 c. Verify declutching pin has dropped into inner slot on handwheel:
! HCV-2895A
! HCV-2895B
- 12. IF removing Handjack from HCV-2895A/B, Waste Evap WD-21 & Ht Exchs DW-46A-2 & DW-46B-2 Outlet/Inlet Valves:
- a. Ensure valve has an OPEN signal:
! HCV-2895A, Waste Evap WD-21 & Ht Exchs DW-46A-2 &
DW-46B-2 Inlet Valve
! HCV-2895B, Waste Evap WD-21 & Ht Exchs DW-46A-2 &
DW-46B-2 Outlet Valve
- b. Press declutching spring to push out declutching pin:
! HCV-2895A
! HCV-2895B
- c. Turn Handwheel COUNTER-CLOCKWISE until worm gear disengages the gear segment:
! HCV-2895A
! HCV-2895B
- d. Allow spring to move handwheel all the way out and release declutching pin into outer slot on handwheel shaft:
! HCV-2895A
! HCV-2895B
- e. Stroke valve as necessary to verify proper operation and position indication:
! HCV-2895A
! HCV-2895B R12
FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 23 OF 69 C
Continuous Use Attachment 2 - Operation of Component Cooling Water Air Operated Valves PROCEDURE (continued) (T) INITIALS
- 13. If locally Closing of HCV-400E/F, HCV-401E/F, HCV-402E/F, HCV-403E/F is desired, perform the following on the applicable valves:
- a. Place the control valve to Close for:
! IA-HCV-400E-TV, Raw Water Inlet Valve HCV-400E Manual Control Valve
! IA-HCV-400F-TV, Raw Water Outlet Valve HCV-400F Manual Control Valve
! IA-HCV-401E-TV, Raw Water Inlet Valve HCV-401E Manual Control Valve
! IA-HCV-401F-TV, Raw Water Outlet Valve HCV-401F Manual Control Valve
! IA-HCV-402E-TV, Raw Water Inlet Valve HCV-402E Manual Control Valve
! IA-HCV-402F-TV, Raw Water Outlet Valve HCV-402F Manual Control Valve
! IA-HCV-403E-TV, Raw Water Inlet Valve HCV-403E Manual Control Valve
! IA-HCV-403F-TV, Raw Water Outlet Valve HCV-403F Manual Control Valve
- b. Verify valve strokes fully Closed for:
! HCV-400E, Cntmt VA-1A Cooling Coil Back-up Raw Water Inlet Valve
! HCV-400F, Cntmt VA-1A Cooling Coil Back-up Raw Water Outlet Valve
! HCV-401E, Cntmt VA-1B Cooling Coil Back-up Raw Water Inlet Valve
! HCV-401F, Cntmt VA-1B Cooling Coil Back-up Raw Water Outlet Valve
! HCV-402E, Cntmt VA-1C Cooling Coil Back-up Raw Water Inlet Valve
! HCV-402F, Cntmt VA-1C Cooling Coil Back-up Raw Water Outlet Valve
! HCV-403E, Cntmt VA-1D Cooling Coil Back-up Raw Water Inlet Valve
! HCV-403F, Cntmt VA-1D Cooling Coil Back-up Raw Water Outlet Valve R12
FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 24 OF 69 C
Continuous Use Attachment 2 - Operation of Component Cooling Water Air Operated Valves PROCEDURE (continued) (T) INITIALS 13 c. Use rachet to replace Handjack by turning COUNTER-CLOCKWISE until it reaches the top:
! HCV-400E
! HCV-400F
! HCV-401E
! HCV-401F
! HCV-402E
! HCV-402F
! HCV-403E
! HCV-403F
- d. Reinstall cover and locking device:
! HCV-400E
! HCV-400F
! HCV-401E
! HCV-401F
! HCV-402E
! HCV-402F
! HCV-403E
! HCV-403F
- e. Verify locking device is installed:
! HCV-400E
! HCV-400F
! HCV-401E
! HCV-401F
! HCV-402E
! HCV-402F
! HCV-403E
! HCV-403F Ind Verif R12
FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 25 OF 69 C
Continuous Use Attachment 2 - Operation of Component Cooling Water Air Operated Valves PROCEDURE (continued) (T) INITIALS 13 f. Remove selected valve from the Locked Component Deviation Log:
! HCV-400E
! HCV-400F
! HCV-401E
! HCV-401F
! HCV-402E
! HCV-402F
! HCV-403E
! HCV-403F CAUTION The following steps may drain CCW from this portion of the system.
- 14. If locally Opening of HCV-400E/F, HCV-401E/F, HCV-402E/F, HCV-403E/F is desired, perform the following for the applicable valves:
- a. Ensure CCW isolation valves for selected unit(s) are closed:
! HCV-400B, Cntmt Clg Coil VA-1A AC Inlet Valve Valve
! HCV-400D, Cntmt Clg Coil VA-1A AC Outlet Valve
! HCV-401B, Cntmt Clg Coil VA-1B AC Inlet Valve Valve
! HCV-401D, Cntmt Clg Coil VA-1B AC Outlet Valve
! HCV-402B, Cntmt Clg Coil VA-8A AC Inlet Valve Valve
! HCV-402D, Cntmt Clg Coil VA-8A AC Outlet Valve
! HCV-403B, Cntmt Clg Coil VA-8BAC Inlet Valve Valve
! HCV-403D, Cntmt Clg Coil VA-8B AC Outlet Valve R12
FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 26 OF 69 C
Continuous Use Attachment 2 - Operation of Component Cooling Water Air Operated Valves PROCEDURE (continued) (T) INITIALS 14 b. Remove the locking mechanism and cover from the valve and place valve information in the Locked Component Deviation Log for the selected valve:
! HCV-400E, Cntmt VA-1A Cooling Coil Back-up Raw Water Inlet Valve
! HCV-400F, Cntmt VA-1A Cooling Coil Back-up Raw Water Outlet Valve
! HCV-401E, Cntmt VA-1B Cooling Coil Back-up Raw Water Inlet Valve
! HCV-401F, Cntmt VA-1B Cooling Coil Back-up Raw Water Outlet Valve
! HCV-402E, Cntmt VA-1C Cooling Coil Back-up Raw Water Inlet Valve
! HCV-402F, Cntmt VA-1C Cooling Coil Back-up Raw Water Outlet Valve
! HCV-403E, Cntmt VA-1D Cooling Coil Back-up Raw Water Inlet Valve
! HCV-403F, Cntmt VA-1D Cooling Coil Back-up Raw Water Outlet Valve
- c. Use the ratchet to release handjack by turning the locking nut CLOCKWISE until it reaches the bottom:
! HCV-400E
! HCV-400F
! HCV-401E
! HCV-401F
! HCV-402E
! HCV-402F
! HCV-403E
! HCV-403F R12
FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 27 OF 69 C
Continuous Use Attachment 2 - Operation of Component Cooling Water Air Operated Valves PROCEDURE (continued) (T) INITIALS 14 d. Place the Control Valve to Open:
! IA-HCV-400E-TV, Raw Water Inlet Valve HCV-400E Manual Control Valve
! IA-HCV-400F-TV, Raw Water Outlet Valve HCV-400F Manual Control Valve
! IA-HCV-401E-TV, Raw Water Inlet Valve HCV-401E Manual Control Valve
! IA-HCV-401F-TV, Raw Water Outlet Valve HCV-401F Manual Control Valve
! IA-HCV-402E-TV, Raw Water Inlet Valve HCV-402E Manual Control Valve
! IA-HCV-402F-TV, Raw Water Outlet Valve HCV-402F Manual Control Valve
! IA-HCV-403E-TV, Raw Water Inlet Valve HCV-403E Manual Control Valve
! IA-HCV-403F-TV, Raw Water Outlet Valve HCV-403F Manual Control Valve
- e. Verify the valve strokes Open:
! HCV-400E
! HCV-400F
! HCV-401E
! HCV-401F
! HCV-402E
! HCV-402F
! HCV-403E
! HCV-403F R12
FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 28 OF 69 C
Continuous Use Attachment 2 - Operation of Component Cooling Water Air Operated Valves PROCEDURE (continued) (T) INITIALS
- 15. If handjacking HCV-2898C/D, Control Room VA Unit VA-46A Raw Water Inlet/Outlet Valves, or HCV-2899C/D, Control Room VA Unit VA-46B Raw Water Inlet/Outlet Valves, perform the following:
- a. Ensure isolation valves are closed for selected valve by taking the air control valve to Close:
! IA-HCV-2898C-TV, Raw Water Inlet Valve HCV-2898C 3-Way Manual Control Valve
! IA-HCV-2898D-TV, Raw Water Outlet Valve HCV-2898D 3-Way Manual Control Valve
! IA-HCV-2899C-TV, Raw Water Inlet Valve HCV-2899C 3-Way Manual Control Valve
! IA-HCV-2899D-TV, Raw Water Outlet Valve HCV-2899D 3-Way Manual Control Valve
- b. Loosen required stem nut on selected valves:
! HCV-2898C, Control Room VA Unit VA-46A Raw Water Inlet Valve
! HCV-2898D, Control Room VA Unit VA-46A Raw Water Outlet Valve
! HCV-2899C, Control Room VA Unit VA-46B Raw Water Inlet Valve
! HCV-2899D, Control Room VA Unit VA-46B Raw Water Outlet Valve
- c. Unlock and turn hand wheel CLOCKWISE until the handwheel stem pusher plate contacts the diaphragm on selected valves:
! HCV-2898C
! HCV-2898D
! HCV-2899C
! HCV-2899D
- d. Tighten stem nut on handjacked valve:
! HCV-2898C
! HCV-2898D
! HCV-2899C
! HCV-2899D R12
FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 29 OF 69 C
Continuous Use Attachment 2 - Operation of Component Cooling Water Air Operated Valves PROCEDURE (continued) (T) INITIALS 15 e. Place locking Device on hand wheel for selected valve:
! HCV-2898C
! HCV-2898D
! HCV-2899C
! HCV-2899D
- f. Independently verify valve is Locked Closed:
! HCV-2898C
! HCV-2898D
! HCV-2899C
! HCV-2899D Ind Verif
- g. Remove selected valve from the Locked Component Deviation Log:
! HCV-2898C
! HCV-2898D
! HCV-2899C
! HCV-2899D
- 16. If handjacking HCV-2898A/B, Control Room VA Unit VA-46A Inlet/Outlet Valves, or HCV-2899A/B, Control Room VA Unit VA-46B Inlet/Outlet Valves, complete the following:
NOTE HCV-2898A/B and HCV-2899A/B can only be hand jacked in the open position.
- a. Ensure the valve to be handjacked is open:
! HCV-2898A, Control Room VA Unit VA-46A CCW Inlet Valve
! HCV-2898B, Control Room VA Unit VA-46A CCW Outlet Valve
! HCV-2899A, Control Room VA Unit VA-46B CCW Inlet Valve
! HCV-2899B, Control Room VA Unit VA-46B CCW Outlet Valve R12
FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 30 OF 69 C
Continuous Use Attachment 2 - Operation of Component Cooling Water Air Operated Valves PROCEDURE (continued) (T) INITIALS 16 b. Loosen stem nut for selected valves:
! HCV-2898A
! HCV-2898B
! HCV-2899A
! HCV-2899B
- c. Turn hand wheel COUNTER-CLOCKWISE until the handwheel is fully backseated for selected valves:
! HCV-2898A
! HCV-2898B
! HCV-2899A
! HCV-2899B
- d. Tighten stem nut for selected valves:
! HCV-2898A
! HCV-2898B
! HCV-2899A
! HCV-2899B
- 17. If removing handjack from HCV-2898A/B, Control Room VA Unit VA-46A Inlet/Outlet Valves, or HCV-2899A/B, Control Room VA Unit VA-46B Inlet/Outlet Valves, complete the following:
NOTE Can verify the handjack removed for HCV-2898A/B and HCV-2899A/B by verifying the hand wheel in the full CLOCKWISE position.
- a. Ensure the selected valve has an open signal:
! HCV-2898A, Control Room VA Unit VA-46A CCW Inlet Valve
! HCV-2898B, Control Room VA Unit VA-46A CCW Outlet Valve
! HCV-2899A, Control Room VA Unit VA-46B CCW Inlet Valve
! HCV-2899B, Control Room VA Unit VA-46B CCW Outlet Valve R12
FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 31 OF 69 C
Continuous Use Attachment 2 - Operation of Component Cooling Water Air Operated Valves PROCEDURE (continued) (T) INITIALS 17 b. Loosen stem nut on selected valves:
! HCV-2898A
! HCV-2898B
! HCV-2899A
! HCV-2899B
- c. Turn hand wheel CLOCKWISE until the handwheel contacts the top of the diaphram casing for selected valves:
! HCV-2898A
! HCV-2898B
! HCV-2899A
! HCV-2899B
- d. Tighten stem nut on selected valves:
! HCV-2898A
! HCV-2898B
! HCV-2899A
! HCV-2899B CAUTION The following steps may drain CCW from this portion of the system.
- 18. If removing Handjack from HCV-2898C/D, Control Room VA Unit VA-46A Raw Water Inlet/Outlet Valve, or HCV-2899C/D, Control Room VA Unit VA-46B Raw Water Inlet/Outlet Valves, complete the following:
- a. Ensure CCW isolation valves for the selected unit are Closed:
! HCV-2898A, Control Room VA Unit VA-46A CCW Inlet Valve
! HCV-2898B, Control Room VA Unit VA-46A CCW Outlet Valve
! HCV-2899A, Control Room VA Unit VA-46B CCW Inlet Valve
! HCV-2899B, Control Room VA Unit VA-46B CCW Outlet Valve R12
FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 32 OF 69 C
Continuous Use Attachment 2 - Operation of Component Cooling Water Air Operated Valves PROCEDURE (continued) (T) INITIALS 18 b. Ensure the hand jacked valves have a Closed signal:
! IA-HCV-2898C-TV, Raw Water Inlet Valve HCV-2898C 3-Way Manual Control Valve
! IA-HCV-2898D-TV, Raw Water Outlet Valve HCV-2898D 3-Way Manual Control Valve
! IA-HCV-2899C-TV, Raw Water Inlet Valve HCV-2899C 3-Way Manual Control Valve
! IA-HCV-2899D-TV, Raw Water Outlet Valve HCV-2899D 3-Way Manual Control Valve
- c. Loosen Stem nut on selected Hand jacked valves:
! HCV-2898C, Control Room VA Unit VA-46A Raw Water Inlet Valve
! HCV-2898D, Control Room VA Unit VA-46A Raw Water Outlet Valve
! HCV-2899C, Control Room VA Unit VA-46B Raw Water Inlet Valve
! HCV-2899D, Control Room VA Unit VA-46B Raw Water Outlet Valve
- d. Unlock handwheel and place valve information in the Locked Component Deviation Log for the selected valve:
! HCV-2898C
! HCV-2898D
! HCV-2899C
! HCV-2899D
- e. Turn handwheel COUNTER-CLOCKWISE until handwheel stem pusher plate contacts the upper diaphragm casing for selected valves:
! HCV-2898C
! HCV-2898D
! HCV-2899C
! HCV-2899D R12
FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 33 OF 69 C
Continuous Use Attachment 2 - Operation of Component Cooling Water Air Operated Valves PROCEDURE (continued) (T) INITIALS 18 f. Tighten stem nut on selected valves:
! HCV-2898C
! HCV-2898D
! HCV-2899C
! HCV-2899D
- g. Open selected valve by turning air valve to the Open position:
! IA-HCV-2898C-TV, Raw Water Inlet Valve HCV-2898C 3-Way Manual Control Valve
! IA-HCV-2898D-TV, Raw Water Outlet Valve HCV-2898D 3-Way Manual Control Valve
! IA-HCV-2899C-TV, Raw Water Inlet Valve HCV-2899C 3-Way Manual Control Valve
! IA-HCV-2899D-TV, Raw Water Inlet Valve HCV-2899D 3-Way Manual Control Valve Completed by Date/Time /
R12
FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 34 OF 69 C
Continuous Use Attachment 3 - Operation of Safety Injection Air Operated Valves PREREQUISITES (T) INITIALS
- 1. Procedure Revision Verification Revision No. Date:
PROCEDURE
- 1. If Handjacking LCV-383-1, or LCV-383-2, perform the following:
- a. Ensure valve to be Handjacked is Closed:
! LCV-383-1, SIRWT SI-5 Outlet Header Level Control Valve
! LCV-383-2, SIRWT SI-5 Outlet Header Level Control Valve
- b. Loosen stem nut on valve to be handjacked:
! LCV-383-1
! LCV-383-2
- c. Turn Handwheel CLOCKWISE, counting the number of turns, until the handwheel stem pusher plate contacts the diaphragm plate on the valve to be Handjacked:
! LCV-383-1
! LCV-383-2
- d. Record number of turns for Handjacked valve:
! LCV-383-1, Turns__________
! LCV-383-2, Turns__________
- e. Tighten stem nut on hand jacked valve:
! LCV-383-1
! LCV-383-2 R12
FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 35 OF 69 C
Continuous Use Attachment 3 - Operation of Safety Injection Air Operated Valves PROCEDURE (continued) (T) INITIALS
- 2. If removing handjack from LCV-383-1, or LCV-383-2, perform the following:
- a. Ensure that the Handjacked valve has a Closed signal:
! LCV-383-1, SIRWT SI-5 Outlet Header Level Control Valve
! LCV-383-2, SIRWT SI-5 Outlet Header Level Control Valve
- b. Loosen stem nut on Handjacked valve:
! LCV-383-1
! LCV-383-2
- c. Turn Handwheel on Handjacked valve COUNTER-CLOCKWISE the number of turns recorded in step 1.d:
! LCV-383-1
! LCV-383-2
- d. Tighten the stem nut for handjacked valve:
! LCV-383-1
! LCV-383-2
- e. Stroke valve as necessary to verify proper operation and position indication.
! LCV-383-1
! LCV-383-2
- 3. If handjacking HCV-753, HCV-754, HCV-749, or HCV-750, perform the following:
- a. Enure the valve to be handjacked is Closed:
! HCV-753, Cntmt Purge Supply Fan VA-24A Discharge Valve
! HCV-754, Cntmt Purge Supply Fan VA-24B Discharge Valve
! HCV-749, Cntmt Purge Disch Unit VA-33A Inlet Valve
! HCV-750, Cntmt Purge Disch Unit VA-33B Inlet Valve R12
FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 36 OF 69 C
Continuous Use Attachment 3 - Operation of Safety Injection Air Operated Valves PROCEDURE (continued) (T) INITIALS 3 b. Align the holes on the manual operator end of stem on valve to be handjacked.
! HCV-753
! HCV-754
! HCV-749
! HCV-750
- c. Insert Pin into hole on valve to be handjacked:
! HCV-753
! HCV-754
! HCV-749
! HCV-750
- d. Remove Pin from the air actuator assembly end on valve to be handjacked:
! HCV-753
! HCV-754
! HCV-749
! HCV-750
- 4. If removing the handjack from HCV-753, HCV-754, HCV-749, HCV-750, perform the following:
- a. Ensure that the Handjacked valve has a Closed signal:
! HCV-753, Cntmt Purge Supply Fan VA-24A Discharge Valve
! HCV-754, Cntmt Purge Supply Fan VA-24B Discharge Valve
! HCV-749, Cntmt Purge Disch Unit VA-33A Inlet Valve
! HCV-750, Cntmt Purge Disch Unit VA-33B Inlet Valve
- b. Insert the Pin on the Air actuator assembly end for handjacked valve
! HCV-753
! HCV-754
! HCV-749
! HCV-750 R12
FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 37 OF 69 C
Continuous Use Attachment 3 - Operation of Safety Injection Air Operated Valves PROCEDURE (continued) (T) INITIALS 4 c. Remove the Pin from the manual operator end of stem for handjacked valve:
! HCV-753
! HCV-754
! HCV-749
! HCV-750
- d. Stroke valve as necessary to verify proper operation and position indication for handjacked valve
! HCV-753
! HCV-754
! HCV-749
! HCV-750
- 5. If handjacking HCV-341, HCV-344 or HCV-345, perform the following:
- a. Ensure that the valve to be handjacked is Closed:
! HCV-341, Shutdown Clg Ht Exchs AC-4A & B Outlet Temperature Control Valve
! HCV-344, Containment Spray Header Isolation Valve
! HCV-345, Containment Spray Header Isolation Valve
- b. Using handwheel, align hole in manual operator for valve to be handjacked:
! HCV-341
! HCV-344
! HCV-345
- c. Insert pin into hole in manual operator for valve to be handjacked:
! HCV-341
! HCV-344
! HCV-345 R12
FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 38 OF 69 C
Continuous Use Attachment 3 - Operation of Safety Injection Air Operated Valves PROCEDURE (continued) (T) INITIALS
- 6. If removing handjack from HCV-341, HCV-344, or HCV-345, perform the following:
- a. Ensure valve that is Handjacked has a Closed signal:
! HCV-341, Shutdown Clg Ht Exchs AC-4A & B Outlet Temperature Control Valve
! HCV-344, Containment Spray Header Isolation Valve
! HCV-345, Containment Spray Header Isolation Valve
- b. Remove Pin from Manual operator for handjacked valve:
! HCV-341
! HCV-344
! HCV-345
- c. Ensure handwheel in its neutral position for valve that was handjacked:
! HCV-341
! HCV-344
! HCV-345
- d. Stroke valve as necessary to verify proper operation and position indication for handjacked valve:
! HCV-341
! HCV-344
! HCV-345 R12
FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 39 OF 69 C
Continuous Use Attachment 3 - Operation of Safety Injection Air Operated Valves PROCEDURE (continued) (T) INITIALS
- 7. If handjacking HCV-482 A/B, OR HCV-483 A/B Shutdown Cooling Heat Exchanger Back Up Raw Water Valves, perform the following:
- a. Enure the valve to be hand jacked is Closed:
! HCV-482A, Shutdown Cooling Ht Exch AC-4A Back-Up Raw Water Inlet Valve
! HCV-482B, Shutdown Cooling Ht Exch AC-4A Back-Up Raw Water Outlet Valve
! HCV-483A, Shutdown Cooling Ht Exch AC-4B Back-Up Raw Water Inlet Valve
! HCV-483B, Shutdown Cooling Ht Exch AC-4B Back-Up Raw Water Outlet Valve
- b. Ensure Instrument Air supply Insolation Valve is Open for selected valve:
! IA-HCV-482A-B, HCV-482A Instrument Air Supply Isolation Valve
! IA-HCV-482B-B, HCV-482B Instrument Air Supply Isolation Valve
! IA-HCV-483A-B, HCV-483A Instrument Air Supply Isolation Valve
! IA-HCV-483B-B, HCV-483B Instrument Air Supply Isolation Valve
- c. Place Raw Water Manual control valve in the Closed position for the selected valve:
! IA-HCV-482A-TV, Raw Water Inlet Valve HCV-482A Manual Control Valve
! IA-HCV-482B-TV, Raw Water Outlet Valve HCV-482B Manual Control Valve
! IA-HCV-483A-TV, Raw Water Inlet Valve HCV-843A Manual Control Valve
! IA-HCV-483B-TV, Raw Water Outlet Valve HCV-483B Manual Control Valve R12
FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 40 OF 69 C
Continuous Use Attachment 3 - Operation of Safety Injection Air Operated Valves PROCEDURE (continued) (T) INITIALS
- 7. d. Loosen the Hand Jack Stem Nut, and back it up to the bottom of the hand wheel for the selected valve:
! HCV-482A
! HCV-482B
! HCV-483A
! HCV-483B CAUTION Do Not Force the hand wheel if excessive resistance is met before the handjack stem nut contacts the bonnet of the actuator housing. It is possible that the valve disk is being forced into the valve seat.
- e. Turn the hand wheel CLOCKWISE until the handjack stem nut contacts the bonnet of the actuator housing for the selected valve:
! HCV-482A
! HCV-482B
! HCV-483A
! HCV-483B
- f. If excessive resistance is met before the stem nut contacts the bonnet of the actuator housing, contact the System Engineer for the selected valve:
! HCV-482A
! HCV-482B
! HCV-483A
! HCV-483B
- g. Lock hand wheel for the selected valve:
! HCV-482A
! HCV-482B
! HCV-483A
! HCV-483B Ind Verif R12
FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 41 OF 69 C
Continuous Use Attachment 3 - Operation of Safety Injection Air Operated Valves PROCEDURE (continued) (T) INITIALS
- 7. h. Remove selected valve from the Locked Component Deviation Log:
! HCV-482A
! HCV-482B
! HCV-483A
! HCV-483B CAUTION The following steps may drain CCW from this portion of the system.
- 8. If removing the handjack from HCV-482A, HCV-482B, HCV-483A, HCV-483B, perform the following:
- a. Ensure CCW isolation valves for selected heat exchanger(s) are closed:
! HCV-480, Shtdn Ht Exch AC-4A AC Inlet Valve
! HCV-484, Shtdn Ht Exch AC-4A AC Outlet Valve
! HCV-481, Shtdn Ht Exch AC-4B AC Inlet Valve
! HCV-485, Shtdn Ht Exch AC-4B AC Outlet Valve
- b. Ensure that the Handjacked valve has a Closed signal:
! HCV-482A, Shutdown Cooling Ht Exch AC-4A Back-Up Raw Water Inlet Valve
! HCV-482B, Shutdown Cooling Ht Exch AC-4A Back-Up Raw Water Outlet Valve
! HCV-483A, Shutdown Cooling Ht Exch AC-4B Back-Up Raw Water Inlet Valve
! HCV-483B, Shutdown Cooling Ht Exch AC-4B Back-Up Raw Water Outlet Valve
- c. Ensure Instrument Air Isolation valve is Open for selected valve:
! IA-HCV-482A-B, Instrument Air Supply Isolation Valve
! IA-HCV-482B-B, Instrument Air Supply Isolation Valve
! IA-HCV-483A-B, Instrument Air Supply Isolation Valve
! IA-HCV-483B-B, Instrument Air Supply Isolation Valve R12
FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 42 OF 69 C
Continuous Use Attachment 3 - Operation of Safety Injection Air Operated Valves PROCEDURE (continued) (T) INITIALS
- 8. d. Unlock and turn Hand wheel COUNTER-CLOCKWISE until valve stem travel stops for selected valve:
! HCV-482A
! HCV-482B
! HCV-483A
! HCV-483B
- e. Contact the Control Room and have selected valve entered into the Locked Component Deviation Log:
! HCV-482A
! HCV-482B
! HCV-483A
! HCV-483B
- f. Run the hand jack stem nut down until it contacts the Bonnet of the actuator housing for the selected valve:
! HCV-482A
! HCV-482B
! HCV-483A
! HCV-483B
- g. Place the raw water manual control valve for the selected valve in the OPEN position for the selected valve:
! IA-HCV-482A-TV, Raw Water Inlet Valve HCV-482A Manual Control Valve
! IA-HCV-482B-TV, Raw Water Outlet Valve HCV-482B Manual Control Valve
! IA-HCV-483A-TV, Raw Water Inlet Valve HCV-483A Manual Control Valve
! IA-HCV-483B-TV, Raw Water Outlet Valve HCV-483B Manual Control Valve R12
FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 43 OF 69 C
Continuous Use Attachment 3 - Operation of Safety Injection Air Operated Valves PROCEDURE (continued) (T) INITIALS
- 8. h. Ensure selected valve is in the Open position:
! HCV-482A
! HCV-482B
! HCV-483A
! HCV-483B
- 9. If handjacking HCV-2908, HCV-2918, or HCV-2928 HPSI Pump Discharge Valves, perform the following:
- a. Ensure the valve to be Handjacked is Closed:
! HCV-2928, HPSI Pump SI-2A Discharge Isolation Valve
! HCV-2908, HPSI Pump SI-2B Discharge Isolation Valve
! HCV-2918, HPSI Pump SI-2C Discharge Isolation Valve
- b. Remove the Handjack Locking pin from the Valve stem for the selected valve:
! HCV-2928
! HCV-2908
! HCV-2918
- c. Turn the valve hand wheel CLOCKWISE until the shaft sleeve contacts the valve yoke on the selected valve:
! HCV-2928
! HCV-2908
! HCV-2918
- d. Attach the Hand wheel locking pin to the hand wheel for the selected valve:
! HCV-2928
! HCV-2908
! HCV-2918 R12
FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 44 OF 69 C
Continuous Use Attachment 3 - Operation of Safety Injection Air Operated Valves PROCEDURE (continued) (T) INITIALS
- 10. If removing the handjack from HCV-2908, HCV-2918, or HCV-2928, perform the following:
- a. Ensure that the Handjacked valve has a Closed signal:
! HCV-2928, HPSI Pump SI-2A Discharge Isolation Valve
! HCV-2908, HPSI Pump SI-2B Discharge Isolation Valve
! HCV-2918, HPSI Pump SI-2C Discharge Isolation Valve
- b. Turn the handwheel COUNTER-CLOCKWISE until the shaft sleeve contacts the valve yoke for the selected valve:
! HCV-2928
! HCV-2908
! HCV-2918
- c. Insert the Handjack locking pin in the valve stem for the selected valve:
! HCV-2928
! HCV-2908
! HCV-2918
- d. Contact the Control Room that the hand jack has been removed for the selected valve:
! HCV-2928
! HCV-2908
! HCV-2918 R12
FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 45 OF 69 C
Continuous Use Attachment 3 - Operation of Safety Injection Air Operated Valves PROCEDURE (continued) (T) INITIALS
- 11. If handjacking HCV-2907, HCV-2917, HCV-2927, HCV-2938, HCV-2948, HCV-2957, HCV-2958, HCV-2967, HCV-2968, HCV-2977, HCV-2978, complete the following for the selected valves:
- a. Ensure valve to be Handjacked is Closed:
! HCV-2907, HPSI Pump SI-2B Suction Isolation Valve
! HCV-2917, HPSI Pump SI-2C Suction Isolation Valve
! HCV-2927, HPSI Pump SI-2A Suction Isolation Valve
! HCV-2938, LPSI Pump SI-1B Discharge Valve
! HCV-2948, LPSI Pump SI-1A Discharge Valve
! HCV-2957, Containment Spray Pump SI-3A Suction Valve
! HCV-2958, Containment Spray Pump SI-3A Discharge Valve
! HCV-2967, Containment Spray Pump SI-3B Suction Valve
! HCV-2968, Containment Spray Pump SI-3B Discharge Valve
! HCV-2977, Containment Spray Pump SI-3C Suction Valve
! HCV-2978, Containment Spray Pump SI-3C Discharge Valve
- b. Remove the Handjack Locking pin from the Valve stem for the selected valve:
! HCV-2907
! HCV-2917
! HCV-2927
! HCV-2938
! HCV-2948
! HCV-2957
! HCV-2958
! HCV-2967
! HCV-2968
! HCV-2977
! HCV-2978 R12
FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 46 OF 69 C
Continuous Use Attachment 3 - Operation of Safety Injection Air Operated Valves PROCEDURE (continued) (T) INITIALS
- 11. c. Turn the valve hand wheel CLOCKWISE until the shaft sleeve contacts the valve yoke on the selected valve:
! HCV-2907
! HCV-2917
! HCV-2927
! HCV-2938
! HCV-2948
! HCV-2957
! HCV-2958
! HCV-2967
! HCV-2968
! HCV-2977
! HCV-2978
- d. Attach the Hand wheel locking pin to the hand wheel for the selected valve:
! HCV-2907
! HCV-2917
! HCV-2927
! HCV-2938
! HCV-2948
! HCV-2957
! HCV-2958
! HCV-2967
! HCV-2968
! HCV-2977
! HCV-2978 R12
FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 47 OF 69 C
Continuous Use Attachment 3 - Operation of Safety Injection Air Operated Valves PROCEDURE (continued) (T) INITIALS
- 12. If Removing the Handjack from HCV-2907, HCV-2917, HCV-2927, HCV-2938, HCV-2948, HCV-2957, HCV-2958, HCV-2967, HCV-2968, HCV-2977, HCV-2978, complete the following for the selected valves.
- a. Ensure the valve to be Handjacked has a Closed signal.
! HCV-2907, HPSI Pump SI-2B Suction Isolation Valve
! HCV-2917, HPSI Pump SI-2C Suction Isolation Valve
! HCV-2927, HPSI Pump SI-2A Suction Isolation Valve
! HCV-2938, LPSI Pump SI-1B Discharge Valve
! HCV-2948, LPSI Pump SI-1A Discharge Valve
! HCV-2957, Containment Spray Pump SI-3A Suction Valve
! HCV-2958, Containment Spray Pump SI-3A Discharge Valve
! HCV-2967, Containment Spray Pump SI-3B Suction Valve
! HCV-2968, Containment Spray Pump SI-3B Discharge Valve
! HCV-2977, Containment Spray Pump SI-3C Suction Valve
! HCV-2978, Containment Spray Pump SI-3C Discharge Valve
- b. Turn the handwheel COUNTER-CLOCKWISE until the shaft sleeve contacts the valve yoke for the selected valve:
! HCV-2907
! HCV-2917
! HCV-2927
! HCV-2938
! HCV-2948
! HCV-2957
! HCV-2958
! HCV-2967
! HCV-2968
! HCV-2977
! HCV-2978 R12
FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 48 OF 69 C
Continuous Use Attachment 3 - Operation of Safety Injection Air Operated Valves PROCEDURE (continued) (T) INITIALS
- 12. c. Insert the Handjack locking pin in the valve stem for the selected valve:
! HCV-2907
! HCV-2917
! HCV-2927
! HCV-2938
! HCV-2948
! HCV-2957
! HCV-2958
! HCV-2967
! HCV-2968
! HCV-2977
! HCV-2978
- d. Contact the Control Room that the hand jack has been removed for the selected valve:
! HCV-2907
! HCV-2917
! HCV-2927
! HCV-2938
! HCV-2948
! HCV-2957
! HCV-2958
! HCV-2967
! HCV-2968
! HCV-2977
! HCV-2978
- 13. If Handjacking HCV-2937, or HCV-2947, complete the following for the selected valve:
- a. Ensure the selected valve is Closed:
! HCV-2937, LPSI Pump SI-1B Suction Valve
! HCV-2947, LPSI Pump SI-1A Suction Valve R12
FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 49 OF 69 C
Continuous Use Attachment 3 - Operation of Safety Injection Air Operated Valves PROCEDURE (continued) (T) INITIALS
- 13. b. Remove the Handjack Locking pin from the Valve stem for the selected valve:
! HCV-2937
! HCV-2947
- c. Turn the valve hand wheel CLOCKWISE until the shaft sleeve contacts the valve yoke on the selected valve:
! HCV-2937
! HCV-2947
- 14. If REMOVING Handjack from HCV-2937, or HCV-2947, perform the following:
- a. Ensure the selected valve has a CLOSED signal:
! HCV-2937, LPSI Pump SI-1B Suction Valve
! HCV-2947, LPSI Pump SI-1A Suction Valve
- b. Turn the handwheel COUNTER-CLOCKWISE until the shaft sleeve contacts the valve yoke for the selected valve:
! HCV-2937
! HCV-2947
- c. Insert the handjack locking pin in the valve stem for the selected valve:
! HCV-2937
! HCV-2947
- d. Contact the Control Room that the hand jack has been removed for the selected valve.
Completed by Date/Time /
R12
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-2 Rev 3 JPM
Title:
Energize 480 volt buses from 13.8 KV Location: Switchgear Rooms Approximate Time: 20 minutes Actual Time: _________________
Reference(s): K/A 000055 EA1.07 EOP/AOP Attachment 5, "Energizing 480 V Buses From 13.8 KV" Handout(s): EOP/AOP Attachment 5, "Energizing 480 V Buses From 13.8 KV" Time Critical: NO Alternate Path: NO JPM Prepared by: Jerry Koske Date: 3/25/09
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-2 Rev 3 Operators Name: _____________________ Employee # ______________
All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):
SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________
Reason, if unsatisfactory:
Tools & Equipment: None Safety Considerations: Be careful not to bump equipment in switchgear rooms Comments:
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-2 Rev 3 TASK The candidate energized 480V buses 1B3C and 1B3C-STANDARD: 4C from the 13.8 KV supply in accordance with EOP/AOP Attachment 5, "Energizing 480 V Buses From 13.8 KV."
INITIAL A station blackout has occurred.
CONDITIONS: Both 161 KV and 345 KV supplies to the station have been lost.
Both Diesel Generators have failed to start.
Energy Marketing reports that 13.8 KV power is available to the plant.
INITIATING CUE: You have been directed to energize 480 volt buses 1B3C, 1B3C-4C and 1B4C using EOP/AOP Attachment
- 5. The Control Room Operators have completed steps 1 and 2.
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-2 Rev 3 Critical Steps shown in gray STEP ELEMENT STANDARD 1 Trip ALL of the following 480 V East Switchgear room breakers : Trip breakers.
1B3C, "T1B-3C MAIN Verify breaker position SECONDARY FEED TO indicators display "OPEN."
480 VAC BUS 1B3C."
1B3C-2, "MCC-3C2 AUX BUILDING (CORR.
26)."
1B3C-7, "TURBINE BUILDING CRANE HE-3."
1B3C-6, "CONTAINMENT SPRAY PUMP SI-3A."
1B3C-3, "OUTDOOR LIGHTING XFMR T1C-3B."
1B3C-5, "MCC-3C3 SERVICE BLDG (3RD FLOOR)."
1B3C-8, "AIR COMPRESSORCA-1A FEED TO LOCAL CONTACTOR." [ SAT ] [ UNSAT ]
2 Trip ALL of the following 480 V breakers: East Switchgear room 1B3C-4C-2, "BREAKER Trip breakers.
UNIT MCC-3C4C-2 Verify breaker position TURBINE BLDG indicators display "OPEN."
(MEZZANINE)."
1B3C-4C-3, "BREAKER UNIT CONTAINMENT COOLING FAN VA-7C." [ SAT ] [ UNSAT ]
1B3C-4C-4, "BREAKER UNIT COMPONENT COOLING WATER PUMP AC-3C."
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-2 Rev 3 STEP ELEMENT STANDARD 3 Trip listed 1B4C 480 V West Switchgear room Breakers.
CUE: After candidate identifies location of bus 1B4C, "Another Operator will trip the breakers."
[ SAT ] [ UNSAT ]
4 Place ALL of the following East Upper Electrical breakers in "OFF" Penetration Room MCC-3C1-A01, "PCV-102-1 PZR POWER OPERATED RELIEF MCC breakers placed in OFF VALVE." position.
MCC-3C1-A2R, "AUX BLDG ROOF-DS, AUX BLDG ROOF STRESS TEST DISC SWITCH."
MCC-3C1-A3L, "MPP-58/EE-98 MOTOR PROTECTION PANEL TRANSFORMER."
MCC-3C1-A3R, HE DS/STRESS GALL-DS, ROOM 66 HOIST &
STRESS GALLERY TEST DISC SWITCHES.
MCC-3C1-A4L, "SPARE.
MCC-3C1-A4R, "EE-4Q INVERTER "C" EE-8K BYPASS TRANSFORMER."
MCC-3C1-A05, "TRANSFORMER T1B- [ SAT ] [ UNSAT ]
3C COOLING FANS."
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-2 Rev 3 STEP ELEMENT STANDARD 5 Energize bus 1B3C: CUE: After Candidate identifies the correct handle Obtain the circuit breaker at the AOP-06 cabinet, "You handle from the Shift Manager have obtained the circuit or the AOP-06 Cabinet. breaker handle."
[ SAT ] [ UNSAT ]
6 Close breaker 1B3C-4, East Switchgear room "EMERG. FEED TO BUS 1B3C Close breaker 1B3C-4 and FROM 13.8KV/480V XFMR verify breaker position T1B-3C-1." indicators display CLOSED.
[ SAT ] [ UNSAT ]
7 Check that Bus 1B3C is Checks indication on VG-energized. 1/1B3C Voltmeters T1B-3C Secondary Phase (1,2,3) (Line to GND) and amber lights for each phase.
CUE: Equal voltage indicated on all three phases and all three amber lights ON with equal intensity.
[ SAT ] [ UNSAT ]
8 Close BT-1B3C, "BUS TIE East Switchgear room 1B3C & 1B3C-4C NORMALLY Close breaker BT-1B3C and CLOSED." verify breaker position indicators display CLOSED.
[ SAT ] [ UNSAT ]
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-2 Rev 3 STEP ELEMENT STANDARD 9 Close BT-1B4C, "BUS TIE CUE: Another Operator will 1B4C & 1B3C-4C NORMALLY close breaker BT-1B4C, OPEN." place Battery Charger #3 in service and transfer DC control power.
Termination Criteria: 480 volt buses 1B3C and 1B3C-4C are energized from 13.8 KV.
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-2 Rev 3 INITIAL A station blackout has occurred.
CONDITIONS: Both 161 KV and 345 KV supplies to the station have been lost.
Both Diesel Generators have failed to start.
Energy Marketing reports that 13.8 KV power is available to the plant.
INITIATING CUE: You have been directed to energize 480 volt buses 1B3C, 1B3C-4C and 1B4C using EOP/AOP Attachment
- 5. The Control Room Operators have completed steps 1 and 2.
EOP/AOP ATTACHMENTS Page 17 of 168 Attachment 5 Energizing 480 V Buses From 13.8 KV INSTRUCTIONS CONTINGENCY ACTIONS
- 1. Trip BOTH of the following 4160 V breakers:
- 2. Place the following control switches in PULL-TO-LOCK:
- CA-1A, Air Compressor
- AC-3C, CCW pump
- SI-2B, HPSI Pump
- VA-3B, Containment Vent Fan
- SI-3A, CS Pump
- VA-7C, Containment Vent Fan R26
EOP/AOP ATTACHMENTS Page 18 of 168 Attachment 5 Energizing 480 V Buses From 13.8 KV INSTRUCTIONS CONTINGENCY ACTIONS
- 3. Trip ALL of the following 480 V breakers (East Switchgear Room):
- 1B3C, "T1B-3C MAIN SECONDARY FEED TO 480 VAC BUS 1B3C"
- 1B3C-2, "MCC-3C2 AUX BUILDING (CORR. 26)"
- 1B3C-7, "TURBINE BUILDING CRANE HE-3"
- 1B3C-6, "CONTAINMENT SPRAY PUMP SI-3A"
- 1B3C-5, "MCC-3C3 SERVICE BLDG (3RD FLOOR)"
EOP/AOP ATTACHMENTS Page 19 of 168 Attachment 5 Energizing 480 V Buses From 13.8 KV INSTRUCTIONS CONTINGENCY ACTIONS
- 4. Trip ALL of the following 480 V breakers (East Switchgear Room):
- 1B3C-4C-2, "BREAKER UNIT MCC-3C4C-2 TURBINE BLDG (MEZZANINE)"
- 1B3C-4C-3, "BREAKER UNIT CONTAINMENT COOLING FAN VA-7C"
- 1B3C-4C-4, "BREAKER UNIT COMPONENT COOLING WATER PUMP AC-3C" R26
EOP/AOP ATTACHMENTS Page 20 of 168 Attachment 5 Energizing 480 V Buses From 13.8 KV INSTRUCTIONS CONTINGENCY ACTIONS
- 5. Trip ALL of the following 480 V breakers (West Switchgear Room):
- 1B4C, "T1B-4C MAIN SECONDARY FEED TO 480 VAC BUS 1B4C"
- 1B4C-8, "CONTAINMENT COOLING & FILTER FAN VA-3B"
- 1B4C-3, "MCC-4C2 AUX BLDG (CORR 4)"
- 1B4C-4, "MCC-4C3 TURB BLDG (MEZZANINE)"
- 1B4C-7, "MCC-4C4 INTAKE STRUCTURE"
- 1B4C-5, "HI PRESS SAFETY INJ.
PUMP SI-2B"
- 1B4C-2, "MCC-4C1 ELECT PENET.
AREA (RM 57W)"
- 1B4C-1, "MCC-4C5 MOTOR CONTROL CENTER TURBINE BUILDING" R26
EOP/AOP ATTACHMENTS Page 21 of 168 Attachment 5 Energizing 480 V Buses From 13.8 KV INSTRUCTIONS CONTINGENCY ACTIONS
- 6. Place ALL of the following breakers in "OFF" (East Upper Electrical Penetration Room):
- MCC-3C1-A01, "PCV-102-1 PZR POWER OPERATED RELIEF VALVE"
- MCC-3C1-A2R, "AUX BLDG ROOF-DS, AUX BLDG ROOF STRESS TEST DISC SWITCH"
- MCC-3C1-A3L, "MPP-58/EE-98 MOTOR PROTECTION PANEL TRANSFORMER"
- MCC-3C1-A3R, HE-12-DS/STRESS GALL-DS, ROOM 66 HOIST & STRESS GALLERY TEST DISC SWITCHES
- MCC-3C1-A4L, "SPARE
- MCC-3C1-A4R, "EE-4Q INVERTER "C" EE-8K BYPASS TRANSFORMER"
- MCC-3C1-A05, "TRANSFORMER T1B-3C COOLING FANS" R26
EOP/AOP ATTACHMENTS Page 22 of 168 Attachment 5 Energizing 480 V Buses From 13.8 KV INSTRUCTIONS CONTINGENCY ACTIONS
- 7. Energize Bus 1B3C by performing the following steps:
- a. Obtain the circuit breaker handle from the Shift Manager or the AOP-06 Cabinet.
- b. Close breaker 1B3C-4, "EMERG.
FEED TO BUS 1B3C FROM 13.8KV/480V XFMR T1B-3C-1" (East Switchgear Room).
- 8. Check that Bus 1B3C is energized.
- 9. Close BOTH of the following 480 V breakers:
- BT-1B3C, "BUS TIE 1B3C &
1B3C-4C NORMALLY CLOSED" (East Switchgear Room)
- BT-1B4C, "BUS TIE 1B4C &
1B3C-4C NORMALLY OPEN" (West Switchgear Room)
R26
EOP/AOP ATTACHMENTS Page 23 of 168 Attachment 5 Energizing 480 V Buses From 13.8 KV INSTRUCTIONS CONTINGENCY ACTIONS
- 10. Place Battery Charger 3 in service by performing the following steps:
- a. Ensure breaker 1B3C-1, "MCC-3C1 ELECT PENET.
AREA (RM 57E)", is closed (East Switchgear Room).
- b. Open BOTH Battery Charger 3 breakers (West Switchgear Room):
- EE-8E-CB1, BATT CHARGER 3 (EE-8E) AC INPUT BREAKER
- EE-8E-CB2, BATT CHARGER 3 (EE-8E)DC OUTPUT BREAKER
- c. Place the "VOLTAGE SELECTOR" switch in "FLOAT" (EE-8E).
(continue)
R26
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-3 Rev 2 JPM
Title:
Local Emergency Manual Start of the Diesel Fire Pump Location: Intake Structure Approximate Time: 10 minutes Actual Time: _________________
Reference(s): K/A# 086000 A2.04 OI-FP-1, Attachment 3, "FP-1B, DIESEL FIRE PUMP AND FP-6B DIESEL FIRE PUMP STRAINER OPERATION."
Handout(s): OI-FP-1, Attachment 3, "FP-1B, DIESEL FIRE PUMP AND FP-6B DIESEL FIRE PUMP STRAINER OPERATION."
Time Critical: NO Alternate Path: YES JPM Prepared by: Jerry Koske Date: 3/05/09 Page 1 of 7
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-3 Rev 2 JPM
Title:
Local Emergency Manual Start of the Diesel Fire Pump Operators Name: _____________________ Employee # ______________
All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):
SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________
Reason, if unsatisfactory:
Tools & Equipment: None Safety Considerations: Potential tripping hazards. Do Not operate any controls.
Comments: Alternate Path Page 2 of 7
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-3 Rev 2 JPM
Title:
Local Emergency Manual Start of the Diesel Fire Pump TASK The Candidate performed a local emergency start of STANDARD: Diesel Fire Pump, FP-1B. The candidate manually opened the Fuel Oil Solenoid Valve and the Cooling Water Bypass valve and started the pump using a Starter Contactor because Manual Start number 1 and 2 were both unsuccessful.
INITIAL The Electric Fire Pump, FP-1A, is out of service.
CONDITIONS: Transformer deluge has activated due to a fire.
The Diesel Fire Pump, FP-1B, did not start automatically.
INITIATING CUE: You are directed to perform a local emergency manual start of the diesel fire pump in accordance with OI-FP-1, Attachment 3, step 3.
Page 3 of 7
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-3 Rev 2 JPM
Title:
Local Emergency Manual Start of the Diesel Fire Pump Critical Steps shown in gray STEP ELEMENT STANDARD Note to Examiner: Provide candidate with a copy of OI-FP-1, Attachment 3.
1 Ensure the following are on: AI-183 AI-183-CB1, Fire Pump FP-1B Batt 1 Switch. Battery 1 is ON.
AI-183-CB2, Fire Pump FP-1B Batt 2 Switch. Battery 2 is ON.
[ SAT ] [ UNSAT ]
2 Place HC/FP-1B-MS, Diesel AI-183 Fire Pump FP-1B Local Control Switch, to Manual 1. Select Manual #1.
[ SAT ] [ UNSAT ]
3 Press HC/FP-1B-1, "Fire Pump AI-183 FP-1B Crank 1 Start Button.
Push Crank 1 Start Button.
[ SAT ] [ UNSAT ]
CUE: Engine did not turn over or start 4 Place HC/FP-1B-MS, Diesel AI-183 Fire Pump FP-1B Local Control Switch, to Manual 2. Select Manual #2.
[ SAT ] [ UNSAT ]
Page 4 of 7
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-3 Rev 2 JPM
Title:
Local Emergency Manual Start of the Diesel Fire Pump STEP ELEMENT STANDARD 5 Press HC/FP-1B-1, "Fire Pump AI-183 FP-1B Crank 2 Start Button.
Push Crank 2 Start Button.
[ SAT ] [ UNSAT ]
CUE: Engine did not turn over or start 6 Open FO-169, Fuel Oil South side of Engine Solenoid Valve.
Turn Knob clockwise to full-in position.
[ SAT ] [ UNSAT ]
7 Open FP-161, Pressure control South side of Engine valve FP-162 bypass valve.
Cooling water bypass valve to OPEN.
[ SAT ] [ UNSAT ]
8 Read Caution Read Caution on page 24
[ SAT ] [ UNSAT ]
9 Engage the starter using either North side of Engine of the two starter contactors.
Raise lever knob on either:
YS/FP-1B-1.
YS/FP-1B-1.
CUE: Engine has started and is running.
Release lever.
[ SAT ] [ UNSAT ]
Page 5 of 7
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-3 Rev 2 JPM
Title:
Local Emergency Manual Start of the Diesel Fire Pump Termination Criteria: Diesel Fire Pump has been started Page 6 of 7
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-3 Rev 2 INITIAL The Electric Fire Pump, FP-1A, is out of service.
CONDITIONS: Transformer deluge has activated due to a fire.
The Diesel Fire Pump, FP-1B, did not start automatically.
INITIATING CUE: You are directed to perform a local emergency manual start of the diesel fire pump in accordance with OI-FP-1, Attachment 3, step 3.
Page 7 of 7
FORT CALHOUN STATION OI-FP-1 OPERATING INSTRUCTION PAGE 18 OF 186 C
Continuous Use Attachment 3 - FP-1B, Diesel Fire Pump and FP-6B Diesel Fire Pump Strainer Operation PREREQUISITES (T) INITIALS
- 1. Procedure Revision Verification Revision No. 68 Date: 3/31/09 JEK PROCEDURE NOTE Prior to declaring FP-1B inoperable the Fire Protection System Engineer or designee shall analyze Room 19 Fire Protection System per SO-G-58 to minimize risk to safety related cable trays.
- 1. IF removing FP-1B, Diesel Fire Pump, from service, THEN complete the following:
- a. Notify the Control Room this system is being removed from service.
- b. Ensure the requirements of SO-G-103 are met and log into any required Action Statements in the Control Room Log.
Shift Mgr
- c. A Fire Impairment has been issued for removing FP-1B from service.
NOTE The following will alarm when FP-1B is placed in PULL OUT:
! ENGINE DRIVEN FIRE PUMP OFF NORM ENGINE FAIL OR DC POWER FAIL (CB-10,11/A13, B-3L)
- d. Place FP-1B control switch in PULL-OUT (CB-10/11).
- e. Place HC/FP-1B-MS, Diesel Fire Pump FP-1B Local Control Switch, in OFF (AI-183).
R68
FORT CALHOUN STATION OI-FP-1 OPERATING INSTRUCTION PAGE 19 OF 186 C
Continuous Use Attachment 3 - FP-1B, Diesel Fire Pump and FP-6B Diesel Fire Pump Strainer Operation PROCEDURE (continued) (T) INITIALS
CAUTION A leak greater than the makeup of the Jockey Pump will cause an inadvertent start of FP-1A when draining FP-1B header.
- 2. IF returning Diesel Fire Pump FP-1B to service, THEN complete the following:
CAUTION Security must be present at the Screen F enclosure and remain there until Sluice Gate CW-14F is closed or CW-1C is placed back in service.
- a. Ensure one of the following Suction Well flow paths is aligned as follows
! CW-14E, Circ Water Pump CW-1C Screen Sluice Gate, is open
! CW-14F, Circ Water Pump CW-1C Screen Sluice Gate, is open
! CW-16B, Circ Water Pumps interconnection Sluice Gate and CW-14C, Traveling Screen Sluice Gate, are open
! CW-16B, Circ Water Pumps interconnection Sluice Gate and CW-14D, Traveling Screen Sluice Gate, are open Shift Mgr
R68
FORT CALHOUN STATION OI-FP-1 OPERATING INSTRUCTION PAGE 20 OF 186 C
Continuous Use Attachment 3 - FP-1B, Diesel Fire Pump and FP-6B Diesel Fire Pump Strainer Operation PROCEDURE (continued) (T) INITIALS CAUTION If FP-1A control switch is taken to pull-to-lock to prevent inadvertent starting a Dedicated Operator must be stationed at the control switch (Ref. SO-G-103)
- 2. c. If desired by the Shift Mgr/CRS to prevent an inadvertent start of FP-1A:
- 1) Station a Dedicated Operator at the FP-1A control switch with instructions to immediately return the control switch to AFTER STOP should water be needed for the Fire Protection System. This would be indicated by receipt of a fire suppression system flow alarm, initiation of manual fire suppression activities using fire hose stations or confirmation of a fire in a protected area.
Dedicated Operator NOTE The following will alarm when FP-1A is placed in PULL OUT:
! MTR DRIVEN FIRE PUMP OFF NORMAL OVERLOAD TRIP (CB-10,11/A13, B-4U)
- 2) Place FP-1A control switch (CB-10/11) in pullout.
CAUTION Slowly throttling open FP-502 while maintaining Fire Main pressure greater than 116 psig will prevent inadvertent starting of Electric Fire Pump FP-1A on low pressure.
- d. IF maintenance was performed on FP-6B, Diesel Driven Fire Pump FP-1B Strainer, THEN ensure maintenance personnel are available and standing by prior to pressurization.
R68
FORT CALHOUN STATION OI-FP-1 OPERATING INSTRUCTION PAGE 21 OF 186 C
Continuous Use Attachment 3 - FP-1B, Diesel Fire Pump and FP-6B Diesel Fire Pump Strainer Operation PROCEDURE (continued) (T) INITIALS
- 2. e. Slowly throttle open FP-502, Fire Pump Disch Valve FP-153 Bypass Valve, to pressurize line to FP-1B.
- f. Verify Fire Main pressure is greater than 116 psig.
- h. Close FP-502.
- i. Return FP-1A to auto if required by:
NOTE The following alarm will reset when FP-1A is placed in AFTER STOP:
! MTR DRIVEN FIRE PUMP OFF NORMAL OVERLOAD TRIP (CB-10,11/A13, B-4U)
- 1) Place FP-1A control switch (CB-10/11) in AFTER STOP.
- 2) Secure the Dedicated Operator for FP-1A.
- j. Place FP-1B control switch in AFTER-STOP (CB-10/11).
R68
FORT CALHOUN STATION OI-FP-1 OPERATING INSTRUCTION PAGE 22 OF 186 C
Continuous Use Attachment 3 - FP-1B, Diesel Fire Pump and FP-6B Diesel Fire Pump Strainer Operation PROCEDURE (continued) (T) INITIALS NOTE The following alarm will reset when HC/FP-1B-MS is placed in AUTO:
! ENGINE DRIVEN FIRE PUMP OFF NORM ENGINE FAIL OR DC POWER FAIL (CB-10/11/A13, B-3L)
- 2. k. Place HC/FP-1B-MS, Diesel Fire Pump FP-1B Local Control Switch, to AUTO (AI-183).
- l. Ensure minimum Level of 75% indicated level of diesel fuel in FO-27, Diesel Fire Pump FP-1B Fuel Oil Storage Tank, by completing the following:
- 1) Unlock and open FO-231, Diesel Tank FO-27 Sightglass Root Valve.
- 2) Allow level in the sightglass to settle at its equilibrium point.
- m. Record FO-27, Diesel Fire Pump FP-1B Fuel Oil Storage Tank level:
Level (33" min.)
- 1) Close and Lock FO-231.
- n. Independently verify the following valve positions: [AR 06498]
! FO-231, Diesel Tank FO-27 Sightglass Root Valve, is Locked Closed
! FP-156, Diesel Fire Pump Strainer FP-6B Drain Valve, is closed
! FP-153, Diesel Fire Pump FP-1B Discharge to Main Headers, is Locked Open
! FP-502, Fire Pump Disch Valve FP-153 Bypass Valve, is closed
! FP-1B CS, Diesel Fire Pump Control Switch, is in AFTER STOP (CB-10/11)
! HC/FP-1B-MS, Diesel Fire Pump FP-1B Local Control Switch, is in AUTO (AI-183)
Ind Verif
- o. Notify Control Room Operator the system has been returned to service.
[AR 06498]
R68
FORT CALHOUN STATION OI-FP-1 OPERATING INSTRUCTION PAGE 23 OF 186 C
Continuous Use Attachment 3 - FP-1B, Diesel Fire Pump and FP-6B Diesel Fire Pump Strainer Operation PROCEDURE (continued) (T) INITIALS
- 2. p. Exit from any Action Statements entered in the Control Room Log.
- q. Clear the Fire Impairment issued for FP-1B.
- 3. IF Local Emergency Manual Starting of the Diesel Fire Pump (AI-183) is required, THEN complete the following:
- a. Ensure the following are ON:
! AI-183-CB1, Fire Pump FP-1B Batt 1 Switch
! AI-183-CB2, Fire Pump FP-1B Batt 2 Switch
- b. Place HC/FP-1B-MS, Diesel Fire Pump FP-1B Local Control Switch, to MANUAL 1.
- c. Press HC/FP-1B-1, Fire Pump FP-1B Crank 1 Start Button.
- d. IF Engine does not start, THEN perform the following:
- 1) Place HC/FP-1B-MS, Diesel Fire Pump FP-1B Local Control Switch, to MANUAL 2.
- 2) Press HC/FP-1B-2, Fire Pump FP-1B Crank 2 Start Button.
- e. IF the Engine has not started, THEN perform the following:
- 1) Open FO-169, Diesel Fire Pump FP-1B Fuel Oil Solenoid Valve, by turning the knob in (clockwise).
R68
FORT CALHOUN STATION OI-FP-1 OPERATING INSTRUCTION PAGE 24 OF 186 C
Continuous Use Attachment 3 - FP-1B, Diesel Fire Pump and FP-6B Diesel Fire Pump Strainer Operation PROCEDURE (continued) (T) INITIALS CAUTION As soon as the engine is running in Step 3), release the lever.
3.e 3) Engage the starter by raising the lever knob on either of the two starter contactors:
! YS/FP-1B-1, Diesel Fire Pump FP-1B #1 Starter Contactor
! YS/FP-1B-2, Diesel Fire Pump FP-1B #2 Starter Contactor
- 4. IF securing from Local Emergency Manual Starting of the Diesel Fire Pump (AI-183),
THEN complete the following:
- a. Place HC/FP-1B-MS, Diesel Fire Pump FP-1B Local Control Switch, to OFF.
- b. Ensure FO-169, Diesel Fire Pump FP-1B Fuel Oil Solenoid Valve, is closed (by turning the knob out counter-clockwise).
- d. Independently verify the following valve positions: [AR 06498]
! FP-161, Pressure Control Valve FP-162 Bypass Valve, is closed
! FO-169, Diesel Fire Pump FP-1B Fuel Oil Solenoid Valve (by turning the knob out counter-clockwise)
Ind Verif R68
FORT CALHOUN STATION OI-FP-1 OPERATING INSTRUCTION PAGE 25 OF 186 C
Continuous Use Attachment 3 - FP-1B, Diesel Fire Pump and FP-6B Diesel Fire Pump Strainer Operation PROCEDURE (continued) (T) INITIALS
- 5. IF placing FP-6B, Diesel Fire Pump FP-1B Strainer, in AUTO or MANUAL, THEN complete one of the following:
- a. IF placing FP-6B, Diesel Fire Pump FP-1B Strainer, in AUTO, THEN place HC/FP-6B, Fire Pump Strainer FP-6B Mode Selector Switch, to AUTO.
CAUTION If the Fire Pumps are in AUTO-STANDBY and FP-1B is not operating, placing FP-6B control box toggle switch in MANUAL will depressurize the Fire Main and start both Fire Pumps.
- b. IF placing FP-6B, Diesel Fire Pump FP-1B Strainer, in MANUAL, THEN place HC/FP-6B, Fire Pump Strainer FP-6B Mode Selector Switch, to MANUAL.
Completed by Date/Time /
Reviewed by Shift Manager [AR 06498]
R68
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-1 Rev 2 JPM
Title:
Control Element Assembly Movement Test Location: Simulator Approximate Time: 18 minutes Actual Time: _________________
Reference(s): K/A: 001000 A4.03 OP-ST-CEA-0003, "CONTROL ELEMENT ASSEMBLY (CEA)
PARTIAL MOVEMENT TEST" OI-RR-1, "REACTOR REGULATING SYSTEM NORMAL OPERATION" Handout(s): OP-ST-CEA-0003, "CONTROL ELEMENT ASSEMBLY (CEA)
PARTIAL MOVEMENT TEST" Time Critical: NO Alternate Path: YES JPM Prepared by: Jerry Koske Date: 3/3/09 Page 1 of 7
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-1 Rev 2 JPM
Title:
Control Element Assembly Movement Test Operators Name: _____________________ Employee # ______________
All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):
SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________
Reason, if unsatisfactory:
Tools & Equipment: None Safety Considerations:
Comments: Alternate Path Page 2 of 7
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-1 Rev 2 JPM
Title:
Control Element Assembly Movement Test TASK The candidate performed the CEA partial movement STANDARD: check for group 3 CEAs using OP-ST-CEA-003. While inserting one of the CEAs, the CEA continued to insert after releasing the IN-OUT-HOLD switch. The candidate stopped the uncontrolled motion by placing the Mode Selector Switch in OFF.
INITIAL The plant is operating at full power with all CEAs fully CONDITIONS: withdrawn.
INITIATING CUE: You have been directed to perform the CEA Partial Movement Check for group 3 CEAs (2, 3, 4 and 5) using OP-ST-CEA-0003.
All prerequisites have been met.
Page 3 of 7
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-1 Rev 2 JPM
Title:
Control Element Assembly Movement Test Critical Steps shown in gray STEP ELEMENT STANDARD 1 Record the initial position of Records position of CEAs each group 3 CEA. 2,3,4 and 5 as 128 inches on OP-ST-CEA-003, attachment 1.
[ SAT ] [ UNSAT ]
2 Rotate the Mode selector CB-4 switch to Manual Individual Places Mode Selector Switch position. (M/M) to the Manual Individual Position (M/I).
[ SAT ] [ UNSAT ]
3 Rotate the Group Selector CB-4 Switch (M/G) to the group Rotate Group Selector Switch containing the CEA to be (M/G) to the "Group 3" moved. position.
[ SAT ] [ UNSAT ]
4 Verify on the DCS display CB-4 CEA_ALL that the group button Ensure CEA-ALL is displayed is DARK GREY. and that Group 3 is DARK GREY.
[ SAT ] [ UNSAT ]
5 Rotate the Rod Selector Switch CB-4 to the CEA to be moved. Rotate Rod Selector Switch to CEA position.
[ SAT ] [ UNSAT ]
Page 4 of 7
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-1 Rev 2 JPM
Title:
Control Element Assembly Movement Test STEP ELEMENT STANDARD 6 Insert CEA a minimum of 6 CB-4 inches then return to normal Push IN-OUT-HOLD switch in position. until CEA position is 122 inches or less. Then Pull IN-OUT-HOLD switch until CEA is fully withdrawn.
[ SAT ] [ UNSAT ]
7 Record Information on Note to Examiner: This step Attachment 1. may be completed after all CEAs have been exercised.
Record inserted to and returned to position for CEA on Attachment 1.
[ SAT ] [ UNSAT ]
8 Rotate the Rod Selector Switch CB-4 to the CEA to be moved. Rotate Rod Selector Switch to next CEA position.
[ SAT ] [ UNSAT ]
9 Insert CEA a minimum of 6 CB-4 inches then return to normal Push IN-OUT-HOLD switch in position. until CEA position is 122 inches or less.
[ SAT ] [ UNSAT ]
NOTE: CEA will continue to insert Page 5 of 7
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-1 Rev 2 JPM
Title:
Control Element Assembly Movement Test STEP ELEMENT STANDARD 10 Immediately place Mode CB-4 Selector Switch in OFF. Immediately return Mode Selector Switch to OFF position before the CEA has been inserted to less than 108 inches. Verify CEA motion has stopped.
[ SAT ] [ UNSAT ]
11 Notify Shift Manager of failure. Notified Shift Manager of uncontrolled CEA motion.
[ SAT ] [ UNSAT ]
12 Verify position of all CEAs. CB-4 Verifies position off all CEAs using Primary and Secondary CEA Position Indication.
[ SAT ] [ UNSAT ]
CUE: The Shift Manager has directed that this surveillance test be terminated.
Termination Criteria: The Mode Selector Switch is in the OFF position and the test has been terminated by the Shift Manager.
Page 6 of 7
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-1 Rev 2 INITIAL The plant is operating at full power with all CEAs fully CONDITIONS: withdrawn.
INITIATING CUE: You have been directed to perform the CEA Partial Movement Check for group 3 CEAs (2, 3, 4 and 5) using OP-ST-CEA-0003.
All prerequisites have been met.
Page 7 of 7
PAGE 1 OF 9 Fort Calhoun Station Unit No. 1 OP-ST-CEA-0003 SURVEILLANCE TEST CONTROL ELEMENT ASSEMBLY (CEA) PARTIAL MOVEMENT CHECK Change No. EC 34712 Reason for Change These changes are intended to facilitate use of the GARDEL core monitoring program and to allow operator, STA, and RE to use the program for the performance of various core monitoring and testing functions.
Requestor T. Heng Preparer T. Heng Issue Date 06-06-08 3:00 pm R13
FORT CALHOUN STATION OP-ST-CEA-0003 SURVEILLANCE TEST PAGE 2 OF 9 CONTROL ELEMENT ASSEMBLY (CEA) PARTIAL MOVEMENT CHECK SAFETY RELATED
- 1. PURPOSE To satisfy, at least quarterly when the Reactor is critical, the requirements of Technical Specification 3.2, Table 3-5, Item 2.
- 2. REFERENCES/COMMITMENT DOCUMENTS 2.1 Technical Specifications:
- 3.2, Table 3-5, Minimum Frequencies for Equipment Tests
- 2.10.2 (4), Full Length CEA Position During Power Operation
- 2.10.2 (6), Shutdown CEA Insertion Limit During Power Operation
- 2.10.2 (7), Regulating CEA Insertion Limits During Hot Standby and Power Operation
- 2.15, Table 2-5, Instrumentation Operating Requirements for Other Safety Feature Functions 2.2 USAR, Section 7 2.3 SO-G-23, Surveillance Test Program 2.4 Ongoing Commitment Documents
- AR 04922, LIC-87-0013
- AR 08779, LIC-88-0765 (LER-88-018)
- AR 14801, LIC-93-0294 (LER-93-016)
- 3. DEFINITIONS None
- 4. EQUIPMENT LIST None
- 5. PRECAUTIONS AND LIMITATIONS 5.1 All anomalies and deficiencies shall be reported immediately to the Shift Manager and noted in the Comment Sheet. An immediate check shall be made to verify Limiting Conditions for Operation, per Technical Specifications, have not been exceeded.
R13
FORT CALHOUN STATION OP-ST-CEA-0003 SURVEILLANCE TEST PAGE 3 OF 9 5.2 Manipulation of all controls as defined in 10CFR55 shall be done by, or under the direct supervision of, a NRC licensed operator.
5.3 Only one method of positive reactivity addition shall be used at any one time.
5.4 During all rod motion, nuclear instrumentation and RCS temperature shall be observed for response.
5.5 Be alert for any abnormal noise or indications when CEDMs are in operation.
5.6 Power Dependent Insertion Limits shall not be violated by more than one (1) CEA at a time during this test.
5.7 Shutdown CEAs shall not be inserted below the exercise limit.
5.8 Each CEA shall be returned to its pretest position prior to testing other CEAs.
5.9 CEAs within a Group should be kept within two (2) inches of each other per OI-RR-1, unless specifically required otherwise by this procedure.
5.10 The Reactor shall not be placed in the Automatic mode.
5.11 No maintenance shall be conducted within this Surveillance Test other than that specifically directed by this procedure.
5.12 Any time the Mode Selector Switch is in any position other than OFF, all available rod position indications shall be monitored, Synchros, SCEAPIS, ERF (page 302), and Core Mimic. [AR 14801]
5.13 If a CEA position abnormality occurs, verify the position of all CEAs. [AR 14801]
5.14 The following annunciators may Alarm during the performance of this Surveillance test:
- REGULATING GROUP WITHDRAWAL PROHIBIT (CB-4, A8, A-1L)
- PDIL GR 1 COMPUTER (CB-4, A8, A-3U)
- PPDIL GR 1 COMPUTER (CB-4, A8, A-4U)
- PDIL GR 2 COMPUTER (CB-4, A8, A-3L)
- PPDIL GR 2 COMPUTER (CB-4, A8, A-4L)
- ROD DRIVE POWER INTERRUPT (CB-4, A8, A-5U)
- ROD POSITION DEVIATION LOW LIMIT (CB-4, A8, B-1U)
- ROD POSITION DEVIATION LOW-LOW LIMIT (CB-4, A8, B-1L)
- PDIL GR 3 COMPUTER (CB-4, A8, B-3U)
- PPDIL GR 3 COMPUTER (CB-4, A8, B-4U)
- VLPM ALARM OR TROUBLE (CB-1,2,3, A6, D-3)
R13
FORT CALHOUN STATION OP-ST-CEA-0003 SURVEILLANCE TEST PAGE 4 OF 9 5.15 The following DCS alarms may occur during the performance of this Surveillance Test:
- ROD BLOCK
- PPDIL
- PDIL
- ISH
- 6. PREREQUISITES INITIALS/DATE 6.1 Procedure Revision Verification:
Revision No. 13 JEK / 3/31/09 6.2 Reactor is critical. JEK / 3/31/09 6.3 No other test is in progress which could potentially affect this test, or if JEK 3/31/09 this test were performed, could have an effect on that test. /
6.4 A prejob briefing has been conducted prior to the start of this test. JEK / 3/31/09 6.5 Primary Synchro CEA Position Indicating System is operable.
[AR 14801] JEK / 3/31/09 6.6 Shift Manager authorizes performance of this test:
Shift Manager SHIFT MANAGER Date/Time 3/31/09 / 0730
- 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 N/A conducted prior to the continuation of this test. /
CAUTION [AR 04922]
When the Reactor is critical, this Surveillance Test must be performed within the specified Technical Specification time interval regardless of rod configuration or use.
7.2 IF not in an All-Rods-Out configuration, THEN contact the Reactor Engineer prior to commencing this test for guidance to ensure the requirements of Technical Specification 3.2, Table 3-5, Item 2 are met. [AR 04922]
N/A
[AR 08779]
R13
FORT CALHOUN STATION OP-ST-CEA-0003 SURVEILLANCE TEST PAGE 5 OF 9 7.3 Record Initial Position of all CEAs on Attachment 1.
7.4 Rotate the Mode Selector Switch (M/M) to the Manual Individual (M/I) position.
7.5 Rotate the Group Selector Switch (M/G) to the Group containing the CEA to be moved.
7.6 If available, verify on SCEAPIS (DCS) display CEA_ALL that the group button is DARK GREY for the group selected.
7.7 Rotate the Rod Selector Switch to the CEA to be moved.
NOTE: If Group 4 CEAs are being used for ASI control, movement of 6 inches in a single direction may be credited. The returned to position may not necessarily be the initial position. Note the time of Group 4 movement for ASI control on the Comment Sheet if applicable.
7.8 Insert or withdraw the CEA, as applicable, a minimum of six (6) inches, THEN return the CEA to its Initial Position.
NOTE: Step 7.9 may be completed after all CEAs within a Group have been exercised, after all CEAs have been exercised, OR after exercising each CEA.
7.9 Record Inserted/Withdrawn To AND Return To information on Test Data Sheet, THEN initial Attachment 1.
7.10 Repeat Steps 7.5 through 7.9 for all CEAs listed on Attachment 1.
7.11 Rotate Mode Selector Switch (M/M) to the OFF position.
7.12 Independently verify each CEA returned to its initial position listed on Attachment 1.
Ind Verif Completed By: Date/Time /
- 8. RESTORATION 8.1 Shift Manager notified this test is completed:
Shift Manager Date/Time /
- 9. ACCEPTANCE CRITERIA 9.1 All CEAs have been moved a minimum of six (6) inches.
R13
FORT CALHOUN STATION OP-ST-CEA-0003 SURVEILLANCE TEST PAGE 6 OF 9
- 10. TEST RECORD 10.1 This entire procedure.
- 11. REVIEW NOTE: The Reactor Engineer shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of the completion of this test of any unexpected results.
11.1 Test data shall be evaluated by the STA and reviewed by the Shift Manager for acceptability within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of completion of this test.
Evaluated by Date/Time /
STA Reviewed by Date/Time /
Shift Manager R13
FORT CALHOUN STATION OP-ST-CEA-0003 SURVEILLANCE TEST PAGE 7 OF 9 Attachment 1 - CEA Partial Movement Check Test Data Sheet Initial Inserted/ Ind Verif CEA Returned to Position Withdrawn Initials Initials Remarks No. (Inches)
(inches) (inches) 30 31 32 33 34 35 36 37 14 15 16 17 6
8 10 12 22 23 24 25 26 27 28 29 2
R13
FORT CALHOUN STATION OP-ST-CEA-0003 SURVEILLANCE TEST PAGE 8 OF 9 Attachment 1 - CEA Partial Movement Check Test Data Sheet Initial Inserted/ Ind Verif CEA Returned to Position Withdrawn Initials Initials Remarks No. (Inches)
(inches) (inches) 3 4
5 38 39 40 41 1
Completed By: Date/Time /
R13
FORT CALHOUN STATION OP-ST-CEA-0003 SURVEILLANCE TEST PAGE 9 OF 9 Comment Sheet R13
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-2 Rev 3 JPM
Title:
Establish Charging Flow via the HPSI Header Location: Simulator Approximate Time: 12 minutes Actual Time: _________________
Reference(s): K/A# 004000 A4.08 AOP-33, Attachment B, "CHARGING FROM THE HPSI HEADER."
Handout(s): AOP-33, Attachment B, "CHARGING FROM THE HPSI HEADER."
Time Critical: NO Alternate Path: NO JPM Prepared by: Jerry Koske Date: 3/23/09 Page 1 of 7
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-2 Rev 3 JPM
Title:
Establish Charging Flow via the HPSI Header Operators Name: _____________________ Employee # ______________
All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):
SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________
Reason, if unsatisfactory:
Tools & Equipment: None Safety Considerations:
Comments:
Page 2 of 7
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-2 Rev 3 JPM
Title:
Establish Charging Flow via the HPSI Header TASK The candidate established Charging flow to the RCS STANDARD: using the Loop 2A High Pressure Safety Injection (HPSI) header following the identification of a leak in the charging line.
INITIAL The plant is operating at full power. AOP-33 has been CONDITIONS: entered due to a leak in the charging header. Charging and letdown have been isolated and the leak has stopped.
INITIATING CUE: The CRS has directed you to reestablish charging pump flow via the HPSI header using HPSI loop 2A injection valve, HCV-318, per AOP-33, Attachment B.
Page 3 of 7
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-2 Rev 3 JPM
Title:
Establish Charging Flow via the HPSI Header Critical Steps shown in gray STEP ELEMENT STANDARD 1 Close CH-194, "CHARGING Direct EONA to close CH-194.
PUMPS CH-1A/B/C DISCHARGE HEADER [ SAT ] [ UNSAT ]
CONTAINMENT OUTBOARD ISOLATION VALVE" (Room CUE: EONA reports that CH-13). 194 is closed.
2 Open HCV-308, Charging CB-1,2,3 Pump HPSI Header Isolation Hold HCV-308 Control Switch Valve. in OPEN until GREEN light goes OFF. Then Release and allow it to return to NORM.
Verify RED light ON and GREEN light OFF.
[ SAT ] [ UNSAT ]
3 Ensure HCV-2987, HPSI AI-30A Header Isolation Valve, is RED light is ON and GREEN open. light is OFF.
[ SAT ] [ UNSAT ]
4 Ensure HCV-307, HPSI Header AI-30B Isolation Valve, is open. RED light ON.
GREEN light OFF.
[ SAT ] [ UNSAT ]
5 Ensure HCV-305, SI-2A and AI-30B SI-2C Discharge Cross- RED light ON.
Connect Valve, is open. GREEN light OFF.
[ SAT ] [ UNSAT ]
Page 4 of 7
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-2 Rev 3 JPM
Title:
Establish Charging Flow via the HPSI Header STEP ELEMENT STANDARD 6 Ensure HCV-304, SI-2B and AI-30A SI-2C Discharge Cross- RED light ON.
Connect Valve, is open. GREEN light OFF.
[ SAT ] [ UNSAT ]
7 Ensure HCV-306, HPSI Header AI-30A Isolation Valve, is open. RED light ON.
GREEN light OFF.
[ SAT ] [ UNSAT ]
8 Close the SI Tank Leakage AI-30A Cooler Pressure Control Valves Place Control Switch in on the loop in which the HPSI MANUAL valve(s) will be opened, If required, adjust PCV-2949 PCV-2949. Controller such that needle indicates 100% (full right).
GREEN light ON.
RED light OFF.
[ SAT ] [ UNSAT ]
9 Open HCV-318 (Loop 2A). AI-30B HCV-318 Control Switch to OPEN. RED light ON, GREEN light OFF.
(Note: may also PULLOUT switch, but not required)
[ SAT ] [ UNSAT ]
Page 5 of 7
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-2 Rev 3 JPM
Title:
Establish Charging Flow via the HPSI Header STEP ELEMENT STANDARD 10 Ensure a charging pump CB-1,2,3 suction source is available. Ensure LCV-218-2 open RED light ON and VCT level indicated on chart or indicator.
OR Ensure LCV-218-3 open RED light ON.
[ SAT ] [ UNSAT ]
11 Operate any available CB-1,2,3 Charging Pumps as necessary Start at least one charging to maintain PZR level within pump, CH-1A/B/C by taking 4% of programmed level. Control switch out of Pull-To-Lock, taking to AFTER-START and verifying RED light ON.
[ SAT ] [ UNSAT ]
Termination Criteria: A charging pump is supplying water to the RCS via the HPSI header.
Page 6 of 7
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-2 Rev 3 INITIAL The plant is operating at full power. AOP-33 has been CONDITIONS: entered due to a leak in the charging header. Charging and letdown have been isolated and the leak has stopped.
INITIATING CUE: The CRS has directed you to reestablish charging pump flow via the HPSI header using HPSI loop 2A injection valve, HCV-318, per AOP-33, Attachment B.
Page 7 of 7
AOP-33 Page 21 of 52 Attachment B Charging Via the HPSI Header INSTRUCTIONS CONTINGENCY ACTIONS NOTE Charging through the HPSI Header will result in the addition of approximately 100 gallons of water at refueling boron concentration into the RCS.
- 1. Close CH-194, "CHARGING PUMPS CH-1A/B/C DISCHARGE HEADER CONTAINMENT OUTBOARD ISOLATION VALVE" (Room 13).
- 3. Ensure ALL of the following valves are open:
- HCV-305, SI-2A and SI-2C Discharge Cross-Connect Valve
- HCV-304, SI-2B and SI-2C Discharge Cross-Connect Valve
AOP-33 Page 22 of 52 Attachment B Charging Via the HPSI Header INSTRUCTIONS CONTINGENCY ACTIONS
- 4. Close the SI Tank Leakage Cooler Pressure Control Valves on the loop in which the HPSI valve(s) will be opened in Step 5:
Loop 1B
- PCV-2909 Loop 1A
- PCV-2929 Loop 2A
- PCV-2949 Loop 2B
- PCV-2969
- 5. Open at least one of the following HPSI Loop Injection Valves:
- HCV-312 (Loop 1B)
- HCV-315 (Loop 1A)
- HCV-318 (Loop 2A)
- HCV-321 (Loop 2B)
R7
AOP-33 Page 23 of 52 Attachment B Charging Via the HPSI Header INSTRUCTIONS CONTINGENCY ACTIONS NOTE Using the SIRWT as a suction source will inject water with refueling boron concentration into the RCS.
- 6. Ensure a charging pump suction source is available.
NOTE Charging flow can be verified on the associated HPSI flow indicator(s) for the HPSI Loop Valve(s) in use, or on ERF (Page 323).
- 7. Operate any available Charging Pumps as necessary to maintain PZR level within 4% of programmed level.
- 8. IF Charging Header repairs are possible 8.1 IF Charging Header repairs are NOT with the Plant in its current operating possible with the Plant in its current mode, operating mode, THEN direct Maintenance to repair leak. THEN place the Plant in desired mode PER ONE of the following procedures:
- AOP-05, Emergency Shutdown
- OP-4, Load Change and Normal Power Operations R7
AOP-33 Page 24 of 52 Attachment B Charging Via the HPSI Header INSTRUCTIONS CONTINGENCY ACTIONS
- 9. WHEN the Charging Header has been repaired, THEN return the CVCS to normal operation PER OI-CH-1, Startup of Charging and Letdown.
- 10. WHEN the CVCS has been returned to normal, THEN IMPLEMENT Attachment E, HPSI Piping Flush, to flush all safety injection piping used in this procedure.
- 11. WHEN HPSI piping flush is completed, THEN GO TO Section 5.0, Exit Conditions.
End of Attachment B R7
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-3 Rev 5 JPM
Title:
Simultaneous Hot and Cold Leg Injection Location: Simulator Approximate Time: 15 minutes Actual Time: _________________
Reference(s): K/A# 006000 A1.11 EOP/AOP Attachment 9, "SIMULTANEOUS HOT AND COLD LEG INJECTION" EOP/AOP Attachment 10, SIMULTANEOUS HOT AND COLD LEG INJECTION WITHOUT INSTRUMENT AIR" Handout(s): EOP/AOP Attachment 9, "SIMULTANEOUS HOT AND COLD LEG INJECTION" EOP/AOP Attachment 10, SIMULTANEOUS HOT AND COLD LEG INJECTION WITHOUT INSTRUMENT AIR" Time Critical: YES - 30 Minutes Alternate Path: YES JPM Prepared by: Jerry Koske Date: 3/25/09 Page 1 of 10
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-3 Rev 5 JPM
Title:
Simultaneous Hot and Cold Leg Injection Operators Name: _____________________ Employee # ______________
All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):
SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________
Reason, if unsatisfactory:
Tools & Equipment: None Safety Considerations: None Comments: Time Critical (30 Minutes), Alternate Path Page 2 of 10
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-3 Rev 5 JPM
Title:
Simultaneous Hot and Cold Leg Injection TASK The candidate began to initiate Simultaneous Hot and STANDARD: Cold Leg injection 5.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> after a LOCA occurred using EOP/AOP Attachment 9, SIMULTANEOUS HOT AND COLD LEG INJECTION. Upon recognizing that HCV-305 could not be closed, the Candidate transitioned to EOP/AOP Attachment 10, SIMULTANEOUS HOT AND COLD LEG INJECTION WITHOUT INSTRUMENT AIR, and successfully provided sufficient flow to both a RCS hot leg and the cold legs.
INITIAL A large LOCA occurred 5.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> ago.
CONDITIONS: A RAS (Recirculation Actuation Signal) was received 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> ago.
HPSI pumps, SI-2A and SI-2B, are operating.
There are no signs of containment sump blockage.
All systems are operating as expected.
INITIATING CUE: ***** TIME CRITICAL *****
The Control Room Supervisor has directed you to initiate Simultaneous Hot and Cold Leg Injection in accordance with EOP/AOP Attachment 9.
Page 3 of 10
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-3 Rev 5 JPM
Title:
Simultaneous Hot and Cold Leg Injection Critical Steps shown in gray STEP ELEMENT STANDARD Note to Examiner:
Do Not provide Attachment 10 to candidate until he makes the transition in JPM step 9.
1 Read Cautions on page 44 of Reads both Cautions.
EOP/AOP Attachments.
[ SAT ] [ UNSAT ]
2 Verify conditions in step 1. Verifies:
A LOCA exists.
RCS Pressure is less than 140 psia 5.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> have elapsed.
[ SAT ] [ UNSAT ]
3 Open at least one of the CB-1,2,3 Charging Pumps HPSI Header Isolation Valves: At least one valves control HCV-308. switch to OPEN with RED light HCV-2988. ON.
[ SAT ] [ UNSAT ]
4 Open at least one of the CB-1,2,3 following PZR Auxiliary Spray Isolation Valves: At least one valves control
- HCV-240. switch to OPEN with RED light
- HCV-249. ON.
[ SAT ] [ UNSAT ]
Page 4 of 10
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-3 Rev 5 JPM
Title:
Simultaneous Hot and Cold Leg Injection STEP ELEMENT STANDARD NOTE: A rapid loss of instrument air pressure occurs due to the rupture of Auxiliary Building air riser "AS."
CUE: If candidate addresses loss of instrument air, inform him that another Operator has responded to the loss of Instrument Air.
5 If only one HPSI Pump is AI-30A/B available, GO TO Attachment
- 11. Verifies that 2 HPSI Pumps are operating and stays in Attachment 9
[ SAT ] [ UNSAT ]
6 Read Caution on page 45. Reads Caution
[ SAT ] [ UNSAT ]
7 Ensure ALL of the following CB-1,2,3 Charging Isolation Valves are For each valve:
closed: GREEN light ON.
- HCV-238. RED light OFF.
- HCV-239. Determines that HCV-247 and
- HCV-247. HCV-248 are closed but that
- HCV-248. HCV-238 and HCV-239 are open.
Does not go to attachment 11 because HCV-247 and HCV-248 are closed.
[ SAT ] [ UNSAT ]
Page 5 of 10
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-3 Rev 5 JPM
Title:
Simultaneous Hot and Cold Leg Injection STEP ELEMENT STANDARD 8 IF ANY of the following HPSI Reads step 6.
Discharge Cross-Connect Valves can NOT be closed Note: May determine that because of a loss of Instrument instrument air is not Air: available and immediately HCV-305 transition to EOP/AOP HCV-306 Attachment 10.
THEN Go To Attachment 10 9 IF HPSI Pump, SI-2A, is AI-30B operating,THEN close HCV- Key Switch to CLOSE.
305, SI-2A and SI-2C GREEN light ON.
Discharge Cross-Connect RED light OFF.
Valve.
Determines that HCV-305 will not close due to a loss of instrument air.
[ SAT ] [ UNSAT ]
10 Transitions to EOP/AOP Transitions to EOP/AOP Attachment 10. Attachment 10.
[ SAT ] [ UNSAT ]
NOTE to Examiner: Provide a copy of EOP/AOP Attachment 10 to Candidate.
11 Reviews Cautions. Reads both Cautions.
[ SAT ] [ UNSAT ]
Page 6 of 10
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-3 Rev 5 JPM
Title:
Simultaneous Hot and Cold Leg Injection STEP ELEMENT STANDARD 12 Verify conditions in step 1. Verifies:
A LOCA exists.
RCS Pressure is less than 140 psia 5.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> have elapsed.
[ SAT ] [ UNSAT ]
13 Verify open at least one of the CB-1,2,3 Charging Pumps HPSI Header Isolation Valves: At least one valves RED light HCV-308. ON.
HCV-2988.
[ SAT ] [ UNSAT ]
14 Verify open at least one of the CB-1,2,3 following PZR Auxiliary Spray Isolation Valves: At least one valves RED light
- HCV-240. ON.
- HCV-249.
[ SAT ] [ UNSAT ]
15 If only one HPSI Pump is AI-30A/B available, GO TO Attachment
- 11. Verifies that 2 HPSI Pumps are operating and stays in Attachment 10
[ SAT ] [ UNSAT ]
16 Read Caution on page 49. Reads Caution
[ SAT ] [ UNSAT ]
Page 7 of 10
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-3 Rev 5 JPM
Title:
Simultaneous Hot and Cold Leg Injection STEP ELEMENT STANDARD 17 Ensure ALL of the following CB-1,2,3 Charging Isolation Valves are For each valve:
closed: GREEN light ON.
- HCV-238. RED light OFF.
- HCV-239. Determines that HCV-247 and
- HCV-247. HCV-248 are closed but that
- HCV-248. HCV-238 and HCV-239 are open.
Stays in Attachment 10
[ SAT ] [ UNSAT ]
18 Close ALL of the following AI-30A/B HPSI Loop Injection Valves:
- HCV-315. Control Switches to CLOSE
- HCV-318. (pull out, counter-clockwise)
- HCV-312. until GREEN lights ON.
- HCV-321. RED light OFF.
[ SAT ] [ UNSAT ]
19 Close HCV-2987, HPSI Header AI-30A/B Isolation Valve.
Control Switch to CLOSE.
GREEN light ON.
RED light OFF.
[ SAT ] [ UNSAT ]
Page 8 of 10
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-3 Rev 5 JPM
Title:
Simultaneous Hot and Cold Leg Injection STEP ELEMENT STANDARD 20 IF evidence of containment AI-30A/B sump blockage does NOT exist, THEN throttle the HPSI Throttle one or more of the Loop Injection Valves until ALL following valves:
of the following criteria are HCV-314.
satisfied: HCV-317.
Charging flow is greater HCV-311.
than180 gpm (FIA-236). HCV-320.
Total HPSI flow is Verify greater than 200 gpm greater than 200 gpm. total flow on FI-313, FI-316, FI-319 and FI-322.
CB-1,2,3 Verify greater than 180 gpm flow on FIA-236.
Note: Plant computer may also be used to verify flows.
[ SAT ] [ UNSAT ]
Termination Criteria: Simultaneous Hot and Cold Leg Injection has been established with greater than 180 gpm flow through charging (Hot Leg) and greater than 200 gpm flow through the HPSI Header (Cold Legs).
Page 9 of 10
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-3 Rev 5 INITIAL A large LOCA occurred 5.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> ago.
CONDITIONS: A RAS (Recirculation Actuation Signal) was received 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> ago.
HPSI pumps, SI-2A and SI-2B, are operating.
There are no signs of containment sump blockage.
All systems are operating as expected.
INITIATING CUE: ***** TIME CRITICAL *****
The Control Room Supervisor has directed you to initiate Simultaneous Hot and Cold Leg Injection in accordance with EOP/AOP Attachment 9.
Page 10 of 10
EOP/AOP ATTACHMENTS Page 44 of 168 Attachment 9 Simultaneous Hot and Cold Leg Injection INSTRUCTIONS CONTINGENCY ACTIONS CAUTIONS
- 2. Simultaneous hot and cold leg injection must be implemented between five and one-half and six hours after a LOCA with RCS pressure less than 140 psia if SDC can not be established.
- 1. Verify that ALL of the following criteria 1.1 IF all of the criteria are NOT satisfied, are satisfied: THEN continue efforts to initiate SDC.
- A LOCA exists
- RCS pressure is less than 140 psia
- Five and one-half hours may elapse before SDC can be established
- HCV-308
- HCV-2988 R26
EOP/AOP ATTACHMENTS Page 45 of 168 Attachment 9 Simultaneous Hot and Cold Leg Injection INSTRUCTIONS CONTINGENCY ACTIONS
- 3. Open at least one of the following PZR Auxiliary Spray Isolation Valves:
- HCV-240
- HCV-249
- 4. IF only one HPSI Pump is available, THEN GO TO Attachment 11, Alternate Hot Leg Injection.
CAUTION Closing HCV-247 isolates a CVCS relief valve.
- 5. Ensure ALL of the following Charging 4.1 IF ANY of the following Charging Isolation Valves are closed: Isolation Valves are open:
- HCV-238
- HCV-247
- HCV-239
- HCV-248
- HCV-247
- HCV-248 THEN GO TO Attachment 11, Alternate Hot Leg Injection.
R26
EOP/AOP ATTACHMENTS Page 46 of 168 Attachment 9 Simultaneous Hot and Cold Leg Injection INSTRUCTIONS CONTINGENCY ACTIONS
- 6. IF ANY of the following HPSI Discharge Cross-Connect Valves can NOT be closed because of a loss of Instrument Air:
- HCV-305
- HCV-304 THEN GO TO Attachment 10, Simultaneous Hot and Cold Leg Injection without Instrument Air.
- 7. IF HPSI Pump, SI-2A is operating, 7.1 IF HPSI Pump, SI-2A is NOT THEN close HCV-305, SI-2A and operating, SI-2C Discharge Cross-Connect Valve. THEN close HCV-304, SI-2B and SI-2C Discharge Cross-Connect Valve.
- 8. Close ALL of the following HPSI Loop Injection Valves:
- HCV-315
- HCV-318
- HCV-312
- HCV-321
R26
EOP/AOP ATTACHMENTS Page 47 of 168 Attachment 9 Simultaneous Hot and Cold Leg Injection INSTRUCTIONS CONTINGENCY ACTIONS
- 10. IF evidence of containment sump 10.1 IF evidence of containment sump blockage does NOT exist, blockage does NOT exist, THEN throttle the HPSI Loop Injection AND all of the criteria are NOT Valves until ALL of the following satisfied:
criteria are satisfied: THEN GO TO Attachment 11, Alternate Hot leg Injection.
- Charging flow is greater than 80 gpm (FIA-236) 10.2 IF evidence of containment sump
- Total HPSI flow is greater than 200 gpm blockage exists, THEN throttle HPSI Loop Injection Valves PER Attachment 26, Curve 3 - Total Hot Leg and Cold Leg Injection vs Time.
End of Attachment 9 R26
EOP/AOP ATTACHMENTS Page 48 of 168 Attachment 10 Simultaneous Hot and Cold Leg Injection Without Instrument Air INSTRUCTIONS CONTINGENCY ACTIONS CAUTIONS
- 2. Simultaneous hot and cold leg injection must be implemented between five and one-half and six hours after a LOCA with RCS pressure less than 140 psia if SDC can not be established.
- 1. Verify that ALL of the following criteria 1.1 IF all of the criteria are NOT satisfied, are satisfied: THEN continue efforts to initiate SDC.
- A LOCA exists
- RCS pressure is less than 140 psia
- Five and one-half hours may elapse before SDC can be established
- HCV-308
- HCV-2988 R26
EOP/AOP ATTACHMENTS Page 49 of 168 Attachment 10 Simultaneous Hot and Cold Leg Injection Without Instrument Air INSTRUCTIONS CONTINGENCY ACTIONS
- 3. Open at least one of the following PZR Auxiliary Spray Isolation Valves:
- HCV-240
- HCV-249
- 4. IF only one HPSI Pump is available, THEN GO TO Attachment 11, Alternate Hot Leg Injection.
CAUTION Closing HCV-247 isolates a CVCS relief valve.
- 5. Ensure ALL of the following Charging 4.1 IF ANY of the following Charging Isolation Valves are closed: Isolation Valves are open:
- HCV-238
- HCV-247
- HCV-239
- HCV-248
- HCV-247
- HCV-248 THEN GO TO Attachment 11, Alternate Hot Leg Injection.
R26
EOP/AOP ATTACHMENTS Page 50 of 168 Attachment 10 Simultaneous Hot and Cold Leg Injection Without Instrument Air INSTRUCTIONS CONTINGENCY ACTIONS
- 6. Close ALL of the following HPSI Loop Injection Valves:
- HCV-315
- HCV-318
- HCV-312
- HCV-321
- 8. IF evidence of containment sump 8.1 IF evidence of containment sump blockage does NOT exist, blockage does NOT exist, THEN throttle the HPSI Loop Injection AND all of the criteria are NOT Valves until ALL of the following satisfied:
criteria are satisfied: THEN GO TO Attachment 11, Alternate Hot leg Injection.
- Charging flow is greater than 180 gpm (FIA-236) 8.2 IF evidence of containment sump
- Total HPSI flow is greater than 200 gpm blockage exists, THEN throttle HPSI Loop Injection Valves PER Attachment 26, Curve 3 - Total Hot Leg and Cold Leg Injection vs Time.
End of Attachment 10 R26
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-4 Rev 3 JPM
Title:
Start a Reactor Coolant Pump Location: Simulator Approximate Time: 7 minutes Actual Time: _________________
Reference(s): K/A# 003000 A4.06 OI-RC-9, "REACTOR COOLANT PUMP OPERATION" Handout(s): OI-RC-9, "REACTOR COOLANT PUMP OPERATION" Time Critical: NO Alternate Path: YES JPM Prepared by: Jerry Koske Date: 3/23/09 Page 1 of 8
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-4 Rev 3 JPM
Title:
Start a Reactor Coolant Pump Operators Name: _____________________ Employee # ______________
All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):
SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________
Reason, if unsatisfactory:
Tools & Equipment: None Safety Considerations: None Comments: Alternate Path Page 2 of 8
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-4 Rev 3 JPM
Title:
Start a Reactor Coolant Pump TASK The Candidate started Reactor Coolant Pump RC-3A in STANDARD: accordance with OI-RC-9, "REACTOR COOLANT PUMP OPERATION." The Candidate then tripped the pump when the motor current did not fall below 425 amps within the time specified in the procedure.
INITIAL The plant is in hot shutdown.
CONDITIONS: Reactor Coolant Pump, RC-3C, is running.
RC-3A is scheduled to be started.
The motor on RC-3A is cold.
There is no one in containment.
INITIATING CUE: You are directed to place RC-3A in service in accordance with OI-RC-9, Attachment 1.
All prerequisites are met.
Page 3 of 8
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-4 Rev 3 JPM
Title:
Start a Reactor Coolant Pump Critical Steps shown in gray STEP ELEMENT STANDARD NOTE to Examiner:
Simulator Operator has inserted the seized rotor malfunction for RC-3A and has also failed the overcurrent relays for the pump's motor.
1 Read the note and cautions Reads the Note and Cautions on page 8 of OI-RC-9
[ SAT ] [ UNSAT ]
2 Setup ERF Display for RC-3A. ERF Type [440] [DSP]
RC-3A Page displays.
[ SAT ] [ UNSAT ]
3 Station operator to respond to CUE: Operator is at AI-270.
vibration alarms.
[ SAT ] [ UNSAT ]
4 Read Note Reads first note on page 9.
Determines it is not applicable.
[ SAT ] [ UNSAT ]
5 Verify controlled Bleed-off flow. ERF page 342 Verify positive bleed-off flow.
[ SAT ] [ UNSAT ]
6 Read Note Reads second note on page 9.
Determines it is not applicable.
[ SAT ] [ UNSAT ]
Page 4 of 8
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-4 Rev 3 JPM
Title:
Start a Reactor Coolant Pump STEP ELEMENT STANDARD 7 Ensure RCS Pressure and Verifies RCS Pressure above RCP NPSH. 225 psia.
Use Figure TDB III.7.a to verify NPSH.
[ SAT ] [ UNSAT ]
8 OI-RC-9, Attachment 1 steps 6 Records N/A for steps and 7 because a RCP is running.
[ SAT ] [ UNSAT ]
9 Read Note Reads note near top of page 10
[ SAT ] [ UNSAT ]
10 Ensure 86/RC-3A reset. CB-1/2/3 86/RC-3A AMBER light ON.
[ SAT ] [ UNSAT ]
11 Verify RCP Reverse rotation is CB-1/2/3 cleared. ANN A-6, A5 is clear.
[ SAT ] [ UNSAT ]
12 Read Note and Caution. Reads note and caution near bottom of page 10
[ SAT ] [ UNSAT ]
13 Start RC-3A oil lift pump. CB-1/2/3 RC-3A-1 to AFTER START and RED light ON.
[ SAT ] [ UNSAT ]
Page 5 of 8
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-4 Rev 3 JPM
Title:
Start a Reactor Coolant Pump STEP ELEMENT STANDARD 14 Verify ARRD oil flow for RC-3A. ERF Page 342.
Note: Page 342 does not display ARRD oil flow for RC-3A.
[ SAT ] [ UNSAT ]
CUE: The oil lift pump has been running for two minutes 15 Start RC-3A. CB-1/2/3 RC-3A CS in AFTER START and RED light ON.
[ SAT ] [ UNSAT ]
16 Monitor Amps. CB-1/2/3 Determines that RC-3A's ammeter did not drop below 425 amps within 17 seconds.
[ SAT ] [ UNSAT ]
17 Trip RC-3A CB-1/2/3 RC-3A CS in AFTER STOP and RED light OFF.
[ SAT ] [ UNSAT ]
18 Monitor RC-3A motor amps. CB-1/2/3 Verifies zero amps on ammeter.
[ SAT ] [ UNSAT ]
Page 6 of 8
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-4 Rev 3 JPM
Title:
Start a Reactor Coolant Pump STEP ELEMENT STANDARD 19 Report RC-3A problem to CRS Reports RC-3A problem and need to manually trip pump to CRS
[ SAT ] [ UNSAT ]
Termination Criteria: RC-3A has been tripped.
Page 7 of 8
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-4 Rev 3 INITIAL The plant is in hot shutdown.
CONDITIONS: Reactor Coolant Pump, RC-3C, is running.
RC-3A is scheduled to be started.
The motor on RC-3A is cold.
There is no one in containment.
INITIATING CUE: You are directed to place RC-3A in service in accordance with OI-RC-9, Attachment 1.
All prerequisites are met.
Page 8 of 8
FORT CALHOUN STATION OI-RC-9 OPERATING INSTRUCTION PAGE 6 OF 66 C
Continuous Use Attachment 1 - Starting Reactor Coolant Pumps (Coupled)
PREREQUISITES (T) INITIALS NOTES
- 1. Attachment 7 provides guidance for starting RCPs for sweeping steam generator tubes.
- 2. Attachment 6 provides recovery guidance from the possibility of a slug of water with reduced boron concentration in an idle RCS loop.
- 1. Procedure Revision Verification Revision No. 69 Date: 3/31/09 JEK
- 2. The Reactor is Shutdown (Mode 3, Mode 4 or Mode 5). JEK
- 3. Communications have been established between the Control Room and locally at each Reactor Coolant Pump, as needed, prior to Reactor Coolant Pump start. JEK
- 4. Applicable sections of Checklist OI-RC-9-CL-A have been completed for each RCP to be run. JEK
- 5. A minimum Reactor Coolant System pressure per TDB-III.7.a or TDB-III.7.d, RCS Pressure and Temperature Limits, has been established to ensure JEK adequate Reactor Coolant Pump Net Positive Suction Head (NPSH).
- 6. The Component Cooling Water System is in operation to each Reactor Coolant Pump to be run per OI-CC-1. JEK
- 7. The Red Motor Heater Lights for each non-operating Reactor Coolant Pump are energized. JEK
- 9. If the RCP has been idle for a long outage OR for maintenance, a general visual inspection of the RCP should be performed prior to starting. JEK
- 10. The Reactor Coolant Pump Motor upper and lower oil reservoirs are filled to levels as specified in Tables 1 through 4. JEK
FORT CALHOUN STATION OI-RC-9 OPERATING INSTRUCTION PAGE 7 OF 66 C
Continuous Use Attachment 1 - Starting Reactor Coolant Pumps (Coupled)
PREREQUISITES (continued) (T) INITIALS
- 13. RCPs to be operated are coupled per MM-RR-RC-0008. JEK PROCEDURE NOTE Controlled Bleedoff Flow can be established within 24 hrs of starting the first RCP.
- 1. Open all the following valves:
! RC-308, RC-3A Reactor Coolant Pump Controlled Bleedoff Isolation Valve O
! RC-309, RC-3B Reactor Coolant Pump Controlled Bleedoff Isolation Valve O
! RC-310, RC-3C Reactor Coolant Pump Controlled Bleedoff Isolation Valve O
! RC-311, RC-3D Reactor Coolant Pump Controlled Bleedoff Isolation Valve O JEK R69
FORT CALHOUN STATION OI-RC-9 OPERATING INSTRUCTION PAGE 8 OF 66 C
Continuous Use Attachment 1 - Starting Reactor Coolant Pumps (Coupled)
PROCEDURE (continued) (T) INITIALS NOTE High vibration alarms should be anticipated when starting RCPs.
CAUTIONS
- 1. IF the Steam Generator secondary side temperature is greater than 30°F above the RCS cold leg temperature, the effects of heat input from the secondary side, and the subsequent effects on heatup rate, must be evaluated/considered.
- 2. If no RCP is running, and Tc is less than 350°F, then a Reactor Coolant Pump shall NOT be started unless the following conditions are satisfied:
! Actual PZR level is less than or equal to 50% per TDB-III.1.a
! RCS pressure must be less than the Maximum Pressure for First Start RCP (TDB-III.7.a curve 3)
- 3. When starting a RCP, ensure RCS Pressure is greater than 225 psia to reduce the possibility of seal failure.
- 2. Set up one ERF Display Screen to monitor the selected Reactor Coolant Pump and Motor parameters as follows:
! RC-3A page 440
! RC-3B page 441
! RC-3C page 442
! RC-3D page 443
- 3. Station an operator at AI-270 (Room 57) to respond to vibration alarms.
OI-RC-13 provides alarm response guidance. JEK R69
FORT CALHOUN STATION OI-RC-9 OPERATING INSTRUCTION PAGE 9 OF 66 C
Continuous Use Attachment 1 - Starting Reactor Coolant Pumps (Coupled)
PROCEDURE (continued) (T) INITIALS NOTE At low RCS Pressure, verification of positive Controlled Bleedoff Flow may NOT be possible.
! RC-3A
! RC-3B
! RC-3C
! RC-3D NOTE When starting the first Reactor Coolant Pump, use TR-346, Shutdown Cooling Inlet/Outlet Temp, black pen LPSI Suction Temp indication to verify NPSH requirements are met.
- 5. Ensure RCS Pressure is greater than 225 psia for RCP seal protection (ensures RCS Pressure is greater than minimum NPSH Pressure per TDB-III.7.a and TDB-III.7.d, RCS Pressure and Temperature Limits).
- 6. Ensure RCS Pressure is less than the Maximum Pressure for First RCP Start curve per TDB-III.7.a, RCS Pressure and Temperature Limits. (NA if an RCP is running).
- 7. Ensure actual corrected level per TDB-III.1.a Pressurizer level is less than 50%. (NA if an RCP is running).
R69
FORT CALHOUN STATION OI-RC-9 OPERATING INSTRUCTION PAGE 10 OF 66 C
Continuous Use Attachment 1 - Starting Reactor Coolant Pumps (Coupled)
PROCEDURE (continued) (T) INITIALS NOTE IF Lockout Relays are NOT RESET, THEN Electrical Maintenance shall be contacted for an inspection of the affected relay(s).
- 8. Ensure the Lockout Relay Switch for the selected RCP is in RESET and the Amber indicating light is ON:
! 86/RC-3A, Pump RC-3A Motor Current Diff
! 86/RC-3B, Pump RC-3B Motor Current Diff
! 86/RC-3C, Pump RC-3C Motor Current Diff
! 86/RC-3D, Pump RC-3D Motor Current Diff
- 9. 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)
NOTE The Oil Lift Pump shall not be run for longer than 10 minutes before starting the Reactor Coolant Pump.
CAUTION Prior to starting a RCP when personnel are in Containment, the Containment Coordinator shall be notified, OR an announcement made on the Gaitronics.
- 10. Place the Oil Lift Pump for the selected RCP to AFTER START:
! RC-3A-1, Oil Lift Pump
! RC-3B-1, Oil Lift Pump
! RC-3C-1, Oil Lift Pump
! RC-3D-1, Oil Lift Pump R69
FORT CALHOUN STATION OI-RC-9 OPERATING INSTRUCTION PAGE 11 OF 66 C
Continuous Use Attachment 1 - Starting Reactor Coolant Pumps (Coupled)
PROCEDURE (continued) (T) INITIALS
- 11. Verify adequate ARRD Lube Oil Flow for the selected RCP. ERF indication shall read NORMAL: (ERF page 342)
! RC-3A F3181
! RC-3B F3184
! RC-3C F3187
! RC-3D F3190
- 12. Startup sequence for selected RCP:
- a. Run the oil lift pump for the selected RCP a minimum of two minutes.
! RC-3A-1, Oil Lift Pump
! RC-3B-1, Oil Lift Pump
! RC-3C-1, Oil Lift Pump
! RC-3D-1, Oil Lift Pump
- b. Place the selected RCP control switch in AFTER START:
! RC-3A, RC Pump
! RC-3B, RC Pump
! RC-3C, RC Pump
! RC-3D, RC Pump
- c. IF the Reactor Coolant Pump motor amps fail to drop below 425 amps within the time listed below, THEN place the control switch in AFTER STOP:
! RC-3A - seventeen (17) seconds
! RC-3B - nineteen (19) seconds
! RC-3C - seventeen (17) seconds
! RC-3D - seventeen (17) seconds R69
FORT CALHOUN STATION OI-RC-9 OPERATING INSTRUCTION PAGE 12 OF 66 C
Continuous Use Attachment 1 - Starting Reactor Coolant Pumps (Coupled)
PROCEDURE (continued) (T) INITIALS
- 13. Verify the following for the selected RCP:
- a. Oil Lift Pump stops (Green indicating light ON):
! RC-3A-1
! RC-3B-1
! RC-3C-1
! RC-3D-1
- b. 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)
NOTE RCP Vibration Hi annunciator may be erratic until pump speed/flow stabilizes.
- c. For the selected RCP verify the following Annunciator is clear:
! RC-3A REACTOR COOLANT PUMP RC-3A VIBRATION HI (CB-1/2/3, A6, A4)
! RC-3B REACTOR COOLANT PUMP RC-3B VIBRATION HI (CB-1/2/3, A6, B4)
! RC-3C REACTOR COOLANT PUMP RC-3C VIBRATION HI (CB-1/2/3, A6, C4)
! RC-3D REACTOR COOLANT PUMP RC-3D VIBRATION HI (CB-1/2/3, A6, D4)
R69
FORT CALHOUN STATION OI-RC-9 OPERATING INSTRUCTION PAGE 13 OF 66 C
Continuous Use Attachment 1 - Starting Reactor Coolant Pumps (Coupled)
PROCEDURE (continued) (T) INITIALS NOTE At low RCS Pressure, verification of positive Controlled Bleedoff Flow may NOT be possible.
- 14. Verify positive Controlled Bleedoff flow for the selected RCP: (ERF page 342)
! RC-3A F3115
! RC-3B F3135
! RC-3C F3155
! RC-3D F3175
- 15. Monitor the ERF Computer and verify all parameters are normal for the selected RCP:
! RC-3A
! RC-3B
! RC-3C
! RC-3D
Completed by Date/Time /
R69
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-5 Rev 3 JPM
Title:
Initiate AFW to SGs Location: Simulator Approximate Time: 10 minutes Actual Time: _________________
Reference(s): K/A# 061000 A2.04 EOP-06, "LOSS OF ALL FEEDWATER" Handout(s) EOP-06, Step 12.
Time Critical: NO Alternate Path: YES JPM Prepared by: Jerry Koske Date: 3/3/09 Page 1 of 6
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-5 Rev 3 JPM
Title:
Initiate AFW to SGs Operators Name: _____________________ Employee # ______________
All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):
SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________
Reason, if unsatisfactory:
Tools & Equipment: None Safety Considerations: None Comments: Alternate Path Page 2 of 6
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-5 Rev 3 JPM
Title:
Initiate AFW to SGs TASK The candidate attempted to supply water to the steam STANDARD: generators from Turbine Driven AFW Pump, FW-10, through the feed rings but was unsuccessful because FW-10 would not start. The Candidate established flow to both Steam Generators through the feed rings using Diesel Driven AFW Pump, FW-54.
INITIAL A reactor trip has occurred following a rupture of CONDITIONS: the Condensate Pumps' common discharge header.
FW-6 is out of service.
There are no Operators available to perform any local actions.
INITIATING CUE: You have been directed to feed both steam generators from FW-10, via the feed rings in accordance with EOP-06, Step 12.
Page 3 of 6
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-5 Rev 3 JPM
Title:
Initiate AFW to SGs Critical Steps shown in gray STEP ELEMENT STANDARD NOTE to Examiner: If the candidate requests an EONT or other In-plant Operator to take any actions during the performance of this JPM, inform him that the EONT is not available.
1 Ensure BOTH of the Feed CB-10,11 Reg Block Valves are GREEN lights ON.
closed:
- HCV-1103. [ SAT ] [ UNSAT ]
- HCV-1104.
2 Start FW-10 AI-66B Place YCV-1045 switch in OPEN, verfiy RED light ON Verify YCV-1045A and/or YCV-1045B OPEN-RED light ON Determines that FW-10 will not start. Goes to contingency action, 12.1.
3 Ensure HCV-1384 is closed. CB-10,11 Control Switch in AFTER CLOSE, GREEN light ON.
[ SAT ] [ UNSAT ]
4 Ensure BOTH of the Feed CB-10,11 Reg Block Valves are GREEN lights ON.
closed:
- HCV-1103. [ SAT ] [ UNSAT ]
- HCV-1104.
Page 4 of 6
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-5 Rev 3 JPM
Title:
Initiate AFW to SGs STEP ELEMENT STANDARD 4 Start FW-54 CB-10,11 Control switch to open.
RED light ON.
[ SAT ] [ UNSAT ]
5 Ensure BOTH of the Feed CB-10,11 header Isolation Valves are open: RED lights ON GREEN lights OFF HCV-1386 HCV-1385 6 Manually control feed flow CB-10,11 via BOTH of the Feed Reg DCS Panel Bypass Valves:
- HCV-1105. Manually open HCV-1105 and
- HCV-1106. HCV-1106 to establish flow.
[ SAT ] [ UNSAT ]
7 Verify AFW Flow established to CB-10,11 or ERF both S/Gs. Flow indicated on meters or ERF computer.
[ SAT ] [ UNSAT ]
8 Record Time. Record Time at step 12.1.a.5)
[ SAT ] [ UNSAT ]
Termination Criteria: Flow established from FW-54 to both Steam Generators Page 5 of 6
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-5 Rev 3 INITIAL A reactor trip has occurred following a rupture of CONDITIONS: the Condensate Pumps' common discharge header.
FW-6 is out of service.
There are no Operators available to perform any local actions.
INITIATING CUE: You have been directed to feed both steam generators from FW-10, via the feed rings in accordance with EOP-06, Step 12.
Page 6 of 6
EOP-06 Page 11 of 41 INSTRUCTIONS CONTINGENCY ACTIONS 812. Initiate AFW using FW-6 or FW-10, 12.1 IF FW-6 and FW-10 are NOT AFW Pumps, by performing step a, b available, or c: THEN initiate AFW using FW-54, Diesel AFW Pump, by performing
- a. Feed S/Gs with AFW through the step a or b:
Feed Rings to maintain S/G level 35-85% NR (73-94% WR):
- a. Feed S/Gs with AFW to the Feed Rings to maintain S/G levels
- 1) Ensure BOTH of the Feed 35-85% NR (73-94% WR):
Reg Block Valves are closed:
- 1) Ensure HCV-1384, FW/AFW
- HCV-1103 Header Cross-Connect Valve,
- HCV-1104 is closed.
- 2) Start at least one of the
- 2) Ensure BOTH of the Feed following AFW Pumps:
Reg Block Valves are closed:
- FW-6
- FW-10
- HCV-1103
- HCV-1104
- 4) Ensure BOTH of the Feed 4) Ensure BOTH of the Feed Header Isolation Valves are Header Isolation Valves are open:
open:
- HCV-1386
- HCV-1386
- HCV-1385
- HCV-1385 (continue) (continue) 8 Continuously Applicable or Non-Sequential Step R16
EOP-06 Page 12 of 41 INSTRUCTIONS CONTINGENCY ACTIONS 812.a. (continued) 12.1.a (continued)
- 5) Manually control feed flow 5) Manually control feed flow via via BOTH of the Feed Reg BOTH of the Feed Reg Bypass Valves: Bypass Valves:
- HCV-1105
- HCV-1105
- HCV-1106
- HCV-1106 Time: Time:
- 6) IF Auxiliary Feedwater flow 6) IF Auxiliary Feedwater flow is is established, established, THEN GO TO Step 15. THEN GO TO Step 15.
(continue) (continue) 8 Continuously Applicable or Non-Sequential Step R16
EOP-06 Page 13 of 41 INSTRUCTIONS CONTINGENCY ACTIONS 8 12. (continued) 12.1 (continued)
- b. Feed S/Gs with AFW to the Feed b. Feed S/Gs with AFW to the AFW Rings via the alternate AFW Nozzles to maintain S/G levels Pump discharge path to maintain 35-85% NR (73-94% WR):
S/G levels 35-85% NR (73-94%
WR): 1) Close BOTH of the Feed Header Isolation Valves:
- 1) Open BOTH of the following
- HCV-1386 valves (Room 19):
- HCV-1385
- FW-745, "MOTOR DRIVEN AUX FEED 2) Open HCV-1384, FW/AFW PUMP FW-6 ALTERNATE Header Cross-Connect Valve.
DISCHARGE VALVE"
- FW-744, 3) Start FW-54, Diesel AFW "TURB-DRIVEN AUX Pump.
FEED PUMP FW-10 ALTERNATE DISCHARGE VALVE"
- 4) IF AFAS has actuated, THEN set BOTH of the
- 2) Ensure BOTH of the Feed following AFW Isolation Valve Reg Block Valves are Controllers to open closed:
(CB-10,11):
- HCV-1103
- HCV-1104
- HIC-1107B
- HIC-1108B (continue) (continue) 8 Continuously Applicable or Non-Sequential Step R16
EOP-06 Page 14 of 41 INSTRUCTIONS CONTINGENCY ACTIONS 812.b (continued) 12.1.b (continued)
- 3) Start at least one of the 5) Place control switches for following AFW Pumps: BOTH of the following AFW Isolation Valves in "CLOSE"
- FW-6
- FW-10 (AI-66A/B):
- 4) Ensure BOTH of the Feed
- HCV-1107B
- HCV-1108B Header Isolation Valves are open:
- 6) Open BOTH of the following
- HCV-1385 AFW Isolation Valves
- HCV-1386 (AI-66A/B):
- 5) Manually control feed flow
- HCV-1107A
- HCV-1108A via BOTH of the Feed Reg Bypass Valves: 7) Manually control BOTH of the following AFW Isolation
- HCV-1105
- HCV-1106 Valves (CB-10,11):
Time:
- HIC-1107B
- HIC-1108B
- 6) IF Auxiliary Feedwater flow is established, Time:
THEN GO TO Step 15.
- 8) IF Auxiliary Feedwater flow is established, (continue) THEN GO TO Step 15.
(continue) 8 Continuously Applicable or Non-Sequential Step R16
EOP-06 Page 15 of 41 INSTRUCTIONS CONTINGENCY ACTIONS 812.b (continued)
- 1) Start at least one of the following AFW Pumps:
- FW-6
- FW-10
- 2) Ensure HCV-1384, FW/AFW Header Cross-Connect Valve, is closed.
- 3) IF AFAS has actuated, THEN set BOTH of the following AFW Isolation Valve Controllers to open (CB-10,11):
- HIC-1107B
- HIC-1108B (continue) 8 Continuously Applicable or Non-Sequential Step R16
EOP-06 Page 16 of 41 INSTRUCTIONS CONTINGENCY ACTIONS 812.c. (continued)
- 4) Place Control Switches for BOTH of the following AFW Isolation Valves in "CLOSE" (AI-66A/B):
- HCV-1107B
- HCV-1108B
- 5) Open BOTH of the following AFW Isolation Valves (AI-66A/B):
- HCV-1107A
- HCV-1108A
- 6) Manually control BOTH of the following AFW Isolation Valves (CB-10,11):
- HIC-1107B
- HIC-1108B Time:
- 13. IF Auxiliary Feedwater flow is established, THEN GO TO Step 15.
8 Continuously Applicable or Non-Sequential Step R16
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-6 Rev 2 JPM
Title:
Operate the Containment Hydrogen Analyzer Location: Simulator Approximate Time: 10 minutes Actual Time: _________________
Reference(s): K/A 028000 A1.01 EOP/AOP Attachment 16, "CONTAINMENT HYDROGEN ANALYZER STARTUP" Handout(s): EOP/AOP Attachment 16, "CONTAINMENT HYDROGEN ANALYZER STARTUP" Time Critical: NO Alternate Path: NO JPM Prepared by: Jerry Koske Date: 3/3/09 Page 1 of 7
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-6 Rev 2 JPM
Title:
Operate the Containment Hydrogen Analyzer Operators Name: _____________________ Employee # ______________
All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):
SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________
Reason, if unsatisfactory:
Tools & Equipment: None Safety Considerations: None Comments:
Page 2 of 7
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-6 Rev 2 JPM
Title:
Operate the Containment Hydrogen Analyzer TASK The Candidate placed the Containment Hydrogen STANDARD Analyzers in service and determined that the hydrogen concentration is below flammability limits.
INITIAL A LOCA occurred followed by a sustained core CONDITIONS: uncovery. The core is now covered but radiation levels in containment indicate that some fuel damage may have occurred. The SAMG Evaluators in the TSC need to know the containment hydrogen concentration to perform core damage assessment.
INITIATING CUE: You are directed to place the Hydrogen analyzers in service per the EOP/AOP Attachment 16 and sample the upper level of containment via HCV-820C and HCV-883C. Determine if Containment Hydrogen Concentration is above flammability limits.
Page 3 of 7
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-6 Rev 2 JPM
Title:
Operate the Containment Hydrogen Analyzer Critical Steps shown in gray STEP ELEMENT STANDARD 1 Open HCV-820C. AI-65A/B Control switch to OPEN.
RED light ON.
[ SAT ] [ UNSAT ]
2 Open HCV-883C. AI-65A/B Control switch to OPEN.
RED light ON.
[ SAT ] [ UNSAT ]
3 Place all of the following AI-43A/B switches in Override: Control switches to ORIDE.
HCV-820A/821A. RED lights ON.
HCV-883A/884A.
HCV-820B/821B.
HCV-883B/884B. [ SAT ] [ UNSAT ]
4 Place recorders, HR-81A/B in AI-65A/B service. Turn recorders on.
[ SAT ] [ UNSAT ]
5 Ensure Range Selector AI-65A/B switches are in 0-10%. Selector switch in 0-10%
position.
[ SAT ] [ UNSAT ]
6 Place the Hydrogen Analyzer AI-65A/B Power On Selector Switches to Switches to ANALYZE ANALYZE. position.
[ SAT ] [ UNSAT ]
Page 4 of 7
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-6 Rev 2 JPM
Title:
Operate the Containment Hydrogen Analyzer STEP ELEMENT STANDARD 7 Ensure the Function Selector AI-65A/B Switches are in SAMPLE. Switches in SAMPLE position.
[ SAT ] [ UNSAT ]
8 Press REMOTE selector AI-65A/B pushbuttons. Depress pushbuttons.
[ SAT ] [ UNSAT ]
9 Check the following: AI-65A/B Containment H2 Alarm Window ON.
Sampling System Remote/Local Off Normal Annunciator in Alarm.
0-10% Range Amber AMBER light ON.
indicating light is ON.
The Sample Indicating Light is ON.
light is ON.
[ SAT ] [ UNSAT ]
10 Press Alarm Reset Push AI-65A/B buttons. Depress push buttons.
[ SAT ] [ UNSAT ]
CUE: 5 minutes have elapsed 11 Obtain hydrogen concentration AI-65A/B reading. Report reading from meters is below flammability limits.
[ SAT ] [ UNSAT ]
Page 5 of 7
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-6 Rev 2 JPM
Title:
Operate the Containment Hydrogen Analyzer Termination Criteria: Containment hydrogen concentration has been determined Page 6 of 7
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-6 Rev 2 INITIAL A LOCA occurred followed by a sustained core CONDITIONS: uncovery. The core is now covered but radiation levels in containment indicate that some fuel damage may have occurred. The SAMG Evaluators in the TSC need to know the containment hydrogen concentration to perform core damage assessment.
INITIATING CUE: You are directed to place the Hydrogen analyzers in service per the EOP/AOP Attachment 16 and sample the upper level of containment via HCV-820C and HCV-883C. Determine if Containment Hydrogen Concentration is above flammability limits.
Page 7 of 7
EOP/AOP ATTACHMENTS Page 79 of 168 Attachment 16 Containment Hydrogen Analyzer Startup INSTRUCTIONS CONTINGENCY ACTIONS
- 1. Start the Hydrogen Analyzers, by performing the following steps:
- a. Open ONE of the Containment Hydrogen Sampling Valves, HCV-820C/D/E/F/G/H.
- b. Open ONE of the Containment Hydrogen Sampling Valves, HCV-883C/D/E/F/G/H.
- c. Place ALL of the following switches in "O'RIDE":
- "H2 ANALYZER VA-81A ISOLATION VALVES OUTBD HCV-820A/821A"
- "H2 ANALYZER VA-81B ISOLATION VALVES INBD HCV-883A/884A"
- "H2 ANALYZER VA-81A ISOLATION VALVES INBD HCV-820B/821B"
- H2 ANALYZER VA-81B ISOLATION VALVES OUTBD HCV-883B/884B" (continue)
R26
EOP/AOP ATTACHMENTS Page 80 of 168 Attachment 16 Containment Hydrogen Analyzer Startup INSTRUCTIONS CONTINGENCY ACTIONS
- 1. (continued)
- d. Place the Hydrogen Analyzer Recorders, HR-81A/B, in service.
- e. Ensure the Hydrogen Analyzer Dual Range Selector Switches are in "0-10%".
- f. Place the Hydrogen Analyzer Power On Selector Switches in "ANALYZE".
- g. Ensure the Function Selector Switches are in "SAMPLE".
- h. Press the "REMOTE" selector push buttons.
(continue)
R26
EOP/AOP ATTACHMENTS Page 81 of 168 Attachment 16 Containment Hydrogen Analyzer Startup INSTRUCTIONS CONTINGENCY ACTIONS
- 1. (continued)
- i. Check the following indications:
- The CONTAINMENT H2 SAMPLING SYSTEM REMOTE/LOCAL OFF NORMAL annunciator (A65A or B, Window 32) is IN ALARM
- H2 0-10% Range Amber indicating light is ON
- The Sample indicating light is ON
- j. Press the "ALARM RESET" push buttons.
- k. WHEN 5 minutes has elapsed since pressing the "ALARM RESET" push button, THEN a valid hydrogen concentration may be read.
End of Attachment 16 R26
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-7 Rev 2 JPM
Title:
Transfer 4160V Buses from 345 KV to 161 KV Location: Simulator Approximate Time: 10 minutes Actual Time: _________________
Reference(s): K/A 000062 A4.01 AOP-31,Section II, "ALL 4160 V BUSES FED FROM 22 KV."
OI-EE-1, Attachment 1, "FEED VITAL/NON-VITAL BUSES FROM 161 KV."
Handout(s): AOP-31,Section II, "ALL 4160 V BUSES FED FROM 22 KV",
step 10.
OI-EE-1, Attachment 1, "FEED VITAL/NON-VITAL BUSES FROM 161 KV."
Time Critical: NO Alternate Path: NO JPM Prepared by: Jerry Koske Date: 03/3/09 Page 1 of 8
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-7 Rev 2 JPM
Title:
Transfer 4160V Buses from 345 KV to 161 KV Operators Name: _____________________ Employee # ______________
All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):
SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________
Reason, if unsatisfactory:
Tools & Equipment: None Safety Considerations: None Comments:
Page 2 of 8
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-7 Rev 2 JPM
Title:
Transfer 4160V Buses from 345 KV to 161 KV TASK The candidate transferred the power supplies to vital STANDARD: buses 1A3 and 1A4 from 345 KV to 161 KV following the restoration of 161 KV power in accordance with AOP-31, "161 KV GRID MALFUNCTIONS" and OI-EE-1, "NORMAL OPERATION OF 4160 VOLT SYSTEM, "
Attachment 1.
INITIAL The plant is operating at full power.
CONDITIONS: A loss of 161 KV occurred due to a grid problem.
Buses 1A3 and 1A4 transferred to 345 KV.
AOP-31, section II was entered and appropriate actions taken.
The 161 KV grid problem has been fixed and 161 KV is available.
INITIATING CUE: You are directed to restore normal 161 KV power to buses 1A3 and 1A4 using AOP-31, section II, step 10 and OI-EE-1, Attachment 1.
Page 3 of 8
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-7 Rev 2 JPM
Title:
Transfer 4160V Buses from 345 KV to 161 KV Critical Steps shown in gray STEP ELEMENT STANDARD 1 Ensure Lockout Relay 86/161 AI-22 is reset. 86 Relay RESET.
[ SAT ] [ UNSAT ]
2 Ensure all of the following AI-24, AI-25, AI-46 Lockout Relays are reset: Relays RESET.
86-1/T1A-4.
86-2/T1A-4.
86-1/T1A-3.
86-2/T1A-3.
86X/FT161. [ SAT ] [ UNSAT ]
3 Read Caution. Read Caution on AOP-31 page 10.
[ SAT ] [ UNSAT ]
CUE: System Operations has been notified.
4 Synchronize and Close at least CB-20 one of the following breakers: Insert Sync switch handle and Breaker 110. turn to ON.
Breaker 111. Breaker switch to AFTER CLOSE.
RED light ON.
[ SAT ] [ UNSAT ]
5 Turn off Sync switch. CB-20 Turn Sync switch handle to OFF.
[ SAT ] [ UNSAT ]
Page 4 of 8
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-7 Rev 2 JPM
Title:
Transfer 4160V Buses from 345 KV to 161 KV STEP ELEMENT STANDARD 6 Enter OI-EE-1, Attachment 1. Enters OI-EE-1, Attachment 1.
7 Ensure both fast Transfer CB-20 switches in manual: Both switches in MANUAL.
43/1A1-1A3.
43/1A2-1A4. [ SAT ] [ UNSAT ]
8 Read Note Reads Note on middle of OI-EE-1, page 4
[ SAT ] [ UNSAT ]
Note: Buses 1A3 and 1A4 may be transferred in either order.
9 Turn 1A33 Synchroscope ON. CB-20 Insert Sync switch handle and turn to ON.
[ SAT ] [ UNSAT ]
10 Verify incoming and running CB-20 voltages are matched. Verify voltages within 25 volts.
[ SAT ] [ UNSAT ]
11 Verify Synchroscope at 12 CB-20 o'clock. Indicator at 12 o'clock.
[ SAT ] [ UNSAT ]
12 Close Breaker 1A33. CB-20 Breaker 1A33 in AFTER CLOSE, RED light ON.
[ SAT ] [ UNSAT ]
Page 5 of 8
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-7 Rev 2 JPM
Title:
Transfer 4160V Buses from 345 KV to 161 KV STEP ELEMENT STANDARD 13 Open Breaker 1A13 CB-20 Breaker 1A13 in AFTER TRIP.
GREEN light ON
[ SAT ] [ UNSAT ]
14 Turn Off Synchroscope. CB-20 Sync switch handle to OFF Verify loads still energized
[ SAT ] [ UNSAT ]
15 Turn 1A44 Synchroscope ON. CB-20 Insert Sync switch handle and turn to ON.
[ SAT ] [ UNSAT ]
16 Verify incoming and running CB-20 voltages are matched. Verify voltages within 25 volts.
[ SAT ] [ UNSAT ]
17 Verify Synchroscope at 12 CB-20 o'clock. Indicator at 12 o'clock.
[ SAT ] [ UNSAT ]
18 Close Breaker 1A44. CB-20 Breaker 1A44 in AFTER CLOSE, RED light ON.
[ SAT ] [ UNSAT ]
Page 6 of 8
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-7 Rev 2 JPM
Title:
Transfer 4160V Buses from 345 KV to 161 KV STEP ELEMENT STANDARD 19 Open Breaker 1A24. CB-20 Breaker 1A24 in AFTER TRIP.
GREEN light ON.
[ SAT ] [ UNSAT ]
20 Turn Off Synchroscope. CB-20 Sync switch handle to OFF Verify loads still energized.
[ SAT ] [ UNSAT ]
21 Verify conditions for fast CB-20 transfer met:
All lock-outs on CB-20 AMBER lights ON for all have amber light on. lock-out relays(vertical Appropriate 4160V panel).
breakers not in pull-to- Control Switches not in lock. PULL-TO-LOCK:
Power is available. o Breaker 1A13 o Breaker 1A24 Voltmeters show proper voltages.
[ SAT ] [ UNSAT ]
22 Place Fast Transfer switches in CB-20 AUTO Both Switches in AUTO.
43/1A1-1A3.
43/1A2-1A4. [ SAT ] [ UNSAT ]
Termination Criteria: Buses 1A3 and 1A4 powered from 161 KV Page 7 of 8
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-7 Rev 2 INITIAL The plant is operating at full power.
CONDITIONS: A loss of 161 KV occurred due to a grid problem.
Buses 1A3 and 1A4 transferred to 345 KV.
AOP-31, section II was entered and appropriate actions taken.
The 161 KV grid problem has been fixed and 161 KV is available.
INITIATING CUE: You are directed to restore normal 161 KV power to buses 1A3 and 1A4 using AOP-31, section II, step 10 and OI-EE-1, Attachment 1.
Page 8 of 8
AOP-31 Page 20 of 28 Section II - All 4160 V Buses Fed From 22 KV INSTRUCTIONS CONTINGENCY ACTIONS
- 10. WHEN 161 KV power is available, THEN restore normal power to Buses 1A3 and 1A4 by performing the following steps:
- a. Ensure Lockout Relay 86/161 is reset (AI-22).
- b. Ensure ALL of the following lockout relays are reset:
- 86-1/T1A-4 (AI-25)
- 86-2/T1A-4 (AI-25)
- 86-1/T1A-3 (AI-24)
- 86-2/T1A-3 (AI-24)
- 86X/FT161 (AI-46)
(continue)
R9
AOP-31 Page 21 of 28 Section II - All 4160 V Buses Fed From 22 KV INSTRUCTIONS CONTINGENCY ACTIONS
- 10. (continued)
CAUTION System Operations should be notified prior to operating any switchyard breakers or disconnect switches to ensure all personnel are clear.
- c. Synchronize and close at least one of the following breakers:
- Breaker 110
- Breaker 111
- d. Transfer buses 1A3 and 1A4 to 161 KV PER Attachment 1 of OI-EE-1, Normal Operation of 4160V System.
End of Section 4.0 R9
FORT CALHOUN STATION OI-EE-1 OPERATING INSTRUCTION PAGE 4 OF 35 C
Continuous Use Attachment 1 - Feed Vital/Non-Vital Buses From 161 KV PREREQUISITES (%) INITIALS
- 1. Procedure Revision Verification Revision No. 25 Date: 3/31/09 JEK
- 2. 161 KV is in service per OI-EG-2. JEK
- 3. IF startup of Gen G1 is being performed, N/A THEN ensure OI-EE-1-CL-A has been completed per OP-1.
PROCEDURE
- 1. Ensure both Fast Transfer Switches are in MANUAL:
! 43/1A1-1A3
! 43/1A2-1A4 NOTE Steps 2 through 5 may be performed in any order.
- 2. Transfer 1A1, Non-Vital Bus, to 161 KV as follows:
- a. Turn on Synchroscope for 1A31.
- b. Verify Incoming and Running voltages are approximately matched.
- c. Verify Synchroscope is approximately at a 12 o'clock position.
- d. Close 1A31.
- e. Open 1A11.
- f. Turn off Synchroscope.
- 3. Transfer 1A2, Non-Vital Bus, to 161 KV as follows:
- a. Turn on Synchroscope for 1A42.
- b. Verify Incoming and Running voltages are approximately matched.
R25
FORT CALHOUN STATION OI-EE-1 OPERATING INSTRUCTION PAGE 5 OF 35 C
Continuous Use Attachment 1 - Feed Vital/Non-Vital Buses From 161 KV PROCEDURE (continued) (%) INITIALS 3 c. Verify Synchroscope is approximately at a 12 o'clock position.
- d. Close 1A42.
- e. Open 1A22.
- f. Turn off Synchroscope.
- 4. Transfer 1A3, Vital Bus, to 161 KV as follows:
- a. Turn on Synchroscope for 1A33.
- b. Verify Incoming and Running voltages are approximately matched.
- c. Verify Synchroscope is approximately at a 12 o'clock position.
- d. Close 1A33.
- e. Open 1A13.
- f. Turn off Synchroscope.
- 5. Transfer 1A4, Vital Bus, to 161 KV as follows:
- a. Turn on Synchroscope for 1A44.
- b. Verify Incoming and Running voltages are approximately matched.
- c. Verify Synchroscope is approximately at a 12 o'clock position.
- d. Close 1A44.
- e. Open 1A24.
- f. Turn off Synchroscope.
R25
FORT CALHOUN STATION OI-EE-1 OPERATING INSTRUCTION PAGE 6 OF 35 C
Continuous Use Attachment 1 - Feed Vital/Non-Vital Buses From 161 KV PROCEDURE (continued) (%) INITIALS
- 6. IF the following conditions for Fast Transfer are met,
! All lock-outs on CB-20 have amber light on
! Appropriate 4160 volt breakers are not in pull-to-lock
! Power is available to transfer to THEN place both Fast Transfer Switches in AUTO.
! 43/1A1-1A3
! 43/1A2-1A4 NOTE Under certain plant conditions, while supplying all 4160 volt buses, overheat of T1A3 or T1A4 could occur. To minimize this potential, loads between the 2 transformers should be balanced as much as practicable.
- 7. Balance loads between T1A3 and T1A4 as plant conditions allow.
Completed by Date/Time /
R25
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-8 Rev 3 JPM
Title:
RPS Power Adjustment Location: Simulator Approximate Time: 15 minutes Actual Time: _________________
Reference(s): K/A# 012000 A4.02 OP-ST-RPS-0005, "RPS POWER ADJUSTMENT" Handout(s): OP-ST-RPS-0005, "RPS POWER ADJUSTMENT" RPS Scaling Amp Offset Measurement Record.
Time Critical: NO Alternate Path: NO JPM Prepared by: Jerry Koske Date: 3/23/09 Page 1 of 10
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-8 Rev 3 JPM
Title:
RPS Power Adjustment Operators Name: _____________________ Employee # ______________
All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):
SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________
Reason, if unsatisfactory:
Tools & Equipment: RPS Trip Unit Bypass Keys 1, 9 and 12 Safety Considerations: None Comments:
Page 2 of 10
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-8 Rev 3 JPM
Title:
RPS Power Adjustment TASK The Candidate performed OP-ST-RPS-0005, "RPS STANDARD: POWER ADJUSTMENT", for RPS channels A and D and adjusted channel "D" NI Power and T Power to agree with XC-105, plant secondary calorimetric power measurement.
INITIAL The plant is operating at full power.
CONDITIONS: Secondary Calorimetric measurement, XC-105, indicates the reactor is operating at 1497.5 MWt.
The STA has verified XC-105 is valid.
The prerequisites for OP-ST-RPS-0005. RPS POWER ADJUSTMENT, have been met.
INITIATING CUE: You have been directed to perform OP-ST-RPS-0005, RPS POWER ADJUSTMENT, for channels A and D, and adjust any channels that need adjustment.
Page 3 of 10
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-8 Rev 3 JPM
Title:
RPS Power Adjustment Critical Steps shown in gray STEP ELEMENT STANDARD 1 Record Channel T Scaling AI-31A/B/C/D Amp Offsets from the RPS Records Channel T Scaling Scaling Amplifier Offset Amp Offsets for channels A Measurement Record (Control and D on test data sheet 1.
Room File drawer) on Test Data Sheet 1 and verify the [ SAT ] [ UNSAT ]
Scaling Amp Offset values on the Power Range Safety Drawers.
2 Record Channel NI Scaling AI-31A/B/C/D Amp Offsets from the RPS Records Channel NI Scaling Scaling Amplifier Offset Amp Offsets for channels A nd Measurement Record (Control D on test data sheet 1 Room File drawer) on Test Data Sheet 1 and verify the [ SAT ] [ UNSAT ]
Scaling Amp Offset values on the Power Range Safety Drawers.
3 Record channels Initial T AI-31A/B/C/D Power readings from RPSCIP Records Initial T Power DVM on Test Data Sheet 1. readings for channels A and D on test data sheet 1.
[ SAT ] [ UNSAT ]
4 Record channels Initial NI AI-31A/B/C/D Power readings from RPSCIP Records Initial NI Power DVM on Test Data Sheet 1. readings for channels A and D on test data sheet 1.
[ SAT ] [ UNSAT ]
Page 4 of 10
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-8 Rev 3 JPM
Title:
RPS Power Adjustment STEP ELEMENT STANDARD 5 Subtract the Scaling Amp AI-31A/B/C/D Offset from Initial T Power Records Initial T Power reading for channels and readings - scaling amp offset record on Test Data Sheet 1. for channels A and D on test data sheet 1.
[ SAT ] [ UNSAT ]
6 Subtract the Scaling Amp AI-31A/B/C/D Offset from the Initial NI Power Records Initial NI Power reading for channels and readings - scaling amp offset record on Test Data Sheet 1. for channels A and D on test data sheet 1.
[ SAT ] [ UNSAT ]
7 Record channels Initial T Pwr AI-31A/B/C/D Calibrate and Nuclear Pwr Records Initial T Pwr Calibrate dial (Power Range Calibrate and Nuclear Pwr Monitor Drawer) settings on Calibrate dial settings for Test Data Sheet 1. channels A and D on test data sheet 1.
[ SAT ] [ UNSAT ]
8 Determine Channel that need Determines Channel "D" adjustment. differs with XC-105 by more than 1% and must be adjusted.
[ SAT ] [ UNSAT ]
9 Place RPSCIP DVM Meter AI-31D Input Switch to METER INPUT Places DVM Meter Input position. Switch to METER INPUT position.
[ SAT ] [ UNSAT ]
Page 5 of 10
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-8 Rev 3 JPM
Title:
RPS Power Adjustment STEP ELEMENT STANDARD 10 Push +10V pushbutton and AI-31D verify DVM reads +9.800 to Pushes +10V pushbutton and
+10.200V. verifies reading.
[ SAT ] [ UNSAT ]
11 Push -10V pushbutton and AI-31D verify DVM reads -9.800 to Pushes -10V pushbutton and
-10.200V. verifies reading.
[ SAT ] [ UNSAT ]
12 Push ZERO pushbutton and AI-31D verify DVM reads -0.200 to Pushes ZERO pushbutton and
+0.200V. verifies reading.
[ SAT ] [ UNSAT ]
13 Record current value of XC- Enters 1497.5 MWt on Test 105 and calculate the Thermal Data Sheet 1. Calculates the Power on Test Data Sheet 1. Thermal Power as 99.8% and enters value on Test Data Sheet 1.
[ SAT ] [ UNSAT ]
14 Enter Technical Specification CUE: Another Operator has Limiting Condition for logged into Technical Operation 2.15, Table 2-2, Speciifications.
Items 2, 3 and 9 for RPS Trip Units 1, 9 and 12. [ SAT ] [ UNSAT ]
Page 6 of 10
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-8 Rev 3 JPM
Title:
RPS Power Adjustment STEP ELEMENT STANDARD 15 Bypass trip units 1, 9 and 12. CUE: Provide TU bypass keys to candidate.
AI-31D Inserts Keys in Trip Units 1, 9 and 12 and turns to BYPASS position.
[ SAT ] [ UNSAT ]
16 Place the DVM selector switch AI-31D to NUCLEAR PWR. Selects NUCLEAR PWR on DVM selector switch
[ SAT ] [ UNSAT ]
17 Adjust the Power Range AI-31D Monitor NUCLEAR PWR Adjusts Potentiometer such CALIBRATE potentiometer that DVM reading equals 99.8 until the DVM equals the plus the NI scaling amp offset.
Thermal Power plus the NI Scaling Amp Offset. [ SAT ] [ UNSAT ]
18 Place the DVM selector switch AI-31D to T PWR. Selects T PWR on DVM selector switch
[ SAT ] [ UNSAT ]
19 Adjust T PWR CALIBRATE AI-31D potentiometer until the Adjusts Potentiometer such NUCLEAR PWR-T PWR (%) that zero deviation indicated sigma meter is nulled on sigma meter.
(0 deviation).
[ SAT ] [ UNSAT ]
Page 7 of 10
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-8 Rev 3 JPM
Title:
RPS Power Adjustment STEP ELEMENT STANDARD 20 Verify trip units are RESET, AI-31D then remove the Bypass Keys Trip Units 1, 9 and 12 not for Trip Units 1, 9 and 12. bypassed with keys removed.
[ SAT ] [ UNSAT ]
21 Exit Technical Specification CUE: Another Operator has LCO 2.15, for trip units 1, 9 and logged out of the Technical
- 12. Specification.
[ SAT ] [ UNSAT ]
22 Repeat Step 7.13 for all Determined that Channel "D" channels to be adjusted. was the only channel that needed to be adjusted.
[ SAT ] [ UNSAT ]
23 Record channels Final AI-31A/B/C/D NUCLEAR PWR CALIBRATE Record Final NUCLEAR PWR Dial settings on Test Data CALIBRATE Dial settings for Sheet 1. channels A and D.
[ SAT ] [ UNSAT ]
24 Record channels Final T AI-31A/B/C/D PWR CALIBRATE Dial settings Record Final T PWR on Test Data Sheet 1. CALIBRATE Dial settings for channels A and D.
[ SAT ] [ UNSAT ]
25 Record channels FINAL T AI-31A/B/C/D Power readings on Test Data Record Final T Power Sheet 1. readings for channels A and D.
[ SAT ] [ UNSAT ]
Page 8 of 10
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-8 Rev 3 JPM
Title:
RPS Power Adjustment STEP ELEMENT STANDARD 26 Record channels FINAL NI AI-31A/B/C/D Power readings on Test Data Record Final T Power Sheet 1. readings for channels A and D.
[ SAT ] [ UNSAT ]
CUE: Another Operator will complete this test for channels B and C.
Termination Criteria: RPS channel 'D" NI Power and T Power have been adjusted to agree with XC-105 per OP-ST-RPS-0005.
Page 9 of 10
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-8 Rev 3 INITIAL The plant is operating at full power.
CONDITIONS: Secondary Calorimetric measurement, XC-105, indicates the reactor is operating at 1497.5 MWt.
The STA has verified XC-105 is valid.
The prerequisites for OP-ST-RPS-0005. RPS POWER ADJUSTMENT, have been met.
INITIATING CUE: You have been directed to perform OP-ST-RPS-0005, RPS POWER ADJUSTMENT, for channels A and D, and adjust any channels that need adjustment.
Page 10 of 10
PAGE 1 OF 8 Fort Calhoun Station Unit No. 1 OP-ST-RPS-0005 SURVEILLANCE TEST RPS POWER ADJUSTMENT Change No. EC 42242 Reason for Change Added a precaution addressing the fluctuating RPSCIP DVM readings. Converted from WordPerfect to Word.
Requestor R. Lowery Preparer L Hautzinger Issue Date 07-17-08 3:00 pm R12
FORT CALHOUN STATION OP-ST-RPS-0005 SURVEILLANCE TEST CONTINUOUS USE PAGE 2 OF 8 RPS POWER ADJUSTMENT SAFETY RELATED
- 1. PURPOSE 1.1 Instructions for adjusting T and NI Power indication.
1.2 This test in conjunction with OP-ST-SHIFT-0001 satisfies the requirements of Technical Specifications, Section 3.1, Table 3-1, Item 1.b.
- 2. REFERENCES/COMMITMENT DOCUMENTS 2.1 Technical Specifications:
- 2.15, Table 2-2, Items 2, 3 and 9
- 3.1, Table 3-1, Item 1.a., Channel Check
- 3.1, Table 3-1, Item 1.b., Channel Adjustment 2.2 SO-G-23, Surveillance Test Program 2.3 OI-NI-1, Nuclear Instrumentation System Normal Operation
- 3. DEFINITIONS None
- 4. TEST EQUIPMENT None
- 5. PRECAUTIONS AND LIMITATIONS 5.1 All anomalies and deficiencies shall be reported immediately to the immediate Supervisor and 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.
5.2 The System Engineer shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of the completion of this test, of any marginal, unexpected or unacceptable results.
5.3 This Surveillance Test is performed on demand as necessary to provide for the adjustment of indicated RPS power.
5.4 This Surveillance Test is not required during Reactor Startup or Shutdown periods which includes Power Operation less than 25%.
R12
FORT CALHOUN STATION OP-ST-RPS-0005 SURVEILLANCE TEST CONTINUOUS USE PAGE 3 OF 8 5.5 Prior to making adjustments with power levels below 50% the Reactor Engineer or Manager-Operations is to be contacted for concurrence.
5.6 The Reactor Engineer shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of the completion of this test of any marginal, unexpected, or unacceptable results.
5.7 RPS Trip Units may be bypassed per the following Limiting Conditions for Operation (LCO):
- Technical Specifications, Section 2.15, Table 2-2, Items 2, 3 and 9 5.8 RPSCIP DVM readings fluctuate, the operator should record a best estimate average of the fluctuating values for NI and DELTA T power. Recording NI or DELTA T power when the NI - DELTA T deviation meter reads zero is not an accurate way of determining the best estimate average for either reading. (CR 2007-4657)
- 6. PREREQUISITES INITIALS/DATE 6.1 Procedure Revision Verification:
12 JEK 3/31/09 Revision No. /
JEK 6.2 Reactor power is greater than 25% and stable. / 3/31/09 CAUTION Careful consideration is required prior to adjusting the channels with lower -T power reading lower than actual power due to a flow stream anomaly. This is to ensure that -T power indication will not be excessively high in the event that the anomaly clears after adjustment is made.
6.3 IF a flow stream anomaly was confirmed AND plant conditions have stabilized, THEN the concurrence between the Manager Operations and Supervisor-Primary Systems is required prior to adjusting -T N/A power. /
Manager-Ops N/A /
Sup-Primary Sys 6.4 IF Reactor power is less than 50%, THEN notify the Reactor Engineer N/A or Manager-Operations for concurrence on performing adjustments. /
6.5 No other test is in progress which could potentially affect this test, or if JEK 3/31/09 this test were performed, could have an effect on that test. /
R12
FORT CALHOUN STATION OP-ST-RPS-0005 SURVEILLANCE TEST CONTINUOUS USE PAGE 4 OF 8 6.6 Shift Manager authorizes performance of this test:
SHIFT MANAGER Shift Manager Date/Time 3/31/09 / 0730
- 7. PROCEDURE INITIALS 7.1 Record all four (4) Channel T Scaling Amp Offsets from the RPS Scaling Amplifier Offset Measurement Record (Control Room File drawer) on Test Data Sheet 1 and verify the Scaling Amp Offset values on the Power Range Safety Drawers.
7.2 Record all four (4) Channel NI Scaling Amp Offsets from the RPS Scaling Amplifier Offset Measurement Record (Control Room File drawer) on Test Data Sheet 1 and verify the Scaling Amp Offset values on the Power Range Safety Drawers.
7.3 Record all four (4) channels Initial T Power readings from RPSCIP DVM on Test Data Sheet 1.
7.4 Record all four (4) channels Initial NI Power readings from RPSCIP DVM on Test Data Sheet 1.
7.5 Subtract the Scaling Amp Offset from Initial T Power reading for all four (4) channels and record on Test Data Sheet 1.
7.6 Subtract the Scaling Amp Offset from the Initial NI Power reading for all four (4) channels and record on Test Data Sheet 1.
7.7 Record all four (4) channels Initial T Pwr Calibrate and Nuclear Pwr Calibrate dial (Power Range Monitor Drawer) settings on Test Data Sheet 1.
7.8 Perform the following for each RPS channel to be adjusted. A B C D 7.8.1 Place RPSCIP DVM Meter Input Switch to METER INPUT position. [ ] [ ] [ ] [ ]
7.8.2 Push +10V pushbutton and verify DVM reads +9.800 to
+10.200V. [ ] [ ] [ ] [ ]
7.8.3 Push -10V pushbutton and verify DVM reads -9.800 to
-10.200V. [ ] [ ] [ ] [ ]
7.8.4 Push ZERO pushbutton and verify DVM reads -0.200 to
+0.200V. [ ] [ ] [ ] [ ]
R12
FORT CALHOUN STATION OP-ST-RPS-0005 SURVEILLANCE TEST CONTINUOUS USE PAGE 5 OF 8 7.9 Verify XC105 Is valid. STA STA 7.10 Ensure all XC105 inputs have either an active scan status or a conservative value input per RE-CPT-RX-0003. STA STA 7.11 IF XC105 input has been removed from scan, THEN ensure a conservative N/A input for current plant conditions has been input per RE-CPT-RX-0003.
STA N/A SM 7.12 Record the current value of thermal power (XC105) and calculate the Thermal Power on Test Data Sheet 1.
NOTE: RPS Channels may be adjusted in any order, but only one channel may be done at a time.
7.13 Adjust one RPS Channel by performing the following: A B C D 7.13.1 Enter Technical Specification Limiting Condition for Operation 2.15, Table 2-2, Items 2, 3 and 9 for RPS Trip Units 1, 9 and 12. [ ] [ ] [ ] [ ]
7.13.2 Bypass trip units 1, 9 and 12. [ ] [ ] [ ] [ ]
7.13.3 Place the DVM selector switch to NUCLEAR PWR. [ ] [ ] [ ] [ ]
CAUTION Ensure the Nuclear Pwr Calibrate Potentiometer is used, not the Subchannel Gain Adjust Potentiometer.
7.13.4 Adjust the Power Range Monitor NUCLEAR PWR CALIBRATE potentiometer until the DVM equals the Thermal Power plus the NI Scaling Amp Offset. [ ] [ ] [ ] [ ]
7.13.5 Place the DVM selector switch to T PWR. [ ] [ ] [ ] [ ]
7.13.6 Adjust T PWR CALIBRATE potentiometer until the NUCLEAR PWR-T PWR (%) sigma meter is nulled (0 deviation). [ ] [ ] [ ] [ ]
7.13.7 Verify trip units are RESET, then remove the Bypass Keys for Trip Units 1, 9 and 12. [ ] [ ] [ ] [ ]
R12
FORT CALHOUN STATION OP-ST-RPS-0005 SURVEILLANCE TEST CONTINUOUS USE PAGE 6 OF 8 7.13.8 Exit Technical Specification LCO 2.15, for trip units 1, 9 and
- 12. [ ] [ ] [ ] [ ]
7.14 Repeat Step 7.13 for all channels to be adjusted. [ ] [ ] [ ] [ ]
7.15 Record all four (4) channels Final NUCLEAR PWR CALIBRATE Dial settings on Test Data Sheet 1. [ ] [ ] [ ] [ ]
7.16 Record all four (4) channels Final T PWR CALIBRATE Dial settings on Test Data Sheet 1. [ ] [ ] [ ] [ ]
7.17 Record all four (4) channels FINAL T Power readings on Test Data Sheet 1. [ ] [ ] [ ] [ ]
7.18 Record all four (4) channels FINAL NI Power readings on Test Data Sheet 1. [ ] [ ] [ ] [ ]
Completed by Date/Time /
- 8. RESTORATION 8.1 Shift Manager notified this test is completed:
Shift Manager Date/Time /
- 9. ACCEPTANCE CRITERIA 9.1 Corrected RPS T Power and corrected RPS NI Power differ from the calculated %
Rated Power (Core Thermal Power) by less than 1%.
- 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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following completion of this test.
Evaluated by Date/Time /
STA Reviewed by Date/Time /
Shift Manager R12
FORT CALHOUN STATION OP-ST-RPS-0005 SURVEILLANCE TEST CONTINUOUS USE PAGE 7 OF 8 Test Data Sheet 1 - Calibration Record Thermal Power = ÷ 15 = %
(XC105)
Parameter AI-31A AI-31B AI-31C AI-31D Initial NI Power (DVM)
NI Scaling Amp Offset Initial NI Power, DVM minus scaling amp offset Initial NUCLEAR PWR CALIBRATE Dial Setting Final NUCLEAR PWR CALIBRATE Dial Setting Final NI Power (DVM)
Initial T Power (DVM)
T Scaling Amp Offset Initial T Power, DVM minus scaling amp offset Initial T PWR CALIBRATE Dial Setting Final T PWR CALIBRATE Dial Setting Final T Power (DVM)
R12
FORT CALHOUN STATION OP-ST-RPS-0005 SURVEILLANCE TEST CONTINUOUS USE PAGE 8 OF 8 Comment Sheet R12
RPS Scaling Amp Offset Measurement Record.
CHANNEL A B C D NI Power Scaling Amp 0.2 0.3 0.3 0.2 Offset Delta T Power Scaling 0.3 0.2 0.3 0.3 Amp Offset
Appendix D Scenario Outline Form ES-D-1 Facility: Fort Calhoun Scenario No: 2009-2 Revision: 3 Examiners: _________________________ Operators: _________________________
Initial Conditions: 100% Power DG-1 Out of Service replacing contactors for 2CR relays.
Turnover: Rotate Condenser Evacuation Pumps, then rotate Containment Cooling Units.
Event Malf Event Event No. No. Type* Description 1 N-BOPO Rotate Condenser Evacuation Pumps per OI-CE-1, Attachment (2 min) 3.
2 N-ATCO Rotate Containment Cooling Units In accordance with OI-VA-1.
(10 min) 3 C-ATCO Dropped CEA - Tech Spec Entry.
LE CUE C-BOPO 4 R-ATCO AOP-05 shutdown to 70% Power.
N-BOPO 5 I-ATCO Controlling Pressurizer Pressure Transmitter, PT-103Y, Fails LE CUE High.
6 C-BOPO Loss of 161 KV - Tech Spec Entry.
LE CUE 7 C-ATCO Another Dropped CEA - Manual Reactor Trip Required.
LE CUE 8 M-ALL Circulating Water Pump, CW-1C, Breaker fails to open preventing DG from loading onto bus 1A4 - Station Blackout.
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Target Quantitative Attributes (Per Scenario; See Section D.5.d) Actual Attributes
- 1. Total malfunctions (5-8) 5
- 2. Malfunctions after EOP entry (1-2) 1
- 3. Abnormal events (2-4) 3
- 4. Major transients (1-2) 1
- 5. EOPs entered/requiring substantive actions (1-2) 1
- 6. EOP contingencies requiring substantive actions (0-2) 1
- 7. Critical tasks (2-3) 2
Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-2 Revision: 3 Event No.: 1 Page 2 of 13 Event
Description:
Rotate Condenser Evacuation Pumps per OI-CE-1, Attachment 3.
Time Position Applicants Actions or Behavior BOPO Obtain copy of OI-CE-1, Attachment 3, Normal Rotation of Condenser Evacuation Pumps.
BOPO Read Notes on page 12 of procedure.
BOPO Direct EONT to ensure Seal Water Makeup is properly aligned:
FW-1351, Separator Tanks Condensate Seal Water Supplu Isolation Valve is Open FW-1349, Vacuum Pumps Separator Tanks Supply Header Isolation is Open DW-357 Condenser Vacuum Pumps Seal Water Supply Line Isolation Valve is Closed.
BOPO Direct EONT to ensure Separator Tank level is within the gage glass and at least 8 inches.
BOPO Start Condenser Evacuation Pump, FW-8C.
Note: ammeter will remain pegged for a relatively long time. This is normal.
BOPO Verify proper operation of FW-8C.
BOPO Direct EONT to throttle open VD-333, FW-43 Makeup Float bypass valve.
BOPO Stop FW-8A by placing control switch in AFTER STOP.
BOPO Direct EONT to close VD-317, FW-41 Makeup Float bypass valve.
Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-2 Revision: 3 Event No.: 2 Page 3 of 13 Event
Description:
Rotate Containment Cooling Units.
Time Position Applicants Actions or Behavior CRS Direct ATCO to place VA-3B in service and shutdown VA-7D in accordance with OI-VA-1, Attachment 1, step 2 and Attachment 2, step 4 .
(Start B shut down D following maintenance)
ATCO Obtain a copy of OI-VA-1, Attachments 1 and 2.
ATCO Momentarily place HCV-401B/D to OPEN.
ATCO Ensure HCV-401C is closed.
ATCO Momentarily place HCV-401A/C to CIRC.
ATCO Throttle open HCV-401C maintaining CCW discharge header pressure at least 70 psig.
ATCO Monitor:
FI-417, VA-1B flow TIC-421, VA-1B temperature PI-499, CCW Discharge Header Pressure TIC-2800, CCW Discharge header temperature TI-717 Fan VA-3B outlet temperature ATCO Start VA-3B and monitor:
VA-3B Current PIC-701, Fan VA-3B DP PI-707 , Fan VA-3B filter DP PI-709, Fan VA-3B Cooling Coil DP TI-717 Fan VA-3B outlet temperature ATCO Stop VA-7D ATCO Throttle close HCV-403C maintaining CCW discharge header pressure less than 125 psig ATCO Verify CC WATER FROM VA-1A NO FLOW (CB-1,2,3,A1,A1-U) in alarm ATCO Momentarily place HCV-403A/C to ISOL ATCO Momentarily place HCV-403B/D to CLOSE
Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-2 Revision: 3 Event No.: 3 Page 4 of 13 Event
Description:
Dropped CEA - Tech Spec Entry.
Time Position Applicants Actions or Behavior ATCO Identify event from Dropped Rod and other alarms (CB-4 A20 E6, CB-4 A8 A5L, B1U, B1L, B2L, B5L, C1U, C2U, C5L).
ATCO Determine that only one rod has dropped (rod #1, grp 4).
CRS Enter AOP-02 (CEA AND CONTROL SYTEM MALFUNCTIONS),
Section III (Misaligned Group 4 CEA).
CRS Read Caution and Notes. (May be performed after stabilizing plant.)
CRS Direct ATCO to stop all CEA movement.
CRS Direct BOP Operator to adjust turbine load to match reactor power.
BOPO Reduce turbine load to match reactor power using T-cold indication.
CRS Direct ATC to control pressurizer pressure (2075-2150 psia) and level (within 2% of programmed value).
ATCO Control pressurizer pressure (2075-2150 psia) and level (within 2% of programmed value).
ATCO Reset Charging Pump Bistables if needed to shutdown a Charging Pump that started automatically.
CRS Direct ATC Operator to reset rod drop bistables.
ATCO Reset rod drop bistables on:
RPS Linear Power Channels Power Range Control Channels CRS Notify System Operations of the power reduction.
CRS Notify Work Week Manager or Reactor Engineer.
Continued on Next Page
Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-2 Revision: 3 Event No.: 3 Page 5 of 13 Event
Description:
Dropped CEA - Tech Spec Entry, continued Time Position Applicants Actions or Behavior CRS LCO 2.10.2(4)e. - One full length CEA misaligned from any other CEA's in (TS) its group by 18 inches or more.
Required Actions:
Reactor power must be reduced to less than 70% within one hour.
The CEA must be realigned or declared inoperable within one hour following the power reduction.
If the CEA is declared inoperable, the reactor must be in hot shutdown within an additional 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.
CRS Inform ATC and BOP operators that Tech Specs and AOP-02 require a power reduction to less than 70% within one hour using boration.
CRS If Pressurizer pressure lowers to 2075 psia or less, then enter Technical Specification LCO 2.10.4(5) - DNBR Margin During Power Operation Above 15% of Rated Power.
Required Actions:
Restore Pressurizer Pressure greater than or equal to 2075 psia within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
Or else, reduce power to less than 15% within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-2 Revision: 3 Event No.: 4 Page 6 of 13 Event
Description:
AOP-05 Emergency Shutdown to 70% Power.
Time Position Applicants Actions or Behavior CRS Direct ATCO and BOPO to commence a power reduction using AOP-05.
CRS Read AOP-05 Notes on page 3 CRS Direct ATCO to begin boration from the SIRWT ATCO Begin boration by:
Ensuring one charging pump running Opening LCV-218-3,"Charging Pump Suction SIRWT Isolation Valve" Closing LCV-218-2, "VCT Outlet Valve" CRS Notify System Operations that power will be reduced.
BOPO Reduce turbine load using potentiometer as needed to control RCS T-cold per TDB Figure III.1, "T-ave Program."
ATCO/ Monitor and control RCS parameters during power reduction:
BOPO T-cold 527-545°F Pressurizer Level 45-60%
ATCO Maximize heaters and spray by placing each control switch in ON:
225 KW Backup Htrs Bank 1 Group 1/2/3 150 KW Backup Htrs Bank 2 Group 4/5 150 KW Backup Htrs Bank 3 Group 8/9 225 KW Backup Htrs Bank 4 Group 10/11/12 ATCO Adjust the selected Pressurizer Pressure controller setpoint pushbuttons to maintain 2100 psia, if required.
CRS Direct the shift chemist to prepare to sample the RCS due to the power (TS) reduction.
NOTE: Technical Specification 3.2 (Table 3-4) requires a sample be taken between 2-8 hours following a power change exceeding 15% power within a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period. The sample must be analyzed for Dose Equivalent I-131.
ATCO May contact the Aux Building Operator to verify sufficient Waste Holdup Tank capacity for power reduction.
Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-2 Revision: 3 Event No.: 5 Page 7 of 13 Event
Description:
Controlling Pressurizer Pressure Transmitter, PT-103Y, Fails High.
Time Position Applicants Actions or Behavior ATCO Respond to Pressurizer Pressure Off-Normal HI/LO Channel Y Alarm.
(CB-1,2,3/A4 B4)
ATCO Identify and report high indication on controlling channel and lowering pressure on other channel.
ATCO/ Refer to ARP.
BOPO CRS Direct ATCO to transfer pressurizer pressure control to channel X or take manual control of pressurizer pressure.
ATCO Transfer pressurizer pressure control to channel X or take manual control of pressurizer pressure, as directed.
ATCO Monitor and control pressurizer pressure.
CRS Notify Work Week Manager of the instrument failure.
Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-2 Revision: 3 Event No.: 6 Page 8 of 13 Event
Description:
Loss of 161 KV - Tech Spec Entry.
Time Position Applicants Actions or Behavior BOPO Identify loss of 161 KV from numerous alarms on CB-20. (CB-20 A15 A1, A2, A3, D5) (CB-20 A17 A2, C4, D2) Determine and report that busses 1A3 and 1A4 have fast transferred and are powered.
CRS Enter AOP-31, section II All 4160 busses fed from 22 KV Read Notes.
CRS/ Verify 2 FW pumps, 2 Condensate pumps and 2 Heater drain pumps BOPO operating.
CRS/ Ensure Main Generator Terminal voltage less than 22,000 volts.
BOPO CRS/ Establish balanced 4160V Bus loading on T1A1 and T1A2 by ensuring all BOPO of the following pumps are operating:
FW-2A, Condensate Pump FW-4A, Feed Pump FW-5A, Heater Drain Pump BOPO starts Heater Drain Pump, FW-5A CRS/ Verify 480 bus voltages greater than 430 volts BOPO CRS Direct BOPO to match flags on breakers 110, 111, 1A31, 1A33, 1A42, 1A44 BOPO Match flags on breakers 110, 111, 1A31, 1A33, 1A42, 1A44 (step 5 of AOP-31)
CRS Direct that signs be placed at entrances to switchgear rooms Review EOP-02, EOP-07 and EOP-20 Continued on Next Page
Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-2 Revision: 3 Event No.: 6 Page 9 of 13 Event
Description:
Loss of 161 KV - Tech Spec Entry., Continued.
CRS LCO 2.7(2)c.- Loss of both service transformers T1A-3 and T1A-4 (TS) inoperable due to a loss of the 161 KV incoming line.
Required Actions:
Verify both Diesel Generators are Operable.
Notify the NRC Operations center within four hours due to the loss of 161 KV.
Special Report must be submitted to the NRC within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
LCO 2.0.1 - LCO action requirement cannot be met Due to the loss of 161 KV and D/G-1 being inoperable, Tech Spec 2.0.1 must be entered.
Required Actions:
Place the plant in hot shutdown within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
However, taking the main generator off-line will result a loss of offsite power.
CRS Report situation to station management.
Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-2 Revision: 3 Event No.: 7 Page 10 of 13 Event
Description:
Another Dropped CEA - Manual Reactor Trip Required.
Time Position Applicants Actions or Behavior ATCO Report that another CEA has fallen into the core.
CRS Direct ATCO to trip the reactor.
ATCO Manually trip the reactor within 60 seconds of the second CEA drop.
(CT)
CRS Enters EOP-00. Directs ATCO and BOPO to perform standard post trip actions.
ATCO Perform Reactivity Control Actions:
Verify power lowering Verify negative startup rate Verify no more than one CEA not inserted Monitor for an uncontrolled RCS Cooldown Notify CRS that Reactivity Control is Met.
BOPO Verify Turbine Tripped:
Stop and Intercept Valves are Closed BOPO Verify Generator Breakers Tripped:
Breakers 3451-4/5 Generator Field Breaker BOPO Verify vital buses, 1A3 and 1A4, are energized.
Reports buses 1A3 and 1A4 are deenergized Directs EONT to Minimize DC loads per EOP/AOP Attachment 6 Reports that DG-2 is running but output breaker is open. DG-1 is out for maintenance BOPO IF SIAS has initiated, THEN verify both Diesel Generators have started.
BOPO Verify non-vital buses, 1A1 and 1A2, are energized.
Reports buses 1A1 and 1A2 are deenergized.
BOPO Verify both 125VDC buses are energized.
BOPO Verify Instrument air status:
Instrument Air pressure is at least 90 psig At least 1 air compressor running Reports that no compressors are running a IA pressure is lowering.
Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-2 Revision: 3 Event No.: 7 Page 11 of 13 Event
Description:
Another Dropped CEA - Manual Reactor Trip Required, Continued.
Time Position Applicants Actions or Behavior ATCO Verify CCW and Raw water status:
At least one CCW pump running CCW Pump Discharge Pressure > 60 psig At least 1 RW Pump running IF CCW Pump Discharge Pressure > 40 psig, THEN verify HCV-438A/B/C/D are open.
Reports that no CCW or Raw Water Pumps are operating.
ATCO Verify Inventory Control:
Pressurizer Level 30-70% trending toward 45-60%
Subcooling, at least 20°F ATCO Verify Pressure Control:
RCS Pressure 1800-2300 psia trending toward 2050-2150 psia PORVs closed ATCO Verify Core Heat Removal:
RCP NPSH adequate per Attachment 2 At least 1 RCP running Core Delta-T less than or equal to 10°F Reports that no RCPs are operating.
BOPO Ensure Main Feedwater is restoring level in at least one S/G to 35-85% NR (73-94% WR):
Both Feed Reg Valves ramped closed Both Feed Reg Bypass Valves ramped 40-45%
No more than 1 Main Feed Pump is operating No more than one Condensate pump is operating No Heater Drain Pumps are operating 43/FW Switch is in OFF Close blowdown isolation valves, HCV-1387A/B and HCV-1388A/B Reports that No FEED Pumps or Condensate Pumps are operating.
Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-2 Revision: 3 Event No.: 7 Page 12 of 13 Event
Description:
Another Dropped CEA - Manual Reactor Trip Required, Continued.
Time Position Applicants Actions or Behavior BOPO Verify Steam Dump and Bypass Valves are controlling BOTH of the following:
T-cold 525-535°F S/G Pressure 850-925 psia Reports that Steam Dump and Bypass valves are not operating.
Controls S/G pressure using HCV-1040 or MS-291 and MS-292 as needed.
ATCO Verify containment conditions:
No unexpected rise in Containment sump level No Containment Area Rad Monitor Alarms No Containment or Stack radiation monitors,RM-051/52/62, alarms No S/G blowdown or Condenser offgas radiation monitor, RM-054A/54B/57, alarms No S/G blowdown or Condenser offgas radiation monitor, RM-054A/54B/57, upward trends Containment pressure < 3 psig AND Containment Temp < 120°F CRS If bus 1A4 is repowered, then enter EOP-02, "LOSS OF OFFSITE POWER, LOSS OF FORCED CIRCULATION,"
If bus 1A4 is not powered, then enter EOP-07, "STATION BLACKOUT"
Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-2 Revision: 3 Event No.: 8 Page 13 of 13 Event
Description:
Circulating Water Pump, CW-1C, Breaker fails to open preventing DG from loading onto bus 1A4 - Station Blackout.
Time Position Applicants Actions or Behavior BOPO Report that CW-1C breaker failed to trip within 15 minutes of reactor trip.
(CT) (This prevents D/G-2 breaker from closing) Direct EONT to manually trip the breaker for CW-1C.
(NOTE: EONT will trip breaker on Lead Examiner CUE).
CRS When D/G-2 output breaker closes, Direct BOPO to verify bus 1A4 voltage.
CRS If EOP-07 was entered, Transitions to EOP-02, "
Scenario ends when EOP-02 has been entered.
FORT CALHOUN STATION FC-95 FORM SHIFT TURNOVER LOG Rev. 29 Modes 1, 2, or 3 03/31/09, 0600 Days Nights X PLANT STATUS:
MODE: 1 X 2 3 Rx Power: 98.60% Rod Position: All Groups ARO Prcs (>2075 psia): 2091 psia Tcold (<543°F): 542.8 °F Lpzr (48 - 60%): 60 % (Actual)
Comments:
SAFEGUARDS STATUS:
(Log any out-of-service safeguards equipment; include major fire protection equipment)
DG-1 RECENT TEMP MODS: (Within the last month)
TM Number Date Description None DEGRADED EQUIPMENT STATUS CR Number Component/System Reason Considered Degraded Resolution 2009003571 DG-1 Out of Service - Replacing contactors for 2CR relays.
SO-O-1 FC/FORM Page 1 of 3
FORT CALHOUN STATION FC-95 FORM SHIFT TURNOVER LOG Rev. 29 Modes 1, 2, or 3 03/31/09, 0600 RELEASES IN PROGRESS: YES NO RELEASE #
Monitor Tank: A B X Waste Gas Decay Tank: A B C D X Containment Pressure Reduction X PROCEDURES and SURVEILLANCE IN PROGRESS/OVERDUE:
PROCEDURE or TEST REASON None CRS review and discuss procedures in progress (Initial)
INSTRUMENT / ANNUNCIATE STATUS (REQUIRING COMPENSATORY ACTION):
ITEM / LOCATION DATE ACTION REQUIRED None TEMPORARY LIFTS:
TAGOUT # EQUIPMENT REASON None POST MAINTENANCE TESTING:
(Equipment, instrument or annunciator requiring PMT for operability)
AVAILABLE Component YES NO PMT REQUIRED FOR OPERABILITY None TECHNICAL SPECIFICATION LCO'S and ODCM / SO-G-103 RESTRICTIONS:
REPORT MADE EQUIP OOS DATE/TIME T.S. / ODCM / G-103 LCO YES NO N/A DG-1 3/31/2009 / 0540 TS 2.7(2)j 7 Day X SO-O-1 FC/FORM Page 2 of 3
FORT CALHOUN STATION FC-95 FORM SHIFT TURNOVER LOG Rev. 29 Modes 1, 2, or 3 03/31/09, 0600 REMARKS:
- Rotate Condenser Evacuation Pumps, FW-8C on and FW-8A Off per OI-CE-1, Attachment 3.
- Place VA-3A in service then shut down VA-7D per OI-VA-1, Attachments 1 and 2.
RCS Boron 998 ppm Neutral Blend (gal acid /gal water)10 / 55 Additions this shift:2 additions of 20 gallons or demineralized water to raise reactor power CRS review ERF alarms and discuss with oncoming CRS: __________
Off going On coming S.M.
C.R.S.
L.O. 1 L.O. 2 STA Fire Brigade Leader Communicator ____
Security Key Transferred (Init)
SO-O-1 FC/FORM Page 3 of 3
FORT CALHOUN STATION FC-75A FORM R4 PROTECTED DQUIPMENT AND OUT-OF-NORMAL SWITCH POSITION/ANNUNCIATOR IN ALARM LIST Date: 03/31/09 Shift (Circle one) 0600-1800 1800-0600 NOTE: the Out-of-Normal position switch and Annunciator Alarm list must include a detailed reason justifying why the switch is in the current position or why the annunciator is in alarm. If the condition is due to an ongoing Surveillance Test or Operating Instruction, then the specific procedure number and step must be listed.
Switch Location Annunciators in Alarm Reason out-of-position/in alarm 43-1/D1 AI-30A DG-1 Out of Service 43-1/1AD1 AI-30A '
BKR 1AD1 CB-20 '
AI-30A/A30,B-4 DIESEL OFF AUTO '
AI-30A/A30,D-4 BKR OFF AUTO '
AI-30A/A30,E-3 BKR PROTECTION OFF-AUTO '
AI-30A/A30, E-4 PANEL TROUBLE '
CB-1,2,3/A1 B-1U CC WATER FROM COIL VA_1B NO FLOW VA-1B is not operating PROTECTED EQUIPMENT SIGN LOCATION REASON PROTECTED DG-2 DG-2 Mode Selector Switch DG-1 Out of Service BRKR 1AD2
FORT CALHOUN STATION OI-VA-1 OPERATING PROCEDURE C PAGE 5 OF 173 Continuous Use Attachment 1 - Containment Cooling and Filtering Operation VA-3A & VA-3B PREREQUISITES (9) INITIALS
- 1. Procedure Revision Verification JEK Revision No. 68 Date: 3/31/09
- 2. OI-VA-1-CL-A has been completed per OP-1. JEK
- 3. IF Containment Cooling is desired, THEN CCW is in service and at least one of the following Containment Cooling Coils is operable:
- VA-1A X
- VA-1B X JEK
- 4. Electrical power is available to the desired fan(s):
- VA-3A, Cont Cooling & Filter Fan, 1B3A-7 X
- VA-3B, Cont Cooling & Filter Fan, 1B4C-8 X JEK R68
FORT CALHOUN STATION OI-VA-1 OPERATING PROCEDURE C PAGE 6 OF 173 Continuous Use Attachment 1 - Containment Cooling and Filtering Operation VA-3A & VA-3B PROCEDURE (9) INITIALS NOTES
- 1. Containment HEPA/Charcoal Filter Unit may be in service while painting or other activities in containment as long as volatile organic compound (VOC) to be released in containment does not exceed administrative limits specified in GM-RR-MX-1050. The administrative limits given in the coating procedure is determined to have negligible affect on filter performance.
- 2. HCV-724A, VA-3A Filtered Air Inlet Damper is permanently open and HCV-724B, VA-3A Unfiltered Air Inlet Damper is permanently closed which puts filters in service (EC 41115). Control Solenoids are AIPE.
CAUTION During Power Operations either VA-3A and VA-7C OR VA-3B and VA-7D must be maintained operable. (SAO 07-003 and CR 2007-3052)
- 1. IF VA-3A, Containment Vent Fan, is to be started, THEN perform the following:
- a. IF Containment Cooling is desired, THEN initiate CCW to VA-1A as follows:
- 2) Ensure HCV-400C, Cntmt Clg Coil VA-1A Outlt Isol Vlv Cntrlr is closed.
- 4) Throttle open HCV-400C maintaining PI-499, CCW Discharge Header Pressure, greater than or equal to 70 psig.
R68
FORT CALHOUN STATION OI-VA-1 OPERATING PROCEDURE C PAGE 7 OF 173 Continuous Use Attachment 1 - Containment Cooling and Filtering Operation VA-3A & VA-3B PROCEDURE (continued) (9) INITIALS 1.a
- 5) Monitor the following parameters:
- FI-416, VA-1A Flow
- TIC-420, VA-1A Temp
- TI-715, Fan VA-3A Outlt Temp (AI-44)
CAUTION Running a fan for an 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-3A and monitor the following:
- VA-3A amps
- PIC-700, Fan VA-3A Diff Press (AI-44)
- PI-706, Fan VA-3A Filter Diff Press (AI-44)
- PI-708, Fan VA-3A Clg Coil Diff Press (AI-44)
- TI-715, Fan VA-3A Outlt Temp (AI-44)
NOTE HCV-725A, VA-3B Filtered Air Inlet Damper is permanently open and HCV-725B, VA-3B Unfiltered Air Inlet Damper is permanently closed which puts filters in service (EC 41115). Control Solenoids are AIPE.
- 2. IF VA-3B, Cntmt Vent Fan, is to be started, THEN perform the following:
- a. IF Containment Cooling is desired, THEN initiate CCW to VA-1B as follows:
- 2) Ensure HCV-401C, Cntmt Clg Coil VA-1B Outlt Isol Vlv Cntrlr is closed.
R68
FORT CALHOUN STATION OI-VA-1 OPERATING PROCEDURE C PAGE 8 OF 173 Continuous Use Attachment 1 - Containment Cooling and Filtering Operation VA-3A & VA-3B PROCEDURE (continued) (9) INITIALS 2.a.
- 4) Throttle open HCV-401C maintaining PI-499, CCW Discharge Header Pressure, greater than or equal to 70 psig.
- 5) Monitor the following parameters:
- FI-417, VA-1B Flow
- TIC-421, VA-1B Temp
- TI-717, FAN VA-3B Outlet Temp (AI-44)
CAUTION Running a fan for an 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-3B and monitor the following:
- VA-3B amps
- PIC-701, Fan VA-3B Diff Press (AI-44)
- PI-707, Fan VA-3B Filter Diff Press (AI-44)
- PI-709, Fan VA-3B Clg Coil Diff Press (AI-44)
- TI-717, Fan VA-3B Outlt Temp (AI-44)
- 3. IF VA-3A is to be shutdown, THEN perform the following:
- a. Stop VA-3A, Cntmt Vent Fan. (AI-30A)
- 1) Throttle close HCV-400C, Cntmt Clg Coil VA-1A Outlt Isol Vlv Cntrlr maintaining PI-499, CCW Discharge Header Pressure, less than 125 psig.
R68
FORT CALHOUN STATION OI-VA-1 OPERATING PROCEDURE C PAGE 9 OF 173 Continuous Use Attachment 1 - Containment Cooling and Filtering Operation VA-3A & VA-3B PROCEDURE (continued) (9) INITIALS 3.b.
- 2) Verify CC WATER FROM VA-1A NO FLOW (CB-1,2,3, A1, A-1U) in alarm.
- 3) Momentarily place Cntmt Clg Coil VA-1A Isol Vlvs Control SW HCV-400A/C to ISOL.
- 4) Momentarily place Cntmt Clg Coil VA-1A Vlvs Control SW HCV-400B/D to CLOSE.
- 4. IF VA-3B is to be shutdown, THEN perform the following:
- a. Stop VA-3B, Cntmt Vent Fan (AI-30B).
- 1) Throttle close Cntmt Clg Coil VA-1B Outlt Isol Vlv Cntrlr HCV-401C maintaining PI-499, CCW Discharge Header Pressure, less than 125 psig.
- 2) Verify CC WATER FROM VA-1B NO FLOW (CB-1,2,3, A1, B-1U) in alarm.
- 3) Momentarily place HCV-401A/C, Cntmt Clg Coil VA-1B Isol Vlvs Control SW to ISOL.
- 4) Momentarily place HCV-401B/D, Cntmt Clg Coil VA-1B Vlvs Control SW to CLOSE.
- 5. Record filter operating times in OP-ST-SHIFT-0001.
Completed by Date/Time /
R68
FORT CALHOUN STATION OI-VA-1 OPERATING PROCEDURE C PAGE 10 OF 173 Continuous Use Attachment 2 - Containment Cooling Operation VA-7C & VA-7D PREREQUISITES (9) INITIALS
- 1. Procedure Revision Verification:
Revision No. 68 Date: 3/31/09 JEK
- 2. OI-VA-1-CL-A has been completed per OP-1. JEK
- 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 X X JEK
- VA-8B
- 4. Electrical power is available to the desired fan(s):
- VA-7C, Containment Air Cooling Fan, 1B3C-4C-3 X
- VA-7D, Containment Air Cooling Fan, 1B3B-4B-4 X JEK PROCEDURE CAUTION During Power Operations either VA-3A and VA-7C OR VA-3B and VA-7D must be maintained operable. (SAO 07-003 and CR 2007-3052)
- 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:
- 2) Ensure HCV-402C, Cntmt Clg Coil VA-8A Outlt Isol Vlv Cntrlr is closed.
R68
FORT CALHOUN STATION OI-VA-1 OPERATING PROCEDURE C PAGE 11 OF 173 Continuous Use Attachment 2 - Containment Cooling Operation VA-7C & VA-7D PROCEDURE (continued) (9) INITIALS 1.a.
- 4) Throttle open HCV-402C maintaining PI-499, CCW Discharge Header Pressure, greater than or equal to 70 psig.
- 5) Monitor the following parameters:
- FI-418, VA-8A Flow
- TIC-422, VA-8A Temp
- TIC-2800, CCW Discharge Header Temp CAUTION Running a fan for an 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:
- 2) Ensure HCV-403C, Cntmt Clg Coil VA-8B OUTLT Isol Vlv Cntrlr is closed.
- 4) Throttle open HCV-403C maintaining PI-499, CCW Discharge Header Pressure, greater than or equal to 70 psig.
R68
FORT CALHOUN STATION OI-VA-1 OPERATING PROCEDURE C PAGE 12 OF 173 Continuous Use Attachment 2 - Containment Cooling Operation VA-7C & VA-7D PROCEDURE (continued) (9) INITIALS 2.a.
- 5) Monitor the following parameters:
- FI-419, VA-8B Flow
- TIC-423, VA-8B Temp
- TIC-2800, CCW Discharge Header Temp CAUTION Running a fan for an 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).
- 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.
R68
FORT CALHOUN STATION OI-VA-1 OPERATING PROCEDURE C PAGE 13 OF 173 Continuous Use Attachment 2 - Containment Cooling Operation VA-7C & VA-7D PROCEDURE (continued) (9) INITIALS
- 4. IF VA-7D, Cntmt Vent Fan, is to be shutdown, THEN perform the following:
- a. Stop VA-7D (AI-30B).
- 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 /
R68
FORT CALHOUN STATION OI-CE-1 OPERATING INSTRUCTION PAGE 11 OF 22 C
Continuous Use Attachment 3 - Normal Rotation of Condenser Evacuation Pumps PREREQUISITES % INITIALS
- 1. Procedure Revision Verification:
Revision No. 24 Date: 3/31/09 JEK
- 2. Power is available for the selected condenser evacuation pump:
! FW-8A, Condenser Evacuation Pump, 1B3B-7
! FW-8B, Condenser Evacuation Pump, 1B4A-4
! FW-8C, Condenser Evacuation Pump, 1B3B-4B-2 X JEK R24
FORT CALHOUN STATION OI-CE-1 OPERATING INSTRUCTION PAGE 12 OF 22 C
Continuous Use Attachment 3 - Normal Rotation of Condenser Evacuation Pumps PROCEDURE % INITIALS NOTES
- 1. The order of pump rotation is A-B-C.
- 2. Seal Water Makeup can be supplied from the Condensate System or the Demineralized Water System as follows:
- a. DW-357, Condenser Vacuum Pumps, FW-8A-8C Seal Water Supply Line Isolation Valve
! Normally used during startup (Pumps DW-40A/B must be running)
- b. FW-1351, Separator Tanks FW-41, 42 & 43 Condensate Seal Water Supply Isolation Valve
! Normally used after a Condensate Pump is started
- c. FW-1349, Vacuum Pumps FW-8A-8C Separator Tanks FW-41-43 Supply Header Isolation Valve
! Normally used as a backup if the Condensate Storage Tank is full
- 1. IF a Condensate Pump is running, THEN ensure Seal Water Makeup is aligned as follows.
! FW-1351, Separator Tanks FW-41, 42 & 43 Condensate Seal Water Supply Isolation Valve, is open
! FW-1349, Vacuum Pumps FW-8A-8C Separator Tanks FW-41-43 Supply Header Isolation Valve, is open
! DW-357,Condenser Vacuum Pumps FW-8A-8C Seal Water Supply Line Isolation Valve (Col. B-5), is closed R24
FORT CALHOUN STATION OI-CE-1 OPERATING INSTRUCTION PAGE 13 OF 22 C
Continuous Use Attachment 3 - Normal Rotation of Condenser Evacuation Pumps PROCEDURE (continued) % INITIALS
- 2. IF no Condensate Pump is running, THEN ensure Seal Water Makeup is aligned as follows.
! FW-1351, Separator Tanks FW-41, 42 & 43 Condensate Seal Water Supply Isolation Valve, is closed
! FW-1349, Vacuum Pumps FW-8A-8C Separator Tanks FW-41-43 Supply Header Isolation Valve, is closed
! DW-357,Condenser Vacuum Pumps FW-8A-8C Seal Water Supply Line Isolation Valve (Col. B-5), is open
- 3. Ensure that the Separator Tank level reads within the gauge glass and at least eight inches prior to starting the Condenser Evacuation Pump.
- 4. Start the Standby Condenser Evacuation Pump (CB-10/11).
- 5. Verify proper operation of the Condenser Evacuation Pump started.
NOTE Condenser Evacuation Separator Tanks are continuously overflowed to minimize the build up of Ammonia in the system.
- 6. Commence continuous feed and bleed of the Condenser Evacuation Separator Tank by throttling open the bypass valve:
! VD-317, Separator Tank FW-41 Makeup Float Bypass Valve (FW-8A)
! VD-325, Separator Tank FW-42 Makeup Float Bypass Valve (FW-8B)
! VD-333, Separator Tank FW-43 Makeup Float Bypass Valve (FW-8C)
- 7. Place the control switch for the Condenser Evacuation Pump being placed in Standby in AFTER STOP (CB-10/11).
- 8. Stop the continuous feed and bleed of the Condenser Evacuation Separator Tank for the Condenser Evacuation Pump being placed in Standby by closing the bypass valve:
! VD-317
! VD-325
! VD-333 Completed by Date/Time /
R24
Appendix D Scenario Outline Form ES-D-1 Facility: Fort Calhoun Scenario No: 2009-4 Revision: 5 Examiners: _________________________ Operators: _________________________
Initial Conditions: 50% Power, Diesel Driven AFW Pump, FW-54, Out of Service, Main Feed Pumps, FW-4A and FW-4C, Out of Service.
Turnover: Maintain 50% operation. Rotate CCW Pumps.
Event Malf Event Event No. No. Type* Description 1 N-ATCO Rotate CCW Pumps.
(2 min) 2 C-BOPO Isolated Phase Bus Duct Cooling Fan Motor Trips.
LE CUE 3 I-ATCO Pressurizer Pressure Safety Channel fails Low - Tech Spec LE CUE TS-CRS Entry.
4 I-BOPO Steam header pressure transmitter, PT-910 Fails High.
LE CUE 5 C - ATCO 10-15 gpm leak to containment - Tech Spec Entry.
LE CUE TS-CRS 6 C - ATCO Feedwater Pump Trips, Reactor Trip.
LE CUE 7 C-BOPO Blowdown fails to isolate automatically.
8 M - ALL Pipe from EFWST to FW-6 and FW-10 breaks. Total Loss of LE CUE Feedwater.
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Target Quantitative Attributes (Per Scenario; See Section D.5.d) Actual Attributes
- 1. Total malfunctions (5-8) 7
- 2. Malfunctions after EOP entry (1-2) 2
- 3. Abnormal events (2-4) 2
- 4. Major transients (1-2) 1
- 5. EOPs entered/requiring substantive actions (1-2) 1
- 6. EOP contingencies requiring substantive actions (0-2) 1
- 7. Critical tasks (2-3) 2 or 3
Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-4 Revision: 5 Event No.: 1 Page 2 of 12 Event
Description:
Rotate CCW Pumps.
Time Position Applicants Actions or Behavior CRS Directs ATCO to switch operating CCW pump from Pump AC-3A to Pump AC-3C.
ATCO Obtains and reviews Procedure OI-CC-1, Attachment 2.
ATCO Directs EONA to Room 69.
ATCO Read Notes on top of page 9.
ATCO Starts pump AC-3C.
CRS/ Logs into Technical Specification 2.4(1)b.
ATCO ATCO Directs EONA to close AC-102, "Pump AC-3A discharge valve."
EONA reports that AC-102 is closed.
ATCO Verify that PI-499, CCW Pump Discharge Header Pressure, indicates approximately 90 psig.
ATCO Stops pump AC-3A.
ATCO Ensures proper operation of pump AC-3C. Directs EONT to reopen Valve AC-102.
ATCO Directs EONA to open AC-102, "Pump AC-3A discharge valve."
EONT reports that AC-102 is open.
CRS/ Exits Technical Specification 2.4(1)b.
ATCO
Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-4 Revision: 5 Event No.: 2 Page 3 of 12 Event
Description:
Isolated Phase Bus Duct Cooling Fan Motor Trips.
Time Position Applicants Actions or Behavior BOPO Respond to "ISO PHASE BUS AIR FLOW LO" alarm. ( CB-10,11/A10, A-6U)
BOPO Determines that the Cooling Fan Motor is not operating.
BOPO May attempt to restart the Cooling Fan.
CRS/ Direct Electrical Maintenance or EONT to change the belt to the other Bus BOPO Duct Cooling Fan Motor.
BOPO Check that generator output is less than 11,200 amps.
BOPO May monitor each phase temperature.
Electrical Maintenance or the EONT reports that the belt has been changed over.
BOPO Start the alternate Cooling Fan Motor.
BOPO Verify low flow alarm clears.
CRS May refer to AOP-27, "GENERATOR MALFUNCTIONS."
Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-4 Revision: 5 Event No.: 3 Page 4 of 12 Event
Description:
Pressurizer Pressure Safety Channel fails Low - Tech Spec Entry Time Position Applicants Actions or Behavior ATCO Respond to "PRESSURIZER SAFETY INJ SIGNAL LO-LO PRESSURE C/P102Y" (CB-1,2,3,/A4, C-5), "TM/LOW PRESSURE CHANNEL TRIP"(CB-4/A20, A-5) and "TM/LOW PRESSURE CHANNEL PRETRIP"(CB-4/A20, B-5)
ATCO Refer to ARPs.
or BOPO ATCO Check redundant channels and report failure of C/P102Y.
ATCO Verify the following:
Pressurizer pressure RCS Cold Leg Temperatures Axial Shape Index Reactor Power, NI and Delta-T CRS LCO 2.15(1) - The number of channels for the TM/LP and High Pressurizer (TS) Pressure trips in service falls one below the total number of installed channels (see Table 2-2). And the number of channels for PPLS actuation in service falls one below the total number of installed channels. (see Table 2-3).
Requires Actions:
The Thermal Margin/ Low Pressure and High Pressurizer Pressure channels must be bypassed or tripped within one hour.
The channels may be bypassed for up to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, after that it must be placed in the tripped position.
CRS Direct the ATCO to bypass channel "C" High Pressurizer Pressure trip unit
- 8 and TM/LP trip unit #9 .
ATCO Place channel "C" trip units #8 and #9 in bypass.
CRS Notify Work Week Manager of instrument Failure.
Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-4 Revision: 5 Event No.: 4 Page 5 of 12 Event
Description:
Steam header pressure transmitter, PT-910 Fails High.
Time Position Applicants Actions or Behavior BOPO Identify rapid decrease in RCS T-cold (VARIABLE OVERPOWER RESET DEMAND, CB-4, A20, C-7) will alarm if uncorrected).
ATCO/ If "VARIABLE OVERPOWER RESET DEMAND",(CB-4, A20, C-7)
BOPO alarms, enter ARP CB-4/A20.
BOPO Recognize PCV-910, "Main Steam Bypass Valve," being open (red light on CB-1,2,3).
BOPO Determine that Steam Header Pressure Transmitter, PT-910 failed high.
CRS Direct BOP to take manual control of PCV-910 and close it.
BOPO Manually close PCV-910 BOPO Monitor RCS T-cold.
ATCO Monitor and control RCS parameters.
CRS Notify Work Week Manager or I&C of the failure of PT-910.
CRS If Pressurizer pressure lowers to 2075 psia or less, then enter Technical Specification LCO 2.10.4(5) - DNBR Margin During Power Operation Above 15% of Rated Power.
Required Actions:
Restore Pressurizer Pressure greater than or equal to 2075 psia within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
Or else, reduce power to less than 15% within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-4 Revision: 5 Event No.: 5 Page 6 of 12 Event
Description:
10-15 gpm leak to containment - Tech Spec Entry.
Time Position Applicants Actions or Behavior ATCO Respond to RM-050 CNTMT PARTICULATE HIGH RADIATION Alarm. (AI-33C/A33C, 1)
ATCO Enter ARP. Verify high radiation on ratemeter.
ATCO Check containment area monitors, report rising dose rates.
CRS/ Check for indication of RCS leakage into containment:
ATCO Dewpoint Temperature Containment Pressure Containment Sump Level Pressurizer Level ATCO Trend Pressurizer level, VCT level, charging and letdown and report to CRS.
CRS Enter AOP-22, "REACTOR COOLANT LEAK",Section I, "Leak Rate Determination and Leak Isolation" CRS Read Cautions and Notes.
CRS Direct Shift Chemist to perform a rapid activity analysis of both S/Gs CRS Ask Shift Manager to implement the Emergency Plan.
CRS/ Determine the RCS leak rate to be approximately 15 gpm.
ATCO CRS Direct Shift Chemist to verify primary to secondary leakrate.
CRS LCO 2.1.4(1) - Greater than 1 gpm unidentified leakage or greater than 10 (TS) gpm identified leakage.
Required Actions:
Reduce leakage to within limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
or else be in hot shutdown within an additional 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and be in cold shutdown within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
If Pressure Boundary Leakage is identified, then:
be in hot shutdown within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and be in cold shutdown within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-4 Revision: 5 Event No.: 5 Page 7 of 12 Event
Description:
10-15 gpm leak to containment - Tech Spec Entry., continued.
Time Position Applicants Actions or Behavior CRS Direct ATCO to isolate letdown and charging.
ATCO Isolate letdown and charging and check leakage rate. Determines that the leak was not isolated.
CRS/ Restore charging and letdown.
ATCO CRS Refer to Attachment A, "Leak Location Guide", determine leak is to Containment.
ATCO Check the rate of level rise in the quench tank.
CRS/ Direct the EONA to check the rate of level rise in the RCDT and Auxiliary ATCO Building Sumps and to visually inspect the Auxiliary Building.
CRS/ Direct Radiation Protection to sample the Auxiliary Building atmosphere ATCO and check the continuous air monitors.
CRS/ Direct the EONA or Chemist to close Sample Isolation Valves, HCV-2500, ATCO 2501, 2502 and 2503, in Room 60.
ATCO Close RCS Sample Isolation Valves, HCV-2504A and HCV-2504B.
CRS/ Direct Chemistry to check the sampling lineups.
ATCO ATCO Start all available Containment Vent Fans and ensure CCW is supplied to the cooling coils.
CRS/ Direct the EONA to place both Containment Sump Pumps in "PULL TO ATCO LOCK."
ATCO Close both Containment Sump Isolation Valves, HCV-506A and HCV-506B.
CRS Direct plant shutdown using either OP-4, "LOAD CHANGE AND NORMAL POWER OPERATION" or AOP-05, "EMERGENCY SHUTDOWN". Will enter AOP-22, "Section II - Reactor Coolant Leak Less Than 40 gpm," after plant shutdown.
Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-4 Revision: 5 Event No.: 6, 7 Page 8 of 12 Event
Description:
Feedwater Pump Trips, Reactor Trip, Blowdown fails to isolate automatically.
Time Position Applicants Actions or Behavior BOPO Determine that the running Feedwater Pump has tripped.
CRS Direct the ATCO to manually trip the reactor.
ATCO Manually trip the reactor.
CRS Enters EOP-00. Directs ATCO and BOPO to perform Standard Post Trip Actions.
ATCO Perform Reactivity Control Actions:
Verify power lowering Verify negative startup rate Verify no more than one CEA not inserted Monitor for an uncontrolled RCS Cooldown Notify CRS that Reactivity Control is Met BOPO Verify Turbine Tripped:
Stop and Intercept Valves are Closed BOPO Verify Generator Breakers Tripped:
Breakers 3451-4/5 Generator Field Breaker BOPO Verify vital buses, 1A3 and 1A4, are energized.
BOPO IF SIAS has initiated, THEN verify both Diesel Generators have started.
BOPO Verify non-vital buses, 1A1 and 1A2, are energized.
BOPO Verify both 125VDC buses are energized.
BOPO Verify Instrument air status:
Instrument Air pressure is at least 90 psig At least 1 air compressor running
Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-4 Revision: 5 Event No.: 6, 7 Page 9 of 12 Event
Description:
Feedwater Pump Trips, Reactor Trip, Blowdown fails to isolate automatically, continued Time Position Applicants Actions or Behavior ATCO Verify CCW and Raw water status:
At least one CCW pump running CCW Pump Discharge Pressure > 60 psig At least 1 RW Pump running IF CCW Pump Discharge Pressure > 40 psig, THEN verify HCV-438A/B/C/D are open ATCO Verify Inventory Control:
Pressurizer Level 30-70% trending toward 45-60%
Subcooling, at least 20°F ATCO Verify Pressure Control:
RCS Pressure 1800-2300 psia trending toward 2050-2150 psia PORVs closed ATCO Verify Core Heat Removal:
RCP NPSH adequate per Attachment 2 At least 1 RCP running Core Delta-T less than or equal to 10°F BOPO Ensure Main Feedwater is restoring level in at least one S/G to 35-85% NR (73-94% WR):
Both Feed Reg Valves ramped closed Both Feed Reg Bypass Valves ramped 40-45%
No more than 1 Main Feed Pump is operating No more than one Condensate pump is operating No Heater Drain Pumps are operating 43/FW Switch is in OFF BOPO Determines DCS has not throttled blowdown flow, manually isolates (CT) blowdown by closing HCV-1387A/B and HCV-1388A/B within 15 minutes of feedwater pump trip.
BOPO Reports no running Main Feed Pumps. Establishes AFW Flow using Motor Driven AFW Pump, FW-6, or Turbine Driven AFW Pump, FW-10.
Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-4 Revision: 5 Event No.: 6, 7 Page 10 of 12 Event
Description:
Feedwater Pump Trips, Reactor Trip, Blowdown fails to isolate automatically, continued.
Time Position Applicants Actions or Behavior BOPO Verify Steam Dump and Bypass Valves are controlling BOTH of the following:
T-cold 525-535°F S/G Pressure 850-925 psia ATCO Verify containment conditions:
No unexpected rise in Containment sump level No Containment Area Rad Monitor Alarms No Containment or Stack radiation monitors,RM-051/52/62, alarms No S/G blowdown or Condenser offgas radiation monitor, RM-054A/54B/57, alarms No S/G blowdown or Condenser offgas radiation monitor, RM-054A/54B/57, upward trends Containment pressure < 3 psig AND Containment Temp < 120°F Reports that containment sump level is rising.
CRS Performs diagnostic actions and enters EOP-03, "LOSS OF COOLANT ACCIDENT."
(Note: May also enter EOP-01, "REACTOR TRIP RECOVERY," and AOP-22, "Section II - Reactor Coolant Leak Less Than 40 gpm," since pressurizer pressure is greater than 1800 psia and stable or rising.)
Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-4 Revision: 5 Event No.: 8 Page 11 of 12 Event
Description:
Pipe from EFWST to FW-6 and FW-10 breaks. Total Loss of Feedwater.
Time Position Applicants Actions or Behavior BOPO Reports loss of AFW Flow.
CRS Transitions to EOP-20, "FUNCTIONAL RECOVERY.", Success path, HR-1.
(NOTE: If EOP-01 entered previously, then may enter EOP-06, "LOSS OF ALL FEEDWATER," at this time.)
CRS Confirm Standard Post Trip Actions.
CRS Request Shift Manager to enter the Emergency Plan.
CRS Monitor the floating steps.
ATCO Trips all Reactor Coolant Pumps within 10 minutes of a total loss of (CT) feedwater being diagnosed.
BOPO Ensure Blowdown is isolated by ensuring the following valves are closed:
HCV-1387A/B HCV-1388A/B CRS Direct Shift Chemist to perform a rapid activity analysis of both steam generators.
CRS Refer to Safety Function Status Checks or Resource Assessment Trees and go to success path HR-1.
CRS Direct ATCO to insert group N CEAs. (If entered EOP-20)
ATCO Insert Group N CEAs, if directed.
ATCO Monitor for establishment of natural circulation:
Delta-T less than 50°F.
Difference between CETs and T-hot less than 10°F.
T-hot and T-cold stable or lowering.
At least 20°F subcooling.
BOPO Begin a controlled plant cooldown using steam dump and bypass valves.
ATCO Monitor RCS pressure per Attachment 2.
CRS Determines that AFW flow cannot be established.
Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-4 Revision: 5 Event No.: 8 Page 12 of 12 Event
Description:
Pipe from EFWST to FW-6 and FW-10 breaks. Total Loss of Feedwater, Continued.
Time Position Applicants Actions or Behavior CRS Direct BOPO to establish Condensate pump feed to the Steam Generators.
BOPO Establish condensate pump feed to the Steam Generators:
Place all FW Pump Control Switches in Pull-To-Lock Direct EONT to open All FW Pump discharge valves Ensure FW Pump Recirc valves are closed Start All FW Pump Lube Oil Pumps Reduce Steam Generator Pressure to less than 550 psia Direct EONT to ensure Condensate Pump Recirc Valve, FCV-1172, is closed ATCO Maintain pressurizer pressure per EOP-AOP Attachment 2 and level 10-70%.
BOPO When S/G pressure is less than 550 psig:
Block SGLS Ensure HCV-1385 and HCV-1386 are open Ensure HCV-1103 and HCV-1104 are closed Reduce pressure to achieve flow through FW bypass Valves, HCV-1105 and HCV-1106 NOTE: The next two steps are expected only if Wide Range Level in both Steam Generators falls below 27%.
CRS IF WR Level in both S/Gs falls below 27%, THEN initiate Once through (CT) Cooling using EOP-20, HR-4 (or EOP-06)
BOPO IF directed to initiate Once through cooling then:
Deenergize all pressurizer heaters.
Initiate PPLS using test switches.
Ensure HPSI pumps running and injection valves open.
Ensure PORV Block valves are open.
Open both PORVs.
Scenario ends with the Steam Generators being fed by the Condensate Pumps or with Once Through Cooling Established.
FORT CALHOUN STATION FC-95 FORM SHIFT TURNOVER LOG Rev. 29 Modes 1, 2, or 3 04/01/09, 0600 Days Nights X PLANT STATUS:
MODE: 1 X 2 3 Rx Power: 49.00% Rod Position: Group 4 @ 88" Prcs (>2075 psia): 2108 psia Tcold (<543°F): 539.6 °F Lpzr (48 - 60%): 56 % (Actual)
Comments:
SAFEGUARDS STATUS:
(Log any out-of-service safeguards equipment; include major fire protection equipment)
RECENT TEMP MODS: (Within the last month)
TM Number Date Description None DEGRADED EQUIPMENT STATUS CR Number Component/System Reason Considered Degraded Resolution 2009003501 AFW Pump FW-54 Out of Service - being repaired excessive vibration 2009003517 Feed Pump FW-2A Out of Service - motor windings shorted Motor off site for rewind 2009003521 Feed Pump FW-2C Out of Service - Seal Leakage Seals being replaced SO-O-1 FC/FORM Page 1 of 3
FORT CALHOUN STATION FC-95 FORM SHIFT TURNOVER LOG Rev. 29 Modes 1, 2, or 3 04/01/09, 0600 RELEASES IN PROGRESS: YES NO RELEASE #
Monitor Tank: A B X Waste Gas Decay Tank: A B C D X Containment Pressure Reduction X PROCEDURES and SURVEILLANCE IN PROGRESS/OVERDUE:
PROCEDURE or TEST REASON None CRS review and discuss procedures in progress (Initial)
INSTRUMENT / ANNUNCIATE STATUS (REQUIRING COMPENSATORY ACTION):
ITEM / LOCATION DATE ACTION REQUIRED None TEMPORARY LIFTS:
TAGOUT # EQUIPMENT REASON None POST MAINTENANCE TESTING:
(Equipment, instrument or annunciator requiring PMT for operability)
AVAILABLE Component YES NO PMT REQUIRED FOR OPERABILITY None TECHNICAL SPECIFICATION LCO'S and ODCM / SO-G-103 RESTRICTIONS:
REPORT MADE EQUIP OOS DATE/TIME T.S. / ODCM / G-103 LCO YES NO N/A None SO-O-1 FC/FORM Page 2 of 3
FORT CALHOUN STATION FC-95 FORM SHIFT TURNOVER LOG Rev. 29 Modes 1, 2, or 3 04/01/09, 0600 REMARKS:
- Perform Normal Rotation of CCW Pumps per OI-CC-1, Attachment 2. Place AC-3C in service, shutdown AC-3A RCS Boron 1165 ppm Neutral Blend (gal acid /gal water)10/87 Additions this shift:2 additions of 20 gallons or demineralized water to raise reactor power CRS review ERF alarms and discuss with oncoming CRS: __________
Off going On coming S.M.
C.R.S.
L.O. 1 L.O. 2 STA Fire Brigade Leader Communicator ____
Security Key Transferred (Init)
SO-O-1 FC/FORM Page 3 of 3
FORT CALHOUN STATION FC-75A FORM R4 PROTECTED DQUIPMENT AND OUT-OF-NORMAL SWITCH POSITION/ANNUNCIATOR IN ALARM LIST Date: 04/01/09 Shift (Circle one) 0600-1800 1800-0600 NOTE: the Out-of-Normal position switch and Annunciator Alarm list must include a detailed reason justifying why the switch is in the current position or why the annunciator is in alarm. If the condition is due to an ongoing Surveillance Test or Operating Instruction, then the specific procedure number and step must be listed.
Switch Location Annunciators in Alarm Reason out-of-position/in alarm FW-4A CS CB-10,11 FW-4A Out of Service FW-30A CB-10,11 FW-4C CS CB-10,11 FW-4C Out of Service FW-30C CB-10,11 CB-10,11/A9 C-3L FW SYSTEM VALVES TROUBLE FW-4A and FW-4C Isolated PROTECTED EQUIPMENT SIGN LOCATION REASON PROTECTED FW-6 FW-6 CS and BKR FW-54 Out of Service FW-10 YCV-1045 CS '
FW-4B CS and BRKR FW-4A and FW-4C OOS
FORT CALHOUN STATION OI-CC-1 OPERATING INSTRUCTION C PAGE 8 OF 73 Continuous Use Attachment 2 - Rotating In service Pumps PREREQUISITES (9) INITIALS
- 1. Procedure Revision Verification Revision No. 65 Date: 04/01/09 JEK
- 2. Power is available for the selected pump:
- AC-3A, Component Cooling Water Pump, 1B3B-4
- AC-3B, Component Cooling Water Pump, 1B4A1
- AC-3C, Component Cooling Water Pump, 1B3C-4C-4 X JEK
- 3. Verify operability of Diesel Generators will meet Tech Spec 2.7 requirements prior to disabling CCW pumps. JEK PROCEDURE NOTE The number of pumps in service can cause fluctuations in CCW temperature.
This can affect letdown temperature and may cause small reactivity changes in the RCS.
CAUTION At least two Component Cooling Heat Exchangers shall be in service at all times to protect against system over pressurization should a second pump automatically start.
- 1. Vent the pump to be started using the associated valve:
- AC-353, Comp Cooling Water Pump AC-3A Casing Vent Valve
- AC-356, Comp Cooling Water Pump AC-3B Casing Vent Valve
- AC-359, Comp Cooling Water Pump AC-3C Casing Vent Valve X JEK
- 2. Start the desired Component Cooling Water Pump:
- AC-3A
- AC-3B
- AC-3C R65
FORT CALHOUN STATION OI-CC-1 OPERATING INSTRUCTION C PAGE 9 OF 73 Continuous Use Attachment 2 - Rotating In service Pumps PROCEDURE (continued) (9) INITIALS NOTES
- 1. When stopping a Component Cooling Water Pump with two or more pumps operating, the pump discharge valve is closed to prevent check valve slamming.
- 2. The Component Cooling Water system contains a corrosion inhibitor, CORRSHIELD NT 4204 and should be considered a personnel hazard if a leak exists.
- 3. Log into Tech Spec 2.4(1)b 7 day LCO or 2.4(2)a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> LCO as appropriate, for the CCW Pump inoperability.
- 4. Close the discharge valve for the Component Cooling Water Pump to be stopped:
- AC-102, Comp Cooling Water Pump AC-3A Discharge Valve
- AC-105, Comp Cooling Water Pump AC-3B Discharge Valve
- AC-108, Comp Cooling Water Pump AC-3C Discharge Valve
- 6. Stop the Component Cooling Water Pump to be shutdown:
- AC-3A
- AC-3B
- AC-3C
- 7. Open discharge valve closed in Step 4.
Ind Verif
- 8. Exit appropriate Tech Spec LCO.
Completed by Date/Time /
R65
Appendix D Scenario Outline Form ES-D-1 Facility: Fort Calhoun Scenario No: 2009-1 (SPARE) Revision: 3 Examiners: _________________________ Operators: _________________________
Initial Conditions: 100% Power. Diesel Driven AFW Pump, FW-54, is out of service. Air Compressor, CA-1A, is out of service.
Turnover: Transfer Letdown Control Valves from LCV-101-1 to LCV-101-2. After that rotate running EHC Pumps.
Event Malf Event Event No. No. Type* Description 1 N-ATCO Transfer Letdown Flow Control Valves.
(2 min) 2 N-BOPO Rotate EHC Pumps.
(14 min) 3 I-ATCO Power Range NI Channel B fails - Tech Spec Entry.
LE CUE 4 C-BOPO Running Bearing Cooling Water Pump, AC-9A, trips.
LE CUE 5 I-ATCO Loop Two Hot Leg RTD, TT-122H, Fails High - Tech Spec LE CUE Entry 6 C-All Loss of Instrument Air.
LE CUE 7 C-ATCO Manual Reactor Trip Required.
8 M-All Steam Generator Safety Valve Fails Open.
LE CUE
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Target Quantitative Attributes (Per Scenario; See Section D.5.d) Actual Attributes
- 1. Total malfunctions (5-8) 5
- 2. Malfunctions after EOP entry (1-2) 1
- 3. Abnormal events (2-4) 2
- 4. Major transients (1-2) 1
- 5. EOPs entered/requiring substantive actions (1-2) 1
- 6. EOP contingencies requiring substantive actions (0-2) 1
- 7. Critical tasks (2-3) 3
Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-1 Revision: 3 Event No.: 1 Page 2 of 15 Event
Description:
Transfer Letdown Flow Control Valves Time Position Applicants Actions or Behavior ATCO Enter OI-CH-1, Attachment 2, "SHUTDOWN OF CHARGING AND LETDOWN."
ATCO Bypass ion exchangers by placing TCV-211-2, Ion Exchangers Bypass Valve to "BYP IX" ATCO Close TCV-202, Ltdn to Regen Ht Exch Isolation Valve.
ATCO Close HCV-204, RC to Ltdn Ht Exch Isolation Valve.
ATCO Stop the operating charging pump, CH-1A. (May place on PULL-OUT.)
ACTO Close Charging Isolation Valves, HCV-238 and HCV-239.
ATCO Enter OI-CH-1, Attachment 1, "STARTUP OF CHARGING AND LETDOWN."
ATCO Ensure LCV-218-2 VCT Outlet Valve is open with control switch in AUTO.
ATCO Read caution on top of page 8.
ACTO Ensure HCV-247, Charging to RC Loop 1A Isolation Valve is open.
ATCO Ensure charging isolation valves open; HCV-247 AND HCV-238 AND/OR HCV-248 AND HCV-239.
ATCO Place HC-101-3, Limiter Bypass Switch, in BYPASS.
ATCO Place HIC-101-1/101-2 Letdown Throttle Valve Controller in MANUAL.
ATCO Close LCV-101-1 and LCV-101-2 ATCO Select LCV-101-2 on HC-101-2 selector switch ATCO Place PIC-210, Letdown Pressure Controller, in MANUAL.
ATCO Throttle PIC-210 to approximately 10% open.
ATCO Verify position of Charging Pumps Mode Select Stby switch is CH-1B-1C.
Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-1 Revision: 3 Event No.: 1 Page 3 of 15 Event
Description:
Transfer Letdown Flow Control Valves, continued.
ATCO Start CH-1A.
ATCO Open HCV-204 and TCV-202.
ATCO Use HIC-101-1/101-2 to initiate letdown flow while adjusting PCV-210 to maintain approximately 300 psig.
ATCO Balance charging and letdown flow.
ATCO Place HC-101-3, Limiter Bypass Switch, in NORMAL.
ATCO Go to OI-RC-8, Attachment 3. and ensure pressurizer level matches programmed level and PIC-210 200-400 psia.
ATCO Adjust bias on HIC-101-1/101-2 until top scale indicates 50%.
ATCO Place HIC-101-1/101-2 transfer switch to BAL, then to AUTO.
ATCO Place PIC-210 to AUTO.
ATCO Make adjustments to HIC-101-1/101-2 as needed.
ATCO If Ion Exchangers were bypassed, then may place TCV-211-1 in AUTO/TO IX.
Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-1 Revision: 3 Event No.: 2 Page 4 of 15 Event
Description:
Rotate EHC Pumps Time Position Applicants Actions or Behavior CRS Direct BOPO to rotate EHC Pumps.
BOPO Enters OI-ST-12, Attachment 7, "NORMAL ROTATION OF ELECTROHYDRAULIC PUMPS."
BOPO Read note in middle of page 13.
BOPO Start standby EHC Pump, EHC-3B.
BOPO Ensure EHC system pressure is stable on PI-2101.
BOPO Ensure EHC-3B motor current is approximately 40 to 50 amps.
BOPO Direct EONT to verify local parameters:
PI-5116 pressure approximately equal to PI-2101 pressure PI-5115 pressure approximately equal to PI-2101 pressure No bubbles visible in EHC-3B suction strainer BOPO Stop EHC pump, EHC-3A. Ensure pump control switch in AFTERSTOP.
BOPO Verify adequate EHC pressure being maintained.
Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-1 Revision: 3 Event No.: 3 Page 5 of 15 Event
Description:
Power Range NI Channel B fails - Tech Spec Entry Time Position Applicants Actions or Behavior ATCO Identify the failure from the Nuclear Instrumentation Inoperable and other alarms. May enter ARP.
ATCO Determine that Power Range NI Channel B Upper Detector has failed.
ATCO Reset Rod Drop Bistables.
CRS Enter AOP-15, "LOSS OF FLUX INDICATION OR FLOW STREAMING."
CRS LCO 2.15(1) - The number of channels for the High Power Level, Thermal (TS) Margin/Low Pressurizer Pressure and Axial Power Distribution trips fell one below the total number of installed channels.
Required Actions:
RPS channel B trip units 1, 9 and 12 must be placed in bypass within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
Since this is a detector failure, they may remain in bypass for up to 7 days. (Note: They may enter 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> LCO until I&C confirms detector failure.)
If detector operability is not restored by the end of the 7 days, the reactor must be placed in hot shutdown within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
CRS Notify Manager - FCS, Manager - Operations or Supervisor - Operation of RPS trip unit bypass.
CRS Obtain the keys and direct the ATC operator to place the 1, 2, 9, 10 and 12 trip units on channel B in bypass.
ATCO Bypass trip units 1, 2, 9, 10 and 12 on RPS channel B.
ATCO Enter channel bypass information in control room log.
or BOPO CRS Inform Work Week Manager of NI Channel Failure.
Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-1 Revision: 3 Event No.: 4 Page 6 of 15 Event
Description:
Running Bearing Cooling Water Pump, AC-9A, trips Time Position Applicants Actions or Behavior BOPO Respond to Cooling Water Pressure Low alarm (CB-10,11 A11 B6U).
BOPO Report that AC-9A has tripped.
ATCO/ Refer to ARP CB-10, A11, B-6U BOPO BOPO Check PI-1917, Turbine Bearing Water Temperature.
BOPO Dispatch EONT to the Bearing Water Pumps.
Note: May receive ISO PHASE BUS TEMP HI alarm is starting backup pump is delayed.
CRS Direct BOPO to start AC-9B.
BOPO Start AC-9B.
CRS Direct BOPO to verify status of Instrument Air System.
BOPO Ensure that air compressor is operating and instrument air pressure normal or restoring.
BOPO Direct EONT to check Breaker for AC-9A EONT reports breaker tripped, pump motor hot.
BOPO May place AC-9A control switch in PULL TO LOCK.
CRS/ May Direct EONT to attempt to reset breaker.
BOPO If Directed, EONT reports breaker will not reset.
CRS Notify Work Week Manager.
BOPO Direct EONT to check level in Bearing Water Head Tank.
EONT reports normal water level.
Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-1 Revision: 3 Event No.: 5 Page 7 of 15 Event
Description:
Loop Two Hot Leg RTD, TT-122H, Fails High - Tech Spec Entry Time Position Applicants Actions or Behavior ATCO Responds to numerous alarms on CB-4, panel A-20 and CB-1,2,3, panel A4.
Reports that trip units 1, 9 and 12 on channel A are tripped.
ATCO/ Reviews ARP.
BOPO ATCO Checks power, pressure and temperature indications and determines that the alarm is caused by failed T-hot channel (A/T122H).
CRS LCO 2.15(2) - High Power Level, Thermal Margin/Low Pressurizer (TS) Pressure and Axial Power Distribution Operable Channels have fallen to the minimum operable channels in TS Table 2.2.
Required Actions:
Because trip units 1, 9 and 12 are already bypassed on RPS channel B. The 1, 9 and 12 trip units on channel A must be placed in the tripped condition within one hour.
One of the channels must be repaired within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or else the plant must be placed in hot shutdown within the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
With NI channel B trip units bypassed and Delta-T channel A trip units tripped, power must be reduced to less than 70% (no time limit).
CRS Either direct the ATC to use the Channel A Power Trip Test Interlock, PTTI, to place the trip units in the tripped condition by placing the "Test Enable" switch in "ENABLE" and the "Test Select" switch in "CAL MID" or else notify I&C to trip the trip units with one hour.
ATCO If directed, use the channel A PTTI to trip the trip units on channel A by placing the "Test Enable" switch in "ENABLE" and the "Test Select" switch in "CAL MID."
CRS Notifies Plant or Operations Management and the Work Week Manager or I&C of the failure.
Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-1 Revision: 3 Event No.: 6 Page 8 of 15 Event
Description:
Loss of Instrument Air Time Position Applicants Actions or Behavior BOPO Respond to "PLANT AIR PRESS LO" alarm (CB-10,11/A21,B-6U)
Report that Plant Air Pressure is less than 96 psig, ARP directs entry into BOPO AOP-17 CRS Enter AOP-17, "LOSS OF INSTRUMENT AIR."
Caution BOPO that Feed Reg Valves, FCV-1101 and FCV-1102, fail as-is CRS when Instrument Air Pressure lowers to 70-80 psig.
CRS Read Notes on page 4 of AOP-17.
CRS/ Ensure all available Air Compressors Start.
BOPO Direct EONT to ensure proper operation of:
CA-1A/B/C, Air Compressors CRS/ CA-12, Air Dryer BOPO CA-11A/B, Pre-Filters CA-13A/B, After-Filters CRS/ Direct all available Operators to search for the source of the air leak BOPO CRS/ Direct EONT to verify "Service Air System Automatic Isolation Valve",
BOPO PCV-1753, closure when instrument air pressure drops to less than 80 psig.
CRS/ Direct EONT to verify "Air Dryers CA-31 & CA-12 Bypass Valve, PCV-BOPO 1752, opens when instrument air pressure drops to less than 78 psig.
CRS Direct BOPO to isolate instrument air to containment.
Close "Instrument Air Containment Isolation Valves", PCV-1849A/B and BOPO after verifying air pressure continues to drop, reopen PCV-1849A/B.
Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-1 Revision: 3 Event No.: 6 Page 9 of 15 Event
Description:
Loss of Instrument Air, Continued Time Position Applicants Actions or Behavior ATCO Maintain RCS pressure 2075-2150 psia and Pressurizer Level 45-60% using charging.
CRS Direct manual reactor trip when air pressure drops to less than 50 psig.
ATCO Manually trip reactor when directed.
CRS Direct BOPO to trip all Main Feedwater Pumps.
BOPO Trip all Main Feedwater Pumps.
Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-1 Revision: 3 Event No.: 7 Page 10 of 15 Event
Description:
Manual Reactor Trip Required Time Position Applicants Actions or Behavior CRS Enters EOP-00. Directs ATCO and BOPO to perform standard post trip actions.
ATCO Perform Reactivity Control Actions:
Verify power lowering Verify negative startup rate Verify no more than one CEA not inserted Monitor for an uncontrolled RCS Cooldown Notify CRS that Reactivity Control is Met.
BOPO Verify Turbine Tripped:
Stop and Intercept Valves are Closed BOPO Verify Generator Breakers Tripped:
Breakers 3451-4/5 Generator Field Breaker BOPO Verify vital buses, 1A3 and 1A4, are energized.
BOPO IF SIAS has initiated, THEN verify both Diesel Generators have started.
BOPO Verify non-vital buses, 1A1 and 1A2, are energized.
BOPO Verify both 125VDC buses are energized.
BOPO Verify Instrument air status:
Instrument Air pressure 90 at least 90 psig At least 1 air compressor running Reports instrument air pressure is low and continuing to lower.
ATCO Verify CCW and Raw water status:
At least one CCW pump running CCW Pump Discharge Pressure > 60 psig At least 1 RW Pump running IF CCW Pump Discharge Pressure > 40 psig, THEN verify HCV-438A/B/C/D are open ATCO Verify Inventory Control:
Pressurizer Level 30-70% trending toward 45-60%
Subcooling, at least 20°F
Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-1 Revision: 3 Event No.: 7 Page 11 of 15 Event
Description:
Manual Reactor Trip Required, continued Time Position Applicants Actions or Behavior ATCO Verify Pressure Control:
RCS Pressure 1800-2300 psia trending toward 2050-2150 psia PORVs closed ATCO Verify Core Heat Removal:
RCP NPSH adequate per Attachment 2 At least 1 RCP running Core Delta-T less than or equal to 10°F BOPO Ensure Main Feedwater is restoring level in at least one S/G to 35-85% NR (73-94% WR):
Both Feed Reg Valves ramped closed Both Feed Reg Bypass Valves ramped 40-45%
No more than 1 Main Feed Pump is operating No more than one Condensate pump is operating No Heater Drain Pumps are operating 43/FW Switch is in OFF Close blowdown isolation valves, HCV-1387A/B and HCV-1388A/B Reports Feed Reg valves open, Feed Reg bypass valves closed and no Main Feed Pumps operating.
Establishes AFW flow to the AFW nozzles.
BOPO Verify Steam Dump and Bypass Valves are controlling BOTH of the following:
T-cold 525-535°F S/G Pressure 850-925 psia Reports that steam dump and bypass valves are closed due to loss of instrument air pressure. Operates HCV-1040 or MS-292 and MS-292 as required to maintain temperature and pressure bands.
Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-1 Revision: 3 Event No.: 7 Page 12 of 15 Event
Description:
Manual Reactor Trip Required, continued Time Position Applicants Actions or Behavior ATCO Verify containment conditions:
No unexpected rise in Containment sump level No Containment Area Rad Monitor Alarms No Containment or Stack radiation monitors,RM-051/52/62, alarms No S/G blowdown or Condenser offgas radiation monitor, RM-054A/54B/57, alarms No S/G blowdown or Condenser offgas radiation monitor, RM-054A/54B/57, upward trends Containment pressure < 3 psig AND Containment Temp < 120°F CRS Perform Diagnostic Actions and enters EOP-01.
Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-1 Revision: 3 Event No.: 8 Page 13 of 15 Event
Description:
Steam Generator Safety Valve Fails Open Time Position Applicants Actions or Behavior ATCO Reports RCS cooldown in progress.
BOPO Reports S/G pressure is lowering.
CRS Directs ATCO to perform emergency boration using EOP-00 contingency action.
ATCO Performs Emergency Boration:
(CT) Ensure FCV-269X/Y Closed Open HCV-268/265/258 Start Boric Acid Pumps, CH-4A/B Start Charging pumps, CH-1A/B/C Close LCV-218-2/3 and HCV-257/264 CRS Perform diagnostic actions and transition to EOP-20, FUNCTIONAL RECOVERY PROCEDURE, due to a loss of instrument air and an excessive heat removal event.
CRS Within EOP-20, go to success path MVA-IA and implement (continue to implement) AOP-17, LOSS OF INSTRUMENT AIR.
On Note: Water Plant Operator Reports Instrument air leak in the intake CUE structure.
CRS Direct Water Plant Operator to isolate leak CRS Direct BOPO to monitor instrument Air Pressure BOPO Reports that Instrument air pressure is now increasing CRS Within EOP-20, go to RCS Core and Heat Removal success path, HR-3.
CRS Direct ATCO or BOPO to verify PPLS, Pressurizer Pressure Low Signal.
ATCO Verify PPLS:
or Ensure emergency boration in progress BOPO Ensure acceptable SI flow per EOP/AOP Attachment 3 Verify 2 HPSI, 2 LPSI and all available charging pumps running
Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-1 Revision: 3 Event No.: 8 Page 14 of 15 Event
Description:
Steam Generator Safety Valve Fails Open, continued Time Position Applicants Actions or Behavior CRS/ Identify Most Affected Steam Generator by downward trends in any of the BOPO following:
Steam pressure S/G level RCS T-cold BOPO Reports that RC-2B is the affected Steam Generator.
BOPO Manually closes MSIVs when steam header pressure reaches 700 psia.
BOPO IF either S/G pressure is less than or equal to 500 psia, THEN ensure SGIS closes all of the following valves:
HCV-1041A, RC-2A MSIV HCV-1041C, RC-2A MSIV Bypass Valve HCV-1042A, RC-2B MSIV HCV-1042C, RC-2B MSIV Bypass Valve HCV-1105, Feed Reg Bypass Valve HCV-1106, Feed Reg Bypass Valve HCV-1103, Feed Reg Block Valve HCV-1104, Feed Reg Block Valve HCV-1386, RC-2A Feed Header Isolation Valve HCV-1385, RC-2B Feed Header Isolation Valve CRS Direct BOPO to isolate Steam Generator, RC-2B BOPO Isolate S/G RC-2B by closing or ensuring closed:
MSIV, HCV-1042A.
MSIV Bypass, HCV-1042C.
Air assisted S.G Safety Valve, MS-292.
BOPO Isolate S/G RC-2B by closing or ensuring closed:
(CT) Feed Reg Valve, FCV-1102 (may need to reset due to low instrument air pressure)
Feed Reg Bypass valve, HCV-1106 Feed Header Isolation Valve, HCV-1385 Feed Reg Block valve, HCV-1104 Blowdown Isolation Valves, HCV-1387A/B AFW Isolation valves, HCV-1108A/B
Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-1 Revision: 3 Event No.: 8 Page 15 of 15 Event
Description:
Steam Generator Safety Valve Fails Open, continued Time Position Applicants Actions or Behavior BOPO Isolate S/G RC-2B by closing or ensuring closed:
Direct EONT to close Packing leakoff line isolation valve, MS-298 Override and close steam to AFW pump-FW-10, YCV-1045B Blowdown Sample Isolation Valves, HCV-2507A/B BOPO Verify the most affected S/G is isolated by downward trends in all of the following for the isolated S/G:
Steam pressure S/G level RCS T-cold CRS Read the Cautions on page 335 of EOP-20 BOPO Prepare to steam S/G RC-2A prior to reaching 27% WR level in RC-2B by one of the following:
Ensuring MSIV HCV-1041A is open Blocking SGLS and opening HCV-1041C, Main Steam Bypass Valve BOPO Establish Steam Flow from RC-2A prior to Wide Range Level on Steam (CT) Generator RC-2B falling to 27% by one of the following:
Opening Air assisted safety valve, MS-291 (OR)
Ensure MSIV, HCV-1041A or MSIV Bypass,HCV-1041C is open and use steam dump and bypass valves. (OR)
Ensure MSIV, HCV-1041A or MSIV Bypass,HCV-1041C is open and open atmospheric dump valve, HCV-1040 BOPO Ensure Auxiliary Feedwater is being supplied to S/G, RC-2A.
Scenario ends with S/G RC-2B isolated and heat removal established using S/G RC-2A.
FORT CALHOUN STATION FC-95 FORM SHIFT TURNOVER LOG Rev. 29 Modes 1, 2, or 3 03/31/09, 0600 Days Nights X PLANT STATUS:
MODE: 1 X 2 3 Rx Power: 98.60% Rod Position: All Groups ARO Prcs (>2075 psia): 2091 psia Tcold (<543°F): 542.8 °F Lpzr (48 - 60%): 60 % (Actual)
Comments:
SAFEGUARDS STATUS:
(Log any out-of-service safeguards equipment; include major fire protection equipment)
RECENT TEMP MODS: (Within the last month)
TM Number Date Description None DEGRADED EQUIPMENT STATUS CR Number Component/System Reason Considered Degraded Resolution 2009003501 AFW Pump FW-54 Out of Service - being repaired excessive vibration 2009003517 Air Compressor CA-1A Out of Service - motor windings shorted 2009003521 LCV-101-1 Erratic flow control LCV-101-2 will be placed into service while System Engineer investigates.
SO-O-1 FC/FORM Page 1 of 3
FORT CALHOUN STATION FC-95 FORM SHIFT TURNOVER LOG Rev. 29 Modes 1, 2, or 3 03/31/09, 0600 RELEASES IN PROGRESS: YES NO RELEASE #
Monitor Tank: A B X Waste Gas Decay Tank: A B C D X Containment Pressure Reduction X PROCEDURES and SURVEILLANCE IN PROGRESS/OVERDUE:
PROCEDURE or TEST REASON None CRS review and discuss procedures in progress (Initial)
INSTRUMENT / ANNUNCIATE STATUS (REQUIRING COMPENSATORY ACTION):
ITEM / LOCATION DATE ACTION REQUIRED None TEMPORARY LIFTS:
TAGOUT # EQUIPMENT REASON None POST MAINTENANCE TESTING:
(Equipment, instrument or annunciator requiring PMT for operability)
AVAILABLE Component YES NO PMT REQUIRED FOR OPERABILITY None TECHNICAL SPECIFICATION LCO'S and ODCM / SO-G-103 RESTRICTIONS:
REPORT MADE EQUIP OOS DATE/TIME T.S. / ODCM / G-103 LCO YES NO N/A None SO-O-1 FC/FORM Page 2 of 3
FORT CALHOUN STATION FC-95 FORM SHIFT TURNOVER LOG Rev. 29 Modes 1, 2, or 3 03/31/09, 0600 REMARKS:
- Transfer Letdown Flow Control from LCV-101-1 to LCV-101-2. Shutdown charging and letdown using OI-CH-1, Att 2.
- Reestablish charging and letdown using LCV-201-2 and CH-1A per OI-CH-1, Att 1 and OI-RC-8, Att 3.
- Perform Normal Rotation of EHC Pumps per OI-ST-12, Attachment 7.
RCS Boron 998 ppm Neutral Blend (gal acid /gal water)10 / 55 Additions this shift:2 additions of 20 gallons or demineralized water to raise reactor power CRS review ERF alarms and discuss with oncoming CRS: __________
Off going On coming S.M.
C.R.S.
L.O. 1 L.O. 2 STA Fire Brigade Leader Communicator ____
Security Key Transferred (Init)
SO-O-1 FC/FORM Page 3 of 3
FORT CALHOUN STATION FC-75A FORM R4 PROTECTED DQUIPMENT AND OUT-OF-NORMAL SWITCH POSITION/ANNUNCIATOR IN ALARM LIST Date: 03/31/09 Shift (Circle one) 0600-1800 1800-0600 NOTE: the Out-of-Normal position switch and Annunciator Alarm list must include a detailed reason justifying why the switch is in the current position or why the annunciator is in alarm. If the condition is due to an ongoing Surveillance Test or Operating Instruction, then the specific procedure number and step must be listed.
Switch Location Annunciators in Alarm Reason out-of-position/in alarm CA-1A CS CB-10,11 Out of Service A-33-1, F7 AIR COMPRESSOR CA-1A OFF NORMAL '
PROTECTED EQUIPMENT SIGN LOCATION REASON PROTECTED FW-6 FW-6 CS and BKR FW-54 Out of Service FW-10 YCV-1045 CS '
CA-1B CA-1B CS and BKR CA-1A Out of Service CA-1C CA-1C CS and BKR '
FORT CALHOUN STATION OI-CH-1 OPERATING INSTRUCTION CONTINUOUS USE PAGE 5 OF 77 Attachment 1 - Startup of Charging and Letdown PREREQUISITES (9) INITIALS
- 1. Procedure Revision Verification Revision No. 76 Date: 3/31/09 JEK
- 2. CVCS Checklist OI-CH-1-CL-A has been completed. JEK
- 3. Component Cooling Water is in operation per OI-CC-1. JEK
- 4. Power is available for the following pumps:
- 5. Liquid Waste Disposal System is available to receive waste from CVCS per OI-WDL-1. JEK
- 6. Charging pumps discharge accumulators precharge pressure has been set to approximately 60 to 90% of anticipated RCS pressure. JEK
- 7. Charging pumps suction accumulators precharge pressure has been set at approximately 15 psig. JEK
- 8. FT-236, Charging Pump Discharge Flow Transmitter, has been vented If the system has been shutdown for greater than two weeks or has been drained. JEK
- 9. If the SIRWT has been drained to 80 inches or less, the SIRWT suction header has been vented per OI-SI-1. N/A
- 10. Ensure Letdown Valve CIAS Override Switches are in NORMAL position.
(CB-1,2,3)
- 43-CIAS/HCV-204 X
- 43-CIAS/TCV-202 X JEK R76
FORT CALHOUN STATION OI-CH-1 OPERATING INSTRUCTION CONTINUOUS USE PAGE 6 OF 77 Attachment 1 - Startup of Charging and Letdown PROCEDURE (9) INITIALS NOTE Review SO-O-23 for appropriate Equipment/System Usage Cycles.
- 1. Start the selected Packing Cooling Pump a minimum of 30 minutes prior to starting a Charging Pump:
- 2. If desired by the SM to equalize the boron concentration in the charging pump, flush a nominal 40 gallons of water (approximately 2%) from the VCT N/A using the desired charging pumps drain valve:
- a. Declare the affected charging pump inoperable:
N/A
- b. Place control switch for selected pump into PULL-TO-LOCK:
- c. Close the discharge valve for selected pump:
FORT CALHOUN STATION OI-CH-1 OPERATING INSTRUCTION CONTINUOUS USE PAGE 7 OF 77 Attachment 1 - Startup of Charging and Letdown PROCEDURE (continued) (9) INITIALS 2
- d. Open the selected charging pump drain valve during system filling to N/A ensure of boron is equalized in the discharge piping:
- e. When nominal 2% has been flushed from the VCT to waste, THEN close the selected charging pump drain valve:
- f. Open and backseat the selected charging pump Discharge Valve:
N/A
N/A Ind Verif
- g. Place control switch for selected pump into AFTER STOP:
- CH-1A N/A
- CH-1B N/A
- CH-1C N/A N/A
- h. Repeat this step as necessary for each affected charging pump.
- 3. Ensure LCV-218-2, Volume Control Tank Outlet Valve, is open with its control switch in AUTO.
R76
FORT CALHOUN STATION OI-CH-1 OPERATING INSTRUCTION CONTINUOUS USE PAGE 8 OF 77 Attachment 1 - Startup of Charging and Letdown PROCEDURE (continued) (9) INITIALS CAUTION HCV-247, Charg to RC Loop 1A Isolation Valve must remain open to provide an alternate makeup path for charging and ensure CH-202, Ltdn to Regen Ht Exch Isolation Valve will be able to relieve thermal expansion in the Regenerative Heat Exchanger.
- 4. Ensure HCV-247, Charg to RC Loop 1A Isolation Valve, is open.
- 5. Ensure at least one of the following combinations of charging isolation valves is open:
- a. Charg to RC Loop 1A Isolation Valves
- HCV-247
- HCV-238
- b. Charg to RC Loop 2A Isolation Valves
- HCV-248
- HCV-239
- 6. At the Shift Managers discretion, place TCV-211-2, Ion Exchangers Bypass Valve to BYP IX.
- 7. Place HC-101-3, Limiter Bypass Switch, in BYPASS.
- 8. Place HIC-101-1/101-2, Letdn Throttle Valve Controller, in MANUAL.
- 9. Close the Letdown Ht Exch Throttle Valves:
- LCV-101-1
- LCV-101-2
- 10. Place HC-101-2, Ltdn Ht Exch Vlvs Selector Sw in the desired position per the Shift Manager.
- 11. Place PIC-210, Letdown Pressure Cntrlr, in MANUAL.
- 12. Throttle PIC-210 to approximately 10% open.
R76
FORT CALHOUN STATION OI-CH-1 OPERATING INSTRUCTION CONTINUOUS USE PAGE 9 OF 77 Attachment 1 - Startup of Charging and Letdown PROCEDURE (continued) (9) INITIALS
- 13. Position Charging Pumps Mode Select Stby switch to select the desired backup Charging Pumps start sequence:
- CH-1B-1C CAUTION Pressurizer Level deviation will start standby charging pumps not in PULLOUT.
- 14. Start the selected charging pump:
- CH-1A, Charging Pump
- CH-1B, Charging Pump
- CH-1C, Charging Pump
- 15. Open the following Letdown Isolation Valves:
- HCV-204, RC to Ltdn Ht Exch Isolation Valve
- TCV-202, Ltdn to Regen Ht Exch Isolation Valve
- 16. Using HIC-101-1/101-2 initiate Letdown flow while adjusting PCV-210 to maintain Letdown pressure approximately 300 psig.
- 17. Balance Charging and Letdown flows to maintain Pressurizer level.
- 18. Place HC-101-3 in NORMAL.
- 19. If desired, place the following controllers in AUTO:
- HIC-101-1/101-2 per OI-RC-8
- PIC-210
- 20. If desired, place CVCS ion exchangers in service per OI-CH-2.
- 21. If desired, check Letdown Pulsation Dampener Pressures per OI-CH-1, Attachment 6.
- 22. Evaluate the evolution for appropriate Equipment/System Usage Cycles.
Completed by Date/Time /
R76
FORT CALHOUN STATION OI-RC-8 OPERATING INSTRUCTION PAGE 9 OF 20 C
Continuous Use Attachment 3 - Transferring Letdown Controller from MANUAL to AUTOMATIC PREREQUISITES (9) INITIALS
- 1. Procedure Revision Verification Revision No. 13 Date: 3/31/09 JEK
- 2. 120 Volt AC System is in normal operation per OI-EE-4. JEK
- 3. Instrument Air is in operation per OI-CA-1. JEK
- 4. CB-1/2/3 Instrumentation and Alarms are operable. JEK PROCEDURE
- 1. Ensure Letdown Controller HIC-101-1/101-2, Letdn Throttle Valves Controller is in (M) MANUAL.
- 2. Manually adjust HIC-101-1/101-2 AND PIC-210, Letdown Press Cntrlr until the following parameters are met:
- Indicated Pressurizer Level (red pen) matches the Programmed Level Setpoint (green pen) on LR-101X or LR-101Y, Pressurizer Level Recorder.
- PIC-210 is maintaining 200 psi to 400 psi.
- 3. Adjust the bias on HIC-101-1/101-2 until the top scale indicates 50% (zero deviation; red pointer aligned with the red dot).
- 4. Place HIC-101-1/101-2 Manual/Auto Transfer Switch to BAL, then to AUTO.
- 5. IF necessary, THEN make fine adjustments to the bias of HIC-101-1/101-2 to ensure Pressurizer Level is maintained at setpoint.
Completed by Date/Time /
R13
FORT CALHOUN STATION OI-ST-12 OPERATING INSTRUCTION PAGE 13 of 19 C
Continuous Use Attachment 7 - Normal Rotation of Electrohydraulic Pumps PREREQUISITES (%) INITIALS
- 1. Procedure Revision Verification Revision No. 23 Date: 3/31/09 JEK
- 2. Standby EHC Pump is in AFTERSTOP. (CB-10) JEK
- 3. Coordination established with Control Room and Turbine Building operator. JEK
- 4. Turbine Plant Cooling Water System is operable and available to the applicable Electrohydraulic Pump Oil Coolers EHC-6A/6B per OI-BW-1. JEK
- 5. Electrical Distribution is aligned per OI-EE-2. JEK PROCEDURE NOTE The EHC Pumps are positive displacement pumps. Minimize time both pumps are in service since each pump tries to take the EHC System load causing pressure oscillations which could affect turbine valves.
- 1. Start the Standby EHC Pump by placing its control switch in AFTER-START (CB-10/11):
! EHC-3A
! EHC-3B
- 2. Ensure any pressure oscillations in the EHC System are dampened and stabilized indicating greater than 1500 psig on PI-2101 (CB-10).
- 3. Check just started EHC Pump Motor current is approximately 40 to 50 amps.
(CB-10/11)
! EHC-3A
! EHC-3B R23
FORT CALHOUN STATION OI-ST-12 OPERATING INSTRUCTION PAGE 14 of 19 C
Continuous Use Attachment 7 - Normal Rotation of Electrohydraulic Pumps PROCEDURE (continued) (%) INITIALS
- 4. Check proper local operation of EHC System as follows:
! Check PI-5116, Pump EHC-3A Discharge Pressure, is approximately equal to PI-2101A, EHC Supply Header Pressure
! Check PI-5115, Pump EHC-3B Discharge Pressure, is approximately equal to PI-2101A, EHC Supply Header Pressure
! For the pump started:
- Verify no bubbles are visible in EHC-2A, Hydraulic Fluid Pump EHC-3A Suction Strainer, Bull=s eye
- Verify no bubbles are visible in EHC-2B, Hydraulic Fluid Pump EHC-3B Suction Strainer, Bull=s eye
! EHC-3A
! EHC-3B
Completed by Date/Time /
R23
FORT CALHOUN STATION OI-CH-1 OPERATING INSTRUCTION CONTINUOUS USE PAGE 10 OF 77 Attachment 2 - Shutdown of Charging and Letdown PREREQUISITES (9) INITIALS
- 1. Procedure Revision Verification 76 JEK Revision No. Date: 3/31/09
- 2. Zinc Injection is secured. JEK
- 3. Tech Spec 2.2 has been referenced. JEK PROCEDURE NOTE If CVCS is shutdown during RCP operation, Pressurizer Level will decrease at a rate equivalent to RCS Leakage and RCP Bleedoff flow.
- 1. Place TCV-211-2, Ion Exchangers Bypass Valve, in BYP IX.
- 2. Close TCV-202, Ltdn to Regen Ht Exch Isolation Valve.
- 3. Close HCV-204, RC to Ltdn Ht Exch Isolation Valve.
- 4. Stop all operating Charging Pumps:
- CH-1A, Charging Pump
- CH-1B, Charging Pump
- CH-1C, Charging Pump
- 5. IF desired THEN place all Charging Pumps in PULL-OUT:
- CH-1A, Charging Pump
- CH-1B, Charging Pump
- CH-1C, Charging Pump
- 6. Close the following charging isolation valves: (AR 13140)
- HCV-238, Charg to RC Loop 1A Isolation Valve
- HCV-239, Charg to RC Loop 2A Isolation Valve R76
FORT CALHOUN STATION OI-CH-1 OPERATING INSTRUCTION CONTINUOUS USE PAGE 11 OF 77 Attachment 2 - Shutdown of Charging and Letdown PROCEDURE (continued)
- 7. Stop the Packing Cooling Pumps a minimum of 30 minutes after stopping Charging Pump(s):
- 8. Evaluate the evolution for appropriate Equipment/System Usage Cycles.
Completed by Date/Time /
R76